ML083090046

Preservice Inspection Program Plan and Request for Relief No. WBN-2/PDI-4

ML083090046
Person / Time
Site:	Watts Bar
Issue date:	10/30/2008
From:	Bajestani M Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
WBN-2/PDI-4, FOIA/PA-2013-0030, FOIA/PA-2013-0139
Download: ML083090046 (77)

Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, TN 37381-2000 October 30, 2008 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 In the Matter of ) Docket No. 50-391 Tennessee Valley Authority )

WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - PRESERVICE INSPECTION PROGRAM PLAN AND REQUEST FOR RELIEF NO. WBN-2/PDI-4 Reference 1: TVA letter dated January 29, 2008, 'Watts Bar Nuclear Plant (WBN) -

Unit 2 - Regulatory Framework for the Completion of Construction and Licensing Activities for Unit 2" Pursuant to 10 CFR 50.55a (a)(3)(i), TVA is submitting a relief request for the WBN Unit 2 Preservice Inspection (PSI) Program. provides relief request WBN-2/PDI-4, which proposes an alternative to ASME Section XI, paragraph IWA-2232 of the ASME Section Xl 2001 Edition through the 2003 Addenda. This request proposes to use Appendix VIII and the Performance Demonstration Initiative (PDI) methodologies for performance of the ultrasonic examination of the reactor pressure vessel shell-to-flange welds in lieu of the requirements of Appendix I and the associated Article 4 of ASME Section V. The proposed alternative provides an acceptable level of quality and safety as required by 10 CFR 50.55a (a)(3)(i). provides an information copy of WBN Unit 2's PSI program. In Reference 1, TVA provided an "Action Required for Licensing" to submit the WBN Unit 2 PSI Program on or before October 30, 2008. The 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 of evaluation results. The ASME Boiler and Pressure Vessel Code,Section XI, 2001 Edition through the 2003 Addenda was used to develop the WBN Unit 2 PSI program. The Authorized Nuclear Inservice Inspector has reviewed the WBN Unit 2 PSI program. The quantity of individual items listed in the summary tables for "total population" and "required examination" will be established as part of WBN Unit 2 construction completion.

Printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 October 30, 2008 Note that this request for relief is similar to the request granted to WBN 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 NRC in a letter dated February 29, 2008 (ADAMS Accession No. ML080630679). This relief request is numbered as WBN-2/PDI-4 for consistency across the units.

TVA requests NRC approval of relief request WBN-2/PDI-4 by June 2009 to support the PSI schedule.

If you have any questions, please contact me at (423) 365-2351.

Sincerely, Masoud Baj jtani Watts Bar it 2 Vice President Enclosures cc: See page 3

U.S. Nuclear Regulatory Commission Page 3 October 30, 2008 cc (Enclosures):

Lakshminarasimh Raghavan U.S. Nuclear Regulatory Commission MS 08H4A One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Patrick D. Milano, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08H4 One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 Loren R. Plisco, Deputy Regional Administrator for Construction U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 U. S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381

Enclosure 1 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 use of an alternative methodology to that contained in ASME Section Xl, paragraph IWA-2232 of the ASME Section XI 2001 Edition through the 2003 Addenda, for the preservice examinations at WBN Unit 2. Specifically, this request is for use of Appendix VIII and Performance Demonstration Initiative (PDI) methodologies for performance of the ultrasonic (UT) examination of reactor pressure vessel (RPV) 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 requirement to perform the volumetric examination of the RPV circumferential shell-to-flange weld at WBN 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, WBN Unit 2 will use the techniques, personnel, and equipment qualified to meet the requirements of ASME Section Xl Appendix VIII, Supplements 4 and 6 of the 2001 Edition through the 2003 Addenda, as administered by the Electric Power Research Institute's (EPRI) PDI processes. WBN plans to use the proposed alternative for the preservice RPV examinations to be performed prior to commercial operation. This proposed alternative represents the best available methodology in qualification of equipment and personnel performing UT examinations and uses an examination process that 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 will result in a reduction of the cost of performing the examinations by pý'ecluding the use of two different sets of examination equipment and will result in lower personnel radiation exposure during future examination by allowing the same methodology for the shell-to-flange weld.

Note that this request for relief is similar to the request granted to WBN 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 NRC in a letter dated February 29, 2008 (ADAMS Accession No. ML080630679).

Enclosure 1 SYSTEM/COMPONENT(S) FOR WHICH RELIEF IS REQUESTED:

ASME Code Class 1 RPV Upper Vessel Shell-to-Flange Welds, Table IWB-2500-1 Category B-A, Item Number B1.30.

APPLICABLE CODE EDITION AND ADDENDA FOR THE GIVEN EXAM:

The applicable ASME Section XI code edition and Addenda of Record for WBN Unit 2 PSI is the 2001 Edition through 2003 Addenda with applicable amendments from 10 CFR 50.55a.

CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED:

In accordance with ASME Section XI, paragraph IWA-2232, "Ultrasonic examinations shall be conducted in accordance with Appendix I."

Further, in accordance with Appendix I, paragraph 1-21 10(b), "Ultrasonic examination of reactor vessel-to-flange welds, closu re 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 REQUESTED:

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 UT examinations of the RPV upper shell-to-flange welds using Section XI, Appendix I, which in turn requires the use of the nondestructive examination 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 is 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. Recent EPRI PDI coordination meetings between the PDI committee members and the NRC Staff representatives have indicated that the NRC Staff expects licensees to submit requests for relief to use the more technically advanced Appendix VIII/PDI processes for the shell-to-flange weld exams in lieu of the Section XI, Appendix I, and its associated Section V, Article 4 processes.

Enclosure 1 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 EPRI's 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 examination 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 examinations 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 do not take into consideration such factors as flaw orientation, which can influence the amplitude of responses.

The EPRI Report NP-6273, "Accuracy of Ultrasonic Flaw Sizing Techniques for Reactor Pressure Vessels," dated March 1989, established that UT examination flaw sizing techniques based on tip diffraction are the most accurate. The qualified prescriptive-based UT examination procedures of ASME Section V, Article 4, have been applied in a controlled process with mockups of RPVs which contained real flaws and the results statistically analyzed according to the screening criteria in Appendix VIII of ASME Section XI. The results show that the procedures in Section V, Article 4, are less effective in detecting flaws than procedures qualified in accordance with Appendix VIII as administered by the PDI processes. Appendix VIII/PDI qualification procedures use the tip diffraction techniques for flaw sizing. The proposed alternative Appendix VIII/PDI UT examination methodology uses analysis tools based upon echo dynamic motion and tip diffraction criteria that has been validated and is considered more accurate than the Section V, Article 4 processes.

UT examination 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 during post-operational examinations. Complying 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.

Enclosure 1 For future RPV shell-to-flange weld examinations, TVA does not anticipate any less coverage than the required minimum of greater than 90 percent. 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, resulting in increased reliability of RPV inspections. Therefore, the proposed alternative methodologies provide 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 PSI for WBN Unit 2.

PRECEDENTS This request for relief is similar to the request granted to WBN 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 29, 2008 (ADAMS Accession No. ML080630679).

Enclosure 2 WBN Unit 2 PSI 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 37381 Docket Number 391 Construction Permit No. CPPR-92, Issued January 23, 1973 Extension Issued October 24, 2000 Program No: WBN-2 PSI Rev. 1 Effective Date: Octnher 23. 21009 Responsible Organization: nsoection Services Organization Prepared by: E. Lnn MeC b 40e Approved by I'If /fj

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTIONPROGRAM PLAN REVISION I PROCEDURE Page 2 of 69 Revision Log I 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.

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 1 PROCEDURE Page 3 of 69 TABLE OF CONTENTS 1.0 Sum mary ........................................ ................................................................................... 4 2.0 C ode A pplicability ............................................................................................................. 5 3.0 D escription ........................... ................. ........................................................................ 6 3.1 Scope .............................................................................................. .................... 6 3.2 Jurisdiction ........................................................................................................... *.6 3.3 R esponsibility .................................................................................................. 7 3.4 Application ...................................................................................................... 7 3.5 Classification and Boundaries .................................. 8 3.6 A ccessibility ......... s.. ................................................... I..................... ................ 9 3.7 Referenced Standards and Specifications ...... .................... 10 3.8 Examination Methods ...... ................................. 10......

3.9 Nondestructive Examination Personnel ............................................................... 1-1 3.10 Inspection Intervals .......................................................................................... 11 3.11 W eld Reference System ................................................................................... 11 3.12 Program Plan and Schedule ............................................................................ 11 3.13 Evaluation of Recorded Conditions ................................................................ 12 3.14 Records and Reports ....................................................................................... 12 3.15 IWB Requirements and Exemptions ............................................................. 12 3.16 IWC Requirements and Exemptions ............................. 13 3.17 IWD Requirements and Exemptions ............................. 15 3.18 IWF Requirements and Exemptions .............................. 16 3.19 Code Cases .............................................. 19 3.20 C ode Relief ...................................................................................................... 20 3.21' Augmented Components ................................................................................ 20 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 IWF Sum m ary Tables ................................................................................................ 47 8.0 Augmented Summary Tables ........................ ...................... 53 9.0 Requests for Relief ...................................................................................................... 57 10.0 ASME Section XI - Technical Positions ................................ 62 11.0 Drawing - Reference List .......................................... 66 12.0 ASME Section XI - Terms...................................................................................... 67

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION I PROCEDURE Page 4 of 69 1.0

SUMMARY

As the owner Tennessee Valley Authority (TVA) had established the original Preservice Inspection (PSI) program at Watts Bar Nuclear Plant (WBN) Unit 2 to perform and document the inspection activities in accordance with Technical Instruction (TI) 50B, ASME Section XI Preservice Inspection Program. The latest working revision of TI-50B, Revision 11 dated September 29, 1989 was placed on "Administrative Hold" and on September 04, 1997 Revision 12 was issued to "Cancel" the document with that being the status of the original PSI program.

This document will be reference to establish the present document as needed.

In a letter dated January 29, 2008, Tennessee Valley Authority (TVA) to U.S. Nuclear Regulatory Commission (NRC) and In the Matter of Docket Number 50-391 Tennessee Valley Authority, "WATTS BAR NUCLEAR PLANT (WBN) - UNIT 2 - REGULATORY FRAMEWORK FOR THE COMPLETION OF CONSTRUCTION AND LICENSING ACTIVITIES FOR UNIT 2", it states in Enclosure 1, "TVA Responses to NRC's Request of Information Needed for Licensing Review Reconstitution", item 4.b.iv, is a commitment to provide a revised Preservice Inspection Program.

The Final Safety Analysis Report (FSAR) for WBN-2 is a "red-lined" version to depict/demonstrate how the FSAR will appear at fuel load, as reference in TVA to NRC letter dated February 8, 2008. Based on FSAR Sections 5.2.8, 5.4.4.4 and 6.6, components subject to examination and/or test are components containing water, steam or radioactive waste shall be examined and tested in accordance with ASME Section XI as required by 10CFR50.55a(g),

except where specific written relief has been requested. FSAR Section 5.2.8 is for TVA Class A (ASME Code Class 1) and Section 6.6 for TVA Class B (ASME Code Class 2) and C and D (ASME Code Class 3) components.

