NL-16-135, Preservice Inspection Program Plan, Watts Bar Nuclear Plant, Unit 2, Program No: WBN-2 PSI Rev. 11
| ML16293A336 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 06/30/2016 |
| From: | Burns E Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16293A318 | List:
|
| References | |
| CNL-16-135 WBN-2 PSI Rev. 11 | |
| Download: ML16293A336 (96) | |
Text
CNL-16-135 Preservice Inspection Program Plan Watts Bar Nuclear Plant Unit 2 Tennessee Valley Authority 110 l Market Street Chattanooga, TN 37402-2801 Watts Bar Nuclear Plant P.O. Box 2000 Spring City, TN37381 Docket Number 391 Construction Permit No. CPPR-92, Issued January 23, 1973 Extens.ion Issued to September 30, 2016 Program No: WBN-2 PSI Rev. 11 Effective Date: __
________ _ Responsible Organization:
Inspection Services Organization E2-2 of 101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 2of100 Revision Log Revision Effective Pages Description of Revision Number Date Affected 0 7-25-08 All Intial Issue 1 10-23-08 19,20,21 Incorporate 10CFR50.55a requirements for Components
& Containing Alloy 600/82/182.
53-56 Editorial corrections as marked. 2 12-01-09 7 Insert MOU statement ll Changed the word Weld to Component Table Added numbers to Total Population and Required Summary Examination 62 Added TP-2 and TP-3 to table 66 Added TP-2 statement 67 Added TP-3 statement Section Added Drawing number reference 11 Section Added Terms 12 Various Editorial correction 3 6-1-10 3 Update Index 7 Remove 3.4.1.1.2.
Mechanical Clamping devices 8 Section 3.4.1.4, define snubber exam and testing Code of Record. Add section 3.4.1.7 to address shop/field exams. 11 Added section 3.8.5 to address IEP-100 and ISOPM-S02-TOC 13,14 Remove 10CFR50.55a(b)(2)(xi) requirement to use 1989 Edition IWB-1220 exemptions.
Also, revise 3.15 .. 6 to reflect IWB-1220 exemptions from 2001A03 Code. 17 Update 3.18.3 to define snubber exam and testing Code of Record. 17-18 Minor editorial changes 20 Added reference to 10CFR40.55a(Q:)(6)(ii)(E) to 3.19.3 21-24 Added Calibration Block section and table 32 Added totals for Exam Cat B-G-2 33 Revised totals for .Exam Cat B-J 45 Added AFWS system to Table for Exam Cat C-F-2 56-58 Revised Augmented commitment Section 8.0 to reflect TV A responses to NRC. 71-73 Updated drawine: lists 4 10-13-10 8 Add reference to NEDP-16, PER CAP action 247419-001.
58 Revised commitment table listing for RV head penetrations CNL-16-135 E2-3of101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERV/CE INSPECT/ON PROGRAM PLAN REVISION 11 PROCEDURE Page 3of100 5 7-27-11 8 Add periodic notification to ANTI of examination record signature status. 13 Add reference to IEP-500 for surface conditioning ofDM welds. 20-21 Correct paragraph letters for "f' and "e". 22 Add Code Cases N-686-1, N-695, and N-696 23 Correct typoeraphical errors 36 Uoclate weld totals for Examination Cateeory B-.J 46 Update weld totals for Examination Category C-F-1 48 Update weld totals for Examination Category C-F-2 50 Add systems and component totals for Examination Cateeory C-G 57 Add support totals for ERCW system 60 Add MRP-146 examination requirements and PER 375365 reference.
62 Updated Relief Request status table 67-86 Added relief requests WBN-2/PSI-1 and WBN-2/PSI-2 95-99 Updated drawine list 6 2-15-12 5 Added information from RR on ASME XI 2001/2003 6 Corrected FSAR reference numbers 9 Removed 1 OCFR50.55a(b
)(2)(iii) reference 14-15 Added paragraphs to outline summary and final reports 22 Added revision number to Code Case N-722 23 Revised per 10CFR50.55a change 60 Removed Note, pertaining to updated requirements in 10CFR50.55a 62 Editioral correction to table 7 10-28-12 55 Added Class 1 support counts for RCS and RHRS. Deleted duplicate RHR system from table. 56 Added Class 2 support counts for AFWS, CSS, MSS, RHRS, and CCS. 57 Added Class 3 support counts for AFWS, CCS, ERCWS, FPCS, and HPFPS .. Included total count by type. Corrected table title. 8 5-31-13 5 Changed paee numbers in Table of Contents.
6 Changed 'reference' to 'referenced' in two places and removed a comma after 4.6.iv. 7 In paragraph 2.3, changed wording to match paragraph 1.0 to address PER 690704. 9 Chane:ed 'NGDC PP-15' to 'NC PP-15' .. 10 Changed 'MOU' to 'MOU-006'.
15-16 In paragraph 3.14, changed 'NGDC' to 'NC'. In paragraph 3.14.1, added items (NIS-1, NIS-2, Stm Gen tubes, Pressure Tests) to agree with NC PP-15, 3.1.5.N and IWA-6230.
24 In paragraph 3.20.3, corrected wording to match 10CFR50.55a(11:)(5)(iv).
34-35 In Exam Category B-G-1, added threaded bushines to four CNL-16-135 E2-4of101 i ! t . : NC PROJECT PROCEDURE 9 7-31-2014 CNL-16-135 WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 Page 4of100 (4) RPV Stud Holes. Modified Note 2 and added Note 8 to address bushine;s.
37 Chane;ed 'safely' to 'safetv'.
47 Chane;ed count from 286 to 303 for CSS total population.
58 Chan2ed counts to reflect current confa?:urations.
60 Changed date from September 20 to September 29 for referenced Letter No 2 from TV A to NRC. 62 Chan2ed 'releir to 'relier. 88 Changed 'there of' to 'thereof'.
92 Changed footnote by replacing
'NGDC' with 'Nuclear Construction' and changing 'MOU-6' to 'MOU-006'.
94-99 Added drawinl! numbers, titles, and Code Classes. all Chaneed 'NGDC' to 'NC' in header throu2hout document.
various Tvuo and spacing corrections to improve readabiJitv.
6 New pa2e numbers in Table Of Contents.
8 Deleted paragraph describing the use of 'TBD' for the incomplete count of components and examinations.
In para2raph 2.2, reworded for clarity. 10, 11 Deleted paragraph describing MOU-006 and it's use as Technical Position 3. Deleted 3.4.1.1.1 thru 3.4.1.1.5 concernine Repair/Replacment.
Moved 3.4.1.7 to 3.4 16 In 3.14.1, added 'or OAR-1' and 'or NIS-2A' for reportine.
23 Deleted 3.18.9 thru 3.18.12 -info is already contained in 3.18.2 ancl 3.18.2.1.
In 3.19, added Code Case N-532-4 for OAR-1 and NIS-2A. 24 Reworded 3.20 for clarity. In 3.20.1, corrected misquote of 1 OCFR50.55a( a)(3) . 25 Reworded 3.21 for clarity. In 3.22, added PSI coordinator responsibilities
-Reference PER 834036. 25, 6 Added 3.23 to address M&TE and PSI coordinator responsibilities.
Changed Table of Contents to match. Reference PER 834036. 29 Reworded footnote for clarification.
35 Corrected weld count for cateeorv B-G-1. 36 Changed Note 4 to 'NIA to U-2 PSI". Deleted 'TBD =To Be Determined'. (Catc2orv B-G-2 .) 37 In Note l(d), changed '25%' to '100% for PSI'. In Note 2, chan2ed '10%' to '100%'. (Cate201-y B-J). 38 Added components and weld counts to two columns. Deleted 'TBD' and 'TBD =To Be Determined'.
39 Changed '28' to '0' in Required Exam column. Deleted 'TBD =To Be Determined'.
43, 45 Added weld counts to two columns. Deleted 'TBD' and 'TBD =To Be Determined'.
44,46 Aclded components and weld counts to two columns. Deleted 'TBD' and 'TBD =To Be Determined'.
Added Note 7, on page 44, to address AFW and BIT nozzle exemptions.
E2-5of101 I I _J NC PROJECT PROCEDURE 10 6-22-2016 CNL-16-135 WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN WBN-2 PSI REVISION 11 Page 5of100 47,48 Added components and weld counts to two columns. Deleted 'TBD' and 'TBD =To Be Determined'.
Added Note 7, on page 48, to address CSS and RHRS exemptions.
49 Added weld counts to 'Total Population' column. 50 Typo correction and deleted 'TBD =To Be Determined'.
51 Deleted 'TBD =To Be Determined'.
53 Added weld counts to two col:umns.
Deleted 'TBD' and 'TBD =To Be Determined'.
54 Reworded for clarity. 55-60 Added support counts and deleted all references to 'TBD'. 62 Added paragraph III.B to address Augmented Exam of the 4 RCP Motor Flvwheels.
63 Added paragraph N.A, B, & C to address Augmented Exam of the RPV and PZR nozzle welds per the Alloy 600 Pro2ram and ASME Code Case N-770-1. 64 Added 'or' and '(Note 2)' to Exam Method column. Added Note 2 to describe exams allowed by NRC EA 03-009. 88, 92, 95 Deleted Technical .Position 3 which encompassed the use of MOU-006. 90 In 2nd and 4th paraeraph, chan2ed 'NGDC' to 'NC'. 95-98 Corrected and added Drawing references ISI-2068-MRP-01
& -02, ISI-2068-W-07, ISI-2068A-E-13
& -14, ISl-2068C-E-03, -04, &-05, ISI-2072-W-01 thru -10, & ISl-2072A-E-01.
101 Added definition for 'NC'. Deleted definition for 'REV'.* 6 Repaii;ination of TOC 8 Added "TI-SOB" and "W.BN-2 PSI" for clarification.
Deleted "red lined' FSAR. Corrected lOCFR reference.
11 Deleted NC-PP-15, added 2-TRI-0-10.2 and NPG-SPP-09.1 12 Added reference to Snubbers and Relief Request WBN-2 /PSI-4. 13 Added definition for HPSI. 22 Added reference to Snubbers and Relief Request WBN-2 /PSI-4. Added 2-PAT-1.8 24 Change "N-532-4" to "N-532-5" per latest revision of Reg Guide 1.147 (Rev 17). Added "'Rev 17".
- 25 Added Code Case N-770-1 and added notes to N-722-1 and N-729-1. Added paragraph (F) for 10CFR50.55a.
Updated 3.20.1 to 10CFR50.55a(z)(l) 30 Added 4 calibration blocks, "SQ-40", "SQ-57", "SQ-59", and "S0-76". 39, 40, Corrected counts based on final PSI exams. 47, 49, 51, 52, 55, 57-62 57 Added Note 6 to explain how a Code exemption is applied. 61-62 Added "(OTHER THAN PIPING)" to two tables for clarity. E2-6of101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 6of100 63-69 Added table to cross reference ISi support numbers to snubber UNIDs. 69 Deleted two Unit l Snubbers from the table 7l Added database info for RCP Motor Flywheel exams in 8.0.III. 73 Added Upper Head injection Auxiliary Heacl Adapter (UPIAID welds. 74 Updated Index of Relief Requests.
74-97 Deleted Relief Requests WBN-2/PDI-4, PSI-1, i>SI-2. 80 Updated Flow Diagram number to include "0-" and "2-" 81-87 Added ISi drawin(!s.
88 Added Class "3" for shell side of RHR HX supports.
89 Added terms "A-E" and "EVT-1" with descriptions.
90 Added term "MSIP" with description.
91 Chan2ed "VE" to "V-E". Typo correction.93-100 Added Attachments l and 2 to address transition from MRP-139 Rev 1 and B2004-01 to ASME Code Case N-770-1. 11 6-30-2016 34, 41, 45, 47, 49, 51, Final counts of examinations.
57, 59, 60,61,62 40 Reinstated Note 5for10% sample of welded attachments.
61 Spread out table vertically to make it more readable.
62 Added a line for 4 SG Unner Lateral Sunoorts, as Fl.42B. 74 Changed Rev 10 to Rev 11 CNL-16-135 E2-7of101 NC PROJECT PROCEDURE WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN TABLE OF CONTENTS WBN-2 PSI REVISION 11 Page 7 oflOO 1.0 Sumn1ary .............................................................................................................................
8 2.0 Code Applicability
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9 3 .0 Description
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10 3 .1 Scope ....................................................................................................................
l 0 3.2 Jurisdiction
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11 3.3 Responsibility
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11 3 .4 Application
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11 3.5 Classification and Boundaries
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12 3 .6 Accessibility
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13 3.7 Referenced Standards and Specifications
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14 3.8 Examination Methods ...........................................................................................
14 3.9 Nondestructive Examination Personnel
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15 3. l 0 Inspection Intervals
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15 3 .11 Component Reference System ............................................................................. l 5 3 .12 Program Plan and Schedule ..................................................................................
16 3 .13 Evaluation of Recorded Conditions
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16 3.14 Records and Reports .............................................................................................
17 3.15 IWB Requirements and Exemptions
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17 3.16 IWC Requirements and Exemptions
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19 3 .17 IWD Requirements and Exemptions
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21 3 .18 IWF Requirements and Exemptions
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22 3.19 CodeCases
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24 3.20 Code Relief ...........................................................................................................
25 3.21 Augmented Components
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26 3.22 Calibration Standards
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26 3.23 Measuring and Test Equipment
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26 4.0 IWB Sununary Tables ......................................................................................................
30 5.0 IWC Summary Tables ......................................................................................................
43 6.0 IWD Summary Tables ......................................................................................................
53 7.0 lWF Sumtnaiy Tables .......................................................................................................
55 8.0 Augmented Examination Regulatory Commitments
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69 9. 0 Requests for Relief ...........................................................................................................
73 10.0 ASME Section XI -Technical Positions
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96 11.0 Drawing Reference List ..................................................................................................
101 12.0 Progra1n -Terms ............................................................................................................
110 Attachment l ..............................................................................................
l 14 Attachment 2 ...............................................................................................
116 CNL-16-135 E2-8of101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 8of100 1.0
SUMMARY
As the owner Tennessee Valley Authority (TVA) had established the original Preservice Inspection (PSI) program at Watts Bar Nuclear Plant (WBN) Unit 2 to perform and document the inspection activities in accordance with Technical Instruction (Tl) SOB, ASME Section XI Preservice inspection Program. The latest working revision of TI-SOB, Revision 11 dated Septeri1ber 29, 1989 was placed on "Administrative Hold" and on September 04, 1997 Revision 12 was issued to "Cancel" the document with that being the status of the original PSI program. This document (TI-50B) will be referenced to establish the present document (WBN-2 PSI) as needed. In a letter dated January 29, 2008, Tennessee Valley Authority (TVA) to U.S. Nuclear Regulatory Commission (NRC) and In the Matter of Docket Number 50-391 Tennessee Valley Authority, "WATTS BAR NUCLEAR PLANT (WBN) -UNIT 2 -REGULA TORY FRAMEWORK FOR THE COMPLETION OF CONSTRUCTION AND LICENSING ACTIVITIES FOR UNIT 2", it states in Enclosure 1, "TV A Responses to NRC's Request oflnformation Needed for Licensing Review Reconstitution", item 4.b.iv is a commitment to provide a revised Preservice Inspection Program. Based on FSAR Sections 5.2.8, 5.4.4.4 and 6.6, components subject to examination and/or test are components containing water, steam or radioactive waste shall be examined and tested in accordance with ASME Section XI as required by lOCFR50.55a(g), except where specific written relief has been requested.
FSAR Section 5.2.8 is for TV A Class A (ASME Code Class I) and Section 6.6 for TVA Class B (ASME Code Class 2) and C and D (ASME Code Class 3) components.
This document is being prepared to re-establish the requirements for the PSI Program Plan at WBN-2, as stated in the previous paragraph.
This program plan fol.lows the inspection requirements of 1 OCFR50.55a(g)(2) which requires that components, including component supports, that are classified as ASME Code Class 1 and 2 must be designed and be provided with access.to enable the performance of inservice examination of such components and supports and must meet the preservice examination requirements set forth in Editions and Addenda of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code or optional Code Cases listed in NRC Regulatol)'
Guide l .14 7 that are incorporated by reference in IOCFR50.55a(a)(3)(ii), in effect six month before the date of issuance of the construction permit. TV A requested and was granted approval to use an alternative ASME Section XI Code year and addenda for the construction completion project at WBN Unit 2. The alternate ASME Code for Preservice Examination (PSI) activities is based on the ASME Section XI Edition and Addenda approved at the time constrnction was resumed on WBN Unit 2. Based on the initial construction permit date for WBN Unit 2 of January 23, 1973 for Construction Permit No. CPPR-92, 10 CFR 50.55a(g)(2) would require the PSI code of record to have been based on the ASME Section XI Code in effect six months prior to the date of issue of the Constrnction Permit. The applicable Code would have been the 1971 Edition through Winter 1971 Addenda of ASME Section XI. Since I 0 CFR 50.55a(g)(2) also allows the use of subsequent Code Editions/
Addenda which are incorporated by reference in 10 CFR 50.5 5a(b )(2 ), the 2001 Edition, through 2003 Addenda was identified as the applicable Code of Record based on the date associated with resumption of construction activities.
Reference the Relief Request Section 9.0 RR "WBN-2/PSI-2" for detail information and basis. CNL-16-135 E2-9 of 101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 9of100 The examination categories and requirements for Class 1 components will be in accordance with subsection lWB of ASME Section XL The examination categories and requirements for Class 2 and 3 components will be in accordance with subsections IWC and IWD of ASME Section XI to the extent practicable. (Watts Bar design was established prior to the publication of subsection IWC and IWD of Section XI; however, accessible Class 2 and 3 components will be examined in accordance with the guidelines ofTWC and IWD of Section XI, as stated in FSAR Sections 5.2.8 and 6.6. Other inspection requirements and/or commitments made by WBN Unit 2 in the regulatory framework Jetter maybe incorporated or reference in this document as augmented inspection activities.
Augmented inspection requirements or commitments, on ASME class components, may be included or referenced in this program plan for mutual eff01t toward achieving the intent of the inspection activities.
2.0 CODE APPLICABILITY 2.1 2.2 2.3 CNL-16-135 The rules of ASME Section XI are a mandatory program of examinations, testing and inspections for evidence of adequate safety to manage deterioration and aging effects. TV A as the owner has the responsibilities to develop a PSI Program Plan to establish a baseline of examinations to demonstrate conformance to the requirements of ASME Section XI for Inservice Inspection activities throughout the life of the plant. These responsibilities include, but are not limited to provision of access in the design and arrangement of the plant to conduct the examination and test, development of plans and schedules, including detailed examination and testing procedures for filing with the enforcement and regulatory authorities having jurisdiction at the site, conduct of the program for examination and tests, and recording of the results of the examination and tests, evaluation of the examination and test results, including corrective actions required and the actions taken. -As stated above, the edition of ASME Section XI is normally established based on the referenced code edition and addenda of I OCFR 50.55a, that is in effect six month before the date of issuance of the initial construction permit. The applicable Code would have been the 197 I Edition through Winter 1971 Addenda of ASME Section XI. Since 10 CFR 50.55a(g)(2) also allows the use of subsequent Code Editions/
Addenda which are incorporated by reference in 10 CFR 50.55a(b)(2), the 2001 Edition, through 2003 Addenda was identified as the applicable Code of Record based on the date associated with resumption of construction activities.
10CFR50.55a Codes and Standards, dated Febmary 27, 2008, specifically 10CFRS0.55a (b)(2), referencesSection XI through 2003 Addenda. Therefore, the 200 I Edition through the 2003 Addenda of Section XI, Division l, Inservice Inspection of Nuclear Power Plant Components is incorporated by reference and will be used to develop this program plan and provide the requirements for examination, testing and inspection of completed components and systems, subject to the listed limitations and modifications referenced throughout this document.
Reference the Relief Request Section 9.0 RR "WBN-2/PSI-2" for additional detail information and basis. E2-10of101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 10 of 100 2.4 Subsequent editions and addenda of ASME Section XI which are incorporated by reference in 10CFR50.55a may be used, subject to documentation as describe in Regulatory Issue Summary 2004-12 and the applicable related requirements, limitations and modifications.
2.5 The Authorized Nuclear Inservice lnspector(s) (ANTI) are assigned to review, verify and certify that the responsibilities and the mandatory requirements of ASME Section XI as written in this document are met. 2.5.1 The Inspector shall review the initial program plan, prior to the start of preservice inspections as well as revisions to the program plan. Also, the Inspector shall submit a report to the program owner documenting the review of the initial program plan and each revision thereafter.
The review shall cover the features that are affected by the requirements of Section XI and this document, as applicable.
Shop and field preservice examinations are exempt from prior review. 2.5.2 The Inspector shall verify that the required examinations of this document, have been performed and the results recorded.
Also, the Inspector shall verify that the nondestructive examination methods used follow the techniques specified and that the examinations are performed in accordance with written qualified procedures and by personnel qualified in accordance with the requirements of ASME Section XL In addition, the Inspector has the prerogative to require re-qualification of any examiner or procedure when they have reason to believe the requirements are not met. 2.5.3 The Inspector shall perform any additional investigations necessary to verify that all applicable requirements of this program plan have been met. 2.5.4 The Inspector shall certify the examination records after verifying that the requirements of this program plan have been met and that the records are correct. A periodic status of examination record review should be communicated with the ANH in order to prevent a large backlog of rn1-reviewed examination records. 2.5;5 WBN-2 shall arrange for the Inspector to have access to all parts of the plant as necessary to make the required inspections and that the Inspector shall be notified and kept informed in advance when the components will be ready for inspection.
2.6 Application of this Code and Code of Record begins \Vhen the requirements of the Construction Code have been satisfied.
3.0 DESCRIPTION
3.1 SCOPE CNL-16-135 This PSI Program Plan identifies the areas subject to inspection, responsibilities, provisions for accessibility and inspectability, examination methods and procedures, frequency of inspections, record keeping and report requirements, evaluation of inspection results and subsequent disposition for results of evaluations.
E2-11 of 101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 11 of 100 3.2 JURISDICTION The jurisdiction of this PSI Program Plan covers the systems that have met all the requirements of the Construction Code, commencing when the construction code requirements have been met, irrespective of physical location.
When portions of systems are completed at different time's jurisdiction of this division shall cover only those portions for which all of the construction requirements have been met. Prior to installation, an item that has met all requirements of the construction code may be corrected using the rules of either the construction code or this division, as determined by WBN-2. 3.3 RESPONSIBILITY The responsibilities of maintaining this PSI Program Plan are the same as for the ISI Program Plan in 2-TRI-0-10.1, "AS.ME Section XI ISl/NDE Program" and NPG-SPP-09.1, "ASME Code and Augmented Programs".
