ML12311A296
| ML12311A296 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/01/2012 |
| From: | Hruby R Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC ME3113, TAC ME4074 | |
| Download: ML12311A296 (104) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 November 1, 2012 10 CFR § 50.34 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391
Subject:
WATTS BAR NUCLEAR PLANT - UNIT 2 - SUPPLEMENTAL SAFETY EVALUATION REPORT (SSER) OPEN ITEM 70 REGARDING THE PRESERVICE INSPECTION PROGRAM PLAN (TAC NOS. ME4074 and ME3113)
TVA hereby provides Revision 7 of the Watts Bar Nuclear Plant Unit 2 (WBN 2) Preservice Inspection Program Plan. The Preservice Inspection Program Plan has been updated to reflect additional numbers of welds based on the issuance of design change documents.
SSER Appendix HH Open Item 70 noted that Section 7 on support welds contained only "To Be Determined". The number of support welds for several but not all applicable plant systems has been added in Revision 7. It is TVA's position that the amount of information available in Section 7 is sufficient to permit the NRC Staff to complete their programmatic review of the WBN 2 Preservice Inspection Program Plan. Should additional validation be required to support the closure of SSER Appendix HH Open Item 70, completion of the Preservice Inspection Program can be addressed as a validation activity.
There are no new regulatory commitments contained in this letter. If you have any questions, please contact Gordon Arent at (423) 365-2004.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1 st day of November, 2012.
Respectfully, Raymond A. Hruby, Jr.
General Manager, Technical Services Watts Bar Unit 2
U.S. Nuclear Regulatory Commission Page 2 November 1, 2012
Enclosure:
Watts Bar Nuclear Plant Unit 2 - Preservice Inspection Program Plan, Revision 7 cc (Enclosure):
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
Enclosure WATTS BAR NUCLEAR PLANT UNIT 2 PRESERVICE INSPECTION PROGRAM PLAN Revision 7
Preservice Inspection Program Plan Watts Bar Nuclear Plant Unit 2 Tennessee Valley Authority 1101 Market Street Chattanooga, TN 37402-2801 Watts Bar Nuclear Plant P.O. Box 2000 Spring City, TN 37381 Docket Number 391 Construction Permit No. CPPR-92, Issued January 23, 1973 Extension Issued October 24, 2000 Program No: WBN-2 PSI Rev. 7 Effective Date: 10-28-2012 Responsible Organization: Inspection Services Organization Bums 4:5-.7 Prepared by: Eben Reviewed by: Char E. Driskell Approved by: _ _ _ __ _
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 2 of 101 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 11 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(g)(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 TVA responses to NRC.
71-73 Updated drawing 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
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 3 of 101 5 7-27-11 8 Add periodic notification to ANII of examination record signature status.
13 Add reference to IEP-500 for surface conditioning of DM welds.
20-21 Correct paragraph letters for "f" and "g".
22 Add Code Cases N-686-1, N-695, and N-696 23 Correct typographical errors 36 Update weld totals for Examination Category 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 Category 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 drawing list 6 2-15-12 5 Added information from RR on ASME XI 2001/2003 6 Corrected FSAR reference numbers 9 Removed 10CFR50.55a(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 RIRS. 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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 4 of 101 TABLE OF CONTENTS 1.0 Sum m ary ............................................................................................................................ 6 2.0 Code A pplicability ......................................................................................................... 7 3.0 D escription ......................................................................................................................... 8 3.1 Scope ............................................................................................................ 8 3.2 Jurisdiction ....................................................................................................... 8 3.3 Responsibility .................................................................................................. 9 3.4 Application ................................................................................. .................... 9 3.5 Classification and Boundaries ........................................................................ 10 3.6 A ccessibility .................................................................................................... 11 3.7 Referenced Standards and Specifications ........................................................ 12 3.8 Exam ination M ethods .................................................................................... 12 3.9 Nondestructive Exam ination Personnel .......................................................... 13 3.10 Inspection Intervals ......................................................................................... 14 3.11 Com ponent Reference System ........................................................................ 14 3.12 Program Plan and Schedule ............................................................................. 14 3.13 Evaluation of Recorded Conditions ................................................................. 15 3.14 Records and Reports ...................................................................................... 15 3.15 IW B Requirem ents and Exem ptions ............................................................... 15 3.16 IW C Requirem ents and Exem ptions ............................................................... 16 3.17 IW D Requirem ents and Exem ptions ............................................................... 18 3.18 IW F Requirem ents and Exem ptions ............................................................... 19 3.19 Code Cases .................................................................................................... 22 3.20 Code Relief ..................................................................................................... 23 3.21 Augm ented Com ponents ............................................................................... 23 3.22 Calibration Standard ....................................................................................... 24 4.0 IW B Summ ary Tables ................................................................................................ 28 5.0 IW C Summ ary Tables ................................................................................................ 41 6.0 IWD Sum m ary Tables ............................................................................................... 51 7.0 IW F Sum m ary Tables .................................................................................................. 53 8.0 A ugm ented Sum m ary Tables ....................................................................................... 59 9.0 Requests for Relief .................................................................................................... 62 10.0 A SME Section X I- Technical Positions .................................................................... 87 11.0 D raw ing - Reference List ........................................................................................... 94 12.0 Program - Term s ............................................................................................................ 100
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 5 of 101 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 (TI) 50B, ASME Section XI Preservice Inspection Program. The latest working revision of TI-50B, Revision 11 dated September 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 will be reference to establish the present document 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 - REGULATORY FRAMEWORK FOR THE COMPLETION OF CONSTRUCTION AND LICENSING ACTIVITIES FOR UNIT 2", it states in Enclosure 1, "TVA Responses to NRC's Request of Information Needed for Licensing Review Reconstitution", item 4.b.iv, is a commitment to provide a revised Preservice Inspection Program.
The Final Safety Analysis Report (FSAR) for WBN-2 is a "red-lined" version to depict/demonstrate how the FSAR will appear at fuel load, as reference in TVA to NRC letter dated February 8, 2008. 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 10CFR50.55a(g),
except where specific written relief has been requested. FSAR Section 5.2.8 is for TVA Class A (ASME Code Class 1) 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 Preservice Inspection (PSI) Program Plan at WBN-2, as stated in the previous paragraph. This program plan follows the inspection requirements of 10CFR50.55a(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 Regulatory Guide 1.147 that are incorporated by reference in IOCFR50.55a(b), in effect six month before the date of issuance of the construction permit.
TVA 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 construction 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 Construction Permit. The applicable Code would have been the 1971 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
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 6 of 101 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.
The examination categories and requirements for Class I components will be in accordance with subsection IWB of ASME Section XI. 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 of IWC and IWD of Section XI, as stated in FSAR Sections 5.2.8 and 6.6.
During the completion of construction and before startup of WBN-2, the quantity of the individual items listed in the summary tables as "total population" and "required examination" of IWB, IWC, IWD and IWF will be established as an ongoing process. For components listed in the summary tables where the "total population" and the "required examination" number is not known the number may be noted as "TBD" (To Be Determined) or to establish an amount the WBN Unit I total may be used and noted with an asterisk (*) until the actual population of Unit 2 is determined. The "total population" and "required examinations" shall be established and documented in the preservice summary report, which is required to be prepared and submitted prior to commercial service.
Other inspection requirements and/or commitments made by WBN Unit 2 in the regulatory framework letter 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 effort toward achieving the intent of the inspection activities.
2.0 CODE APPLICABILITY 2.1 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.
2.2 TVA as the owner has the responsibilities to develop a PSI Program Plan to establish a baseline of examinations to demonstrate conformance of the requirements to 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.
2.3 As stated above, the edition of ASME Section XI is established based on the referenced code edition and addenda of 10CFR 50.55a, that is in effect six month before the date of issuance of the construction permit. IOCFR50.55a Codes and Standards, dated February 27, 2008, specifically IOCFR50.55a (b)(2) which referencesSection XI through 2003
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 7 of 101 Addenda. Therefore, the 2001 Edition through the 2003 Addenda of Section XI, Division 1, 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.
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 Inspector(s) (ANII) 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 initialrprogram 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 XI. 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 ANII in order to prevent a large backlog of un-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 when the requirements of the Construction Code have been satisfied.
3.0 DESCRIPTION
3.1 SCOPE
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVlCE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 8 of 101 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.
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 included in NGDC PP-15.
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.
3.4.1 The following items are part of the Section XI Preservice Inspection requirements, but are not included in this document:
3.4.1.1 The Repair/Replacement (R/R) Program Plan, when implemented, will be utilized to perform the required activities for ASME Section XI components. The Repair/Replacement Program Plan is in accordance with Watts Bar Procedures and RfR work activities packages, with the following limitations and modifications as outlined in 10CFR50.55a.
- 1. 10CFR50.55a(b)(2)(xii), Underwater Welding, will be addressed in the Repair/Replacement Programs, if needed.
- 2. 10CFR50.55a(b)(2)(xvii), Reconciliation of Quality Requirements is addressed in the Repair/Replacement Program, if needed.
- 3. 10CFR50.55a(b)(2)(xxiii), Evaluation of Thermally Cut Surfaces in IWA-4461.4.2 will be addressed in the Repair/Replacement Program, if needed.
- 4. 10CFR50.55a(b)(2)(xxv), Mitigation of Defects by Modification will be addressed in the Repair/Replacement Program, if needed.
- 5. 10CFR50.55a(b)(2)(xxvi), Pressure Testing Class 1, 2,and 3 Mechanical Joints of IWA-4540(c) of the 1998 Edition must be applied and will be addressed in the Repair/Replacement Program as described, if needed.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 9 of 101 It should also be noted that a "Memorandum of Understanding" (MOU) has been established to address the interfacing systems between Unit 1 and 2. Portions of the Unit 2 systems were documented on Unit 1 ASME N-5 code data reports as being within the Unit 1 ASME boundary but are not within the operational boundary for Unit 1. Therefore this area has been address and for work activities prior to startup will have to be performed to ASME Section XI R/R. The letter and a more detailed description of the process and how it should work.can be found in this document as Technique Position-3 (TP-3).
3.4.1.2 The requirements of Examination Category B-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 IWA-5000, IWB-5000, IWC-5000 and IWD-5000 for all Class 1, 2, and 3 components, with the limitations and modifications as outlined in 10CFR50.55a for the inservice interval requirements.
3.4.1.3 The rWB 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.
3.4.1.4 The IWF-5000 requirements for preservice examination and testing of snubbers will be performed using Subsection ISTD 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.
3.4.1.5 The IWE requirements for Class MC and Metallic Liners of Class CC components are documented in the IWE Program Plan and Schedule. The requirements will be utilized to perform the required examination as addressed by Subsection IWE, with limitations and modifications outlined in 10CFRS0.55a(b)(2)(ix) and subparagraphs (A), (B), and (F) through (I).
3.4.1.6 The IWL 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 referred to as a concrete containment under pressure. However, the concrete structural slab (containment floor) is subject to the repair/replacement requirements of Article IWL of ASME Section XI.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 10 of 101 3.4.1.7 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.
3.5 CLASSIFICATION AND BOUNDARIES 3.5.1 A list of flow diagrams pertaining to the systems boundaries indicating the TVA Class A, B, C and D or ASME Class 1, 2 and 3 systems, structures and components required to be examined is included in Section 11.
3.5.2 A list of weld and support location drawings based on the flow diagram boundaries and utilized for component identification and location within those boundaries is also included in Section 11.
3.5.3 The rules of IWB shall be applied to those components that are classified ASME Class 1 or TVA Class A.
3.5.4 The rules of IWC shall be applied to those components that are classified ASME Class 2 or TVA Class B.
3.5.5 The rules of IWD shall be applied to those components that are classified ASME Class 3 or TVA Class C or D.
3.5.6 The requirements of IWF shall be applied to component supports classified ASME Class 1, 2 and 3 or TVA 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 permits 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.
3.6 ACCESSIBILITY Provisions for accessibility shall include the following considerations:
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 11 of 101 3.6.1 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 crud or corrosion product buildup, material selection to minimize activation in service and shielding from irradiation effects.
3.6.2 Access for the Inspector, examination personnel, and equipment necessary to conduct the examinations shall be provided.
3.6.3 Sufficient space for removal and storage of structural members, shielding and insulation shall be provided.
3.6.4 Installation and support of handling machinery where required to facilitate removal, disassembly and storage of equipment, components and other materials shall be provided.
3.6.5 Performance of examinations alternative to those specified in the event structural defects or indications are revealed that may require such alternative examinations, when necessary.
3.6.6 Necessary operations associated with repair/replacement activities shall be performed.
3.7 REFERENCED 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 IWA-1600-1.
3.8 EXAMINATION METHODS 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:
Visual (VT), an examination method used to evaluate an item by observation.
VT - 1 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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 12 of 101 Volumetric (Vol), an examination method used to detect the presence of discontinuities throughout the volume of material.
UT - Ultrasonic RT - Radiography 3.8.1 The examination method or methods to be used on a component are specified in the summary tables in Section 4.0, 5.0, 6.0 and 7.0 for ASME Class 1, 2 and 3 components and/or parts.
3.8.2 When preparation of a surface for nondestructive 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.
3.8.3 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 methods, combination of methods, or newly developed techniques as outlined in IWA-2240 will utilize the 1997 Addenda of Section XI as stated in 10CFR50.55a(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 of reduced 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 part geometry.
3.8.5 Nondestructive examination (NDE) procedures are controlled in accordance with IEP- 100, "Administration of Nondestructive Examination (NDE)
Procedures." A listing of NDE procedures is provided in ISOPM-S02-TOC, "ISO Program Manuals NDE Procedures Table of Contents." These procedures are controlled and available electronically in the Business Support 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 IOCFR50.55a regarding personnel qualification and certification as noted below.
3.9.1 10CFR50.55a(b)(2)(xiv), Appendix VHI personnel qualification.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 13 of 101 3.9.2 10CFR50.55a(b)(2)(xv), Appendix VIII specimen set and qualification requirements.
3.9.3 10CFR50.55a(b)(2)(xvi), Appendix VIII single side ferritic vessel and piping and stainless steel piping examination.
3.9.4 10CFR50.55a(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 REFERENCE SYSTEM 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 1, 2 and 3 systems, including piping, vessel and other components, where practical. The 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 interrelationship with TVA classification of components and ASME Section XI inspection activities as described in Technical Position TP-l, 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/ISI 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.
3.12.1 For each examination category, the summary tables identify the item number, component or part,, 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 summary report 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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 14 of 101 3.12.3 During the PSI activities a list shall be maintained of the components examined and as a minimum the component or part number, the report number, acceptance and/or evaluation process, percentage of examination volume or area complete, with an explanation of 90% or less coverage, if applicable and reported to the program owner.
3.13 EVALUATION OF RECORDED CONDITIONS Evaluation shall be made of flaws detected during the examinations as required by ASME Section XI, Articles IWB-3000 for Class 1 components, IWC-3000 for Class 2 components, and IWD-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.
3.14 RECORDS AND REPORTS 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 IWA-6000 of Section XI. These activities are requirements in addition to being implemented by Watts Bar procedures for, Record Control.
Nuclear Generation Development & Construction (NGDC) Project Procedure (PP),
specifically NGDC 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.
3.14.1 Prepare and submit the PSI Summary Report to U2 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:
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 Request written to date 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
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 15 of 101 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 depart. The Site Final Report shall contain, but not be limited to, the following The PSI Summary Report Summary of PSI examinations on ASME Class 3 Non-Regulatory Augmented Examinations Summary of Personnel Certifications 3.15 IWB REQUIREMENTS AND EXEMPTIONS 3.15.1 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-O 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. 10CFR50.55a provides the following requirements in lieu of and in addition to the requirements contained within this document:
3.15.3.1 10CFR50.55a(b)(2)(xxi) requires inclusion of Items B3.120 and B3.140 examination requirements of the 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 In the case of the vessels only, the examination are performed after the hydrostatic test required by Section III.
3.15.4.2 Such examinations are conducted under conditions and with equipment and techniques equivalent to those that are expected to be employed for subsequent inservice examinations.
3.15.4.3 The shop and field examination records are or can be documented and identified in a form consistent with those required for records management.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 16 of 101 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 IWB Class 1 components.
3.15.6 The following components or parts 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 Piping of NPS 1 and smaller, except for steam generator tubing; 3.15.6.2 Components and their connections in piping of NPS 1 and smaller; 3.15.6.3 Reactor vessel head connections and associated piping, NPS 2 and smaller, made inaccessible by control rod drive penetrations; 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 REOUIREMENTS AND EXEMPTIONS 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 performed and completed prior to initial plant startup.
3.16.3 Components shall be examined as specified in the Summary 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:
3.16.4.1 In the case of the vessels only, the examination are performed after the hydrostatic test required by Section III.
3.16.4.2 Such examinations are conducted under conditions and with equipment and techniques equivalent to those that are expected to be employed for subsequent inservice examinations.
3.16.4.3 The shop and field examination records are or can be documented and identified in a form consistent with those required for records management.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 17 of 101 3.16.5 The following Class 2 components or parts of components are exempt from the volumetric and surface examination requirements.
