ML101200202
| ML101200202 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  (CPPR-0092) |
| Issue date: | 12/07/2009 |
| From: | Mcclain E Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML101200202 (80) | |
Text
Enclosure 2 WBN Unit 2 Preservice Inspection Program Plan
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 17381 Docket Number 391 Construction Permit No. CPPR-92, Issued January 23, 1973 Extension Issued October 24, 2000 Program No: WBN-2 PSI Rev. 2 Effective Date:
I 9.f7...9fO Responsible Organization, npcinSricsOgnzto Prepared by: R.
LL= Me lain Approved by
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 2 of 74 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
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Pages3 of 74 TABLE OF CONTENTS 1.0 Sum m ary.............................................................................................................................
4 2.0 Code Applicability..........................................................................................................
5 3.0 Description.........................................................................................................................
6 3.1 Scope...........................................................................................................
6 3.2 Jurisdiction.........................................................................................................
6 3.3 Responsibility....................................................................................................
7 3.4 Application......................................................................................................
7 3.5 Classification and Boundaries..........................................................................
8 3.6 Accessibility......................................................................................................
9 3.7 Referenced Standards and Specifications.......................................................
10 3.8 Exam ination M ethods......................................................................................
10 3.9 Nondestructive Exam ination Personnel...........................................................
11 3.10 Inspection Intervals.........................................................................................
11 3.11 Com ponent Reference System.........................................................................
11 3.12 Program Plan and Schedule............................................................................
12 3.13 Evaluation of Recorded Conditions...............................................................
12 3.14 Records and Reports......................................................................................
12 3.15 IW B Requirem ents and Exemptions................................................................
13 3.16 IW C Requirem ents and Exemptions................................................................
14 3.17 IW D Requirements and Exemptions...............................................................
16 3.18 IW F Requirem ents and Exemptions...............................................................
17 3.19 Code Cases.....................................................................................................
19 3.20 Code Relief....................................................................................................
20 3.21 Augmented Components.....................................
21 4.0 IW B Summ ary Tables................................................................................................
22 5.0 IW C Sum m ary Tables...............................................................................................
35 6.0 IW D Summ ary Tables...............................................................................................
45 7.0 IW F Sum m ary Tables..................................................................................................
47 8.0 Augmented Sum m ary Tables.......................................................................................
53 9.0 Requests for Relief.......................................................................................................
57 10.0 A SM E Section XI.- Technical Positions....................................................................
62 11.0 Draw ing - Reference List...........................................................................................
69 12.0 Program - Term s........................................................................................................
72
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 4 of 74 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 IOCFR50.55a(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 1 OCFR50.55a(g)(2) which requires that components, including component supports, that are classified as ASME Code Class 1 and 2 must be designed and be provided with access to enable the performance of inservice examination of such components and supports and must meet the preservice examination requirements set forth in Editions and Addenda of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code or optional Code Cases listed in NRC Regulatory Guide 1.147 that are incorporated by reference in I OCFR50.55a(b), in effect six month before the date of issuance of the construction permit.
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 6.2.2 and 6.2.5.
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
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 5 of 74 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. 10CFR50.55a Codes and Standards, dated February 27, 2008, specifically 10CFR50.55a (b)(2) which referencesSection XI through 2003 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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 6 of 74 2.5.1 The Inspector shall review the initial program plan, prior to the start of preservice inspections as well as revisions to the program plan. Also, the Inspector shall submit a report to the program owner documenting the review of the initial program plan and each revision thereafter. The review shall cover the features that are affected by the requirements of Section XI and this document, as applicable.
Shop and field preservice examinations are exempt from prior review.
2.5.2 The Inspector shall verify that the required examinations of this document, have been performed and the results recorded. Also, the Inspector shall verify that the nondestructive examination methods used follow the techniques specified and that the examinations are performed in accordance with written qualified procedures and by personnel qualified in accordance with the requirements of ASME Section 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.
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 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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 7 of 74 3.3 RESPONSIBILITY The responsibilities of maintaining this PSI Program Plan are included in NGDC PP-1 5.
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 R/R 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)(xiii), Mechanical clamping devices will be addressed in the Repair/Replacement Programs, if needed.
- 3. 1 OCFR5 0.55 a(b)(2)(xvii), Reconciliation of Quality Requirements is addressed in the Repair/Replacement Program, if needed.
- 4. 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.
- 5. 1 OCFR50.55a(b)(2)(xxv), Mitigation of Defects by Modification will be addressed in the Repair/Replacement Program, if needed.
- 6. 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.
It should also be noted that a "Memorandum of Understanding" (MOU) has been established to address the interfacing systems between Unit I and 2. Portions of the Unit 2 systems were documented on Unit I 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
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 8 of 74 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 IWB requirements of Steam Generator Tubing of Examination Category B-Q, regarding the extent and frequency of the examination, is governed by Technical Specification and documented in the Steam Generator Tubing Program Plan and Schedule as addressed in 10CFR50.55a(b)(2)(iii).
3.4.1.4 The IWF-5000 requirements for preservice examination and tests of snubber is governed by ASME/ANSI OM, Part 4, 1987 with OMa-1988, using the VT-3 visual examination method. As an optional requirements, per IOCFR50.55a(b)(3)(v), Subsection ISTD of the ASME/ANSI OMb 2003 code may be use to provide inspection requirements for examinations and tests of snubbers by making appropriate changes to their technical specifications or licensee-controlled documents.
Examinations must be performed using the VT-3 visual examination method.
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 1 0CFR50.55a(b)(2)(ix) and subparagraphs (A), (B), and (F) through (W).
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.
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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 9 of 74 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:
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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 10 of 7/4 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 -
Magnetic Particle ET-Eddy Current Note: 1 OCFR50.55a(b)(2)(xxii), prohibits the use of an ultrasonic examination method for surface examination as allowed by IWA-2220.
Volumetric (Vol), an examination method used to detect the presence of discontinuities throughout the 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,
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 11 of 74 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 1 OCFR50.55a(b)(2)(xix).
3.8.4 The extent of exam and examination requirements for volume or area coverage, as required in the summary tables of this document for each component, shall be documented on the applicable examination record and shall identify both the cause and percentage 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 3.9 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 10CFR50.55a(b)(2)(xiv), (xv), (xvi), (xviii) and (xxiv). The written practice shall control the personnel requirement for nondestructive examination for this document and is outlined with the additional provisions of 10CFR50.55a regarding personnel qualification and certification as noted below.
3.9.1 10CFR50.55a(b)(2)(xiv), Appendix VIII personnel qualification.
3.9.2 10CFR50.55a(b)(2)(xv), Appendix VIm 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-1, listed in this document. The identification of the components
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 12 of 74 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.
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
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 13 of 74 requirements in addition to being implemented by Watts Bar procedures for, Record Control.
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 1 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. I OCFR50.55a 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)(xi), states that licensees may not apply IWB-1220, Components Exempt from Examination, but instead shall apply IWB-1220, 1989 Edition. Reference paragraph 3.15.6.
3.15.3.2 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.
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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 14 of 74 3.15.6 The following components or parts of components are exempt from the volumetric and surface examination requirements as noted in the 1989 Edition of Section XI as referenced in 1 OCFR5 0.5 5a(b)(2)(xi):
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 I and smaller; 3.15.6.3 Reactor vessel head connections and associated piping, NPS 2 and smaller, made inaccessible by control rod drive penetrations.
Note: Piping is defined as having a cumulative inlet and cumulative outlet pipe cross-sectional area neither of which exceeds the nominal outside diameter cross-sectional area of the designated size.
3.16 IWC REQUIREMENTS AND EXEMPTIONS 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 frdm 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.
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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 15 of 74 (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 1 1/22 and smaller; (2) Class 2 vessels, pumps, and valves and their connections in piping NPS 1 /2 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 1 2 and smaller; (2) Class 2 vessels, pumps, and valves and their connections in piping NPS 1 1/2 and smaller (c) Class 2 vessels piping, pumps, valves, other components connections of any size in systems that operate (when the system function is required) at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200' F (93'C).
(d) Class 2 piping and other components of any size beyond the last shutoff valve in opened portions of systems that do not contain water during normal plant operating conditions.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 16 of 74 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 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.
3.17 IWD REQUIREMENTS AND EXEMPTIONS 3.17.1 Subsection IWD 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 (c) components that operate at a pressure of 275 psig or less and at a temperature of 2001F 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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 17 of 74 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 REQUIREMENTS 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 2000F 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 Snubber is governed by ASME/ANSI OM, Part 4, 1987 with OMa-1988, using the VT-3 visual examination method. As an optional requirement, per 1 OCFR50.55a(b)(3)(v), Subsection ISTD of the ASME/ANSI OMb 2003 code may be use to provides inspection requirements for examinations and tests of snubbers by making appropriate changes to their technical specifications or licensee-controlled documents. Examinations must be performed using the VT-3 visual examination method.
Integral and nonintegral attachments for snubbers, including lugs, pins, bolting and clamps, shall be examined in accordance with the requirements of this document.
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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 18 of 74 3.18.5 The support examination boundaries for both integral and nonintegral 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 nonintegral support connected to a pressure retaining component is the contact surface between the component and the support.
(d) The boundary of a nonintegral support connected to a building structure is the surface of the building structure.
(e) Where the mechanical connection of a nonintegral 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.
(g) 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 nonintegral attachments of pressure retaining components, and integral and nonintegral supports. The examination boundary does not include the attachment of the intervening element to the building structure.
(h) All integral and nonintegral 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.
I (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
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 19 of 74 (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 200OF 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 200OF 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 Case is accepted for use in Regulatory Guide 1.147 and shall be utilized where applicable:
N-460 Alternative Examination Coverage for Class 1 and 2 welds. To be used on all IWB-2500, Class 1 and IWC-2500, Class 2 welds.
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.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 20 of 74 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-3512-1with 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 shall be utilized where applicable.
N-722 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.
This Code Case shall be use subject to the conditions specified in paragraphs IOCFR50.55a(g)(6)(ii)(D)(2) through (6) in the Code of Federal Regulations.
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 10CFR50.55a(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 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 certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit information to support the determinations.
NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 2 PROCEDURE Page 21 of 74 3.20.3 1 OCFR50.55a(g)(5)(iv) states "Where an examination requirement by code or addenda is determined to be impractical by the licensee and is not included in the revised inservice inspection program plan as permitted by paragraph 10CFR50.55a(g)(4), the basis for the determination much be demonstrated to the satisfaction of the commission not later than 12 month after the expiration of each subsequent 120 month period of operation during which the examination is determined to be impractical."
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 10CFR50.55a.
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.
WBN-2 PSI REVISION 2 WATTS BAR UNIT - 2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 22 of 74 SECTION 4.0 IWB
SUMMARY
TABLES For ASME CLASS 1 CATEGORIES B-A Pressure Retaining Welds in Reacor 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-1-2 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 2 WATTS BAR UNIT-2 IWB
SUMMARY
TABLES PRESERVCE INSPECTION PROGRAM PLAN Pa 2
O 7
Examination Category B-A, pressure Retaining Welds in Reactor Vessel Inspection Prog am B Item Component Component Exam Extitnaton Extent of Acceptance Total Required No.
Examined Compliance Method RFimqNo.
Exam Standard Population Examination
______Fig.
No.
B3.0 Shell Welds 31.11 Circumferential Applicable Vol.
AWB-2500-U IWB-3510 4
(2) rB31 B1.12 Longitudinal NA to UNIT-2 31.20 Head Welds Accessible B1.21 Circumferential Applicable Vol.
IWB-2500-3 length of IWB-3510 2
2 weld Accessible B1.22 Meridional Applicable Vol.
IWB-2500-3 length of all IWB-3510 6
6 welds 31.30 Shell to Flange Applicable Vol_
IWB-2500-4 Weld (2)
IWB-3510 I
1 B 1.40 Head to Flange Applicable VoL & Suf.
IWB-2500-5 Weld (2)
IWB-3510 I
I B1.50 Repair Welds (1) 131.51 Beltline *egion NA to UNIT-2 Totals Examination Category B-A 14 14 NOTES:
(1) NA to Utit-2 (2) o senteialy 100% of th we.ld length.
(3) NA to Unit-2 Preserici acniities (4) NA to Unit-2 Prsenrin atvites (5) NA to Unit-2 Presaere ascdibes
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 iWB
SUMMARY
TABLES PRESERViCE INSPECTION PROGRAM PLAN Page 24 of 74 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels Inspection P ram B Item Component component Exam Examination E
Total Required Requireet Exam Standard Population Examination No.
Examined Compliance Method Fig. No.
Pressurizer B2.10 Shell to Head B2.11 Circumferential Applicable Vol.
IWM-2500-1 Both Welds IW1B-3510 2
2 (4) lfofall B2.12 Longitudinal Applicable Vol.
2 (2)
B2.20 Head Welds B2.21 Circumferential NA to UNIT-2
.B2.22 Meridional NA to UNIT-2 Steam Generators (Primary side)
B230 Head Welds B231 Circumferntial NA to UN)T-2 B2.32 Metidional NA to UNIT-2 Weld B2.40 Tubesheet to Head Weld Applicable VoL IWB-2500-6 (4)
IWB-3510 4
4 Heat Exchanger (Primary side) - Head B2.50 Head Welds B2.51 Circurarsem ntial NA to UNIT-2 B2.52 Meridional NA to UNIT-2 Heat Exchanger (Primaxy side) - Shell BZ60 Tubeoseet io Head Welds NA to UNIT-2 B270 Longitudinal Welds NA to IJNIT-2 B2.80 Tubesheet t Shell Welds NA to UNIT-2 Totals Examination Category B-B 8
8 NOTES:
(1) NAto Unit-2 Prmerviee advitkes (2) The weld elcid far eaninataon is dia* weld inersectng the esumfneesatW weld.
(3) NA to Unit-2 Preservi ascdivie (4) Inclafd =eadiaaly 100% of the weld lengh
WBN-2 PSI REVISION 2 WA 7TS BAR UNIT-2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN ae..o.
Page 25 of 74 Examination Category B-D, Full Penetration Welded Nozzles in Vessels Ins _ection Progrm B Item Component Component Exam Examination Extent of Accetance Total Req-hocd Requirements Exam Standard Population Examinaton No. (8)
Examined Compliance Method Fig No.
Reactor Vessel 390 Noze to Vesel Welds Applicable Vol.
WNoz IWB-3512 8
8 (a) through (c)
(1)
B3.100 Nozzle Inside Radius Section Applicable EV(
(4)
(N)
IWB-3512 8
8 (9)
(1)
Pressurizer B3. 110 Nozzle to Vessel Welds Applicable VoL IWB-2500-7 All Nozzles lWB-3512 6
6 (a) through (c)
(1) 33.120 Nozzle Inside Radius Section Applicable VoL (7)
(4)
All Nozzles IWB-3512 6
6 (6)
(1)
Steam Generators (Primary side)
B3.130 Nozzle to Vessel Welds NA to UNIT-2 B3.140 Nozzle Inside Radus Secton Applicable Vol- (7)
(4)
All Nozzles IWB-3512 a
8 (6)
(1)
Heat Excangcr (Primay side) - Head B3.150 Nozzle to Vessel Welds NA to UNIT-2 B3.160 Nozzle Inside Radius Section NA to UNIT-2 Totals Examination Category B-D 36 36 NOTES:
(1) Ineludes nozzles with fall penefration welds to vessel shell (or head) snd integrally cast nozles. but eacludes esnsays sad hwxlsles either welded to or istegrmaly cast in vessel.
(2) NA to Uaft-2 Preservice activities (3) HA to Unit-2 Preserice activities (4) The exaaaisatio volumes shell apply to the applicable Figuse shown in Figs. IWB-25D0-7(a) throug (d (5) NA to Unai-2 Prese-via activities (6) 10W50.55ab)(2)(xiX)(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 examinatio with sbaneed c
aaificatioe that has a resolution scestivity to detest a t-mil width wie or crack ublialsa the allowable flaw length criteria in Table tWB-3512-I, maybe perormed pl of an altmoossic exaesssawon, refernce I0CFR50,5Sa~b2Xto)(A).
(0) Category Items 310 -
3.80 are based on Inspetion Program A and do not apply to Unit-2.
(9) Code Case N-648-I, with conditional appreval, see paragraph 3.192 for det*ls of exam a and at= uftmanom
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Pg 26 Of 74 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles Inspection Promram B Item Component Component Exam Re ien Extent of Acceptance Total Required No.
Examined Compliance Method Fig. No.
Exam Stadard Population Examinmaion 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 Thain NPS 4-Nozzle-to-Safe End Butt Welds NA to UNIT-2 B5.30 Nozzleto-Sade End Socket Welds NA to UNIT-2 Pressurizer B5.40 NPS 4 or Lage-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur IWB-2500-8 Alt Welds IWB-3514 6
6 B5.50 Less TTan NIS 4-Nozde-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 L.ger-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 UN1T-2 Heat Extetnges B5.100 NPS 4 or Larger-Nozzle-to-Safe End Butt Welds NA to UNlT-2 B5.110 Less Than NPS 4-Nozzle-to-Safe End Butt Welds NA to UNJT-2 B5.120 Nozzle-to-Safe End Socket Welds NA to UNIT-2 Totals Examioation Category B-F 22___..
22 Note:
(1)
NA to Unit*2 Prmservic activies t2)
NA to Umt-2 Penevic actvtita
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 27 of 74 Examination Category B-G-1, Pressure Retaining Bolting, Greater than 2 in. in Diameter Inspection Program B Item Component Component 1 Exam Examints Extent of Acceptance Total Required No.
Examined I
Compliance Method eit N Exam Standard Population Examination NO F
Copiac Metho Fig-.No II 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 Fane IWB-3515 54 54 Surface B6.50 Closure Washes, Btshings (2)
Applicable VT-1 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 B6.90 Nuts, Bushings, and Washers NA to UNIT-2 Steam CMerators B6.90 Bolts and Studs NA to UNrT-2 B6.100 Flange Surface, when connection disassembled NA to UNIT-2 B61 10 Nuts, Bushings, and Washers NA to UNrT-2 Heat Exchangers B6.120 Bolts and Studs NAtoIUNIT-2 B6.130 Flange Surface, when connection disassembled NA to UNIT-2 B6.140 Nuts% Bushings, and Washers NA to UNIT-2 Notes, at end of this sectio.
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 iWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 28 of 74 Examination Category B-G-1, Pressure Retaining Bolting, Greater than 2 in. in Diameter Inspection Pro am B Item Component Component Exam Exaination Extent of Acceptance Total Required No.
Examined Compliance Method Rquig.mn Exam Standard Population Examination Fig. No.
Piping B6.150 Bolts and Studs NA to UNIT-2 B6.160 Flange Surfac 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 FWB-3515 96 96 s6.190 Flang Surface, when connection disassembled AFnpliable VT-I Suh FWg-(2)(4)(6)
Surfaces IWB3517 4
4 B6.200 Nuts, Busaings and Washers NA to Unit-2 Valves B6.210 Bolts and Studs NAto Unit-2 B6.220 Flange Surfacc, when connection disassembled NA to Unit-2 B6.230 Nuts, Bushings, and Washers NA to Unit-2 Totals Examination Category B-G-I 316 316 NOTES:
(I) Botting may be =euvssed. (a) in place unde tenioa; (b) whei tlhe conaction is dissio blad; (c) ahen the bolting is ersanvad.
(2) Threads in bae material of flanges snifn are required to be eamnied only when the conineains aea disesmebled.
(3) NA to Unit-2 Ptenervice awidviti (4) Visuad emniaion Of bolted coneotions, VT-1 of the flange sorhce, nuts and washers, for pumps is required only when the nuaponea is coumiaed nuder Eonmination Category B-1,. This is foe one pumip inn a gr of pumps pr*fochnig similr fintin in a syotum and is requid only when dimssembly for maintennune, repai, or wvasdri onunanin, as stated in B-1,2. (Se note 2 in sucurmay table for oeeguy B-Lý2)
(5) NA to Unit-2 Psassne -ditlisa (6) Ehannatbots m"luds I a annola sfaoe of fanige *roeedineach tnd.
(7) When bolts or suds am smnvd fur esdasinona, arfne= examination menting the acceptance standards of FWB-351 5 may be nsio~ned for vounitamros examionnee.