3.4 APPLICATION Components identified in this program plan for examination include items such as the reactor vessel, reactor pressure vessel internals (including the core support structure), steam generators, pressurizer, piping systems (including their valves, pumps and heat exchangers) and all respective supports to the components.
Shop and field examinations may be credited for preservice examination of Class 1 or 2 components in Subsections IWB or IWC provided the requirements of IWB-2200(b) or IWC-2200(b), respectively, are met. 3.4.1 The following items are part of the Section XI Preservice Inspection requirements, but are not included in this document:
3.4. l. I The Repair/Replacement (R/R) Program Plan is utilized to perform the required activities for ASME Section XI components, and is in accordance with TV A and Watts Bar Procedures NPG-SPP-09
.1.3, Tl-l 00.014 and NC PP-15, and R/R work order packages.
3.4.1.2 The requirements of Examination Category 8-P, C-H and D-B, All Pressure Retaining Components for System Leakage Tests, are not required prior to initial plant startup. A System Pressure Test Program Plan and Schedule will be developed as required to perform the examination for systems and components as outlined in ASME Section XI, Articles IW A-5000, IWB-5000, IWC-5000 and IWD-5000 for all Class 1, 2, and 3 components, with the limitations and modifications as outlined in IOCFR50.55a for the inservice interval requirements.
3.4.l.3 The IWB requirements of Steam Generator Tubing of Examination Category B-Q, regarding the extent and frequency of the examination, is governed by Technical Specification and documented in the Steam Generator Tubing Program Plan and Schedule.
NEDP-16, "Steam Generator Program," provides the requirements for implementation of the preservice inspection of steam generator tubing. CNL-16-135 E2-12of101 NC PROJECT PROCEDURE WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 Page 12 of 100 3.4.1.4 The IWF-5000 requirements for preservice examination and testing of snubbers will be perf01med using Subsection lSTD of the ASME/ANSI OM Code 2001 Edition through 2003 OMb Addenda, as permitted by 10CFR50.55a(b)(3)(v).
Examinations shall be performed using the VT-3 visual examination method described in IWA-2213.
as amended by Relief Request WNB-2/PSl-4 (refer to Section 9.0). Refer to 2-SI-0-912, "Snubber Visual Examination (Hydraulic and Mechanical)", for a listing of snubbers.
Section 7.0 of this procedure has a listing of PSI snubbers with a cross reference to the snubber UN IDs. The ISI drawings, by system, show snubber field locations.
3 .4.1.5 The lWE requirements for Class MC and Metal lie Liners of Class CC components are documented in the IWE Program Plan and Schedule.
The requirements will be utilized to perfonn the required examination as addressed by Subsection IWE, with limitations and modifications outlined in 10CFR50.55a(b)(2)(ix) and subparagraphs (A), (B), and (F) through (I). 3 .4.1.6 The lWL requirements for Class CC Concrete Components is defined at WBN-2 as a concrete structural slab that is covered by a liner and a concrete floor making it inaccessible for examination and therefore exempt from examination in accordance with IWL-1220.
The remaining Shield Building wall is a reinforced concrete structure similar in shape to the steel containment vessel but is not refeITed to as a concrete containment under pressure.
However, the concrete stmctural slab (containment floor) is to the repair/replacement requirements of Article IWL of ASME Section XI. 3.5 CLASSIFICATION AND BOUNDARIES 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5 CNL-16-135 A list of flow diagrams pertaining to the systems boundaries indicating the TV A Class A, B, C and D or ASME Class I, 2 and 3 systems, structures and components required to be examined is included in Section I 1. A list of weld and suppmt location drawings based on the flow diagram boundaries and utilized for component identification and location within those boundaries is also included in Section 11. The rnles of IWB shall be applied to those components that are classified ASME Class 1 or TV A Class A. The rules of I WC shall be applied to those components that are classified ASME Class 2 or TV A Class B. The rules ofIWD shall be applied to those components that are classified ASME Class 3 or TV A Class C or D. E2-13of101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 13 of 100 3.5.6 The requirements of lWF shall be applied to component supports classified ASME Class I, 2 and 3 or TV A Class A, B. C and D as describe above. 3 .5. 7 Optional construction of a component within a system boundary to a classification higher than the minimum class established in the component Design Specification shall not affect the overall system classification by which the applicable rules are determined.
3.5.8 Where all components within the system boundary or isolable portions of the system boundary are classified to a higher class than required by the group classification criteria, the rules of the higher classification may be applied, provided the rules of the higher classification apply in their entirety.
3.5.9 The portion of piping that penetrates a containment vessel, which is required by Section III to be designed to Class 1 or Class 2 rules for piping and which may differ from the classification of the balance of the piping system, need not affect the overall system classification.
3 .5 .10 If a system safety criteria perm its a system to be nonnuclear safety class and Watts Bar optionally classifies and constructs that system, or portion thereof, to Class 2 or Class 3 requirements, the application of the rules is at the option of Watts Bar. 3.5.11 The High Pressure Safety Injection (HPSI) System, as described in ASME Section XI, IWC-122 l(b), consists of the. Refueling Water Storage Tank (RWST), piping from the RWST to the CVCS and SIS Pumps (including the pumps), piping from the CVCS and SIS Pumps to the RCS, and CVCS piping that provides RCP Seal Injection to the RCP Seals. 3.6 ACCESSIBILITY CNL-16-135 Provisions for accessibility shall include the following considerations:
3.6.l 3.6.2 3.6.3 3.6.4 3.6.5 Design considerations other than access provisions may be needed for specific components to render preservice/inservice inspections practical, such as surface finish of components subject to cmd or corrosion product buildup, material selection to minimize activation in service and shielding from irradiation effects. Access for the Inspector, examination personnel, and equipment necessary to conduct the examinations shall be provided.
Sufficient space for removal and storage of structural members, shielding and insulation shall be provided.
Installation and support of handling machinery where required to facilitate removal, disassembly and storage of equipment, components and other materials shall be provided.
Performance of examinations altemati ve to those specified in the event structural
- defects or indications are revealed that may require such alternative examinations, when necessary.
- E2-14 of 101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERV/CE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 14 of 100 3.6.6 Necessaty operations associated with repair/replacement activities shall be perfotmed.
3.7 REFERENCE.D STANDARDS AND SPECIFICATIONS When standards and specifications are referenced, their revision date or indicator shall be as listed in ASME Section XI, 2001 Edition through 2003 Addenda, specifically Table IW A-1600-1.
3.8 EXAMINATION METHODS CNL-16-135 ASME Section XI identifies three types of examinations to perform inspections as visual, surface and volumetric.
The actual examination method is defined and the techniques used are described in the legend below: 3.8.1 3.8.2 3.8.3 Visual (VT), an examination method used to evaluate an item by observation.
VT -I Detection of Surface Conditions VT -2 Evidence of Leakage VT -3 General Mechanical and Structural Conditions Surface (Sur), an examination method used to detect the presence of discontinuities on the surface of the material.
PT -Liquid Penetrant MT -Magnetic Particle ET -Eddy Current Note: 10CFR50.55a(b)(:2)(xxii), prohibits the use of an ultrasonic examination method for surface examination as allowed by IWA-2220.
Volumetric (Vol), an examination method used to detect the presence of discontinuities throughout the vo 1 ume of material.
UT -Ultrasonic RT -Radiography The examination method or methods to be used on a component are specified in the sunuuaty tables in Section 4.0, 5.0, 6.0 and 7.0 for ASME Class 1, 2 and 3 components and/or parts. When preparation of a surface for nondestmctive examination is required, the preparation shall be by a mechanical method. Such surfaces shall be blended into the surrounding area as may be required to perform the examination.
The wall thickness shall not be reduced below the minimum thickness required by design. For surface conditioning of dissimilar metal welds the applicable provisions of IEP-500 shall be applied. All the above nondestructive examinations will be performed using specific techniques and procedures that are identified in ASME Section XI, or alternative examinations that are demonstrated to be equivalent or superior to those identified.
The provision for substitution of these alternative examination E2-15 of 101 NC PROJECT PROCEDURE WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN WBN-2 PSI REVISION 11 Page 15 of 100 methods, combination of methods, or newly developed techniques as outlined in IW A-2240 will utilize the 1997 Addenda of Section XI as stated in 1 OCFR50.55a(b
)(2)(xix).
3.8.4 The extent of exam and examination requirements for volume or area coverage, as required in the summary tables of this document for each component, shall be documented on the applicable examination record and shall identify both the cause and percentage ofreduced examination coverage.
Reference to Code Case N-460 when the entire examination volume or area cannot be examined due to interference by another component or pa1t geometry.
3.8.5 Nondestructive examination (NDE) procedures are controlled in accordance with IEP-100, "Administration of Nondestructive Examination (NDE) Procedures." A listing ofNDE procedures is provided in ISOPM-S02-TOC, "ISO Program Manuals NOE Procedures Table of Contents." These procedures are controlled and available electronically in the Business Suppo1t Library (BSL). 3.9 NONDESTRUCTIVE EXAMINATION PERSONNEL Personnel performing nondestructive examinations to this program plan shall be qualified and certified using a written practice prepared in accordance with ASME Section XI, as modified by IOCFR50.55a(b)(2)(xiv), (xv), (xvi), (xviii) and (xxiv). The written practice shall control the personnel requirement for nondestructive examination for this document and is outlined with the additional provisions of 10CFR50.55a regarding personnel qualification and certification as noted below. 3. 9.1 I OCFR50.55a(b
)(2)(xiv), Appendix VIII personnel qualification.
3.9.2 I OCFR50.55a(b)(2)(xv), Appendix VIII specimen set and qualification requirements.
3.9.3 I OCFR50.55a(b)(2)(xvi), Appendix Vlll single side ferritic vessel and piping and stainless steel piping examination.
3 .9.4 1 OCFR50.55a(b
)(2)(xviii), Certification of NDE personnel.
3.9.5 10CFR50.55a(b)(2)(xxiv), Incorporation of the Performance Demonstration Initiative and Addition of Ultrasonic Examination Criteria.
3.10 INSPECTION INTERVAL The Preservice Inspection Program is prepared in accordance with Program B of ASME Section XI to establish the baseline inspections for future inspection intervals.
3.11 COMPONENT RE.FERENCE SYSTEM CNL-16-135 A component reference system, such as TVA Procedure N-GP-8 Weld Reference System, shall be established during the preservice examinations and will continue to be used during the Inservice Inspection process. This applies to all components inspected in the Class I, 2 and 3 systems, including piping, vessel and other components, where practical.
The E2-16of101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 16of100 drawings used for PSI are based on the classification of the boundaries outlined on the WBN Unit 2 Flow Diagrams to establish the basis for the inte1Telationship with TV A classification of components and ASME Section XI inspection activities as described in Technical Position TP-1, listed in this document.
The identification of the components required to be inspected by PSI shall be the same as or similar to the identification recorded for the code data report and/or shop construction records. For the purpose of traceability of field and shop weld components on the PSI/IS! weld and support location drawing, the referenced isometric and the numbering of the welds on the isometric shall be used wherever possible.
3.12 PROGRAM PLAN AND SCHEDULES The program plan summary tables contained in Sections 4.0, 5.0, 6.0 and 7.0 are by examination category as outlined for ASME Section XI components.
3.12. l For each examination category, the summary tables identify the item number, component or pati, compliance to the Watts Bar Unit-2, examination method, examination figure, extent of exam, acceptance standard, total population and required examinations for each category item, total examination in the category and notes pertaining to the items. It should be noted that the total population and required examinations may change during the preservice examination period due to changes, modifications and actual walkdowns of the systems but will be document for the summaty repoti for the initial inservice inspection activities.
3.12.2 The program schedule, which is directly related to the summary tables of the program plan, will list the specific identification number of components or parts (welds, bolts, studs or other items) with their, code category and item numbers, method of exam, area to be examined as a minimum and any other essential information.
3.12.3 During the PSI activities a list shall be maintained of the components examined and as a minimum the component or pmi number, the report number, acceptance and/or evaluation process, percentage of examination volume or area complete, with an explanation of90% or less coverage, if applicable and reported to the program owner. 3.13 EVALUATION OF RECORDED CONDITIONS CNL-16-135 Evaluation shall be made oftlaws detected during the examinations as required by ASME Section XI, Articles IWB-3000 for Class 1 components, IWC-3000 for Class 2 components, and JWD-3000 for Class 3 components and IWF-3000 for component supports.
Flaws detected shall be sized by bounding rectangle or square the flaw for the purpose of description and dimensioning as described in Section XI, IWA-3300.
Flaw Characterization, or IWA-3400, Linear Flaws. All flaws shall be evaluated, after they have been characterized, by comparing the results with the acceptance standard specified in the summary tables. E2-17 of 101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 17 of 100 3.14 RECORDS AND REPORTS CNL-16-135 Examination records and reports shall be filed and maintained in a manner that will allow access for future reference.
The record keeping and reporting requirements in this program meets the requirements of IW A-6000 of Section XI. These activities are requirements in addition to being implemented by Watts Bar procedures for, Record Control. Nuclear Construction (NC) Project Procedure (PP), specifically NC PP-15 requires that the PSI program owner provide instructions for the PSI Summary Report and Site Final Report the following shall be submitted as a minimum. 3.14. l Prepare and submit the PSI Summary Report to lJ2 Site Licensing for processing and submittal to the NRC. The PSI Summary Report shall be submitted to the NRC prior to the date that WBN 2 is placed into commercial service. The summary report shall contain the following information:
Owner's Report for Preservice Inspections, Form NIS-1 or OAR-1 Owner's Report for Repair/Replacement Activities, Form NIS-2 or NIS-2A Steam Generator Tubing Inservice Inspections Components Examined Examination Category and Item Number Code Cases, as applicable Examination Method Total number of components Number of components required to be examined Relief Requests written to date Pressure Test reports (if applicable)
Cover sheet providing the following information:
Date of document completion Name and address of Owner Name and address of generating plant Name or number designation of the unit Commercial Service Date for the unit 3 .14.2 Prepare the Site Final Report, which includes all pertinent PSI data such as Personnel Certifications, Examination Data Sheets, and the PSI Summary Report. Submit the Site Final Report to Management Services for lifetime retention as a QA record. If possible, the report should be (but is not required to be) issued by Fuel Load to ensure documentation is captured before construction personnel depatt. The Site Final Report shall contain, but not be limited to, the following The PSI Summary Repott Summary of PSI examinations on ASME Class 3 Non-Regulatory Augmented Examinations Summary of Personnel Certifications E2-18 of 101 J NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERV/CE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 18 of JOO 3.15 IWB REQUIREMENTS AND EXEMPTIONS CNL-16-135 3.15. l Subsection IWB provides the rules and requirements for Class 1 pressure retaining components and their integral attachments.
3 .15 .2 Preservice examinations required to be performed and completed in the Class I systems are extended to include essentially 100% of the pressure retaining welds in all non-exempt components prior to initial plant startup, except examination category B-P, the VT-3 requirements for the internal surfaces of categories B-L-2 and B-M-2 and category B-0 shall be extended to include only the welds in the outer peripheral of the control rod housings.
3 .15 .3 Component requirements shall be examined as specified listed in the Summary Tables in Section 4.0 of this document.
I OCFR50.55a provides the following requirements in lieu of and in addition to the requirements contained within this document:
3.15.3.l 10CFR50.55a(b)(2)(xxi) requires inclusion of Items B3.120 and 83.140 examination requirements ofthe 1998 Edition be addressed.
3.15.4 Shop and field examinations may serve in lieu of on-site preservice examination provided the following:
3.15.4.1 3.15.4.2 3.15.4.3 In the case of the vessels only, the examination are performed after the hydrostatic test required by Section III. Such examinations are conducted under conditions and with equipment and techniques equivalent to those that are expected to be employed for subsequent inservice examinations.
The shop and field examination records are or can be documented and identified in a form consistent with those required for records management.
3.15.5 Evaluation of Examination Results shall be in accordance with the Acceptance Standard requirements listed in the Summary Tables of Section 4.0 for lWB Class 1 components.
3 .15 .6 The following components or patts of components are exempt from the volumetric and surface examination requirements as noted in IWB-1220 of the PSI Code of Record: 3.15.6.1 3.15.6.2 3.15.6.3 Piping of NPS 1 and smaller, except for steam generator tubing; Components and their connections in piping ofNPS 1 and smaller; Reactor vessel head connections and associated piping, NPS 2 and smaller, made inaccessible by control rod drive penetrations; E2-19of101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 19 of 100 3.15.6.4 Welds or portions of welds that are inaccessible due to being encased inside concrete, buried underground, located inside a penetration, or encapsulated by guard pipe. Note: Piping is defined as having a cumulative inlet and cumulative outlet pipe cross-sectional area neither of which exceeds the nominal outside diameter cross-sectional area of the designated size. 3.16 IWC REQUIREMENTS AND EXEMPTIONS CNL-16-135 3 .16.1 Subsection IWC provides the rules and requirements for Class 2 pressure retaining components and their integral attachments.
3 .16.2 The preservice inspection requirements shall apply to those Class 2 components initially selected for examination (except category C-H) and not exempt or excluded from inservice examination, shall be perfonned and completed prior to initial plant startup. 3 .16.3 Components shall be examined as specified in the Summaty Tables for IWC listed in Section 5.0 of this document.
3 .16.4 Shop and field examinations may serve in lieu of on-site preservice examination provided the following:
3.16.4.l 3.16.4.2 3.16.4.3 In the case of the vessels only, the examination are perfonned after the hydrostatic test required by Section III. Such examinations are conducted under conditions and with equipment and techniques equivalent to those that are expected to be employed for subsequent inservice examinations.
The shop and field examination records are or can be documented and identified in a form consistent with those required for records management.
3 .16.5 The following Class 2 components or parts of components are exempt from the volumetric and surface examination requirements.
3.16.5. l Class 2 components within RHR, ECC and CHR systems or portions of systems. (a) For systems, except the High Pressure Safety lnjection; (I) Class 2 piping N PS 4 and smaller; (2) Class 2 vessels, pumps and valves and their connections in piping NPS 4 and smaller: (b) Class 2 High Pressure Safety Injection portion; E2-20 of 101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 20 of 100 CNL-16-135 (1) Class 2 piping NPS 1 Yi and smaller; (2) Class 2 vessels, pumps, and valves and their connections in piping NPS 1 Yi and smaller (c) Class 2 vessels piping, pumps, valves, other components connections of any size in statically pressurized, passive (i.e. no pumps) portions (i.e., Safety Injection Tanks (SlTs) and associated discharge piping): ( d) Class 2 piping and other components of any size beyond the last shutoff valve in opened ended portions of systems that do not contain water during no11nal plant operating conditions.
3 .16.5.2 Class 2 components within systems or portions of systems other than RHR., ECC and CHR systems. 3.16.5.3 (a) For Class 2 systems, except for the Auxiliary Feedwater System. (1) Class 2 piping NPS 4 and smaller; (2) Class 2 vessels, pumps and valves and their connections in piping NPS 4 and smaller; (b) Class 2 Auxiliary Feed water Systems. ( 1) Class 2 piping NPS 1 Yi and smaller; (2) Class 2 vessels, pumps, and valves and their connections in piping NPS l Yi and smaller (c) Class 2 vessels piping, pumps, valves, other components connections of any size in systems that operate (when the system function is required) at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200° F (93°C). ( d) Class 2 piping and other components of any size beyond the last shutoff valve in opened portions of systems that do not contain water during normal plant operating conditions.
Class 2 components that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by guard pipe. 3.16.6 Evaluation of examination results shall be in accordance with the acceptance standard requirements listed in the Summary tables of Section 5.0 for IWC Class 2 components.
E2-21 of 101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 21 of 100 Note: Piping is defined as having a cumulative inlet and cumulative outlet pipe sectional area neither of which exceeds the nominal outside diameter cross-sectional area of the designated size. 3.17 IWD REQUIREMENTS AND EXEMPTIONS CNL-16-135 3 .17.1 Subsection IWD provides the ml es and requirements for Class 3 pressure retaining components and their integral attachments.
3 .17 .2 The preservice inspection requirements, with the exception of category D-B, shall be performed and documented completely once prior to initial plant startup and shall apply to pressure retaining components and their integral attachments on Class 3 systems in support of the following fi.mctions: (a) reactor shutdown (b) emergency core cooling ( c) containment heat removal ( d) atmosphere cleanup (e) reactor residual heat removal (f) residual heat removal from spent fuel storage pool 3.17.3 Components required to he examined are specified in the Summary Tables for IWD listed in Section 6.0 of this document.
3 .17.4 The following Class 3 components or parts of components are exempted from the VT-I visual examination requirements. (a) piping NPS 4 and smaller (b) vessels, pumps, and valves and their connections in piping NPS 4 and smaller (c) components that operate at a pressure of 275 psig or less and at a temperature of200°F or less in systems or portions of systems whose function is not required in support of reactor residual heat removal, containment heat removal and emergency core cooling (d) welds or portions of welds that are inaccessible due to being encased in concrete.
buried underground, located inside a penetration or encapsulated by guard pipe. 3 .17 .5 Evaluation of examination results shall be in accordance with the acceptance standard requirements listed in the Summary tables of Section 6.0 for IWD Class 3 components.
Note: Piping is defined as having a cumulative inlet and cumulative outlet pipe sectional area neither of which exceeds the nominal outside diameter cross-sectional area of the designated size. E2-22 of 101 ' **--*****.!
NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 22 of 100 3.18 IWF REQUIREMENTS AND EXEMPTIONS 3 .18. l The requirements for examination of Class 1, 2, 3 and MC component supports of nonexempt components are outlined within this section. The examination requirements shall apply to piping supports and supports for vessels, pumps and valves. Note: There are no MC supports based on the design as being a free standing steel containment.
3.18.2 An initial preservice examination is to be performed on all component suppo11s, not exempted by this document, once prior to startup. Component supports within systems that operate at a temperature greater than 200°F during normal operations shall be performed during or following initial system heatup and cooldown.
3.18.2.1 Component supports that have been adjusted in accordance with the acceptance standard for component support or corrected by repair/replacement shall be reexamined unless determine unnecessary by the evaluations.
3 .18.3 The preservice visual examination and functional testing requirements of Snubbers will use Subsection lSTD of the ASME/ ANSI OM 2001 Edition through OMb 2003 Code as allowed by I OCFR50.55a(b)(3)(v).
Examination of snubbers shall be perfonned using the VT-3 visual examination method described in lWA-2213, as amended by Relief Request WNB-2/PSl-4 (refer to Section 9.0). ISTD-4120 states that if the period between the preservice examination and initial system preoperational test exceeds 6 months, reexamination shall be performed in accordance with ISTD-41 IO(a), ISTD-4llO(d), and ISTD-41 lO(e). This reexamination may be accomplished in conjunction with ISTD-4130.
Integral and non-integral attachments for snubbers, including Jugs, pins, bolting and clamps, shall be examined in accordance with the requirements of this document.