This document is being prepared to re-establish the requirements for the Preservice Inspection (PSI) Program Plan at WBN-2, as stated in the previous paragraph. This program plan follows the inspection requirements of 10CFR50.55a(g)(2) which requires that components, including component supports, that are classified as ASME Code Class 1 and 2 must be designed and be provided .with access to enable the performance of inservice examination of such components and supports and must meet the preservice examination requirements set forth in Editions and Addenda of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code or optional Code Cases listed in NRC Regulatory Guide 1.147 that are incorporated by reference in IOCFR50.55a(b), in effect six month before the date of issuance of the construction permit.

The examination categories and requirements for Class 1 components will be in accordance with subsection IWB of ASME Section X1. 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 I PROCEDURE Page 5 of 69 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 1 total may be used and noted with an asterisk (*) until the actual population of Unit 2 is determined. The "total population" and "requited 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 IOCFR 50.55a, that is in effect six month before the date of issuance of the construction permit. 10CFR5 0.5 5a 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 1 PROCEDURE Page 6 of 69 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 times 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 1 PROCEDURE Page 7 of 69 3.3 RESPONSIBILITY The responsibilities of maintaining this PSI Program Plan are included in NGDC PP-15.

3.4 APPLICATION Components identified in this program plan for examination include items such as the reactor vessel, reactor pressure vessel internals (including the core support structure),

steam generators, pressurizer, piping systems (including their valves, pumps and heat exchangers) and all respective supports to the components.

3.4.1 The following items are part of the Section Xi Preservice Inspection requirements, but are not included in this document:

3.4.1.1 The Repair/Replacement (R/R) Program Plan, when implemented, will be utilized to perform the required activities for ASME Section XI components. The Repair/Replacement Program Plan is in accordance with Watts Bar Procedures and 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. 10CFR50.55a(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-4461.2 will be addressed in the Repair/Replacement Program, if needed.

5. 10CFR50.55a(b)(2)(xxv), Mitigation of Defects by Modification will be addressed in the Repair/Replacement-Program, if needed.

6. 10CFR5O.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.

3.4.1.2 The requirements of Examination Category B-P, C-H and D-B, All Pressure Retaining Components for System Leakage Tests, are not required prior to initial plant startup. A System Pressure Test Program Plan and Schedule will be developed as required to perform the examination for systems and components as outlined in ASME Section XI, Articles IWA-5000, IWB-5000, IWC-5000 and IWD-5000 for all Class 1, 2, and 3 components, with the limitations and modifications as outlined in 10CFR50.55a for the inservice interval requirements.

3.4.1.3 The 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

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION I PROCEDURE Page 8 of 69 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 10CFR50.55a(b)(3)(v), Subsection ISTD of the ASME/ANSI OMb 2003 code maybe 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 10CFR50.55a(b)(2)(ix) and subparagraphs (A), (B), and (F) through (M.

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 diagramspertaining to the systems boundaries indicating the TVA Class A, B, C and D or ASME Class 1, 2 and 3 systems, structures and components required to be examined is included in Section 11.

3.5.2 A list of weld and support location drawings based on the flow diagram boundaries and utilized for component identification and location within those boundaries is also included in Section 11.

3.5.3 The rules of IWB shall be applied to those components that are classified ASME Class 1 or TVA Class A.

3.5.4 The rules of IWC shall be applied to those components that are classified ASME Class 2 or TVA Class B.

3.5.5 Therules of IWD shall be applied to those components that are classified ASME Class 3 or TVA Class C or D.

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI

..PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION I PROCEDURE Page 9 of 69 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.

3.6.5 Installation and support of handling machiriery where required to facilitate removal, disassembly and storage of equipment, components and other materials shall be provided.

3.6.4 Performance of examinations alternative to those specified in the event structural defects or indications are revealed that may require such alternative examinations, when necessary.

3.6.5 Necessary operations associated with repair/replacement activities shall be performed.

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 1 PROCEDURE Page 10 of 69

. .............. 3.7 REFERENCED STANDARDS AND SPECIFICATIONS . -----

When standards and specifications are referenced, their revision date or indicator shall be as listed in ASME Section XI, 2001 Edition through 2003 Addenda, specifically Table IWA-1600-1.

3.8 EXAMINATION METHODS ASME Section XI identifies three types of examinations to perform inspections as visual, surface and volumetric. The actual examination method is defined and the techniques used are described in the legend below:

Visual (VT), an examination method used to evaluate an item by observation.

VT - 1 Detection of Surface Conditions VT - 2 Evidence of Leakage VT - 3 General Mechanical and Structural Conditions Surface (Sur), an examination method used to detect the presence of discontinuities on the surface of the material.

PT - Liquid Penetrant MT - Magnetic Particle ET - Eddy Current Note: I 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 componet a peciea 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.

3.8.3 All the above nondestructive examinations willbe performed using specific techniques and procedures that are identified in ASME Section XI, or alternative examinations that are demonstrated tobe equivalent or superior to those identified. The provision for substitution of these alternative examination methods, combination of methods, or newly developed techniques as outlined in IWA-2240 will utilize the 1997 Addenda of Section XI as stated in 10CFR50. 55 a(b)(2)(xix).

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PROCEDURE JPage PRESERVICE INSPECTION PROGRAM PLAN REVISION I 11 of 60 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 documelited 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 i6CFR50.55a 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 VIII specimen set and qualification requirements.

3.9.3 10CFR50.55a(b)(2)(xvi), Appendix VIII single side ferritic vessel and piping and stainless steel piping examination, 3.9.4 10CFR50.55a(b)(2)(xviii), Certification of NDE personnel.

3.9.5 10CFR50.55a(b)(2)(xxiv), Incorporation of the Performance Demonstration Initiative and Addition of Ultrasonic Examination Criteria.

3.10 INSPECTION INTERVAL The Preservice Inspection Program is prepared in accordance with Program B of ASME Section XI.

3.11 WELD REFERENCE SYSTEM A weld reference system, such as N-GP-8 Weld Reference System, will 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.

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. Itshould be noted that the total population and required examinations may change during the preservice examination period due

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 1 PROCEDURE Page 12 of 69

. 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 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 I 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 8-L-2 and B-M-2 and category B-O shall be extended to include only the welds in the outer peripheral of the control rod housings.

3.15.3 Component requirements shall be examined as specified listed in the Summary Tables in Section 4.0 of this document. 10CFR50.55a provides the following requirements in lieu of and in addition to the requirements contained within this document:

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 1 PROCEDURE Page 13 of 69 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 10CFR50.5 5a(b)(2)(xxi) requires inclusion of Items B33.120 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 I components.

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 10CFR50.55a(b)(2)(xi):

3.15.6.1 Piping of NPS 1 and smaller, except for steam generator tubing; 3.15.6.2 Components andtlheir connecionsýth*i ipiping of NPS -land 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

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2, PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION I PROCEDURE Page 14 of 69 excluded from inservice examination,,shall be performecand,*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 exaiiiinations.

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 CH-R systems or portions of systems.

(a) For systems, except the High Pressure Safety Injection; (1) Class 2 piping NPS 4 and smaller; (2) Class 2 vessels, pumps and valves and their connections in piping NPS$,4and smaller,:

(b) Class 2 High Pressure Safety Injection portion; (1) Class 2 piping NPS 1 1/2/and smaller; (2) Class 2 vessels, pumps, and valves and their connections in piping NPS 1 1/22 and smaller (c) Class 2 vessels piping, pumps, valves, other components connections of any size in statically pressurized, passive (i.e. no pumps) portions (i.e., Safety Injection Tanks (SITs) and associated discharge piping);

(d) Class 2 piping and other components of any size beyond the last shutoff valve in opened ended portions of systems that do not contain water during normal plant operating conditions.

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVWCE INSPECTION PROGRAM PLAN REVISION I PROCEDURE Page 15 of 69 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 V2 and smaller; (2) Class 2 vessels, pumps, and valves and their connections in piping NPS 1 Y2 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 2000 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.

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:

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION I PROCEDURE Page 16 of 69 (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-1 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 200°F or less in systems or portions of systems whose function is not required in support of reactor residual heat removal, containment heat removal and emergency core cooling (d) welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration or encapsulated by guard pipe.

3.17.5 Evaluation of examination results shall be in accordance with the acceptance standard requirements listed in the Summary tables of Section 6.0 for IWD Class 3 components.

- Note: Piping is defined as having a cumulative inlet and cumulative outlet pipe cross-.

sectional area neither of which exceeds the nominal outside diameter cross-sectional are&a' of the designated size.

3.18 IWF REOUIREMENTS 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

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION I

.PROCEDURE Page 17 of 69 systems that operate ata temperature-greater than 2009F 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 IOCFR50,55a(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.

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 S q0rppmpnent isthedistance 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

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT , PRESERVICE INSPECTION PROGRAM PLAN REVISION I PROCEDURE Pago 18 of 69 carries the weight.f.o thescomponent-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.

3.18.8 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.

(b) weld connections to building structure (c) weld and mechanical connections at intermediate joints in multi-connected integral and nonintegral supports (d) clearances of guides and stops, alignment of supports, and assembly of support items (e) hot or cold settings of spring supports and constant load supports (f) accessible sliding surfaces 3.18.9 T6e rinh6o"f ekamination 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.

3.18.10 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.

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI

.PROJECT PRESERVICE INSPECTION PROGRAM PLAN* REVISION I PROCEDURE Page 19 of 69 3.18.11- 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.

3.18.12 Examinations for systems that operate at a temperature greater than 200'F during normal plant operation shall be performed during or following initial system heatup and cooldown.

3.18.13 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.

3.18.14 For systems that operate at a temperature greater than 200°F during normal plant operation, Watts Bar shall perform an additional preservice examination on the affected component supports during or following the subsequent system heatup and cooldown cycle unless determined unnecessary by evaluation.

3.19 CODE CASES 3.19.1 The following Code Case is accepted for use in Regulatory Guide 1.147 and shall be utilized where applicable:

N-460 Alternative Examination Coverage for Class I 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.

Conditional use states that, In place of a UT examination, licensees may perform a visual examination with enhian e0d61gnfication that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-35 12-1with 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 Mateiialhsl.§

NGDC PROJECT I WATTS BAR PRESERVICE NUCLEAR PLANT INSPECTION PROGRAM UNITPLANI 2 WBN-2 PSI.1 REVISION PROCEDURE Page 20 of 69 N-729-1 Alternative Examination Requirements for PWR-Reactor-Vessel .7, 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 IOCFR50.55a(a)(3) states "Proposed alternatives tothe 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) Ifthe 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, 3.20.3 10CFR50.55a(g)(5)(iv) states "Where anexamination requirementlby 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. - - ...- I

NGDC WATTS BAR NUCLEAR PLANT UNIT 2 WBN-2 PSI PROJECT PRESERVICE INSPECTION PROGRAM PLAN REVISION 1 PROCEDURE Page 21 of 69 3.214.-- 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 I WATTS BAR UNIT- 2 INS

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 22 of 69 SECTION4.0 -,

IWB

SUMMARY

TABLES For ASME CLASS 1 CATEGORIES B-A Pressure Retaining Welds in Reactor Vessel B-B Pressure Retaining Welds in Vessels Other Than Reactor Vessels B-D Full Penetration Welded Nozzles in Vessels B-F Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles B-G-1 Pressure Retaining Bolting, Greater Than 2 Inches in Diameter B-G-2 Pressure Retaining Bolting, 2 Inches and Less in Diameter B-J Pressure Retaining Welds in Piping B-K Welded Attachments for Vessels, Piping, Pumps and Valves B-L-1 Pressure Retaining Welds in Pump Casings B-L-2 Pump Casings - (NA reference 3.15.2)

B-M-1 Pressure Retaining Welds in Valve Bodies B-M-2 Valve Bodies - (NA reference 3.15.2)

B-N-1 Interior of Reactor Vessel B-N-2 Welded Core Support Structures and Interior Attachments to Reactor Vessels B-N-3 Removable Core Support Structures B-O Pressure Retaining Welds in.Control Rod Housings ASME Section XI items that do not apply to Watts Bar Unit 2 within this Program Plan will be identified with, "NA to Unit-2", this documents the item dots not apply and will not be referenced further within the program plan, schedule or summary reports.