IWBN-2 PSI REVISION 2 WATTS BAR UNIT-2 PFdB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN P
74 Examination Category B-G-2, Pressure Retaining Bolting, 2in. and Less in Diameter Inspection Pro ram B itemComonet Coponnt xam Examination Item Co Component Exam Requi s or Extent of Acoeptance Total Required No.
Examined Compliance Method R
iee or Exam Standard Populaion(5)
Examination I
~Fig.
No.
Reactor Vessel B7,l0 Bolt, Studs, and Nuts NA to Unit-2 Pressurze B7,20 Bolt, Studs, and Nuts (1) (2)
Applicable VT-I Surface All Stds, IWB-3517 1
TBD and Nuts Steam Generators B7,30 Bolt, Studs, and Nuts (1) (2)
Applicable VT-I Surface Al Studs, rWB-3517 9
TBD andNNuts Heat Exchangers B7,40 Bolt, Studs, and Nuts NA to Unit-2 Piping All Bol, B7.50 Bolt, Studs, and Nuts (1)
Applicable VT-I Surface Studs, and IWB-3517 13 TBD Nuts Pumps B7.60 Bolt, Studs, and Nuts (1) (2)
Applicable VT-I Surface All Studs, WB3517 9
TBD and Nuts Valves B7.70 Bolt, Studs, and Nuts (I) (2)
Applicable VT-i Surface
B7.80 (4)
Bolt, Studs, and Nuts (1) (4)
NA to Unit-2 Totals Examination Category B-G-2 59 TBD I
NOTUS:
(I) Bo*ting is reqwrcd to be exammed only whten a connection is disassemblcd a bolting is removed.
(2) For vessels, pmnps, or valvews, namnaioa of bolting is requied oely when the compoanet is emasomad unde Examinatioa Category B-B, B-L-2, or B-M-2. F i
onat af bolted ctmectios is reqired only oce, dueiag the tttaa (See amae 2 n oamotary table for catagory B-L-2 and B-M-2)
(3) NA to Unti-2 Preservioe activites (4) hI piovsaons of,xamimaoi Category B-G-2, htem 87.0, ha are in the 1995 Edition are applicable. refkrea 10CFR'50.55L(b)(2Xu')(B), oay to rmerd.boi...
(5) Total populanon r-teescs "bolted crcmecions".
F&D - To be dremonad
WBN-2 PSI REVISION 2 WATTS BAR UNIT - 2 riWB
SUMMARY
TABLES PRESERVlCE INSPECTION PROGRAM PLAN Page 30 Of 74 Examination Category B-J, Pressure Retaining Welds in Piping Inspection Program B Item Component Component Exam Examination Exdent of Acceptance Total Requied No.
Exmnined Compliance Method Reqirements Exam Standard Population Examination Fig. No.
B9.10 NPS 4 or Larger B9.11 Circumferential Welds Applicable Vol. & Stir IWB-2500-8 Welds (1) (4)
IWB-3514 280 280 (5)(6)(7)
B9.20 Less Than NPS 4 B921 Circumferential Welds other than PWR Welds IWB-3514 57 57 High Pressure Safely Injection Systems (1) (4) (5)
B9.22 Circumferential Welds of PWR High Applicable VoL IWB-2500-8 Welds WB-3514 42 42 Pressure Safely Injection System (2) (4) (6) (7)
B9.30 Branch Pipe Connection Welds B9.31 NPS 4 or Larger Applicable Vol. & Sur IWB-2500-9, 10&
Welds (1) (4)
IWB-3514 11 1
1I (5)(6)(7)
B9.32 Less Than NPS 4 Applicable Sur.
IWB-2500-9, 10 &
Welds IWB-3514 29 29 11 (1) (4) (5)
B9.40 Socket Welds Applicable Sur.
IWB-2500-8 Welds IWB-3514 394 394 (1) & (4)
Totals Ex*amonalioR Category B-J 813 813 Note*
(1) Exazomnaianon shla inadd th fotloseinF (a) All tosaioal *ns in each ptpe or branch ran connected to vesses (b) All terminal ends and joints in each pipe or branchsel, connected to other componerns what the srs levels
- ecead either of the fiowrig huis under loads asnonate with sp1otfic netnsnt events and operational condition:
(1) primary plus secondaty stress intensity range of 2.4Sm for ferritic steel end neonentic steel (2) cuonnlative se factor U of 0.4 (c) All dissi ar metal welds net coved under Category B-F.
(d) Additcnoal piping welds so that the total namber of cicmuferetialn butt welds (or branch connection or sorket welds) selscted for ecamination eqnals 25% ofthe ciresorferesW bn welds (or branch connection or socket welds) to the reactoe coolant piping nystnie Thin rotal does not inolude welds enestpted by IWBe-1220 or welds to Item N~o. Bs9.22.
These ardditional welds msyhbe locatedino one loop (one toopqis defined for both
- WR ord BWR planet in the 1977 Edition).
(2) A 10% sample of PWR high pressure safoty injection system cacunfercatiol welds m piping > NPS 11,2 (DN 40) end < M'S 4 (DNIQO) shell he selected for cosmnabon. This ample shell he selected from ocanboue determined by the Owner as mot likely to be subject to thermal fotigne. Thermal breng may be conned by condition such asvalve I*roa ge ornnbulmsee ef fe (3) NA to Unit-2 Preserve activities (4) lnducdm essentially IW0% of weld length.
(5) For cihaunfexential welds with inteseotuig lorgitudimnl welds, sunfan enanninotic of the Iongitudinal piping welds s requited for those portions ofthe welds within the examointn bhouriet offntenneonng tn sin, o Category B-F and B-I crnrmdmfential welds.
(6) FPo cannnferential welds with intersecting lnegitudiml welds, volhanea enomntion of the ltogitalinel piping welds is requited fir those portions of the welds within the econnnaticnoundarien of intersecting Eannination Category BMF and B-J cireumfna tlial welds. The following reqtnments shall Want be met:
(a) When tongroadinnl welds =n specified and locations ate hanoen, enamecoatsontequrancmnns shall he met fsr both transverse and parallel flases at the intersection offth welds and for thar length of )nngitudinal weld within the nircunsfiertial weld aconsinnio voluane.
(b) When longitudinal welds are specified but locatibou we unknown, or the e.nence of longaudinal welds is uncetain, the e nam ton reqtoi ts, sma be met for both transverse and par*llel flaow within the airte examination volam= ofiaersecting circumferential welds.
(7) For welds is carbon or low alloy stees, only those welds showing reportable preservuec transverse indications need to he eauied by the ultrasonic method for reflectuns transverse to the weld length directon except that
,irceferenaial welds with intersecting tloaiodmal welds shall meet Note (5).
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN pag 31 Of 74 Examination Category B-K, Welded Attachments for Vessels, Piping, Pumps and Valves Inspection Proram B iten Component Component Exam EExmenn of Acceptanc Total Required No.
examined Compliance eReo Figemeos Exam Standard Population Examination NO. xamned ompianc Mehod Fig. No.
Pressure Vessels Each welded Surhmt IWB-2500-13, 14 E~ach welded
-51 BIO10 Welded Attachments (1)
Applicable attachment IWB-3516 5
5 (7) and 15 (2)(6)
Piping IWB-200-1, 14 Each welded 130.20 Welded Altachentls (1)
Applicable Surface IWB-2500-13,14 attachme IW3516 D
TD andl15 atahet NB31 BTD (2)(6) 81030 Welded Attachmaets (1)
NA to Unit-2 Valves B1O.40 Welded Attachments (1)
NA to Unit-2 Totals Examination Category B-K TBD TBD NOTES:
(1) Weld buildup on nozzles that is in *pressina netr normal conditions and piovides only oomponent support is excladed fro minalin. Exmination i liaited to those welded aftaelnents that mee the fDlowing conditions:
(a) the man ea is on the oinide sinfae of the pressure riaining cmtpnea (b) the attachment p*ovides omaponet aTopert as defined in NP-I 110; (c) the tanhoent weld jois the unthmet ether dame*y n the ftsu e of the component no to an Wnrally eas no forged autahient to the ooiponent, and (d) the antachment weld is ful pmetabion fillet, or partal penetration, ntnioumor no in teni (2) The extnt of the examnantion no*hies essmaially 100% of the length of die atinlanhe weld at each mnadanent subject to cammandn.
(3) NA to Ujmt-2 Pservino acivities (4) NA to Unit-2 Presrvice activities (5) NA to Unit-2 Prensice actavities (6) Examination is required wheee component support member deformation, e.g, boken, behn, or pulled ant patsý a idenbled during epeuion, netli& maimenanoe, cmanation, o* tstmi (7) For the configuratinon shown in Figs. 1WB-2500-13 and IWB-2500-4, a nsafe oanationa fie ano nessil side ofthe tthaent weld shall be pefosne& Aftwntieely, for the configuration shown in Fig. r
- l-2500-14, a volmnetric examination of volume A-B-CD fioam an accessible side of the aftaclenet weld may be perefomed to lien ofthe sedece ommia*tin of suafaces A-n no C-fD.
TBD - To be detereand
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 32 of 74 Examination Category B-I-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 Pr Imn B Item Component Component Exam Examinti Extent of Acceptance Total Requited No.
Examined Compliance Method Rieqirent Exam Standard Population Examination I____
Fi_- No.
B12.10 Purap casing welds, B-L-A (4)
Applicable VT-I IWB-2500-16 All welds IWB-3518 4
4 B1210 Pump casing, B-L-2 (2) 4 0
Valves B 1230 Valves, less than NPS 4 valve body welds, B-M-1 (4)
NA to Unit-2 B12.40 Valves, NPS 4 or larger valve body welds, B-M-1 (4)
NA to Uait-2 B 12.50 Valve body. eceeding NPS 4, B-M-2 (2)
TBD 0
Totala Examination Category B-L-1 TBD 4
I I
NOTES:
(1) NA to Unit.2 Preseevice activities (2) NA to Umt-2 Ptservice actiiies, re*f*rce IWB-2200 (3) NA to S.eit-2 Preservie acivite, (4) Includes esstisly 100% of weld lengt*
TBD -Tn be detensne
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 AWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 33 of 74 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 I
pection Program B Item Component Component Exam Exmit Ete &
Accepta Total Required No.