Thermal movement verification of snubbers will be in accordance with procedure 2-PTI-999-02, "Thermal Expansion" and 2-PAT-1.8, "Thern1al Expansion of Piping Systems".
-3.18.4 Supports exempt from the examination requirements are those connected to piping and other items exempted from volumetric., surface, VT-1 or VT-3 visual examination.
In addition, portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe are also exempt from the examination requirements.
CNL-16-135 E2-23of101 NC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 23 of I 00 CNL-16-135 3.18.5 The support examination boundaries for both integral and non-integral supports are as follows. (a) The boundary of an integral support connected to a pressure retaining component is the distance from the pressure retaining component as indicated for Class 1, 2 and 3. (b) The boundary of an integral suppo1t connected to a building structure is the surface of the building structure. ( c) The boundary of a non-integral support connected to a pressure retaining component is the contact surface between the component and the support. ( d) The boundary of a non-integral support connected to a building structure is the surface of the building structure. ( e) Where the mechanical connection of a non-integral suppo1t is buried within the component insulation, the support boundary may extend from the surface of the component insulation, provided the support either carries the weight of the component or serves as a structural restraint in compress10n. (f) The examination boundary of an intervening element shall include the attachment portion, which includes welds, bolting, pins, clamps, etc. of the intervening element to pressure retaining components, integral and non-integral attachments of pressure retaining components, and integral and non-integral supports.
The examination boundary does not include the attachment of the intervening element to the building structure. (g) All integral and non-integral connections within the boundary governed by IWF rules and requirements are included.
- 3. l 8.6 Examination of component supports shall include: (a) mechanical connections to pressure retaining components and building structure.
For pipe-clamp-type supports, the mechanical connection to the pressure boundary includes the bolting, pins, and their i11te1face to the clamp, but does not include the component-to-clamp interface. (b) weld connections to building structure ( c) weld and mechanical connections at intennediate joints in connected integral and nonintegral supports (d) clearances of guides and stops, alignment of supports, and assembly of support items E2-24of101 NC . WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERV/CE INSPECTION PROGRAM PLAN REVISION 11 PROCEDURE Page 24 of 100 ( e) hot or cold settings of spring supports and constant load supports (f) accessible sliding surfaces 3.18.7 The methods of examination shall comply with those listed in Section 7.0 for IWF Summary Tables. Alternative methods of examination meeting the requirements of IW A-2240 may be used. Examinations that detect conditions that require evaluation may be supplemented by other examination methods and techniques to determine the character of the flaw (that is, size, shape, and orientation).
Visual examinations that detect surface flaws that exceed the acceptance criteria may be supplemented by either surface or volumetric examinations.
3.18.8 Evaluation of examination results shall be in accordance with the Acceptance Standard requirements listed in the Summary Table of Section 7.0 for IWF Class 1, 2 and 3 component supports.
3.19 CODE CASES CNL-16-135 3.19. l The following Code Cases are accepted for use in Regulatory Guide 1.147, Rev 17, and shall be utilized where applicable:
N-460 Alternative Examination Coverage for Class 1and2 welds. To be used on all IWB-2500, Class 1 and IWC-2500, Class 2 welds, Section Xl, Division 1. N-532-5 Repair/Replacement Activity Documentation Requirements and Inservice Inspection Summary Repott Preparation and Submission,Section XI, Division 1. N-686-1 Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3,Section XI, Division 1 N-695 Qualification Requirements for Dissimilar Metal Piping Welds,Section XI Division 1 N-696 Qualification Requirements for Appendix VIII Piping Examinations Conducted from the Inside Surface,Section XI, Division I 3 .19 .2 The following Code Case is conditionally accepted for use in Regulatory Guide 1.147 and shall be utilized where applicable:-
N-648-1 Alternative Requirements for Inner Radius Examinations of Class 1 Reactor Vessel Nozzles. Conditional use states that, in place of a UT examination, licensees may perform a visual examination with enhanced magnification that E2-25of101 NC PROJECT PROCEDURE WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN *. Calibration
- : .Block ID ...... * ... Size
- WB-0 I 6.00 WB-02 8.00" . WB-03 12.00" ****-*-***********************
- -*---****
- i.
.. * .16.:00.
.... 'WB-05 32.00" . 2.00" . *---* -----*----.----.-
--.. ' Schedule or ' Thickness
... . .... **-*-..... Sch 160 (0.715") . Sch 14Q
--*** .. .. . -§c,h 1.41 ()" §c:h 16.0 (0.346") WBN-2 PSI REVISION 11 Page 28 of 100
- Material ********1*******-******
............*...
I SA-376 TP304
- SA-376 TP304 ; SA-376 TP316
- SA-333 Gr6 . .. ...........................
.. SA-516 Gr70 ........................
- TP304 i . : WB-06 ; WB-07 ! WB-08 i 8.oo** Sch 120 (0.758") , TP304 ____ §ch 80
........ . WB-12 . WB-13 : WB-14 .........
..... . 12.00" . 8.00 . 14.00" ...... **-******-***
-***** 3.00 2.50" . 4.00" ... ******.
40(9.}07")
- A-312 TP3 I 6 , ___ §ch_l60 ( 1.352") ... .... A-312 TP304 ........................
§C:!°l 16.QJQA50)
' TP304-H .: Sch 160 (0.396'_'.}_
__ _ SA-376 TP304 ********-***********-*
..........
- -* .................. . Sch I A-312 TP304 . . ..... . .. .. ... ...... . . . .........
.. . ...... .. ' 1.482 : SA-516 Gr70
- WB-15* __
j 1.028" . SA-376 TP304 . WB-16 WB-17 WB-18
- 12.00" .........
- ----**--
... ! 5.00'" 18.00" 6.00" ..................................... : WB-21 WB-22 1.50" I 0.00" . NOT USED _ **--*-****-
...........
Sc.::Jl.1§()(1.322")
Sch 160 (0.5??"). . Sch 80 8') .
?.\:?\;!i (Q:??2 ) Sch 1§0 (0.31}').
1.493" 1.375" DIA x 17.00" LTH STUD *NIA SA-3 76 TP304 i SA-403 WP3 16 : St\3
- Al06 GrB ' SA-376 TP304
- SA-106 Gr B
- SA-193 GrB7 WB-23 WB-24 ..........................................
---** ... .. . .. ....... .. ........................ . ""'"-'H""" """"' '* H**i** **"' ,,., '.-.. *********--**********---- .................. .
- WB-25 . . ....... -********
i WB-26
- WB-27 WB-28 . WB-29 1.250" OTA x 5.00" LTH STUD . NIA l.675"DTAx 10.SO"LTHSTUD
- NIA **-* *-_.................
.............. . .. .............. -_ .. . . 4.50" DIA x 30.50" LTH STUD *NIA
- 2.00" DIA x 8.00" L TH STUD : NI A ..................
-...... *NOT USED i 8.00" 1.206" . **-* ........ . . ...................................... . ' SA-193 GrB7 . ...... , SA-193 GrB7 ; SA-193 GrB7 SA-193 GrB7
- SA-376 TP304 ...... l ' ' .. *' *...* 1 l WB-30 i WB-31 : 5.00" 0.918" 1.125 DIA x 7.50" LTH STUD NIA SJ\}}() TP3Qj *-*-*-** AISI 4140 WB-32
- WB-33 . WB-34 ..... -*-----.. ** 1.250'" DIA x 10.00" LTH STUD NIA 10.00" 14.00" ..... . ..................... . . Sch 14() 0::90()] .. ..... . . Sch 14() U}47")_ ....
- WB-35 NOT USED *************************'***
CNL-16-135 E2-29 of 101
- AISI 4140 TP304 TP304 .. J NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN PROCEDURE , ......................................
.. .
- Calibration i
x 10.75" LTH STUD :
- 6.oo;: * ** . WB-38 i WB-39 'WB-40
- WB-41 : WB-42 1 WB-43 :
'WB-45 WB-46 \VB-47 ; 8.00" . 4.00" 12.00" ................................... 18.00" 18.00" ... ... .... .......... . FLAT 8.00" LTH x 5.00" WTH . ... . *-*-*-** ...........
- -********
.. . : 2.00" DIA x 9.00" LTH STUD .........
- -*****
14.00" . .. __ **--*** ... ...... .. ........... .. . . ... .. . ... ..
- Vessel 22.375" LTH x 6.01" WTH ....... : (9l:P.JP.
WA T-01) .... . Vessel 33.875" LTH x 6.01" WTH jQI,-.P.ID l Vessel 43.31" LTH x 8.08 WTH ***************-- ...............
... . ! WB-50 j Vessel32.75"LTHx 11.18"WTH ............... t 27.S3;;LTH x 6:00;, WTf-i ' WB-51 ............... ! (QbJ?. ... . ..... _ .. ..
- WB-52 WB-53 WB-54 . WB-55 4.00" I 0.00" 12.00"
- Pressurizer 15.00" LTH x 6.125" WTH ........ ._. _____ ,_,,, ; Pressurizer 20.00" L TH x 6.250 ! WTH
.... . . ..... Schedule or Thickness NIA ...
- 80
' 4.016" ' Sch 160 (0.516'} 40 30 (0.431") . 40 (0.641') . . 2.150" 'NIA 5.805" --*l* ... -... -*****-****** . 8.625" 11.187 10.25" 7.125" 0.656" 3.000 . 160 (1.212") 3.300" . 4.000" WBN-2 PSI REVISION 11 Page 29 of 100 , Material ............. , ....... -... .
- AISI 4140 ; SA-53 GrB SA-533 GrA A-312 TP304 Q4
- SA-403 TP304 SA-240 TP304 SA-240 TP304 ...... j, r .............................
- SA193 GrB7 ** T 8 TP3 o4 .....................
j ... ; A-508 Cl2 ' A-508 Cl2 : A-508 Cl2 : A-508 Cl2 A-508 Cl2 .. i A-508 Cl2 .. ***,**"*" .... --***---*--**--***,,, ... ..... , ......... -*--.. **!
- SA-351 Gr CF8
- SA-533 GrA Cl2 SA-533 GrA Cl2 WB-56 WB-57 .. *-*--* **-** ******* Stm Gen 25.125" LTH x 7.000" WTH 5.000" *i Pressurizer 17
- WB-58 WTH .................................... " 31.00" (ID) J. l. QQ'.' (ID) ..... . : 2.00" . 3.00"
- 3.00" ! 4.00" ******** .........
- -*-***-*****----**-****---*---*********
- WB-65 4.00" CNL-16-135 3.062" 2.400" Sch 80
... ....... ............ .. ........ ... . ........ ... :
- Sch_80 (0.343'J E2-30of101
' SA-216 GrWCC SA-533 GrA Cl2 : SA351 CF8A
- SA351 CF8A SA-376 TP304 ..............
- -*-..... ' SA-376 TP304
- SA-376 TP304 *****-...... . ' SA-3 76 TP304 , SA-376 TP304 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVJCE INSPECTION PROGRAM PLAN PROCEDURE . .
,.,.,., **--****-* .,_ ... *-*--('" . : Calibration ' i : Block ID ...... *-*-* ********-*
- WB-66 WB-67 , WB-68 WB-69 Size. (Dia.) 14.00" 16.00" I 20.00" i 24:00" i 6" DIA STUD ; 6.57" OD I 5.00" ID i WB-72 [ 6.5T:_QD I 5.00" ID '. Schedule or ! Thickness
.... --... ---.. ** .. 1 (0.3 70) . . . .. ___ . . , Sch (O.J.??J . ......... , .sch i Sch (0.375] ..... NIA : 0.787'" ; 0.786" ****************************. WBN-2 PSI REVISION 11 Page 30 of 100 ; Material A-358 TP304 A-358 TP304 A-358 TP304 A-358 TP304 AISI 4340 ....................... . SB-166 TP600 ***-*-********--*-****--***** .. ************-**** .. **** SA-479 TP304L I SA-182 ............... ,,_, _______ ........ . SB-166 TP600 i ... W..8-:n ......... J
- 2. 75. II:) . ____ .... . ' ........ ' '
TPA91 I . : . .. __ ...... --. ' ! 0.625" ; WB-74 ; 4.00" OD I 2.75" ID r***********------*-*-* --******-. **-*****-*-*-*-****.
- -*****-*****---***-*-*-**-
.. --.-...... -** *****-**-.**-****-** ,. ... *-*----* **-... i WB-75
- 4.5" dia. RCP stud : WB-7 6_ ..... .. _ : 6. ??."' 9_i_a.:.-RPV stt!d i INNER RADIUS CAL BLOCK -' FLAT
- Alternate cal block ............
--* .. *-**** . **--. ********** ......... --*****--*-****** thru _-85 __ 1 ................. .
- _____ j_4"
... __ _ ' WB-87 i 2" Pipe Sch 160 ! & -T .... r Alternate b.l.2c;_Is- .. ' .. ; WB-97 ! 98 §_9:40
- Alternate cal block
......... ._ -' .. . NIA i NIA 'NIA .337" .344" NIA ! NIA
- 479 TPA91 . .. -...... .. .......... . .... ********-*-*---**
- -
.... . -----* -!.\.540 -" ..... ! : SA-540
- SA-240 TP304 ...............
-....... **"*****l
- A-516 Gr70 A-240 TP304 ' SA-335 GrP22 --**-***--*-**'"*" SA-335 GrP22 , A-516 Gr70 ....... ._ .. _____ , ... ,. . TP304 .-.. ---**---------
... ---**** ..
- ___
l.§9-?2. ! __ x.- ....... , .... ____ ........................ ____ ..... ... -........ r CNL-16-135
- F!a.
- t.Q..6'._'
x 14") . Flat(} 4. x 1_4") E2-31 of 101
- SA-216 Gr wee : * ******---.... *h ** * .........
_ ** __ .., __ _
- SA-508 Cl-2 CNL-16-135 WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN SECTION 4.0 IWB
SUMMARY
TABLES For ASME CLASS 1 CATEGORIES B-A B-B B-D B-F B-G-1 B-G-2 B-J Pressure Retaining Welds in Reactor Vessel Pressure Retaining Welds in Vessels Other Than Reactor Vessels Full Penetration Welded Nozzles in Vessels Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles Pressure Retaining Bolting, Greater Than 2 Inches in Diameter Pressure Retaining Bolting, 2 Inches and Less in Diameter Pressure Retaining Welds in Piping B-K Welded Attachments for Vessels, Piping, Pumps and Valves B-L-1 Pressure Retaining Welds in Pump Casings B-L-2 Pump Casings -(NA reference 3.15.2) B-M-1 Pressure Retaining Welds in Valve Bodies B-M-2 Valve Bodies -(NA reference 3.15.2) B-N-1 Interior of Reactor Vessel B-N-2. Welded Core Support Structures and Interior Attachments to Reactor Vessels B-N-3 Removable Core Support Structures B-0 Pt*essure Retaining Welds in Control Rod Housings WBN-2 PSI REVISION 11 IWB
SUMMARY
TABLES Page 31 of 100 ASME Section XI items that do not apply to Watts .Bar Unit 2 within this Program Plan will be identified with, **NA to Unit-2". statement documents that thl' itl.'m does not apply and will not be rrferenced further within the program plan, schedule or summary reports. E2-32of101 ,. WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 32 of 100 Examination Category B-A, Pressure Retaining Welds in Reactor Vessel Inspection Pro: ram B Item Component Component Exam Examination Extent of Acceptance Total Required Requirements No. Examined Compliance Method Fig. No. Exam Standard Population Examination Bl.10 Shell Welds Bl.I I Circumferential Applicable Vol. IWB-2500-1 All Welds IWB-3510 4 4 (2) Bl.12 Longitudinal NA to UNIT-2 -. --Bl.20 Head Welds Accessible Bl.21 Circumferential Applicable Vol. IWB-2500-J length of IWB-3510 2 2 weld Accessible Bl.22 Meridional Applicable Vol. IWB-2500-3 length of all IWB-3510 6 6 welds 131.30 Shell to Flange Applicable Vol. lWB-2500-4 Weld (2) !WB-3510 I l Bl.40 Head to Flange Applicable Vol. & Suf. IWB-2500-5 Weld (2) lWB-3510 1 I 81.50 Repair Welds (I) Bl.51 Belt!inc region NA to UNIT-2 ----Totals Examination 8-A 14 14 NOTES: (I) NA to \Jnit-1 (])Includes essentially 100% of the weld length. 13) NA to Uuil-2 Prescrvicc activities (4) NA lo Unit-2 l'reservicc nctivities (5) NA to Uni1-2 Preservice activities CNL-16-135 E2-33of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 33 of 100 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels Inspection Pros ram B Item Component Component Exam Examination Extent of Acceptance Total Required Requirements No. Examined Compliance Method Fig. No. Exam Standard Population Examination Pressurizer 82.10 Shell Lo Head 82.11 Circumferential Applicable Vol. IW8-2500-l Both Welds IWB-3510 2 2 ' (4) !ft of all 82.12 Longitudinal Applicable Vol. lWD-2500-2 weld lWB-3510 2 2 (2) B2.20 Head Welds 82.21 Circumferential NA to UNIT-2 ----B2.22 Meridional NA to UNIT-2 ----Steam Generators (Primary side) 82.30 Head Welds B2.31 Circumferential NA to LINIT-2 ----82.32 Meridional NA to UNIT-2 ----82.40 Tubeshcct to Head Weld Applicable Vol. IWB-2500-6 Weld lWB-3510 4 4 (4) Heal Exchanger (Primary side) -Head B2.SO Head Welds 82.51 Circumforential NA to UNIT-2 ------82.52 Meridional NA to UNlT-2 -. -. --Heat Exchanger (Primary side) -Shell 82.60 Tubesheet to Head Welds NA to llN!T-2 -. -. --B2.70 Longillldinal Welds NA to UNIT-2 ------82.80 Tuhesheet to Shell Welds NA to UNIT-2 -. --. Totals ExaminAtion Cate1?orv 8-8 8 8 NOTES: (I) NA to Unit-2 Preservice activities (2) The weld selected for examination is that weld int"secting the circumferential weld. (3) NA to Unit-2 Preservicc activities !4) Includes essentially 100% of the weld length CNL-16-135 E2-34of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 34 of 100 Examination Category B-D, Full Penetration Welded Nozzles in Vessels Inspection Pro *ram B Item Component Component Exam Examination Extent of Acceptance Total Required Requirements No. (8) Examined Compliance Method Fig. No. Fxam Standard Population Examination Reactor Vessel 83.90 Nozzle to Vessel Welds Applicable Vol. IWB-2500-7 All Nozzles lWB-3512 12 12 (a) through (c) (I) 83.100 Nozzle Inside Radius Section Applicable EVT-1 (4) All Nozzles IW8-3512 12 12 (9) (I) Pressurizer 83.110 Nozzle to Vessel Welds Applicable Vol. IWB-2500-7 All No?.Zlcs IW8-35l2 6 6 (a) through (c) (I) B3.120 Nozzle Inside Radius Section Applicable Vol. (7) (4) All Nozzles IW8-35l2 6 6 (6) (I) Steam Generators (Primary side) 133.130 Nozzle to Vessel Welds NA to UNIT-2 ---133. 140 Nozzle Inside Radius Section Applicable Vol. (7) (4) All No?.Zles IWB-3512 8 8 (6) (I) Heat Exchanger (Primary side) -Head B3.150 Nozzle to Vessel Welds NA to UNlT-2 ----83.160 Nozzle Inside 1iadins Section NA to UNIT-2 ----Totals Examination Cate2ory B-D 44 44 NOTES: (li Includes 1107.z]es with full pen*tration welds to vessel shell I or head) and integrally cast nozzles, but excludes manways and handholes either welded to or integrally <ast in vessd. (2) NA to Uuit-2 Preservice activities \])NA to Unit-2 Preservice activities (4) The examination volumes shall apply to the applicable Fii,>tire shown in Figs. lWB-2500-7(a) through (d). (5) NA to lJnit-2 Preservice activities (6) IOCRF50.55a(b)f2)(xxi)(A) Table lWB-2500-1 Items B3.120 and IB.140 (Inspection Program B) in the 1998 Edition must be applied when u;;ing the 2001 Edition, 2003 Addenda. (7) A visual examination with enhanced magnification that has a resolution sensitivity to detect a I-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-.1512-1. may be performed in place ofan ultrasonic examination. reference I OCFR50.55a(bX1)(xxi)(A). (8) Category Items B3.t0 *-B3.80 are based on lnspeclion Proi,.,.am A and do not apply to Unit-2. (9) Code Case N-648-1, with conditional approval. see paragraph J.19.1 for details of exam area and other infonnation. CNL-16-135 E2-35of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 35 of 100 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles Inspection Proi ram B ltcm Component Component Exam Examination Extent of Acceptanc.: Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No. Reactor Vessel B5.IO NI'S 4 or Larger-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur lWB-2500-8 All Welds IWB-3514 8 8 85.20 Less Than NPS 4-Nozzle-Lo-Safe End Butt Welds NA to UNIT-2 ----B5.30 Nozzle-to-Safe End Socket Wdds NA to UNIT-2 ----Pressurizer B5.40 NI'S 4 or Larger-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur IWB-2500-8 All Welds lWB-3514 6 6 B5.50 Less Than NI'S 4-NouJe-to-Safe End Butt Welds NA to UNlT-2 ----85.60 Nozzle-to-Safe End Socket W clds NA to UNIT-2 ----Steam Generators B5.70 NI'S 4 or Larger-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur IWB-2500-8 All Welds !WB-3514 8 8 BS.SO Less Than NI'S 4-Nozzle-to-Safc End Butl Wdds NA to UN!T-2 ----85.90 Nozzle-to-Safe End Socket Welds NA to UNIT-2 ----Heat Exchangers B5.IOO NPS 4 or Larger-Nozzle-lo-Safe End Butt Welds NA to UNIT-2 ----135.110 Less Than NPS 4-Nozzle-to-Safe End Butt Welds NA to UNIT-2 ----85.l'.W Nozzle-to-Safe Encl Socket Welds NA Lo UNlT-2 ----Totals Examination B-F 22 22 Note: (1) NA to Unit-2 activities (2) NA to lJnit-2 Presl!rvicc activifies CNL-16-135 E2-36of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT* 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 36 of 100 . Examination Category B-G-1, Pressure Retaining Bolting, Greater than 2 in. in Diameter Inspection Pro ram B Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No. Reactor Vessel B6.10 Closure Head Nuts Applicable VT-I Surfaces All Nuts IWB-3517 5.t 54 B6.20 Closure Studs (I )(7) Applicable Vol. IWB-2500-12 All Studs IWB-3515 54 54 B6.40 Threads in Flange (2)(6) Applicable Vol. IWB-2500-12 All Flange IWB-3515 5.t 54