3.16.5.1 Class 2 components within RHR, ECC and CHR systems or portions of systems.
(a) For systems, except the High Pressure Safety Injection; (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 High Pressure Safety Injection portion; (1) Class 2 piping NPS I V2 and smaller; (2) Class 2 vessels, pumps, and valves and their connections in piping NPS 1 1/22 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 (SITs) 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 normal plant operating conditions.
3.16.5.2 Class 2 components within systems or portions of systems other than RHR, ECC and CHR systems.
(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 Feedwater Systems.
(1) Class 2 piping NPS I 1/2/and smaller; (2) Class 2 vessels, pumps, and valves and their connections in piping NPS I /2 and smaller
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 18 of 101 (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 2000 F (93 0C).
(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.
3.16.5.3 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.
Note: Piping is defimed 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.
3.17 IWD REQUIREMENTS AND EXEMPTIONS 3.17.1 Subsection IWVD provides the rules 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 functions:
(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 be 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
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 19 of 101 (c) components that operate at a pressure of 275 psig or less and at a temperature of 200'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 cross-sectional area neither of which exceeds the nominal outside diameter cross-sectional area of the designated size.
3.18 IWF REQUIREMIENTS AND EXEMPTIONS 3.18.1 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 supports, 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 ISTD of the ASME/ANSI OM 2001 Edition through OMb 2003 Code as allowed by 10CFR50.55a(b)(3)(v). Examination of snubbers shall be performed using the VT-3 visual examination method described in IWA-2213.
Integral and non-integral attachments for snubbers, including lugs, pins, bolting and clamps, shall be examined in accordance with the requirements of this document.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 20 of 101 Thermal movement verification of snubbers will be in accordance with procedure 2-PTI-999-02, "Thermal Expansion".
3.18.4 Supports exempt from the examination requirements are those connected to piping and other items exempted from volumetric, surface, VT-I 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.
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 support 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 support 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 compression.
(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.
3.18.6 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 interface to the clamp, but does not include the component-to-clamp interface.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT, PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 21 of 101 (b) weld connections to building structure (c) weld and mechanical connections at intermediate joints in multi-connected integral and nonintegral supports (d) clearances of guides and stops, alignment of supports, and assembly of support items (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 IWA-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.
3.18.9 All examinations listed in the Summary Table of Section 7.0 shall be performed completely, once, as a preservice examination. These preservice examinations shall be extended to include 100% of all supports not exempted by IWF-1230.
3.18.10 Examinations for systems that operate at a temperature greater than 200'F during normal plant operation shall be performed during or following initial system heatup and cooldown.
3.18.11 Prior to service, the applicable examinations listed in the Summary Table of Section 7.0 shall be performed on component supports that have been adjusted in accordance with IWF-3000 or corrected by various activities.
3.18.12 For systems that operate at a temperature greater than 200'F during normal plant operation, Watts Bar shall perform an additional preservice examination on the affected component supports during or following the subsequent system heatup and cooldown cycle unless determined unnecessary by evaluation.
3.19 CODE CASES 3.19.1 The following Code Cases are accepted for use in Regulatory Guide 1.147 and shall be utilized where applicable:
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 22 of 101 N-460 Alternative Examination Coverage for Class I and 2 welds. To be used on all IW-B-2500, Class 1 and IWC-2500, Class 2 welds.
N-686-1 Alternative Requirements for Visual Examinations, VT-1, VT-2, and VT-3,Section XI, Division I 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 1 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 has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-Iwith limiting assumptions on the flaw aspect ratio. The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table (the external surface is from point M to point N in the figure).
3.19.3 The following Code Cases are incorporated by reference in 10CFR50.55a(g)(6)(ii)(D) and (E) and shall be utilized where applicable.
N-722-1 Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials.
N-729-1 Alternative Examination Requirements for PWR Reactor Vessel Upper Heads with Nozzles having Pressure Retaining Partial Penetration Welds.
3.20 CODE RELIEF During the preservice inspections it may be determined that certain examination or inspection requirements are not practical to perform as outlined in Section XI. Code relief may be requested by following the circumstances as listed below for an alternative or for impractical examinations. An index of requests for relief its subject, status and comments are listed in section 9.0 as they are established.
3.20.1 IOCFR50.55a(a)(3) states "Proposed alternatives to the requirements of paragraphs (c), (d), (e), (f), (g), and (h) of this section or portions thereof may be
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 23 of 101 used when authorized by the Director of the Office of Nuclear Reactor Regulation. The applicant shall demonstrate that:
(i) The proposed alternatives would provide an acceptable level of quality and safety, or (ii) Compliance with the specified requirements of this section would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety."
3.20.2 10CFR50.55a(g)(5)(iii) If the licensee has determined that conformance with a code requirement is impractical for its facility, the licensee shall notify the NRC and submit, as specified in § 50.4, information to support the determinations.
Determinations of impracticality in accordance with this section must be based on the demonstrated limitations experienced when attempting to comply with the code requirements during the inservice inspection interval for which the request is being submitted. Requests for relief made in accordance with this section must be submitted to the NRC no later than 12 months after the expiration of the initial or subsequent 120-month inspection interval for which relief is sought.
3.20.3 10CFR50.55a(g)(5)(iv) states "Where an examination requirement by code edition or addenda is impractical, the basis for this determination must be submitted for NRC review and approval not later than 12 months after the expiration of the initial or subsequent 120 month inspection interval for which relief is sought."
3.21 AUGMENTED COMPONENTS This program includes an augmented examination section for items required to be examined as identified below. The types of commitments not required by ASME Section XI and are committed to be inspected or examined. The Summary Tables for the commitments by Watts Bar is located in Section 8.0.
3.21.1 Examination requirements other than ASME Section XI of IWB, IWC, IWD and IWF on Class 1, 2 or 3 components in accordance with Safety Analysis Report (SAR) or IOCFR50.55a.
3.21.2 USNRC Notices, Bulletins, or Generic Letters shall be followed as committed to by Watts Bar.
3.21.3 INPO or other industry operating experiences shall be followed as committed to by Watts Bar.
3.21.4 Westinghouse bulletins or notices shall be followed as committed to by Watts Bar.
3.22 CALIBRATION STANDARDS Calibration blocks used for ultrasonic examination shall be controlled in accordance with IEP-203, "Control of Calibration Standards." Refer to the Table below for a listing of
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 24 of 101 WBN calibration blocks. Calibration blocks from other TVA sites and/or vendors may be used for WBN Unit 2 preservice following review and assignment by a TVA Level I11.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 25 of 101 Calibration Schedule or Block ID Size (Dia.) [ Thickness Material WB-01 S.........
....... 6.00"
....................... ...I..
.......... Sch
....?......... 160 (0.715")
......... i
...........SA-376
.. .. ... .........TP304 . .. . ............ .. .... .. ...
WB-02 8.00" Sch 140(0.942") - SA-376 TP304 i .....
WB-03 '12.00" Sch 140 (1.158") ~ SA-376 TP316 WB-04 V 16.00" Sch 80 (0.754") SA-333 Gr6- -
WB-05 32.00" 1.410" r70 WB-06 2.00" Sch 160 (0.346") TP304 WB-07 8.00" Sch 120 (0.758") TP304 WB-08 12.00" Sch80 (0.7671) SA-376TP316 WvB-09........
.... ....... 88.00"
....... 00...
Scb... .. !
.. -40o. ...(0.307")
o..0 .7 ') ............ ... ........... A-312 ...........
i....... . P..
TP316 ... 6..................
WB-10 V 14.00" Sch 160 (1.352") - A-312 TP304 WB-11 ...... ....................
3.00" ...... ....................
S Sch .!
160 .. .. ............
(0.450") .....
........... . TP304-H TP.4 - ..... ......................
TB-12 2.50" I ...SA-376 .............. TP304 WB-12~ ~~ 25"---------------------------96" ~
WB-13 : 4.00" - Sch 120 (0.450") A-312 TP304 WvrB-14 . . FLAT (12.00" x 4.00") . .1.482" SA-516 Gr70 WB-15 7_ .. ....i.. .FLAT ..T....
(12.00" ..O.:
........ .x 4.00")..4 108 o... s ........
- ..... . ..'.. . f S.-3...T . . ..P.......
SA36T 04 .4................. .............
WB-16 i12.00" Sch16(.322") SA-376 TP304 WB-17 5.00" Sch 160 (0.585") - SA-403 WP316 WB-18 .... . . .........
. .......... . 18.00"
. .... .... . ................... ... ....... ..... .. ....... ..... ......... .. ...... . ............. ... . Sch 80 (0.938")
. ... .. . . . .. ....... SA-333 WB-19 i 6.00"3 Sch XXH (0.782") A106 GrB WB-20 - 1l50"-- Sch 160 (0.312") 0 SA-376 TP304 -
VWB-21 10.00" 1.493" SA-106 Gr B WB-22 INOT USED WB-23 _ 1.375" DIA x 17.00" LTH STUD N/A SA-193 GrB7
......i....... .......... ..........
I... .............
WB-24 1.250" DIA x 5.00" LTH STUD N/A SA-193 GrB7 WB-25 - 1.675" DIA x 10.50" LTH STUD N/A SA-193 GrB7 WB-26 4.50" DIA x 30.50" LTH STUD N/A SA-193 GrB7 WB-27 i 2.00" DIA x 8.00" LTH STUD N/A SA-193 GrB7 WB-28 ...
2*7.... ......... ....... NOT ._0 "USED ............... ..........
6.T .... P.... ... ......................
WvB-29 8.00" 1.206" .SA-376 TP304 WB-30 5.00" 0.918" SA-376 TP304 VM-31 _: 7 ... 1.125" DIA x7.50" LTH STUD ,LS .x _5 .,_ .....
N/A .:._.. ......................
........ ...... .......... ........ . ......A 1A AIS ! k4140 _4 . . . .... ..... ..
WB-32 1.250" DIA x 10.00" LTH STUD N/A AIS14140 WB-33 10.00" Sch 140 (1.006") TP304 WB-34 14.00" - - -- Sch 140 (1.247") 1TP304 - [-
WB-35 NOT USED 1
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 26 of 101 C -alibration .. Schedule or Block 11) Size ( ia.) Thickness Material _
WB-36 1.50" DIA x 10.75" LTH STUD NAAISI 4140 _
WB-37 6.00" Sch 80 (0.433") SA-53 GrB WB-38 8.00" Sch80 (0.484") SA-106 GrB 3: ......... ................................................
9.... .
L....... 6 .... WT..... ...... ............... ............................................ _...6.........................................
I............._......,0...1 ............S . .A-......... . .... ...... ................................
WB-39 240"_ T 6.00" WTH) 4.016" - - SA-533 GrA. ..
WB-40 4.00" Scl6(2.516") A-312 TP304 WB- 41 . -
. 2 ..
12.00".Sch.0. . 0 40 (0.363") . . ...6.
. ............. ... . ....... A-312TP304 ......... ... .. ..
WB-42 18.00" Sch-40 (0.641") SA-403 TP304 2{B-40 :18.00" WB-44 FLAT 8.00" LT x 5.00" WTH 2.150" .6 SA-240 TP304 l . ... . .... . . . . ....
. .... ;......................... I.........................
IWB-45 ;_ ..*4....... _... 7.DIA
...2.00" * .x .9 9.00" .P. L LTH *S STU-D .. .......... ................... .............
N/A 6...........
I.... ............... ............. ......
..... .A. !...
SA193 93........
GrB37 r.. ..... ............... ......
WB-46~14.00" Sch 40 (0.470" SA-358 TP304 Vessel 22.375" LTH x 6.01" WTH WB-47 (OLD ED WAT-021) 5.805" A-508 C12 Vessel 33.875" LTH x 6.01" WTrH
....... . .-...... 8.... ............
.. ..O .. . . ...
.......... .I . .T.WA
. 2................ ..... ....
........... . ....... ..... . 8. 2... 5...... ...........
.... .. ............. .. ...... ... . .A ..... . C..!.... .......... ........ ......... ....
Vessel 43.31" LTH x 8.08" WTH WB-49 . L(O. ID WAT-03, .. 11.187" A-508.C!2 ..
WB-50........ .... Vessel ......... ..
32.75" 5..."....
.es..f E...........
LTH ~ ~ x ...........
11.18" S. .............
WTH f ..................... .... .............
10.25" . ............... ..... ...................................................................
A-508 ........... ..............
C12... .....................
Vessel 27.53" LTH x 6.00" WVTH (OLD W -5 ID WAT-05) 7.125" A-508 C12 WB-52 . ......... .. . .
4.00" . . .. *
..... .. 0...6...
0.656"' .... . .......
I. . . . ... ... ......
.. .. . .Tri-metallic
.......... ....... .r..ea!.!
... ... 3............07 ........................................................................
WB-53.................. .. ..... ... ..........
.3._..00..'. ................................... ..... ....... ........ #..598 .......... C1_.2 WB-54 12.00" Sch 160 (1.212') SA-351 Gr CF8 Pressurizer 15.00" LTH x 6.125" S 1 WB-55 WTIH. 20 3.300"
.. . SA-533 GrA C12 Pressurizer 20.00" LTH x 6.250" i WB-56
.. WTH ................................................................................................ ....................
. . . .. . . . ...... 4.000"
............................. SA-533
.................... ......... .... ................................... ...................... .... GrA
.... ............ . ......... C12
- WB-57 Stm Gen 25.125" LTH x 7.000" WTH 5.000" SA-216 GrWCC Pressurizer 17.937" LTH x 6.750" WB-58 WTH 3.062" SA-533 GrA.... .................
........................... C12 ........... ....
WB-59 i~~~ . .. .. ....... . . .... . .~~ 31.00"
. . . .. . ............. ... ...... (ID) 2.400"
..... ............. ....... .............. ................... ............ .................. ..................... ..... ............... . .. . ...... . ...... SA351 CF8A WB-60 31 .00 D3) )000" 3D SA351 CF8A
!WB-61 2.00" Sch 80 (0.225") SA-376 TP304 SWB-62 .3. 00" ..... . . .. .. Sch 40 (0.265") SA-376 TP304 WB-63 3.00" - Sch 80 (0.297") SA-376 TP304. .
WB-64 4.00" - Sch 40 (0.268") SA-376 TP304 WB -65 4.00" Sch 80 (0.343") SA-376 TP304
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERWCE INSPECTION PROGRAM PLAN REVISION 7 PROCEDURE Page 27 of 101 Calibration Schedule or Block E Blo_ _k_. __Size S ze ((Dia.)-- j ~a .) .............................. ------- ......... .............
... . ............"....n.
..... Thickness ..................... Material WB-66 14.00" Sch 30 (0.3 70") A-358 TP304 3B-67
.. ... .. ... ...... ....... ................... 16.00" i .......
....................... . .................... ................ . .. . Sch
... . . ... . 30. .... (0.395")
... .. ..... . ..... -. . . ... .. A-358 TP304 WB-68 20.00" . . .. Sch
. Sch.......
.0 20
- 20. 37 5" (0.375") ...........
. T. P 3 094. .......................
4 .........
SA-35R TP304
- 3rB-70 6" DIA STUD ____ IN/A AISI 4340 WB-71 6.57" OD /5.00" ID 0.787" .. SB-166 TP600 SA-479 TP304L ISA-WB-72 6.57" OD /5.00" ID 0.786" 182 WB-73 4.00" OD 2.75" ID 0.625" SB- 166 TP600 SA-182 TPA91/SA-W-74 ! ......
- 4.0 OD
...................... ....... /2.75"
........... ............... ID...............
........ ...... ,0.625"
.......... 479 TPA91 WB-75 2 4.5" dia. RCP stud i N/A A540 (E4340H)
WB-76 6.75" dia. RPV stud N/A SA-540 UINNER RADIUS CAL BLOCK -
WB-77 FLAT N/A SA-240 TP304 WB-78 thru -
-81 Alternate cal block __N/A A-516 Gr70 WBN-82 thru -85 Alternate cal block N/A A-240 TP304 WB-86 4" Pipe Sch 80 .337" SA-335 GrP22 WB-87 -. 2" Pipe Sch 160 .344" SA-335 GrP22 WB-95 & - i 96 . . Altermate cal block N/A A-5 16 Gr70
- 3WB-97 &-
98 Altemate cal block N/A TP3!04
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 28 of 101 SECTION 4.0 IWB
SUMMARY
TABLES For ASME CLASS 1 CATEGORIES B-A Pressure Retaining Welds in Reactor Vessel B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels B-D Full Penetration Welded Nozzles in Vessels B-F Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles B-G-1 Pressure Retaining Bolting, Greater Than 2 Inches in Diameter B-G-2 Pressure Retaining Bolting, 2 Inches and Less in Diameter B-J 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-O Pressure Retaining Welds in Control Rod Housings 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 further within the program plan, schedule or summary reports.
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 29 of 101 Examination Category B-A, Pressure Retaining Welds in Reactor Vessel Inspection Program B Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.