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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 23 Of 69 Examination Category B-A, Pressure Retaining Welds in Reactor Vessel Inspection Program B Item Component Component Exam Examination Extent of Acceptance Total Required Requirements Exam Standard Population Examination No. Examined Compliance NE Method inC piM o Fig. No.

BI.10 Shell Welds All Welds IB31 B11.11 Circumferential Applicable Vol. IWB-2500- A (2)IWB-3510 B11.12 Longitudinal NA to UNIT-2 B1.20 Head Welds Accessible B1.21 Circumfer*ntial 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 BI.30 Shell to Flange, Applicable Vol. IWB-2500-4 Weld (2) IWB-3510 1 B1.40 Head to Flange Applicable Vol. & Suf IWB-2500-5 Weld (2) IWB-3510 1 B1.50 Repair Welds (1)

B1.51 Beldine region NA to UNIT-2 - - -

Totals Examination Category B-A 14 . 14 NOTES:

(1) NA to Unit-2 (2) Includes essentially 100% of the weld length.

(3)NA to Unit-2 Preservice activites (4) NA to Unit-2 Presezce activities (5) NA to Unit-2 Preservice activities

WBN-2 PSI REVISION 1

'WATTS BAR UNIT- 2 IWB

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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 24 of 69 Examination Category B-B, Pressure Retaining Welds in Vessels Other Than Reactor Vessels Inspection Program B Item Component component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.

Pressurizer B2.10 Shell to Head Both Welds B2. 11 Circumferential Applicable Vol. IWB-2500-1 (4) IWB-3510 2 2 Ift of all B2.12 Longitudinal Applicable Vol. IWB-2500-2 weld IWB-3510 2 2 (2)

B2.20 Head Welds B2.21 Circmferential NA to UNIT-2 B2.22 Meridional NA to UNIT-2 Steam Generators (Primary side)

B2.30 Head Welds B2.31 Circumferential NA to UNIT-2 ,

B2-32 Meridional NA to UNIT-2 Weld W -50, B2.40 Tubesheet to Head Weld Applicable Vol. IWB-250.6 IWB-3510 4 4 (4)

Heat Exchanger (Primary side) - Head B2.50 Head Welds B2.51 Circumferential NA to UNIT-2 B2.52 Meridional NA to UNIT-2 - -

Heat Exchanger (Primary side) - Shell 12.60 Tubesheet to Head Welds NA to UNIT-2 -

B2.70 Longitudinal Welds NA to UNIT-2 - ,-,

B2.80 Tubesheet to Shell Welds NA to UNIT-2 - " -

Totals Examination Category B-B 8 NOTES:

(1)NA to Umit-2 Ptrevic activitics (2) The weld selected for examination is that weld intesecting the circumferential weld.

(3) NA to Unit-2 Preseric activities (4) Includes essentially 100% of the weld length

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TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 25 of, 69 Examination Category B-D, Full Penetration Welded Nozzles in Vessels Inspection Program B __

Item Component Component Exam Examination Extent of Acceptance Total Required No. (8) Examined Compliance Method Requirements Exam Standard Population Examination

_____ Fig. No.

Reactor Vessel B3.90 Nozzle to Vessel Welds Applicable Vol (a)WB-2500-7 through (c) All Nozzles (1) IWB-3512 8 8 B3.100 Nozzle Inside Radius Section Applicable (9)

EVT-1 ()(1) All Nozzles IWB-3512 8 8 Pressurizer B3. 110 Nozzle to Vessel Welds Applicable Vol. IWB-2500-7 All Nozzles IWB-3512 6 6 (a) through (c) (1)

B13120 Nozzle Inside Radius Section Applicable Vol. (4) All Nozzles 1WB-3512 6 6 (6) (1)

Steam Generators (Primary side)

B3.130 Nozzle to Vessel Welds NA to UNIT-2 B3.140 Noe I R Appble Vol. (7) (4) All Nozzles IWB-3512 8 8 (1)

(6)

Heat Exchanger (Primary side) - Head B3.150 Nozzle to Vessel Welds NA to UNIT-2 B3.160 Nozzle Inside Radius Section NA to UNIT-2 Totals Examination Categor.B-D 36 36 NOTES:

(1) Includes nozzles with full penetration welds to vessel shell (or head) and integrally cast nozzles, but excludes manways and handholes either welded to or integrally cast in vessel (2)NA to Unit-2 Preservice activities (3) NA to Unt-2 Preservice activities (4) The examination volumes shall apply to the applicable Figure shown in Figs. IWB-2500-7(a) through (d).

(5) NA to Unit-2 Preservice activities (6) IOCRF0,5O5a(b)(2)(xxiXA) Table IWB-2500-1 Items B3.120 and B3.140 (Inspection Program B) in the 1998 Edition must be applied when using the 2001 Edition, 2003 Addenda.

(7) A visual examination with enhanced magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria in Table IWB-35t2-i, may be performed in place of an ultrasonic examination.

(8) Category Items B3.10 - B3.80 are based on Inspection Program A and do not apply to Unit-2.

(9) Code Case N-648-1, with conditional approval, see paragraph 3.19.2 for details of exam area and other information.

, I WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWB

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 26 of 69 Examination Category B-F, Pressure Retaining Dissimilar Metal Welds in Vessel Nozzles Ins pection Program B Item Component Component Exam Examination Extent of Acceptance Total ,. Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.

Reactor Vessel B5.10 NPS 4 or Larger-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur IWB-2500-8 All Welds JWB-3514 8 B5.20 Less Than NPS 4-Nozzle-to-Safe End Butt Welds NA to UNIT-2 B5.30 Nozzle-to-Safe End Socket Welds NA to UNIT-2 Pressurizer B5.40 NPS 4 or Larger-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur IWB-2500-8 All Welds IWB-3514 6 6 B5.50 Less Than NPS 4-Nozzle-to-Safe End Butt Welds NA to UNIT-2 -

B5.60 Nozzle-to-Safe End Socket Welds NA to UNIT-2 Steam Generators B5.70 NPS 4 or Larger-Nozzle-to-Safe End Butt Welds Applicable Vol. & Sur IWB-2500-8 All Welds. IWB-3514 8 8 B5.80 Less Than NPS 4-Nozzle-to-Safe End Butt Welds NA to UNIT-2 -. -

B5.90 Nozzle-to-Safe End Socket Welds NA to UNIT-2 Heat Exchangers B5.100 NPS 4 or Larger-Nozzle-to-Safe End Butt Welds NA to UNIT-2 -

B5.110 Less Than NPS 4LNozzle-to-Safe End Butt Welds NA to UNIT-2 B5.120 Nozzle-to-Safe End Socket Welds NA to UN1T-2 -

Totals Examination Category B-F 22 22 Note:

(1) NA to Unit-2 Pres-ere aivities (2) NA to Unit-2 Preservioe aeties i

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWB

SUMMARY

TABLES PRESERVlCE INSPECTION PROGRAM PLAN Page 27 of 69 Examination Category B-G-d, Pressure Retaining Bolting, Greater than 2 in. in Diameter SInsection Program B Component Component Exam Examination Extent of Acceptance Total Required Item No. Examined Compliance IFig.Method Requirements No. II Exam Standard Population J Examination Reactor Vessel B6.10 Closure Head Nuts Applicable VT-1 Surfaces All Nuts IWB-3517 54 54 B6.20 Closure Studs (1)(7) Applicable Vol. IWB-2500-12 All Studs IWB-3515 54 54 B6.40 Threads in Flange (2)(6) Applicable Vol. IWB-2500-12 Flange IWB-3515 54 54 Surface B6.50 Closure Washers, Bushings (2) Applicable VT-I Surfaces All Washers IWB-3517 54 54 Pressurizer 36.60 Bolts and Studs NA to UNIT-2 -

B6.70 Flange Surface, when connection disassembled NA to UNIT-2 B6.80 Nuts, Bushings, and Washers NA to UNIT-2 -

Steam Generators B6.90 Bolts and Studs NA to UNIT-2 -

B6.100 Flange Surface, when connection disassembled NA to UNHT-2 -

B6.110 Nuts, Bushings, and Washers NA to UNIT-2 -

Heat Exchangers B6.120 Bolts and Studs NA to UN1T-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 section.

WBN-2 PSI REVISION i

'WATTS BAR UNIT- 2 IWB

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 28 of 69 Examination Category B-G-l, Pressure Retaining Bolting, Greater than 2 in. in Diameter B 6InFnection PrS gram B Item Component Component- Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requfirementxa Standard Population Examination

,. Fig. No.

Piping **

B6.150 Bolts and Studs q, NA to UNIT-2 .

B6.160 Flange Surface, when connection disassembled NA to UNIT B6.170 Nuts, Bushings, and Washers NA to UNIT-2 - - -

Pumps B6.180 Bolts and Studs (1) (7) Applicable Vol. IWB-2500-12 Studs IWB-3515 96 96 B6.190 Flange Surface, when connection disassembled Applicable VT-I Surfaces Flange 4 4 (2) (4) (6) Surfaces ]W1-3517 B6.200 Nuts, Bushings and Washers NA to Unit-2--.

Valves B6.210 Bolts and Studs NA to Unit-2 - -

B6_220 Flange Surface, when connection disassembled NA to Unit-2 - .

B6.230 Nuts, Bushings, and Washers NA to Unit-2 Totals Examination Category B-G-I 316 316 NOTES:-

(1)Botting may be examined: (a) inplace under tension; (b) when the connection is disassembled (c)when the bolting is removed.

(2)Threads in base material of flanges surface are required to be examined only when the connections are disassembled, (3)NA to Umt-2 Prese'vice activities (4) Visual examination of bolted connections, VT-I of the flange surface, nuts and washers, for pumps is required only when the component is examined under Examination Category B-L,-2. This is for one pump in a group of pumps performing similar functions in a system and is required only when disassembly for maintenance, repair, or volumetric examination, as stated inB-L-2. (See note 2 in summary table for category B-L-2)

(5) NA to Unit-2 Preservice activities (6) Examination includes I in. anmnlar surface ofifange surrounding each stud.

(7) When bolts or studs are removed for examination, surface examination meeting the acceptance standards of IWE-3515 may be substituted for volumetri examination.