Examined Copliance Metihod R
eintet Frequency of Fig. No.
Examn Standard Population Examination Reactor Vessel Each B13.10 Vessel Interior B-N-I (1)
Applicable VT-3 Accessible Areas Inspection IWB-3520.2 1
1 Period Reactor Vessel (SWR)
B13.20 Interior ataclhments within beltline region NA to Unit-2 B-N-2 B13-30 Interior atachments beyond the beltline region NA to Unit-2 B-N-2 B13.40 Core Support Structure NA to Unit-2 B-N-2 Reactor Vessel (PWR)
B13.50 Interior attachments wthin belline, region NA to Unit-2 B-N-2 B13-60 Interior attckinments beyond the belsline region Applicable VT-3 Accessible Welds Welds IWB-3520-2 6
6 B-N-2 B13.70 Core Support Structre Applicable Accessible B-N-3 (2)
Sutface Srfaces IWs-3520.2 1
1 Examination Category 9-N-i I
1 Exasuination Category B-N-2 6
6 Totals Examination Category B-N-3 1
1 NOTES:
(I) Areas o be mandined shalt iedo the spaces above ad below the eretor core that are made accesible for eamasnby removal ofc oomperas during nonmal refueling otges (2) The srerore shall be removed from the reacr vessel fex uasmiatlian.
(3) NA to Unir-2 Presermce activities
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 IWB
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page I
Examination Category B-O, Pressure Retaining Welds in Control Rod Housings Inspection Program B Item Component Component Exam Examination Extent of Acceptance Total Required Companc Method Requirements Exam Standard Population Examination No. xamned ompianc Mehod Fig No.
Reactor Vessel Volumetric 100%
B14.10 Welds in CRD Housing (1)
Applicable or IWB-2500-I8 Peripheral IWB-3523 20 20 Surface CRD Housing Totals Examination Category B-O 20 20 Noet:
(1) 20 P*tipeat =npoo*
of tho79 Tot ClD Htlo.siap.
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 iwc
SUMMARY
TABLES PRESERVlCE INSPECTION PROGRAM PLAN Page 35 Of 74 SECTION 5.0 IWC
SUMMARY
TABLES For ASME CLASS 2 INDEX CATEGORY C-A, C-B, C-C, C-D, C-F-1 C-F-2 C-G, Pressure Retaining Welds in Pressure Vessels Pressure Retaining Nozzle Welds in Vessels Welded Attachments for Vessels, Piping, Pumps, and Valves Pressure Retaining Bolting Greater than 2 Inch in Diameter Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Pressure Retaining Welds in Pumps and Valves ASME Section XI items that do not apply to Watts Bar Unit 2 within this Program Plan will be identified with, "NA to Unit-2", this documents the item does not apply and will not be referenced further within the program plan, schedule or summary reports.
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 IWC
SUMMARY
TABLES PRESER VICE INSPECTION PROGRAM PLAN Page 36 of 74 Examination Category C-A, Pressure Retaining Welds in Pressure Vessels Inspection ram B Item comsponent Component Exam
~Exation Extent and No-Examined Compliance Mex Requirements Frequency of Accptance Total Required Fig. No.
Exam Standard Population Examination Welds at CLIO Shell Circumferential Welds (1) (3) (4)
Applicable Volumetric gro (5)
IWC-2500-1 structral IWC-3510 5
TBD discontinuity (2)
Welds at Volumenic gross C1.20 Head Cir eential Welds (1) (3) (4)
Applicable 5WC-2500-1 structural IWC-3510 15 TBD discontinuity (2)
Welds at a Volumetric gross C30 Tube t-toShel Weld (1) (3) (4)
.Applicable (5)umetric IWC-2500-2 structural IWC-3510 4
TBD (5) discontinuty (2)
Totals Examination Category C-A I
NOTES:
(I) tactados enarolally 100% of she weld lnsgds.
C2) Gros steaoal discontiouity is dfiratd iuNlB-3213.. Examples ae jmwions betwem shels of difesthid* esses*. oy sbll-to-ooical seljsnedar. shset (Obead).to-flare welds.and heod-to-shell welds.
(3) in the case ofacmltiple vessels of similar dresm sime, and smviee (suh as samra generators, heat m ebargast atay be lSaoird to one vess ordmilriaed armong the vessels (4) The vessel areas seletd forte u1 niial 2tomsaso shalt be remeiacood = the sacmo ~ssenee oase tine s je lifetimet oftb she esnpom, so the seader proseabl.
(5) For welds in vessels with nominal all thidosos of 0.2 in or less. a surfte caasieation may be applied in leu of a voluweeliexmination The acoaninatio shall e*lncde th weld and 0-5 in, on either side of the weld The accept*nce srd f" the exainamtion shall be those specified for piping in IWC-3514-TBD = To Be Detersasins
WBN-2 PSI REVISION 2 WATTS BAR UNIT. 2 Fwc
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 37 of 74 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels npecltion P m B Item Component Component Exam E
E Acceptance Total Required No.
Examined Compliance Mathod Requiremenl Frequency of Stadard Populataon ExaTinRoedon I
Fig No.
Exam C2.10 Nozzles in Vessels V
I/2 in. nominal Thickness (1) (2) (3X4)
C2.11 Nozzle-wo-Shell (nozzle-to-head) Weld Applicable Surface IWC-2500-3 (6)
IWC-35 11 0
TBD C2.20 Nozzles Without Reinforcing Plate in Vessels >
1/2 in. Nominal Thick= (1) (2) (3) (4)
Surface and IWC-2500..4 C2.21 Nozzle-to Shell Weld (nozzle-to-head)
Applicable Surf c
(n),IWC-2500)4 (6)
IWC-3511 14 TBD Voluetneric (a).b)ce(d)
)22.21 Nozzle Inside Radius Section Applicable Volumetric I'WC-2500-4 (6)
C2.30 Nozzles With Reinforcing Plate in Vessels > %
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 C2N32 w en Shell We, ld (nozzle-to-head)
Applicable Volumetric IWC-2500-4(c)
(6)
IWC-3511 4
TBD 022 whenl inside ofvessl in aecessibienBI C2-33 Nozzle-to Shell Weld (nozzle-to-head)
Applicable Visual, VT-2 (5)
(6)
No Leakag 0
TBD when inside of vessel is inaccessible otals Examination Catecory C-B 30 TBl NOTES:
(I) incudes notzles welded to or integrally cast in vessels that connect to POW:g ras (maaways and *tn.dholet aehaled).
(2) Ineludes only those pipng runs selected ftr examitention sderr Exesantioa Category C-F.
(3) The azzles seclted ioially ft examaistio shallt e bere*enind to the ewmes steqoc oeam the sersice tlim ofthe component t the e* tent e icaL (4) Inthe ase of mautiple vessels of simln design. site, and sersvie (stch ns steam genoeaters hear car ges, the treqitd examinatio*st may be limited to ser vessel or ted ntong the vessels (5) The telltale hole in thesrinforcig plate hAi be examined for evidence of leatsu while vessel is undergoing the system ekaae test a equekdby examination categoy C-H (6) Nozoles at terminal erds (1) of gpipog n, (2).
TBD = To be determined I
WBN-2 PSI REVISION 2 WATTS BAR UNIT - 2 IwC
SUMMARY
TABLES PRESERVlCE INSPECTION PROGRAM PLAN Page 38 of 74 Examination Category C-C, Welded Attachments for Vessels, Piping, Pumps, and Valves Inspection Prog aram B
Item Component Component Exam Examinaton Extent and Acceance Total Requited No.
Examined Compimce M hod Requirements Frequency of Standad Population Examination Fig. No.
Exam Pressure Vessels (1) (3)
C3.10 Welded Attachments Applicable Surface IWC-2500-5 (2X4X6)
IWC-3512 22 TBD Piping (1) (3)
C3.20 Welded Attachments Applicable Surface IWC-2500-5 (2X4X6)
IWC-3512 83 TED Pumps (1) (3)
C3.30 Welded Attachenits Applicable Surface IWC-2500-5 (2X4X6)
IWC-3512 14 T1D Valves C3.40 Welded Atachments NA to Unit 2*
0 TBD Totals ExAmiustion Category C-C 119 TBD NOTES.
(1) E-o na is limited to those welded aandiments that mea the following cosditions:
(a) the amameot is on the outside surface of the j"We, retainig component; (b) the aotfohmt provides comxpoent support as defined in NF-I le0; (c) the 2tachaaiot weld join the am*chmeet either diretly to the soefan of the compoewe orto m mitotuily cuse or flfd atocIoCat to the c*mpoae and (d) the attach*ent weld is fall peactation, fillet or patial peneusetao, Contious, or mueraittent (2) The extent of tý examination includes essentially 100% of the length of the atchment weld at ebch attahment subjet to emaminatio.
(3) Selecbte samples of welded aftacheannut shall be eamined each inspection ioterval.
(4) For multiple vessels of similar design, tenfion, and service, only ow welded atachmena of only one of the mulhiple veselsshallbe selected fix enn mastion.
(5) For piog. pumps, and valves, a sample of 10% of the welded avachmeots assoeiated with the component supports selected for exm*asat*on ader IWF.2510 shall be examind.
(6) Ex*f*at*on is rmputed wev compoent suapport mehber defoewatios e.g., brokeo, bhat, or pulled our parts
- g ioperatio.
tefeli s
nas
- c.
mtawno or mtt TBD - To be determined I
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 rWc
SUMMARY
TABLES PRESER ViCE INSPECTION PROGRAM PLAN Page 39 of 74 Examination Category C-D, Pressure Retaining Bolting Greater than 2 in. in Diameter Inspection Proigram B ItemCo Component C
Exan Rquir n
rq Eent y f Acceptance Total Required No xmie omplinen Exa Requirements Frequtency of No.
Examined compliace Method Fig. No.