B3.10 Shell Welds BI.1 I Circumferential Applicable Vol. IWB-2500-1 All Welds IWB-3510 4 4 (2)
B 1.12 Longitudinal NA to UNIT-2 -
B 1.20 Head Welds Accessible B 1.21 Circumferential Applicable Vol. IWB-2500-3 length of IWB-3510 2 2 weld Accessible BI.22 Meridional Applicable Vol. IWB-2500-3 length of all IWB-3510 6 6 welds B11.30 Shell to Flange Applicable Vol. IWB-2500-4 Weld (2) IWB-3510 I B1.40 Head to Flange Applicable Vol. & Suf. IWB-2500-5 Weld (2) IWB-3510 I BI.50 Repair Welds (I)
B3.51 Beltline region NA to UNIT-2 Totals Examination Category B-A 14 14 NOTES:
(I) NA to Unit-2 (2) Includes essentially 100% of the weld length.
(3) NA to Unit-2 Preservice activities (4) NA to Un~it-2 Preservice activities (5) NA to Unit-2 Preservice activities
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 30 of 101 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels Inspection Program B Item No Component xmndCmlac Component Exam ehd Examination Requirements Extent of Exntf Acceptance Acetne Total TtlRqid Required No. Examined Compliance Method Fig.mNo. Exam Standard Population Examination Pressurizer B2.10 Shell to Head B2.11 Circumferential Applicable Vol. IWB-2500-1 Both Welds IWB-3510 2 2 (4)
Iff of all B2.12 Longitudinal Applicable Vol. IWB-2500-2 weld IWB-3510 2 2 (2)
B2.20 Head Welds B2.21 Circumferential NA to UNIT-2 -
B2-22 Meridional NA to UNIT-2 Steam Generators (Primary side)
B2.30 Head Welds B2.31 Circumferential NA to UNIT-2 B2.32 Meridional . NA to UNIT-2 B2.40 Tubesheet to Head Weld Applicable Vol. IWB-2500-6 Weld IWB-3510 4 4 (4)
Heat Exchanger (Primary side) - Head B2.50 Head Welds B2.51 Circumferential NA to UNIT-2 - -
B2.52 Meridional NA to UNIT-2 -
Heat Exchanger (Primary side) - Shell B2.60 Tubesheet to Head Welds NA to UNIT-2 -
B2.70 Longitudinal Welds NA to UNIT-2 -
B2.80 Tubesheet to Shell Welds NA to UNIT-2 - - -
Totals Examination Category B-B 8 8 NOTES:
(1)NA to Unit-2 Preservice activities (2) The weld selected for examination is that weld intersecting the circumferential weld.
(3)NA to Unit-2 Preservice activities (4) Includes essentially 100% of the weld length
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 31 of 101 Examination Category B-D, Full Penetration Welded Nozzles in Vessels Inspection Program B Item Component Component Exam Examination Extent of Acceptance Total Required No. (8) Examined Compliance Method Requirements Exam Standard Population Examination 8)xm
___o.___ eCmlneeh Fig. No.
Reactor Vessel B3.90 Nozzle to Vessel Welds Applicable Vol. WB-25007 All Nozzles IWB-3512 8 8 (a) through (c) (1)
B3.100 Nozzle Inside Radius Section Applicable EVT-9 (4) Alt Nozzles IWB-3512 8 8 (9)()
Pressurizer B3.1 10 Nozzle to Vessel Welds Applicable Vol. IWB 25007 All Nozzles IWB-3512 6 6 B3. 120 (a) through (c) (1)
All Nozzles IB31 (6) Nozzle Inside Radius Section Applicable Vol. (7) (4) (1) IWB-3512 6 6 Steam Generators (Primary side)
B3.130 Nozzle to Vessel Welds NA to UNIT-2 -
B3.140 All Nozzles (6) Nozzle Inside Radius Section Applicable Vol. (7) (4) (1) IWB-3512 Heat Exchanger (Primary side) - Head B3.150 Nozzle to Vessel Welds NAto UNIT-2 - -
B3.160 Nozzle Inside Radius Section NA to UNIT-2 Totals Examination Category B-D 36 36 NOTES:
(1) Includes nozzles with full penetration welds to vessel shell (or head) and integrally cast nozzles, but excludes manways and handholes either welded to or integrally cast in vessel.
(2) NA to Unit-2 Preservice activities (3) NA to Unit-2 Preservice activities (4) The examination volumes shall apply to the applicable Figure shown in Figs. IWB-2500-7(a) through (d).
(5) NA to Unit-2 Preservice activities (6) 10CRF50.55a(b)(2)(xxi)(A) Table IWB-2500-1 Items B3.120 and B3.140 (Inspection Program B) in the 1998 Edition must be applied when using 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-3512-I, may be performed in place of an ultrasonic examination, reference 10CFR50.55a(b)(2)(xxi)(A).
(8) Category Items B3.10 - B3.80 are based on Inspection Program A and do not apply to Unit-2.
(9) Code Case N-648-1, with conditional approval, see paragraph 3.19.2 for details of exam area and other information.
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWB3
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 32 Of 101 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles Ins pection Program B item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.
Reactor Vessel B5.10 NPS 4 or Larger-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur IWB-2500-8 All Welds IWB-3514 8 8 B5.20 Less Than NPS 4-Nozzle-to-Safe End Butt Welds NA to UNIT-2 B5.30 Nozzle-to-Safe End Socket Welds NA to UNIT-2 Pressurizer B5.40 NPS 4 or Larger-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur IWB-2500-8 All Welds IWB-3514 6 6 B5.50 Less Than NPS 4-Nozzle-to-Safe End Butt Welds NA to UNIT-2 B5.60 Nozzle-to-Safe End Socket Welds NA to UNIT-2 Steam Generators B5.70 NPS 4 or Larger-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur IWB-2500-8 All Welds IWB-3514 8 8 B5.80 Less Than NPS 4-Nozzle-to-Safe End Butt Welds NA to UNIT-2 B5.90 Nozzle-to-Safe End Socket Welds NA to UNIT-2 Heat Exchangers B5.100 NPS 4 or Larger-Nozzle-to-Safe End Butt Welds NA to UNIT-2 B5.110 Less Than NPS 4-Nozzle-to-Safe End Butt Welds NA to UNIT-2 B5.120 Nozzle-to-Safe End Socket Welds NA to UNIT-2 Totals Examination Category B-F 22 22 Note:
(1) NA to Unit-2 Preservice activities (2) NA to Unit-2 Preservice activities
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES DDC-* DtII= I IAICD* Y'IIM DDnP0DAR DI AAI I I Page 33 of 101 Examination Category B-G-1, Pressure Retaining Bolting, Greater than 2 in. in Diameter Inspection Program 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 54 54 B6.20 Closure Studs (1)(7) Applicable Vol. IWB-2500-12 All Studs IWB-3515 54 54 B6.40 Threads in Flange (2)(6) Applicable Vol. IWB-2500-12 Flange IWB-3515 54 54 Surface B6.50 Closure Washers, Bushings (2) Applicable VT-I Surfaces All Washers IWB-3517 54 54 Pressurizer B6.60 Bolts and Studs NA to UNIT-2 - -
B6.70 Flange Surface, when connection disassembled NA to UNIT-2 -
B6.80 Nuts, Bushings, and Washers NA to UNIT-2 -
Steam Generators B6.90 Bolts and Studs NA to UNIT-2 -
B6. 100 Flange Surface, when connection disassembled NA to UNIT-2 -
B6.1 10 Nuts, Bushings, and Washers NA to UNIT-2 -
Heat Exchangers B6.120 Bolts and Studs NA to UJNIT-2 -
B6.130 Flange Surface, when connection disassembled NA to UNIT-2 -
B6.140 Nuts, Bushings, and Washers NA to UNIT-2 -
C .1 1 .1. .1.
Notes; at end of this section.
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 34 of 101 Examination Category B-G-I, Pressure Retaining Bolting, Greater than 2 in. in Diameter Inspection Program B Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population p Examination Fig. No.
Piping B6.150 Bolts and Studs NA to UNIT-2 B6.160 Flange Surface, when connection disassembled NA to UNIT-2 B6.170 Nuts, Bushings, and Washers NA to UNIT-2 - -
Pumps B6.180 Bolts and Studs (1) (7) Applicable Vol. IWB-2500-12 Studs IWB-3515 96 96 B6.190 Flange Surface, when connection disassembled Applicable VT-I Surfaces Flange IWB-3517 4 4 (2) (4) (6) Surfaces B6.200 Nuts, Bushings and Washers NA to Unit-2 - - - -
Valves B6.210 Bolts and Studs NA to Unit-2 - - - -
B6.220 Flange Surface, when connection disassembled NA to Unit-2 - - - -
B6.230 Nuts, Bushings, and Washers NA to Unit-2 - - - - -
Totals Examination Category B-G-1 316 316 NOTES:
(1) Bolting may be examined: (a) in place under tension; (b) when the connection is disassembled; (c) when the bolting is removed.
(2) Threads in base material of flanges surface are required to be examined only when the connections are disassembled-(3) NA to Unit-2 Preservice activities (4) Visual examination of bolted connections, VT-I of the flange surface, nuts and washers, for pumps is required only when the component is examined under Examination Category B-L-2. This is for one pump in a group of pumps performing similar functions in a system and is required only when disassembly for maintenance, repair, or volumetric examination, as stated in B-L-2. (See note 2 in summary table for category B-L-2 (5) NA to Unit-2 Preservice activities (6) Examination includes I in. annular surface of flange surrounding each stud.
(7) When bolts or studs are removed for examination, surface examination meeting the acceptance standards oflWB-3515 may be substituted for volumetric examination.
I-WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 35 of 101 Examination Category B-G-2, Pressure Retaining Bolting, 2in. and Less in Diameter Inspection Program B Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements or Exam Standard Population(5) Examination Fig. No.
Reactor Vessel B7.10 Bolt, Studs, and Nuts NA to Unit-2 Pressurizer B7.20 Bolt, Studs, and Nuts (1) (2) Applicable VT-I Surface All Studs, IWB-3517 I and Nuts Steam Generators B7.30 Bolt, Studs, and Nuts (1) (2) Applicable VT-I Surface All Studs, IWB-3517 8 8 and Nuts Heat Exchangers B7.40 Bolt, Studs, and Nuts NA to Unit-2 Piping All Bolt, B7.50 Bolt, Studs, and Nuts (I) Applicable VT-I Surface Studs, and IWB-3517 13 13 Nuts Pumps B7.60 Bolt, Studs, and Nuts (1) (2) Applicable VT-I Surface All Studs, IWB-3517 8 8 and Nuts Valves CRD Housing (only when disassembled)
B7.80 (4) Bolt, Studs, and Nuts (1) (4) NA to Un(t-2 Totals Examination Category B-G-2 59 59 NOTES:
(1) Bolting is required to be examined only when a connection is disassembled or bolting is removed.
(2) For vessels, pumps, or valves, examination of bolting is required only when the component is examined under Examination Category B-B, B-L-2, or B-M-2. Examination of bolted connection is required only once during the interval. (See note 2 in summary table for category B-L-2 and B-M-2.)
(3)NA to Unit-2 Preservice activities (4) The provisions of Examination Category B-G-2, Item B7.80, that are in the 1995 Edition are applicable, reference IOCFR50.55a(b)(2)(xxi)(B), only to reused boltina.
(5)Total population represents "bolted connections".
TBD = To be determined
WBN-2 PSI REVISION 7 I WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 36 of 101 Examination Category B-J, Pressure Retaining Welds in Piping Ins pection Pro ram B Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination
______________________________ ____________Fig. No.
B9.10 NPS 4 or Larger B9.11 Circumferential Welds Applicable Vol. & Sur IWB-2500-8 Welds (5) (6)(1)()
(7) IWB-3514 285 285 B9.20 Less Than NPS 4 Circumferential Welds other than PWR Welds B9.21 High Pressure Safely Injection Systems Applicable Sur. IWB-2500-8 (1) (4) (5) IWB-3514 105 105 B9.22 Circumferential Welds of PWR High Applicable Vol. IWB-25008 (2) Welds Pressure Safely Injection System IWB-3514 42 42 (4) (6) (7)
B9.30 Branch Pipe Connection Welds B9.31 NPS 4 or Larger Applicable Vol. & Sur IWB-2500-9, 10 & Welds (I) (4) IWB-3514 I 11 I1 (5)(6)(7)
B9.32 Less Than NPS 4 Applicable Sur. IWB-2500-9, 10 & Welds IWB-3514 29 29 II (1) (4) (5)
B9.40 Socket Welds Applicable Sur. IWB-2500-8 Welds IWB-3514 406 406 (1) & (4)
Totals Examination Category B-J 878 87 Notes:
(1) Examinations shall include the following:
(a) All terminal ends in each pipe or branch nun connected to vessels.
(b) All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed either of the following limits under loads associated with specific seismic events and operational conditions:
(I) primary plus secondary stress intensity range of 2.4Sm for ferritic steel and austenitic steel (2) cumulative usage factor U of 0.4 (c) All dissimilar metal welds not covered under Category B-F.
(d) Additional piping welds so that the total number of circumferential butt welds (or branch connection or socket welds) selected for examination equals 25% of the circumferential butt welds (or brancd connection or socket welds) in the reactor coolant piping system. This total does not include welds exempted by IWB-1220 or welds in Item No. B9.22. These additional welds may be located in one loop (one loop is defined for both PWR and BWR plants in the 1977 Edition).
(2) A 10% sample of PWR high pressure safety injection system circumferential welds in piping > NPS 11/2 (DN 40) and < NPS 4 (DNIOO) shall be selected for examination. This sample shall be selected from locations determined by the Owner as most likely to be subject to thermal fatigue. Thermal fatigue may be caused by conditions such as valve leakage or turbulence effects.
(3) NA to Unit-2 Preservice activities (4) Includes essentially 100% of weld length.
(5) For circumferential welds with intersecting longitudinal welds, surface examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting Examination Category B-F and B-J circumferential welds.
(6) For circumferential welds with intersecting longitudinal welds, volumetric examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting Examination Category B-F and B-J circumferential 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 of the welds and for that length of longitudinal weld within the circumferential weld examination volume.
(b) When longitudinal welds are specified but locations are unknown, or the existence of longitudinal welds is uncertain, the examination requirements shall be met for both transverse and parallel flaws within the entire examination volume of intersecting circumferential welds.
(7) For welds in carbon or low alloy steels, only those welds showing reportable preservice transverse indications need to be examined by the ultrasonic method for reflectors transverse to the weld length direction except that circumferential welds with intersecting longitudinal welds shall meet Note (5).
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 37 of 101 Examination Category B-K, Welded Attachments for Vessels, Piping, Pumps and Valves Ins pection Program B Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.
Pressure Vessels Surface IWB-2500-13, 14 Each welded B10.10 Welded Attachments (I) Applicable (7) and 5 5 (7) and 15 15 attachment (2)(6) IWB-3516 Piping IWB-2500-13, 14 Each welded 1310.20 Welded Attachments (1) Applicable Surface 5attachment IWB-3516 TBD TBD (2)(6)
Pumps BI0.30 Welded Attachments (1) NA to Unit-2 Valves BI0.40 Welded Attachments (1) NA to Unit-2 Totals Examination Category B-K TBD TBD NOTES:
(1) Weld buildup on nozzles that is in compression under normal conditions and provides only component support is excluded from examination. Examination is limited to those welded attachments that meet the following conditions:
(a) the attachment is on the outside surface ofthe pressure retaining component; (b) the attachment provides component support as defined in NF-l 110; (c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component, and (d) the attachment weld is full penetration fillet, or partial penetration, continuous or intermittent.
(2) The extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination.
(3) NA to Unit-2 Preservice activities (4) NA to Unit-2 Preservice activities (5) NA to Unit-2 Preservice activities (6) Examination is required whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.
(7) For the configurations shown in Figs. IWB-2500-13 and IWB-2500-14, a surface examination from an accessible side of the attachment weld shall be performed. Alternatively, for the configuration shown in Fig. IWB-2500-14, a volumetric examination of volume A-B-C-D from an accessible side of the attachment weld may be performed in lieu of the surface examination of surfaces A-B or C-D.
TBD = To be determined
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 38 Of 101 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 Inspection Program B Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.
Pumps B12.10 Pump casing welds, B-L-I (4) Applicable VT-I IWB-2500-16 All welds IWB-3518 4 4 B 12.20 Pump casing, B-L-2 (2) 4 0 Valves B12.30 Valves, less than NPS 4 valve body welds, B-M-I (4) NA to Unit-2 - -
B12.40 Valves, NPS 4 or larger valve body welds, B-M-l (4) NA to Unit-2 - -
B712.50 Valve B-M-2body, exceeding NPS 4, (2) 28 28 Totals Examination Category B-L-1 TBD 4 NOTES:
(I) NA to Unit-2 Preservice activities (2) NA to Unit-2 Preservice activities, reference RWB-2200 (3) NA to Unit-2 Preservice activities (4) Includes essentially 100% of weld length.