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWB

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN 29 of, 69 Page Examination Category B-G-2, Pressure Retaining Bolting, 2in. and Less in Diameter Inspection Program B Item Component Component Exam RExaination Extent of Acceptance Total Required No. Examined Compliance Method Reqiements or Exam Standard Population Examination

__________________________________ ___________Fig._No.

Reactor Vessel B7.10 Bolt, Studs, and Nuts NA to Unit-2 - - -

Pressurizer B7.20 Bolt, Studs, and Nuts (1) (2) Applicable VT-1 Surface All Studs, IWB-3517 16 16

. __and Nuts Steam Generators B730 Bolt, Studs, and Nuts (1) (2) Applicable VT-i Surface All Studs, IWB-3517 128 128

. _ __._and Nuts Heat Exchangers B7.40 Bolt, Studs, and Nuts NA to Unit-2 - -

Piping All Bolt, B7.50 Bolt, Studs, and Nuts (1) Applicable VT-i Surface Studs, and lWB-3517 TBD TBD Nuts PUMPS

• : ~~~~AllStuds, IB31 B B B7.60 Bolt, Studs, and Nuts (1) (2) Applicable VT-I Surface and Nuts I"-3517 T3D T3D Valves B7.70 Bolt, Studs, and Nuts (1) (2) Applicable VT-I Surface Al S IWB-3517 TBD TBD

-_ _ _ _* _ _ _and Nuts CRD Housing (only when disassembled)

B7.80 (4), Bolt, Studs, and Nuts (1) (4) Applicable VT-I Surface All Studs IWB-3517 TBD TBD Totals Examination Category B-G-2 TBD TBD NOTES:

(1) Bolting is required to be examined only when a connection is disassembled or bolting is removed.

(2) For vessels, pwrips,or valves, examinabion ofbolting is required only when the component is examined under Examination Category B-B, B-L-2, or B-M-2. Examination of bolftd connection is required only once during the interval. (See note 2 in summary table for category B-L-2 and B-M-2.)

(3) NA to Unit-2 Preservice activities (4)The provisions of Exami,,ation Category B-G-2, Item B7.80, that are inthe 1995 Edition are applicable, refrence I0CFR50.55a(b)(2)(x:n')(B), only to reused bolting.

TBD = To be determined

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWB

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 30 of 69 Examination Categoiy B-J, Pressure Retaining Welds in Piping Inspection Pro m B Item Component Component Exam Examination Extent of Aceeptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination

______________________ _________Fig._No.

B19.10 NPS 4 or Larger B9.11 Circumferential Welds Applicable Vol. & Sur IWB-2500-8 We'ds () (4) I-3514 TBD TED (5) (6) (7)

B9_20 Less Than NPS 4 Circmnfcrential Welds other PWR Ahan Welds B9.21 High Pressure Safely Injection Systems Applicable Sur. IWB-2500-8 (1) (4) (5) IWB-3514 TBD TBD Circumiferential Welds of PWR High Applicable Vol. IWB-2500-8 Welds IWB-3514 TBD TBD B9.22 Pressure Safely Injection System A c (2) (4) (6) (7)

B9.30 Branch Pipe Connection Welds B9.31 NPS4 or Larger Applicable VoL & Sur IWB-2500-9, 11 10 & Welds (5)(6)(1)(7)(4) IWB-3514 TBD T3D B9.32 Less Than NPS 4 Applicable Sur. IWB-2500-9, 11 10 & (1)Welds (4) (5) IWB-3514 TBD TBD B9.40 Socket Welds Applicable Sur. IWB-2500-8 Welds IWB-3514 TBD TED (1) & (4)

Totals Examination Category B-J TBD TBD Notes:

(1) Examinations shall include the following:

(a) All terminal ends in each pipe or branch un connected to vessels.

(b) All terminal ends and joints in each pipe or branch run connected to other components where the stress levels exceed either of the following limits under loads associated with specific seismic events and operational conditionm (1) primary ples secondary stress intensity range of 2.4S mfor firrilic steel and austenitic steel (2) cumulative usage factor U of 0.4 ..i (c) All dissimilar metal welds not covered under Category B-F.

(d) Additional piping welds so that the total number ofcircumferential butt welds (or branch connection or socket welds) selected for examination equals 25% of the circumferential butt welds (or branch connection or socket welds) in the reactor coolant piping system. This t6tal does not include welds exempted by IWB-1220 or welds in Item No. B9-22. These additional welds may be located in one loop (one loopis defined for both PWR and BWR plants in the 1977 Edition).

(2) A 10% sample of PWR high pressure safety injection system circumferential welds in piping MNPS 11/2 (DN 40) and < NPS 4 (DN100) shall be selected for examination. This sample shall be selected from locations deterimined by the Owner as most likely to be subject to thermal fatigue. Thermal fatigue may be caused by conditions such as valve leakage or turbulence effects.

(3) NA to .nit-2 Preservice activities (4) Includes essentially 100% ofweld length.

(5) For cirumifea-ential welds with intersecting longitudinal welds, surface examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting Examinaton Category B-F and B-J circumferential welds.

(6) For circumferential welds with intersecting longitudinal welds, volumetnc examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting Examination Category B-F and B-J circumferential welds The following requirements shall also be met:

(a) When longitudinal welds ar specified and locations are known, examination requirements shall be met for both trausverse and pmallel flaws.at the intersection of the welds and for that length of longitudinal weld within the circumferential weld examination volume.

(b) When longitudinal welds are specified but locations ameunlknown, or the existence of longitudinal welds is uncertain, the examination requirements shall be met for both transves and parallel flaws within the entire examination volume of intersecting circumferential welds.

(7) For welds in carbon or low alloy steels, only those welds showing reportable preservice transverse indications need to be examined by the ultrasonic method for reflectors transvese to the weld length direction except that circumferential welds with interseting longitudinal welds shall meet Note (5).

TED = To be determined

,i.

p*

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 INB

SUMMARY

TABLES PRESERICE INSPECTION PROGRAM PLAN Page 31 of. 69 Examination Category B-K, Welded Attachments for Vessels, Piping, Pumps and Valves

_ __ Inspection Pro ram B Item component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.

Pressure Vessels Surface IWB-2500-13, 14 Each welded Alcabl attachment IWB-3516 TBD TBD (7) and 15 Piping A32501,4 Each welded .

B 10.20 Welded Attachments (1) Applicable Surface IWB-2500-13,

• and 15 14 attachment atahet IWB-3516 WB31TD TBD TBD D

(.2X6)

Pumps WB-2500- 13, 14 Each welded B10.30 Welded Attachments (1) Applicable Surface a-n 15 attachment IWB-3516 TBD TBD (2)(6)

Valves Each welded B110.40 Welded Attachments (1) Applicable Surface IWB-2500-13,14 attachment IWB-3516 TBD TBD and 15 (2)(6)

Totals Examination Category B-K TBD TBD NOTES:

(1) Weld buildup on nozzles that is in compression under normal conditions and provides only component support is excluded from examination. Examination is limited to those welded attachments that meet the following conditions:

(a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides component support as defined in NF-I 110; (c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component, and (d) the attachment weld is full penetation fillet, or partial penetration, continuous or intermittent (2) The extent of the examination includes essentially 100% of the length ofthe attachment weld at each attachment subject to examination.

(3) NA to Unit-2 Preservice activities (4) NA to Unit-2 Preservice activities (5) NA to Umt-2 Preservice activities (6) Examination is required whenever component support member deformation, e.g., broken, bern, or pulled out parts, is identified during operation, refueling, maintenance, exainnation, or testing.

(7) For the configurations shown in Figs. IWB-2500-13 and IWB-2500-14, a surface examination from an accessible side of the attachment weld shall be performed. Alternatively, for the configuration shown in Fig. IWB-2500-14, a volumetric examination of volume A-B-C-D from an accessible side of the attachment weld may be performed in lieu of the stuface examination of surfaes A-B or C-D.

TBD = To be determined

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWB

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 32 of 69 Examination Category B-L-1, Pressure Retaining Welds in Pump Casings; B-M-1, Pressure Retaining Welds in Valve Bodies; B-L-2, Pump Casings; B-M-2, Valve Bodies Inspection Program B __

Examination Item Component Component Exam Requirements Extent of Acceptance Total Required No. Examined Compliance Method Fig. Exam Standard Population Examination

_______ ________ Fig. No.

Pumps B12.10 Pump casing welds, B-.-i (4) Applicable VT-1 IWB-2500-16 All welds IWB-3518 T1D TBD B12-20 Pump casing, B-L-2 (2) --

Valves B1220 Valves, less than NPS 4 valve body welds, B-M-1 (4) Applicable Surface IWB-2500-17 All welds IWB-3518 TBD TBD B12.40 Valves, NPS 4 or larger valve body welds, B-M-1 (4) Applicable Volumetric IWB-2500-17 All welds IWB-3518 TBD TBD B12.50 Valve body, exceeding NPS 4, B-M-2 (2)

Totals Examination Category B-LI TBD TBD Examination Category B-M-1 TBD TBD NOTES:

(1)NA to Unt-2 Preservice actvities (2) NA to Umt-2 Preservice activities, reference IWB-2200 (3)NA to Unit-2 Preservice activites (4) Iacludes essentially 100% of weld lengta.

TBD = To be determined

,1

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWB

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 33 of 69 Examination Category B-N-i, Interior of Reactor Vessel; B-N-2, Welded Core Support Structures and Interior Attachments to Reactor Vessels B-N-3, Removable Core Support Structures Inspection Program B Item Component Component ExamExamination Extent & Acceptance Total Required Exaine Cmplanc MthoaFi.do.rxa Population Examination No. ExaminedCompliance Method Requiremen Fig. No. ,, Exam of Frequency Stancded Reactor Vessel Each B13.10 Vessel Interior B-N-1 (I) Applicable VT-3 Accessible Areas Inspection IWB-3520.2 I Period Reactor Vessel (BWR)

B13.20 Interior attachments within belfline region . NA to Unit-2

• B-N-2 B13.30, Interior attachments beyond the beltline region .

B.3, B-N-2 . NA N to Unit-2------

Bl3A~CoreSu~f~fri*,

B-N-2 eNA toUnit-2-----

Reactor Vessel (PWR)

B13.50 Interior B-N-2 attachments within bertline region NA to Unit-2 Interior beyond the beltine region Applicable VT-3 Accessible Welds Welds IWB-3520.2 6 6 B13.60 B-N-2 attachments Core Support Structure A Accessible S 1 B 13.70 B-N-3 (2) Applicable VT-3 Surfaces Surfaces IWB-3520.2 I I Examination Catgory B-N-1 _,_1 -_1 Examination Category B-N-2 6 6 Totals Examination Category B-N-3 _'_I_1_'

NOTES:

(1)Areas tobe examined shall include the spaces above and below the reactor core that are made accessible for examination by removal of components during normal refueling outages.

(2)The structure shall be removed from the reactor vessel for examination.

(3)NA to Unit-2 PRservice activities TBD = To be determined

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 INB

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 34 of 69 Examination Category B-O, Pressure Retaining Welds in Control Rod Housings Ins pection Program B Item Component Component Exam Examination Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.

Reactor Vessel

• • 1000%.