- Sn1d Holes 86.50 Closure Washers, Bushings (2)(&) Applicable VT-l Surfaces All Washers IWB-3517 54 54 Applicable VT-I Surfaces All Bushings IWB-3517 4 4 Pressurizer 86.60 Bolts and Studs NA to UNIT-2 ------86.70 Flange Surface, when connection disassembled NA to UNIT-2 ------B6.80 Nuts, Bushings, and Washers NA toUNIT-2 ------Steam Generators B6.90 Bolts and Studs NA to UNIT-2 ------B6.IOO Flange Surface. when connection disassembled NA to UNIT-2 ------B6.llO Nuts, Bushings, and Washers NA to UNTT-2 ------Heat Exchangers B6.120 Bolts and Studs NA to UNJT-2 -----B6.130 Flange Surface, when connection disassembled NA to lJNIT-2 ------B6.l40 N u1s, Bushings, and Washers NA to UNIT-2 ------Notes; al end section. CNL-16-135 E2-37of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT-2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 37 of 100 Examination Category B-G-1, Pressure Retaining Bolting, Greater than 2 in. in Diameter Inspection Proi ram B !tern Component Component Exam Examination Extent of Acceptance Total R..:quired Requirements No. Examined Compliance Method Fig. No. Exam Standard Population Examination Piping B6.150 Bolts and Studs NA to UNlT-2 ------B6.160 Flange Sud'ace, when connection disassembled NA Lo UNIT-2 ------136.170 Nuts, Bushings, and Washers NA to UNIT-2 ------Pumps 86.180 Bolts and Studs ( 1 ) (7) Applicable Vol. !WB-2500-12 Studs lWB-3515 96 96 136.190 Flange Surface, when connection disassembled Applicable VT-I Surfaces Flange !WB-3517 4 4 (2) (4) (6) Surfaces 136.200 Nuts, Bushings and Washers NA lo Unit-2 ----Valves B6.210 Bolts and Studs NA to Unit-2 ------86.220 Flange Surface. when connection NA to Unit-2 ------B6.230 Nuts, Bushings. and Washers NA to Unit-2 ------Totals Examination C:ateimry B-G-1 320 320 NOTES: (I) Bolting may bo oxamined: (a) in place under tension; (bl when !he connection is disassembled: Cc) when the bnlting is remowd. (li Hnshings and threads in base rnalcrial or nangcs are required to be cxamin<d only when the co1111cctions arc disassembled. Bushings may be inspc-cted in place. (3i NA to Unit-2 Prescrvice activities (4) Vis1111l examination of bolted connections, VT-1 of the flange surface, nuts and washers, for pumps is required only when the component is examined under Examination Cat<b'O'Y B-L-2. This is for one pump in a group of pumps performing functions in a system and is required only \vhcn disassembly for maintenance. repair, or volumetric cxaminntion, as stated in B-L-2. (Sec note 2 in summary tabll!' for B-L-2). (5) NA lo l!uil-2 Prcscrvicc activities. (6) Examination include:; I in. annular surface ofthmgl! surrounding l!ach stud hole or bushing. (7) When bolts or studs are removed for examination, surface examination meeting the acceptance standards of IWB-3515 may be subslituted tor voiumet1ic examinalion. I 8) Unit-2 has -I bushings installed in Rl'V stud hol.s 14. 30, 35, and 39. CNL-16-135 E2-38of101 Item No. B7.IO 87.20 87.30 87.40 ll7.50 137.60 B7.70 137.80 (4) Totals NOTES: WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN Examination Category B-G-2, Pressure Retaining Bolting, 2in. and Less in Diameter Inspection Pro1 ram B Reactor Vessel Component Examined
*----
Pressurizer (_IL(?.l_ _________ ,_ ........ ----*--**--*- Steam Generators
- -*-----*--*----**---
Heal Exchangers .. .. .. ___________________ ,_, __ , ___ _ Piping Bolt. Studs_ and Nuts (I) Pumps .... .. m ___ .. **-_ --*----*--**--* Valves ................. ______ _ CRO Housing (only when disassembled) Bolt, Studs, and Nuts (I) (4) Examination Catt'l!orv B-G-2 Component Compliance NA to Unit-2 Applicable Applicable NA to Unit-2 Applicable Applicable Applicable NA to Unit-2 (PSI) Exam Method VT-I VT-1 VT-1 VT-I VT-I Examination Requirements or Fig. No. Surface Surface Surface Surface Extent of Exam All Studs, and Nuts All Studs, and Nuts All Bolt, Studs, mid Nuts All Studs, and Nuts All Studs, and Nuts Acceptance Standard IWB-3517 IWB-3517 IWB-3517 IWB-3517 IWB-3517 ll) Bolting is required to be examined only when a connection is disassembled or bolting is removed. WBN-2 PSI REVISION 11 IWB
SUMMARY
TABLES Page 38 Total Population(5) 8 13 8 29 59 of 100 Required Examination 8 13 8 29 59 (2i For wssds. pnmps, or valves, examination (If bolting is required only when the component is examined under Examination Category B-B, B-L-2, or B-M-2. Examination of bolted connecriou is required only once during the interval. (Sec note 2 in summary table for category B-L-2 and B-M-2.) (3) NA to Unit-2 Preservice activities (4) NA to Unit-:! Prescrvice activities (5) Total population represents "bolted connections". CNL-16-135 E2-39of101 WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN Examination Category B-J, Pressure Retaining Welds in Piping Inspection Propram B Item Component Component Exam Examination Extent of Requirements No. Examined Compliance t-.*fethod Fig. No. Exam 89.10 NPS 4 or Larger 89.11 Circumferential Welds Applicable Vol. & Sur 1W8-2500-8 Welds (I) (4) (5) (6) (7) 89.20 Less Than NPS 4 89.21 Circumferential Welds other than PWR Applicable Sur. IWB-2500-8 Welds High Pressure Safoty Injection Systems (I) (4) (5) 89.22 Circumferential Welds of PWR High Applicable Vol. IWB-2500-8 Welds Pressure Safety Injection System (2) (4) (6) (7) B9.30 Brandi Pipe Connection Wdds 89.31 NI'S 4 or Larger Applicable Vol. &Sur IWB-2500-9, I 0 & Welds(\) (4) II (5) (6) (7) 89.32 Less Than NPS 4 Applicable Sur. IWB-2500-9. IO & Welds II (l) (4) (5) 89.40 Socket Welds Applicable Sur. IWB-2500-8 Welds (I) & (4) Totals Examina lion Cate1wrv B-.J Notes: ( I) Examinations shall include the following: (a) All tenuinal ends in each pipe or branch nm connected to vessels. WBN-2 PSI REVISION 11 IWB
SUMMARY
TABLES Page 39 of 100 Acceptance Total Required Standard Population Examination IW8-3514 286 286 lWB-3514 122 122 IW8-3514 43 43 IWB-3514 11 1l IW8-3514 28 28 lWB-3514 428 428 918 918 (b) All tennin:il ends and joints in each pipe or branch nm co11ncctccl to other components where the stress levels exceed either of the following limits under loads associated with specific seismic events and operational (I) primary plus secondary stress intensity range of2.4Sm for territic steel and anstenitic steel (2) cumulative usage factor lJ of 0.4 (c) All dissimilar metal welds lll>t covereJ under Category B-F. (d) Additional piping welds so that the total number of circumferential buli welds (or brauch conuection or socket welds) selected for examiuation e<Jtrnls 100% for PSI of the circumforential bu11 welds (or branch connectiou or socket welds) in I he reactor coolant piping system. This total does not include welds exempted by !WD-1220 or welds in Item No. B9.22. These additional welds ma>* be located in one loop (one loop is defioed for both PWR and flWR plants in the 1977 Edition). (2) A I 00% $ample for PS! of PWR high pressure safoty injection system circumferential welds in pipini; 2: NPS 11,2 (DN 40) and< NPS 4 (DNlOO) shall be selected for examination. This sample shall be selected from locations detcnnined by tbc Owner as most likely to be subject to thermal fatigue. The1mal fatigue may be caused by conditions such as valve leakage or turbulence effects. (3) NA to Uuil-2 Preservice activities \4) Includes essentially 100% of weld length. (5) For circnml'erential welds \vith intersecting longitudinal welds, surface examination ofthe longitudinal piµing welds is required for those portions of the welds within the examination boundaries ofinrersecting Examination Category B-F :rnd B-J circumferential welds. (6) For circumi'erential welds with intersecting longitudinal welds. volumetric examinati(ln of the lnngiludinal piping welds is required for those portions of the welds within the examination boundaries of intersecting Examination Category B-f and 13-J circumforential welds. The following requirements shall also be met: (a) When longitudinal welds are specified and locations are known. examination requirements shall be met for both transverse and parallel flaws at the intersection oft he welds and for that length of longitudinal weld within the circumferential weld examination volume. (b) When longitudinal welds are specified but locations are unkno1'1l, or the existence of longitudinal welds is uncertain, the examination requirements shall be mel for both transverse and parallel flaws witliin the entire examination volu1ne of inlersec1ing welds. (7) For welds in carbon or low alloy steels. only t11ose welds showing reportable preservice transverse indications need 10 be examined by the ultrasonic method for reflectors transverse to the weld length direction exce.pt that circumferential welds with intersecting longitudinal welds shall meet Not< (5).
- CNL-16-135 E2-40of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 40 of 100 Examination Category B-K, Welded Attachments for Vessels, Piping, Pumps and Valves Inspection Pro ram B Item Compom:nt Component Exam Examination Extent of Accc:ptance Total Required Requirements No. Examined Compliance Method Fig. No. Exam Standard Population Examination Pressure Vessels Surface IWB-2500-13. 14 Each welded BIO.IO Welded Attachments (I) Applicable (7) and 15 attachmc:nl JWB-3516 PZR 5 PZR 5 (2i(6) Piping IWB-2500-13, 14 Each welded RCS 2 RCS .1 BI0.20 Wdded Attachmc:nts (1) Applicable Surface and 15 attachment IWB-3516 SIS I SIS t (2)(5)(6) BIO.JO Pumps NA to Unit-2 ----Welded Attachments (I) BI0.40 Valves NA to lJnit-2 Welded Attachments (I) ----Totals Examination Category B-K 8 7 NOTES: (1 J Weld buildup on nozzles that is in comprc,;sion under m>rmal conditions and provides only component support is excluded from examination. Examination is limited to those wdded attachments thm meet rhe following conditions: (a> the attachment is 011 the omside smface of the pressure retaining component: tb) the attachment provides component support as defined in NF-1110: (c) the attachment weld joius the attachment either directly to the surface ,,f the cc1111po11ent or to an integrally cast or forged attachment to the compment, and (d) the attachment weld is full penetration fillet. or partial penetration. continuous or intennittenr.
- 12) The extent of the e'amiuation includes essentially 100% ofrhe length of the allachment weld at each attachment subject to examina1ic1n.
(3) NA to Unit-2 Preservicc activities [4) NA to Unil-2 Presef\*ice activities t 5) For piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports sdected for examination nuder lWF-2510 shall be examiued. (6) Examinatioll is required whenever component support member cldbmrntion, e.g .* broken, bent. or pull!!d out pm1s. is identified during operation, rcfudi11g, maintenance. e-xamination. or testing. (7) For the conligurnlions showu in Figs. fWB-2500-1.l and a surface examination from an accessible side of the attachment weld shall be performed. Alternatively, for the cm1figuration shown in Fig. lWB-1500-14, a volumetric examination of volum< A-B-C-D from an accessible side of the attaclunent weld may he performed in lieu of the surfoce examination of surfaces A-B or C-D. CNL-16-135 E2-41 of 101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 41 of 100 Examination Category B-L-1, Pressure Retaining Welds in Pump Casings; B-M-1, Pressure Retaining Welds in Valve Bodies; B-L-2, Pump Casings; B-M-2, Valve Bodies lnsoection Pro ram B Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Ex mu Standard Population Examination Fig. No. Pumps Bl2.10 Pump casing welds, B-L-J (4) Applicable VT-I IW13-2500-16 All welds IWB-3518 4 4 Bl2.20 Pump casing, B-L-2 (2) ----4 0 Valves 1312.30 Valves, less than NPS 4 valve body welds. NA ro Unit-2 B-M-1 (4) ------B 12.40 Valves. NI'S 4 or larger valve body wdds. NA to Unit-2 B-M-1 (4) ------Bl2.50 Valve body. exceeding NPS 4, (2) 29 0 B-M-2 ----Totals Exnmination Cateeorv B-L-1 37 4 NOTES: <I) NA to Unil-2 Preservice aclivities (2) NA to Unit-2 Preservice aclivities, reference TWB-2200 (3) NA to Unil-2 Preservice ac!ivities (4) tncludos essentially 100% of weld lenk>lh. CNL-16-135 E2-42 of 101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 42 of 100 Examination Category B-N-1, Interior of Reactor Vessel; B-N-2, Welded Core Support Structures and Interior Attachments to Reactor Vessels B-N-3, Removable Core Support Structures Inspection Pro1*ram B Item Component Component Exam Examination Extent& Acceptance Total Required No. Examined Compliance Method Requirements Frequency of Standard Population Examination Fig. No. Exam Reactor Vessel Each B\3.10 Vessel Interior B-N-1 (I) Applicable VT-3 Accessible Areas Inspection IWB-3520.2 I I Period Reactor Vessel (BWR) 813.20 Interior attachments within beltlinc region NA to Unit-2 ------B-N-2 B 13.30 Interior attachments beyond the beltline region NA to Unit-2 ------B-N-2 813.40 Core Support Structure NA to Unit-2 ------B-N-2 Reactor Vessel (PWR) Bl3.50 Interior attachments within beltline region NA to Unit-2 ------B-N-2 813.60 Interior attachments beyond the beltlim: region Applicabk vr-J Accessible Welds Welds IWB-3520.2 6 6 B-N-2 813.70 Core Support Stmcture Applicable VT-J Accessible Surfaces IWB-3520.2 I I B-N-3 (2) Surfaces Examination CatC!!orv B-N-1 1 I Examination Catei?orv B-N-2 6 6 Totals Examination B-N-3 l l NOTES: (I) Areas to bo examined shall the spaces above aud below the reactor core that arc mado accessible for examination by removal of components during nonnal refueling outages. (2) The structure shall be removed from the reactor vessel for examination. (3J NA to Pre:-;t!rvice iictiviries CNL-16-135 E2-43of101 WATTS BAR UNIT-2 PRESERVICE INSPECTION PROGRAM PLAN WBN-2 PSI REVISION 11 IWB
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TABLES Page 43 of 100 Examination Category B-0, Pressure Retaining Welds in Control Rod Housings Inspection Pro ram B Item Component Component Exam Examination Extent of Acceptance Total Required Requirements No. Examined Compliance Method Fig. No. Exam Standard Population Examination Reactor V esscl Volumetric 100% 814.10 Welds in CRD Housing (I) Applicable or IWB-2500-18 Peripheral IWB-3523 20 20 CRD Surface Housing Totals Examination Cate2orv B-0 20 20 Note: (l) 20 Peripheral components of the 78 Total CRD Housings. CNL-16-135 E2*A4of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWC
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 44 of 100 INDEX CATEGORY SECTION5.0 IWC
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TABLES For ASMECLASS2 C-A, Pressure Retaining Welds in Pressure Vessels C-B, Pressure Retaining Nozzle Welds in Vessels C-C, Welded Attachments for Vessels, Piping, Pumps, and Valves C-D, Pressure Retaining Bolting Greater than 2 Inch in Diameter C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Piping C-G, Pressure Retaining Welds in Pumps and Valves ASME Section XI items that do not apply to Watts Bar Unit 2 within this Program Plan will be identified with, "'NA to Unit-2, this documents the item does not apply and will not be referenced lhrther within the program plan, schedule or summary reports. CNL-16-135 E2-45of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 45 of 100 Examination Category C-A, Pressure Retaining Welds in Pressure Vessels Inspection Pro"ram B Item Component Component Exam Examination Extent and Acceptance Total Required Requirements Frequency of No. Examined Compliance Method Fig. No. Exam Standard Population Examination Welds at Volumetric gross Cl.10 Shell Circumferential Welds (I) (3) (4) Applicable (5) IWC-2500-1 structural lWC-3510 17 6 discontinuity (2) Welds at Volumetric gross Cl.20 Head Circumferential Welds ( 1) (3) (4) Applicable (5) IWC-2500-1 stnu:tural IWC-3510 II 7 disc-0ntinuity (2) Welds at Volumetric gross Cl.30 Tubesheet-lo-Shell Weld (I) (3) (4) Applicable (5) IWC-2500-2 structural IWC-3510 4 l discontinuity (2) Totals Examination Categorv C-A 32 14 NOTES: ( l) lnclndes essentially 100% of the weld length. (2) Gross structurnl discontinnity is defined in NB-3213.2. Examples betwoen shells of diftl:rem thicknesses. cylindrical shell-to-conical shell junctions. shell (or head)-to-nange welds, and head-to-shell wdds. (J) In the case ofmnltiple vessels of similar design, size. and service (such as steam genera!ors. heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels. (4) The wss<I areas selected for the initial examination shall be reexamined in the same sequence (1vcr the service lifrtime of the component. to the extent prnctical. (5) For welds in vessels with nominal wall thkkness of0.2 in. or less. a surface examination may be applied in lieu ofa volumetric examination. The examination shall include the weld and 0.5 in. on either side of the weld. The acceptance standard for the examination shall be those specified for piping in IWC-3514. CNL-16-135 E2-46of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 46 of 100 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels Inspection Proi*ram B Item Component Component Exam Examination Extent and Acceptance Total Required No. Examined Compliance Method Re<1uirements Frequency of Standard Population Examination Fig. No. Exam C2.10 Nozzles in 112 in. nominal Thickness (1) (2) (3)(4) C2.J l Nozzle-to-Shell (nozzle-lo-head) Weld Applicable Surface IWC-2500-3 (6) JWC-3511 0 0 C2.20 Nozzles Without Reinforcing Plate in Vessds > !Ii in. Nominal Thickness (1) (2) (3) (4) RHRHX 4 2 Surface and IWC-2500-4 MS 4 I C2.21 Nozzle-to Shell Weld (nozzle-IO-head) Applicable Volumetric (a),(b)or(dl (6) lWC-3511 Af1W 4 I MFW 4 I UIT 2 2 RHRHX 4 2 IWC-2500-4 MS 4 I C2.22 Nozzle Inside Radius Section Applicable Volumetric ( a),(b )or( d) {6) IWC'-3511 (7) AHV 0 0 MFW 4 l (7) BIT 0 0 C2.30 Nozzles With Reinforcing Plare in Vessels > \', in. Nominal Thickness (l) (2) (3) (4) -C2.31 Reinforcing Plate Welds to Nozzle and Vessel Applicable Surface 1WC-2500-4(c) (6) lWC-3511 cs 4 2 C2.J2 Noak-to Shell Weld (nozzle-to-head) Applicable Volumetric !WC-2500-4(c) (6) !WC-3511 cs 4 2 when inside of vessel is accessible C2.3J Nozzle-to Shell Weld (nozzle-to-head) Applicable Visual, VT-2 (5) (6) No Leakage 0 0 when inside of vessel is inaccessible Totals Examination Cate!!on* C-H 38 15 NOTES: tll Includes nozzles welded to or integrally in vessels that connect to piping runs lmnnways and handholes are excluded). lnclmles only those piping runs selected for ex.1mination under Examination Category C-F. 13) The no7.zles selected initially for examinati<'ll shall bc reexamined in the same sequence over the service lifetime of the component. to thc extenl practical. (4) In the case of multi1>le vessels of similar design, size, and service (such as stcam generators, heat exchangers). the required examinations may be limited to one vessel or distributed among the vessels. (5) The telltale hole in the reinforcing µlate shall be examined for evidence of leakage while vessel is undergoing the system leakage test as required by examination category C-H ( 6) Nozzles at tem1inal ends (I) of piping run 12). (7) AFW and BIT nozzles aro *: I 2" NPS and are therefore exempt from NoZ7Je lnuor Radius Section exams. L;NL-1 o-1 ;j!) t:.£-4 f OT 1 Ul WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWC
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 47 of 100 Examination Category C-C, Welded Attachments for Vessels, Piping, Pumps, and Valves Inspection Pro ramB Item Component Component Exam Examination Extent and Acceptance Total Required Requirements Frequency of No. Examined Compliance Method Fig. No. Exam Standard Population Examination C3.10 Pressure Vesst:ls (I) (3) Applicable Surface JWC-2500-5 (2)(4)(6) IWC-3512 11 II Welded Attachments C3.20 Piping (I) (3) Applicable Surface !WC-2500-5 (2)(4)(6) IWC-3512 121 13 Welded Attachments C3.30 Pumps (I) (3 j Applicable Surface IWC-2500-5 (2)(4)(6) IWC-3512 4 2 Welded Attachments C3.40 Valves NA to Unit2* 0 0 Welded Attachments
Totals Examination C-C 136 26 NOTES: (I) Examination is limited to those welded anachmeuts that meet the following conditions:
<a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides component support as defined in NF-1110; \c) the atladunen\ weld joins the auachmcm either directly to ll1e Sllrface of the component or to an integrally cast or forged attachment to the component; and (d) lhe attachment weld is foll penetration. fillet, or partial penetration, cominuous, or inlermittent. (2) The extent of the examinarion inclL1des essentially 100% of the leni,oth of the attachment weld at each attachment subject to examination. IJ) Seleclcd samples of welded allacluncnts shall be examined each inspection interval. (4) For mulliple vessels of similar design, function, and service, only one welded a11achmcnt of only one of the multiple vessels shall be selected for examination. (5) For piping, pumps, and valves. a sample of 10% of the welded attachments with the component supports selected for examination under !WI'-2510 shall be examined. i6) Examination is required whenever component support memher defonnation, e.g., broken, henl, or pulled out parts. is identified during operation. refueling, maintenance, examination. or testing. CNL-16-135 E2-48of101
- i. Item No. C4.IO C4.20 C:4.30 C4.40 Total NOTES: WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN Examination Category C-D, Pressure Retaining Bolting Greatel' than 2 in. in Diametel' Inspection Pro ram B Component Examined Pressure Vessels (I) (2) Bolts and Studs Piping (3) Bolts and Studs Pumps Bolts and Studs Valves Bolts and Studs Examination Catei?orv C-D Component Compliance Applicable NA to Unit2 NA tollnit2 NA to Unit 2 Exam Method Volumetric (5) Examination Requirements Fig. No. IWC-2500-6 Extent and Frequency of Exam All bolts or studs at the bolted connection (4) Acceptance Standard IWC-3513 (5) (!)The examination may be porfonned on boiling in place under load or upon disassembly of tho connoction.