Exam Standard Population Examination Pressure Vessels (1) (2)
All bolts or Studs at he "WC-3513 C4.10 Bolts and St*ds Applicable (o5u)ie IWC-2500-6 bolted TBD (5) connecton (5)
(16 bolts)
(4)
Piping (3)
C4.20 Bolts and Studs NA to Unit 2 0
TBD PUMPS C430 Bolls and Studs NAto Unit 2 0
TBD Valves C4.40 Bolts and Studs NA to Unit 2 0
TBD Total Examination Category C-D 1
TBD I
I NOTES:
(1) The examination may be performed on bltmg in place under load owp on dismembly of tlh connection.
(2) Thm et axtion ofbotting for vessel puaps, or valves may be conducted c one vessel, wne pump, or one vave among a oup of vel pumps, orv*v* tb are -
an s 1
o m
addiion, whe the compoont* to be examined omatais a group of bolted conneciom of sinilar d agn d aim (suh As flanged connection or maway eav=e the easinaton maybe conducted on me belted comac on among the grop.
(3) The
-amination of fmi-bolting in piping systems my be limited to 00e bolted connection among a group of bolted connectimntt me similar in design, sim f untion, aod siv.
(4) The maas selected for tE initial examminaion shall be reesammed in the same seqacnce over the service lidtia ofte compces, to the extent practical.
(5) W*me bolts or shads ae removed for amimation, sunfoace eaxaimaon meeting the acceptance sndards ofIWB.3515 may be sibstaited for votemonic emmination.
TBD =To be determined
WBN-2 PSI REVISION 2 WATTS BAR UNIT - 2 IWC
SUMMARY
TABLES PRESERVWCE INSPECTION PROGRAM PLAN Page 40 Of 74 Examination Category C-F-i, Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping Inspection Program B Item Component Component Exam Examination Extent and Total Required No.
Exained Compli Method Reurements Frequency of A tance Population Examination ICmplanc_
Mehod Fig, No.
Exam (2)
(2)(3)
C5.10 Piping Welds > 3/9 inm Nominal Wall Thickness 100% of for Piping >NPS 4 each weld C5.11 Cintunferential Welds (> NPS 4) requiring RMRS Applicable Vol- & Sur.
IWC-2500-7 exam IWC-3514 270 21 SIS Applicable Vol. & Sur.
IWC-2500-7 (4X5X6)
IWC-3514 155 12 C5.20 Piping Welds > 1/5 in. nominal Wall Thickness 100% of for PipingZ 2 and* NPS 4 each weld C5.21 Circurnibentral Welds (1)
Applicable Vol. & Sur.
IWC-2500-7 requiring IWC-3514 T3D TBD (High Pressure Saety Injection) exam (4X5X6) 100% of each weld C5.30 Socket Welds Applicable Sur.
IWC-2500-7 requiring IWC-3514 TBD TBD exam (4)(5X6) 100% of C5.40 Pipe Branch Connections of Branch Piping >
each weld C5.41 NPS 2requiring C5.41 NP 2 IWC-2500-ea Circumferential Weld Applicable Sur.
9,l0,I,2&3 (4)(5)
IWC-3514 TBD TBD Total Examination Category C-F-I TBD TBD
WYBNK-2 PSI REVISION 2 WATTS BAR UNIT-2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 41 of 74 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 < lNS 4 (DN 100) apply to PWR high pressuoe safely injection and amitinay feedwater systems in accordane with the exemption etzioia of WC-1220.
(2) The wmkls selected for e
.a.on shall include 7.M btm o n less tian 2n welds, of al dissitalar mtal, asiloattc stainles steel at high alloy melds not ototpt* d by IWC-1220. (Some welds not exempted by IWC-1220 ate not requirnd to be nondesoructively examined per Exatination Category C-F-1. These welds, weve, shal be included to the total wold cat to which the 73% sampling rate is applie&) The examinations shall be distibouted on fowlows:
(a) the examtinatios shall be distributed amons the Cltss 2 systems prorated, to the degree practicable on the ntmber of tonenipt dissimilar metal, iastemic stainless steel, orhigh alloy welds in oat hystem (i.e., if a tystem contains 30% of tte noroxempt welds, thie 30% of the noadesodtve examinations requited by oxatin aon Category C-F-I should be perotemed oa that system);
(b) withila syste, the examinatioa* shall be distibuted among terminal ends, disaimilr metal welds, and struttual discoittinuities [Se Note (3)] prorated, to th degree peactziable, on fhe namber of ooneocmpt terminal ends, dismilat metal welds, and stuctural discooanmitiaen in that system, and (c) withi eaoh system examatmijons shall be disributed betwee line sizes proat-ed to the degree praticable.
(3) Structal discontinuities mnclde pipe weld joints to vessel nozzol* wsave bodies, pump casings, pipe fitings (tnob s eflbws, tecat reducers, Gaugs, e*c., canfatonag to ANSI BIti 9). and pipe branch connets and (4) The melds selected for examination shall be ree* a
- ined in t me sequence, dating subsequent inspectioni interals ove the senlile itits ofthe piping component, to the extent praotical (5) For circumfential welds with intersecting longniudinal welds, surfife examination of the longitulinal piping welds is requited for dthae pattimis of the wolds within the examition obonndaries of itnte citing
-cntaa*er ia w*lds.
(6) Fat cra*tintaea welds wh m sectit langiotdinal welds, volumoltie examination of the longinalial piping welds is required for those portions ofthe wslds within the examinatiomn bonaries of fintagectiag cirmansfirential melds. Thie following rqnrenmerto shall also he roet (a) When longitndinal welds ae spetibed and location ae known, examination requirement sbthll be met for beth treanserse rad parallel flawsat dth interseentn of the melds and far tht l-efnt of lo.gtuelinal weld witda the ciraumferential wold exanumaison volunme (b) Wha loagtudiml welds ar specied but locatons me tanknown, or the existence of lagtdin welds in uncertain, the exmiatims reqadremets shall he met for both leonseetne and pwael flaws within the entire examination volume of intersecting wneumfototial melds.
TBD - To be determined
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 WC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 42 of 74 Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Ins pection P ram B Item Component Component Exam Eammation Extent an Total Restuirn No.
Examined Compliance Method Requirements Freqenoy of Sta c
Population Exammaion Fig No.
Exam Stadard (2)
(2)(3)
C5.50 Piping Welds a 3/8 in. Nominal Wall Thickness 100% of for Piping >NPS 4 eahwl C5.5t Circumferential Welds (1) rexamin FWS Applicable VoL & Sur.
- 4) 7 IWC-3514 100 8
MSS Applicable Vol. & Sur.
IWC-2500-7 (4X5)())
IWC-35l4 138 11 C5.60 Piping Welds > 1/5 in. nominal Wall Thickness 100% of fDr Piping > 2 and <NPS 4 each weld C5.61 Circunferential Welds (1)
Applicable Vol. & Sur IWC-2500-7 requiring IWC-3514 TBD TBD exam (5X6)(7)
C5.70 Socket Welds NA to Unit 2 C5.90 Pipe Branch Connections of Branch Piping C5.81 NPS 2 Circumferential Weld (IX4)
NA to Unit 2 Total Examination Category C-F-2 TBD TBD
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 IWC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 43 of 74 Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Inspection Program B NOTES:
(1) Reau-esuent for examination of welds in piping SNPS 4 (DN 100) apply to PWR bigh pessune safety injectionand awitvy eede*tertsystems, inaccordancewithte exemption criterc aof[ WC1220.
(2) Ths welds selected for exnmation shall include 7 5%,ý bot not less than 28 welds, of all en'ocn end low aliny stel welds neat exempted by 1WC-220. (Some wnlds nut exenpted by IWC-1220 me not rqnied to bn nondenuouvci exay mined per Examination Category C-F-2. These welds, however, shall be included in the total weld count to which the 7.5% sampling te is appied.) The amitioes shall be disn"ihted as follows (a) the exosmsnaious sh"ll be distrhssoed omons the Class 2 systems prorated, to the degreep lcachable, on the osanhr of xne pt caton nod lo alloy steel welds in each system (ie., ifa system contains 30% oftbe nosexempt welds, then 3 V% of the nondesstuctive examinatsons requied by Exaumsaton Categosy C-F-2 should be perfosmed on tiht system)
(h) within a systemn, the examauotionso shall he distributed among totminol ends ond tlshctuafsssoldnaoudnames,
[sceNote (3)] prorated, to the degree practicable, on the numbee of noexemespt termutsial ends asd ostruatsal discoutinuities in dtat system; and.
(c) withi caach system, exammatioos e*lfl be distribted hetween line siesn prorated to tho degree practicice.
(3) Structural docornmtse sinclude pipe weldjeints to vessel n=les valve bodies, pomp muego, pipe fitlings (tuch as elheses tees, reducers, Ranges, st., conforming to ANSI B 16.9), end pipe brtash connections and fittings.
(4) The welds seineted for esamnonua shall be reexamied ur the sarne sertunce, daring subsequnt inspedroa inevals ovre the service I ofthe piping component, to the mcxnt prectcal.
(5) Only those welds shosing repovtable preseros transverse sein&=n need to be examined *y*th ultsasonic method fthe eflectoss mansverse to the weld length dionion, etcepet la ciwmfinel welds with rslerseaing looegrlo al weld shll meet Note (7).
(6) For shcusss*fen*tal welds with inmtersecting longitudinal welds, surface eamsinanion of the longitsdinal pipmg welds in reqated thr those postins ofshe welds within the mxmmaban houndaries of inteectitg rondamferenat welds.
(7) For catcum-ferental welds with intersecting longitudinal welds, volumetin Iema on ofthe longitudinal pipsng welds is requi for tose portios ofthe wel within the examination hoondaies ofinsersectiug cocuosferential welds. The following requirements shall also be met (s) When longitudiml welds art specified and locanorm are known, exasiation requlirements shall be met for beth nantswes and parallel flaws at the heerserton of the welds end for tint length of longitudina weld within the circmnferenti*l weld exanination volume.
When longitudinal welds se specifid but locations are aknow., or tee existance of longitudinal welds in unertei, the shll he met for both Movt andparsllel flw within. the t*ce exanmiaon volume of intssec=g cuetemteal welds.
TBD = To be determined
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 WIC
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 44 of 74 Examination Category C-G, Pressure Retaining Welds in Pumps and Valves Inspection Pro Tam B Item Component Component Exam Acceptance Total Required No.
Examined Compliance Nfetfrd Requrretl Frequenay of Standard Population Examination Fig. No.