Volumetric B14.10 Welds in CRD Housing (1) Applicable or IWB-2500-18 CRD peripheral IB32 IWB-3523 2002 20 Surface Housing Totals Examination Category B-O 20 20 Note:

(1) 78 CDR Housings Total

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWC

SUMMARY

TABLES PRESER ViCE INSPECTION PROGRAM PLAN Page 35 of -69 SECTION 5.0 IWC

SUMMARY

TABLES For ASME CLASS 2 INDEX CATEGORY C-A, Pressure Retaining Welds in Pressure Vessels C-B, Pressure Retaining Nozzle Welds in Vessels C-C, Welded Attachments for Vessels, Piping, Pumps, and Valves C-D, Pressure Retaining Bolting Greater than 2 Inch in Diameter C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping C-F-2 Pressure Retaining Welds in Carbon oriLow Alloy Steel Piping C-G, Pressure Retaining Welds in Pumps and Valves ASME Section XI items that do not apply to Watts Bar Unit 2 within this Program Plan will be identified with, "NA to Unit-2", this documents the item does not apply and will not be referenced further within the program plan,.schedule or summary reports.

II WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWC

SUMMARY

TABLES PRESERViCE INSPECTION PROGRAM PLAN Page 36 of 69 Examination Category C-A, Pressure Retaining Welds in Pressure Vessels Inspection Program B Item Component Component Exam Exa tion E t and Acceptance Total Required Compoinen MEx Frequency Exam of Stando No.m No.

Exomponent Examined Compliance Methodd Requirements Fig. No.

Welds at Volumetric grss CI.10 Shell Circumferential Welds (1) (3) (4) Applicable (5) IWC-2500-1 structural IWC-3510 5* TBD discontinuity (2)

Welds at Volumetric =

C1.20 Head Circumferential Welds (1) (3) (4) Applicable (5) IWC-2500-1 structural IWC-3510 15" TBD discontinuity (2)

Welds at gross Volumetric IWC-2500-2 IW -50*TD C1.30 Tubesheet-to-Shell Weld (1) (3) (4) Applicable (5) structural IWC-3510 4 TBD

, (2)

Totals Examination Category C-A NOTES:

(1)Includes essentially 100% of the weld length.

(2) Gross structural discontinuity is defined inNB-3213.2. Examples are junctions between shells of different thicknesses, cylindrical shell-to-conical shell junctions, shell (or head)-to-flange welds, and head-to-shell welds.

(3) In the case of multiple'vessels of simil design, size, and service (such as steam generators, heat exchangers), the required examinations may be limited to one vessel or distributed among the vesses.

(4) The vessel areas selected for the initial examination shall be reexamined in the same sequence over the service lifetime of the component, to the extent practical.

(5)For welds in vessels with nominal wall thickness of 0.2 in. or less, a surface examination may be applied in lieu of a volumetric examination- The examination shall include the weld and 0.5 in. on either side of the weld. The acceptance standard for the examination shall be those specified for piping in IWC-3514.

• Based on Unit 1 TBD = To Be Determined

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWC

SUMMARY

TABLES PRESERWCE INSPECTION PROGRAM PLAN Page 37 of 69 Examination Category C-B, Pressure Retaining Nozzle Welds in Vessels Inspection Program B Item Component Component Exam Examination Extent and Accetance Total Requed No. Examined Compliance Method Requirements Frequency of Standard Population Examination NpFig. No. Exam C2.10 '. Nozzles in Vessels _ 1/2 in. nominal Thicmess ,!

(1)(2)(3)(4)

C2.11 Nozzle-to-Shell (nozzle-to-head) Weld Applicable Surface IWC-2500-3 (6) IWC-3511 0* TBD C2.20 Nozzles Without Reinforcing Plate, in Vessels >

in. Nominal Thickness (1) (2) (3) (4)

C2.21 Nozzle-to Shell Weld (nozzle-to-head) Applicable Surface and IWC-2500-4 (6) IWC-3511 14* TBD Volumetric (a),(b)or(d)

C2.22 Nozzle Inside Radius Section ~(a),(b)or(d) Applicable Volumetric IWC-2500-4 (6) IWC-3511 8* TBD C230 Nozzles With Reinforcing Plate in Vessels > V/

in. Nominal Thickness (1) (2) (3) (4)

C231 Reinforcing Plate Welds to Nozzle and Vessel Applicable Surface IWC-2500-4(c) (6) IWC-3511 4* TBD C232 Nozzle-to Shell Weld (nozzle-to-head) Applicable Volumetric IWC-2500-4(c) (6) IWC-3511 4* TBD when inside of vessel is accessible C2.33 Nozzle-to Shell Weld (nozzle-to-head) Applicable Visual, VT-2 (5) (6) No Leakage 0* TBD when inside of vessel is inaccessible Totals Examination Category C-B NOTES:'

(1) Includes nozzles welded to or integrally cast invessels that connect to piping rims (manways and bandholes are excluded).

(2) Includes only those piping runs selected for examination under Examination Category C-F.

(3) The nozzles selected initially for examination shall be reexamined in the same sequence over the service lifetime of the component to the exaent practical.

(4) In the case of multiple vessels of similar design, size, and *ervice (such as steam generators, heat exchangers), the required examinations may be limited to one vessel or distributed among the vessels.

(5) The telltale hole in the reinforcing plate shall be examined for evidence ofleakage while vessel is undergoing the system leakage test as required by examination category C-H (6) Nozzles at terminal ends (1) of piping run (2).

'Based on Unit I TBD = To be determined

WBN-2 PSI REVISION 1 WATTS BAR UNIT- 2 IWC

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN of 69 Page 38 Examination Category C-C, Welded Attachments for Vessels, Piping, Pumps, and Valves Inspection Pro am B Item Component Component EaExamination Extent and Nt. Eomponedt Complanen M oExam Requirements Frequency of Acceptance Total R quired No. Examined Compliance Method Standard Population Examination Pressure Vessels (1) (3) '?.

C3.10 Welded Attachments Applicable Surface IWC-2500-5 (2X4)(6) IWC-3512 22* TBD Piping (1) (3)

C3.20 Welded Attachments Applicable Surface IWC-2500-5 (2X4)(6) IWC-3512 83* TBD Pumps (1) (3)

C3.30 Welded Attachments Applicable Surface IWC-2500-5 (2X4X6) IWC-3512 14* TBD Valves C3.40, Welded Attachments NA to Unit 2* 0* . TBD Totals Examination Category C-C NOTES:

(1)Examination is limited to those welded attachments that meet the following conditions:

(a) the attachment is on the outside surface of the pressure retaining component; (b) the attachment provides component support as defined in NF-i 110; (c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the conponent, and (d) the attachment weld is full penetration, fillet, or partial penetration, continuous, or intermittent.

(2)The extent of the e6amination includes essentially 100% of the length of the attachment weld at each attachment subject to examination.

(3) Selected samples of welded attachments shall be examined each inspection inteaml.

(4) For multiple vessels of similar design, function, and servioe, only one welded attachment of only one of the multiple vessels shall be selected for examination.

(5) For piping, pumps, and valves, a sample of 10% of the welded attachments associated with the component supports selected for examination under IWF-25 10 shall be examinerd (6).Examination is requied whenever component support member deformation, e.g., broken, beat, or pulled out parts, is identified during operation, refueling, maintenance, examination, or testing.

Based on Unit 1 TBD = To be determined

WBN-2 PSI REVISION I WATTS BAR UNIT- 2

• iwC

SUMMARY

TABLES PRESER VICE INSPECTION PROGRAM PLAN Page 39 of 69 Examination Category C-D, Pressure Retaining Bolting Greater than 2 in. in Diameter inspection ProgramB Item Component Component Exam Examination Extent and Acceptance Total Required No. Examined Compliance Method Requirements Exam of Frequency Standard Population Examination Fig. No.

Pressure Vessels (1) (2)

All bolts or Apcal Volumetric IWC-2500-6 Studs at e IWC-3513 TBD C.10 Bolts and Studsonnection (5) (16 bolts)

(4)

Piping (3)

C4.20 Bolts and Studs NA to Unit 2 0* TBD Pumps C4.30 Bolts and Studs NA to Unit 2 0* TBD Valves C4.10 Bolts and Studs NA to Unit 2 0* TBD Totals Examination Category C-D __:-___

NOTES:

(1)The examination may be performed on bolting inplace under loadeor upon disassembly of the connection.

(2) The examination of bolting for vessels, pumpsor valves may be conducted on one vessel, one pump, or one valve among a group of vessels, pusps, or valves that are similar in design, size, function, and service. In addition, when the component to be examined contains a group of bolted connections of similar design and size (such as flanged connections or manway covers), the examination may be conducted on one, bolted connection among the group-(3) The examination of flange bolting in piping systems may be limited to one bolted connection among a group of bolted connections that are similar in design, size, function, and service.

(4) The areas selected for the initial examination shall be reexamined in the same sequence over the service lifetime of the componenl, to the extent practical.

(5)When bolts or studs are onmoved for examination, surface examination meeting the acceptance standards ofIWB-3515 may be substituted for volumetric examination.

• Based on Unit I TBD = To be determined

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWC

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 40 of 69 Examination Category C-F-1, Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Piping Inspection Pro ram B Item Component Component Exam Examination Extent and Acceptance Total Required No. Examined Compliance Method Requirements Fig. No. Frequecy Exam ..of Standard Population Examination C5, 0 Piping Welds ? 3/8 in. Nominal Wall Thickness for Piping > NPS 4 100% of each weld C5.1I Circumferential Welds A Applicable Vol. & Sur. IWC-2500-7 requiring IWC-3514 833* TBD exam (2X4)(5)(6)

C52.0 Piping Welds > 1/5 in. nominal Wall Thickness for Piping Ž2 and* 4NPS 4 100%/* of each weld C5.21 Circumferential Welds (1) Applicable Vol. & Sur. IWC-2500-7 requiring IWC-3514 677* TBD exam (2X4)(5)(6) 100% of each weld C5.30, Socket Welds Applicable Sur. IWC-2500-7 requiring IWC-3514 603* TBD exam

.(2X4)(5)(6)

C5.40n Pipe Branch Connections of Branch Piping I NPS 2 100% of iwc-~oo- each weld C5.41 Circumferential Weld Applicable Sur. 9,10,11,12&13 0 requiring rexamng IWC-3514 IC354 21*

21 TBD exam (2)(4X5)

Totals Examination Category C-F-1 _;

WBN-2 PSI REVISION 1 WATTS BAR UNIT- 2 IWC

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN ""

Page 41 of1 i 69 Examination Category C-F-i, Pressure Retaining Welds in Austenitic Stainless Steel or High Aloy Piping Inspection Program B NOTES:

(1) Requirements for examintion of welds in piping 4 NPS 4 (DN 100) apply.to PWR high pressure safety injection and auxilisry feedwater systems in accordance with the exemption criteria of IWC-1220. !i (2) The welds selected for examination shall include 7.51/o, but not less than 28 welds, of all dissimilar metal, austenitic stainless steel or high alloy welds not exempted by IWC-1220. (Some welds not exemtet d by IWC-1220 are not required to be nondestructively examined per Examination Category C-F-I. These welds, however, shall be included in the total welcd.oosut to which the 7.5% sampling rate is applied.) The examinations shall be distributed as folMows:

(a) the examinations shall be distributed among the Class 2 systems prorated, to the degree prlacticable, on the number of nonexempt dissimilar metal, austetntic stainless steel, or high alloy welds in each system (i.e., if a system contains 30% of the nonexempt welds, then 30% of the nondestruive examinations required by Examination Category C-F-I should be performed on that system);

(b) within a system, the examinations shall be distributed among termuna ends, dissimilar metal welds, and structural discontinuities [See Note (3)].prorated, to the degree practicable, on the number of nonexempt terminal ends, dissimilar metal weldsý and structural discontinuities in that system; and (c) within each system, examinations shall be distributed between line sizes prorated to the degree practicable.

