Text

American Society of Mechanical Engin,Section XI, Second and Third 10-Year Inspection Interval, Inservice Inspection Owners Activity Report for Cycle 14 Operation
	ML17212A550
Person / Time
Site:	Watts Bar ; (NPF-090)
Issue date:	07/31/2017
From:	Simmons P; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML17212A550 (185)
	v • d • e

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 July 31, 2017 10 CFR 50.55a ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390

Subject:

AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION Xl, SECOND AND THIRD lO.YEAR INSPECTION INTERVAL, INSERVICE INSPEGTION OWNER'S ACTIVITY REPORT FOR CYCLE 14 OPERATION The Tennessee Valley Authority is submitting the Watts Bar Nuclear Plant, Unit 1, American Society of Mechanical Engineers (ASME), Section Xl, Owner's Activity Report for Unit 1 Cycle 14 operation as required by Article IWA-6000, Section Xl, Division 1. The reports are contained in the enclosures to this letter and is in accordance with the requirements of ASME Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice !nspection Summary Report Preparation and Submission."

The report is an overview of the results from inservice examinations that were performed on components within the ASME Section Xl boundary, up to and including the Unit 1 Cycle 14 refueling outage, during the third period of the second 10 year inspection interval and the first period of the third inspection interval. The applicable provisions of the ASME Code require that this report be submitted 90 days from the end of the applicable outage, i.e., by July 31,2017. provides a copy of 1-TRl-0-10.3, the third interval lSl/NDE program plan. This plan is attached for information only and does not require NRC approval.

There are no new regulatory commitments associated with this submittal. lf you have questions regarding this letter, please contact Kim Hulvey al (423) 365-7720.

Respectfully, /

Paul Simmons Site Vice President Watts Bar Nuclear Plant

U. S. Nuclear Regulatory Commission Page 2 July 31, 2017

Enclosures:

American Society of Mechanical Engineers, Section Xl, Second 1O-Year

!nservice lnspection lnterval, lnservice lnspection Owner's Activity Report for Cycle 14 Operation (Form OAR-1)

American Society of Mechanical Engineers, Section Xl, Third 1O-Year Inservice lnspection lnterval, !nservice lnspection Owner's Activity Report for Cycle 14 Operation (Form OAR-1) 1-TRl-0-10.3 - Unit 1 ASME Section Xl lSl/NDE Program Third lnterval cc (Enclosures):

NRC RegionalAdministrator - Region ll NRC Senior Resident lnspector - Watts Bar Nuclear Plant NRC Project Manager - Watts Bar Nuclear Plant

ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT I AIT'IERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI, SECOND IO.YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 14 OPERATION

FORM OAR.I OWNER'S ACTIV]W REPORT U 1R14 Report Nurnber Plant Unit No.

Watts Bar Nuclear Plant, P.O. Box 2000, Spring C

, TN 3739t-2000 Commercial Service Date May 27, L995 Refueling Outage No.

2nd U 1R14 (if applicable)

Current lnspection lnterva I

,2 (1

,3'" r 4, other)

Current lnspection Period 3rd Edition and Addenda of Section Xl applicable to the lnspection Plans Date / Revision of lnspection Plans 2001 Edition, 2003 Addenda April 15th, 2016 / t-tl-t00.012, Revision 00 Edition and Addenda of Section Xl applicable to repair/replacement activities. if different than the inspection plans same May 17th, 20L7 / r-rnl-0-10.2, Revision 17 Code Cases used:

N'450, N513-3, N'532-5, N-566-2, N-585-1, N-578-1, N-624 N-685, N-686-1, t{-695, N-7m, N-70G1, N-722-1, N-729-1, tu753, N-770-l CERNF]CATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests, meet the lnspection plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of conform to the requirements of Section Xl U1R14 (refuelinS outage nurnber)

Signed Date 7, o/,.?.

Repair Replacement and lnservice lnspection Prograrn Owner Province of Tennessee CERTIFICATE OF INSERVICE INSPECTION

l. the undersigned, holding a valid commisslon lssued by the National Board of Boiler and Pressure Vessel lnspectors and the State or The Hartford Steam Boiler lnspection and lnsurance Company of Connectacut of and employed by Hartford, Connecticut have inspected the items described in this owner's Activity Report, and state that to the best of my knowledge and beltef, tlte Owner has perfornred atl activities represented by this report in accordance with the requirements of Section Xl By signing this certificate neither the lnspector nor his employer makes any warranty expressed or implied concerning the repalr/ replacement activities and evaluation described in this report. Furthermore, neither the lnspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection Comrnissions NB 14057tNR, TN 4132 National Board, State, Province, and Endorsements 1**a, E-l of 3

rABLE 1 ITEMS WITH FTAWS OR RETEVANT COND]TIONS THAT REqUIRED EVATUATION FOR CONTINUED SERVICE TABLE 2 ABSTRACT OF REPAIRS, REPTACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONNT{UED SERVICE Examination Category and Item Number Item Description Evaluation Description D-B / Dz.rO 10" High Pressure Fire Protection Piping A through wall leak in a 10" diameter Class 3 pipe was evaluated in accordance with ASME Code Case N-513-3. The leak rate was minimal and would have no effect on the safety function of the system. This condition is within the bounding condition for a flooding impact.

therefore flooding is not a concern. Civil Analysis showed that structural integrity was maintained and there was no concern for a line break at the leak location.

Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number CRDM 48 Vent Plug at E3 Removed eye bolt, tightened vent plug and seal welded a threaded plug to the top of the CRDM in place of the eye bolt.

DlAel201s Work Order (WO) 117339974 E-2 of 3

REPORTING REQUIRED BY 10 CFR s0.ssa(bX2Xixl ASME Section Xl, Subsection IWE Steel Containment Vessel lnspection Program 10 CFR 50.55a(bX2Xix) requires the reporting of inaccessible areas and additional examinations identified during the performance of ASME Section Xl, Subsection IWE Steel Containment Vessel lnspection Program when conditions exist in accessible areas that could indicate the presence of or result in degradation to such inaccessible areas.

During U1R14 (18) Leak Chase Channel(LCC) boxes were examined in accordance with table lWE-2500-l,Category E-A, ltem number E1.30 of ASME Section Xl 2001 Edition with the 2003 Addenda. The examination included opening the box lids to check for moisture intrusion, hereby destroying the moisture barrier formed by the gasket material and caulking between the box and lid. Once the box lid was removed the pipe cap inside was removed to allow accessto the LCC below by use ofa boroscope.

There are (16) LCC boxes in the WBN Unit 1 Raceway. Water was discovered in (6) of those boxes. No water was discovered in the LCCs below the boxes in the raceway confirming no water reached the inaccessible areas of the containment liner in the LCC system below the raceway. All (15) boxes were cleaned and re-sealed with new caulking and gasket material and shall be examined in the next IWE period.

There are (2) LCC boxes in the WBN Unit 1 Keyway. Water was discovered in (1) of the boxes, but due to a defect in the pipe within the box, access to the LCC below through that box is not possible. The LCC system below the boxes in the keyway are connected so it is possible to inspect the LCC through the other box in the keyway. Water was discovered in the LCC by use of a boroscope. The water was subsequently removed and a follow up examination was performed. The results of the follow up examination revealed no measurable degradation of the containment liner plate within the LCC system. An engineering evaluation was performed and it was concluded these areas are not likely to experience accelerated degradation or aging. The (2) boxes were cleaned and re-sealed with new caulking and gasket material and shall be examined in the next IWE period. The flaw identified was corrected when the boxes were sealed with new caulking and gasket material and as such do not require successive lnspections in accordance with IWE-2420(b).

E-3 of 3

ENCLOSURE 2 TEN N ESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT {

AMERICAN SOCIETY OF i'IECHANICAL ENGINEERS, SECTION XI, THIRD 1 O.YEAR INSPECTION INTERVAL, INSERVICE INSPECTION OWNER'S ACTIVITY REPORT FOR CYCLE 14 OPERATION

FORM OAR-1 OWNER'S ACTIVIW REPORT U 1R14 Report Nurnber Plant Unit No.

Com mercial Service Date May 27, L996 Refueling Outage No.

U 1R14 (if applicable)

Current lnspection lnterval Watts Bar Nuclear Plant, P.O, Box 2000,

, TN 3739L-2000 3rd f,T 1st Current lnspection Period (1,2"-,3 Edition and Addenda of Section Xl applicable to the lnspection Plans Date / Revision of lnspection Plans 2OO7 Edition, 2008 Addenda Edition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspectlon plans July 20th, 2OL7 / r-rnl-0-10.3, Revision 001 Code Cases used:

N-513-3, N-532-5, N-596-1, N-71G1, N-722-t, N-729-1, N-753, N-770-t CERTIFICATE OF COI{FORMANCE I certify that (a) the statements made in this repon are correct; (b) the examinations and tests, meet the lnspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activitaes and evaluations supporting the completion of U lR14 conform to the requirements of Section Signed n, Repair Replacement and lnservice lnspection Program Owner (refueling outage number)

DateT),--

CERTIFICATE OF INSERVICE INSPECIIOITI l, the undersiBned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel lnspectors and the State or Province of The Hartford Steam Boiler of Inspection and lnsurance Company of Connecticut Tennessee and employed by Hartford, Connecticut have inspected the items described in this Owner's Activity Report, and state that to the best of my knowledge and belief, the Owner has performed all activities represnted by this report in accordance with the requirements of Section Xl By sitning this certificate neither the lnspector nor his employer makes any warranty expressed or implied concerning the repair/ replacement activities and evaluation described in this report. Furthermore, neither the lnspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection Commissions NB 140571NR, TN 4132 National Board, State, Province, and Endorsements

).n-o-0 E-1 of 3

TABLE 1 ITEMS WITH FTAWS OR RETEVANT CONDITIONS THAT REqUIRED EVALUATION FOR CONTINUED SERVICE TABLE 2 ABSTRACT OF REPAIR' REPTACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Examination Category and Item Nurnber Item Description Evaluation Description D-B / D?.rO 10" High Pressure Fire Protection Piping A through wall leak in a 10" diameter Class 3 pipe was evaluated in accordance with ASME Code Case N-513-3. The leak rate was rninimal and would have no effect on the safety function of the system, This condition is within the bounding condition for a flooding impact.

therefore flooding is not a concern. Civil Analysis showed that structural integrity was maintained and there was no concern for a line break at the leak location.

Code Class Item Desription Description of Work Date Completed Repair/Replacement Plan Number 2

Loop 2 Steam Generator Upper Lateral Support Ring Girder Shim Replaced missing Jam nut 4/20120L7 Work Order (WO)

LL8644626 Loop 4 Stearn Generator Upper Lateral Support Ring Girder Shim Replaced missing Jarn n ut 412L/20L7 Work Order (WO) 1186s3 150 Loop 4 Steam Generator Upper Lateral Support Splice Plate Tightened Loose Bolt 3

10" High Pressure Fire Protection Pi pi ng Repaired through wall leak 7 /r8120L7 Work Order (WO) 117590s54 3

Containment Lower Compartment Cooler lnstalled Blank off Plates to stop leaking coils 5/LLl2OL7 Work Order (WO) 1.18646713 E-2 of 3

REPORTING REQUIRED BY 10 CFR 50.55a(bX2Xix)

ASME Section Xl, Subsection IWE Steel Containment Vessel lnspection Program 10 CFR 50.55a(b)(2Xix) requires the reporting of inaccessible areas and additional examinations identified during the performance of ASME Section Xl, Subsection IWE Steel Containment Vessel lnspection Program when conditions exist in accessible areas that could indicate the presence ofor result in degradation to such inaccessible areas.