Exam Pumps C6.10 Pumps Casing Welds NAto Unit 2 Valves (IX2X3)
C620 Valve Body Welds Applicable Surface IWC-2500-8 (4)
IWC-3515 TBD TBD Total Examination Cateeory C-G TBD TBD NOTES:
(1)k Incae of multiptepumps or solve of simia design, sime function, and service in a system, reqaired weld examinations maybe Hemiled to allfthewas in new pumap or we valve mtote same grosaor sdiebated among any of te pumps or valves of Iat same group.
(2) The enmisttion may be performed from eita the Smsid or outside sutace ofthe compoDen.
(3) The pamps and valves iidally selected for examimaton shall be reexamined in the sane sequente over the service titedm of Sm osent, to th extent pracsial.
(4) 100% welds in all compoaene in each piping rss examined uande Examiasion Czapry C-F, ach inspection mterval.
T111
= To be dateemiand
WBK-2 PSI REVISION 2 WATTS BAR UNIT'- 2 riND
SUMMARY
TABLES PRESER VICE INSPECTION PROGRAM PLAN Page 46 of 74 SECTION 6.0 IWD
SUMMARY
TABLES for ASME CLASS 3 INDEX CATEGORY D-A, Welded Attachments for Vessels, Piping, Pumps and Valves ASME Section XI itemas 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 2 WATTS BAR UNIT-2 FWvD
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 48 of 74.
Examination Category D-A, Welded Attachments for Vessels, Piping, Pumps and Valves Inpection ram B Item Component Component Exam eqtitao nt atyo Acceptance Total REqutted CoepuianenMeths Frequency of Standard Populatio Examination No.
Examined Compliac Method Fig No.
Exam Pressure Vessels (1)
D1.10 Welded Attachments Applicable VT-I TWD-2500-1 (2) (4X5)
IWD-3000 TBD TBD Piping (1)
D120 Welded Attachments Applicable VT-1 IWD-2500-1 (2) (4X5)
IWD-3000 TBD TBD Pumps (1)
Dl.30 Welded Attachments NA to Unit-2 Valves (1)
'1D.40 Welded Attachments NA to Unit-2 Total Examination Category D-A TBD TED NOTES:
(1) Examination is limited to those welded attadchents that meet the following cooditions:
(a) the attaehmeat is on the oatside rethe of the pressre retaining component (b) the ngtach-est wpovides o0tponmt sqlpport as dened in NF-1t0, (c) the aetadcment weLd joins the oancaheet either directly to the staface of the eomponent or to an integrally east argod attachment to the component, and (d) the earclaendn weld is 1411lpeatenation, fillet, or partial pernetation, coannutous. or internmiten (2) The extent of the examination includes eseaetially I 00% of the length of the attehmcent weld at eaeh attachment subject to exadnadnot.
(3) N/A to WBN-2 Pttservice Exainatton (4) Exatination i requmied wheaever component supoprt membet detaion, e.g., broken, beat ar pulled oitparts, ts htitfed datg opeatne, refefh.
manmenne, wasnaftoe, ortestm&
(5) 100% of requred area ofaaelt welded attahments, each mnspection interal or each occure-nce identified in note (4ý TBD = To be detmmiied I
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 IWF
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 47 of 74 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 2 WATTS BAR UNIT-2 IWF
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 48 of 74 Examination Category F-A, Supports Inspection Program B Item Support Types Emined Component Exam Examirenatio Extent of Acceptance Total Required No.
Compliance Method RFiCNom.ts Exam Standard Population Examination Fig. No F110 Class 1 Piping Supports (1) (2)
Applicable VT=3 IWF-1300-1 (5)
IWP-3410 TBD TED FI-20 Class 2 Piping Supports (1) (2)
Applicable VT-3 IWF-1300-1 (5)
IWF-3410 TED TBD F1.30 Class 3 Piping Supports (1) (2)
Applicable VT-3 IWF-1300-1 (5)
IWF-3410 TBD TBD 1.40 Supports O Than Piping supports (1)
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 amb= dSha. be 1ate9rized to idenify support types by COMpontat Mppo fidon (e.&, A = mppm smuch as ace directionl rod bhngn; B = supposts as msti-doecnosai reaa g and miC = uepom dt allow thermal movement, sc as inap). Refnc tables below for emd typo. This is establisbed for far rrtrm (2) The totals s be ompnsed of sop from each system (such as Main Steam. Feedwatee, or RHR, piopatiol to the total aember ofo-e p v4*orts ofeaci type mid fesetia w9ithaca systee Refeencue tables below for each system. This is esablisiml for firtar acthsiota.
(3) N/A to W'BN-2 Prwrice lasperctio.
(4) N/A to WBN-2 Prtsnv tesperhic.
(5) 100% of all supports not exempted TBD = To be rt*dued
WEN-2 PSi REVISION 2 WATTS BAR UNIT-2 IWF
SUMMARY
TABLES PRESERViCE INSPECTION PROGRAM PLAN Page 49 of 74 CLASS 1 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Examination Item Exam Total Category Number Type & Derption Method Number FI.IOA Type A Supports (one directional restraints)
Visual, VT-3 TBD F-A, F1.1OB Type B Supports Supports (multidirectional restraints)
Class I Type C Supports Piping FI.10C (thermal movement, i.e. variable or Visual, VT-3 TBD constant springs)
F1.10D Type D Supports Visual, VT-3 TBD (Snubber Types)
To TED CLASS I NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE Type A Type B TypeC_
Type D Ss Total Reg.
Total
% IReq.
Total Reg.
Total
% IReq.
Ttl CVCS 100 100 100 100 RCS 100 100 100 100 RHR 100 100 100 100 RH]RS 100 100 100 100 SIS 1
100 100 ----- -
100 100 TED TED TBD - To Be Delommed
WBN-2 PSI REVISION 2 WATTS BAR UNIT-2 IWE
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN pag 50 Of 74 CLASS 2 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Examination Item T
Exam Total Cateory Number Type & Description Method Number F1.20A Type A Supports (one directional restraints)
F-A, FI.20B Type B Supports Visual, VT-3 TBD Supports (multidirectional restraints)
Class 2 Type C Supports Piping F1.20C (thermal movement, Le. variable or Visual, VT-3 TBD constant springs)
FI.20D Type D Supports Visual, VT-3 TBD (Snubber Types)
I Total TBD CLASS 2 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE Sys Tye A Tye B TypeC Type D Totals Sys Total Req.
Total Rea.
Total Reg.
Total Req.
AFWS 100 100 100 100 CSS 100 100 100 100 CVCS 100 100 100 100 FWS 100 100 100 100 MSS 100 100 100 100 RHRS 100 100 100 100 SIS 1 100 100 100 100 I_
II ITBD TBD TBD = To Be. Determm
WBN-2 PSI REVISION 2 WAITS BAR UNIT-2 PF
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 51 of 74 CLASS 3 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Examination Item ripion Exam
[NTotal Catgor..
ube Method
-Number FI3OAType A Supports F1.34A TpASuorsVisual, VT-3 TBD (one directional restraints)
F-A, FI.30B Visual, VT-3 TBD Supports (multidirectional restraints)
Class 3 Type C Supports piping FI.30C (thermal movement, Le. variable or Visual, VT-3 TBD constant springs)
FI.30D Type D Supports Visual, VT-3 TBD (Snubber Types)
I Totals TBD CLASS 3 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE SYS A
Type B TypeC Type D Total Sys Total Reg.
Total Reg.
Total Reg.
Total
% IReq.
T AFWS 100 1100 10 100 CCS 100 100 100 100 ERCWS 100 100 100 100 FPCS 100 100 100 100 EUPFPS 100 100 1010 100 F -- r-I 17
-l ITBD
-TB-D TBD - To Be Det*fied
WATTS BAR UNIT-2 PRESERVICE INSPECTION PROGRAM PLAN WBN-2 PSI REVISION 2 IWF
SUMMARY
TABLES Page 52 of 74 CLASS 1, 2 & 3 NON-EXEMPT SUPPORTS DISTRIBUTION BY TYPE Examination Item Type & Descrption Exam J Total Cato Number Method Number FI.40A Type A Supports Visual, VT-3 TBD (one directional restraints)
F-A, F1.40B Typ B Supports Visual, VT-3 TOD Supports (multidirectional restraints)
CIass, 2 & 3 Type C Supports Components F1.40C (thermal movement, Le. variable or Visual, VT-3 TBD constant springs)
F1.40D Type D Supports Visual, VT-3 TBD (Snubber Types)
Totas TBD CLASS 1, 2 & 3 NON-EXEMPT SUPPORTS DISTRIBUTION BY SYSTEM & TYPE Type A TI e ye ye Sys I To Pe B C
I D
Totals Total Req.
Total Req.
Total I%
Req.
Total Rea.
TBD 100 100 100 100 TBD TBD TBD = To Be Deeatumed
WBN-2 PSI REVISION 2 WA TS BAR UNIT-2 AUGMENTED
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 53 of 74 SECTION 8.0 AUGMENTED EXAMINATION REGULATORY TYPE Code Case N-722 Code Case N-729-1 Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials.
Alternative Examination Requirements For PWR Reactor Vessel Upper Heads With Nozzles having Pressure Retaining Partial Penetration Welds.
This Code Case shall be use subject to the conditions specified in paragraphs 10CFR50.55a(g)(6)(ii)(D)(2) through (6) in the Code of Federal Regulations.
The above Code Cases are intended to replace the following NRC Bulletins that are address in the Watts Bar Unit 2 activities:
NRC Bulletin 2001-01 Circumferential Cratndg of Reactor Pressure Vessel Head Penetration Nozzles NRC Bulletin 2002-01 Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity NRC Bulletin 2002-02 Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Program NRC Bulletin 2003-02 Leakage from Reactor Pressare Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity NRC Bulletin 2004-01 Inspection of Alloy 82/1821600 Materials used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurizer Water Reactors The Code Case items that do not apply to Watts Bar Unit 2 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 report.
WVBN-2 PSI REVISION 2 WATTS BAR UNIT-2 AUGMENTED
SUMMARY
TABLES PRESERViCE INSPECTION PROGRAM PLAN....