(3) Structural discontinuities include pipe weldjoints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers, flanges, etc., conforming to ANSI BI6.9), and pipe branch connections and fittings, (4) The welds selected for examiriation shall be reexamined in the same sequene, during subsequent inspection intervals over the service lifetime of the piping component, to the extent practical.

(5) For circumferential welds with intersecting longitudinal welds, surface examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting circumferential welds.

(6) For circumferential welds with intersecting longitudinal welds, volImetric examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting circumferentidal welds. The following requirements shall also be met:

(a) When longitudinal welds are specified and locations are known, examination requirements shall be met for both transverse and parallel flaws at the intrsection of the welds and for that length of longitudinal weld within the circumferential weld examination volume.

(b) When longitudinal welds art specified but locations are unknown, or the existence of longitudinal welds is uncertain, the examiation requirements shall be met for both transverse and parallel flaws within the entire examination volume of intersecting circumferential welds.

Based on Unit 1 TBD = To be determined

VWBN-2 PSI REVISION 1 WATTS BAR UNIT- 2 IWC

SUMMARY

TABLES PRESERWCEINSPECTION PROGRAM PLAN Page 42 Of 69 Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low.Alloy Steel Piping Ins pection Program B Component Component Exam Examination Extent and Item Frequency of Acceptance Total Required Requirements N.xaieCopin Method Fig. No. Exam Standard Population Examination c5.0 Piping Welds 2!3/8 in. Nominal Wall Thickness for Piping > NPS 4 100% of each weld C5.51 Circumferential Welds (1)(4) Applicable Vol. & Sur. IWCa2500-7 requiring IWC-3514 425* TBD exam (2X5X6)(7)

C5.60 Piping Welds > 1/5 in. nominal Wall Thickmess for Piping Ž2 and* 4NPS 4 100% of each weld C5.61 Circumferential Welds (1)(4) Applicable Vol. & Sur. IWC-2500-7 requiring IWC-3514 159* TBD exam (2X5)(6)(7)

C5.70 Socket Welds NA to Unit 2 C5.80 Pipe Branch Connections of Branch Piping >

NPS2 C5.81 Circunfrenmtial Weld (1)(4) NA to Unit 2 Totals Examination Category C-F-2

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWC

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 43 of 69 Examination Category C-F-2, Pressure Retaining Welds in Carbon or Low Alloy Steel Piping Inspection Program B NOTES:

(1) Requirements for examination of welds in piping :5PS 4 (DN 100) apply to PWR high pressure safety injection and auxiliary feedwater systems in accordance with the exemption criteria of IWC-1220.

(2) The weldsaselected for examinion shall include 7.5%, but not less than 28 welds, ofall carbon and low alloy steel welds not exempted by "WC-1220. (Some welds not exempted by IWC-1220 are not required to be nondestructively examined per Examination Category C-F-2. These welds, however, shall be included in the total weld count to which the 7.5% sampling rate is applied.) The exammations shall be distributed as follows:

(a) the examinations shall be distributed among the Class 2 systems prorated, to the degree practicable, on the number of nonexempt carbon and low alloy steel welds in each system (i.e., if a system contains 30% of the nonexempt welds, then 30% of the nondestructive examinations required by Examination Category C-F-2 should be paformed n that system);

(b) vithin a system, the examinations shell be distributed among terminal ends and structural discontinuities [see Note (3)] prorated, to the degree practicable, on the number of nonexempt terminal ends and structural discontinuities in that system; and (c) within each system, examinations shall be distributed between line sizes prorated to the degree practicable.

(3) Structural discontinuiies include pipe weld joints to vessel nozzles, valve bodies, pump casings. pipe fittings (such as elbows, teMereducers, flanges, etc., conforming to ANSI B16.9), and pipe branch connections and fitigs.

(4) The welds selected for examination shall be reexamined in the same sequence, dsring subsequent inspection intervals over the service lifetime of the piping component, to the extent practical.

(5) Only those welds showing reportable preservice transverse indications need to be examined by the ultrasonic method for reflectors nansverse to the weld length direction, except that circumferential welds with intersecting longitudinal weld shall meet Note (7).

(6) For circumferential welds with intersecting longitudinal welds, surface examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of inersecting circumferential welds.

(7) For circumferantial welds with intersecting longitudinal welds, volumetric examination of the longitudinal piping welds is required for those portions of the welds within the examination boundaries of intersecting circumferential welds. The following requirements shall also be met:

(a) When longitudinal welds are specified and locations are known, examinationaequirements shall be met for both transverse and parallel flaws at the intersection of the welds and for that length of longitudinal weld within the circumferential weld examination volume.

(b) When longitudlnal welds are specified but locations ameunknown, or the existence of longitudinal welds is uncertain, the examination requirements shall be met for both transverse and parallel flawsmithin the entire examination volume of intersecting circumferential welds.

Based on Unit 1 TBD = To be determined

WBN-2 PSI REVISION 1 WATTS BAR UNIT- 2 IWC

SUMMARY

TABLES PRESERVICE INSPECTIONPROGRAM PLAN Page 44 Of 69 Examination Category C-G, Pressure Retaining Welds in Pumps and Valves Inspection Program B Item Component Component Exam Examination Extent and Acceptance Total Required No. Examined Compliance Method Requirements Frequency of Standard Population Examination

_________ ______ Fig. No. Exam Pumps C6.I01! Pumps Casing Welds NA to Unit 2 Valves (1)(2)(3)

C620 Valve Body Welds Applicable Surface IWC-2500-8 (4) IWC-3515 30* TBD Totals Examination Category C-G_

NOTES:

(1) In case of multiple pumps or valves of similar design, size, function, and srvice in a system, required weld examinations may be limited to all the welds in one pump or one valve in the same group or distributed among any of the pumps or valves of that same group.

(2) The examination may be performed fom eidther the inside or outside surface of the componenL (3) The pumps and valves initially selected for examination shall be reexamined in the same sequence over the service lifetime of the component, to the extent practical.

(4) 100% vwelds in all components in each piping run examined under Examination Category C-F, each inspection interval.

• Basedon Unit 1 TBD = To be determined

WBN-2 PSI REVISION 1 WATTS BAR UIT- 2 IWD

SUMMARY

TABLES PRESERVlCE INSPECTION PROGRAM PLAN Page 45 of 69 SECTION 6.0 rWD SumMARY TABLES for ASME CLASS 3 INDEX CATEGORY D-A, Welded Attachments for Vessels, Piping, Pumps and Valves ASME Section XI items that do not apply to Watts Bar Unit 2 within this Program Plan will be identified with, "NA to 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 I WATTS BAR UNIT- 2 IWD

SUMMARY

TABLES PRESERWlCE INSPECTION PROGRAM PLAN Page 46 of' 69 Examination Category D-A, Welded Attachments for Vessels, Piping, Pumps and Valves Inspection Program B Item Component Component Exam Examination Extent and Acceptance Total Required No. Examined Compliance Method Requirements Frequency Exam of Fig. No. Standard Population Examination Pressure Vessels (I)

DI.10 Welded Attachments Applicable VT-. IWD-2500-1 (2) (4X5) IWD-3000 18* TBD Piping (1)

D120 Welded Attachments Applicable VT-i IWD-2500-1 (2) (4)(5) IWD-3000 255* TBD Pumps (I)

DI.30 Welded Attachments NA.to Unit-2 Valves (1)

DI .40 Welded Attachments NA to Unit-2 Totals Examination Category D-A "

NOTES:

(1) Examination is limited to those welded attachments that meet the following conditions:

(a) the attachment is on the outside surface of the pressure retaining component; (b)the attachment provides component support as defined inNF-ll 10; (c) the attachment weld joins the attachment either directly to the surface of the component or to an integrally cast or forged attachment to the component; and (d) the attachment weld is full penetration, fillet, or partial penetration, continuous, or intermittent.

(2)The extent of the examination inchldes essentially 100% of the lnogth of the attachment weld at each attachment subject to examination.

(3)N/A to WBN-2 Preservice Examination (4) Examination is required whenever component support member deformation, e.g., broken, bent, or pulled out parts, is identified during operation, refueling, maintemance, examination, or testing.

(5) 100% of required area of each welded attachments, each inspection interval or each occurrence identified in note (4).

• Based on Unit 1 TBD = To be determined

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 IWF

SUMMARY

TABLES PRESERVICE :,Page INSPECTION PROGRAM PLAN 47 of 69 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 1 WATTS BAR UNIT- 2 IWF

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 48 of 69 Examination Category F-A, Supports

_ __Inspection Program B Item Support Types Examined Component Exam Exaqirmation Extent of Acceptance Total Required No. S Compliance Method Requirements Exam Standard Population Examination

_________ Fig. No.

FI.10 Class I Piping Supports (I) (2) Applicable VT-3 IWF-1300-1 (5) IWF-3410 TBD TBD F1.20 Class 2 Piping Supports (1) (2) "Applicable VT-3 [WF-1300-1 (5) IWF-3410 TBD 1TBD Fl.30 Class 3 Piping Supports (1) (2) Applicable VT-3 IWF-1300-1 (5) IWF-3410 TBD TBD F11.40 Classp 3 Pipin S3pports g (1) (2) Applicable VT-3 IWF-1300-1 (5) IWF-3410 TBD TBD I

F1.40 MC Supports NA to Unit-2 Totals Examination Category F-A NOTES:

(1) Item numbers shall be categorized to identify support types by component support function (e.&, A supports such as oe directional rod hangr*s; B = supports suh as multi-directional resweints; and C s t allow thermal movement, such as springs). Reference tables below for each type. This is established for future activities.

(2)The totals shall be comprised of supports from each system (such as Main Steam, Feedwater, or RHR), proportional to the total number of non-exempt supports of each type and function within each systen Reference tables below for each system. This is established fbr fiuure activities.

(3) N/A to WBN-2 Preservice Inpection.

(4) N/A to WBN-2 Preservice Inspection.

(5) 100% ofall supports not exempted TBD = To be determined

WBN-2 PSI REVISION I WATTS BAR UNIT - 2 wNF

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 49 of 69 CLASS I NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Examination Item Typ & D Exam Total Category Number Type & scripton Method Number F1.1OA Type A Supports (one directional restraints)

F-A, F1.10B TypeVisual, VT-3 TBD Supports (multidirectional restraints)

Class 1 Type C Supports Piping i FI.10C (thermal movement, i.e. variable or Visual, VT-3 TBD constant springs)

Type D Supports FI.10D Visual, VT-3 TBD (Snubber Types)

Totals TBD CLASS I NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE SType A Type B Type C TepD Totals Total  % Req. Total  % Req. Total  % Reg. Total  % Req.