E-3 of 3

ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT, UNIT 1 1-TRt-0-10.3 UNIT 1 ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL

Watts Bar Nuclear PIant Unit 1 Technical Requirements lnstruction 1-TRI-0-10.3 UNIT 1 ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL Revision 0001 Quality Related Level of Use. lnformation Use Effective Date: 07-20-2017 Responsible Organization: PGM, Engineering Program Group Prepared By: Shane C. Norton Approved By: James A. Harvey

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 2 of 174 Revision Log Revision or Change Number Effective Date Affected Page Numbers Description of Revision/Change 0000 09/09 116 ALL lnitial lssue of 3rd lnterval Program 0001 07 120117 20 Provide actual start date of the third lSI Interval.

146 Corrected examination history for SIF-D087 -1 1.

No examination was performed in Cycle 12.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 3 of 174 1.0 1.1 1.2 1.3 1.4 1.5 1.6 3.0 3.1 3.2 4.0 5.0 6.0 7.0 7.1 2,0 DEVELOPMENTAL REFERENCES........

..................22 2.1 WBN Unit 1 Technica! Requirement Manua1...............

................22 2.2 WBN Final Safety Analysis Report

.............22 2.3 NRC Documents

.........22 2.4 ASME Reference Documents..............

.......22 2.5 Plant Procedures and lnstructions........,.....

................23 2.6 EPRI Documents.............

...........25 2.7 Nuclear Energy lnstitute (NEI) Guidelines

..................25 2.8 Westinghouse Documents.........

.................25 2.9 lSl Drawings...........

....25 2.10 Abbreviations.........

.....26 Table of Contents TNTRODUCTTON

..........6 Purpose

........6 Scope and Applicability.......

..........7 Codes of Record and Code Cases

.............11 1.3.1 Current Code Requirements.........

................ 11 1.3.2 Current Code Cases

..... 14 1.3.3 Code lnterpretations.........

............ 19 1.3.4 History of lSl and PSI Programs

................... 19 Frequency lnspection lntervals and lnspection Periods..............................20 Technical Requirements Fulfilled and Modes

.............21 PREREQUISITES AND PRECAUTIONS

...26 Prerequisites...........

....26 Precautions..............

................... 26 spEctAL TooLS AND EQU!PMENT...........

.............27 ACCEPTANCE STANDARDS

...................27 QUALIFICATIONS OF NDE PERSONNEL...........

,....29 IMPLEMENTATION AND RESPONSIBILITIES

.........29 NDE Examinations....

.......,..........30

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 4 of 174 7.2 7.3 7.4 7.5 7,6 7.7 7.8 7.9 7.10 7.11 7.12 8.0 Appendix B:

Appendix G:

Appendix D:

Appendix E:

Table of Contents (continued) 7.1.1 NDE Coverage Requirements

...... 30 Components Subject to Examination........

.................. 31 Notification of Indication..........

....34 Additional ExaminationsforASME Code Class 1,2,and 3..............

..........35 Corrective Action Program and Successive Examinations.........

................41 Configuration Changes..........

.....43 Calibration Standards

.................44 Records and Reports............

......44 Requests for Relief (RFR)......

.....45 lnterval Schedule and Scan Plan.........

....... 46 Augmented Examinations........

...................47 RrsK TNFORMED TNSERVTCE TNSPECTTON (Rr-rsr)....

............48 7.12.1 lntroduction..............

.....48 7.12.2 Purpose

........48 7.12.3 Scope......

......48 7.12.4 Frequency

..... 48 7.12.5 Rl-lsl Periodic Updates

................ 49 7.12.6 Performance Monitoring..........

......49 PERFORMANCE.....

...52 9.0 RECORDS.............

.....55 9.1 QA Records...........

.....55 9.2 Non-QA Records

........55 Appendix A: Examination Summary Table for ASME Class 1 Components..........

....56 Examination Summary Table for ASME Class 2 Components..........

....78 Examination Summary Table for ASME Class 3 Gomponents..........

....97 Examination Summary Table for ASME Class 1,2, and 3 Component Supports...........

..107 Examination Summary Table for Risk-lnformed Piping Welds

......,127

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 5 of 174 Appendix F:

Appendix G:

Appendix H:

Appendix l:

Appendix J:

Appendix K:

Source Notes:

Table of Contents (continued)

Class 1 (B-M-2) Valve Listing....

............. 131 ISI Drawing List......

.133 Schedule of Successive Examinations..

............... 138 Notification of Additional Sample Results Form.......

........... 139 Requests for Relief

.140 Augmented Examinations...

...141 Source Notes......

.....174

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 6 of 174 1.1

1.0 INTRODUCTION

Purpose ln accordance with Title 10 Code of Federal Regulations (CFR) Part 50.55a(g), this program implements the Watts Bar Nuclear Plant (WBN) Unit 1 Technical Surveillance Requirement 3.4.5.2 and fulfills the requirements of NPG-SPP-09.1, Part A - ASME Section XI ISI and Augmented Nondestructive Examinations; and Part F - Risk-lnformed lnservice and Testing Program Development and lmplementation, as applicable to lnservice lnspection (lS!) implementation. This program is organized to comply with the lSl and nondestructive examination (NDE) requirements of the 2007 Edition with the 2008 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, Division 1, Articles 1000, 2000, 3000, and 6000.

This ISI/NDE Program is an administrative Technical Requirement lnstruction (TR!)

employed to obtain data via NDE of ASME Section Xl Code Class 1,2, and 3 equivalent components to determine acceptance of components for continued service during operation and if a flaw is an isolated case or of a generic nature. lt shall serve as TVA's lSl/NDE plan and schedule in accordance with the requirements of IWA-1400 for the WBN Unit 1 Third lSl inspection Interval. The term component is used to refer a vessel, pump, valve, storage tank, piping system or core support, as applicable to its context.

This lSl/NDE Program reflects the built-in limitations of the original plant design (See Note), geometry, construction, component materials, and the current technology or state-ofthe-art nondestructive examination techniques. lt specifies the number of components to be examined, the examination methods to be used and provides lSl Examination Summary tables from which specific items are scheduled for examination. These items are described and detailed in lSl scan plans.

NOTE The Watts Bar Nuclear Power plant was designed to meet the intent of the "Proposed General Design Criteria for Nuclear Power Plant Construction Permits" published in July, 1967. The Watts Bar construction permit was issued in January, 1973. See 50.55a(gX2) design and accessibility requirements for performing inservice inspection in plants with CPs issued between 1971 and 1974. Consideration has been given to the inspectability of the ASME Code Class 1 systems in the design of components, in the equipment layout, and in the support structures to permit access for the purpose of inspection. Access for inspection is defined as access for examination by direct or remote means and/or by contacting vessel surfaces during nuclear unit shutdown. Reference FSAR 5.2.8.2

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 7 of 174 1.2 Scope and Applicability This program outlines details for planning and implementing the Third 1O-Year ISI/NDE lnspection lnterval for ASME Section Xl Code Class 1, 2, and 3 equivalent components and their supports at WBN Unit 1 in accordance with IWA-2430, lnspection lntervals, and the Risk-lnformed lnservice lnspection (R!-lSl) Program in accordance with Code Case N-716-1 and IWA-2420(a), which requires that each inspection plan shall include the following:

A. lnspection Period and lnterva! dates B. The Edition and Addenda of ASME Section Xl that apply to the required examination and tests C. The classification and identification of components subject to examination and test D. Code Cases proposed for use and the extent of their application ln accordance with !WA-1400 (c), it is the responsibility of WBN to submit the lSl plans and inspection summary reports required by IWA-1400(c) to the Nuclear Regulatory Commission (NRC).

Associated programs, such as Pump and Valve Testing, Snubber lnservice Examination and Testing, Repair and Replacements, System Pressure Tests (including the associated Categories B-P, C-H, and D-B, W-2 Visual Examinations),

Examination of Containment Structures (Article IWE) and Steam Generator Tube Examinations (Examination Category B-Q) are covered by other instructions or procedures and are NOT part of this instruction.

The TVA Flow Diagrams and the lSl Drawings are used to identify the components and systems to be examined (see Appendix G for listing).

IWB-1220 describes the Class 1 components exempt from volumetric and surface examination. Applicable exemptions are as follows.

A. Piping, vessels, pumps, valves and piping segments NPS 1 and smaller.

B. Piping, vessels, pumps, valves and piping segments which have one inlet and one outlet, both of which are NPS 1 and smaller.

C. Piping, vessels, pumps, valves and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectiona! area defined by the OD of NPS 1 pipe.

D. Reactor Vessel Head connections and associated piping 2" nominal pipe size (NPS) and smaller, made inaccessible by control rod drive penetrations.

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paoe 8 of 174 1.2 Scope and Applicability (continued)

E. Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by a guard pipe.

IWC-1221and IWC-1223 describe the Class 2 components in Residual Heat Removal (RHR), Emergency Core Cooling (ECC), and Containment Heat Removal (CHR) systems, except High Pressure Safety lnjection (HPSI), exempt from volumetric and surface examinations. Applicable exemptions are as follows.

A.

B.

C.

D.

For RHR, ECC, valves and their Piping, vessels, one outlet, both and CHR systems, piping connections pumps, valves and of which are NPS 4 except HPSI, piping, vessels, pumps, NPS 4 and smaller.

piping segments which have one inlet and and smaller.

Piping, vessels, pumps, valves and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 pipe.

For High Pressure Safety lnjection system,

1. Piping, vessels, pumps, valves and their piping connections NPS 1-112 and smaller.

2. Piping, vessels, pumps, valves and piping segments which have one inlet and one outlet, both of which are NPS 1-112 and smaller.

3. Piping, vessels, pumps, valves and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 1-112 pipe.

E. Piping, vessels, piping, pumps, valves, other components, and their piping connections of any size in statically pressurized, passive safety injection systems.

Vessels, piping, pumps, valves, and other components beyond the last shutoff valve in open ended portions of systems that do not contain water during normal operating conditions.

Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by a guard pipe.

F.

G.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 9 of 174 1.2 Scope and Applicability (continued)

IWC-1222 and IWC-1223 describe the Class 2 components in systems other than RHR, ECC, and CHR systems exempt from volumetric and surface examinations, as follows:

A. For systems except Auxiliary Feedwater,

1. Piping, vessels, pumps, valves and their piping connections NPS 4 and smaller.

2. Piping, vessels, pumps, valves and piping segments which have one inlet and one outlet, both of which are NPS 4 and smaller.

3. Piping, vessels, pumps, valves and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 pipe.

B. For Auxiliary Feedwater,

1. Piping, vessels, pumps, valves and their piping connections NPS 1-112 and smaller.

2. Piping, vessels, pumps, valves and piping segments which have one inlet and one outlet, both of which are NPS 1-112 and smaller.

3. Piping, vessels, pumps, valves and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 1-112 pipe.

C. Vessels, piping, pumps, valves, other components, and their piping connections of any size in systems that operate (when the system function is required) at a pressure less than or equal to 275 psig and at a temperature less than or equal to 200 F.

D. Vessels, piping, pumps, valves, and other components beyond the last shutoff valve in open ended portions of systems that do not contain water during normal operating conditions.

E. Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by a guard pipe.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 10 of 174 1.2 Scope and Applicability (continued)

IWD-1220 describes the Class 3 components exempt from visual examination requirements. Applicable exemptions are as follows:

A. Piping, vessels, pumps, valves, and their piping connections NPS 4 and smaller.

B. Piping, vessels, pumps, valves and piping segments which have one inlet and one outlet, both of which are NPS 4 and smaller.

C. Piping, vessels, pumps, valves and piping segments which have multiple inlets or multiple outlets whose cumulative pipe cross-sectional area does not exceed the cross-sectional area defined by the OD of NPS 4 pipe.

D. Piping, vessels, pumps, valves, and their piping connections that operate at a pressure less than or equal to 275 psig and at a temperature less than or equal to 200 whose function is not required in support of RHR, ECC, or CHR systems.

E. Welds or portions of welds that are inaccessible due to being encased in concrete, buried underground, located inside a penetration, or encapsulated by a guard pipe.