Page 54 of 74 Examination Category A-E, Augmented Examination Class I PWR Components Containing Alloy 600182/182 (1)(2) tem co ent Component Exam I
Examination I
No Comoned Compone Method Rqui Exte of AcceIptanc Total Required No.
Examined Co Ihc (3)(4X5)
Fig No.
Sandard Population Examination Additional Examinations for PWR Pressure Retaining CC N-T72 Welds in Class I components Fabricated With Alloy 600/82/182 Materials Reactor Vessel B15.80 B15.90 B15.95 B15.100 Steam Genertms 315.110 B15.115 B15.120 B15.130 B15.135 RPV bottom mounted mstrument pentrations Hot leg nozzle-to-pipe connections Cold kg nozxte4o--pipe connections Instrument connections Hot leg nozzle-to-pipe connections Cold leg nozzle-to-pipe connections Bottom channel head drain tube penemraton Primary side hot leg instumentatton connections Primary side cold leg insrumentation connections Applicable Applicable Applicable Applicable Applicable Applicable N/A to Unit 2 N/A to Unit 2 NiA to Unit 2 Visual, VE Visual, VE Visual, yE Visual, VE Visual, VE Visual, VE All penetrations All connections All connections All connections All connections All connections 100%
100%
100%
100%
100%
IWB-3522 IWB-3522 rNB-3522 IWB3-3522 MW-3522 IWB-3522 58 4
4 3
4 4
58 4
4 3
4 4
WIBN-2 PSI REVISION 2 WATTS BAR UNIT. 2 AUGMENTED
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLANPae 5
Of 7
Examination Category A-E, Augmented Examination Class 1 PWR Components Containing Alloy 600V/182 (1X2)
Item Component Component Exam Examination tent Of Acceptance Total Required No.
Examined Compliance Metod Requirements Exam Standard Populaton Eaminatron (3X4)(5)
Fig. No.
Etdd p
to Pressurizer B15.140 Heater penetrations Applicable Visual, VE All penetrations 100%
IWB-3522 78 78 B15.150 Spray nozle-to-pipe conmecton Applicable Visual, VE All conneatl 100%/6 IWB-3522 I
t B15.160 Safety and Relief nozzle-to-pipe connection Applicable Visual, VE All connections 100%
IWH-3522 4
4 BL5.170 Surte nozzle-to-pipe conetion Applicable Visual, VE All connections 100%
1W8-3522 1
1 B15.180 Isrument connections N/A to Unit 2 B15.190 Drainnozzle-to-pipe connection N/Ato Unit 2 Piping B15-200 Hot leg instrunentation otnnection N/A to Unit 2 B15.205 Cold leg insumtmnation connection N/A to Unit 2 B15.210 Hotieg full penetration welds N/Ato Unit 2 B15-215 Cold leg ful penetraion welds N/A to Unit 2 (1) ALuoyt6tdIS$lS q~va =U NSNO6600(S-ld3, taitt ta-it?, SB-itt ad SB-5t4ýLUNSN0tOS(SFA 5.14 tsctC,-3).,t UNS Wt6lt2 ISFA5.11 EllrC~e-3ý (3) Th Vnaaj Exaso oaVE) prloed o,e eAlloy 6eo/i n/iionsape,~aft hrdenoaf~einn ounare~y -n~eito udeeaqig~ondft anti o~le~opo~qeau sWalfcuftsehalon (a) A aie iVE othebwooaul mrace poreo wdini the jeaio
, ronoa.. Akonu~vy. theVE mey be puterfino T1tie thatc mle d
esc~li~et~eeef proies
-bf-rdnai es~.. p.-e meta i b eqleaeW.hea-(b) The VE m~y be peoloreeed b.ethey~e W -oroepaool.idipeee-ia&
(0l The dinxxVE sbal be, palbuned a a distane W gr~eeee, a4 R (1.2 m) freese oomam nciat end vh adeemaaeeees ilhunfinnialeMe esuficien i allow eenohnion oflneeciat b.-b-aehavinga ngin ofnaft 2-ea do itt10 in (2.7 oeel.
(4) P-4ma perfirtningbte VE ebel be qeelliet as VI-2 Vnes
-ineivs end bel h neapisiti nelinnon of tin (4) hoes otettidoml t-n aein otisdeeaofs athneed -se kdowsp tees Alloy tO5V2inc weseassodexendte rliog hosicacid -rosott oafocet fwkisoeam oapunom.e (5) A. a-ei emeaensi-ima perfinnood ft-oes tin oo inpesi do wo %sbed eorae in -looeisthdie requinuem" ofesable rwt-25001 eat Appsendix V01i (1995 Edtison withthe 1996 Addesds is law) "bi W neusblai lies, ofd Ve E seetiamiceoaf the, tatt (6) NA. WBN-2 Presereac Ct)XkeWW42Paese
WBN-2 PS1 REVISION 2 WATTS BAR UNIT-2 AUGMENTED
SUMMARY
TABLES PRESERVICE INSPECTION PROGRAM PLAN Pae-'Of 7
Examination Category A-E, Augmented Examination Class I PWR Reactor Vessel Upper Head Examinaton IExeto Item Component Component Exam RequirEments xet of Acc'ptanc Total Required No.
Examined Compliance Method Fig. No.
Exam Standard Population Examination Alternative Examinationa Requirements for PWR CC N-729-1 Reactor Vessel Heads with Nozzles Having Pressure Retaining Partial Penetration Welds Head with UNS N06600 nozzles and N06082 or W86182 Applicable Visual, VE Fig. l(l 1) 100%
3140 83 83 B4.l0 partial penetaton welds (IX2)
(3)
B4.20 UNS N06600 nozzles and N682 or W96192 partial Applicable vol. &
Fig. 2 (5X1) 00%
3130 93 83 penetration welds SurS.
(7)(10) 14-30 Head with nozzles and partial penetration welds of N/A to Unit 2 PWSCC resistant materials R4.40 Nozzles and partial penetration welds of PWSCC N/A to Unit 2 reirstnt materials in heads Nan (1) tin yEb oMit fh rooorr
-wix-h j
p iLd A) A isu iban orte noaroal wrfno ore.MM no.arufi-offt h"d ivratoaorroly t10t% ofinhe atnoe otehnnkwhf jiehu4 tfordodtdWbobed otnsouina mn pman (t.
orratnn lioaPwo n
nRooM&*toA th ecnnnosum shal xado&t 055% off auo in. ft the na oftbe nozzdo.a doedW in Fiq I wd tohe bmdosure-ll mda dondill ofmoy ch obosrauimo. The nonioo~o my be pathatnýil othndlaor in plýUt roaano
.ppa.d tttn pond. noolno. ot..
apooo -. ot mf-W-41orabn donomrmo (b) The naiwnton maryk pwfixMa roigh tie "Mhn deynoorl lo) Th...
xaot-o h.U bo peronad okh. ffaukioto tnd d.otno detort.11-rsolfo.fl-o-nrna b
ts grtrr
-ta0.t15i h, (2.7 n-) i. WhaLa (0P--d op..tontoaethoVE st t q5.tlen..VT-2 -9
-a d I&B a
meonrrcwtdaa I= tro(4) bf QafdttWisl U=% =
tdeuctnotof bad onk l hm UNS NOdtt. UiNS N06M = UrIS W9612 n.ponnd tnnta knmroddon-i.. otodivon
ý aod ototowoonp (3) tEnottorta moy be pafon wh the syoý daenao-ziod (4) NA f., WEN-2 ft-.n (5n)
If&.-e0 1
enro
.honqotonoo r*pt Zoonbo.o tVe ft~rrv onpofr eoAayodi I hflt ho.d -od fho -boot.shl bo.ftdmiud f. tsondaphntM -
ky hooiontrduiona th p-sWr..
(6)NA toWSRt-Sfrnvi (7) I =
ou&o.r pe~rfo-d, basoha. vooonod -f-
-onirnroo h.lt Wpatoned
(.) forptansith EDY ýZ nivd.ara&odig cuseo (b) for phrn a sh EDY 2t.odEDY:tZ Wn lasatn the soeod ftitng mtaý 0-(o) for1b,ftsooithEDY4. -looth.aFohonry is, sar (d.tsdon 00wiy toWES)
(S) KAf. WD1-250noio (9) NA par 10CaR5.55.
(10) Kohodo oosdUy ton1A ft foo. -vh-(tt) Eonotm Riaoqt R&p SNo. nvrht fpa..refood to CC N-729-1
WBN-2 PSI REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 57 of 74 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 REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVWCE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 58 of 74 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 shell-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 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 59 of 74 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 REOUESTED:
In accordance with ASME Section XI, paragraph IWA-2232, "Ultrasonic examinations shall be conducted in accordance with Appendix L" 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 VIIUPDI 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 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 60 of 74 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 (EPRI) 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 VIII/PDI 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 VIIL/PDI qualification procedures use the tip diffraction techniques for flaw sizing. The proposed alternative Appendix VIII/PDI 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 700 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.
WRN-2 PSI REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 61 of 74 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.
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 conditiohs 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 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE I
I IPage 62 of 74 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 (I,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 X1 Class 1, May be used for all Section XI TP-1 Boundary 2 & 3 Components 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 1 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 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 63 of 74 Basis for Section XI Boundary Identification Watts Bar Nuclear (WBN) Unit 2 ASME Section XI Preservice Inspection (PSI)
TP-I 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 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 64 of 74 Class 3 to Class 2, Class 2 to Class 1 or any combination there of. 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 Xl EXaminations (XIEX) and ASME Section XI Pressure Tests (XIPT) color coded drawings.
- 2)
ASME Section XI Pressure Tests (XLPT)
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 1 or any combination there of. All other boundaries on safety Class systems that represent the activities associated with Section XI are to enhance and distinguish the various pressure test boundaries.
A color coded drawing can be established and labeled (i.e. 2-48W801-1-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 1 or any combination there of. All other boundaries on safety Class systems that represent the activities associated with Section XI are to enhance and distinguish the various examination
WBN-2 PSI REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 65 of 74 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 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 66 of 74 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 conformation 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.