WBN-2 PSI REVISION 11 IWC
SUMMARY
TABLES Page 48 Total Population BIT l ( 16 bolts) 0 0 0 of 100 Required Examination 0 0 0 (2) The examination of bolting for vessels, pumps. or valves may be conducted on one \.;cssel. one pump, or one valve mnong a group of vessels. pumps. or valves that are similar in design, size, function. and service. In addition, when lbe componont to be examined contains a of bolted connectio11s of similar design and size (such as flanged connections or manway covers), the examination may be conducted on one bolted connection among the group. (3) 'llie examination of flange bolting in piping systems may be limited to one bolted connection among n group of bolted that aro similar in design, size, function, and service. (4) The areas selected for the initial examination shall be reexamined in the same sequence over the service lifetime of the component, to the extent practical. (5j When or studs are rcmovod for oxaminalion, 511rface examination meeting the :icceptancc stand:irds of !WB-35 I 5 may be substituted for volumetric examination. CNL-16-135 E2-49of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWC
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 49 of 100 Examination Category C-F-1, Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping lnsoection Pro* ram B Item Component Component Exam Examination Extent and Acceptance Total Required No. Examined Compliance Method Requirements Frequency of Standard Population Examination Fig. No. Exam (2) (2)(3) CS.IO Piping Welds<! 3/8 in. Nominal Wall Thickness I00%of for Piping> NPS 4 each weld CS.II Circumferential (Bult) Wdds (> NPS 4) n::quiring (7) css Applicable Vol. & Sur. JWC-2500-7 IWC-3514 263 20 eves Applicable Vol. & Sur. IWC-2500-7 exan1 IWC-3514 63* 0* (7) RHRS Applicable Vol. & Sur. JWC-2500-7 (4)(5)(6) IWC-3514 282 21 SIS Applicable Vol.&Sur. IWC-2500-7 IWC-3514 296 24 C5.20 Piping Welds > 115 in. nominal Wall Thickness 100%of for Piping;:: 2 and::; NPS 4 each weld C5.21 Circumferential (Butt) Welds (I) requiring (High Pressure Safoty Injection) eves Applicable Vol.&Sur. IWC-2500-7 exam JWC-3514 201 16 SIS Applicable Vol. & Sur. IWC-2500-7 (4)(5)(6) IWC-3514 284 22 100%of each weld C5.30 Socket Welds requiring eves Applicable Sur. IWC-2500-7 exam IWC-3514 289 23 1. SIS Applicable Sur. IWC-2500-7 (4)(5)(6) IWC-3514 253 19 C5.40 Pipe Branch Connections ol'Branch Piping? !00%of NPS2 ench weld C5.41 Circumforential (Butt) Weld requiring eves Applicahle Sur. IWC-2500-i:xam JWC-3514 3 I SIS Applicable Sur. 9, I 0.11,12& 13 (4)(.5) IWC-3514 8 I Total Examination Cateeorr C-F-1 1942 147 *Piping wall less than 0.375 CNL-16-135 E2-50 of 101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWC
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TABLES NOTES: PRESERVICE INSPECTION PROGRAM PLAN Page Examination Category C-F-1, Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping Inspection Program B 50 of \I) Requirements for examination "f welds in piping"-NPS 4 (DN JOO) apply to PWR high pressure safely injection and auxiliary feedwator systems in accordance with the exemption cri1eria of IWC-1220. 100 (2) The welds sdected for examination shall include 7.5%, but not Jess than 28 welds, of all dissimilar metal. austenitic stainless steel or high alloy welds not exempted by (Some welds not exempted by IWC-1220 are not required to be nondestruclively examined per Examination C"tegory C-F-1. These welds, however, shall be iucluded in the total weld count to which the 7.5% sampling rate is applied.) The examinatious shall be distributed as follows: (a) the examinations shall be distributed among the Class 2 systems prorated. to the degree practicable. on the number of nonexempt dissimilar metal, austenitk stainless steel, or high alloy wdds in each system (i.e., ifa system contains 30% of the nonexempt welds, then 30% of the nondestructive examinations required by Examination Category C-F-1 should be performed on that system); (bl within a system. the examinations shall be distribut*ed among terminal encl*. dissimilar metal welds. and stmctural discontinuities [See Note (J)] prorated, to the degree practicable, cm th< number of nnnoxempt terminal ends. dissimilar metal welds, and stmctural discontinuities in that system; and (c) within each system, examiuations shall be distributed between line sizes prorated to the degree practicable. (3) Structural discontinuities include pipe weldjoinls to vessel noZ7Jes. valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers. flanges, etc., conforming to ANSI Bl6.9), and pipe branch connections and fittings. (4) The welds selected for examination shall be reexamined in Ilic same sequence .* during subsequent inspection intervals over the service lifetime of the piping compoucnt, to the extent practical.
- 15) For circumferential welds "ith intersecting longitndinal welds, surface examination oflhe longitudinal piping wel<ls is required for rhose portions of the welds within the examiuation boundaries of intersecting weJds. (6) For circumferential welds with intersecting longitudinal welds, volumetric examination of the longitudinal piping welds is required for those portinus of the welds within !he examination bonndmies of intersecting cirrnmferential welds. The following requirements shall also be met: (a) When longitudinal welds ore specified and locati,)us arc known, examination requirements shall be mcl for both transverse and parallel flaws at the intersection of the welds and for that length of longitudinal weld within the circumforcntial examination volume. (b) Wheu longiru<linal welds are specified but locations are unknown, or the existence of longituwnal welds is uncertain, the examinaiion requirements shall be met for both transverse and parallel flaws within the entire exmninarion volume of imersecting circumferential
'"'*\!fds. (7) The examination exemption in IWC-122l(d) is applied to Containment Spray and RHR Spray beginning ot the surface of the water/air interface in the riser piping and continuing up to the open-ended >>>ray nozzles. CNL-16-135 E2-51 of 101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWC
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 51 of 100 Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Inspection Pro ram B Item Component Component Exam Examination Extent and Acceptance Total Required Requirements Frequency of Population Examination No. Examined Compliance Method Fig. No. Exam Standard (2) (2)(3) CS.50 Piping Welds 3/8 in. Nominal Wall Thickness 100%of for Piping> NPS 4 each weld C5.51 Circumferential Welds (I) requiring ' AFWS Applicable Vol. & Snr. IWC-2500-7 exam IWC-3514 20 2 FWS Applicable Vol. &Sur. IWC-2500-7 (4)(5)(6)(7) f\VC-3514 267 20 MSS Applicable Vol. & Sur. IWC-2500-7 IWC-3514 141 ll C5.60 Piping Welds> 115 in. nominal Wall Thickness 100%of each weld for Piping<: 2 and :5. NPS 4 requiring C5.61 Circumferential Welds (I) AFWS Applicable Vol. & Sur. IWC-2500-7 IWC-3514 176 13 exam (5)(6)(7) C5.70 Socket Welds NA to Unit 2 ------C5.80 Pipe Branch Connections of Branch CS.81 NPS 2 Circumtercntial Weld (I l(4) NA !oUnit2 ------Total Examination Cateeorv C-F-2 604 46 CNL-16-135 E2-52of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT-2 IWC
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TABLES NOTES: PRESERVICE INSPECTION PROGRAM PLAN Page Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Inspection Pro2ram B 52 of (I) Requirements for examination of welds in piping 5 NPS 4 (DN I 00) apply to PWR high pressure safety injection
- rnd auxilim)'
Fcedwater systems in accordance with the exemption criteria of IWC-1220. 100 (2) The welds selected for examination shall include 7 .5%, but not less than 28 welds, of all carbon and low alloy steel welds not exempted by IWC-1220. (Some welds not exempted by IWC-1220 are not re<1uired to nondestructively examined per Examination Category C-F-2. These welds, however, shall be i11cl11ded in !he tot<tl weld cmml to which the 7.5% sampling rate is applied.) The examinations shall be distrihuted as follows: (a) the examinations shall be distributed among the Class 2 systems prorated, to the degree practicable, on the number of nonexempt carbon and low alloy steel welds in each system (i.e., if a system contains 30% of the nonexempt weld>. then 30% of the nondestructive examinations required by Examination Categot)' C-F-2 should be perfonned on that system); (b) within a system, the exmninations shall be distributed among terminal ends and structural disconcinuities [sec Note (3)] prorated. to the degree practicable. 011 the number of nonexempt tenninal ends and stncctural diSCl)lltinuities in that system: and (ci within each systom, examinations shall be distributed between line sizes proraled to the degree practicable. (3) Structural discominuities include pipe weldjoints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers, flanges, etc., conforming to ANSI Bl6.9), and pipe branch connections and fittings. (41 The welds selected for examination
- hall be reexamined in the same sequence, during subsequent inspection imervals over the service lifetime of the piping component, to the extent practical.
(5) Only those welds showing reportable preservice transverse indications need to be examined by the 1tltrasonic method for rellectors trans\'erse Ill the weld length direction. except that circumforential welds with longitudinal weld shall meet Note (7 ). (6) For circumferential welds with intersecting longitudinal welds, surface examination of the longitudinal piping weld5 is required for those portions of the welds within lhe exmnination bounJaries of intersecting welds. (7i For circumferential wdds with intersecting longitudinal welds. volumelric examination of the longincdinal piping welds is required for those portions of the welds within the examination boundaries of intersec.ting cfrcun1fcrc1ltial welds. The following requirements 5J1all also b.; met: (a) When \Wlds are specified and locations are known, exnmination requirements shall be met for both transverse and parallel flaws at the intersection of the and for that lenglh oflongitudinal weld witl1in tile circumferential weld exa111ination volmnc. r.bl When longitudinal welds are specified but locations nee u11know11, or the existence of longitudinal welds is uncertain, the examination requirements shall be met for both transverse and parallel flaws within the entire examination \.'olmm: of intcrst!cting circumfernntial welds. CNL-16-135 E2-53of101 !_ Item No. C6.10 C6.20 Total NOTES: WATTS BAR UNIT-2 PRESERVICE INSPECTION PROGRAM PLAN Examination Category C-G, Pressure Retaining Welds in Pumps and Valves Inspection Pro1 ram 8 Component Component Exam Examination Extent and Acceptance Requirements Frequency of Examined Compliance Method Fig. No. Exam Standard Pumps Pumps Casing Welds NA to Unit 2 ----Valves ( 1)(2)(3) Valv..: Body Welds AFWS Applicable Surlitce IWC-2500-8 (4) IWC-3515 MSS Applicable Surface l\VC-2500-8 (4) IWC-3515 Examination Cate11orv C-G WBN-2 PSI REVISION 11 IWC
SUMMARY
TABLES Page 53 of 100 Total Required Population Examination --8 1 211 I 28 2 (1) In case of multiple pnmps or valves of similar design. size. limction. and service in a system, required weld examinations may be limited to all the in one pnmp or one valve in the same !,'TOUp or distributed among any of the pumps or valves of that same group. (2) The examination may be perfonned from either the inside or (llltside snrfoce of the component. (3) The pumps aud valves initially selected for examination shall be reexamined in the same sequence over the service liretime of the cmuponeut. lo the extent pr:tctical. (4) 100% weld$ in all components in each piping nm examined under Examination Category C-F. each inspection interval. CNL-16-135 E2-54of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN IWD
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TABLES Page 54 of 100 SECTION6.0 IWD
SUMMARY
TABLES for ASMECLASS3 INDEX CATEGORY D-A, Welded Attachments for Vessels, Piping. Pumps and Valves ASME Section XI items that do not apply to Watts Bar Unit 2 within this Program Plan will be identified with, "NA to llnit-2". this documents the item does not apply and will not be referenced further within the 11rogram plan, schedule or summary reports.
- CNL-16-135 E2-55of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWD
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 55 of 100 Examination Category D-A, Welded Attachments for Vessels, Piping, Pumps and Valves Inspection Proi ram B Item Component Component Exam Examination Extent and Acceptance Total Required Requirements Frequency of No. Examined Compliance Method Fig. No. Exam Standard Population Examination Pressure Vessels ( 1) Dl.10 Welded Applicable VT-1 IWD-2500-1 (2) (4) (5) IWD-3000 4 4 Piping (I) Dl.20 Welded Applicable VT-I IWD-2500-1 (2) (4) (5) IWD-3000 34 34 Pumps (I) IJl.30 Welded Attachments NA to Unit-2 --. -Valves 1. l) Dl.40 Welded Attachments NA to Unit-2 --. -Totnl Examination D-A 38 38 NOTES: (I) Exmnina1ion is limited to those welded anachmems that meet the followi11g conditions: (a) the attachment is on the omsiJe surface of the retaining component: lb) th< attachment provides componc11t support as defined in NF-1110: (c) lhc attaclnnent weld joins 1he allachment eilher directly to the surface o'rthe componeul or lo an inlcgrally cast or forged allachrncnt to the componem: aud (d) the attachment weld is full penetration, fill el, or partial penetration, continuous, or imem1i11ent. (2) The extent of the examination includes essenlially 100% of the length oflhe attachment weld ot each altachment subject to examination. (3) NIA to WBN-2 Prc<ervicc Examinotio11 \* (4) Examination is required whenever componcnl support member deformation, e.g., broken. bcnl, or pulled out parts, is identified during operalion, refueling, maimenance, e><llminaliou, or tesling. (5) 100% ofrcq11ircd area of each welded anaehment. each inspection inlerval or each occurrence idemilied in note. (4). CNL-16-135 E2-56of101 -**-*.! WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWF
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 56 of 100 SECTION7.0 IWF
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TABLE For ASME CLASS l, 2, 3 & MC INDEX CATEGORY F-A, Supports ASME Section XI items that do not apply to Watts Bar Unit 2 within this Program Plan will be identified with, "NA to lfnit-2", this documents the item does not apply and will not he referenced further within the program plan, schedule or summary reports. CNL-16-135 E2-57of101 item No. Fl. I 0 Fl.20 Fl.30 Fl.40 Fl.40 Total NOTES: WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN Examination Category F-A, Supports Inspection Proe:ram B Component Exam Examination Support Types Examined Requirements Compliance Method Fig. No. Class I Piping Supports ( l) (2) Applicable VT-3 IWF-1300-l Class 2 Piping Supports (l) (2) (6) Applicable VT-3 lWF-1300-1 Class 3 Piping Supports (I) (2) Applicable VT-3 IWF-1300-1 Supports Other Than Piping supports (I) Applicable VT-3 JWF-1300-1 Class I, 2 and 3 MC Supp011s NA to Unit-2 -Examination Category F-A WBN-2 PSI REVISION 11 IWF
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TABLES Page 57 of 100 Extent of Acceptance Total Rt:quired Exam Standard Population Examination (5) IWF-3410 265 265 (5) IWF-3410 1180 1180 (5) IWF-3410 314 314 (5) IWF-3410 38 38 ----1797 1797 (I) Item numbers shall be categorized Ill identify support tYl""' by component support function \e.g., A= supports such as one directional rod hangers; B supp011s such as multi-directional restraints; and C '"supports that allow thormal movement. such as springs). Reference tables below for each type. This is for future activities. t2) The totals shall be comprised of supports from each system (such as Main Steam, Feedwoter. or RHR). proportional to the total number of non-exempt supports of each type and function within each system. Reference tables below for each system. This is established for future activities. (3) NiA to WBN-2 Presen:ice Inspection. (4) N/A to WBN-2 Preservice Inspection. (5) I 00% or all supports not exempted. (6) The examination exemption in IWC-122 l(d) and !WF-!230 is applied to Containment Spray and RHR Spray Systems beginning at the surface of the water/air interface in the riser piping and continuing up to the open-ended spray nozzles. CNL-16-135 E2-58of101 ----- Sys eves RCS RHRS SIS Totals CNL-16-135 WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN Examination Category F-A, Supports Chlss l Piping Type A CLASS 1 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Item Type & Description Exam Number Method Fl.IOA Type A Supports Visual, VT-3 (one directional restraints) Fl.JOB Type B Supports Visual, VT-3 (multidirectional restraints) Type C Supports Fl.lOC (thermal movement, i.e. variable or Visual, VT-3 constant springs) F1.10D Type D Supports Visual, VT-3 (Snubber Types) Totals CLASS 1 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE TypeB TypeC TvoeD Total % Req. Total O/o Rea. Total O/o Reci. Total % 26 100 26 18 100 18 3 100 3 13 100 11 100 11 8 100 8 9 100 9 17 100 3 100 3 4 100 4 6 100 6 10 100 41 100 41 61 100 61 11 100 11 24 100 81 81 91 91 29 29 64 E2-59of101 WBN-2 PSI REVISION 11 IWF
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TABLES Page 58 of 100 Total Number 81' 91 29 64 265 Req. Totals 13 60 60 17 45 45 10 23 23 24 137 137 64 265 265 Sys AFWS css eves FWS MSS RHRS SIS ccs Totals CNL-16-135 WATTS BAR UNIT-2 PRESERVICE INSPECTION PROGRAM PLAN Total 82 80 132 21 13 76 137 1 542 F-A, Supports Class 2 Piping TvpeA O/o Rcq. 100 82 100 80 100 132 100 21 IOO 13 100 76 IOO 137 100 1 542 CLASS 2 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Item Type & Description Exam Number Method F1.20A Type A Supports Visual, VT-3 (one directional restraints) Ft.208 Type B Supports Visual, VT-3 (multidirectional restraints) Type C Supports Fl.20C (thermal movement, i.e. variable or Visual, VT-3 constant springs) Fl.20D Type D Su1lports Visual, VT-3 (Snubber Types) Totals CLASS 2 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE Type B TypcC D Total % Req. Total % Rcq. Total % 67 100 67 11 100 11 32 100 51 100 51 10 100 10 14 100 146 100 146 8 100 8 7 100 5 100 5 0 100 0 10 JOO 1 100 I 13 100 13 28 100 20 100 20 14 100 14 17 100 138 100 138 17 JOO 17 28 100 0 100 0 0 100 *o 0 100 428 428 73 73 136 E2-60of101 WBN-2 PSI REVISION 11 IWF
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TABLES Page 59 of 100 Total Number 542 428 73 136 1179 Req. Totals 32 192 192 14 155 155 7 293 293 10 36 36 28 55 55 17 127 127 28 320 320 0 1 1 136 1179 1179 Sys AFWS ccs ERCWS FPCS HP FPS Totals CNL-16-135 WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN Examination Catee:ory F-A, Su1>ports Class 3 Piping CLASS 3 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Item Type & Description Exam Number Method FI.30A Type A Supports Visual, VT-3 (one directional restraints) FI.308 Ty1>e B Supports Visual, VT-3 (multidirectional restraints) Type C Supports Fl.30C (thermal movement, i.e. variable or Visual, VT-3 constant springs) Ft.30D Type D Supports (Snubber Types) Visual. VT-3 Totals CLASS 3 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE Total Number 162 132 19 2 315 Type A Type B TvpeC Ty1>e D Total % Req. Total % Req. Total % Req. Total % Req. 27 100 27 9 100 9 4 100 4 0 100 0 59 100 59 39 JOO 39 7 IOO 7 1 100 1 76 100 76 84 100 84 8 100 8 I 100 1 0 100 0 0 100 0 0 100 0 0 100 0 0 100 0 0 100 0 0 100 0 0 100 0 162 162 132 132 19 19 2 2 E2-61 of 101 WBN-2 PSI REVISION 11 IWF
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TABLES Page 60 of 100 Totals 40 40 I06 106 169 169 0 0 0 0 315 315 CNL-16-135 WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN Examination Cate2orv F-A, Supports Class I, 2 & 3 Components CLASS 1, 2 & 3 NON-EXEMPT SUPPORTS (OTHER THAN PIPING) DISTRIBUTION BY TYPE Item Type & Description Exam Number Method FJ.40A Type A Supports Visual, VT-3 ( onc directional restraints) Fl.41B (Class I) Type B Supports (mnltidirectional restraints) Fl.428 (Class 2) (Includes 4 Class 2 SG Upper Lateral Visual, VT-3 Supports) Fl.438 (Class 3) Type C Sup1lorts F1.40C (thermal movement, i.e. variable or Visual, VT-3 constant springs) Type D Supports Fl.42D (Class 2) (Snubber Types) Visual, VT-3 4 SG Upper Lateral Suppo11s have 5 Hydraulic Snubbers each Totals E2-62of101 WBN-2 PSI REVISION 11 IWF
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TABLES Page 61 of 100 *-Total Number 0 12 19 7 0 4 42 System Code Class PZR I RPV 1 RPVH I RCP 1 SG 1 SG 2 SG 2 cs 2 eves 2 RHRS 2 SIS 2 AFWS 3 CS/CCS 3 CVCS/CCS 3 RHRS/CCS 3 Totals CNL-16-135 WATTS BAR UNIT -2 PRESERVICE INSPECTION PROGRAM PLAN Code Item No. Fl.418 Fl.418 Fl.418 Fl.41B Fl.4IB Fl.428 Fl.42D Ft.428 Fl.42B Fl.428 Fl.42B Fl.438 FI.438 Fl.438 Fl.43B CLASS 1, 2 & 3 NON-EXEMPT SUPPORTS (OTHER THAN PIPING) DISTRIBUTION BY SYSTEM & TYPE Type A TvoeB TvoeC Total O/o Rea. Total % Rcq. Total % 0 JOO 0 2 100 2 0 100 0 JOO 0 I 100 l 0 100 0 100 0 1 100 1 0 100 0 100 0 4 100 4 0 100 0 100 0 4 100 4 0 100 0 100 0 4 100 4 0 100 0 100 0 0 100 0 0 100 0 100 0 4 100 4 0 100 0 100 0 4 100 4 0 100 0 100 0 4 100 4 0 100 0 100 0 3 100 3 0 100 0 100 0 3 100 3 0 100 0 100 0 2 100 2 0 100 0 100 0 0 100 0 0 100 0 100 0 2 100 2 0 100 0 100 0 38 JOO 38 0 JOO E2-63of101 . . WBN-2 PSI REVISION 11 IWF
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TABLES Page 62 of 100 Tvoe D Totals Rea. Total % Rea. 0 0 100 0 2 2 0 0 100 0 I 1 0 0 JOO 0 .1 I 0 0 100 0 4 4 0 0 100 0 4 4 0 0 100 0 4 4 0 4 100 4 4 4 0 0 100 0 4 4 0 0 100 0 4 4 0 0 100 0 4 4 0 0 100 0 3 3 0 0 100 0 3 3 0 0 100 0 2 2 0 0 100 0 0 0 0 0 JOO 0 2 2 0 4 100 4 42 42 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWF
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 63 of 100 CNL-16-135 E2-64of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWF
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 64 of 100 :,system t jRHRS 2-47A432-3-15 F-A F1.10D 2-SNUB-063-0497. ..