!WF-1230 describes the Class 1,2, and 3 component supports exempt from visual examination requirements. Applicable exemptions are as follows:

A. Supports exempt from the examination requirements of !WF-2000 are those connected to piping and other items exempted from volumetric, surface, or VT-1 or VT-3 visual examination by IWB-1220,1WC-1220, IWD-1220, and B. Portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe are exempt from the examination requirements of IWF-2000.

Personnel responsible for performance of the examinations should familiarize themselves with the requirements of this instruction prior to performing the examinations. Specifics concerning performance of NDE are NOT a part of this program, but are included in lnspection Services Organization Programs Manual (refer to !nspection and Examination Program (lEP) series).

WBN UNIT l ASME SECTION XI ISI/NDE I 1.TRI.O.l 0.3 Unit 1 PROGRAM THIRD INTERVAL lRev. 0001 Paqe 11 of 174 1.3 1.3.1 Codes of Record and Code Cases Gurrent Code Requirements The WBN Unit 'l Code of Record for the Third lnspection lnterval is the 2007 Edition with the 2008 Addenda of the ASME Boiler and Pressure Vessel Code, Section Xl, Division 1 in accordance with 10 CFR 50.55a(g)(4xii), as required to be listed in this plan in accordance with IWA-2420(a)(2) and required in accordance with Title 10 Code of Federal Regulations (CFR) Part 50.55(a) Codes and Standards, Paragraph (gX4), [10 CFR 50.55a(g)(4)], that is contained in Federal Register Notice (FRN) Vol.

79, No. 214 I November 5,2014 / Rules and Regulations and became effective on December 5,2014 as corrected by FRN / Vol. 79, No. 238 / December 11,2014.

10 CFR 50.55a mandated additional requirements, conditions and/or exceptions are listed below along with the applicable 10 CFR 50 reference:

10 CFR 50.55a Reference M an dated Add itional Requ i rements/Cond itions/Exem ptions 10 CFR 50.55a(bx2xii)

Section Xl condition: Pressure-retaining welds in ASME Code Class 1 piping (applies to Table IWB-2500 and IWB-2500-1 and Category B-l).

lf the facility's application for a construction permit was docketed prior to July 1, 1978, the extent of examination for Code Class 1 pipe welds may be determined by the requirements of Table IWB-2500 and Table IWB-2600 Category B-J of Section Xl of the ASME BPV Code in the '1974 Edition and Addenda through the Summer 1975 Addenda or other requirements the NRC may adopt.

(Note: This reference is provided for information/completeness only, Category B-J welds will be examined in accordance with CC N-716-1.)

1 0 CFR 50.55a(b)(2)(xiv)

Section Xl condition: Appendix Vll! personnel qualification.

All personnel qualified for performing ultrasonic examinations in accordance with Appendix Vlll must receive 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of annual hands-on training on specimens that contain cracks. Licensees applying the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(t )(ii) of this section may use the annual practice requirements in Vll-4240 of Appendix Vll of Section Xl in place of the 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of annual hands-on training provided that the supplemental practice is performed on material or welds that contain cracks, or by analyzing prerecorded data from material or welds that contain cracks. ln either case, training must be completed no earlier than 6 months prior to performing ultrasonic examinations at a licensee's facility.

1 0 CFR 50.55a(b)(2XxviiiXA)

N D E person nel certification : First provision.

Level I and ll nondestructive examination personnel must be recertified on a 3-year interval in lieu of the S-year interval specified IWA*2314(a) and IWA-2314(b).

WBN uNlr I ASME sEcfloN xr rsl/NDE l1-TRr-0-1 0.3 Unit 1 PROGRAM THIRD INTERVAL lRev.0001 Paqe 12 of 174 1.3.1 Current Code Requirements (continued) 10 GFR 50.55a Reference Mandated Additional Requirements/Conditions/Exemptions 1 0 CFR 50.55a(bX2XxxiXA)

Table IWB-2500-1 examination requirements: First provision.

The provisions of Table IWB 2500-1, Examination Category B-D, Full Penetration Welded Nozzles in Vessels, ltems 83.120 and 83.140 (lnspection Program B) of the 1998 Edition must be applied when using the 1999 Addenda through the latest edition and addenda incorporated by reference in paragraph (aXl Xii) of this section. A visual examination with magnification that has a resolution sensltivity to detect a 1-milwidth wire or crack, utilizing the allowable flaw length criteria in Table IWB-3512-1,1997 Addenda through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, with a limiting assumption on the flaw aspect ratio (i.e., a/l = 0.5), may be performed instead of an ultrasonic examination.

1 0 CFR 50.55a(b)(2)(xxii)

Section Xl condition: Surface examination.

The use of the provision in IWA-2220, "Surface Examination," of Section Xl, 2001 Edition through the latest edition and addenda incorporated by reference in paragraph (a)(1)(ii) of this section, that allows use of an ultrasonic examination method is prohibited.

1 0 CFR 50.55a(b)(2)(xxix)

Section Xl condition: Nonmandatory Appendix R.

Nonmandatory Appendix R, "Risk-lnformed lnspection Requirements for Piping,"

of Section Xl, 2005 Addenda through the latest edition and addenda incorporated by reference in paragraph (aXl Xii) of this section, may not be implemented without prior NRC authorization of the proposed alternative in accordance with paragraph (z) of this section.

10 CFR 50.55a(bx5)

Conditions on inservice inspection Gode Cases.

Licensees may apply the ASME BPV Code Cases listed in Regulatory Guide 1.147, Revision 17, without prior NRC approval, subject to the following:

10 CFR 50.55a(b)(5xi) lSlGode Case condition: Applying Code Gases.

When a licensee initially applies a listed Code Case, the licensee must apply the most recent version of that Code Case incorporated by reference in paragraph (a) of this section.

10 CFR 50.55a(b)(5xii) lSl Gode Case condition: Applying different revisions of Code Cases.

lf a licensee has previously applied a Code Case and a later version of the Code Case is incorporated by reference in paragraph (a) of this section, the licensee may continue to apply, to the end of the current 12O-month interval, the previous version of the Code Case, as authorized, or may apply the later version of the Code Case, including any NRC-specified conditions placed on its use.

Licensees who choose to continue use of the Code Case during subsequent 12O-month lSl program intervals will be required to implement the latest version incorporated by reference into 10 CFR 50.55a as listed in Tables 1 and 2 of Regulatory Guide 1.147, Revision 17.

WBN UNIT l ASME SECTION XI ISI/NDE I 1.TRI.O-1 0.3 Unit 1 PROGRAM THIRD INTERVAL lRev. 0001 Paqe 13 of 174 1.3.1 Current Code Requirements (continued) 10 CFR 50.55a Reference M a n dated Add itio nal Req u i rem ents/Go nd iti ons/Exe m ptio ns 1 0 CFR 50.55a(b)(5xiii)

ISlCode Gase condition: Applying annulled Code Cases.

Application of an annulled Code Case is prohibited unless a licensee previously applied the listed Code Case prior to it being listed as annulled in Regulatory Guide 1.147.lf a licensee has applied a listed Code Case that is later listed as annulled in Regulatory Guide 1.147, the licensee may continue to apply the Code Case to the end of the current 120-month interval.

10 CFR 50.55a(gX5Xiv) lSl program update: Schedule for completing impracticality determinations.

Where the licensee determines that an examination required by Code edition addenda is impractical, the basis for this determination must be submitted for NRC review and approval not later than 12 months after the expiration of the initial or subsequent 12O-month inspection interval for which relief is sought.

or 1 0 CFR 50.55a(sXoXiiXDXl)

Augmented lSl requirements: Reactor vessel head inspections.

All licensees of pressurized water reactors must augment their inservice inspection program with ASME Code Case N-729-1, subject to the conditions specified in paragraphs (gX6XiiXD)(2) through (6) of this section.

(Program Note: (gX6)(iiXDX4) By September 1, 2009, ultrasonic examinations must be performed using personnel, procedures, and equipment that have been qualified by blind demonstration on representative mockups using a methodology that meets the conditions specified in paragraphs (gXOXiiXD)(4X0 through (lv), instead of the qualification requirements of Paragraph -2500 of ASME Code Case N-729-1. References herein to Section Xl, Appendix Vlll, must be to the 2004 Edition with no addenda of the ASME BPV Code.)

lmplementation of this requirement is part of the Augmented Examination Program (Appendix K).

10 CFR s0.SSa(sXoXiiXEXl )

Augmented lSl requirements: Reactor coolant pressure boundary visual inspections.

All licensees of pressurized water reactors must augment their inservice inspection program by implementing ASME Code Case N-722-1, subject to the conditions specified in paragraphs (gx6)(iiXE)(2) through (4) of this section. The inspection requirements of ASME Code Case N-722-1 do not apply to components with pressure retaining welds fabricated with Alloy 6001821182 materials that have been mitigated by weld overlay or stress improvement.

lmplementation of this requirement is part of the Augmented Examination Program (Appendix K).

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 14 of 174 10 CFR 50.55a Reference Mandated Add itional Req u i rements/Cond itions/Exem ptions 10 CFR so.SSa(gXoXiiXFXl )

Augmented lSl requirements: Examination requirements for Class 1 piping and nozzle dissimilar-metal butt welds.

Licensees of existing, operating pressurized-water reactors as of July 21,2011 shall implement the requirements of ASME Code Case N-770-1, subject to the conditions specified in paragraphs (gXOXiiXF)(2) through (gx6xiiXFX70) of this section, by the first refueling outage after Augusl22,2011.

lmplementation of this requirement is part of the Augmented Examination Program (Appendix K).

1.3.1 Current Code Requirements (continued) 1.3.2 Current Gode Cases Any code case applicable to ASME Section Xl and listed in the most recently approved revision of Regulatory Guide 1.147 may be used without prior NRC approval. Code cases used shall be implemented in their entirety unless limitations have been imposed by NRC or are stated in Regulatory Guide 1.147,Table 2.

lmplementation of any conditions on the use of the code case specified in Regulatory Guide 1.147 is required. lnitial implementation of a code case must be of the most recently approved revision stated in the current Regulatory Guide 1.147. All Code Cases listed in the table below are considered implemented at the time of initial issuance of this plan. However, once a code case is implemented, update to a later approved revision is not required until the end of the lnspection lnterval.

As required to be listed in this plan in accordance with IWA-2420(aX4) and IWA-2441(a), the following Code Cases were accepted for use by the NRC in Regulatory Guide 1.147, Revision 17, and are available and listed for use in this Plan for Watts Bar Unit 1.

Additionally, Code Cases N-722-1, N-729-1, and N-770-1 are Code Cases that are required for use in accordance with 10 CFR 50.55a and are implemented in accordance with Appendix K of this TRl.

Code Case Title / Conditions N-432-1 Repair Welding Using Automatic or Machine Gas Tungsten-Arc Welding (GTAW) Temper Bead Technique N-508-4 Rotation of Serviced Snubbers and Pressure Relief Valves for the Purpose of Testing Gonditions for Use:

When Section Xl requirements are used to govern the examination and testing of snubbers and the lSl Code of Record is earlier than Section Xl, 2006 Addenda, Footnote 1 shall not be applied.

WBN UNIT l ASME SECTION XI ISI/NDE I1.TRI.O.1 0.3 Unit 1 PROGRAM THIRD INTERVAL lRev. 0001 Paqe 15 of 174 1.3.2 Current Code Cases (continued)

Code Case Title / Conditions N-513-3 Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Conditions for Use:

The repair or replacement activity temporarily deferred under the provisions of this Code Case shall be performed during the next scheduled outage.

N-516-3 Underwater Welding Licensees must obtain NRC approval in accordance with '10 CFR 50.55a(z) regarding the technique to be used in the weld repair or replacement of irradiated material underwater.

N-526 Alternative Requirements for Successive lnspections of Class 1 and 2 Vessels N-532-5 Alternative Requirements to Repair and Replacement Documentation Requirements and lnservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000 N-561-2 Alternative Requirements for Wall Thickness Restoration of Class 2 and High Energy Class 3 Carbon Steel Piping Conditions for Use:

(1) Paragraph 5(b): for repairs performed on a wet surface, the overlay is only acceptable until the next refueling outage.