CVCS 100 100 100 100 RCS 100 100 100 100 RHR 100 100 100 100 RHRS 100 100 100 100 SIS 100 100 100 1 100 F ' TBD TD]

TBD = To Be Determined

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 PNF

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 50 Of 69 CLASS 2 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Examination item T Exam Total Category Number Type & Description Method Number F1OAType F1.20A A Supports Visual, VT-3 TBD (one directional restraints)

F-A, F1.20B Type B SupportsTBD Supports (multidirectional restraints)

Class 2 Type C Supports Piping FI.20C (thermal movement, i.e. variable or Visual, VT-3 TBD constant springs)

FI.20D Type D Supports Visual, VT-3 TBD (Snubber Types)

Totals TBD CLASS 2 NON-EXEMPT PIPING SUPPORT

• ' DISTRIBUTION BY SYSTEM & TYPE yTpeA TypeB Type C Type D Sys Total  % Req. Total  % Req. Total  % Reg. Total  % Req. Totals 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 100 ... 100 100 100 TBD TBD TBD = To Be Detemined

WBN-2 PSI REVISION 1 WATTS BAR UNIT-2 INF

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 51 of 69.

CLASS 3 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY TYPE Examination Item T Exam Total Category INumber Type & Description Method Number F1.30A Type A Supports Visual, VT-3 TBD (one directional restraints)

F-A, F-AFType FI.30B "Visual, B Supports VT-3 TBD Supports (multidirectional restraints)

Class 3 Type C Supports Piping F1.30C (thermal movement, i.e. variable or Visual, VT-3 TBD constant springs)

F1.30D Type D Supports Visual, VT-3 TBD (Snubber Types) I Totals TBD CLASS 3 NON-EXEMPT PIPING SUPPORT DISTRIBUTION BY SYSTEM & TYPE SysTyA Tpe B Type C Type D Totals Total  % Req. Total  % Req. Total  % RN. Total  % Req.

AFWS 100 100. 100 100 CCS 100 100 100 100 ERCWS 100 100 100 100 FPCS 100 100 100 100

-PFPS 100 0100 100 _____ 100 r_ [_____ I I TBD TBD TBD = To Be Detumined

' *WBN-2 PSI REVISION 1 WATTS BAR UNIT- 2 INF

SUMMARY

TABLES Page 52 of 69 PRESERVICE INSPECTION PROGRAM PLAN CLASS 1, 2 & 3 NON-EXEMPT SUPPORTS DISTRIBUTION BY TYPE Examination Item Type &'Description Exam Total Category Number T & Method [Number F1.40A Type A Supports Visual, VT-3 TBD (one directional restraints)

F-A, F1.40B 'r. B Supports Visual, VT-3 TBD Supports (multidirectional restraints)

Class 1,2 & 3 Type C Supports Components F1.40C (thermal movement, i.e. variable or Visual, VT-3 TBD constant springs)

F1.40D Type D Supports Visual, VT-3 TBD (Snubber Types)

Totals TBD CLASS 1, 2 & 3 NON-EXEMPT SUPPORTS DISTRIBUTION BY SYSTEM & TYPE Sys Type A ype B .Type C Type D Totals Sy Total  % Req. Total  % Req. Total  % Req. Total  %

TBD 100 _ 100 100 100_

-TBDBD]

TBD = To Be Determined

WBN-2 PSI REVISION I WATTS BAR UNIT- 2 AUGMENTED

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN Page 53 Of 69 SECTION 8.0 AUGMENTED EXAMINATION REGULATORY TYPE Code Case N-722 Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/82/182 Materials.

Code Case 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 10CFR50.55a(g)(6)(ii)(D)(2) through (6) in the Code of Federal Regulations.

The above Code Cases are intended to replace the £ollowing NRC Bulletins that are address in the Watts Bar Unit 2 activities:

NRC Bulletin 2001-01 Circumferential Cracking 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 Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity NRC Bulletin 2004-01 Inspection of Alloy 82/182V600 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 reports.

WBN-2 PSI REVISION 1 WA TTS BAR UNIT- 2 AUGMENTED

SUMMARY

TABLES PRESERVICE INSPECTION PROGRAM PLAN P Of 69 Examination Category A-E, Augmented Examination Class I PWR Components Containing Aloy 600/82/182 (1)(2)

Exa;m Examination Extent of Acceptance Total Required item Component Component Meth~od *Requirements Ea tnad Pplto xmnto No.Exaine .Comliace (3)(4)(5) Fig. No.

Additional Examinations for PW4R Pressure Retaining CC N-722 Welds in Class 1 components Fabricated With Alloy 600182/182 Materials Reactor Vessel B15.80 RPV bottom mounted instrument penetrations Applicable Visual, VE All penetrations 100% _IWB-3522 58  : 58 B 15.90 Hot leg nozzle-to-pipe connections , Applicable Visual, YE All connections 100%c IWB-3522 4 .. 4 B15.95 Cold leg no2zle-t0-pipe connections Applicable Visual, VE All connections 100% IWB-3522 4 4 0

B15.100 Instrument connections Applicable Visual, VE All connections 100 % IWB-3522 3 3 Steamr Generators

• B15.110 Hot leg nozzle-to-pipe'connections , Applicable Visual, VE All connectious 100% IWB-3522 4 4 0

B15.115 Cold leg nozzle-to-pipe connections Applicable Visual, VE All connections 100 h IWB-3522 4 4 B 15.120 Bottom channel head drain tube penetration N/A to Unit 2 B15.130 Primary side hot leg instumentation, connections N/A to Unit 2 B115. 135 Primary side cold leg instrumentation connections N/A to Unit 2

WBN-2 PSI REVISION I WATT 2AUGMENTED BA UNI-

SUMMARY

TABLES PRESERVlCE INSPECTION PROGRAM PLANPae5 of,6

• Examination Category A-E, Augmented Examination Class 1 PWR Components Containing Alloy 600/82/182 (1)(2)

Item Component Component Exam Examination. Extent of Acceptance Total Required No. Examined Compliance Exam Standard Population Examination (3)(4)(5) Fig. No.

Pressurizer B15.140 Heater penetrations Applicable Visual, VE All penetrations 100% IWB-3522 78 78 B 15.150 Spray nozzle-to-pipe connection Applicable Visual, VE All connections 100% IWB-3522 1 I B15,160 Safety and Relief nozzle-to-pipe connection Applicable Visual, VE All connections 100% IWB-3522 4 4 B15.170 Surge nozzle-to-pipe connection Applicable Visual, VE All connections 100% IWB-3522 1 1 B15.180 Instrument connections N/A to Unit 2 B15.190 Drain nozzle-to-pipe connection N/A to Unit 2 Piping B15.200 Hot leg instrumentation connection N/A to Unit 2 - -

B 15.205 Cold leg instrumentation connection N/A to Unit 2 -

B135.210 Hot leg full penetration welds N/A toUnit2 - -2 B15.215 Cold leg fall penetration Welds N/A to Unit 2 (1) Alloy 600/92/182 are equivalent to tINS N06600 (SB-163, SB-166, SB-167, SB-168 and S1-564), UNS N06082 (SFA 5.14 ERNiCr-3) andlUNS W86182 (SFA 5.11 MEcrFe-3),

(2) The reactor vessel closurebead is not addressed in this Cane.

(3) The Visual Examination (VE) perforied on Alloy 600/82/I 82 components for evidence of pressure boundary leakage and corrosion on adjacent ferritic steel components shall consist ofthe following-(a) A direct VE ofthe bare-metal sauface performed with the insulation removed. Alternatively, the yE may be palbrned with insulation it place using remote visual inspection equipment that provides re*o*htion ofthe compo*net metal ntirice equivalent to a bareý-

metal direct VE.

(b) The VE may be performed when the system or component isdepressurized.

(c) The direct VE shall be performed at a distance nt greater than 4 ft(1.2 m) from the component and with a demonstrated illumination level safciea to allow resolution oftower case eharacters having a height ofnor greatw than 0.105 in (Z.7 mm).

(4) Personnel performing the VE shall be qualified as VT-2 visual ewaminees and shall have completed a minimum of four (4) hours of additional training in detection of borated water leakage from Alloy 600/87/182 nompoeems and the resulting boric acid corrosion of adjacent ferrnc steel componeata.

(5) An ultrasonic exsamination, peraformed from the component inside or ouitside &Act in acecrdance with the reqsiremnets of Table IWB-2500-1 and Appendix VIII (1995 Edition with the 1996 Addenda or later) shall be acceptable in lieu of the E requirement of this table.

(6) NA to WBN-2 Presmvice-(7) NAto WBN-2 Preservice.

WBN-2 PSI REVISION I WATTS BAR UNIT - 2 AUGMENTED

SUMMARY

TABLES PRESERVlCE INSPECTION PROGRAM PLAN Page 56 Of 69 Examination Category A-E, Augmented Examination Class I PWR Reactor Vessel Upper Head Item Component Component Exam Examination. Extent of Acceptance Total Required No. Examined Compliance Method Requirements Exam Standard Population Examination Fig. No.

Alternative Examinations Requirements for PWR CC N-729-1 Reactor Vessel Heads with Nozzles Having Pressure Retaining Partial Penetration Welds B4.10 Head with UNS N06600 nozzles and N06082 or W86182 Applicable Visual, VE Fig. 1 100% 3110 83 83 partial penetration welds F 2(1(2) (3) 3 UNS N06600 nozzles and N06082 or* W86182 partial Appliale Vol. & F.25100 3130 83 83 penetr~ation welds :Sur. .. .. (7)(10) 3140 _

B4.30 nozzles and partial penetration welds of Head withresistant N/A to Unit 2 PWSCC materials B4.40 Nozzles and partial penetration welds ofPWSCC N/A to Unit 2 resistant materials in heads Notes.

(1)The VE shall consist of the following:

a) A dirert aminstaion of .ft*hre-metal surface of the e.ire ou.ter muface, cf the head,including essentially 100% oftbe imrsection of ecuh norzle withthe head. Ifwelded orholted obstructons we present (ie., minrrr insulation, insulation suppose feet, shroud support risgug), tlse cninasion shall include? gMof the ae in the region ofthe nozzles as drem ed uF& I and the head suriace uphill and dowhf of asy s obstructions. Theom nation maybe perfrmed wish insulation in place using

• oe equipment that povide resoluion ofthe compone*t metal surfaceequivalent to abare-metal direct examination.

(b) The exmmination may be performed with the system depressurized.

(c) The e*miinabion shall be performed with as illumination level and a sufficient distance to allow resolution of lower case charaeter not greater thai 0.105 in. (2.7 rin) in height.

(2) Petaossel performing the VE shall be qualified as a Vr-2 visual e and shall have completed aslan four (4) hrof additional training in detection ofhorated water leakage tom UNS N066,

,aiaq MS N06082 or UNS W96112 components and the reslting bonic acid corrosion ofadjacen fearitie steel componets.

(3) Examination may be performodwith the system depresauized.

(4) NA for WBN-2 Preserviec (5) If the eaminattion area or volume requirements of Fig. 2 cannot be met, the alteratve requirements of Appendix I shall be used and the evaluation shall be submitted to the regulatory authority having jurisdiction at the pl*nt site.