TBD = To be determined
WBN-2 PSI REVISION 7 I I WATTS BAR UNIT- 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 39 of 101 Examination Category B-N-I, 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 Program B Item Component Component Exam Examination Extent & Acceptance Total Required No. Examined Compliance Method Fig. No. Exam Standard Population Examination Reactor Vessel Each B13.10 Vessel Interior B-N-I (1) Applicable VT-3 Accessible Areas Inspection lWB-3520.2 I Period Reactor Vessel (BWR)
B13.20 Interior attachments within beltline region NA to Unit-2 B-N-2 B113.30 Interior attachments beyond the beltline region NA to Unit-2 B-N-2 B 13.40. Core Support Structure NA to Unit2 B-N-2 Reactor Vessel (PWR)
B13.50 Interior attachments within beltline region NA to Unit-2 B-N-2 B 13.60 Interior attachments beyond the beltline region Applicable VT-3 Accessible Welds Welds IWB-3520.2 6 6 B-N-2 B 13.70 Core Support Structure Applicable VT-3 Accessible Surfaces IWB-3520.2 1 I B-N-3 (2) Surfaces Examination Category B-N-I 1 I Examination Category B-N-2 6 6 Totals Examination Category B-N-3 I 1 NOTES:
(1) Areas to be examined shall include the spaces above and below the reactor core that are made accessible for examination by removal of components during normal refueling outages.
(2) The structure shall be removed from the reactor vessel for examination.
(3)NA to Unit-2 Preservice activities
WATTS BAR UNIT- 2 WBN-2 PSI REVISION 7 I I IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 40 of 101 Examination Category B-O, Pressure Retaining Welds in Control Rod Housings Inspection Program B Item No Component xmndCmlac Component Exam ehd Examination Requirements Extent of Exeto Acceptance Acetne Total TtlRqid Required No. Examined Compliance Method Fig.mNo. Exam Standard Population Examination Reactor Vessel Volumetric 100%
B14.10 Welds in CRD Housing (1) Applicable or IWB-2500-18 Peripheral IWB-3523 20 20 SurfaceCRD Housing Totals Examination Category B-O 20 20 Note:
(1)20 Peripheral components of the 78 Total CRD Housings.
WBN-2 PSI REVISION 7 I WATTS BAR UNIT- 2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 41 of 101 SECTION 5.0 IWC
SUMMARY
TABLES For ASME CLASS 2 INDEX CATEGORY 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-I 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 Xl 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 further within the program plan, schedule or summary reports.
WBN-2 PSI REVISION 7 II WATTS BAR UNIT - 2 IWC
SUMMARY
TABLES PRESER VICE INSPECTION PROGRAM PLAN Page 42 of 101 Examination Category C-A, Pressure Retaining Welds in Pressure Vessels Inspection Prozram B Item No. Component.
Component omplince Exam Mthoduig.ment Examination Extent and Feqey Acceptance StnadooafRqi Total Required No. Examined Compliance Method Requirements Frequency of Standard Population Examination Welds at Volumetric gross CI.O Shell Circumferential Welds (1) (3) (4) Applicable IWC-2500-1 structural IWC-3510 5 TBD (5) discontinuity (2)
Welds at Volumetric gross C1.20 Head Circumferential Welds (1) (3) (4) Applicable (5) 1WC-2500-1 structural IWC-3510 15 TBD discontinuity (2)
Welds at Volumetric gross CI.30 Tubesheet-to-Shell Weld (1) (3) (4) Applicable (5) IWC-2500-2 structural IWC-3510 4 TBD discontinuity (2)
Totals Examination Category C-A NOTES:
(1) Includes essentially 100% of the weld length.
(2) Gross stnrctural discontinuity is defined in NB-3213.2. Examples are junctions between shells of different thicknesses, cylindrical shell-to-conical shell junctions, shell (or head)-to-flange welds, and head-to-shell welds.
(3) In the case of multiple vessels of similar design, size, and service (such as steam generators, heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels.
(4) The vessel areas selected for the initial examination shall be reexamined in the same sequence over the service lifetime of the component, to the extent practical.
(5) For welds in vessels with nominal wall thickness of 0.2 in. or less, a surface examination may be applied in lieu of a volumetric examination. The examination shall include the weld and 0.5 in. on either side of the weld. The acceptance standard for tihe examination shall be those specified for piping in IWC-3514.
TBD = To Be Determined
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 43 Of 101 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels Ins pection Program B Item Component Component Exam Examination Extent and Acceptance Total Required No. Examined Compliance Method Fig. No.
Requirements Exam of Frequency Stnad Standard Pplto Population Exmain Examination C11~ Nozzles in Vessels < 1/2 in. nominal Thickness (1) (2) (3)(4)
C2.11 Nozzle-to-Shell (nozzle-to-head) Weld Applicable Surface IWC-2500-3 (6) IWC-3511 0 TBD C2.20 Nozzles Without Reinforcing Plate in Vessels >
V2 in. Nominal Thickness (I) (2) (3) (4)
C2.21 Nozzle-toSurface and IWC-2500-4 ()IC3111 C2.21 Nozzle-to Shell Weld (nozzle-to-head) Applicable Volumetric (a),(b)or(d) (6) WC-3511 14 TBD C2.22 Nozzle Inside Radius Section Applicable Volumetric IWC-2500-4 (6) IWC-3511 8 TBD (a),(b)or(d)
Nozzles With Reinforcing Plate in Vessels > I/2 in. Nominal Thickness (1) (2) (3) (4)
C2.31 Reinforcing Plate Welds to Nozzle and Vessel Applicable Surface IWC-2500-4(c) (6) IWC-3511 4 TBD C2.32 Nozzle-to Shell Weld (nozzle-to-head) Applicable Volumetric IWC-2500-4(c) (6) IWC-3511 4 TBD C.2 when inside of vessel is accessibleTB C2.33 Nozzle-to Shell Weld (nozzle-to-head) Applicable Visual, VT-2 (5) (6) No Leakage 0 TBD when inside of vessel is inaccessible Totals Examination Category C-B 30 TBD NOTES:
(1) Includes nozzles welded to or integrally cast in vessels that connect to piping runs (manways and handholes are excluded).
(2) Includes only those piping runs selected for examination under Examination Category C-F.
(3) The nozzles selected initially for examination shall be reexamined in the same sequence over the service lifetime of the component, to the extent practical.
(4) In the case of multiple vessels of similar design, size, and service (such as steam generators, heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels.
(5) The telltale hole in the reinforcing plate 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 terminal ends (I) of piping run (2).
TBD = To be determined
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 44 of 101 Examination Category C-C, Welded Attachments for Vessels, Piping, Pumps, and Valves Inspection Pro ram B Item Component Component Exam ExaminationAcceptance Total Required No. Examined Compliance Method Requirements Fig. No. Frequency Exam of Standard Population Examination Pressure Vessels (1) (3)
C3.10 Welded Attachments Applicable Surface IWC-2500-5 (2)(4)(6) IWC-3512 22 TBD Piping (1) (3)
C3.20 Welded Attachments Applicable Surface IWC-2500-5 (2)(4)(6) IWC-3512 83 TBD Pumps (1) (3)
C3.30 Welded Attachments Applicable Surface IWC-2500-5 (2)(4)(6) IWC-3512 14 TBD Valves C3.40 Welded Attachments NA to Unit 2* 0 TBD Totals Examination Category C-C 119 TBD NOTES:
(1) Examination is limited to those welded attachments 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-1 110; (c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component; and (d) the attachment weld is full penetration, fillet, or partial penetration, continuous, or intermittent.
(2) The extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination.
(3) Selected samples of welded attachments shall be examined each inspection interval.
(4) For multiple vessels of similar design, function, and service, only one welded attachment 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 associated with the component supports selected for examination under IWF-2510 shall be examined.
(6) Examination is required whenever component support member deformation, eg., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.
TBD = To be determined
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 45 of 101 Examination Category C-D, Pressure Retaining Bolting Greater than 2 in. in Diameter Tnsnection Proenram Bi Item No Component xmndCmlac Component ehd Exam Requirements Examination Frequency Extent andof Acceptance Total Required No. Examined Compliance Method Standard Population Examination Fig. No. Exam Pressure Vessels (1) (2)
All bolts or Volumetric studs at the IWC-3513 I C4.10 Bolts and Studs Applicable (5) IWC-2500-6 bolted (5) (16 bolts) TBD (5) ~~~~connection ()(6bls (4)
Piping (3)
C4.20 Bolts and Studs NA to Unit 2 - 0 TBD Pumps C4.30 Bolts and Studs NA to Unit 2 0 TBD Valves C4.40 Bolts and Studs NA to Unit 2 0 TBD Total Examination Category C-D I TBD NOTES:
(1) The examination may be performed on bolting in place under load or upon disassembly of the connection.
(2) The examination of bolting for vessels, pumps, or valves may be conducted on one vessel, one pump, or one valve among a group of vessels, pumps, or valves that are similar in design, size, function, and service. In addition, when the component to be examined contains a group of bolted connections 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) The examination of flange bolting in piping systems may be limited to one bolted connection among a group of bolted connections that are 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.
(5) When bolts or studs are removed for examination, surface examination meeting the acceptance standards of IWB-3515 may be substituted for volumetric examination.
TBD = To be determined
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 46 of 101 Examination Category C-F-i, Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping In cnorfinn Prnnrc m U 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)
C5. 10 Piping Welds > 3/8 in. Nominal Wall Thickness 100% of for Piping > NPS 4 each weld C5. 11 Circumferential Welds (> NPS 4) CSS Applicable Vol. & Sur. IWC-2500-7 requiring IWC-3514 286 23 CVCS Applicable Vol. & Sur. IWC-2500-7 exam IWC-3514 55* 0*
RHRS Applicable Vol. & Sur. IWC-2500-7 (4)(5)(6) IWC-3514 280 21 SIS Applicable Vol. & Sur. IWC-2500-7 IWC-3514 291 24 C5.20 Piping Welds > 1/5 in. nominal Wall Thickness 100% of for Piping > 2 and < NPS 4 each weld C5.21 Circumferential WeldsInjection)reuin (High Pressure Safety (I) requiring CVCS Applicable Vol. & Sur. IWC-2500-7 exam 1WC-3514 353 30 SIS Applicable Vol. & Sur. IWC-2500-7 (4)(5)(6) IWC-3514 283 22 100%of each weld C5.30 Socket Welds requiring CVCS Applicable Sur. IWC-2500-7 exam IWC-3514 358 30 SIS Applicable Sur. IWC-2500-7 (4)(5)(6) 1WC-3514 254 19 C5.40 Pipe Branch Connections of Branch Piping > 100% of NPS 2 each weld C5.41 Circumferential Weld requiring CVCS Applicable Sur. IWC-2500- exam IWC-3514 3 SIS Applicable Sur. 9,10,11,12&13 (4)(5) IWC-3514 8 Total Examination Category C-F-1 2171 171
- Piping wall less than 0.375"
II WBN-2 PSI REVISION 7 11 WATTS BAR UNIT- 2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 47 of 101 Examination Category C-F-I, Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping Inspection Program B NOTES:
(1) Requirements for examination of welds in piping 4 NPS 4 (DN 100) apply to PWR high pressure safety injection and auxiliary feedwater systems in accordance with the exemption criteria of IWC-1220.
(2) The welds selected for examination shall include 7.5%, but not less than 28 welds, of all dissimilar metal, austenitic stainless steel or high alloy welds not exempted by IWC-1220. (Some welds not exempted by IWC-1220 are not required to be nondestructively examined per Examination Category C-F-1. These welds, however, shall be included in the total weld count to which the 7.5% sampling rate is applied.) The examinations 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, austenitic stainless steel, or high alloy welds in each system (i.e., if a system contains 30% of the nonexempt welds, then 30% of the nondestructive examinations required by Examination Category C-F-I should be performed on that system);
(b) within a system, the examinations shall be distributed among terminal ends, dissimilar metal welds, and structural discontinuities [See Note (3)] prorated, to the degree practicable, on the number of nonexempt terminal ends, dissimilar metal welds, and structural discontinuities in that system; and (c) within each system, examinations shall be distributed between line sizes prorated to the degree practicable.
(3) Structural discontinuities include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees. reducers, flanges, etc., conforming to ANSI B16.9), and pipe branch connections and fittings.
(4) The welds selected for examination shall be reexamined in the same sequence, during subsequent inspection intervals over the service lifetime of the piping component, to the extent practical.
(5) For circumferential welds with intersecting longitudinal welds, surface examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting circumferential welds.
(6) For circumferential welds with intersecting longitudinal welds, volumetric examination ofthe longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting circumferential 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 of the welds and for that length of longitudinal weld within the circumferential weld examination volume.
(b) When longitudinal welds are specified but locations are unknown, or the existence of longitudinal welds is uncertain, the examination requirements shall be met for both transverse and parallel flaws within the entire examination volume of intersecting circumferential welds.
TBD = To be determined
WATTS BAR UNIT- 2 WBN-2 PSI REVISION 7 I1I IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 48 of 101 Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping InsDection Program 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)
C5.50 Piping Welds > 3/8 in. Nominal Wall Thickness 100% of for Piping > NPS 4 each weld C5.51 Circumferential Welds (1) requiring AFWS Applicable Vol. & Sur. IWC-2500-7 exam IWC-3514 16 2 FWS Applicable Vol. & Sur. IWC-2500-7 (4)(5)(6)(7) IWC-3514 277 27 MSS Applicable Vol. & Sur. IWC-2500-7 IWC-3514 138 I1 C5.60 Piping Welds > 1/5 in. nominal Wall Thickness 100% of for Piping >2 and < NPS 4 each weld C5.61 Circumferential Welds (I) AFWS Applicable Vol. & Sur. IWC-2500-7 requiring IWC-3514 171 13 exam (5)(6)(7)
C5.70 Socket Welds NA to Unit 2 - -
Connections of Branch Piping >
C5.80C.1 NPS Branch Pipe 2 Circumferential Weld (1)(4) NA to Unit 2 - -
Total Examination Category C-F-2 602 53
I I WBN-2 PSI REVISION 7 - 1 WATTS BAR UNIT- 2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 49 of 101 Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Inspection Program B NOTES:
(I) Requirements for examination of welds in piping _<NPS 4 (DN 100) apply to PWR high pressure safety injection and auxiliary Feedwater systems in accordance with the exemption criteria of]WC-1220.
(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 required to be nondestructively examined per Examination Category C-F-2. These welds, however, shall be included in the total weld count to which the 7.5% sampling rate is applied.) The examinations 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 carbon and low alloy steel welds in each system (i.e., if a system contains 30% of the nonexempt welds, then 30% of t[le nondestructive examinations required by Examination Category C-F-2 should be performed on that system);
(b) within a system, the examinations shall be distributed among terminal ends and structural discontinuities [see Note (3)] prorated, to the degree practicable, on the number of nonexempt terminal ends and structural discontinuities in that system; and (c) within each system, examinations shall be distributed between line sizes prorated to the degree practicable.
(3) Structural discontinuities include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers, flanges, etc., conforming to ANSI B16.9), and pipe branch connections and fittings.
(4) The welds selected for examination shall be reexamined in the same sequence, during subsequent inspection intervals 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 ultrasonic method for reflectors transverse to the weld length direction, except that circumferential welds with intersecting longitudinal weld shall meet Note (7).
(6) For circumferential welds with intersecting longitudinal welds, surface examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting circumferential welds.
(7) For circumferential welds with intersecting longitudinal welds, volumetric examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting circumferential 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 of the welds and for that length of longitudinal weld within the circumferential weld examination volume.
(b) When longitudinal welds are specified but locations are unknown, or the existence of longitudinal welds is uncertain, the examination requirements shall be met for both transverse and parallel flaws within the entire examination volume of intersecting circumferential welds.
TBD = To be determined
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 50 of 101 Examination Category C-G, Pressure Retaining Welds in Pumps and Valves Inspection Program B Item Component Component Exam Examination Extent and Acceptance Total Required No. Examined Compliance Method Requirements Frequency of Standard Population Examination Fig. No. Exam Pumps C6.10 Pumps Casing Welds NA to Unit 2 Valves (1)(2)(3)
C6.20 Valve Body Welds AFWS Applicable Surface IWC-2500-8 (4) IWC-3515 10 1 MSS Applicable Surface 1WC-250,r8 (4) IWC-3515 20 1 Total Examination Category C-G 30 NOTES:
(1) In case of multiple pumps or valves of similar design, size, function, and service in a systemn,required weld examinations may be limited to all the welds in one pump or one valve in the same group or distributed among any of the pumps or valves ofthat same group.
(2) The examination may be performed from either the inside or outside surface of the component.
(3) The pumps and valves initially selected for examination shall be reexamined in the same sequence over the service lifetime of the component, to the extent practical.
(4) 100% welds in all components in each piping run examined under Examination Category C-F, each inspection interval.
TBD = To be determined
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWD
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 51 of 101 SECTION 6.0 IWD
SUMMARY
TABLES for ASME CLASS 3 INDEX CATEGORY D-A, Welded Attachments for Vessels, Piping, Pumps and Valves ASME Section X1 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 further within the program plan, schedule or summary reports.