(2) Paragraph 7(c): if the cause of the degradation has not been determined, the repair is only acceptable untilthe next refueling outage.

(3)The area where the weld overlay is to be applied must be examined using ultrasonic methods to demonstrate that no crack-like defects exist.

(4) Piping with wall thickness less than the diameter of the electrode shall be depressurized before welding..

N-562-2 Alternative Requirements for Wall Thickness Restoration of Class 3 Moderate Energy Carbon SteelPiping Conditions for Use:

(1) Paragraph 5(b):for repairs performed on a wet surface, the overlay is only acceptable until the next refueling outage.

(2) Paragraph 7(c): if the cause of the degradation has not been determined, the repair is only acceptable untilthe next refueling outage.

(3) The area where the weld overlay is to be applied must be examined using ultrasonic methods to demonstrate that no crack-like defects exist.

(4) Piping with wall thickness less than the diameter of the electrode shall be depressurized before welding.

WBN UNIT l ASME SECTION XI ISI/NDE I 1.TRI.O.1 0.3 Unit 1 PROGRAM THIRD INTERVAL IRev. 0001 Paqe 16 of 174 1.3.2 Gurrent Code Gases (continued)

Code Case Title / Gonditions N-569-1 Alternative Rules for Repair by Electrochemical Deposition of Class 1 and 2 Steam Generator Tubing Conditions for Use:

NOTES: Steam Generator tube repair methods require prior NRC approval through the Technical Specifications. This Code Case does not address certain aspects of this repair, e.9.,

the qualification of inspection and plugging criteria necessary for staff approval of the repair method. ln addition, if the user plans to "reconcile," as described in Footnote 2, the reconciliation is to be performed in accordance with IWA-4200 in the 1995 Edition through the 1996 Addenda of ASME Section Xl N-586-1 Alternative Additional Examination Requirements for Classes 1,2, and 3 Piping, Components, and Supports, Section Xl, Division 1 N-597-2 Requirements for Analytical Evaluation of Pipe Wall Thinning, Section Xl, Division 1 Conditions for Use:

(1) Code Case must be supplemented by the provisions of EPRI Nuclear Safety Analysis Center Report 202L-R2,"Recommendations for an Effective Flow Accelerated Corrosion Program" (Ref. 6), April 1999, for developing the inspection requirements, the method of predicting the rate of wall thickness loss, and the value of the predicted remaining wall thickness. As used in NSAC-202L-R2, the term "should" is to be applied as "shall" (i.e., a requirement).

(2) Components affected by flow-accelerated corrosion to which this Code Case are applied must be repaired or replaced in accordance with the construction code of record and Owner's requirements or a later NRC approved edition of Section lll, "Rules for Construction of Nuclear Power Plant Components," of the ASME Code (Ref. 7) prior to the value of tp reaching the allowable minimum wall thickness, tmin, as specified in -3622.1(aX1) of this Code Case.

Alternatively, use of the Code Case is subject to NRC review and approval per 10 CFR 50.55a(z).

(3) For Class 1 piping not meeting the criteria of -3221, the use of evaluation methods and criteria is subject to NRC review and approval per 10 CFR 50.55a(z).

N-600 Transfer of Welder, Welding Operator, Btazer, and Brazing Operator Qualifications Between Owners N-613-1 Ultrasonic Examination of Full Penetration Nozzles in Vessels, Examination Category B-D, Item Nos. 83.10 and 83.90, Reactor Nozzle-to-VesselWelds, Figs. IWB-2500-7(a), (b), and (c)

N-629 Use of Fracture Toughness Test Data to Establish Reference Temperature for Pressure Retaining Materials N-639 Alternative Calibration Block Material Conditions for Use:

Chemical ranges of the calibration block may vary from the materials specification if (1) it is within the chemical range of the component specification to be inspected, and (2) the phase and grain shape are maintained in the same ranges produced by the thermal process required by the material specification.

WBN UNIT l ASME SECTION XI ISI/NDE I 1.TRI-0.1 0.3 Unit 1 PROGRAM THIRD INTERVAL lRev. 0001 Paqe 17 of 174 1.3.2 Current Gode Cases (continued)

Code Case Title / Conditions N-641 Alternative Pressure-Temperature Relationship and Low Temperature Overpressure Protection System Requirements N-643-2 Fatigue Crack GroMh Rate Curves for Fenitic Steels in PWR Water Environment N-648-1 Alternative Requirements for lnner Radius Examination of Class 1 Reactor Vessel Nozzles Conditions for Use:

ln lieu of a UT examination, licensees may perform a W-1 examination in accordance with the code of record for the lnservice lnspection Program utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio.

N-651 Ferritic and Dissimilar MetalWelding Using SMAW Temper Bead Technique Without Removing the Weld Bead Crown of the First Layer N-660 Risk-lnformed Safety Classification for Use in Risk-lnformed Repair/Replacement Activities Conditions for Use:

The Code Case must be applied only to ASME Code Classes 2 and 3, and non-Code Class pressure retaining components and their supports.

N-661-2 Alternative Requirements for Wall Thickness Restoration of Classes 2 and 3 Carbon Steel Piping for Raw Water Service Conditions for Use:

(1) Paragraph a(b): for repairs performed on a wet surface, the overlay is only acceptable until the next refueling outage.

(2) Paragraph 7(c): if the cause of the degradation has not been determined, the repair is only acceptable untilthe next refueling outage.

(3) The area where the weld overlay is to be applied must be examined using ultrasonic methods to demonstrate that no crack-like defects exist.

(a) Piping with wall thickness less than the diameter of the electrode shall be depressurized before welding.

N-705 Evaluation Criteria for Temporary Acceptance of Degradation in Moderate Energy Class 2 or 3 Vessels and Tanks N-706-1 Alternative Examination Requirements of Table IWB-2500 1 and Table IWC-2500-1 for PWR Stainless Steel Residual and Regenerative Heat Exchangers N-712 Class 1 Socket Weld Examinations N-716-1 Alternative Piping Classification and Examination Requirements

WBN UNIT l ASME SECTION XI ISI/NDE I1.TRI-0.1 0.3 Unit 1 PROGRAM THIRD INTERVAL lRev.0001 Paqe 18 of 174 1.3.2 Current Code Cases (continued)

Code Gase Title / Conditions N-722-1 Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated With Alloy 6001821182 Materials NRG Mandatory:

10 CFR 50.55a(g)(6XiiXEX1), All licensees of pressurized water reactors shall augment their inservice inspection program by implementing ASME Code Case N-722-1 subject to the conditions specified in paragraphs (gXOXiiXE)(2) through (gXOXiiXeX4)of 10 CFR 50.55a.

The inspection requirements of ASME Code Case N-722-1 do not apply to components with pressure retaining welds fabricated with Alloy 6001821182 materials that have been mitigated by weld overlay or stress improvement.

N-729-1 Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds NRC Mandatory:

10 CFR 50.55a(gX6XiiXD)(1), All licensees of pressurized water reactors shall augment their inservice inspection program with ASME Code Case N-729-1 subject to the conditions specified in paragraphs (gX6XiiXD)(2) through (6) of 10 CFR 50.55a. Licensees of existing operating reactors as of September 10, 2008 shall implement their augmented inservice inspection program by December 31, 2008. Once a licensee implements this requirement, the First Revised NRC Order EA-0F009 no longer applies to that licensee and shall be deemed to be withdrawn. NOTE: Paragraph (gX6XiiXO)(4) requires the use of the 2004 Edition of Section Xl, Appendix Vlllwith this Code Case N-731 Alternative Class 1 System Leakage Test Pressure Requirements N-735 Successive lnspection of Class 1 and 2 P,ping Welds N-747 Reactor Vessel Head-to-Flange Weld Examinations N-751 Pressure Testing of Containment Penetration Piping Conditions for Use:

When a 10 CFR 50, Appendix J, Type C test is performed as an alternative to the requirements of IWA-4540 (lWA-4700 in the 1989 edition through the 1995 edition) during repair and replacement activities, nondestructive examination must be performed in accordance with IWA-a5{0{a)(2) of the 2002 Addenda of Section Xl.

N-762 Temper Bead Procedure Qualification Requirements for Repair/Replacement Activities Without Post Weld Heat Treatment, Section Xl, Division 1 N-765 Alternative to lnspection lnterval Scheduling Requirements of IWA-2430

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 19 of 174 1.3.2 Current Code Cases (continued)

Code !nterpretations Specific Code lnterpretations that are used in this plan that correspond to the use of Section Xl requirements are listed in the table below. Code lnterpretations used by WBN as part of this plan are used with the understanding that they are neither reviewed or approved by the NRC.

History of ISI and PSI Programs A Preservice lnspection Program was performed in accordance with Technical Instruction (Tl) 50A, ASME Section Xl Preservice lnspection Program.

The WBN Unit 1 operating license (low power) was issued on November 9th, 1995.

Commercial Operation began on May 27,1996 and the first interval lSl program was originally scheduled for May 27, 1996 to May 26,2006. The first 10-year inspection interval was extended in accordance with IWA-2430(d) to end on May 26,2007.

The second interval is scheduled to end on May 26,2017.

1.3,3 1.3.4 Code Case Title I Conditions N-770-1 Alternative Examination Requirements and Acceptance Standards for Class 1 PWR Piping and Vessel Nozzle Butt Welds Fabricated With UNS N06082 or UNS W86182 Weld Filler Material With or Without Application of Listed Mitigation Activities NRC Mandatory:

10 CFR 50.55a(gX6XiiXF)(1), Licensees of existing, operating pressurized-water reactors as of July 21, 2011 shall implement the requirements of ASME Code Case N-770-1, subject to the conditions specified in paragraphs (g)(6)(ii)(F)(2) through (g)(O)(iiXrX10) of 10 CFR 50.55a, by the first refueling outage after August22,2011.

N-773 Alternative Qualification Criteria for Eddy Current Examinations of Piping lnside Surfaces, Section Xl, Division 1 SECTION XI CODE INTERPRETATIONS USED lnterpretation and Subject Date lssued and File No.

Question and Reply lSl Program Applicability None at this time.

N/A N/A N/A NOTES: None.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paoe 2A of 174 1.4 Frequency lnspection lntervals and Inspection Periods The inservice examinations required by ASME Section Xl shall be performed during each 10-year interval of service (inspection interval). The inspection intervals represent calendar years after the unit has been placed into commercial service.

The lSl examinations required by ASME Section Xl, Division 1, during this inspection interval for Unit 1 shall follow the requirements of IWA-2431; i.e., successive inspection intervals will be of 10 years following the previous inspection interval. As allowed by IWA-2430(c )(1), the inspection interval may be decreased or extended by as much as one year from the original pattern of intervals. ln addition, if the unit is out of service continuously for six months or more, the inspection interval may be extended for an equivalent period in accordance with IWA-2430(d).

Each inspection interval is divided into three (3) inspection periods. The length of each inspection period being between three (3)years to four (4) years.

IWA-2430(cX2) allows the performance of examinations to satisfy the requirements of the extended period or interval in conjunction with examinations performed to satisfy the requirements of the successive period or interval. However, an examination performed to satisfy requirements of either the extended period or interva! or the successive period or interval shall not be credited to both periods or intervals.

The first inspection interva! was extended by one year. The third inspection interval will begin prior to the end of the second inspection interval to bring the inspection interval dates back to the original pattern of intervals in accordance with IWA-2430(c)(1).

Third lnspection Interval Period durations are:

o First lnspection Period - October 19,2016 through May 26, 2019 Second Inspection Period - May 27,2019 through May 26,2023 Third lnspection Period - May 27,2023 through May 26,2026 This TRI may be performed in any mode and is applicable for all operational modes.