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...... . *-* ................. .. .. .. "J iRHRS j47A432-3-06 jF-A JF1.10D -- .. .... ... ---.. -----**-. .. .............. ________ .. ... **----* ...................... _ .. ,,............................. ... ..---*---"* ---....... --* *------* ...... t 7 4-017 __ .. .. __ , .......... --...... . . . .... -* ........ -........ ____ .......... --... .... --.. ..... -.............. -... CNL-16-135 E2-65of101 . WBN-2 PSI REVISION 11 WATTS BAR UNIT-2 IWF
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 65 of 100 -------*-** .... ............ .: " rtNumb [AFWS 03B-2AFW-R242 , F-A ; F1 .20D : 2-SNUB-003-0448. !
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 66 of 100 ,,**" . :{ ;* ,{t /, k ........ ... _ __
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 67 of 100 CNL-16-135 E2-68of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 IWF
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 68 of 100 ,
- i.
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.. .. ................ .. .., .... ...... ... .. .. .. --.. --........ _***--j IRHRS l63-2SIS-R155 lF-A jF1.2oD----..,[2-SNUB-063-D3D5. . --I !RHRS __ [F-A __ IF1 :20[) __ & .. jRHRS J63-2SIS-R170 lf-A 'IF1.20D _ _J .. .. .. ............... __ * -__ -- -*--"-*: ........ J lRHRS 74-2RHR-R014 F-A .20D . 2-SNUB-074-0387-N & -S. Dual snubbers. ____ --***----***-----*-**--------"*-*-*-------**** __ -_-** . ....... ,. .... "" .... .. -* --------* ... *-**-----=----=--** \SIS 2-47A435-03-018 F-A 'if1 .200 ' SNUB-063-0493-B & -T. Dual snubbers. J' \sls="""--f4'iA437=2=4- .................... .. s*:0*63'.."0481:---*-"******-***** .. ........ _____ ....... .............................. -.............. !sis 12-63-014 .. . JF-A . . :IF1 .200 !12-SNUB-063-0213. . .. . .. ...... .. . .. . . ..... ... . .. . . . ! ........ ,. .......................... ... -* _ .. .... ...... ...... .... ... .. ... I 1s1s: ***_,--*--W63-"Q43 ___ ... _ .... **-----.,-----*:_,.,--- ---................. ______ ..... * --**-----
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 69 of 100 . er Cafegocy! lterrdii'umbef iS.G . . _ *.* * . thru HydraulicSnubbt:Jrs) arei t:JXamined as. 1 s.upport Io .. CNL-16-135 E2-70of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 AUGMENTED
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 70 of 100 SECTION 8.0 AUGMENTED EXAMINATION REGULATORY COMMITMENTS I. Letters from TV A to NRC: 1. WBN U2, Initial Response to Bulletins and Generic Letters, dated September 7, 2007, ML 072570676
- 2. WBN U2, Supplemental Response to NRC Bulletin 2004-01, "Inspection of Alloy 82/182/600 Materials used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors," dated September 29, 2008, ML 082750518
- 3. WBN U2, Supplemental Information Regarding Certain NRC Generic Letters and Bulletins, dated April 1, 2010, ML 100950044 For the ASME Section XI program portion, the letters listed above are divided into Preservice and Inservice requirements, excluding steam generator tubing, below. The Inservice requirements will be incorporated into the first interval ISI program for WBN Unit 2. Preservice Commitments
- l. (Attachment 3 of referenced letter land Enclosure I ofreferenced letter 3) WBN U2 will perform a baseline inspection of the RPV head penetration nozzles prior to fuel load that consists of paragraph IV.C(S)(b) of the First Revised Order EA-03-009.
- 2. (Attachment 5 of referenced letter 1) TV A will perfonn a baseline inspection (VT-2) of the lower head penetrations prior to fuel load. 3. (Attachment 6 of referenced letter I, Enclosure l of referenced letter 2, and Enclosure 5 of referenced letter 3) WBN U2 will pe1form NOE prior to and after completion of mechanical stress improvement process (MSIP) of the pressurizer power operated relief valve connections, the safety relief valve connections, and the spray line nozzle and surge line nozzle connections.
Should circumferential cracking be observed in either pressure boundary or non-pressure boundary portions of any of the locations covered by the scope of NRC Btilletin 2004-01, TV A will develop plans to perform an adequate extent-of-condition evaluation, and TV A will discuss those plans with cognizant NRC technical staff prior to starting Unit 2. CNL-16-135 E2-71of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 AUGMENTED
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 71 of lnservice Commitments I. (Enclosure I of referenced letter 3) WBN U2 will perform inspections during the first refueling outage according to 1 OCFR50.55a(g)(6)(ii)(D)(2) through (6) and ASME Code Case N-729-1. 100 2. (Attachment 5 of referenced letter 1) WBN U2 will perfonn a VT-2 examination of the RPV lower head penetrations during the first refueling outage. . 3. (Attachment 6 of referenced letter 1, Enclosure 1 of referenced letter 2, and Enclosure 5 of referenced letter 3) WBN U2 will perform bare metal visual (BMV) inspection of the upper pressurizer A 1 loy 600 locations at the first refueling outage. If any evidence of apparent reactor coolant pressure boundary leakage is discovered during the BMV examination, then 1\TDE capable of determining crack orientation will be performed in order to accurately characterize the flaw, the orientation, and extent. TVA will develop plans to perfonn an adequate extent of condition evaluation, and plans to possible expand the scope of NOE to other components in the pressurizer, which will be discussed with NRC technical staff prior to restaiting Unit 2. TV A will provide the required response for inspections performed within 60 days after completion of the first refueling outage. ' II. Other PSJJISI commitments Preservice Commitment NC0080008099 -TV A plans to submit PSI related relief requests on or before September 24, 20 I 0. Inservice Commitment NC0080008038 -Submit Inservice Inspection (JSI) program within 6 months after receiving an operating license. In. Augmented PSJJISI Exam A. Ultrasonic examination of those areas identified in calculation package 110448.301, "MRP-146 Assessment ofNormally Stagnant Non-Isolable Branch Lines. This examination will be conducted as a baseline during PSI (WBN Construction Completion Project) and at the specified periodicity during lnservice Intervals. Refer to PER 375365. Additional NOE qualification and training are required to perform these ultrasonic examinations. EXREQ is "AUGMRP" and Category is "146" in the PSI database. B. NRC Regulatory Guide 1.14, Rev I, Regulatory Position C.4.b, requires the ultrasonic and surface examination of all 4 Reactor Coolant Pump Motor Fl)'wheels. The NRC requirement is repeated in WBN-2 Technical Specification 5.7.2.10 and Technical Requirements Manual TSR 3 .4.5. l. WBN-2 PSI is utilizing shop data following fabrication as the baseline data since these exams were performed prior to press-fitting the flywheels onto the RCP Motor shafts. All 4 flywheels were examined. EXREQ is "AUG-0 I" and Categ01y is "A" in the PSI database. CNL-16-135 E2-72of101 WBN-2 PSI REVISION 11 WATTS BAR UNIT -2 AUGMENTED
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 72 of 100 IV. Other Regulatory I Code Issues A. The PSI examinations for 8 RPV Nozzle-to-Safe End (SE) welds consist of UT from the inside diameter (ID), PT from the outside diameter (OD), and Eddy Current Testing (ECT) from the ID Mechanical Stress Improvement Process (MSlP) as part of the MRP-139 Rev 1 I Alloy 600 Program and serve as baseline exams for transition to ASME Code Case N-770-1 for ISJ during the First 10-Year ISi Interval. B. The PSI exams for 6 Pressurizer Nozzle-to-SE welds consist of UT and PT from the OD after MSIP as part of the NRC Bulletin 2004-01 and serve as baseline exams for transition to ASME Code Case N-770-1 for ISI during the First 10-Year ISi Interval. C. Paragraphs A and B above should be captured in the future ISi Program for the First I 0-Year ISI Interval and in foture revisions of NPG Business Practice BP-257 and NPG Common Technical Procedure NETP-1 i3. CNL-16-135 E2-73of101 i J WBN-2 PSI REVISION 11 WATTS BAR UNIT* 2 AUGMENTED
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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 73 of 100 Examination Category A-E, Augmented Examination -Preservice Commitment Class 1 PWR Comoonents Containinl! Allov 600/82/182 Item Component Component Exam Examination Extent of Acceptance Total Required Requirements No. Rxamined Compliance Method Fig. No. Exam Standard Population Examination RPV CRD Nozzle J-Groove welds EA 03-009 UT NRC letter April 78 78 llpper NIA Note l l 1.2003 Head Vent pipe J-Groove weld (revised) or (ML030980322) I l CRD No:t.zle .I-Groove welds EA 03-009 Surface Wetted 78 78 Vent pipe ,J-Groove weld (revised) (Note '.!l N/A Surface of see above 1 I weld lipper Head Injection Voluntary UT& N/A DMW lWB-3514-2 8 8 Auxiliary Head Adapter (UPIAH) welds PT RPV NRC Bulletin Area around Lower Instrumentation No1.zle Penetrations 2003-02 VT-2 N/A instrument No Leakage 58 58 Head nozzles Spray Nozzle-to-pipe eonneetion NRC Bulletin Pre-and I I Pressurizer Relief/Safety No:r.zk-to-pipe connection 2004-0 I UT lWB-2500-8 Post-MSIP JWH-3514 -I -I Surge Nozzle-to-pipe connection I 1 Note l -Examine weld from 2" above Lhe highest point of the root of the J-groove weld on a horizontal plane and from 2" below the toe of the J-groovc weld on a horizontal plane. Note 2 -NRC EA 03-009 allows UT or surface exam or combination of both. CNL-16-135 E2-74of101 WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE RFRNumber WBN-2/PDI-4 WBN-2/PSI-l Rev 0 --------------- WBN-2/PSl-l Rev 1 WBN-2/PSI-2 WBN-2/PSI-3 WBN-2/PSI-4 16-PDI-5 CNL-16-135 SECTION9.0 REQUESTS FOR RELIEF INDEX Subject 1 OCFR50.55a Alternative Examination for RPV Shell-to -Flange 1 OCFR50.55a(a)(3)(i) Class 1 Component 1 OCFR50.55a(g)(5)(iii) Examination Limitations _________________________ ., ___ ------------------------- WBN-2 i PSI-1, Rev 1 1 OCFR50.55a(g)(5)(iii) ASME Code Class I And 2 Welds With Limited Coverage Examinations for PSI ASME Section XI 200 l IOCFR50.55a(a)(3 }(i) Edition through 2003 Addenda Code of Record Inaccessible Steam lOCFR50.55a(g)(5)(iii) Generator Lower-Shell-To-Cone Weld SG-48-5-2. Limited exam coverage. (L44 150710 002) Weepage of Hydraulic I OCFR50.55a(z)(I) Fluid from Hydraulic Snubbers on Steam Generator Upper Lateral Class 2 Suooorts Use of 5% Notches in UT I OCFR50.55a(z)(l) Calibration Blocks E2-75of101 Page 74 of 100 Status Comments Approved 9/3i09 TAC No. ME0022 Submitted to Under NRC review NRCon 10/12i2010
Re-submitted Under NRC Review with WBN-2 PSI Rev 1 I Approved 02!17/2011 TAC No. ME3113 Approved 10/0 1/20 l 5. TAC No. MF6474 Approved 04/05/2016. CAC No. MF7447 Submitted to Condition Report NRC in TVA 1041394 and Relief Letter CNL-16-Request is for all 7 022 on May 27. TV A nuclear Units. 2016. Under NRC review (L44 160517 002) WBN-2 PSI REVISION 11 NC PROJECT PROCEDURE WATTS BAR NUCLEAR PLANT UNIT 2 PRESERV/CE INSPECTION PROGRAM PLAN Technical Positions Page 75 of JOO SECTION 10.0 ASME SECTION XI TECHNICAL POSITIONS Technical determination made during implementation of this PSI program and/or the examinations to clarif)* a position .that is not clearly understandable or exclusive to Watts Bar Unit 2 from the referenced requirements. Each Technical Position should be numbered ( 1.2,3,ecL) and reference to the corresponding paragraph in this or any other document that the subject pertains to and signed by as a minimum the progrmn O\mer and a technical person, if appropriate 1md inserted in its entirety into this section following the next revision,. TP-1 TP-2 CNL-16-135 Basis for Section XI May be used for all Section Xl Section XI Class I, Boundary activities or individually as stated in Identification 2 & 3 Components the TP. Retrieval of Historical Records May be used for retrieval of Shop Records and Management Radiograph and other records Radiographs Lifetime Storage Vault. E2-76of101 NC PROJECT PROCEDURE WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN Basis for Section XI Boundary Identification Watts Bar Nuclear (WBN) Unit 2 ASME Section XI Preservice Inspection (PSI) TP-1 WBN-2 PSI REVISION 11 Technical Positions Page 76 of 100 This document is a technical position to establish the basis of the inten-elationships with TV A c.lassification system and ASME Section XI activities. Nothing in this technical position shall change the overall classification of a system or component from its original design. The intent is to adjoin the design of the plant with the inspection requirements of ASME Section XI requirements for inspection. The overall design of systems structures and components to the appropriate TVA classification is based on the guidelines in the Design Criteria Document, procedure number WB-DC-40-36, "The Classification of Piping, Pumps, Valves, and Vessels". These criteria apply to piping, pumps, valves, and other pressure retaining components within fluid systems that perform a safety function. Primary and secondary safety functions are classified according to their relative importance in protecting the health and safety of the general public. The TVA Class A. B, C and D systems are classified as ASME Section III Class I, 2 and 3 respectively, based on the relationship between the ANS Safety Class, TV A classifications, and Regulatory Guide 1.26 classifications. The Mechanical flow diagrams are labeled with the TV A classification in such a manner that the classification of every portion of a system can be determined from its flow diagram. The flow diagrams are used to designate the TV A classification A, B, C and D to establish the ASME Class 1, 2 or 3 boundaries to detennine the ASME Section XI requirements. ASME Section XI requires components identified for inspection and testing shall be governed by the group classification criteria and provides the inspection requirements for Class I, 2 and 3 components. ASME Section XI, IWA-1320 states the mles for IWB shall be applied to those systems whose components are classified ASME Class 1 and the rules for IWC apply to components classified as ASME Class 2 and the rules for IWD apply to components classified as ASME Class 3. Therefore, based on the guidance ofWB-DC-40-36 with reference to the ANS documents and Regulatory Guide 1.26 for classification of components, the labeling and marking of the boundary interface on the flow diagrams for classification of system. Section XI activities shall be dete1mined for ASME Class I. 2 and 3 systems and components. In reference to the boundary marking on the mechanical flow diagrams, Section XI inspection and testing boundaries will be determined, as required and if needed to farther distinguish the boundaries a color coding method can be used for informational purposes only for the various activities. To further distinguish the activities they are separated to explain the intent of the each and color coding of the boundaries. I) ASME Section XI Systems and Components (XISC) This activity is to identify the system boundaries for components subject to Section XI activities. The boundaries are established based on the WBN -2 design and mechanical flow diagrams that apply to items classified as TVA Class A, B, C and Dor ASME Section III Code Class 1, 2 & 3. This activity is not intended to include the Section XI inspection or testing requirements on systems or portions of a system that are optionally upgraded to a high classification, unless specifically directed by other requirements. This applies to systems of nonnuclear safety class to ASME Section III Class 2 or 3 and/or CNL-16-135 E2-77of101 WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 77 of 100 Class 3 to Class 2, Class 2 to Class I or any combination of these. All other boundaries on safety Class systems represent the activities associated with Section XI, including Repair and Replacement regardless of the reason or method that detected the condition requiring the repair/replacement. To further distinguish the boundaries a set of color coded drawing can be established and labeled (i.e.2-48W801-XISC) with the XISC to designate the activities for systems and components for this scope of Section XL Red will be used to represent TVA Safety Class A or ASME Code Class 1. Yellow will be used to represent TV A Safety Class B or ASME Code Class 2 and finally green to represent TV A Safety Class C & Dor ASME Code Class 3. This set of color coded drawing is for informational use only and should be review for changes during periodic and/or interval updates to correspond with Section XI. Note: This set of drawings may or may not be needed prior to startup as explained in NC PP-15, paragraph 2.0 C, but is needed to establish the ASME Section XI EXaminations (XIEX) and ASME Section XI Pressure Tests (XIPT) color coded drawings.
- 2) ASME Section XI Pressure Tests (XIPT) This activity is to identify the pressure testing requirements based on Section XI and within the previously established boundaries for Systems and Components.
The pressure test boundaries are determined and established by the general requirements of Article IW A-5000 for ASME Class 1, 2, & 3 systems and components requiring a pressure test. The boundary limits are generally defined by the location of the safety class interface valves within the system or as describe in IWB, IWC and IWD requirements for Class 1, 2 and 3 systems respectively. This activity is not intended to include the Section XI inspection or testing requirements on systems or portions of a system that are optionally upgraded to a high classification, unless specifically directed by other requirements. This applies to systems of nonnuclear safety class to ASME Section lII Class 2 or 3 and/or Class 3 to Class 2, Class 2 to Class 1 or any combination there of. All other boundaries on safety Class systems that represent the activities associated with Section XI are to enhance and distinguish the various pressure test boundaries. A color coded drawing can be established and labeled (i.e. 2-48W801-l-XIPT) with the XIPT, to designate the system boundaries requiring a pressure tests and a visual VT-2 to be performed. The colors used to represent Class 1, 2 & 3 components are the same as previously established. This set of drawings is for infonnational use only and should be review for changes during periodic and/or interval updates to correspond with Section XI. Note: This set of drawings is not needed prior to startup as explained in NC PP-15, paragraph 2.0 C, but is needed to establish the ASME Section XI EXaminations (XIEX) color coded drawings.
- 3) ASME Section XI EXaminations (XIEX) This activity is to identify the examination requirements based on Section XI and within the previously established boundaries for systems and components that are not exempted from volumetric, surface or visual requirements on Class 1, 2 and 3 pressure retaining components.
This activity is not intended to include the Section XI inspection or testing requirements on systems or portions of a system that are optionally upgraded to a high classification, unless specifically directed by other requirements. This applies to systems of nonnuclear safety class to ASME Section III Class 2 or 3 and/or Class 3 to Class 2, Class 2 to Class I or any combination thereof. All other boundaries on safety Class systems that represent the activities associated with Section XI are to enhance and distinguish the various examination CNL-16-135 E2-78 of 101 WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 78 of 100 boundaries. A color coded drawing can be established and labeled (i.e.2-48W801-1-XIEX) with the XIEX, to designate the system boundaries requiring an examination by volumetric, surface or visual VT-1 or VT-3 methods. The colors used to represent Class I, 2 & 3 components are the same as previously established. This set of drawings is for infonnational use only and should be review for changes during periodic and/or interval updates to correspond with Section XI. Also, the drawings will be a reference to establish the boundaries when creating the various location drawings to identify the individual examinations that will support the population of WBN Unit 2 Preservice Inspection Program Plan. 4) ASME Section XI IWE/IWL (XIIWE) This activity is to identify the examination boundaries based on Section XI IWE (ASME Categories MC) requirements that are determined to be accessible and not exempt. The boundaries will be determined by using the configuration drawing based on the design ofWBN-2. To enhance and distinguish the various examination boundaries a color coded drawing can be established and labeled XIIWE, to designate the system boundaries requiring an examination. The boundaries will be represented by an outline of the color blue to designate the boundaries for examination. This set of drawings is for informational use only and should be review for changes during periodic and/or interval updates to correspond with Section XI. Also, the drawing will be referenced to establish the detailed IWE drawing for PSI and ISi. Note: The revision on all flow diagrams and the revision (RXX) used on the informational use color coded drawing for Section XI does not have to be the same but shall be reviewed for changes that will effect the overall Section XI configuration for inspection and/or testing. As a minimum these drawing shall be reviewed prior to each period and/or interval change as described in the WBN-2 Program Plan. Prepared By: E. Lynn McClain 5/12/2008 Program Owner: E. Lynn McClain 5/12/2008 Technical Review: Charlie Driskell 5/12/2008 CNL-16-135 E2-79of101 NC PROJECT PROCEDURE WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN Basis for Retrieval of Historical Records and Radiographs Watts Bar Nuclear (WBN) Unit 2 ASME Section XI Preservice Inspection (PSI) TP-2 WBN-2 PSI REVISION 11 Technical Positions Page 79 or IOO During the course of establishing the baseline inspection or during the inservice inspection certain records are required to be retrieved from time to time. The intent of the retrieval is for confirmation of or aid in the inspection activities to qualify, verify or validate the components configuration, i.e. weld map records, retrieval of radio graphs, etc. for various reasons. The following outline may be used to retrieve weld map data and radiographs.
- 1. Select a weld from the desired PSI/ISi drawing. Example: Drawing ISI-2068-W-04, weld RCS-025 2. Locate weld on referenced as constructed drawing from BSL. Example: WBN-E-2282-IC-I 44. Enter as E2882IC 144 3. Identity the weld as a field weld or shop weld. If the weld is a field weld, order the radiograph from Records Management Lifetime Storage Vault. If the weld is a shop weld, identify the sketch number and then retrieve from BSL. Example: SK-£2882-1300.
Enter as E2882-l300
- 4. Identify the weld number and piece mark on the piping fabrication sketch. Example: Weld K, pc 68-RC-6 5. Identify the box number the radiograph is located in from the Supplier Radiograph Index Manual located in the Records Management Lifetime Storage Vault (Index is sorted like the example).