I. 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 E2882IC 144
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 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 67 of 74 TP-3 Watts Bar Unit I and 2 Memorandum of Understanding ASME Section Xi Interface WBN Unit I systems were completed and licensed under the requirements of the ABME Section III program and since then, ASME Section XI has been Implemented. Portions of several Unit 2 systems were documented on Unit I ASME N-6 Code Date Reports as being within the Unit I ASME boundary but are not within the operational boundary for Unit 1.
Boundary calculations and design output (I.e,, Unit 2 aros hatching) shows theme portions of systems as under unit 2 configuration control. As a result of how these portions of systems were Installed end documented, work that needs to be performed In these areas to startup unit 2 will have to be performed to AGME Section:Xl, Returning these portions of systems to ABME Section III Is not an option due to the potential Impact on the Unit I ASME programs and potential delay to Unit 2.
Thefoilowing process will be followed to perform and document ASME Section Xl work on portions of Unit 2 systems outside of the Unit I operating boundary that are documented In Unit I ASME N-6 packages.
Work will be performed In accordance with the Unit I ASME Section XI requirements 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 end WDCRe as needed.
Work will be planned and performed using the Unit 2 Work Order (WO) process which Invokes the requirements of SPP-0.1, TI-100.014, and MMDP-10.
Bechtel Is designated as the RepalrlReplacement organization In accordance with SPP-91, Section 361.
WO's willlbe reviewed and approved by Bechtel QA, Unit 1 Welding and the ASME Section Xi Coordinator.
Planned WO's will be reviewed byithe Unit 1 ASME ANII.
Work wlil be performed by Bechtel, Quality Control inspections will be performed by Bechtel, and endorsed by Unit 2 TVA.
Non-destructive Examinations will be performed by Unit 2 TVA ISOINDE for Section Xl RepairlReplacement.
Radiatlon Protection and Site Support will be performed by TVA Unit 2 staff.
Completed WO's will be reviewed by the Unit I AN II prior to closure, Prior to closing the WOe nd submitting it for ANII review, Bechtel will Issue a Unit 2 WO to punohilet and track to Section XI In-service Leak Test (I8LT).
WO'a will be closed by Bechtel and Work Completion Statements (WCS) Issued.
- The WCS will be processed and EDCR closed by Bechtel.
The EDCR closure package will reference the ISLT WO.
ISLT.shall be performed during or before/after hydrostatic tasting 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 complited work will be documented on the Unit 1 ASME NIS-1 and NIS-2A forms.
TheUnit 11 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.
Pipinglcomponents In these regions will be added to the Unit 2 ASME Section X! 181
-population prior to Unit 2 stertup.
WBN-2 PSI REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 68 of 74 TP-3 Watts Bar Unit I and 2 Memorandum of Understanding ASME Section Xi Interface.
[1 +~ii14 A~
OMauldin" I~ate' t6kq n
i ll 1 3 l
J I G., Mauldin'*'
- Date' WON Unit I Engineering Mgr 0l '6k IL Awh Date wae.It2n e~
nggM qr j16,j M.11e WBN Unit 8lIte VP w
qIRCNooEdineer Date
-1.Wqldlný Engineer Dt i
M. BoJehtani WON Unit 2 VP Date S.4ce 5eA. _(ewoA~
WBN 2IN-5 Group 6a -Date WBN 2 Welding Engineer Date 1 7. w ý WBN 1 ANII el Date MX2 Date WP, 2 -Nuclear Assurance (D*M BS 29Bechhd eld Erglneerlng Date J2~v~f fZ. :3W.tA GM4A This document can be found in BSL (Business Support Library) file "WBN, Unit 2-NGDC, TVA Unit 2, General Information, MOU-6.
The 30 Drawings specifically referenced in the table of contents have been processed into ADAMS.
These drawings can be accessed within the ADAMS package or by performing a search on the Document/Report Number.
D-01 thru D-30
WBN-2 PSI REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 69 of 74 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 47W801-' 2'.
47W803-4.l 47W803-2 47W803-3 47W809-1 47W809--2 47W809-3 47W809-5 47W809-7 47W809-9 47W810-1 47W811-1 47W812-1 47W813-1 47W814-2 47W819 47W830-1 47W845 47W845-2 47W845-3 47W845-4 47W845-5 47W850-2 47W855-1 47W859-1 47W859-3 47W8594-&'
47W862-2..
47W865-5 Main & Reheat Steam (1)
SG Blowdown (1)
Feedwater (3)
Chemical & Volume Control (62)
CVC & Boron Recovery (62)
CVC & Boron Recovery (62)
CVC & Boron Recovery (62)
Flood Mode Boration Makeup (84)
Chemical & Volume Control (62)
Safety Injection (63)
Containment Spray (72)
Reactor Coolant (68)
Ice Condenser (61)
Primary Water (81)
Waste Disposal (77)
Essential Raw Cooling Water (67)
Essential Raw Cooling Water (67)
Essential Raw Cooling Water (67)
Essential Raw Cooling Water (67)
Essential Raw Cooling Water (67)
Fire Protection Raw Service Water (26)
Fuel Pool Cooling & Cleaning (78)(62)
Component Cooling (70)
Component Cooling (70)
Component Cooling (70)
SG Wet Layup, Closed Recirculation Loop (41)
Air Conditioning Chilled Water (31) 2 2
2 2&3 3
1,2&3 2&3 3
3 2&3 2
1,2&3 1,2&3 2&3 1&2 2
2 2
3 3
2&3 3
3 3
2&3 3
2&3 3
2 2
WBN-2 PSI REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 70 of 74 Drawing Number ISI-2001-W-01 ISI-2001-W-02 ISI-2001 -W-03 ISI-2001 -W-04 ISI-2062-W-01 ISI-2062-W-02 ISI-2062-W-03 ISI-2062-W-04 ISI-2062-W-05 ISI-2062-W-06 ISI-2063-W-01 ISI-2063-W-02 ISI-2063-W-03 ISI-2063-W-04 ISI-2063-W-05 ISI-2063-W-06 ISI-2063-W-07 ISI-2063-W-08 ISI-2063-W-09 ISI-2063-W-10 ISI-2063-W-11 ISI-2063-W-12 ISI-2063-W-13 ISI-2063-W-14 ISI-2068-W-01 ISI-2068-W-02 ISI-2068-W-03 ISI-2068-W-04 ISI-2068-W-05 ISI-2068-W-06 ISI-2074-W-01 ISI-2074-W-02 ISI-2074-W-03 ISI-2074-W-04 ISI-2074-W-05 ISI-2074-W-06 COMPONENT LOCATIONS Drawing Title.(System)
MSS WELD LOCATIONS MSS WELD LOCATIONS MSS WELD LOCATIONS MSS WELD LOCATIONS CVCS WELD LOCATIONS CVCS WELD LOCATIONS CVCS WELD LOCATIONS CVCS WELD LOCATIONS CVCS WELD LOCATIONS CVCS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS SIS WELD LOCATIONS RCS WELD LOCATIONS RCS WELD LOCATIONS RCS WELD LOCATIONS RCS WELD LOCATIONS RCS WELD LOCATIONS RCS WELD LOCATIONS RHRS WELD LOCATIONS RHRS WELD LOCATIONS RHRS WELD LOCATIONS RHRS WELD LOCATIONS RHRS WELD LOCATIONS RHRS WELD LOCATIONS Code Class 2
2 2
2 1
1 1
1 1
1 2
2 2
2 21 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1&2 2
2 2
2 2
WBN-2 PSI REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERWCE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 71 of 74 Drawing Number ISI-2074-W-07 ISI-2074-W-08 ISI-2074-W-09 COMPONENT LOCATIONS Drawing Title (System)
RHRS WELD LOCATIONS RHRS WELD LOCATIONS RHRS WELD LOCATIONS Code Class 2
1&2 1&2
WBN-2 PSI REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Program Terms PROCEDURE Page 72 of 74 SECTION 12.0 TERMS ACWS:
Air Conditioning Chilled Water System (3 1)
ALARA:
As Low As Reasonably Achievable ANIL:
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 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM.PLAN Program Terms PROCEDURE Page 73 of 74 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:
RPV:
WBN-2 PSI REVISION 2 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Program Terms PROCEDURE Page 74 of 74 RSW:
RLV:
RT:
RX:
S:
SCH:
SDCHX:
SD:
SER:
SG:
SGBD:
SH:
SIS:
SI:
SUR:
SFPC:
SS:
SXI:
Tee:
TK:
Tech. Spec:
TRM:
TVA UFSAR:
UHIS:
UT:
VCT:
VOL:
VT:
VT-I:
VT-2:
VT-3:
VE:
WDS:
WBN:
W:
Raw Service Water (System 25)
Relief Valve Radiograph Examination Reactor Supports Schedule Shutdown Cooling Heat Exchanger Shutdown Safety Evaluation Report Steam Generator Steam Generator Blowdown (System 1 & 15)
Sheet Safety Injection System (63)
Safety Injection Surface Examination Spent Fuel Pit Cooling (System 84)
Stainless Steel Section XI, Rules for Inservice Inspection Tee Thickness Technical Specification Technical Requirements Manual Tennessee Valley Authority Updated Final Safety Analysis Report Upper Head Injection System (87)
Ultrasonic Examination Volume Control Tank Volumetric Examination Visual Examination Visual Examination for Detection of Surface Conditions Visual Examination for Evidence of Leakage Visual Examination for General Mechanical and Structural Condition Visual Examination (VT-2 Augmented Type)
Waste Disposal System (77)
Watts Bar Nuclear Welds Flow Diagrams with Class Boundaries Watts Bar Nuclear Plant Units 1 and 2 Piping System Classification TVA ANS CLASS AFETY CODE JURISDICTION BOUNDARY CLASS A
1 Class 1, ASME Boiler and Pressure Vessel Code Section III B
2a Class 2, ASME Boiler and Pressure Vessel Code Section III C
2b Class 3, ASME Boiler and Pressure Vessel Code Section III D
3 Class 3, ASME Boiler and Pressure Vessel Code Section III G
Unclassified System K
Unclassified System L
Unclassified System M
2b ANSI B31.5 N
2 ANSI B31.5 P
Class 3, ASME Boiler and Pressure Vessel Code Section III Technical Specifications and Steam Generator Tubing Program Plant List of Commitments
- 1. Plan for preservice inspection and testing of snubbers will be provided no later than June 15, 2010.