Except for examinations that may be deferred to the end of the inspection interval, the required examinations shall be performed in accordance with the following plan that complies with IWA-2430 and IWA-2431; IWB-2420, and Table IWB-2411-1; IWC-2411, and Table IWC-2411-1; !WD-2411, and Table IWD-2411-1; and IWF-2410 and Table IWF-2410-1.

The examinations deferred to the end of the inspection interval shall be completed by the end of the inspection interval.

This instruction is to be scheduled to be performed at least once each refueling outage.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 21 of 174 Technical Requirements Fulfilled and Modes Performance of this TRI satisfies the following Technical Surveillance Requirements:

Owner Statement SURVEILLANCE REQUIREMENT APPLICABLE MODES PERFORMANCE MODES TSR 3,4.5.1 ALL MODES MODES 5 and 6 TSR 3.4.5.2 ALL MODES ALL MODES Owner:

Tennessee Valley Authority Address of Corporate Office:

Chattanooga Office Complex fiU Market Street Chattanooga, Ten nessee 37 402-2841 Name and Address of Nuclear Power Plant:

Watts Bar Nuclear Plant P.O. Box 2000 Spring City, Tennessee 37381-2000 Applicable Nuclear Power Units:

Watts Bar Nuclear Plant, Unit 1 Gommercial Operation Date:

May 27,1996

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1 -TRl-0-1 0.3 Rev. 0001 Pase 22 of 174 2.0 DEVELOPMENTAL REFERENCES 2.1 WBN Unit 1 Technical Requirement Manual A. Technical Surveillance Requirement 3.4.5.1 and 3.4.5.2.

2.2 WBN Final Safety Analysis Report A. Section 3.2, Classification of Structures, Systems and Components B. Section 5.2.6, Pump Flywheels (Reactor Coolant Pump)

C. Section 5.2.8,lnservice lnspection of ASME Code Class 1 Components D. Section 5.4.4.4,lnservice lnspection (Reactor Vessel and Appurtenances)

E. Section 6.6, lnservice lnspection of ASME Code Class 2 and 3 Components 2.3 NRG Documents A. 10 CFR Part 50.55a, Codes and Standards, lnservice lnspection Requirements B. 10 CFR Part 50.2, Definitions C. Regulatory Guide 1.14, Reactor Coolant Pump Flywheel lntegrity D. Regulatory Guide 1.26, Quality Group Classification and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants E. Regulatory Guide 1.147,lnservice lnspection Code Case Acceptability ASME Section Xl Division 1.

F. Federal Register Notice Vol. 79, No. 214 / November 5,2014 / Rules and Regulations and became effective on December 5, 2014 as corrected by FRN /

Vol. 79, No. 238 / December 11,2014 2.4 ASME Reference Documents A. ASME Boiler and Pressure Vessel Code, Section Xl, Division 1,2007 Edition with the 2008 Addenda B. ASME Section Xl Code Cases as listed in Section 1.3

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 23 of 174 2.5 Plant Procedures and lnstructions A. Standard Programs and Processes, Department Procedures, and Site Standard Practices, Technical Procedures, Business Practices

1. NADP-1, NPG-SPP-03.18, Conduct of Quality Assessment and lnspection

2. MMTP-102, Erection of Scaffoldsffemporary Work Platforms and Ladders

3. MMTP-104 Guidelines And Methodology for Assembling And Tensioning Threaded Connections

4. NETP-113, PWR Alloy 600 Program and other Augmented lnspection Requirements

5. BP-257,lntegrated Material lssues Management Plan

6. NPG-SPP-31.2,Records Management

7. NPG-SPP-22.300, Corrective Action Program

8. NPG-SPP-O3.5, Regulatory Reporting Requirements

9. NPG-SPP-05.2, ALARA Program

10. NPG-SPP-05.4, Chemical Traffic Control

11. NPG-SPP-06.1, Work Order Process lnitiation

12. NPG-SPP-06.4, Measuring and Test Equipment

13. NPG-SPP-06.5, Foreign Material Control

14. NPG-SPP-07.2, Outage Management

15. NPG-SPP-06.9.1, Conduct of Testing

16. NPG-SPP-06.9.2, Surveillance Test Program

17. NPG-SPP-09.1, ASME Code and Augmented Programs

18. NPG-SPP-09.1.2, ASME Section Xl System Pressure Test Programs

19. NPG-SPP-09.1.3, ASME Section Xl Repair/Replacement Program

20. NPG-SPP-09.1.4, lnservice !nspection Database

21. NPG-SPP-09.3, Plant Modifications and Engineering Change Control B. Plant lnstructions

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 24 of 174 2.5 Plant Procedures and lnstructions (continued) 1. 1-Tl-1 2.07a, Containment Access Modes 1 - 4

2. 1-Tl-1 2.07b, Containment Access Modes 5 & 6 C. WBN Maintenance and Technical lnstructions

1. 0-Ml-0.002,ValveMaintenance

2. 1-Ml-68.001, Disassembly and Reassembly of the Reactor Pressure Vessel and Attachments (Unit 1)

3. 0-Ml-68.004, Reactor Coolant Pump Seal lnspection or Replacement

4. 0-Ml-68.06, Removal, lnspection and Maintenance of Reactor Coolant Pump Rotating Element

5. 1-Ml-68.007, Removal and lnstallation of Steam Generator Primary Manway Covers

6. 0-Ml-68.013, Remova! and Replacement of Pressurizer Safety Valves

7. 1-Ml-68.14, Removal and Replacement of Pressurizer Manway Cover

8. 0-MI-68.018, Adjustment and Replacement of Reactor Coolant Pump Main Flange Bolts

9. 1-Ml-68.021, Pressurizer PORV Maintenance

10. 0-Tl-203, Snubber Program

11. 1-TRl-68-6, System Leakage Test Reactor Coolant System

12. 1-TRl-68-901, Reactor Coolant 1O-Year End of Interval System Leakage Test D. lnspection and Examination Procedures

1. IEP-100, Administration of Nondestructive Examination (NDE) Procedures

2. IEP-200, Qualification and Certification Requirements for TVA Nuclear (TVAN) Nondestructive Examination (NDE) Personnel

3. IEP-203, Control of Calibration Standards

4. IEP-300, Qualification and Certification of Ultrasonic TVA Nuclear (TVAN) personnel for Preservice and lnservice ASME Section Xl Examinations

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 25 of 174 2.5 PIant Procedures and lnstructions (continued)

5. IEP-500, Surface Condition Assessment and lmprovement Process for Dissimilar Meta! Weld Ultrasonic Examinations

6. N-GP-7, Computation of Component Support Settings in Accordance With ASME Section Xl 2.6 EPRI Documents A. EPRI Materials Reliability Program (MRP)

1. MRP-126, Generic Guidance for an Alloy 600 Management Plan

2. MRP-139, Primary System Piping Butt Weld lnspection and Evaluation Guideline

3. MRP-146, Management of Thermal Fatigue in Normally Stagnant Non-lsolable Reactor Coolant System Branch Lines B. EPRI Guidelines

1. EPRI Report 1018181, Nondestructive Evaluation: Guideline for Conducting Ultrasonic Examinations of Dissimilar Metal Welds 2.7 Nuclear Energy lnstitute (NEl) Guidelines A. NE! 03-08, Guideline for the Management of Materials lssues 2.8 Westinghouse Documents A. WAT-D-12064, SG Upper Lateral Support Splice Bolts 2.9 ISI Drawings (See Appendix G)

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 26 of 174 2.10 Abbreviations ALARA ASNT ASME CFR DCRM IEP ISI NDE NRC RADPRO RFR Rt-tsl RWP SI SPP WO As Low As Reasonably Achievable American Society for Nondestructive Testing American Society of Mechanical Engineers Code of Federa! Regulations Document Control and Records Management lnspection and Examination Procedures lnservice lnspection Nondestructive Exami nation Nuclear Regulatory Commission Radiation Protection Request for Relief Risk lnformed - Inservice lnspection Radiation Work Permit Su rveillance I nstruction Standard Processes and Procedures Work Order 3.0 PREREQUISITES AND PRECAUTIONS 3.1 Prerequisites A. When craft support of minor or similar maintenance (examples: scaffolding, insulation removal, buffing of welds using Scotchbrite pads, and cleaning bolts) is required to facilitate performance of this TRl, a WO may be used. This WO shall be processed in accordance with NPG-SPP-06.1. Additional WOs are required to remove fire barrier insulation foam in sleeves, piping support clamps, steam generator support rings, reactor coolant pump flywheel access covers and plugs, etc.

B. Contact RADPRO for radiation work permit (RWPyALARA preplanning requirements. Coordination with RADPRO should begin as soon as components are identified to be scheduled for examination during a particular refueling outage.

3.2 Precautions A. Safety belts should be worn when working from scaffolding or ladders in accordance with MMTP-1 02.

B. Protective clothing, such as long-sleeve shirts, should be worn when working around hot pipes and equipment.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 27 of 174 3.2 Precautions (continued)

C. Care should be exercised when climbing on plant structures and piping to ensure firm footing and to prevent damaging site equipment. Walking on flex hoses and insulation shall be avoided.

D. Efforts should be made to ensure proper planning to reduce delays and radiation exposure in performance of the work.

E. Read and observe all applicable precautions as indicated in WBN lnstruction 1-Tl-12.07a and 1-Tl-12.07b, Containment Access, and NPG-SPP-06.5, Foreign Material Control.

4.0 SPECIAL TOOLS AND EQUIPMENT Equipment shall be specified by individual Craft and/or NDE Procedures.

5.0 ACCEPTANCE STANDARDS All acceptance standards for ASME Code Class 1,2, and 3 equivalent components and their supports shall be in accordance with IWA 3000, lWB 3000, IWC 3000, IWD 3000, IWF-3000 of ASME Section Xl; or Code Case N-716-1 for Rl lSl; and the lnspection Services Organization Programs Manuals.

Evaluations of examinations in accordance with IWB-3132.3,1W8-3142.4, IWC-3122.3,1WC-3132.3 or IWF-3'122.3 shall be submitted to the regulatory authority having jurisdiction at the plant site as part of the Owners Activity Report (OAR) reporting requirements of Code Case N-532-5 and the results of any IWB-3600, IWC-3600, or IWD-3600 evaluations that have been completed and/or reviewed by the regulatory authority having jurisdiction at the plant site.

NOTE Evaluations of examinations performed in accordance with this plan contained in IWB-3600, IWC-3600, or IWD-3600 shall be, as required by Section Xl, submitted to the regulatory authority having jurisdiction at the plant site for review or approval. These submittals should be to made as soon as possible when the evaluations are completed as they may affect startup during a refueling outage.

WBN UNIT l ASME SECTION XI ISI/NDE I 1.TRI.O.1 0.3 Unit 1 PROGRAM THIRD INTERVAL lRev. 0001 Paqe 28 of 174 5.0 ACCEPTANCE STANDARDS (continued)

Acceptance Standards Examination Category Components and Parts Examined Acceptance Standard B-A Welds in Reactor Vessel rwB-3510 B-B Welds in other vessels lwB-3510 B-D Nozzle welds in vessels rwB-3512 B-F RX Vessel dissimilar metal welds IWB-3514 or See Exam. Cat. R-A or Code Case N-770-7, as applicable B-G-1 Class 1 Bolting >2" twB-3515, tWB-3517 B-G-2 Class 1 Bolting>2" twB-3517 B-J Welds in piping IWB-3514 or See Exam. Cat. R-A B-K Welded attachments rwB-3516 B-L.2 Pump casings twB-3519 B-M-2 Valve bodies lwB-3519 B-N-1 Reactor vessel interior twB-3524.2 B-N-2 Reactor vessel integrally welded core support structures lwB-3 52A.1, tWB-3 520.2, respectively B.N-3 Reactor vessel removable core support structures twB-3520.2 B-O Welds in CRD housings IWB-3523 B-P Pressure Retaining Components IWB-3522 C-A Welds in pressure vessels lvvc-3s10 C-B Nozzle welds in vessels lwc-3511 C-C Welded attachments for Class 2 Pressure vessels; Piping, Pumps, and Valves rwc-3512 C-D Class 2 Bolting >2" in Diameter twc-3513 C-F.1 Welds in austenitic stainless steel or high alloy piping IWC-3514 (lWB-3514) or See Exam.