Example: E-2882, 68-RC-6 PC, SK 1300-K is located in Box number42 6. Request that Records Management order the required radiograph from the National Underground Storage Facility. Example: Box 42 is located in Room RC, Section 3, Shelf 2, Bin 6 Prepared By: Program 0\\-ner: Technical Review: CNL-16-135 E. Lynn McClain 10/13/2009 E. Lynn McClain 10/13/2009 M. Darlene Tinley 10/13/2009 \...__ E2-80 of 101 WBN-2 PSI REVISION 11 NC WATIS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 80 of 100 SECTION 11.0 DRAWING REFERENCE LIST Some of the drawings will be included as the preservice inspections are completed and drawings are updated. Drawing Number 2-47W801-1 2-47W801-2 2-47W803-l 0-47W803-2 2-47W803-3 2-47W809-l 2-47W809-2 0-47W809-3 0-47W809-5 0-47W809-7 0-47W809-9 2-47W810-1 2-47W811-l 2-47W812-1 2-47W813-1 2-47W814-2 0-47W819-1 0-47W830-1 0-47W832-1 0-47W832-2 0-47W845-1 0-47W845-2 2-47W845-3
2-47W845-4 0-47W845-5 0-47W850-2 2-47W851-l 0-47W855-1 0-47W856-l 0-47W859-1 2-47W859-3 t 0-47W859-4 2-47W862-2 2-47W865-5 CNL-16-135 FLOW DIAGRAMS Drawing Title (System) Main & Reheat Steam ( 1) SG Blowdown (1) Feed water (3) Auxiliary Feedwater (3) Auxiliary Feedwater (3) Chemical & Volume Control (62) CVC & Boron Recovery (62) CVC & Boron Recovery (62) CVC & Boron Recovery (62) Flood Mode Boration Makeup (84) Chemical & Volume Control (62) Residual Heat Removal (7 4) Safety Injection (63) Containment Spray (72) Reactor Coolant (68) Ice Condenser ( 61) Primary Water (81) Waste Disposal (77) Raw Service Water & HPFP (25/26) Raw Service Water & HPFP (25/26) Essential Raw Cooling Water (67) Essential Raw Cooling Water (67) Essential Raw Cooling Water (67) Essential Raw Cooling Water (67) Essential Raw Cooling Water (67) Fire Protection Raw Service Water (26) Floor & Equipment Drains (77) Fuel Pool Cooling & Cleaning (78 )( 62) Demin Water & Cask Decon (59) Component Cooling (70) Component Cooling (70) Component Cooling (70) SG Wet Layup, Closed Recirculation Loop (41) Air Conditioning Chilled Water (31) E2-81 of 101 Code Class 2 2 2&3 3 1,2&3 2&3 3 3 2&3 2 1,2&3 1,2&3 2&3 1&2 2 2 2 '"' .:> 3 3 3 2&3 3 3 3 2&3 2&3 2 ,., .:> 2&3 3 2 2 WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 81 of 100 COMPONENT LOCATIONS Drawing Number Drawing Title (System) Code Class ISI-2000-GEN-1 thru DRAWING REFERENCE TABLE NIA -16 ISI-2001-E-01 STEAM GENERA TOR 1&2 ISI-2001-E-02 STEAM GENERATOR 1 ISI-2001-E-03 STEA.NI GENERATOR SUPPORTS 1&2 ISI-2001-E-04 MAIN STEAM SAFETY VALVES 2 ISI-2001-H-01 MSS SUPPORT LOCATIONS 2 ISI-2001-H-02 MSS SUPPORT LOCATIONS 2 ISI-2001-H-03 MSS SUPPORT LOCATIONS 2 ISI-2001-H-04 MSS SUPPORT LOCATIONS 2 ISI-2001-W-O 1 MSS WELD LOCATIONS 2 ISI-2001-W-02 MSS WELD LOCATIONS 2 ISI-2001-W-03 MSS WELD LOCATIONS 2 ISI-200 l-W-04 MSS WELD LOCATIONS 2 ISI-2003A-H-Ol FEEDW ATER SUPPORT LOCATIONS 2 ISI-2003A-H-02 FEEDW ATER SUPPORT LOCATIONS 2 ISI-2003A-H-03 FEEDW ATER SUPPORT LOCATIONS 2 ISI-2003A-H-04 FEEDW ATER SUPPORT LOCATIONS 2 ISI-2003A-W-01 FEEDW ATER WELD LOCATIONS 2 ISI-2003A-W-02 FEEDWATER WELD LOCATIONS 2 ISI-2003A-W-03 FEEDW ATER WELD LOCATIONS 2 ISl-2003A-W-04 FEEDWATER WELD LOCATIONS 2 ISI-2003B-E-01 AUXFDWR VALVE WELD LOCATION 2 ISI-2003B-E-02 MDAFW PUMP SUPPORT LOCATIONS 3 ISI-2003B-E-03 TDAFW PUMP SUPPORT LOCATIONS ,., .) ISI-2003B-H-01 AUX FDWR SUPPORT LOCATIONS 2 TSI-2003B-H-02 AUX FDWR SUPPORT LOCATIONS 2 ISI-2003B-H-03 AUX FDWR SUPPORT LOCATIONS 2 ISI-2003B-H-04 AUX FDWR SUPPORT LOCATIONS 2 ISI-2003B-H-05 AUX FDWR SUPPORT LOCATIONS 2 ISI-2003B-H-06 AUX FDWR SUPPORT LOCATIONS 2 ISI-2003B-H-07 AUX FDWR SUPPORT LOCATIONS 2 ISI-2003B-H-08 AUX FDWR SUPPORT LOCATIONS 2 ISI-2003B-H-09 AUX FDWR SUPPORT LOCATIONS 2 .TSI-20038-H-10 AUX FDWR SUPPORT LOCATIONS 2 ISI-20038-H-l l AUX FDWR SUPPORT LOCATIONS 2 CNL-16-135 E2-82of101 ............................
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...... ****-*****-- WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVJCE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 82 of 100 ISI-2003B-H-12 AUX FDWR SUPPORT LOCATIONS 3 ISI-2003B-H-13 AUX FDWR SUPPORT LOCATIONS "' -' ISI-2003B-H-14 AUX FDWR SUPPORT LOCATIONS 3 ISI-2003B-W-Ol AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-02 AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-03 AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-04 AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-05 AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-06 AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-07 AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-08 AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-09 AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-10 AUX FDWR WELD LOCATIONS 2 ISI-2003B-W-11 AUX FDWR WELD LOCATIONS 2 ISI-2062-H-01 eves SUPPORT LOCATIONS 1 ISI-2062-H-02 eves SUPPORT LOCATIONS 1 ISI-2062-H-03 eves SUPPORT LOCATIONS 1 ISI-2062-H-04 eves SUPPORT LOCATIONS I ISI-2062-H-05 eves SUPPORT LOCATIONS 1 ISI-2062-H-06 eves SUPPORT LOCATIONS 1 IS I-2062-H-07 eves SUPPORT LOCATIONS 2 ISI-2062-H-08 eves SUPPORT LOCATIONS 2 ISI-2062-H-09 eves SUPPORT LOCATIONS 2 ISI-2062-H-10 eves SUPPORT LOCATIONS 2 ISI-2062-H-11 eves SUPPORT LOCATIONS 2 ISI-2062-H-12 eves SUPPORT LOCATIONS 2 ISI-2062-H-13 eves SUPPORT LOCATIONS 2 ISI-2062-H-14 eves SUPPORT LOCATIONS 2 ISI-2062-H-15 eves SUPPORT LOCATIONS 2 ISI-2062-H-16 eves SUPPORT LOCATIONS 2 ISI-2062-H-l 7 eves SUPPORT LOCATIONS 2 ISl-2062-H-l 8 eves SUPPORT LOCATIONS 2 ISI-2062-H-19 eves SUPPORT LOCATIONS 2 ISI-2062-H-20 eves SUPPORT LOeA TIONS ') ISI-2062-H-21 eves SUPPORT LOCATIONS 2 ISI-2062-H-22 eves SUPPORT LOCATIONS 2 ISI-2062-H-23 eves SUPPORT LOCATIONS 2 ISI-2062-H-24 eves SUPPORT LOCATIONS 2 ISI-2062-H-25 eves SUPPORT LOCATIONS 2 ISI-2062-H-26 eves SUPPORT LOCATIONS 2 ISI-2062-H-27 eves SUPPORT LOCATIONS 2 ISI-2062-H-28 eves SUPPORT LOCATIONS 2 ISI-2062-H-29 eves SUPPORT LOCATIONS 2 CNL-16-135 E2-83of101
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.... ............. .. ......................... __ ................. WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 83 of 100 ISI-2062-H-30 eves SUPPORT LOCATIONS 2 ISI-2062-H-31 eves SUPPORT LOCATIONS 2 ISI-2062-H-32 eves SUPPORT LOeA TIONS "") ISI-2062-H-33 eves SUPPORT LOCATIONS 2 ISI-2062-H-34 eves SUPPORT LOCATIONS 2 ISl-2062-H-35 eves SUPPORT LOCATIONS 2 ISI-2062-W-Ol eves WELD LOCATIONS 1 ISI-2062-W-02 . eves WELD LOCATIONS 1 ISI-2062-W-03 eves WELD LOCATIONS 1 ISI-2062-W-04 eves WELD LOCATIONS 1 ISI-2062-W-05 eves WELD LOCATIONS 1 ISI-2062-W-06 eves WELD LOCATIONS 1 ISI-2062-W-07 eves WELD LOCATIONS 2 TSI-2062-W-08 eves WELD LOCATIONS 2 ISI-2062-W-09 eves WELD LOCATIONS 2 ISI-2062-W-10 eves WELD LOCATIONS 2 ISI-2062-W-11 eves WELD LOCATIONS 2 ISI-2062-W-12 eves WELD LOCATIONS ,.., "-ISI-2062-W-13 eves WELD LOCATIONS 2 ISI-2062-W-14 eves WELD LOCATIONS 2 ISI-2062-W-15 eves WELD LOCATIONS 2 ISI-2062-W-16 eves WELD LOCATIONS 2 ISI-2062-W-17 eves (SEAL INJ) WELD LOCATIONS 2 ISI-2062-W-18 eves WELD LOCATIONS 2 IST-2062-W-19 eves WELD LOCATIONS 2 ISI-2062-W-20 eves WELD LOCATIONS 2 ISI-2062-W-21 eves WELD LOCATIONS 2 ISI-2062-W-22 eves WELD LOCATIONS 2 ISI-2062-W-23 eves WELD LOCATIONS 2 ISI-2062-W-24 eves WELD LOCATIONS 2 ISI-2062-W-25 eves (SEAL INJ) WELD LOCATIONS 2 ISI-2062-W-26 eves WELD LOCATIONS 2 ISI-2062-W-27 eves WELD LOCATIONS 2 ISI-2062-W-28 eves WELD LOCATIONS 2 ISI-2062-W-29 eves WELD LOCATIONS 2 ISI-2062-W-30 eves WELD LOCATIONS 2 ISI-2062-W-31 eves WELD LOCATIONS 2 ISI-2062-W-32 eves WELD LOCATIONS 2 ISI-2062-W-33 eves WELD LOCATIONS 2 ISI-2062-W-34 eves WELD LOCATIONS 2 ISI-2062-W-35 eves WELD LOCATIONS 2 CNL-16-135 E2-84of101 ..... *-**.. . ..... ...... -... -_,.,, .. . .......................... " .... -........ WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 84 oflOO ISI-2062A-E-01 CENT CHG PUMP WELD & SUPPORT 2 LOCATIONS IS I-2062B-E-02 SL WTR HT EXCH SPT LOCATION ') ISI-2062C-E-O 1 SL WTR INJ FLTR WELD LOCATIONS 2 ISI-2062C-E-02 SL WTR INJ FLTR SUPT LOCATIONS 2 ISI-2062D-K-Ol SL WTR FILTER SUPT LOCATIONS 2 ISI-2063-H-Ol SIS SUPPORT LOCATIONS 2 ISI-2063-H-02 SIS SUPPORT LOCATIONS 2 lSI-2063-H-03 SIS SUPPORT LOCATIONS 2 ISI-2063-H-04 SIS SUPPORT LOCATIONS 2 ISI-2063-H-05 SIS SUPPORT LOCATIONS 2 ISI-2063-H-06 SIS SUPPORT LOCATIONS 1 ISI-2063-H-07 SIS SUPPORT LOCATIONS 1 ISI-2063-H-08 SIS SUPPORT LOCATIONS 1 ISI-2063-H-09 SIS SUPPORT LOCATIONS I ISI-2063-H-10 SIS SUPPORT LOCATIONS 1 ISI-2063-H-11 SIS SUPPORT LOCATIONS 1 ISI-2063-H-12 SIS SUPPORT LOCATIONS 1 ISI-2063-H-13 SIS SUPPORT LOCATIONS 1 ISI-2063-H-14 SIS SUPPORT LOCATIONS 1 ISI-2063-H-15 SIS SUPPORT LOCATIONS 2 ISI-2063-H-16 SIS SUPPORT LOCATIONS 2 ISI-2063-H-l 7 SIS SUPPORT LOCATIONS 2 ISI-2063-H-18 SIS SUPPORT LOCATIONS 2 ISI-2063-H-19 SIS SUPPORT LOCATIONS 2 ISI-2063-H-20 SIS SUPPORT LOCATIONS 2 ISI-2063-H-21 SIS SUPPORT LOCATIONS 2 ISI-2063-H-22 SIS SUPPORT LOCATIONS 2 ISI-2063-H-23 SIS SUPPORT LOCATIONS 2 ISI-2063-H-24 SIS SUPPORT LOCATIONS 2 ISI-2063-H-25 SIS SUPPORT LOCATIONS 2 ISI-2063-H-26 SIS SUPPORT LOCATIONS 2 ISI-2063-H-27 SIS SUPPORT LOCATIONS 2 ISI-2063-H-28 SIS SUPPORT LOCATIONS 2 ISI-2063-H-29 SIS SUPPORT LOCATIONS 2 ISI-2063-H-30 SIS SUPPORT LOCATIONS 2 ISI-2063-H-31 SIS SUPPORT LOCATIONS 2 ISI-2063-H-32 SIS SUPPORT LOCATIONS 2 ISI-2063-H-33 SIS SUPPORT LOCATIONS 2 ISI-2063-H-34 SIS SUPPORT LOCATIONS 2 ISI-2063-H-35 SIS SUPPORT LOCATIONS 2 ISI-2063-H-36 SIS SUPPORT LOCATIONS 2 ISI-2063-H-37 SIS SUPPORT LOCATIONS 2 CNL-16-135 E2-85of101
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WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 85 of 100 ISI-2063-H-38 SIS SUPPORT LOCATIONS 2 ISI-2063-H-39 SIS SUPPORT LOCATIONS 2 ISI-2063-W-Ol SIS WELD LOCATIONS 2 ISI-2063-W-02 SIS WELD LOCATIONS 2 ISI-2063-W-03 SIS WELD LOCATIONS 2 ISI-2063-W-04 SIS WELD LOCATIONS 2 ISI-2063-W-05 SIS WELD LOCATIONS 2 ISI-2063-W-06 SIS WELD LOCATIONS 1 ISI-2063-W-07 SIS WELD LOCATIONS 1 ISI-2063-W-08 SIS WELD LOCATIONS 1 ISI-2063-W-09 SIS WELD LOCATIONS 1 ISI-2063-W-10 SIS WELD LOCATIONS 1 ISI-2063-W-11 SIS WELD LOCATIONS 1 ISI-2063-W-12 SIS WELD LOCATIONS 1 ISI-2063-W-13 SIS WELD LOCATIONS 1 ISI-2063-W-14 SIS WELD LOCATIONS 1 lSl-2063-W-15 SIS WELD LOCATIONS 2 ISI-2063-W-16 SIS WELD LOCATIONS 2 ISI-2063-W-l 7 SIS WELD LOCATIONS 2 ISI-2063-W-18 SIS WELD LOCATIONS 2 ISI-2063-W-19 SIS WELD LOCATIONS 2 ISI-2063-W-20 SIS WELD LOCATIONS 2 ISI-2063-W-21 SIS WELD LOCATIONS 2 ISI-2063-W-22 SIS WELD LOCATIONS 2 ISI-2063-W-23 SIS WELD LOCATIONS 2 ISI-2063-W-24 SIS WELD LOCATIONS 2 ISI-2063-W-25 SIS WELD LOCATIONS 2 ISI-2063-W-26 SIS WELD LOCATIONS 2 ISI-2063-W-27 SIS WELD LOCATIONS 2 ISI-2063-W-28 SIS WELD LOCATIONS 2 ISI-2063-W-29 SIS WELD LOCATIONS 2 ISI-2063-W-30 SIS WELD LOCATIONS 2 ISI-2063-W-31 SIS WELD LOCATIONS ') ISI-2063-W-32 SIS WELD LOCATIONS 2 ISI-2063-W-33 SIS WELD LOCATIONS 2 ISI-2063-W-34 SIS WELD LOCATIONS 2 ISI-2063-W-35 SIS WELD LOCATIONS 2 ISI-2063-W-36 SIS WELD LOCATIONS 2 ISI-2063-W-37 SIS WELD LOCATIONS 2 ISI-2063-W-38 SIS WELD LOCATIONS 2 ISI-2063-W-39 SIS WELD LOCATIONS 2 CNL-16-135 E2-86of101 WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 86 of 100 ISI-2063A-E-01 SIS BIT TANK WELD & 2 SUPPORT LOCATIONS ISI-2063B-E-O 1 SIS PUMP WELD & SUPPORT LOCATIONS ISI-2067-H-01 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-02 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-03 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-04 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-05 ERCW SUPPORT LOCATIONS ,., .) ISI-2067-H-06 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-07 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-08 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-09 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-10 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-l l ERCW SUPPORT LOCATIONS ,.., .) ISI-2067-H-12 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-13 ERCW SUPPORT LOCATIONS ,.., .) ISI-2067-H-14 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-15 ERCW SUPPORT LOCATIONS 3 ISI-2068-H-01 RCS PIPING SUPPORT LOCATIONS 1 ISI-2068-H-02 RCS PIPING SUPPORT LOCATIONS 1 ISI-2068-H-03 RCS PIPING SUPPORT LOCATIONS 1 ISI-2068-H-04 RCS PIPING SUPPORT LOCATIONS 1 ISI-2068-H-05 RCS PIPING SUPPORT LOCATIONS 1 ISI-2068-MRP-01 RCS MRP 146 BRANCH LOCATIONS 1 ISI-2068-MRP-02 RCS MRP 146 BRANCH LOCATIONS l ISI-2068-W-01 RCS WELD LOCATIONS 1 ISI-2068-W-02 RCS WELD LOCATIONS 1 ISI-2068-W-03 RCS WELD LOCATIONS 1 ISI-2068-W -04 RCS WELD LOCATIONS 1 ISI-2068-W-05 RCS WELD LOCATIONS 1 ISI-2068-W-06 RCS WELD LOCATIONS 1 IST-2068-W-07 RCS WELD LOCATIONS 1 ISI-2068A-E-01 RV GENERAL ARRGMNT l ISI-2068A-E-02 RV INTERIOR VIEW 1 ISI-2068A-E-03 RV SEAM WELDS 1 ISI-2068A-E-04 RV CLOSURE HEAD 1 ISI-2068A-E-05 CRD & VENT PIPE PENTR l ISI-2068A-E-06 AUX HEAD ADAPTER 1 ISI-2068A-E-07 CLOSURE HEAD PENTR l ISI-2068A-E-08 CLOSURE HEAD PEN & CRD J-WELD 1 ISI-2068A-E-09 RV STUD LOCATION & DETAIL l CNL-16-135 E2-87 of 101 :J .... ******-.. ****** .. . .... ... . WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 87 of 100 ISI-2068A-E-10 CLOSURE STUDS, NUTS, & WASHER 1 DETAILS ISI-2068A-E-l l RV SUPPORT 1 ISI-2068A-E-12 RV BOTTOM HEAD PENTR 1 ISI-2068A-E-13 RV BOTTOM HEAD INTERNAL VIEW 1 ISI-2068A-E-14 RV BOTTOM HEAD EXTERNAL VIEW 1 ISI-2068A-E-15 RV WELD SEAMS 1 ISI-2068A-E-16 RV MAIN LOOP NOZZLES -HOT LEG 1 ISI-2068A-E-17 RV MAIN LOOP NOZZLES -COLD LEG 1 ISI-2068A-E-18 REACTOR VESSEL CORE BARREL 1 (OR LOWER INTERNALS) SI-2068A-E-19 RV HEAD CRDM RESTRAINT 1 ISI-2068B-E-O 1 RCP MAIN FLG & LOWER SEAL BL TG 1 ISI-2068B-E-02 RCP MOTOR AUG FLYWHEEL EXAM NIA ISI-2068B-E-03 RCP CASING WELD LOCATION 1 ISI-2068B-E-04 NIA ISI-2068B-E-05 RCS PUMP SUPPORTS 1 ISI-2068C-E-01 PRESSURIZER l ISI-2068C-E-02 PRESSURIZER (MANW A Y BLT) 1 ISI-2068C-E-03 PRESSURIZER SURGE NOZZLE 1 DETAILS ISI-2068C-E-04 PRESSURIZER SPRAY, SAFETY, & 1 RELIEF NOZZLE DETAILS ISI-2068C-E-05 PRESSURIZER HEATER DETAILS I ISI-2068C-E-06 PRESSURIZER (SUPPORT SKIRT & 1 SEISMIC LUG DETAIL) ISI-2070-H-Ol CCS SUPPORT LOCATIONS 3 ISI-2070-H-02 CCS SUPPORT LOCATIONS 3 ISI-2070-H-03 CCS SUPPORT LOCATIONS .., _, ISI-2070-H-04 CCS SUPPORT LOCATIONS .., j ISI-2070-H-05 CCS SUPPORT LOCATIONS 3 ISI-2070-H-06 CCS SUPPORT LOCATIONS .., _, ISI-2070-H-07 CCS SUPPORT LOCATIONS 2&3 ISI-2072-H-01 CONT SPRAY SUPPORT LOCATIONS 2 ISI-2072-H-02 CONT SPRAY SUPPORT LOCATIONS 2 ISI-2072-H-03 CONT SPRAY SUPPORT LOCATIONS 2 ISI-2072-H-04 CONT SPRAY SUPPORT LOCATIONS 2 ISI-2072-H-05 CONT SPRAY SUPPORT LOCATIONS 2 ISI-2072-H-06 CONT SPRAY SUPPORT LOCA TlONS 2 ISI-2072-H-07 CONT SPRAY SUPPORT LOCATIONS 2 ISI-2072-H-08 CONT SPRAY SUPPORT LOCATIONS 2 CNL-16-135 E2-88of101 ........ , ......... 'O>HHH 0 *********-**-******--*** ". **' WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVJCE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 88 of 100 ISI-2072-H-09 CONT SPRAY SUPPORT LOCATIONS 2 ISI-2072-H-10 CONT SPRAY SUPPORT LOCATIONS 2 I ISI-2072-W-Ol CONT SPRAY PIPING WELDS 2 ISI-2072-W-02 CONT SPRAY PIPING WELDS 2 ISI-2072-W-03 CONT SPRAY PIPING WELDS 2 ISI-2072-W-04 CONT SPRAY PIPING WELDS 2 ISI-2072-W-05 CONT SPRAY PIPING WELDS 2 ISI-2072-W-06 CONT SPRAY PIPING WELDS 2 ISI-2072-W-07 CONT SPRAY PIPING WELDS 2 ISI-2072-W-08 CONT SPRAY PIPING WELDS 2 ISI-2072-W-09 CONT SPRAY PIPING WELDS ') ISI-2072-W-10 CONT SPRAY PIPING WELDS 2 ISI-2072A-E-01 CONT SPRAY PUMP SUPPORTS 2 ISI-2072B-E-01 CONT SPRAY HX WELD LOCATIONS 2 ISI-2072B-E-02 CONT SPRAY HX SUPPORT DETAILS 2&3 ISI-2074-H-Ol RHRS SUPPORT LOCATIONS 1&2 ISI-2074-H-02 RHRS SUPPORT LOCATIONS 2 ISI-2074-H-03 RHRS SUPPORT LOCATIONS 2 ISI-2074-H-04 RHRS SUPPORT LOCATIONS 2 ISI-2074-H-05 RHRS SUPPORT LOCATIONS 2 ISI-2074-H-06 RHRS SUPPORT LOCATIONS 2 IST-2074-H-07 RI-IRS SUPPORT LOCATIONS 2 ISI-2074-H-08 RHRS SUPPORT LOCATIONS 1&2 ISI-2074-H-09 RHRS SUPPORT LOCATIONS 1&2 ISI-2074-W-01 RHRS WELD LOCATIONS 1&2 ISI-2074-W-02 RHRS WELD LOCATIONS 2 ISI-2074-W-03 RHRS WELD LOCATIONS 2 ISI-2074-W-04 RHRS WELD LOCATIONS 2 ISI-2074-W-05 RI-IRS WELD LOCATIONS 2 ISI-2074-W-06 RHRS WELD LOCATIONS 2 ISI-2074-W-07 RHRS WELD LOCATIONS 2 ISI-2074-W-08 RHRS WELD LOCATIONS 1&2 ISI-207 4-W-09 RHRS WELD LOCATIONS 1&2 ISI-2074A-E-Ol RHR PUMP SUPPORT LOCATIONS 2 ISI-2074B-E-01 RHR HT EXCH CHANNEL WELDS 2 ISI-2074B-E-02 RHR HT EXCH SUPPORTS 2&3 CNL-16-135 E2-89of101 NC PROJECT PROCEDURE ACWS: ALARA: ANH: ASME: AUG: AFW: A-E: WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN SECTION 12.0 PROGRAM -TERMS Air Conditioning Chilled Water System (31) As Low As Reasonably Achievable -Authorized Nuclear Inservice Inspector American Society of Mechanical Engineers Augmented Auxiliary Feedwater System (003B) Category -Augmented BC: Branch Coru1ection CC: Code Case CFR: Code of Federal Regulations CH: Charging CHR: Containment Heat Removal Circ: Circumferential CL: Cold Leg CCS: CRD: CSS: CS: CSP: eves: DWG: DM: E: ECCS: ERCW: EL: EPRI: ET: EVT-1: FW: FWS: FMBMS: H: HL: CNL-16-135 Component Cooling System (70) Control Rod Drive Contaimnent Spray System (72) Carbon Steel Containment Spray Pump Chemical and Volume Control System (62) Drawing Dissimilar Metal Equipment Emergency Core Cooling System Essential Raw Water Cooling System (67) Elbow Electric Power research Institute Eddy Current Examination Enhanced Visual VT-1 (RPV) Feed water Feedwater System (03A) Flood Mode Boration Makeup System (84) Hanger I Support Hot Leg E2-90 of 101 WBN-2 PSI REVISION 11 I Terms Page 89 of 100 NC PROJECT PROCEDURE HPFP: HX: ICS: IEP: INPO: ISi: IWA: IWB: IWC: IWD: IWE: IWF: IWL: MOU: MSIP: MSS: MT: NC: NDE: NRC: NGDC: PP: P: PENT: PSI: PSV: PWR: PT: PZR: PCV: PWS: R: RC: RCP: RHR: RHRS: CNL-16-135 WBN-2 PSI REVISION 11 WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN High Pressure Fire Protection (26) Heat Exchanger Ice Condenser System (61) Inspection and Examination Procedures Institute for Nuclear Power Operations Inservice Inspection Section XI General Requirements Section XI Class 1 Components Section XI Class 2 Components Section XI Class 3 Components Section XI Class MC Components Section XI Class 1, 2, 3 & MC Component Supports Section XI Class CC Components Memorandum of Understanding Mechanical Stress Improvement Process Main Steam System (01) Magnetic Particle Examination Nuclear Construction Nondestructive Examination Nuclear Regulatory Commission Nuclear Generation Development & Construction Project Procedure Pipe Penetration Preservice Inspection Pressure Relief or Safety Valve Pressurized Water Reactor Penetrant