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 IWD
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 52 of 101 Examination Category D-A, Welded Attachments for Vessels, Piping, Pumps and Valves Inspection Program B Item Component Component Exam Examination Extent and No. Examined Compliance Method Requirements Frequency of Stance Potao Eqaired Fig. No. Exam Standard Population Examination Pressure Vessels (1)
D13.10 Welded Attachments Applicable VT-I IWD-2500-1 (2) (4)(5) IWD-3000 TBD TBD Piping (1)
D1.20 Welded Attachments Applicable VT-I IWD-2500-1 (2) (4)(5) IWD-3000 TBD TBD Pumps (I)
D1.30 Welded Attachments NA to Unit-2 Valves (I)
D1.40 Welded Attachments NA to Unit-2 Total Examination Category D-A TBD TBD NOTES:
(1) Examination is limited to those welded attachments 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-I 110; (c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component; and (d) the attachment weld is full penetration, fillet, or partial penetration, continuous, or intermittent.
(2) The extent of the examination includes essentially 100% of the length of the attachment weld at each attachment subject to examination.
(3) N/A to WBN-2 Preservice Examination (4) Examination is required whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.
(5) 100% of required area of each welded attachments, each inspection interval or each occurrence identified in note (4).
TBD = To be deteromined
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWF
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 53 of 101 SECTION 7.0 IWF
SUMMARY
TABLE For ASME CLASS 1, 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 Unit-2", this documents the item does not apply and will not be referenced further within the program plan, schedule or summary reports.
WBN-2 PSI REVISION 7 I WATTS BAR UNIT- 2 IWF
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 54 of 101 Examination Category F-A, Supports Inspection Program Examination" Item Component Exam Equinatiot Extent of Acceptance Total Required No. Support Types Examined Compliance Method Requirements Exam Standard Population Examination
_________ Fig. No.
F7.10 Class I Piping Supports (1) (2) Applicable VT-3 IWF-1300-1 (5) IWF-3410 TBD TBD F1.20 Class 2 Piping Supports (1) (2) Applicable VT-3 IWF-1300-1 (5) IWF-3410 TBD TBD FI.30 Class 3 Piping Supports (I) (2) Applicable VT-3 IWF-1300-1 (5) IWF-3410 TBD TBD Fl Supports Other Than Piping supports (I) Applicable VT-3 IWF-1300-1 (5) IWF-3410 TBD TBD Class 1, 2 and 3 F1.40 MC Supports NA to Unit-2 -
Total Examination Category F-A TBD TBD NOTES:
(1) Item numbers shall be categorized to identify support types by component support function (e.g., A = supports such as one directional rod hangers; B = supports such as multi-directional restraints; and C = supports that allow thermal movement, such as springs). Reference tables below for each type. This is established for future activities.
(2) The totals shall be comprised of supports from each system (such as Main Steam, Feedwater, 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) N/A to WBN-2 Preservice Inspection.
(4) N/A to WBN-2 Preservice Inspection.
(5) 100% of all supports not exempted TBD = To be determined
WBN-2 PSI REVISION 7 WATTS BAR UNIT - 2 IWF
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 55 of 101 CLASS I NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Examination Item 1 Exam Total Category Number Type & Description Method Number FI.10A Type A Supports Visual, VT-3 TBD (one directional restraints)
F-A, FI.10B Type B Supports Visual, VT-3 TBD Supports (multidirectional restraints)
Class I Type C Supports Piping FI.10C (thermal movement, i.e. variable or Visual, VT-3 TBD constant springs)
FI.J0D Type D Supports Visual, VT-3 TBD (Snubber Types)
Totals]F TBD CLASS I NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE SYS TypeA Type B ype C ype D Totals Sys Total % Req. Total % Req. Total % Req. Total % Req.
CVCS 100 100 100 100 RCS 12 100 12 3 100 3 9 100 9 13 100 13 37 37 RHRS 2 100 2 7 100 7 6 100 6 9 100 9 24 24 SIS 100 100 100 100
_ _ _ _001 1 _ 1 _ 1_TBD TBD TBD = To Be Determined
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWF
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 56 of 101 CLASS 2 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Examination Catgor Item Number Type & Description j Exam Mto Total jNme Ctgr NubrII Method Number FI.20A Type A Supports Visual, VT-3 TBD (one directional restraints)
F-A, F1.20B Type B Supports Visual, VT-3 TBD Supports (multidirectional restraints)
Class 2 Type C Supports Piping FI.20C (thermal movement, i.e. variable or Visual, VT-3 TBD constant springs)
F1.20D Type D Supports (Snubber Visual, VT-3 TBD Types)
Totalsil TBD CLASS 2 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE Sys Type A Type B Type C jD Totals Total % Req. Total % Req. Total % Req. Total % Req. Total AFWS 81 100 81 67 100 67 11 100 11 33 100 33 192 192 CSS 87 100 87 53 100 53 10 100 10 13 100 13 163 163 CVCS 100 100 100 100 FWS 100 100 100 100 MSS 17 100 17 1 100 1 13 100 13 28 100 28 59 59 RHRS 71 100 71 24 100 24 15 100 15 16 100 16 126 126 SIS 100 100 100 100 CCS 1 100 1 0 100 0 0 100 0 0 100 0 1 1 TBD TBD TBD = To Be Determined
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWF
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 57 of 101 CLASS 3 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Examination Item & De ti Exam Total Category Number I Type escrip Method Number F1.30A Type A Supports Visual, VT-3 159 (one directional restraints)
F-A, FI.30B Type B Supports Visual, VT-3 132 Supports (multidirectional restraints)
Class 3 Type C Supports Piping F1.30C (thermal movement, i.e. variable or Visual, VT-3 19 constant springs)
FI.30D Type D Supports Visual, VT-3 9 (Snubber Types)
Totals 319 CLASS 3 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE Sys Type A ype B Type C TypeD Totals Total % Req. Total % Reg. Total % Reg. Total % Req. Totals AFWS 25 100 25 10 100 10 3 100 3 0 100 0 38 38 CCS 60 100 60 38 100 38 8 100 8 8 100 8 114 114 ERCWS 74 100 74 84 100 84 8 100 8 1 100 1 167 167 FPCS 0 100 0 0 100 0 0 100 0 0 100 0 0 0 HPFPS 0 100 0 0 100 0 0 100 0 0 100 0 0 0 159 100 159 132 100 132 19 100 19 9 100 9 319 319
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 IWF
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 58 of 101 CLASS 1, 2 & 3 NON-EXEMPT SUPPORTS DISTRIBUTION BY TYPE CLASS 1, 2 & 3 NON-EXEMPT SUPPORTS DISTRIBUTION BY SYSTEM & TYPE Sys Type ____ Type C ype Dotals Sys Total % Req. Total % IReq. Total % Req. Total % Req.
100 100 100 100 I TBD TBD TBD = To Be Determined
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 AUGMENTED
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 59 of 101 SECTION 8.0 AUGMENTED EXAMINATION REGULATORY COMMITMENTS Letters from TVA to NRC:
- 1. WBN U2, Initial Response to Bulletins and Generic Letters, dated September 7,2007, ML072570676
- 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 20, 2008, ML082750518
- 3. WBN U2, Supplemental Information Regarding Certain NRC Generic Letters and Bulletins, dated April 1, 2010, ML100950044 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
- 1. (Attachment 3 of referenced letter I and Enclosure I of referenced 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(5)(b) of the First Revised Order EA-03-009.
- 2. (Attachment 5 of referenced letter 1) TVA will perform a baseline inspection (VT-2) of the lower head penetrations prior to fuel load.
- 3. (Attachment 6 of referenced letter 1, Enclosure 1 of referenced letter 2, and Enclosure 5 of referenced letter 3) WBN U2 will perform NDE 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 Bulletin 2004-01, TVA will develop plans to perform an adequate extent-of-condition evaluation, and TVA will discuss those plans with cognizant NRC technical staff prior to starting Unit 2.
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 AUGMENTED
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 60 of 101 Inservice Commitments
- 1. (Enclosure 1 of referenced letter 3) WBN U2 will perform inspections during the first refueling outage according to I0CFR50.55a(g)(6)(ii)(D)(2) through (6) and ASME Code Case N-729-1.
- 2. (Attachment 5 of referenced letter 1) WBN U2 will perform 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 Alloy 600 locations at the first refueling outage. If any evidence of apparent reactor coolant pressure boundary leakage is discovered during the BMV examination, then NDE capable of determining crack orientation will be performed in order to accurately characterize the flaw, the orientation, and extent. TVA will develop plans to perform an adequate extent of condition evaluation, and plans to possible expand the scope of NDE to other components in the pressurizer, which will be discussed with NRC technical staff prior to restarting Unit 2. TVA will provide the required response for inspections performed within 60 days after completion of the first refueling outage.
H. Other PSI/ISI commitments Preservice Commitment NCO080008099 - TVA plans to submit PSI related relief requests on or before September 24, 2010.
Inservice Commitment NCO080008038 - Submit Inservice Inspection (ISI) program within 6 months after receiving an operating license.
MI. Augmented PSI/IS1 Exam A. Ultrasonic examination of those areas identified in calculation package 110448.301, "MRP-146 Assessment of Normally 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 Inservice Intervals. Refer to PER 375365. Additional NDE qualification and training are required to perform these ultrasonic examinations. EXREQ is "AUGMRP" and Category is "146" in the PSI database.
WBN-2 PSI REVISION 7 WATTS BAR UNIT - 2 AUGMENTED
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLANPae 1 Of 01 Examination Category A-E, Augmented Examination - Preservice Commitment Class I PWR Components Containing Alloy 600/82/182 Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.I NRC letter RPV CRD Nozzle J-Groove welds EA 03-009 April I1, 78 78 Upper V p weld ( UT N/A Note 1 2003 1 Head Vent pipe J-Groove weld (revised)(ML030980322)
CRD Nozzle J-Groove welds EA 03-009 Wetted 78 78 Vent pipe J-Groove weld (revised) Surface N/A Surface of see above weld 1 1 RPV NRC Bulletin Area around Lower Instrumentation Nozzle Penetrations 2003-02 VT-2 N/A instrument No Leakage 58 58 Head nozzles Spray Nozzle-to-pipe connection NRC Bulletin Pre- and I I Pressurizer Releif/Safety Nozzle-to-pipe connection 2004-01 UT IWB-2500-8 Post- MSIP IWB-3514 4 4 Surge Nozzle-to-pipe connection I I Note I - Examine weld from 2" above the highest point of the root of the J-groove weld on a horizontal plane and from 2" below the toe of the J-groove weld on a horizontal plane.
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 62 of 101 SECTION 9.0 REQUESTS FOR RELIEF INDEX RFR Number Subject 10CFR50.55a Status Comments Alternative Examination Approved WBN-2/PDI-4 for RPV Shell-to -Flange 10CFR50.55a(a)(3)(i) 9/3/09 TAC No. ME0022 WBN-2/PSI-l Class I Component I OCFR50.55a(g)(5)(iii) Submitted to Under NRC review Examination Limitations NRC on 10/12/2010 WBN-2/PSI-2 ASMIE Section XI 2001 10CFR50.55a(a)(3)(i) Approved Edition through 2003 02/17/2011 Addenda Code of Record TAC No.
ME3113
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERWCE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 63 of 101 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI, REQUEST FOR RELIEF WBN-2/PDI-4 TVA requests approval for an alternative to ASME Section XI, paragraph IWA-2232 of the ASME Section XI 2001 Edition through the 2003 Addenda, for the Preservice Examinations at Watts Bar Unit
- 2. Specifically, for use of Appendix VIII and Performance Demonstration Initiative (PDI) methodologies for performance of the ultrasonic examination of reactor pressure vessel shell-to-flange welds in lieu of the requirement of Appendix I and the associated Article 4, ASME Section V EXECUTIVE
SUMMARY
In accordance with 10 CFR 50.55a(a)(3)(i), TVA is requesting relief from the specific requirements of performing the volumetric examination of the reactor pressure vessel (RPV) circumferential shel I-to-flange weld at Watts Bar Unit 2 in accordance with the requirement of Appendix I of Section XI. In lieu of the requirements of Appendix I and its associated sub-requirements of Article 4 of Section V, Watts Bar Unit 2 will use the techniques, personnel, and equipment qualified to meet the requirements of ASME Section XI Appendix VIII, Supplements 4 and 6 of the 2001 Edition through the 2003 Addenda, as administered by the Electric Power Research Institute's (EPRI) Performance Demonstration Initiative (PDI) processes. Watts Bar plans to use the proposed alternative for the Preservice RPV examinations to be performed prior to commercial operations. This proposed alternative represents the best available methodology in qualification of equipment and personnel performing ultrasonic examinations and uses an examination process that has provided and will provide the highest practical quality and greatest amount of coverage for the performance of the shell-to-flange weld examinations. As such, the proposed alternative methodology provides an acceptable level of quality and safety. In addition, the approval of this relief results in savings in the cost of performing the examinations, with not having to incorporate the use of two different sets of examination equipment, and also in future examination will results in lower personnel radiation exposure from not having to use a different methodology for the shell-to-flange weld.
Note that this request for relief is similar to the request granted to Watts Bar Unit 1 during the First and Second 10 Year Intervals submitted most recently in a letter from TVA to the NRC, dated February 7, 2007 and approved by the Staff in a letter dated February 28, 2008 (Ref. ML080630679).
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 64 of 101 SYSTEM/COMPONENT(S) FOR WHICH RELIEF IS REQUESTED:
ASME Code Class 1 Reactor Pressure Vessel (RPV) Upper Vessel Shell-to-Flange Welds, Table IWB-2500-1 Category B-A, Item Number B 1.30:
APPLICABLE CODE EDITION AND ADDENDA FOR THE GIVEN EXAM The applicable ASME section XI code edition and Addenda of Record for Watts Bar Unit 2 Preservice inspection is the 2001 Edition through 2003 Addenda with applicable amendments from 10CFR50.55a.
CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED:
In accordance with ASME Section XI, paragraph IWA-2232, "Ultrasonic examinations shall be conducted in accordance with Appendix I."
Further, in accordance with Appendix I, paragraph 1-2110(b) "Ultrasonic examination of reactor vessel-to-flange welds, closure head-to-flange welds, and integral attachment welds shall be conducted in accordance with Article 4 of Section V, except that alternative examination beam angles may be used."
RELIEF REOUESTED:
Pursuant to 10 CFR 50.55a(a)(3)(i), TVA requests relief from performing the designated vessel shell-to-flange weld examination in accordance with the requirements of ASME Section XI, paragraph IWA-2232, Appendix I, and the associated Article 4 of Section V methodology in accordance with paragraph 1-2110(b).
BASIS FOR RELIEF:
In accordance with ASME Section XI, Subarticle IWA-2232, TVA is required to perform ultrasonic examinations (UT) of the RPV upper shell-to-flange welds using Section XI, Appendix I, which in turn requires the use of the NDE methodologies and processes of ASME Section V, Article 4. In addition, the guidance of RG-1.150, Revision 1, was historically applied. The above listed weld is the only circumferential shell weld in the RPV that are not examined in accordance with the requirements of ASME Section XI, Appendix VIII, as mandated in 10 CFR 50.55a. This rule change mandated the use of ASME Section XI, Appendix VIII, Supplements 4 and 6 for the conduct of RPV examinations. It has been recently stated in EPRI PDI coordination meetings between the PDI committee members and the NRC Staff representatives that the NRC Staff expectations are that licensees should submit requests for relief to use the more technically advanced Appendix VIIIPDI processes for the shell-to-flange weld exams, in lieu of the Section XI Appendix I and its associated Section V, Article 4 processes.
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 65 of 101 PROPOSED ALTERNATIVES TVA proposes to use the procedures, personnel, and equipment qualified to meet the requirements of ASME Section XI Appendix VIII, Supplements 4 and 6 as administered by the Electric Power Research Institute's (EPR1) Performance Demonstration Initiative (PDI), to conduct the required vessel-to-flange weld examinations.
JUSTIFICATION FOR GRANTING RELIEF:
ASME Section V, Article 4, describes the required techniques to be used for the UT of welds in ferretic pressure vessels with wall thicknesses greater than 2 inches. The techniques were first published in ASME Section V in the 1974 Edition, summer 1975 Addenda. The calibration techniques, recording criteria and flaw sizing methods are based upon the use of a distance-amplitude-correction curve (DAC) derived from machined reflectors in a basic calibration block. UT performed in accordance with Section V, Article 4, used recording thresholds of 50 percent DAC for the outer 80 percent of the required examination volume and 20 percent DAC from the clad/base metal interface to the inner 20 percent margin of the examination volume. Indications detected in the designated exam volume portions, with amplitudes below these thresholds, were therefore not required to be recorded. Use of the Appendix VIHIPDI processes would enhance the quality of the examination results reported because the detection sensitivity is more conservative and the procedure requires the examiner to evaluate all indications determined to be flaws regardless of their associated amplitude. The recording thresholds in Section V, Article 4, requirements and in the guidelines of RG-1.150, Revision 1, are generic and somewhat arbitrary and do not take into consideration such factors as flaw orientation, which can influence the amplitude of UT responses.
The EPRI Report NP-6273, "Accuracy of Ultrasonic Flaw Sizing Techniques for Reactor Pressure Vessels," dated March 1989, established that UT flaw sizing techniques based on tip diffraction are the most accurate. The qualified prescriptive-based UT procedures of ASME Section V, Article 4 have been applied in a controlled process with mockups of RPVs which contained real flaws and the results statistically analyzed according to the screening criteria in Appendix VIII of ASME Section XI. The results show that the procedures in Section V, Article 4, are less effective in detecting flaws than procedures qualified in accordance with Appendix VIII as administered by the PDI processes. Appendix VIII/PDI qualification procedures use the tip diffraction techniques for flaw sizing. The proposed alternative Appendix VIIIJPDI UT methodology uses analysis tools based upon echo dynamic motion and tip diffraction criteria which has been validated, and is considered more accurate than the Section V, Article 4 processes.