Cat. R-A

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 29 of 174 Acceptance Standards Examination Category Components and Parts Examined Acceptance Standard C-F-2 Welds in carbon or low alloy steel piping IWC-3514 (lWB-3514) or See Exam.

Cat. R-A C-H Pressure Retain ing Components rwc-3516 (rwB-3522)

D-A Welded Attachments for Vessels, Piping, Pumps, and Valves rwD-3000 (rwc-3500)

D-B All Pressure Retaining Components rwD-3000 (rwc-3500)

F-A Supports lwF-341A R.A Risk lnformed Piping Examinations Code Case N-716-1 twB-3514 Code Case N-722-1 PWR Components Containing Alloy 6001821182 twB-3s22 Code Case N-729-1 Class 1 PWR Reactor Vessel Upper Head

-31 30, -3140 Code Case N-770-1 Class 1 PWR Pressure Retaining Dissimilar Metal Piping and Vessel Nozzle Butt Welds Containing Alloy 821182

-31 30, -3140 5.0 ACCEPTANCE STAN DARDS (continued) 7.0 QUALIFICATIONS OF NDE PERSONNEL Personnel performing NDE operations shall be qualified and certified in accordance with IWA-2300, IEP-200, IEP-300, and IEP-500 if the examination of dissimilar metal welds is required.

IMPLEMENTATION AND RESPONSIBILITIES Anv revisions to this prooram initiated bv other oroups shall be submitted to lSl/NDE for aooroval orior to incorporatino the revisions into this orooram.

Responsibilities shall be in accordance with NPG-SPP-09.1, Part A.

6.0

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paoe 30 of 174 7.1 NDE Examinations A. NDE methods shall be in accordance with IWA-2200 of ASME Section X! and this program as planned in Appendices A-D.

B. NDE shall be performed in accordance with IWA-2200 and the individual NDE Procedures of IEP-100.

C. !n accordance with IWA-2600, a reference system shall be established for all welds and areas subject to surface or volumetric examination. Each such weld and area shall be located and identified by a system of reference points in accordance with applicable NDE procedures. The system shall permit identification of each weld, location of each weld centerline, and designation of regular intervals along the length of the weld.

7.1.1 NDE Coverage Requirements A. All nondestructive examinations of the required examination, surface or volume, shall be conducted to the maximum extent practical. When performing VT-1, surface, radiographic, or ultrasonic examination on a component with defined surface or volume, Essentially 100% of the required surface or volume shall be examined. Essentially 100% coverage is achieved when the applicable examination coverage is greater than g0o/oi however, in no case shall the examination be terminated when greater than 90% coverage is achieved, if additional coverage of the required examination surface or volume is practical.

B. The lSl program owner shall be notified prior to the performance of any examination that is anticipated to result in less then 100% coverage. Alternative examination methods and substitutions of more accessible components shall be considered.

C. When maximum extent practical of a required code examination is less than 100o/o of the required code examination volume or area, the percentage of examination shall be documented on the examination data sheet. The cause of the limitation shall be clearly specified and documented on the examination data sheet. Additionally, when the maximum extent practical of a required code examination is less than Essentiallyl00% of the required code examination volume or area, the extent of examination shall be handled as a request for relief in accordance with NPG-SPP-O9.1, Part A.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 31 of 174 7.2 Components Subject to Examination A. ASME Class 1 Equivalent Components Subject to Examination (lWB) 1.

2.

3.

4, 6.

7.

5.

The ASME Class 1 equivalent systems subject to examination include all or parts of: Chemical and Volume Control System; Reactor Coolant System; Residual Heat Removal System; and Safety lnjection System.

The specific components subject to examination are identified on drawings listed in Appendix G, ISI Drawings List.

Components are scheduled for examination in accordance with ASME Section Xl, Table IWB-2500-1. The number of components within each system, the number selected for examination during the interval and the number selected for examination by period are provided in Appendix A.

ASME Class 1 valves subject to examination are listed in Appendix F.

The rules of IWB-1 220 (a), (b),and (c) have been used to establish exemption criteria for components and establish the numbers in Appendix A.

Examination Category B-A, B-B, B-D, B-G-1, B-G-2, B-K, B-L-2, B-M-2, B-N-1, B-N-2, B-N-3, B-O, and B-P components shall be selected for examination in accordance with Table IWB-2500-1,2007 Edition with the 2008 Addenda of ASME Section Xl except as modified by CC N-716-1.

Code Category B-F and B-J piping welds for purposes of inservice examination have been reclassified as Code Category R-A in compliance with Code Case N-716-1, "Alternative Piping Classification and Examination Requirements, Section Xl, Division 1". Periodic updates to the Rl-lSl program will be required as discussed in Section7.12.5.

Examination requirements for ASME Class 1 component supports, Examination Category F-A, shall be in accordance with ASME Section Xl Subsection lWF. See Section7.2D.

Welded support attachment examination is also required whenever component support member deformation (e.9., broken, bent, or pulled out parts) is identified during operation, refueling, maintenance, examination, inservice inspection, or testing.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paoe 32 of 174 7.2 Components Subject to Examination (continued)

B. ASME Class 2 Equivalent Components Subject to Examination (!WC)

1. ASME Class 2 equivalent systems subject to examination include all or parts of: 'Containment Spray System; Feedwater System; Emergency Core Cooling System (includes portions of Containment Spray, Chemical Volume Control, Safety !njection and Residual Heat Removal,); Main Steam System; Residual Heat Removal System; Safety lnjection System, and Steam Generator Blowdown System. The specific components subject to examination are identified on drawings listed in Appendix G, lSl Drawings List.

2. Components are scheduled for examination in accordance with ASME Section Xl, Table IWC-2500-1,2007 Edition with the 2008 Addenda of ASME Section Xl. The number of components within each system, the number selected for examination during the interval and the number selected for examination by period are provided in Appendix B.

3. The rules of IWC-1220 have been used to establish exemption criteria for components and establish the numbers in Appendix B.

4. Examination Category C-A, C-8, C-C, C-D, and C-H components shall be selected for examination in accordance with Table IWC-2500-1 except as modified by CC N-716-1.

5. Code Category C-F-1 and C-F-2 piping welds for purposes of inservice inspection have been reclassified as Code Category R-A in compliance with Code Case N-716-1, "Alternative Piping Classification and Examination Requirements, Section Xl, Division 1". Periodic updates to the Rl-lSl program will be required as discussed in SectionT.'12.5.

6. Examination requirements for ASME Class 2 component supports, Examination Category F-A, shall be in accordance with ASME Section Xl Subsection lWF. See Section7.2D.

7. Welded support attachment examination is also required whenever component support member deformation (e.9.: broken, bent, or pulled out parts) is identified during operation, refueling, maintenance, examination, inservice inspection, or testing.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paoe 33 of 174 7.2 Components Subject to Examination (continued)

C. ASME Class 3 Equivalent Components Subject to Examination (lWD)

1. ASME Class 3 equivalent systems subject to examination include all or parts of: Auxiliary Feedwater System; Component Cooling System; Essential Raw Cooling Water System; Fuel Pool Cooling and Cleaning System; and, High Pressure Fire Protection System. The specific components subject to examination are identified on drawings listed in Appendix G, lsl Drawings List.

2. The rules of IWD-1220 have been used to establish exemption criteria for components.

3. Examination Category D-A and D-B components shall be selected for examination in accordance with Table IWD-2500-1.

4. Examination requirements for ASME Class 3 component supports, Examination Category F-A, shall be in accordance with ASME Section Xl Subsection lWF. See Section7.2D.

D. Component Supports Subject to Examination (lWF)

1. Component supports shall be examined in accordance with Table IWF-2500-1. Component supports to be examined shall be the supports of components NOT exempted in accordance with section 7.2D.2. These component and piping supports are within the systems identified in sections 7.24.1,7.28.1, and 7.2C.1. The specific supports subject to examination are identified on lSl Drawings listed in Appendix G.

2. Component supports exempt from NDE examinations are those connected to piping or other items exempted from volumetric, surface or VT-1 or VT-3 visual exa mi nation by IWB-1 220, IWC-1 220, and IWD-1 220, and portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe.

3. Supports depicted as snubbers on the support drawings are subject to examination up to but not including the connection to the snubber assembly (pins) in accordance with IWF-1300(h). The snubber is outside the examination boundary. The examination/testing of snubbers is covered by the Snubber lnservice Testing Program.

4. The number of supports subject to an examination sample plan, the number selected for examination during the inspection interval and the number selected for examination by period are provided in Appendix D.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0,1 0.3 Rev. 0001 Paoe 34 of 174 7.2 Gomponents Subject to Examination (continued)

5. Support examination boundaries shall be in accordance with IWF-1300.

Acceptance range for support settings shall be calculated in accordance with lnspection Services Organization Programs Manuals (Refer to Nondestructive Examination Procedure N-GP-7).

6. Component supports that have been adjusted in accordance with IWF-3000 or corrected by repair or replacement shall be preservice examined prior to return of the system to service per the applicable examinations listed in Table IWF-2500-1.

Also, for systems that operate above 200 degrees F during normal operation, an additional preservice examination shall be performed on the affected component support(s) during or following the subsequent system heat-up and cool-down cycle unless determined unnecessary by evaluation. This examination shall be performed during operation or at the next refueling outage.

7. Piping support function is determined by using the latest analysis drawing with change paper for piping. lf the piping does not have an associated analysis drawing, the latest support drawing with change paper will be used to determine support function.

a. Support Function A - Supports such as one-directional restraints.

b. Support Function B - Supports such as multidirectional restraints.

c. Support Function C - Supports that allow thermal movement, such as variable or constant force springs.

d. Support Function D - Either hydraulic or mechanical snubbers.(portions of supports that contain snubbers, but outside of the snubber pins) 7.3 Notification of lndication ln the event an unacceptable indication is identified in the course of an inservice examination, a CR shall be written and a Notice of lndication(NOl) shall be initiated in accordance with NPG-SPP-09.1, Part A. The NOI is to be used to:

A. Notify Plant Management of unacceptable indications found during the performance of a scheduled ASME Section Xl inservice examination that will require evaluation and a disposition in accordance with plant procedures.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 35 of 174 7.3 7.4 Notification of lndication (continued)

B. Notify lSl/NDE Representative of indications that exceed the acceptance criteria of Article IWX-3000 of the ASME Section Xl Code and that the indications have been documented on an examination report form contained within the NDE procedure used for examination.

C. Provide ISO and ISI/NDE Representative with a method to track examination reports that require reexamination or a documented disposition for closure.

D. As a final product, with the disposition provided in accordance with plant procedures added to Part l! of the NOI Form; to provide the lSl/NDE representative a method of determining if additional and/or successive examinations are required in accordance with the Code.

Additional Examinations for ASME Gode Class 1,2, and 3 After a Notification of lndication (NOl) has been dispositioned and returned to the lSl/NDE Representative (reference Section 7.3), the NOI shall be evaluated to determine if additional examinations shall be required in accordance with ASME Section Xl IWB-2430, IWC-2430, IWD-2430, or IWF-2430. If it is determined that additional examinations are required, these examinations shall be performed during the same outage as the initial examinations. A sample is defined as those items (welds, areas, or parts) as described or intended in a particular examination category and item number. The additional examination samples shall be selected from welds, areas, or parts of similar material and service preferably within the same system. However, this additiona! selection may require inclusion of piping systems other than the one containing the flaws or relevant conditions. The initial sample is defined as the sample scheduled for examination at a particular outage for Section XI credit.