Examination Pressurizer Pressure Control Valve Primary Water System (81) Reducer Reactor Coolant Reactor Coolant Pump Residual Heat Removal Residual Heat Removal System (74) E2-91 of 101 Terms Page 90 of 100 NC PROJECT PROCEDURE RECIRC: RCS: RPV: RSW: RLV: RT: RX: S: SCH: SDCHX: SD: SER: SG: SGBD: SH: SIS: SI: SUR: SFPC: SS: SXI: Tee: TK: Tech. Spec: TRM: TVA UFSAR: UHIS: UT: VCT: VOL: VT: VT-1: VT-2: VT-3: V-E: CNL-16-135 WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN Recirculation Reactor Coolant System (68) Reactor Pressure Vessel Raw Service Water (System 25) Relief Valve Radiograph Examination Reactor Supports Schedule Shutdown Cooling Heat Exchanger Shutdown Safety Evaluation Report Steam Generator Steam Generator Blowdown (System 1 & 15) Sheet Safety Injection System (63) Safety Injection Surface Examination Spent Fuel Pit Cooling (System 84) Stainless Steel Section XI, Rules for Inservice Inspection Tee Thickness Technical Specification Technical Requirements Manual TelUlessee Valley Authority Updated Final Safety Analysis Report Upper Head Injection System (87) Ultrasonic Exan1ination Volume Control Tank Volumetric Examination Visual Examination WBN-2 PSI REVISION 11 Terms Page 91 of 100 Visual Examination for Detection of Surface Conditions Visual Examination for Evidence of Leakage Visual Examination for General Mechanical and Strnctural Condition Visual Exanlination (VT-2 Augmented Type) E2-92of101 NC PROJECT PROCEDURE WDS: WBN: W: CNL-16-135 WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN Waste Disposal System (77) Watts Bar Nuclear Welds E2-93 of 101 WBN*2 PSI REVISION 11 Terms Page 92 oflOO WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Terms PROCEDURE Page 93 of 100 Attachment 1 Transition from EPRI Material Reliability Program MRP-139 Rev 1 And NRC Bulletin 2004-01 To ASME Code Case N-770-1 During Nuclear Constmction Phase of Watts Bar Unit 2 To properly categorize and inspect the Unit 2 RCS dissimilar-metal (OM) butt welds, the WBN-2 PSI staff utilized the EPRI Material Reliability Program MRP-139 (applicable only to Unit 1 Reactor inlet and outlet nozzles and Pressurizer nozzles), along with NRC Bulletin 2004-01 (applicable to both Unit 1and2 Pressurizers), to identify welds containing Alloy 600/821182 materials (non-ferrous, high-nickel, high-chromium welds) that could potentially be susceptible to Primary Water Stress Corrosion Cracking (PWSCC) during the future commercial operation of Unit 2. The DM welds identified are the 8 Reactor Pressure Vessel (RPV) Nozzle-to-Safe-End welds (per MRP-139 Rev 1 ), the 6 Pressurizer Nozzle-to-Safe-End welds (per NRC Bulletin 2004-01 ), and the 4 capped RPV Upper Head Injection DM nozzle-to-pipe welds (UPIAH 4A-D), and the 4 UPIAH RPV-to-nozzle welds (UPIAH 2/3A-D, which are not Safe-End welds per MRP-139 Rev 1). All 14 of the Safe-End welds (RPV inlet and outlet nozzles and the Pressurizer nozzles) were mitigated in 2010 using the Mechanical Stress Improvement Process (MSIP), in which the welds were mechanically squeezed or compressed using steel clamps and hydraulic equipment in order to change the residual stress profile in the welds to a compressive state so that the welds do not crack during plant operation. Unit 2 has not, as yet, been subjected to the hot, pressurized conditions associated with commercial operation. For the application of MSIP of the 8 RPV Nozzle-to-SE Welds, refer to Work Order 111350955. For the application of MSIP of the 6 Pressurizer Nozzle-to-SE Welds, refer to Work Order 09-954268-000. The 8 UPIAH welds were not subjected to MSIP. All of the 8 RPV Nozzle-to-SE welds were volumetrically (ultrasonically) inspected, using Appendix VIII procedures, after the application of the MSIP. These welds also received an Eddy Current examination on the inside surface. The 6 Pressurizer Nozzle-to-SE welds received a volumetric ultrasonic test (UT) examination per Appendix VIII and a dye penetrant test (PT) examination before and after application of MSIP. No cracking was identified in any of the 14 welds. The 4 capped RPV Upper Head OM nozzle-to-pipe welds (UPIAH 4A-D) received a manual volumetric ultrasonic test (UT) examination from the OD per Appendix VIII and a dye penetrant test (PT) examination from the OD, both manual exams by TV A personnel. The 4 UPIAH RPV Head-to-nozzle welds (UPIAH 2/3A-D) received an automated UT from the ID by AREVA and a manual dye penetrant (PT) examination from the OD by TV A personnel. AREVA referred to these weld as the AHA welds". This is typical for 4 locations. No cracking was identified in any of the 8 welds. In the future, during plant operation, the 14 Safe-End welds will be inspected per ASME Section XI and Code Case N-770-1 Table 1 as Category D welds (Uncracked and Mitigated with Stress CNL-16-135 E2-94of101 WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Terms PROCEDURE Page 94 of 100 Improvement). Also, in the future, during plant operation. the 4 capped RPV Upper Head Injection DM nozzle-to-pipe welds will be inspected per ASME Section Xl and Code Case N-770-1 Table 1 as Category B welds (Unmitigated Butt Weld at Cold Leg operating temperature >/= 525F and< 580F) but are not addressed in MRP-139 Rev 1. The examinations performed during the Preservice Inspection (PSI) meet the requirements prescribed in Code Case N-770-1, although Unit 2 PSI is not committed to the Code Case. The PSI serves as the baseline examinations for future Code Case N-770-1 inspections to be performed after Unit 2 enters commercial operation. The examinations performed as PSI comply with Code Case N-770-1 Figure 1, Notes 1, 4, 12, and 13. The other figures and notes do not apply to WBN Unit 2. Note that under MRP-139 Rev 1, Tables 6-1 and 6-2, the 14 Safe-End welds would be classified as Category C (Non-resistant Material, Mitigated with Stress Improvement, Inspected, and Uncracked). The 4 UPIAH 2/3A-D welds are not included in the scope addressed in this paragraph. The future ISI Program Plan for the 1st 10-Year Interval of commercial operation will incorporate the examination schedule for the 18 above-mentioned welds. For a comparison of the Inservice Inspection categories and schedule of future ISI examinations for commercial operation contained in MRP-139 Rev 1 and Code Case N-770-1, see Attachment 2 titled "Comparison of MRP-139 Rev 1 and Code Case N-770-1, RCS Welds Susceptible to PWSCC (Primary Water Stress Corrosion Cracking), Watts Bar Unit 2 Preservice Inspection (PSI)". The NPG Business Practice, BP-257, Integrated Materials Issues Management Plan, will be revised to address WBN-2 when Unit 2 goes into Commercial Operation. The NPG Common Technical Procedure, NETP-113, PWR Alloy 600 Progran1 and Other Augmented Inspection Requirements, may be revised, if needed, to address WBN-2 when Unit 2 goes into Commercial Operation. The RCS butt welds on the Steam Generator Nozzle-to-Safe-End welds do not contain Alloy 600/82/182 materials in contact with primary water and therefore are not susceptible to Primary Water Stress Corrosion Cracking (PWSCC). MRP-139 Rev 1 addresses these SG Nozzle-to-SE welds as Category A, Resistant Materials, and does not prescribe any additional ISI examinations beyond those contained in ASME Code Section XI. AS:tvffi Code Case N-770-1 only addresses welds that are susceptible to PWSCC and is therefore not applicable to these SG Nozzle-to-SE welds. The Control Rod Drive Mechanism welds, which do contain Alloy 600 material, are ASME Code Category B-0, "Pressure Retaining Welds in Control Rod Housings", and are not addressed by ASME Code Case N-770-1, which only addresses Category B-J and B-F welds. These CRD weld are produced during the shop fabrication of the RPV Head and receive a final machining on the inside diameter and outside diameter. These welds have not had a history of failures during operation. These B-0 welds are examined per ASME Code requirements. CNL-16-135 E2-95 of 101 WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Terms PROCEDURE Page 95 of 100 Attachment 2 Comparison ofMRP-139Rev1 and Code Case N-770-1 RCS (Code Category B-F & B-J) Welds Susceptible to PWSCC (Primary Water Stress Corrosion Cracking) A Resistant Materials B Non-resistant Material. Reinforced by full structural or optimized weld Overlay Inspected Uncracked c ! Non-Resistant Material Mitigated by SI inspected Uncracked NIA c Uncracked i Reinforced by full structural Overlay D Uncracked butt weld Mitigated with Stress
- improvement (SI) [Note l] CNL-16-135 Watts Bar Unit 2 Preservice Inspection (PSI) *"'"* C.M .* :*.t.. * ;,_;t-N-,770-t
., ... * ,;, . Ex1,1pt R!lquiremerits'" . . . . :. ,.:.* _:;,_., ,: : . Existing Code Examination Program or Approved Alternative i Steam Generator Nozzle-to-
- i SE Welds are NOT . Existing Code Examination Program or Approved Alternative 50% of each mitigation
...... :.
- type within next 6 years: if , no indication, continue with existing Code examination program or approved alternative.
NIA Volumetric: Population to be sampled at 25% per l 0-year Interval Examine (UT) all welds no sooner than the 3rd refueling outage and no later than I 0 years following SI application, 1st Interval. In 2nd Interval, 25% of uncracked welds shall be added to the lSl Program (-2410) and examined once each inspection Interval. . ... _ E2-96 of 101
- susceptible to PWSCC. ....
NIA to WBN-1. Applicable to WBN-2. 8RPV Nozzle-to-SE Welds (4 Cl& 4HL) and 6 Pressurizer Nozzle-to-SE Welds are susceptible to PWSCC and have been examined for PSI. [Notes 2 & 3]. Already required to UT & PT by Code Cat B-F at B-D frequency. NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERV/CE INSPECTION PROGRAM PLAN PROCEDURE MRP-,139 . ASME CC N.:. ;* .. '> f,77();;1
- MRP,.139 .'; . ..
- ):id:** , .*. ,Category/
.. * * ** '" Re9uirements . :* . -. ' ; .. WBN-2 PSI REVISION 11 Terms Page 96 of 100 RemarkS:' . ._.., :. rl!?: .. M. ;,: .... 0
- i. D Non-resistant Material.
No SL Pressurizer & Hot Leg. 2: 2** and MU/HPl. Inspected. Uncracked. E Non-resistant Material No SI Cold Leg 2: 4" or with ECCS function. Inspected. Un cracked. (NIA to UHI ********- F Non-resistant Material Inspected Cracked ! Reinforced by full structural or optimized weld overlay G A-1 Unmitigated butt weld at HL operating temp > 625°F A-2 Unmitigated butt weld at 100% per period, but no longer than 5 years between exams for PZR locations (including Surge line nozzle : welds) l 00% every 5 years for Hot Leg location (including Surge line nozzle welds , near Hot Leg and the dual HL operating use line MU/HP[ nozzle temp :S _ . __ ---* _ .. . B Unmitigated butt weld at Cold Leg operating temp 2: 525°F and <580°F F Cracked butt weld reinforced by full structural weld overlay of Alloy 52/152 material E Cracked butt weld mitigated with Stress 100% every 6 years Once in next 5 years; if no additional indications/ growth, continue with existing Code examination program for unflawed condition or approved alternative Visual: Each refueling outage Volumetric: Every second refueling outage Visual (VE): Once per Interval Volumetric (UT): Every second inspection period not to exceed 7 years Inspect once during the first or second refueling outage following overlay. lf no indications, population sample at 25%. Volumetric: Once during the first or second refueling outage following Non-resistant Material Inspected. Cracked. Mitigated by SI. ! Improvement 100% at 2 RFO intervals. If no additional indications/growth with the 2nd exam (4th RFO), continue with existing Code examination program for unflawed condition or approved alternative application of SI. Tf no indication of growth, population sample at 25% per Interval. (SI) CNL-16-135 E2-97of101 NIA to WBN-2. Applicable to WBN-2. 8 Upper Head Injection welds on capped penetrations (-5" NPS) are susceptible to PWSCC and have been examined for PSI. [Notes 5 & 71 NIA to WBN-2. Nl.4 to WBN-2.
NC PROJECT PROCEDURE .
MRP.:139 . _,,, *770.-'f'. . , ,. I ' " Description Item l. H ' Non-resistant Material Pressurizer & Hot Leg Exam does not meet requirements . of Fig 5-1 Item 6 Configuration not addressed in Appendix VIII Not inspected Unknown crack status I Non-resistant Material Cold Leg Exam does not meet requirements of Fig 5-1 Item 6 Con figuration not addressed in Appendix VIII Not inspected Unknown crack status .......... -.. ******* ... ._ .. J Non-resistant Material Pressurizer and Hot Leg The Unknown Crack Status is i not addressed byN-770-1, but Categm)' A-1 or A-2 could be applied. The Unknown Crack Status is not addressed by N-770-1, but Category A-1 or A-2 could be applied. NIA CNL-16-135 WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVJCE INSPECTION PROGRAM PLAN :. *,_ . *. :: .
- .
- ... Frequency defined in Table 6-1 ofMRP-139 for Category D to the extent possible.
Additional interim requirements as defined in Section 5.1.7 of MRP-139. Frequency defined in Table 6-1 of MRP-139 for Category E to the extent possible. Additional interim requirements as defined in Section 5 .1. 7 of MRP-139. .:ii:,::*** . ,,,,,[1 .. Requirements . The Unknown Crack Status is not addressed by N-770-1, but Category A-1 or A-2 could be applied. The Unknown Crack Status is not addressed by N-770-l, but Category A-1 or A-2 could be applied. NIA (Visual exams are addressed in Category D above) E2-98of101 WBN-2 PSI REVISION 11 Terms Page 97 oflOO <.' . Remarks;:* . .... . .. **:*= NIA to WBN-2 . NIA to WBN-2. NIA to WBN-2. WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Terms PROCEDURE :. .. * **. K Non-resistant Material Cold Leg NIA NIA NIA NIA CNL-16-135 NIA G Uncracked butt 1 weld mitigated with an Inlay H Uncracked butt weld mitigated with an Onlay J Cracked butt weld mitigated with an lnJay K Cracked butt weld mitigated with an Onlay : * ' MilP;tiI39 Exam Visual examination as defined in Section 5.2.1 of MRP-139 RI at least once every 3 RFOs or until mitigated or replaced. Analysis may be used as basis for visual exam every Interval, after meeting Category E. In RFOs that UT is performed, a visual exam is credited. NIA NIA NIA NIA
- Exam Reqµirel,nents . , NIA (Visual exams are addressed in Category E above) . .. **-----*****
....... _, __ .. . . . . Perform a volumetric exam and a surface exam of all welds no sooner than the third refueling outage and no later than the shorter of I 0 years following inlay or the design life of the .
- PerfOrni" a
- r* exam and a surface exam of all welds no sooner than the third refueling outage and no later than the shorter of I 0 years following inlay or the , design life of the
- inlay Once during the first *:* or second refueling outage following application of inlay. This exam shall include a volumetric exam and a surface exam. Page 98 oflOO . *:.. Remarks; NIA to WBN-2. NIA to WBN-2. NIA to WBN-2. NIA to WBN-2. -****** ..... -*-. . **-*--*-***--.... -*-*-***--*-**
..................... . Once during the first or second refueling outage following application of inlay. This exam shall include a volumetric i exam and a surface exam. i. NIA to WBN-2. E2-99of101 WBN-2 PSI REVISION 11 NC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Terms PROCEDURE Page 100 of 100 Note I: The Stress Improvement technique utilized at WBN Unit'.! is Mechanical Stress Improvement Process (MSIP). MSIP was performed on the 8 RPV Nozzle-to-SE welds and the 6 Pressurizer Nozzle-to-SE welds in the year 2010. Note 2: The PSI examinations performed on the 8 RPV Nozzle-to-SE welds, atler the application ofMSIP. consisted of Volumetric (UT) examination as specified in MRP-139 and ASME Code Case N-770-1, although WBN Unit 2 is not committed to Code Case N-770-1 for Preservice Inspection. A Voluntary Surface (Eddy Current) examination was also performed on the inside surface of all the welds. A Smface (Dye Penetrant) examination was performed on the outside surface of each of the 8 welds. All 8 RPV Nozzle-to-SE welds were demonstrated to be acceptable by the various NDE methods. The PSI examinations serve as baseline examinations for the application of ASME Code Case N-770-1 during the First 10-Year Interval ofISI. Note 3: The PSI examinations performed on the 6 Pressurizer Nozzle-to-SE welds, before and after the application of
- MSIP, included Volumetric (UT) and Surface (Dye Penetrant) performed on the outside surface as specified in NRC Bulletin 2004-01 and the ASME Code Section XI 2001 Edition with Addenda thru 2003. All 6 Pressurizer Nozzle-to-SE welds were demonstrated to be acceptable by the NOE methods. The PSI exams perfom1ed per ASME Code Section XI and NRC Bulletin 2004-01 serve as baseline examinations for the application of ASME Code Case N-770-1 during the First l 0-Year Interval ofIST. Note 4: The Steam Generator Nozzle-to-SE Welds do not contain Alloy 600/82/182 materials in contact with primary water and therefore are not susceptible to Primary Water Stress Corrosion Cracking (PWSCC). Note 5: The PSI examinations performed on the 4 Upper Head Injection Auxiliary Head Adaptor (UPIAH) lines include 8 welds. There are 4 Tnconel welds (UPI AH 4A-D) which join the Inconel nozzle to the 5 NPS stainless steel pipe. These 4 welds were examined by UT and PT, both from the OD, by TVA personnel.
The RPV Head-to-nozzle welds (UPIAH 2/3A-D, and referred to as *'the AHA welds") were examined by AREVA with UT from the ID. The OD was examined with PT by TV A personnel. The 4 AHA welds do not contain a true Safe-End but do contain "buttering, which is a layer of weld material made of Alloy 600, and an Inconel weld. These 8 welds did not receive MSIP. Note 6: The Extent and Frequency of Examination. along with Note 1 l(b)(2), in ASME Code Case N-770-1 have been modified by 10CFR50.55.a(g)(6)(ii)(F)(9). This table includes those additional NRC requirements. Note 7: The RPV Upper Head temperature is assumed to be the same as WBN Unit 1, which is 557 degrees f_ Note 8: The Control Rod Drive Mechanism welds, which do contain Alloy 600 material, are ASME Code Category B-0. "Pressure Retaining Welds in Control Rod Housings", and are not addressed by ASME Code Case N-770-1, which only addresses Category B-J and B-F welds. These CRD weld are produced during the shop fabrication of the RPV Head and receive a final machining on the inside diameter and outside diameter. These welds have not bad a history of failures during operation. These B-0 welds are examined per ASME Code requirements. CNL-16-135 E2-101 of 101}}