UT performed in accordance with the Section V, Article 4 processes requires the use of beam angles of 00, 450, 600, and 70' with recording criteria that precipitates equipment changes. Having to perform these process changes is time consuming and results in increased radiation exposure for the examination personnel. Having to comply with the specific ASME Section XI, Appendix I requirements for the RPV circumferential shell-to-flange weld, when the data is obtained using a less technically advanced process, results in an examination that does not provide a compensating increase in quality and safety for the higher costs and personnel exposures involved.
For future RPV shell-to-flange weld examinations TVA does not anticipate any less coverage than the required minimum of 90 percent of coverage. However, if any such limitations are encountered during the conduct of the examinations, separate individual relief requests will be submitted, as needed.
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 66 of 101 Procedures, equipment, and personnel qualified through the Appendix VIII, Supplements 4 and 6 PDI programs have shown to have a high probability of detection of flaws and are generally considered superior to the techniques employed earlier for RPV examinations. This results in increased reliability of RPV inspections and conditions where an acceptable level of quality and safety is provided with the proposed alternative methodologies. Accordingly, approval of this alternative evaluation process is requested pursuant to 10 CFR 50.55a(a)(3)(i).
IMPLEMENTATION SCHEDULE AND DURATION:
Upon approval by the NRC staff, TVA will implement the provisions of this request for the Preservice Inspection for Watts Bar Unit 2.
PRECEDENTS Note that this request for relief is similar to the request granted to Watts Bar Unit 1 during the First and Second 10 Year Intervals submitted most recently in a letter from TVA to the NRC, dated February 7, 2007 and approved by the Staff in a letter dated February 28, 2008 (Ref. ML080630679).
WBN-2 PSI REVISION 7 I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 67 of 101 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF WBN-2 / PSI-1
SUMMARY
In accordance with 10 CFR 50.55a(g)(5)(iii), TVA is requesting relief from the "essentially 100%" code coverage required weld examination volume. This relief request addresses ASME Code Class 1 welds with the Examination Category and Item Numbers as specified in this relief request. The examination limitations described in this relief request are inherent to the component design and manufacture of the installed components given the original construction permit date for WBN Unit 2 of January 23, 1973.
NRC Information Notice 98-42, "Implementation of 10 CFR 50.55a(g) Inservice Inspection Requirements," defined "essentially 100%" as "more than 90 percent of the specified examination volume." In Code Case N-460, "Alternative Examination Coverage for Class I and Class 2 Welds,Section XI, Division 1," the ASME provided the same definition.
1.0 SYSTEM/COMPONENTS FOR WHICH RELIEF IS REQUESTED The Class 1 components for which relief is requested are listed in Table I along with information related to materials of construction, configuration and NDE results.
2.0 APPLICABLE CODE EDITION AND ADDENDA The applicable ASME Section XI Code Edition and Addenda for Watts Bar Unit 2 preservice inspection is the 2001 Edition through 2003 Addenda as amended by 10 CFR 50.55a.
3.0 CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED In accordance with 10 CFR 50(g)(5)(iii), relief is requested from the extent of examination requirements of "essentially 100%" for the following examination categories and item numbers:
B-A, B 1.40 (note 2); B-J, B9.11 (note 4); B-J, B9.22 (note 4); and B-J, B9.31 (note 4). This relief request is applicable to the ultrasonic examination method associated with the subject examination categories and item numbers.
WBN Unit 2 has invoked ASME Section XI Code Case N-460, "Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1." Code Case N-460 states, in part, "...when the entire examination volume or area cannot be examined.. .a reduction in examination coverage.. .may be accepted provided the reduction in coverage for that weld is less than 10%."
WBN-2 PSI REVISION 7 I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 68 oflO1 4.0 BASIS FOR RELIEF In accordance with 10 CFR 50.55a(g)(5)(iii), relief is requested on the basis that the Code required "essentially 100%" examination coverage is impractical due to physical obstructions and limitations imposed by design, geometry, and/or physical obstructions for the welds and associated components listed in Table 1.
ASME Section XI, IWB-2200, "Preservice Examination" requires that "...preservice examination be extended to include essentially 100% of the pressure retaining welds in all Class 1 components...";
therefore, no alternate Class 1 welds are available for selection. Compliance with the examination requirements of ASME Section XI would require significant modification of plant components to remove obstructions, redesign of plant systems/components, and/or replacement of components where geometry is inherent to the component design.
Weld profile sketches and coverage plots are included in the nondestructive examination (NDE) reports attached to this relief request for the applicable welds in Table 1.
5.0 PROPOSED ALTERNATIVES WBN Unit 2 performed the ASME Section XI Code required preservice volumetric examinations listed in Table I to the maximum extent possible utilizing qualified/certified personnel and approved procedures.
For Examination Category B-J piping welds listed in Table 1, the examination personnel and equipment were required to meet Appendix VIII requirements as implemented by the Electric Power Research Institute (EPRI) Performance Demonstration Initiative (PDI) and mandated by 10 CFR 50.55a. The shear wave examination of the applicable stainless steel welds listed in Table 1, where access was limited to one-side and the piping thickness is greater than 0.500", were also supplemented by a refracted longitudinal wave examination. For those welds in Table 1, where access was limited to one-side and the piping thickness is 0.500" or less, a supplemental 70' shear wave was performed.
For the Examination Category B-A RPV head-to-flange weld, W08-09, listed in Table 1, the examination personnel and equipment were required to meet Article 4 of Section V, except that alternative examination Beam angle: s may be used, as specified in ASME Section XI, Mandatory Appendix I, 1-2110(b). The Article 4,Section V examination was supplemented with an Appendix VIII qualified examination; however, no additional coverage was achieved or credited based on the Appendix VIII supplemental examination.
6.0 JUSTIFICATION FOR GRANTING RELIEF The welds listed in Table 1 were examined to the maximum extent possible utilizing qualified/certified personnel, qualified equipment, and approved procedures to meet the preservice acceptance standards of ASME Section XI 2001 Edition through 2003 Addenda.
Surface conditioning of the subject welds was performed to the extent necessary to preclude a reduction in coverage associated with weld crowns, weld shrinkage, and/or surface roughness.
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESER VICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 69 of 101 Welds SIF-D 199-05 and SIF-D 199-06 had recordable root geometry identified by volumetric examination. Weld SJF-D197-05 had a recordable, but acceptable surface indication 1/8" in length located on the outside diameter valve side at the weld toe identified by surface examination. These three welds have not been in service and were acceptable to the construction code standards for installation. The examinations performed on these welds for both construction code and the limited coverage preservice examination, greater than 70% coverage minimum, are sufficient to ensure structural adequacy of the subject welds.
These welds also met the ASME Section III NDE acceptance criteria associated with construction, which for Class I butt welds requires radiography. The construction code radiography, while providing additional assurance of the structural integrity of the subject welds, is not qualified in accordance with ASME Section XI, Appendix VIII, and cannot be credited for ASME Section XI coverage. Additionally, the welds listed in Table 1 will be subjected to an ASME Section III pressure test prior to initial plant startup.
The proposed alternative volumetric examination will provide reasonable assurance that unallowable inservice flaws have not developed in the subject welds or that they will be detected and repaired prior to return of the reactor vessel to service. Thus an acceptable level of quality and safety will have been achieved and public health and safety will not be endangered by allowing the proposed alternative examination in lieu of the Code requirement.
7.0 IMPLEMENTATION SCHEDULE AND DURATION Upon approval by the NRC staff, TVA will implement the provisions of this relief request for the Preservice Inspection of Watts Bar Unit 2.
WBN-2 PSI REVISION 7 I WATTS BAR UNIT- 2 Request for Relief PRESERVlCE INSPECTION PROGRAM PLAN Page 70 of 101 TABLE 1 - ASME CODE CLASS 1 COMPONENTS System / Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information RCS / SA-351 CF-8A B-J / B9.11 27.5"/ R-P0147 75% Beam angle: 450 refracted longitudinal RCF-C2-2 (pipe and pump) 2.21" Transducer Size: .5"xl.0" Limitation upstream due to pump housing configuration.
NRI* (PT NRI*)
RCS / SA-351 CF-8A B-J / B9.11 27.5"/ R-P0149 75% Beam angle: 450 refracted longitudinal RCF-C3-2 (pipe and pump) 2.21" Transducer Size: .5"xl.0" Limitation upstream due to pump housing configuration.
NRI* (PT NRI*)
RCS / SA403 WP304 B-J / B9.11 4" /0.531" R-P0228 90% Beam angle: 1) 450 shear and 2) 700 shear RCF-D 145-05 (tee and reducer) Transducer Size: 1) .250" and 2) .250" Limitation due to tee and reducer configuration.
NRI* (PT NRI*)
RCS / SA-403 WP304 / B-J/ B9.11 4" /0.531" R-P0226 50% Beam angle: 1) 450 shear and 2) 600 refracted RCF-D145-08 SA-182 F316 longitudinal (elbow/valve) Transducer Size: 1) .250" and 2) dual 8xl4mm Limitation due to valve body taper.
NRI* (PT NRI*)
RCS I SA-351 CF-8A B-J/B9.11 31" /2.48" R-P0152 75% Beam angle: 450 refracted longitudinal RCF-G I-4 (pipe and pump) Transducer Size: .5"xl.0" Limitation downstream due to pump housing configuration.
NRI* (PT NRI*)
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 71 of 101 TABLE I - ASME CODE CLASS I COMPONENTS System / Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information RCS / SA-351 CF-8A B-J / B9.11 31" /2.48" R-P0156 75% Beam angle: 450 refracted longitudinal RCF-G2-4 (pipe and pump) Transducer Size: .5"xl .0" Limitation downstream due to pump housing configuration.
NRI* (PT NRI*)
RCS I SA-351 CF-8A B-J / B9.11 31" /2.48" R-P0150 75% Beam angle: 450 refracted longitudinal RCF-G3-4 (pipe and pump) Transducer Size: .5"xl.0" Limitation downstream due to pump housing configuration.
NRP* (PT NRI*)
RCS / SA-351 CF-8A B-J / B9.11 31" /2.48" R-P0155 75% Beam angle: 450 refracted longitudinal RCF-G4-4 (pipe and pump) Transducer Size: .5"xl.0" Limitation downstream due to pump housing configuration.
NRI* (PT NRI*)
RCS / SA-351 CF-8A / B-J / B9.31 6" / R-P0101 50% Beam angle: 450 refracted longitudinal RCS-1-6 SA-182 F316 2.33"** Transducer Size: .5"xL.0" (pipe/branch) Limitation from branch connection side due to configuration.
NRI* (PT NRI*)
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 72 of 101 TABLE 1 - ASME CODE CLASS 1 COMPONENTS System / Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information RCS / SA-35 1 CF-8A / B-J / B9.31 6" / R-PO 105 50% Beam angle: 450 refracted longitudinal RCS-2-6 SA- 182 F316 2.33"** Transducer Size: .5"xl.0" (pipe/branch) Limitation from branch connection side due to configuration.
NRI* (PT NRI*)
RCS / SA-351 CF-8A / B-J / B9.31 6" / R-P0106 50% Beam angle: 450 refracted longitudinal RCS-3-6 SA-182 F316 2.33"** Transducer Size: .5"xl.0" (pipe/branch) Limitation from branch connection side due to configuration.
NRI* (PT NRP*)
RCS / SA-351 CF-8A / B-J / B9.31 4" R-P0107 46% Beam angle: 1) 450 shear and 2) 600 refiracted RCW-01 SA-182 F316 2.21"** longitudinal (pipe/branch) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from pipe side due to configuration.
NRI* (PT NRI*)
RCS / SA-351 CF-8A / B-J/ B9.31 4" / R-P0108 41% Beam angle: 1) 450 shear and 2) 600 refracted RCW-02 SA- 182 F316 2.21"** longitudinal (pipe/branch) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from pipe side due to configuration NRI* (PT NRI*)
WBN-2 PSI REVISION 7 II WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 73 of 101 TABLE 1 - ASME CODE CLASS 1 COMPONENTS System / Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information RHRS / SA-403 WP316 / B-J / B9.11 14" / R-P0689 76% Phased array 250 to 700 shear wave sector RHRF-D031-04 SA-182 F316 1.250" (16 element probe) and 400 to 700 refracted (tee/valve) longitudinal wave sector (15 element probe supplemental)
Limitation due to valve to tee configuration.
NRI* (PT NRI*)
RHRS / SA-376 TP316 / SA- B-J / B9.11 14"! R-P0766 83% Phased array 250 to 700 shear wave sector RHRF-D031-13 182 F316 1.250" (16 element probe) and 400 to 700 refracted (pipe/valve) longitudinal wave sector (15 element probe supplemental)
Limitation due to valve to tee configuration.
NRP* (PT NRI*)
RHRS / SA-403 WP316 / B-J / B9.11 10" / 1.00" R-P0767 90% Phased array 250 to 700 shear wave sector RHRF-D031-14 SA- 182 F316 (16 element probe) and 400 to 700 refracted (elbow/valve) longitudinal wave sector (15 element probe supplemental)
Limitation due to valve to elbow configuration.