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 36 of 174 7.4 Additional Examinations for ASME Code Class 1,2, and 3 (continued)

NOTE Code Case N-586-l "Alternative Additiona! Examination Requirements for CIass 1,2,3 Piping, Gomponents, Supports" Code Case N-586-1 may be used as an alternative to additional examination requirements of ASME Section Xl, provided the engineering evaluations addressed under ltem (a) of the code case and the additional examinations addressed under ltem (b) of the code case shall be performed during the current outage. lf the additional examinations performed under item (b) of the code case reveal indications exceeding the applicable acceptance criteria of Section Xl, the engineering evaluations and the examinations shall be further extended to include additional evaluations and examinations during the current outage.

NOTES A. Class 1 and 2 piping welds for the third inspection interval shall be in accordance with the Rl-lSl additional examination requirements of Code Case N-716-1, as outlined in section 7.12.

B. Welds, areas, or parts are those described or intended in a particular inspection item of Table IWX-2500-1.

C. An inspection item, as listed in Table IWX-2500-1, may comprise a number of welds, areas, or parts of a component required to be examined in accordance with the inspection plan and schedule (lWA-2420).

Additional Examinations for Class 1 Equivalent Components (lWB)

Additional examinations for Class 1 equivalent components (lWB), excluding supports, shall be in accordance with the requirements of IWB-2430.

1. Examinations performed in accordance with Table IWB-2500-1, except for Examination Category B-P, of the initial sample that reveal flaws or relevant conditions exceeding the acceptance standards of Table IWB-3410-1 shall be extended to include additional examinations except for volumetric and surface examinations where IWB-3112(b) is applicable.

(Such as, flaws detected by volumetric or surface examinations that meet the nondestructive examination standards of NB-2500 and N8-5300, as documented in QA records, shall be acceptable).

A.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 37 of 174 7.4 Additional Examinations for ASME Code CIass 1,2, and 3 (continued) 2, The first additional examination sample shall include an additional number of welds, areas, or parts included in the inspection item equal to the number of welds, areas, or parts included in the inspection item that were scheduled to be performed during the present inspection period. The additional examinations shall be selected from welds, areas, or parts of similar material and service. This additional selection may require inclusion of piping systems other than the one containing the flaws or relevant conditions.

3. lf the first additional examinations of section 7.4.A.2 reveal flaws or relevant conditions exceeding the acceptance standards of Table IWB-3410-1, except where IWB-31 12(b) is applicable; the examinations shatl be further extended to include additional examinations during the current outage. The second additional examination sample shall include the remaining number of welds, areas, or parts of similar material and service subject to the same type of flaws or relevant conditions.

4. lf examinations performed in the second additional examination sample reveal indications exceeding the acceptance standards of Table IWB-3410-1, the indications shall be evaluated for further action, if needed.

5. For the inspection period following the period in which the examinations of IWB-2430(a) or (b) were completed, the examinations shall be performed as originally scheduled in accordance with IWB-2400.

6. lf welded attachments are examined as a result of identified component support deformation, and the results of these examinations exceed the acceptance standards of Table IWB-3410- 1, additional examinations shall be performed, if determined necessary, based on an evaluation.

B. Additional Examinations for Class 2 Equivalent Components (!WC)

Additional examinations for Class 2 equivalent components (lWC), excluding supports, shall be in accordance with IWC-2430. The additional examination samples are defined as those items (welds, areas, or parts) in a particular examination category and item number and within the same system. The initial sample is the sample scheduled for examination at a particular outage for ASME Section Xl credit.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 38 of 174 7.4 Additional Examinations for ASME Code Glass 1,2, and 3 (continued)

1. Examinations performed in accordance with Table IWB-2500-1, except for Examination Category C-H, of the initial sample that reveal indications exceeding the acceptance standards of table IWC-3410-1 shall be extended to include additional examinations in the same outage except for volumetric and surface examinations where IWC-31 12(b) is applicable.

(Such as, flaws detected by volumetric or surface examinations that meet the nondestructive examination standards of NC-2500 and NC-5300, as documented in QA records, shall be acceptable).

2. The first additional sample shall include an additional number of items included in the inspection item equal b 2Ao/o of the number of items included in the inspection item that are scheduled to be performed during the inspection interval. The additional examination sample shall be selected from items of similar material and service. This additional selection may require inclusion of piping systems other than the one containing the flaws or relevant conditions.

3. lf the first additional examinations of Section 7.4.8.2 reveal flaws or relevant conditions exceeding the acceptance standards of Table IWC-3410-1, except where IWC-3121(b) is applicable, the examinations shall be further extended to include additional examinations during the current outage. The second additional examination sample shall include the remaining number of items of similar material and service subject to the same type of flaws or relevant conditions.

4. For the inspection period following the period in which the examinations of 7.4.8.2 or 7.4.8.3 were completed, the examinations shall be performed as originally scheduled in accordance with IWC-2400.

5. lf welded attachments are examined as a result of identified component.

support deformation, and the results of these examinations exceed the acceptance standards of Table IWB-3410- 1, additional examinations shall be performed, if determined necessary, based on an evaluation.

C. Additional Examinations for Class 3 Equivalent Components (lWD)

Additional examinations for Class 3 equivalent components (lWD) shall be in accordance with IWD-2430.

1. Examinations performed in accordance with Table IWB-2500;1, except for Examination Category D-B, of the initial sample that reveal flaws or relevant conditions exceeding the acceptance standards of Table IWD-3000 shall be extended to include additional examinations during the current outage.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 39 of 174 7.4 Additional Examinations for ASME Gode Class 1,2, and 3 (continued)

2. The first additional sample shall include an additional number of welds, areas or parts included in the inspection item that are scheduled to be performed during the inspection interval equal to 20o/o of the number of welds, areas, or parts included in the inspection interva!. The additional examination sample shall be selected from welds, areas, or parts of similar material and service. This additional selection may require inclusion of piping systems other than the one containing the flaws or relevant conditions.

3. lf the first additional examination sample of section 7.4.C.2 reveals flaws or relevant conditions exceeding the acceptance standards of Table IWD-3000, the examinations shall be further extended to include additional samples during the current outage. The extent of the additional examinations shall be determined by engineering based upon an engineering evaluation of the root cause of the flaws or relevant conditions.

The corrective actions shall be documented in accordance with IWA-6000.

4. For the inspection period following the period in which the examinations of 7.4.C.2 or 7.4.C.3 were completed, the examinations shall be performed as originally scheduled in accordance with IWD-2400.

5. lf welded attachments are examined as a result of identified component support deformation, and the results of these examinations exceed the acceptance standards of Table IWB-3410- 1, additional examinations shall be performed, if determined necessary, based on an evaluation.

D. Additional Examinations for Component Supports (lWF)

Additional examinations for component supports (lWF) shall be in accordance with IWF-2430.

1. Examinations performed in accordance with IWF-2500 of the initial sample that reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400 and that require corrective action shall be extended during the current outage, a) to include component supports immediately adjacent to those component supports for which corrective measures are required, and b) to include additional supports within the system, equa! in number and of the same type and function as those scheduled for examination during the inspection period.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 40 of 174 7.4 Additional Examinations for ASME Code Class 1, 2, and 3 (continued)

2. When the second additional sample of section7.4D.1 reveals flaws or relevant conditions exceeding the acceptance standards of IWF-3400 and that require corrective action, examinations shall be extended to include a third additional sample of all nonexempt supports potentially subject to the same failure modes that required corrective actions in accordance with 7.4.D.1 and7.4.D.2. Also, these additional examinations shall include nonexempt component supports in other systems when support failures requiring corrective actions indicate non-system related failure modes.

3. When the third additional sample of section 7.4D.2 reveals flaws or relevant conditions exceeding the acceptance standards of IWF-3400 and that require corrective action, examinations shall be extended to those exempt component supports that could be affected by the same observed failure modes and could affect nonexempt components.

E. Completion of Additional Examinations (lWB, IWC, lWD, and IWF)

After ASME Section Xl Code requirements for additional examinations are complete and the final sample examinations reveal indications, which exceed the acceptance standards of Article IWX-3000, the indications shall be evaluated for further action, if needed, within the affected system(s) and/or other systems.

Site Engineering shall be notified by using the Notification of Additional Sample Results Form in Appendix l. lncluded in the notification should be a summary of the indications found, number of examinations, number of indications in each sample, type of examinations performed, examination category, item number, copies of the NOls, and any other pertinent information.

Site Engineering will complete the Evaluation/Recommendation section of Appendix l. The recommendation forms the basis for any additional examination. The Additional Comoonents to be Examined section may be completed by Site Engineering OR completed by lSl/NDE based on the guidance provided by Site Engineering in their recommendation.

F. Additional Examinations for Rl-lSl Components (R-A)

As an alternative to the additional examination requirements of IWB-2430, IWC-2430, or IWD-2430, the following requirements shall be met.

1. Examinations performed in accordance with Table 1 of this Case, that reveal flaws or relevant conditions exceeding the acceptance standards of Table IWB-3410-1, shall be extended to include a first sample of additional examinations during the current outage.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI IS!/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 41 of 174 7.4 Additional Examinations for ASME Code Class 1, 2, and 3 (continued)

The piping structural elements (welds) to be examined in the first sample of additional examinations shall include HSS elements with the same postulated degradation mechanism in systems whose materials and service conditions are similar to the element that exceeded the acceptance standards.

The number of examinations required is the number of HSS elements with the same postulated degradation mechanism scheduled for the current inspection period. lf there are not enough HSS elements to equal this number, then the remaining HSS elements and LSS elements shall be added up to and including this number that are subject to the same degradation mechanism.

lf the additional examinations required by 7.4F.1reveal flaws or relevant conditions exceeding the acceptance standards of Table IWB-3410-1, the examinations shall be extended to include a second sample of additional examinations during the current outage.

The second sample of additional piping structura! elements to be examined shall include all remaining HSS piping structural elements in subject to the same degradation mechanism, and The Owner shall also examine LSS piping structural elements subject to the same degradation mechanism or document the basis for their exclusion.

7.5 Corrective Action Program and Successive Examinations Corrective actions required as a result of lSl examinations shal! be handled in accordance with NPG-SPP -22.300.

The sequence of component examinations which was established during the first inspection interval shall be repeated during each successive inspection interval, to the extent practical. The sequence of component examinations may be modified in a manner that optimizes scaffolding, radiological, insulation removal, or other considerations, provided that the required number of examinations is maintained.

If welded attachments are examined as a result of identified component support deformation and the results of these examinations exceed the applicable acceptance standards; successive examinations shall be performed, if determined necessary, based on an evaluation.

a.

b.

2.

a.

b.

A. Successive Examinations - Class 't Equivalent Components

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 42 of 174 7,5 Corrective Action Program and Successive Examinations (continued)

Areas containing flaw indications or relevant conditions evaluated in accordance with IWB-3132.3 or IWB 3142.4 and NPG-SPP-22.300 that qualify for continued service shall be reexamined during the next three inspection periods listed in the inspection schedules. lf the re-examinations reveal that the flaw indications remain essentially unchanged for three successive inspections, then the component examination schedule may revert to the original schedule.

Components requiring successive examinations shall be scheduled for examination in Appendix H.

B. Successive Examinations - Class 2 Equivalent Components Components with flaw indications evaluated in accordance with IWC-3122.3 or

!WC-3132.3 and NPG-SPP-22.300 that qualify for continued service shall be reexamined during the next inspection period listed in the inspection schedule.

lf the reexamination reveals that the flaw indications remain essentially unchanged, the component examination schedule may revert to the original schedule. Components requiring successive examinations shall be scheduled for examination in Appendix H.

C. Successive Examinations for Class 3 Equivalent Components Components with flaw indications or relevant conditions evaluated in accordance with IWD-3000 and NPG-SPP-22.300 that qualify for continued service shall be re-examined during the next inspection period listed in the inspection schedule. !f the re-examination reveals that the flaws remain essentially unchanged, the component examination schedule may revert to the original schedule. Components requiring successive examinations shall be scheduled for examination in Appendix H.