(6) NAt o WN-2 Pxeervice (7) If not previously performed, baseline volumetic and surface eaminatiios shalltbe performed.-

(a) for plans with EDY >M2 at the nev re&eling outage, (b) for plants with EIY -28and EDY _12, no laterthan the second refiseling outage, or, (c) for planis; with EDY -c3, no later thianFebruary 10, 2008.

(8) NA for WBN-2 Preservice (9) NA per1dCFRSe.ssa (10) Includes essentially 100t/9ofsurf~aneorvolitmn

WBN-2 PSI REVISION 1 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 57 of 69 SECTION 9.0 REQUESTS FOR RELIEF INDEX

WBN-2 PSI REVISION I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 58 of 69 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 X1 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 I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 59 of 69 SYSTEMICOMPONENT(S) FOR WHICH RELIEF IS REQUESTED:

ASME Code Class I Reactor Pressure Vessel (RPV) Upper Vessel Shell-to-Flange Welds, Table IWB-2500-1 Category B-A, Item Number B 1.30:

APPLICABLE CODE EDITION AND ADDENDA FOR THE GIVEN EXAM The applicable ASME section XI code edition and Addenda of Record for Watts Bar Unit 2 Preservice inspection is the 2001 Edition through 2003 Addenda with applicable amendments from 10CFR50.55a.

CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED:

In accordance with ASME Section XI, paragraph IWA-2232, "Ultrasonic examinations shall be conducted in accordance with Appendix I."

Further, in accordance with Appendix I, paragraph 1-21 10(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 REQUESTED:

Pursuant to 10 CFR 50.55a(a)(3)(i), TVA requests relief firom 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-l.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 VIII/PDI 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 I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 60 of 69 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 VIII/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 0Q,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.

WBN-2 PSI REVISION I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Request for Relief PROCEDURE Page 61 of 69 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 conditions where an acceptable level of quality and safety is provided with the proposed alternative methodologies. Accordingly, approval of this alternative evaluation process is requested pursuant to 10 CFR 50.5 5a(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 I 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 1 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 62 of 69.

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 (1,2,3,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 May be used for all Section XI TP-1 Boundary Sectionactivities or individually as stated in Identification 2 & 3 Components the TP.

WBN-2 PSI REVISION I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 63 of 69 Basis for Section XI Boundary Identification Watts-Bar Nuclear (WBN) Unit 2 ASME Section XI Preservice Inspection (PSI)

TP-1 This document is'a technical position to establish the basis of the interrelationships with TVA classification system and ASME Section XI activities. Nothing in this technical position shall change the overall classification of a system or component from its original design. The intent is to adjoin the design of the plant with the inspection requirements of ASME Section XI requirements for inspection. The overall design of systems structures and components to the appropriate TVA classification is based on the guidelines in the Design Criteria Document, procedure number WB-DC-40-36, "The Classification of Piping, Pumps, Valves, and Vessels". These criteria apply to piping, pumps, valves, and other pressure retaining components within fluid systems that perform a safety function. Primary and secondary safety functions are classified according to their relative importance in protecting the health and safety of the general public. The TVA Class A, B, C and D systems are classified as ASME Section III Class 1, 2 and 3 respectively, based on the relationship between the ANS Safety Class, TVA classifications, and Regulatory Guide 1.26 classifications. The Mechanical flow diagrams are labeled with the TVA classification in such a manner that the classification of every portion of a system can be determined from its flow diagram. The flow diagrams are used to designate the TVA classification A, B, C and D to establish the ASME Class 1, 2 or 3 boundaries to determine the ASME Section XI requirements.

ASME Section XI requires components identified for inspection and testing shall be governed by the group classification criteria and -provides the inspection requirements for Class 1, 2 and 3 components.

ASME Section XI, IWA- 1320 states the rules for IWB shall be applied to those systems whose components are classified ASME Class 1 and the rules for IWC apply to components classified as ASME Class 2 and the rules for IWD apply to components classified as ASME Class 3.

Therefore, based on the guidance of WB-DC-40-36 with reference to the ANS documents and "ReulatoryGuide 1.26 f6r:i-eas'ification6f 'omponents, the labeling and marking of the boundiry 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 I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 64 of 69 Class 3 to Class 2, Class 2 to Class I 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 remaining color coded drawings.ý

2) ASME Section XI Pressure Tests (XIPT)

This activity is to identify the pressure testing requirements based on Section XI and within the previously established boundaries for Systems and Components. The pressure test boundaries are determined and established by the general requirements of Article IWA-5000 for ASME Class 1, 2, & 3 systems and components requiring a pressure test. The boundary limits are generally defined by the location of the safety class interface valves within the system or as describe in IWB, IWC and IWD requirements for Class 1,2 and 3 systems respectively. This activity is not intended to include the Section XI inspection or testing requirements on systems or portions of a system that are optionally upgraded to a high classification, unless specifically directed by other requirements. This applies to systems of nonnuclear safety class to ASME Section III Class 2 or 3 and/or Class 3 to Class 2, Class 2 to

• Class 1 or any combination there of. All other boundaries on safety Class systems that represent the activities associated with Section XI are to enhance and distinguish the various pressure test boundaries.

A color coded drawing can be established and labeled (i.e. 2-48W801-l-XIPT) with the X[PT, 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 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 remaining color coded drawings.

3) ASME Section XI EXaminations (XIEX)

This activity is to identify the examination requirements based on Section XI and within the previously established boundaries for systems and components that are not exempted from volumetric, surface or visual requirements on Class 1, 2 and 3 pressure retaining components. This activity is not intended to include the Section XI inspection or testing requirements on systems or portions of a system that are optionally upgraded to a high classification, unless specifically directed by other requirements. This applies to systems of nonnuclear safety class to ASME Section III Class 2 or 3 and/or Class 3 to Class 2, Class .2 to Class I or any combination there, of. All other boundaries on safety Class systems that represent the activities associated with Section XI are to enhance and distinguish the various examination boundaries. A color coded drawing can be established and labeled (i.e.2-48W801-1-XIEX) with the

WBN-2 PSI REVISION I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Technical Positions PROCEDURE Page 65 of 69 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 IS1.

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 I ecnnical Kxuvitew; Charlie:~lt DI.)IkeII ,./ 12/./0,8U

WBN-2 PSI REVISION 1 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN Drawing Reference List PROCEDURE Page 66 of 69 SECTION 11.0

,DRAWING REFERENCE LIST Some of the drawings will be included as the preservice inspections arm completed and the drawings are updated, Drawing Number Drawing Title (System) Code Class 47W801-1 Main & Reheat Steam (1) 2 47W801-2 SG Blowdown (1)(15) 2 47W803-1 Feedwater (3) 2 47W803-2 Auxiliary Feedwater (3) 2&3 47W803-3 Auxiliary Feedwater (3) 3 47W809-1 Chemical & Volume Control (62) 1,2&3 47W809-2 CVC & Boron Recovery (62) 2&3 47W809-3 CVC & Boron Recovery (62) 3 47W809-5 CVC & Boron Recovery (62) 3 47W809-7 Flood Mode Boration Makeup (84) 2&3 47W809-9 Chemical & Volume Control (62) 2 47W810-1 Residual Heat Removal (74) 1,2&3 47W81 1-1 Safety Injection (63) 1,2&3 47W812-1 Containment Spray (72) 2&3 47W813-1 Reactor Coolant (68) 1&2 47W814-2 Ice Condenser (61) 2 47W819-1 Primary Water (81) 2 47W830-1 Waste Disposal'(77) 2 47W845-1 Essential Raw Cooling-Water (67) .. 3 47W845-2 Essential Raw Cooling Water (67) 3 47W845-3 Essential Raw Cooling Water (67) 2&3 47W845-4 Essential Raw Cooling Water (67) 3 47W845-5 Essential Raw Cooling Water (67) 3 47W850-2 Fire Protection Raw Service Water (26) 3 47W855-1 Fuel Pool Cooling & Cleaning (78)(62) 2&3 47W859-1 Component Cooling (70) 3 47W859-3 Component Cooling (70) 2&3 47W859-4 Component Cooling (70) 3 47W862-2 SG Wet Layup, Closed Recirculation Loop (41) 2 47W865-5 Air Conditioning Chilled Water (31) 2

WBN-2 PSI REVISION 1 NGDC WATTS BAR NUCLEAR PLANT UNIT 2 -

PROJECT PRESERVICE INSPECTION PROGRAM PLAN ASME Section X1 Terms PROCEDURE Page 67 of 69 SECTION 12.0 ASME SECTION XI TERMS ALARA: As Low As Reasonably Achievable ANIL: Authorized Nuclear Inservice Inspector ASME: American Society of Mechanical Engineers AUG: Augmented.

BC: Branch Connection CFR: Code of Federal Regulations CH: Charging CHR: Containment Heat Removal Circ: Circumferential CL: Cold Leg

.CCS: Component Cooling System CRD: Control Rod Drive CSS: Containment Spray System CS: Carbon Steel CSP: Containment Spray Pump CVCS: Chemical and Volume Control System DWG: Drawing.

.... * ..."...*": :DM :, Dissimilar Metal - -

ECCS: Emergency Core Cooling System ERCW: Essential Raw Water Cooling System E: Elbow FW: Feedwater FMBMS: Flood Mode Boration Makeup System HL: Hot Leg HPFP: High Pressure Fire Protection Hx: Heat Exchanger IEP: Inspection and Examination Procedures INPO: Institute for Nuclear Power Operations PSI: Preservice Inspection MSS: Main Steam System

,WBN-2 PSI REVISION I NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN ASME Section X1 Terms PROCEDURE Page 68 of 69 NDE: Nondestructive Examination NRC: Nuclear Regulatory Commission P: Pipe PENT: Penetration PSV: Pressure Relief or Safety Valve PWR: Pressurized Water Reactor PZR: Pressurizer PCV: Pressure Control Valve R: Reducer RC: Reactor Coolant RCP: Reactor Coolant Pump REV: Revision RHR: Residual Heat Removal RHRS: Residual Heat Removal System RECIRC: Recirculation RCS: Reactor Coolant System RPV: Reactor Pressure Vessel RSW: Raw Service Water (System)

RLV: Relief Valve RX: Reactor SDCHX: Shutdown Cooling Heat Exchanger SD: Shutdown SER: Safety Evaluation Report SG: Steam Generator SGBD: Steam Generator Blowdown (System)

SIS: Safety Injection System SI: Safety Injection SUR: Surface Examination SFPC: Spent Fuel Pit Cooling (System)

SS: Stainless Steel Tee: Tee TK: Thickness Tech. Spec: Technical Specification TRM: Technical Requirements Manual TVA Tennessee Valley Authority UFSAR: Updated Final Safety Analysis Report

WBN-2 PSI REVISION i NGDC WATTS BAR NUCLEAR PLANT UNIT 2 PROJECT PRESERVICE INSPECTION PROGRAM PLAN ASME Section XI Terms PROCEDURE Page 69 of 69 VCT: Volume Control Tank VOL: Volumetric Examination VT: Visual Examination VE: Visual Examination (VT-2 Augmented Type)

WDS: Waste Disposal System WBN: Watts Bar Nuclear