NRI* (PT NRI*)
RHRS / SA-403 TP316 / SA- B3 / B9.11 10" / 1.00" R-P0759 88% Phased array 250 to 700 shear wave sector RHRS-015 403 WP316 (16 element probe)
(pipe/tee) Limitation from tee side configuration NRI* (PT NRI*)
PSI REVISION 7 ReuN-2 II WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 74 of 101 TABLE 1 - ASME CODE CLASS 1 COMPONENTS System / Materials Category/ Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information RPV / SA-508 C12 B-A / B 1.40 173" R-PI014 75% Beam angle: 1) 00 longitudinal 2) 450 shear and 3)
W08-09 (ring and flange) 7.30" 600 shear, Transducer Size: 1) 1", 2) .5" x 1.0", and
- 3) .5" x 1.0" Limitations from the flange profile configuration and three lifting lugs (4.0" tall x 5.9" length each and have a 12.8" arc length in contact with RPV head) see attached sketch NRI* (PT NRI*)
SIS / SA-376 TP304 / SA- B-J / B9.22 1.5" / R-P0590 50% Phased array 350 to 800 shear wave sector (8 SIF-B-T076-06 182 F316 0.281" element probe), Limitation from flange side (pipe/flange) configuration NRT* (UT only)
SIS / SA-376 TP304 / SA B-J / B9.22 1.5" / R-P0591 50% Phased array 350 to 800 shear wave sector (8 SIF-B-T076-23 182 F316 0.281" element probe), Limitation from flange side (pipe/flange) configuration NRI* (UT only)
SIS / SA-376 TP304 / B-J / B9.22 1.5" / R-P0650 75% Phased array 350 to 800 shear wave sector (8 SIF-B-T077-01 SA-403 WP304 0.281" element probe), Limitation from tee side (pipe/tee) configuration NRI* (UT only)
SIS / SA-376 TP304 / SA- B-J / B9.22 1.5"/ R-P0588 50% Phased array 350 to 700 circ/80 0 axial shear wave SIF-B-T095-01 182 F316 0.281" sector (8 element probe), Limitation from branch (pipe/nozzle) side configuration NRI* (UT only)
SIS / SA-376 TP304 / SA- B-I / B9.22 1.5" / R-P0589 50% Phased array 350 to 700 circ/800 axial shear wave SIF-B-T097-13 182 F316 0.281" sector (8 element probe)
(pipe/flange) Limitation from flange side configuration NRI* (UT only)
WBRq-2 PSI REVISION 7 I WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 75 Of 101 TABLE 1 - ASME CODE CLASS 1 COMPONENTS System / Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information SIS / SA-376 TP304 / SA- B-J / B9.22 1.5" / R-P0646 50% Phased array 350 to 800 shear wave sector (8 SIF-B-T 107-04 182 F316 0.281" element probe)
(pipe/flange) Limitation from flange side configuration NRI* (UT only)
SI1 / SA-376 TP304 / SA- B-J / B9.22 1.5"! R-P0649 50% Phased array 350 to 800 shear wave sector (8 S1F-B-T107-05 182 F316 0.281" element probe)
(pipe/flange) Limitation from flange side configuration NRI* (UT only)
SIS / SA-376 TP304 / SA- B-J / B9.22 1.5" / R-P0647 75% Phased array 350 to 800 shear wave sector (8 SIF-B-T107-26 182 F316 0.281" element probe)
(pipe/nozzle) Limitation from branch side configuration NRI* (UT only)
SIS / SA-376 TP304 / SA- B-J / B9.22 1.5" / R-P0651 49% Phased array 350 to 800 shear wave sector (8 SIF-B-T142-01 182 F316 0.281" element probe)
(pipe/nozzle) Limitation from branch side configuration NRI* (UT only)
SIS / SA-376 TP304 / SA- B-J / B9.22 1.5"! R-P0648 71% Phased array 350 to 800 shear wave sector (8 SIF-B-T !54-01 182 F316 0.281" element probe)
(pipe/nozzle) Limitation from branch side configuration NRI* (UT only)
SIS / SA-376 TP304 / SA- B-J / B9.22 3" / 0.281" R-P0508 70% Beam angle: 1) 450 shear and 2) 700 shear SIF-D193-03 182 F316 Transducer Size: 1) .250" and 2) .250" (pipe/valve) Limitation from valve side due to configuration NRI* (UT only)
WBN-2 PSI REVISION 7 WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 76 of 101 TABLE 1 - ASME CODE CLASS 1 COMPONENTS System / Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information SIS / SA-376 TP316 / SA- B-J / B9.11 10"/ 1.00" R-P0437 68% Phased array 250 to 700 shear wave sector SIF-D196-03 182 F316 (16 element probe) and 400 to 700 refracted (pipe/valve) longitudinal wave sector (15 element probe supplemental)
Limitation due to valve to elbow configuration NRI* (PT NRI*)
SIS / SA-376 TP316 / SA- B-J / B9.11 10" 1.00" R-P0472 73% Beam angle: 1) 450 shear and 2) 700 refracted SIF-D196-05 182 F316 longitudinal (pipe/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRP* (PT NRI*)
SIS/ SA403 WP316 / B-J / B9.11 10" /1.00" R-P0486 75% Phased array 250 to 700 shear wave sector SIF-D196-06 SA- 182 F316 (16 element probe) and 400 to 700 refracted (tee/valve) longitudinal wave sector (15 element probe supplemental)
Limitation due to valve to tee configuration NPJ* (PT NRI*)
SIS / SA-403 WP316 / B-J / B9.11 6" / 0.719" R-P0440 73% Beam angle: 1) 450 shear and 2) 700 refracted SIF-D 196-07 SA- 182 F316 longitudinal (elbow/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT NRI*)
W13N-2 PSI REVISION 7 II WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 77 of 101 TABLE I - ASME CODE CLASS 1 COMPONENTS System / Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information SIS / SA-376 TP316 / SA- B1J / B9.11 10"/ 1.00" R-P0487 73% Phased array 250 to 700 shear wave sector SIF-D196-10 182 F316 (16 element probe) and 400 to 700 refracted (pipe/valve) longitudinal wave sector (15 element probe supplemental)
Limitation from valve side due to configuration NRI* (PT NRI*)
SIS / SA403 WP316 / BJ / B9.11 10" 1.00" R-P0488 75% Phased array 250 to 700 shear wave sector SIF-D 196-11 SA-182 F316 (16 element probe) and 400 to 700 refracted (elbow/valve) longitudinal wave sector (15 element probe supplemental)
Limitation from valve side due to configuration NRI* (PT NRI*)
SIS / SA-376 TP316 / SA- BJ / B9.11 10" 1.00" R-P0304 75% Phased array 250 to 700 shear wave sector SIF-D 197-03 182 F316 (16 element probe) and 400 to 700 refracted (pipe/valve) longitudinal wave sector (15 element probe supplemental)
Limitation from valve side due to configuration NRI* (PT NRI*)
SIS / SA403 WP316 / B-J / B9. 11 10" /1.00" R-P0287 73% Beam angle: 1) 450 shear and 2) 700 refracted SIF-D197-05 SA- 182 F316 longitudinal (tee/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT - 1/8" recordable linear)
WBN-2 PSI REVISION 7 I WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 78 of 101 TABLE 1 - ASME CODE CLASS I COMPONENTS System / Materials Category/ Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information SIS / SA-376 TP316 / SA- B- / B9.11 10" / 1.00" R-P0306 74% Beam angle: 1)450 shear and 2) 700 refracted SIF-D197-08 182 F316 longitudinal (pipe/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT NRI*)
SIS / SA-403 WP316 / B-J / B9.11 10" / 1.00" R-P0305 74% Beam angle: 1) 450 shear and 2) 700 refracted SIF-D 197-09 SA- 182 F316 longitudinal (elbow/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT NRI*)
SI1 / SA-376 TP316 / SA- B-J / B9.11 6" / 0.719" R-P0620 50% Phased array 250 to 700 shear wave sector SIF-D197-11A 182 F316 (16 element probe) and 400 to 700 refracted (pipe/valve) longitudinal wave sector (dual element probe)
Limitation from valve side due to configuration NRI* (PT NRI*)
SIS / SA-376 TP316 / SA- B-J / 89.11 10" 1.00" R-P0348 75% Phased array 250 to 700 shear wave sector SIF-D198-03 182 F316 (16 element probe) and 400 to 700 refracted (pipe/valve) longitudinal wave sector (15 element probe supplemental)
Limitation from valve side due to configuration NRI* (PT NRI*)
WBN-2 PSI REVISION 7 II WATTS BAR UNIT - 2 Request for Relief PRESER VICE INSPECTION PROGRAM PLAN Page 79 Of '101 TABLE 1 - ASME CODE CLASS 1 COMPONENTS System / Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information SIS/ SA-376TP316/SA- B-J/B9.11 10"/1.00" R-P0341 75% Beam angle: 1) 450 shear and 2) 700 refracted SIF-D198-04 182 F316 longitudinal (pipe/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT NRI*)
S1S/ SA-403 WP316/ B-J /B9.11 10" /1.00" R-P0344 75% Beam angle: 1) 450 shear and 2) 700 refracted SIF-D198-05 SA-182 F316 longitudinal (tee/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT NRI*)
SIS / SA-403 WP316 / B-J / B9.11 6" / 0.719" R-P0349 75% Beam angle: 1) 450 shear and 2) 700 refracted SIF-D1398-06 SA-182 F316 longitudinal (elbow/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT NRI*)
SIS/ SA-403 WP316/ B-J / B9.11 10"/1.00" R-P0343 75% Beam angle: 1) 450 shear and 2) 600 refracted SIF-D 198-10 SA- 182 F316 longitudinal (elbow/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT NRI*)
WBN-2 PSI REVISION 7 iI WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 80 of 101 TABLE 1 - ASME CODE CLASS 1 COMPONENTS System I Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information SIS / SA-403 WP316 / B-J / B9.11 10" /1.00" R-P0434 57% Beam angle: 1)450 shear and 2) 700 refracted SIF-D199-03 SA-182 F316 longitudinal (elbow/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT NRI*)
SIS / SA-376 TP316 / SA- B-J / B9.11 10" /1.00" R-P0369 74% Phased array 250 to 700 shear wave sector SIF-D199-05 182 F316 (16 element probe) and 400 to 700 refracted (pipe/valve) longitudinal wave sector (15 element probe supplemental)
Limitation from valve side due to configuration.
Recordable root geometry 3600 at varying amplitude.
(PT NRI*)
SIS / SA-403 WP316 / B-J / B9.11 I10" 1.00" R-P0370 75% Phased array 250 to 700 shear wave sector SIF-D 199-06 SA- 182 F316 (16 element probe) and 400 to 700 refracted (tee/valve) longitudinal wave sector (15 element probe supplemental)
Limitation from valve side due to configuration.
Recordable root geometry 3600 at varying amplitude.
(PT NRI*)
WBN-2 PSI REVISION 7 I WATTS BAR UNIT- 2 Request for Relief PRESERVICE INSPECTION PROGRAM PLAN Page 81 of 101 TABLE I - ASME CODE CLASS 1 COMPONENTS System / Materials Category / Dia. / Report Limited Component ID (Configuration) Item No. Thk. Number Scan % Additional Information SIS / SA-403 WP316 / BJ / B9.11 6" / 0.719" R-P0405 70% Beam angle: 1) 450 shear and 2) 700 refracted SIF-D199-07 SA- 182 F316 longitudinal (elbow/valve) Transducer Size: 1) .375" and 2) dual 8xl4mm Limitation from valve side due to configuration NRI* (PT NRI*)
SIS / SA-376 TP316 / SA- B-J I B9.11 10" 1.00" R-P0382 73% Phased array 250 to 700 shear wave sector SIF-D199-10 182 F316 (16 element probe) and 400 to 700 refracted (pipe/valve) longitudinal wave sector (15 element probe supplemental)
Limitation from valve side due to configuration.
NRI* (PT NRI*)
SIS/ SA-403 WP316 / B-J / B9.11 10" / 1.00" R-P03 83 73% Phased array 250 to 700 shear wave sector SIF-D 199-I1 SA- 182 F316 (16 element probe) and 400 to 700 refracted (elbow/valve) longitudinal wave sector (15 element probe supplemental)
Limitation from valve side due to configuration.
NRI* (PT NRI*)
SIS / SA-403 WP316 B-i / B9.11 6" / 0.719" R-P0491 61% Phased array 250 to 700 shear wave sector SIF-D199-15 (tee and elbow) (16 element probe) and 400 to 700 refracted longitudinal wave sector (15 element probe supplemental)
Limitation from tee side due to configuration.
NRI* (PT NRI*)
- NRI: No Recordable Indications
- Nominal wall thickness is given from the piping side of a branch connection
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESER VICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 82 of 101 RPV Head Lifting Lug Sketch 4 /
4 /
~~ A I
I.,i AR14ETIWIN EN "OS Tlf. W Wadt A00 SKI, K r
(3/4 04 0%(e& to!
e- *TRw WiLciwo rr amALL i MrBIAbiL wui~oo Aimc 110CM TWt ICNs Lb IRA Nf7 LIppti copLrLIUN' 0F. UE- RerIPNADRIr vE I usDRAM 01 FIJ%4D VFLIII1*4 TOPALM& sMa@YH14V WNTOI2Tb3 A&CRjS
" "'"= ... .N'.=:
L I
li I.._ d, V.
LIF LTING LUG DETAILS
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 83 of 101 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) SECTION XI REQUEST FOR RELIEF WBN-2/PSI-2 TVA requests approval to use the 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 construction was resumed on WBN Unit 2.
EXECUTIVE
SUMMARY
In accordance with 10 CFR 50.55a(a)(3)(i), TVA is requesting relief to utilize a later Code of Record for PSI activities during the WBN Unit 2 construction completion project. 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 Construction Permit. The applicable Code would have been the 1971 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.
SYSTEM/COMPONENTS FOR WHICH RELIEF IS REQUESTED:
ASME Code Class 1, 2, 3, IWF, and MC components including the applicable Examination Categories and Item Numbers.
APPLICABLE CODE EDITION AND ADDENDA FOR THE GIVEN EXAM:
The ASME Section XI Code Edition and Addenda code of record requested for the WBN Unit 2 construction completion project preservice examination (PSI) is the 2001 Edition through 2003 Addenda as limited and/or amended by the rules of 10 CFR 50.55a and those Code Cases either approved for use by Regulatory Guide 1.147 and adopted by WBN Unit 2 or where specific relief has been requested and granted by NRC.
REQUIREMENTS FROM WHICH RELIEF IS REQUESTED:
Permission is requested to adopt a later NRC approved Code Edition and Addenda as provided in 10 CFR 50.55a(g)(2).
RELIEF REOUESTED:
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 Construction Permit.
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 84 of 101 The applicable Code would have been the 1971 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 50.5 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.
BASIS FOR RELIEF:
The resumption of construction activities at WBN Unit 2 associated with the construction completion project resulted in an a span of approximately 35 years since the initial construction permits were issued.
This 10 CFR 50.55a(g)(2) requirement for determining the PSI code of record would have allowed the use of the 1971 Edition though Winter 1971 (71/W71) Addenda of ASME Section Xl; however, the provision in 10 CFR 50.55a(g)(2) to allow the use of subsequent Code Editions/Addenda which are incorporated by reference in 10 CFR 50.55a(b)(2) allows the use of a technically superior PSI Code of Record based on 30 years of ASME Code committee knowledge and revisions. For example Class MC, metal containment, examination was not required in the 71 /W71 Section XI code, but it is a requirement of Subsection IWE of the 2001 Edition through 2003 Addenda of ASME Section XI.
PROPOSED ALTERNATIVES:
Utilize the 2001 Edition through 2003 Addenda of ASME Section XI for WBN Unit 2 construction completion activities subject to the modifications and limitations imposed by 10 CFR 50.55a.
JUSTIFICATION FOR GRANTING RELIEF:
The 2001 Edition through 2003 Addenda of ASME Section XI was approved for use in 10 CFR 50.55a(b)(2) and 10 CFR 50.55a(g)(2) allows the use of subsequent Code Editions/Addenda which are incorporated by reference in 10 CFR 50.55a(b)(2). See excerpt from the 2008 CFR which was in effect at the time of resumption of WBN Unit construction activities:
(2) As used in this section, references to Section XW of the ASME Boiler and Pressure Vessel Code refer to Section X9, and include the 1970 Edition through the 1976 Winter Addenda, and the 1977 Edition (Division 1) through the 2003 Addenda (Division 1), subject to thefollowing limitations and modifications:
The 2001 Edition through 2003 Addenda of ASME Section XI incorporates 30 years of technical lessons learned when compared to the 1971 Edition through Winter 1971 Addenda of the ASME Section XI Code.
IMPLEMENTATION SCHEDULE AND DURATION:
This relief will be utilized for the duration of PSI activities associated with the WBN Unit 2 construction completion project.
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 85 of 101 SECTION 10.0 ASME SECTION XI TECHNICAL POSITIONS Technical determination made during implementation of this PSI program and/or the examinations to clarify a position that is not clearly understandable or exclusive to Watts Bar Unit 2 from the referenced requirements. Each Technical Position should be numbered (l,2,3,ect.)
and reference to the corresponding paragraph in this or any other document that the subject pertains to and signed by as a minimum the program owner and a technical person, if appropriate and inserted in its entirety into this section following the next revision,.
TP Number Subject Reference Comments Basis for Section XI Section XI Class 1 May be used for all Section XI TP-S Boundary C lass activities or individually as stated in Identification the TP.
TP-2 Retrieval of Historical Records May be used for retrieval of Shop Records and Management Radiograph and other records Radiographs Lifetime Storage Vault.
TP-3 Watts Bar Unit I and 2 Section XI R/R Process to follow and document Memorandum of activities for Unit 2 ASME Section XI work on portions Understanding, ASME of Unit 2 systemsSection XI Interface
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 86 of 101 Basis for Section XI Boundary Identification Watts Bar Nuclear (WBN) Unit 2 ASME Section XI Preservice Inspection (PSI)
TP-1 This document is a technical position to establish the basis of the interrelationships with TVA classification 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 1, 2 and 3 respectively, based on the relationship between the ANS Safety Class, TVA classifications, and Regulatory Guide 1.26 classifications. The Mechanical flow diagrams are labeled with the TVA 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 TVA classification A, B, C and D to establish the ASME Class 1, 2 or 3 boundaries to determine 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 1, 2 and 3 components.
ASME Section XI, IWA-1320 states the rules 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 of WB-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 determined for ASME Class 1, 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.
- 1) 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 D or 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
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 87 of 101 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 XI.
Red will be used to represent TVA Safety Class A or ASME Code Class 1. Yellow will be used to represent TVA Safety Class B or ASME Code Class 2 and finally green to represent TVA Safety Class C
& D or 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 NGDC 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 IWA-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 III Class 2 or 3 and/or Class 3 to Class 2, Class 2 to Class I 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-I-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 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 is not needed prior to startup as explained in NGDC 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 there of. All other boundaries on safety Class systems that represent the activities associated with Section XI are to enhance and distinguish the various examination
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 88 of 101 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 1, 2 & 3 components are the same as previously established. 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 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 of WBN-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
WBN-2 PSI REVISION 7 I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 89 of 101 Basis for Retrieval of Historical Records and Radiographs Watts Bar Nuclear (WBN) Unit 2 ASME Section XI Preservice Inspection (PSI)
TP-2 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 radiographs, 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-144. Enter as E28821C 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-E2882-1300. Enter as E2882-1300
- 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 number 42
- 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: E. Lynn McClain 10/13/2009 Program Owner: E. Lynn McClain 10/13/2009 Technical Review: M. Darlene Tinley 10/13/2009
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 90 of 101 TP-3 Watts Bar Unit I and 2 Memorandum of Understanding ASME Section Xl Interface WBN Unit I systems were completed and licensed under the requirements of the ASME Section III program and since then, ASME Section XI has been Implemented. Portions of several Unit 2 systems were documented on Unit 1 ASME N-5 Code Dats Reports as being within the Unit I ASME boundary but are not within the operational boundary for Unit I.
Boundary calculations and design output (i.e., Unit 2 cross hatching) shows these portions of systems as under unit 2 configuration control. As a result of how these portions of systems were installed and documented, work that needs to be performed in these areas to startup unit 2 will have to be performed to ASME Section:Xl. Returning these portions of systems to ASME Section III is not an option due to the potential impact on the Unit I ASME programs and potential delay to Unit 2.
The-following process will be followed to perform and document ASME Section Xi work on portions of Unit 2 systems outside of the Unit I operating boundary that are documented in Unit I ASME N-5 packages.
" Work will be performed In accordance with the Unit I ASME Section XI requirements a Configuration control will be under the Unit 2 programs, procedures, and processes.
- Changes outside the Unit I operating boundary will be Issued and Implemented by Bechtel using the Unit 2 Work Order process and EDCRs as needed.
- Work will be planned and performed using the Unit 2 Work Order (WO) process which Invokes the requirements of SPP-9.1, TI-100.014, and MMDP-10.
" Bechtel Is designated as the Repair/Replacement organization In accordance with SPP-9, 1, Section 3.5.1.
" WO'. will be reviewed and approved by Bechtel QA, Unit 1 Welding and the ASME Section Xl Coordinator.
e Planned WO'e will be reviewed by.the Unit I ASME ANII.
" Work will be performed by Bechtel.
" Quality Control inspections will be performed by Bechtel, and endorsed by Unit 2 IVA.
- Non-destructive Examinations will be performed by Unit 2 TVA ISO/NDE for Section XI Repalr/Replacement.
" Radiation Protection and Site Support will be performed by TVA Unit 2 staff,
- Completed WO's will be reviewed by the Unit I ANII prior to closure.
" Prior to closing the WO and submitting It for ANII review, Bechtel will Issue a Unit 2 WO to punchlist and track to Section XI In-service Leak Test (ISLT).
- The WCS will be processed and EDCR closed by Bechtel.
The EDCR closure package will reference the (SLT WO.
- ISLT shall be performed during or before/after hydrostatic testing of Unit 2 systems In accordance with the Unit 2 WO that was issued at completion of the physical work.
- After completion of the system hydro I ISLT, the completed work will be documented on the Unit 1 ASME NIS-1 and NIS-2A forms.
- The Unit 1 / Unit 2 interface boundary will continue to be controlled per TI-12.08, Control of Unit Interfaces. Revision of Unit IPs will be performed using the DCN process per SPP-9.3. Operations will Isolate U2 components from U1, following interface point removal, utilizing the SPP-10.2 clearance process.
-population prior to Unit 2 startup.
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 91 of 101 TP-3 Watts Bar Unit I and 2 Memorandum of Understanding ASME Section Xl Interface riZ?ý-11"Av4 G. Mauldin "
Ar t1 7 Date' o 41 4L C- h -Date WBN Unit I Engineering Mgr Bit2n eaing gr
% M.-SkA~g) Dhte M. Bajestani Date WBN Unit I-Site VP WBN Unit 2 VP 6h!
eA.
cr dl f/,IL vw WBN CoordinatorDe eR WBN 2*N-5 Group 1' "Date ZL11 4~ ltjp'ssA irl¢ - w B-N I Welding Engineer 2A,,.W41./f*t Date WBN 2 Welding Engineer Date WBN 1 ANII 61 Date
ýýO. &LLtogfL a I -
-qZcq Date WýZJ~NDE 2 NuclearAssurance /DdEe "B/2 BechW eld Engineering Date This document can be found in BSL (Business Support Library) file "WBN, Unit 2-NGDC, TVA Unit 2, General Information, MOU-6.
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 92 of 101 SECTION 11.0 DRAWING REFERENCE LIST Some of the drawings will be included as the preservice inspections are completed and the drawings are updated.
FLOW DIAGRAMS Drawing Number Drawing Title (System) Code Class 47W801-1 Main & Reheat Steam (1) 2 47W801-2 SG Blowdown (1) 2 47W803-1 Feedwater (3) 2 47W803-2 Auxiliary Feedwater (3) 2&3 47W803-3 Auxiliary Feedwater (3) 3 47W809-1 Chemical & Volume Control (62) 1,2&3 47W809-2 CVC & Boron Recovery (62) 2&3 47W809-3 CVC & Boron Recovery (62) 3 47W809-5 CVC & Boron Recovery (62) 3 47W809-7 Flood Mode Boration Makeup (84) 2&3 47W809-9 Chemical & Volume Control (62) 2 47W810-1 Residual Heat Removal (74) 1,2&3 47W81 1-1 Safety Injection (63) 1,2&3 47W812-1 Containment Spray (72) 2&3 47W813-1 Reactor Coolant (68) 1&2 47W814-2 Ice Condenser (61) 2 47W819-1 Primary Water (81) 2 47W830-1 Waste Disposal (77) 2 47W832-1 Raw Service Water & HPFP (25/26) 3 47W832-2 Raw Service Water & HPFP (25/26) 3 47W845-1 Essential Raw Cooling Water (67) 3 47W845-2 Essential Raw Cooling Water (67) 3 47W845-3 Essential Raw Cooling Water (67) 2&3 47W845-4 Essential Raw Cooling Water (67) 3 47W845-5 Essential Raw Cooling Water (67) 3 47W850-2 Fire Protection Raw Service Water (26) 3 47W851-1 Floor & Equipment Drains (77) 2&3 47W855-1 Fuel Pool Cooling & Cleaning (78)(62) 2&3 47W856-1 Demin Water & Cask Decon (59) 2 47W859-1 Component Cooling (70) 3 47W859-3 Component Cooling (70) 2&3 47W859-4 Component Cooling (70) 3 47W862-2 SG Wet Layup, Closed Recirculation Loop (41) 2 47W865-5 Air Conditioning Chilled Water (31) 2
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 93 of 101 COMPONENT LOCATIONS Drawing Number Drawing Title (System) Code Class ISI-2001-E-01 STEAM GENERATOR 1&2 ISI-2001-E-02 STEAM GENERATOR 1 ISI-2001-E-03 STEAM GENERATOR SUPPORTS 1&2 ISI-2001-W-01 MSS WELD LOCATIONS 2 ISI-2001-W-02 MSS WELD LOCATIONS 2 ISI-2001-W-03 MSS WELD LOCATIONS 2 ISI-2001-W-04 MSS WELD LOCATIONS 2 ISI-2003A-W-01 FEEDWATER WELD LOCATIONS 2 ISI-2003A-W-02 FEEDWATER WELD LOCATIONS 2 ISI-2003A-W-03 FEEDWATER WELD LOCATIONS 2 ISI-2003A-W-04 FEEDWATER WELD LOCATIONS 2 ISI-2003B-E-01 AUX FDWR VALVE WELD LOCATION 2 ISI-2003B-W-01 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-1 I AUX FDWR WELD LOCATIONS 2 ISI-2062-W-01 CVCS WELD LOCATIONS 1 ISI-2062-W-02 CVCS WELD LOCATIONS 1 ISI-2062-W-03 CVCS WELD LOCATIONS 1 ISI-2062-W-04 CVCS WELD LOCATIONS 1 ISI-2062-W-05 CVCS WELD LOCATIONS 1 ISI-2062-W-06 CVCS WELD LOCATIONS 1 ISI-2062-W-07 CVCS WELD LOCATIONS 2 ISI-2062-W-08 CVCS WELD LOCATIONS 2 ISI-2062-W-09 CVCS WELD LOCATIONS 2 ISI-2062-W-10 CVCS WELD LOCATIONS 2 ISI-2062-W-1 1 CVCS WELD LOCATIONS 2 ISI-2062-W-12 CVCS WELD LOCATIONS 2 ISI-2062-W-13 CVCS WELD LOCATIONS 2 ISI-2062-W-14 CVCS WELD LOCATIONS 2
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 94 of 101 COMPONENT LOCATIONS Drawing Number Drawing Title (System) Code Class ISI-2062-W-15 CVCS WELD LOCATIONS 2 ISI-2062-W-16 CVCS WELD LOCATIONS 2 ISI-2062-W-17* later ISI-2062-W-18 CVCS WELD LOCATIONS 2 ISI-2062-W- 19 CVCS WELD LOCATIONS 2 ISI-2062-W-20 CVCS WELD LOCATIONS 2 ISI-2062-W-21 CVCS WELD LOCATIONS 2 ISI-2062-W-22 CVCS WELD LOCATIONS 2 ISI-2062-W-23 CVCS WELD LOCATIONS 2 ISI-2062-W-24 CVCS WELD LOCATIONS 2 ISI-2062-W-25* later ISI-2062-W-26 CVCS WELD LOCATIONS ISI-2062-W-27 CVCS WELD LOCATIONS ISI-2062A-E-01 CENT CHG PUMP WELD & SUPPORT LOCATIONS ISI-2062B-E-02 SL WTR HT EXCH SPT LOCATION ISI-2062C-E-01 SL WTR INJ FLTR WELD LOCATIONS ISI-2062C-E-02 SL WTR INJ FLTR SUPT LOCATIONS ISI-2062D-E-01 SL WTR FILTER SUPT LOCATIONS ISI-2063-W-01 SIS WELD LOCATIONS ISI-2063-W-02 SIS WELD LOCATIONS ISI-2063-W-03 SIS WELD LOCATIONS ISI-2063-W-04 SIS WELD LOCATIONS ISI-2063-W-05 SIS WELD LOCATIONS ISI-2063-W-06 SIS WELD LOCATIONS ISI-2063-W-07 SIS WELD LOCATIONS ISI-2063-W-08 SIS WELD LOCATIONS ISI-2063-W-09 SIS WELD LOCATIONS ISI-2063-W-10 SIS WELD LOCATIONS ISI-2063-W-11 SIS WELD LOCATIONS ISI-2063-W-12 SIS WELD LOCATIONS ISI-2063-W-13 SIS WELD LOCATIONS ISI-2063-W-14 SIS WELD LOCATIONS ISI-2063-W-15 SIS WELD LOCATIONS ISI-2063-W-16 SIS WELD LOCATIONS ISI-2063-W-17 SIS WELD LOCATIONS ISI-2063-W-18 SIS WELD LOCATIONS ISI-2063-W-19 SIS WELD LOCATIONS
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 95 of 101 COMPONENT LOCATIONS Drawing Number Drawing Title (System) Code Class 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 ISI-2063-W-30 SIS WELD LOCATIONS ISI-2063-W-31
- SIS WELD LOCATIONS ISI-2063-W-32 SIS WELD LOCATIONS ISI-2063-W-33 SIS WELD LOCATIONS ISI-2063-W-34* SIS WELD LOCATIONS ISI-2063-W-35 SIS WELD LOCATIONS ISI-2063-W-36 SIS WELD LOCATIONS ISI-2063-W-37* SIS WELD LOCATIONS ISI-2063-W-38 SIS WELD LOCATIONS ISI-2063-W-39 SIS WELD LOCATIONS ISI-2067-H-01 ERCW SUPPORT LOCATIONS ISI-2067-H-02 ERCW SUPPORT LOCATIONS ISI-2067-H-03 ERCW SUPPORT LOCATIONS ISI-2067-H-04 ERCW SUPPORT LOCATIONS ISI-2067-H-05 ERCW SUPPORT LOCATIONS ISI-2067-H-06 ERCW SUPPORT LOCATIONS ISI-2067-H-07 ERCW SUPPORT LOCATIONS ISI-2067-H-08 ERCW SUPPORT LOCATIONS ISI-2067-H-09 ERCW SUPPORT LOCATIONS ISI-2067-H-10 ERCW SUPPORT LOCATIONS ISI-2067-H-1 1 ERCW SUPPORT LOCATIONS
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 96 of 101 ISI-2067-H- 12 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-13 ERCW SUPPORT LOCATIONS 3 ISI-2067-H-14 ERCW SUPPORT LOCATIONS 3
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 97 of 101 COMPONENT LOCATIONS Drawing Number Drawing Title (System) Code Class ISI-2068-W-01 RCS WELD LOCATIONS 1 ISI-2068-W-02 RCS WELD LOCATIONS I 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 ISI-2068A-E-01 RV GENERAL ARRGMNT 1 ISI-2068A-E-02 RV INTERIOR VIEW I ISI-2068A-E-03 RV SEAM WELDS 1 ISI-2068A-E-04 RV CLOSURE HEAD 1 ISI-2068A-E-05 CRD & VENT PIPE PENTR 1 ISI-2068A-E-06 AUX HEAD ADAPTER 1 ISI-2068A-E-07 CLOSURE HEAD PENTR 1 ISI-2068A-E-08* later I ISI-2068A-E-09 RV STUD LOCATION & DETAIL 1 ISI-2068A-E-10 CLOSURE STUDS, NUTS, & WASHER 1 DETAILS ISI-2068A-E-1 1 RV SUPPORT 1 ISI-2068A-E-12 RV BOTTOM HEAD PENTR 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-2068B-E-01 RCP MAIN FLG & LOWER SEAL BLTG 1 ISI-2068B-E-02 RCP MOTOR AUG FLYWHEEL EXAM N/A ISI-2068B-E-03 RCP CASING WELD LOCATION 1 ISI-2068B-E-04 RCP AUG PUMP SHAFT EXAM N/A ISI-2068B-E-05 RCS PUMP SUPPORTS 1 ISI-2068C-E-01 PRESSURIZER 1 ISI-2068C-E-02 PRESSURIZER (MANWAY BLT) 1 ISI-2068C-E-06 PRESSURIZER (SUPPORT SKIRT & 1 SEISMIC LUG DETAIL)
ISI-2072B-E-01 CONT SPRAY HT EXCH WELD 2 LOCATIONS ISI-2072B-E-02 CONT SPRAY HT EXCH SUPPORT 2&3 DETAILS
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 98 of 101 COMPONENT LOCATIONS Drawing Number Drawing Title (System) Code Class 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 RHRS 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-2074-W-09 RHRS WELD LOCATIONS 1&2 ISI-2074A-E-01 RHR PUMP SUPPORT LOCATIONS 2 ISI-2074B-E-01 RHR HT EXCH CHANNEL WELDS 2 ISI-2074B-E-02 RHR HT EXCH SUPPORTS 2
- Drawing developed (to be issued)
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Terms PROCEDURE Page 99 of 101 SECTION 12.0 TERMS ACWS: Air Conditioning Chilled Water System (31)
ALARA: As Low As Reasonably Achievable ANII: Authorized Nuclear Inservice Inspector ASME: American Society of Mechanical Engineers AUG: Augmented AFW: Auxiliary Feedwater System (003B)
BC: Branch Connection CC: Code Case CFR: Code of Federal Regulations CH: Charging CHR: Containment Heat Removal Circ: Circumferential CL: Cold Leg CCS: Component Cooling System (70).
CRD: Control Rod Drive CSS: Containment Spray System (72)
CS: Carbon Steel CSP: Containment Spray Pump CVCS: Chemical and Volume Control System (62)
DWG: Drawing DM: Dissimilar Metal E: Equipment ECCS: Emergency Core Cooling System ERCW: Essential Raw Water Cooling System (67)
EL: Elbow EPRI: Electric Power research Institute ET: Eddy Current Examination FW: Feedwater FWS: Feedwater System (03A)
FMBMS: Flood Mode Boration Makeup System (84)
HL: Hot Leg HPFP: High Pressure Fire Protection (26)
Hx: Heat Exchanger
WBN-2 PSI REVISION 7 I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Terms PROCEDURE Page 100 of 101 ICS: Ice Condenser System (61)
IEP: Inspection and Examination Procedures INPO: Institute for Nuclear Power Operations ISI: Inservice Inspection IWA: Section XI General Requirements IWB: Section XI Class 1 Components IWC: Section XI Class 2 Components IWD: Section XI Class 3 Components IWE: Section XI Class MC Components IWF: Section XI Class 1, 2, 3 & MC Component Supports IWL: Section XI Class CC Components PSI: Preservice Inspection MOU: Memorandum of Understanding MSS: Main Steam System (01)
MT: Magnetic Particle Examination NDE: Nondestructive Examination NRC: Nuclear Regulatory Commission NGDC: Nuclear Generation Development & Construction PP: Project Procedure P: Pipe PENT: Penetration PSV: Pressure Relief or Safety Valve PWR: Pressurized Water Reactor PT: Penetrant Examination PZR: Pressurizer PCV: Pressure Control Valve PWS: Primary Water System (81)
R: Reducer RC: Reactor Coolant RCP: Reactor Coolant Pump REV: Revision RHR: Residual Heat Removal RHRS: Residual Heat Removal System (74)
RECIRC: Recirculation RCS: Reactor Coolant System (68)
WBN-2 PSI REVISION 7 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Terms PROCEDURE Page 101 of 101 RSW: Raw Service Water (System 25)
RLV: Relief Valve RT: Radiograph Examination RX: Reactor S: Supports SCH: Schedule SDCHX: Shutdown Cooling Heat Exchanger SD: Shutdown SER: Safety Evaluation Report SG: Steam Generator SGBD: Steam Generator Blowdown (System I & 15)
SH: Sheet SIS: Safety Injection System (63)
SI: Safety Injection SUR: Surface Examination SFPC: Spent Fuel Pit Cooling (System 84)
SS: Stainless Steel SXI: Section XI, Rules for Inservice Inspection Tee: Tee TK: Thickness Tech. Spec: Technical Specification TRM: Technical Requirements Manual TVA Tennessee Valley Authority UFSAR: Updated Final Safety Analysis Report UHIS: Upper Head Injection System (87)
UT: Ultrasonic Examination VCT: Volume Control Tank VOL: Volumetric Examination VT: Visual Examination VT-I: Visual Examination for Detection of Surface Conditions VT-2: Visual Examination for Evidence of Leakage VT-3: Visual Examination for General Mechanical and Structural Condition VE: Visual Examination (VT-2 Augmented Type)
WDS: Waste Disposal System (77)
WBN: Watts Bar Nuclear W: Welds