D. Successive Examinations for Class 1,2 and 3 Component Supports (lWF)

When a component support is accepted for continued service in accordance with !WF-3112.2 or IWF-3122.2the component support shall be re-examined during the next inspection period listed in the inspection schedule. Component supports requiring successive examination shall be scheduled for examination in Appendix H.

When these examinations do not require additional corrective measures, the inspection schedule may revert to the original schedule.

E. Successive Examinations for Rl-lSI Components (R-A)

As an alternative to the successive inspection requirements of IWB-2420, IWC-2420, or IWD-2420, the following requirements shall be met.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI IS!/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paoe 43 of 174 7.5 Corrective Action Program and Successive Examinations (continued)

1. The sequence of piping examinations established during the first inspection interval using this Case shall be repeated during each successive inspection interval to the extent practical. The examination sequence may be modified to optimize scaffolding, radiological, insulation removal, or other considerations, provided the percentage requirements of Tables IWB-2411-1 are met.

2. lf piping structural elements are accepted for continued service by analytical evaluation in accordance with IWB-3132.4 or IWB-3142.4, before, during, or after implementation of this Case, the areas containing flaws or relevant conditions shall be reexamined during the next three inspection periods.

3. lf the reexaminations required by 7.5E.2 reveal that the flaws or relevant conditions remain essentially unchanged for three successive inspection periods, the examination schedule shall revert to the original schedule of successive inspections.

F. Applicability of !WX-2430 to Successive Examinations The sample expansion and additional examination requirements of IWX 2430 apply when conducting successive inspections in accordance with IWX 2420(b).

The purpose of successive inspections is to ensure that assumptions made in the analyses which allow leaving a flaw in service remain valid. However, if new flaws are found while conducting the successive examinations, then those flaws must be appropriately dispositioned because (1) they may or may NOT be related to the originalflaw left in service, and (2) the provisions of IWX 2430 must be followed.

7.6 Configuration Changes When modifications are made to existing system, or systems are deleted from or added to scope of the scope of the ASME Section Xl lSl/NDE Program, the drawings shall be reviewed and revised by !S!/NDE Representative. ldentification of changes in system configurations shall be assessed. Piping, welds, and components shall be included in or deleted from the ASME Section Xl lSl/NDE Program, accordingly.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 44 of 174 7.6 7.7 7.8 Configuration Changes (continued) lf variations in configuration are discovered or modifications (including additions and deletions), replacements, or repairs are made during the service life of the unit, these changes shall be marked on field corrected copies of the appropriate drawings. These field corrected copies shall be used in the performance of examinations. The scan plan shall be revised in accordance with Section 7.10, as necessary to reflect these field corrected drawings (interim working drawings) and any preservice and/or inservice examinations performed due to these variations in configuration. lS!/NDE Representative shall be responsible for reviewing the proposed change, revising and issuing the drawing as necessary in accordance with NPG-SPP-09.1, Part A.

Calibration Standards Calibration blocks used for ultrasonic examination shall be in accordance with NPG-SPP-09.1, Part A and IEP-203.

Records and Reports Records and reports shall be prepared in accordance with NPG-SPP-O9.1, Part A.

ISI Summary Report for Class 1, 2,3 and MC Components An lSl summary report in accordance with NPG-SPP-O9.1 shal! be prepared and submitted to Site Licensing and other review organizations on a schedule that permits submittal to the NRC within 90 days after turbine generator synchronization following a refueling outage. The report shall be prepared in accordance with the requirements of ASME Code Case N-532-5. Any Augmented Examination results contained in Attachments 10 and 11 that specifically require submittal to the NRC in the lS! Summary Report wil! have to be added as a supplement to the Owner's Activity Report (OAR) since Code Case N-532-5 does NOT cover Augmented Examinations.

ISI Site Final Report An lSl Site Fina! Report of all examinations conducted in accordance with this plan shall be prepared. The lSl Site Final Report shall be submitted to Management Services for retention as a quality assurance record. The lSl Site Final Report should contain, but NOT be limited to, the following information:

A.

B.

1. A title page stating "ASME Section Xl Report Watts Bar Nuclear Plant, Unit, 2, Table of Contents lnservice Inspection Site Final and Refueling Outage."

3. Part I - lntroduction and Overall Summary

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 45 of 174 7.8 Records and Reports (continued)

4. Part ll - The ISI Summary Report with appendices as prepared in Section A.

Part lll - Summary of lSl Examinations ASME Class 1,2,3 and MC Components, Augmented Examinations (regulatory and self-imposed),

Preservice Examinations, Voluntary Examinations, Successive Examinations and Additional Samples Part lV - Scan Plans and Scan Plan Revision Logs (if applicable)

Part V - Summary of personnel information such as: Contract Approvals, lSl/NDE Personnel, Summary of Certifications, Signature Log, Reading List, NDE Equipment and Materials

8. Part VI - Calibration and Examination Data Sheets, and Notification of lndication Log and Reports All procedures and equipment shall be identified sufficiently to permit duplication of the examination at a later date.

The lSl Site Final Report shall be reviewed and submitted for retention as a quality assurance record in accordance with NPG-SPP 31.2, Records Management. Records and reports shall be in accordance with NPG-SPP-O9.1, Part A.

7.9 Requests for Relief (RFR) lf TVA has determined that an ASME Section Xl Code requirement:

A. is impractical [10 CFR 50.55a(g)(5xiii)],

B. may be achieved in an adventitiously alternative manner that would provide an acceptable level of quality or safety [10 CFR 50.55a(z)(1)],

C. would result in hardship or unusual difficulty without a compensating increase in the leve! of quality and safety.l10 CFR 50.55a(z)(2)],

or if essentially 100% examination coverage cannot be obtained in accordance with 7.1.1, TVAshall submitwritten requestsforrelief (RFR)tothe NRCwith information to support the need for relief and any proposed alternate examinations. The impractical Code requirements or relief alternative shall be identified as a part of the examination schedule tables (Appendices A-D) in this program and references to a particular RFR shall be included. Requests for relief shall be prepared in accordance with NPG-SPP-09. 1.

Requests for relief listings are included in Appendix J.

5.

C.

D.

WBN Unit 1 UNIT l ASME PROGRAM SEGTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 46 of 174 7.1A lnterval Schedule and Scan Plan For each inspection interval, a detailed implementation schedule shall be prepared for each inspection plan described in this procedure. The schedule shall include the following, in accordance with IWA-2420:

A. ldentification of the components selected for examination and test, including successive exams from prior periods; B. The Code requirements by examination category and item number for each component and the examination or test to be performed and the extent of the examination or test; ldentification of drawings showing items that require examination; List of examination procedures; Description of alternative examinations and identification of components to be examined using alternative methods; ldentification of calibration blocks used for ultrasonic examination of components.

NOTE The detailed implementation schedule for the first two inspection interv.als was developed and maintained electronically in the lSl Database.

A computerized data base system will be utilized for status and Section Xl credit of completed lS! examinations and those augmented examinations which have been integrated with the ASME Section Xl lSl/NDE Program. The data base is utilized to provide a scan plan. A scan plan is the primary scheduling document for each fue!

cycle, listing components requiring examination during a specific refueling outage. A scan plan may also be utilized to provide a listing of components to be examined for non-outage activities.

Prior to performing exams, the scan plan shall be approved by Programs Engineering Group. As part of the approva! process, the scan plan shall be reviewed by the lSl/NDE supervisor, NDE Level lll examiner, lSl Program Owner, Engineering Programs Manager, and independently verified. The independent verification shall verify al! required exams (lSl and Augmented) are contained in the scan plan. All reviews and verifications shall be documented by signature on the scan plan coversheet. The finalized scan plan shall be provided to Authorized lnspector for review and comment (lWA-21 10). The finalized scan plans shall be the QA record of Section Xl credit for examinations performed in accordance with this TRl.

C.

D.

E.

F.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Pase 47 of 174 7.10 lnterval Schedule and Scan Plan (continued)

During implementation phases (usually outage periods), it may become necessary to revise the scan plan. Scan plan revisions can be initiated by Engineering Programs Representative, lSO, or by other personnel involved with the implementation of the scan plan. AII revisions shall be independently verified by the ASME Section Xl Program owner and a qualified NDE Level lll examiner, as documented in the scan plan revision log. The finalized revised scan plan shall be provided to Authorized lnspector for review and comment (lWA-2110). Once the revisions are incorporated into the final scan plan, additional approval by the Programs Engineering Manager shall be documented on the revised scan plan cover sheet. Revisions shall be coordinated, as needed, with the appropriate plant planning and scheduling personnel for facilitating the use of supporting craft personnel. Revisions to the scan plan shall be controlled in the same manner as the original. However, interim working copies may be hand written to allow examinations to be performed before a formal revision is issued. The approving individuals shall initial and date interim revisions on the scan plan.

NOTE When inservice examinations are performed as a result of instructions other than this program (e.9., maintenance instructions, work plans, etc.), copies of the examination data sheet shall be submitted to Engineering Programs by the performing organization for assignment of a report number and incorporation into the scan plan.

7.11 Augmented Examinations Augmented examinations are performed in addition to ASME Section Xl code requirements. The augmented examinations may be required by the NRC or be self-imposed by TVA. Typical sources include generic letters, lE bulletins, technical specifications, vendor recommendations, and industry experience. NPG-SPP-09.1, Part A provides requirements for requesting augmented examinations. Appendix K provides a description and schedule for augmented examinations currently integrated with the lSl Program.

When examination of components fall into the scheduled examination requirements of lS! and also satisfy augmented requirements, then credit for both requirements may be taken by one examination; (i.e., duplicate examinations are not required).

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 48 of 174 7.12 RISK TNFORMED INSERVTCE TNSPECTTON (Rr-!Sr) 7.12.1 lntroduction The objective of the Rl-lSI program is to provide an alternative method for selecting and categorizing piping and components into High Safety Significant (HSS) and Low Safety Significant (LSS) groups for the purpose of developing a Rl-lSl program as alternative to the ASME Section XI requirements for Examination Categories B-F, B-J, C-A, C-8, C-D, C-F-1, and C-F-2.

The current Rl-lSl program follows the alternative classification and examination requirements guidance in Code Case N-716-1.

7.12.2 Purpose The Rl-lSl program outlines an acceptable alternative approach to the existing Section Xl requirements for the scope and frequency of piping examination.

7.12.3 Scope Code Case N-716-1 provides alternative requirements to IWB 2420, IWB-2430, Table IWB-2500-1 Examination Categories B-F and B-J, IWC-2420,1WC-2430, and Table IWC-2500-1 (excluding Examination Categories C-C and C-H), for lSl of Class 1 piping welds or Class 2 components, IWB-2200 and IWC-2200 for preservice inspection of Class 1 piping welds or Class 2 components, or as additional requirements for Class 3 or Non-Class components.

7.12.4 Frequency During the Third 10-Year lSl lntervalWBN Unit 1 will implement 100% of the inspection locations selected for examination per Code Case N-716-1.

Examinations shal! be performed such that the period percentage requirements of ASME Section Xl are met. All Category C-A and C-B welds are considered LSS and do not require examination except for Steam Generator welds. ln lieu of the percentage requirements of Table IWC-2411-1 the Steam Generator exams may be performed in any one period in accordance with IWC-2411(a).

The inspection periods and inspection interval are defined in Section 1.4. The piping segments and inspection strategy (i.e., frequency, number of examinations, and examination methods) are deflned in Table E.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 49 of 174 7.12.5 R!-lSl Periodic Updates As a minimum, updates to 1-TRl-0-10.3, Rl-lSI Program, shall be performed at least on an inspection period basis that coincide with the inspection program requirements contained in Section X!, IWA-2411. The third inspection period reevaluation will serve as the subsequent inspection interval reevaluation The performance of each inspection period reevaluation may be accelerated or delayed by as much as one year. Each reevaluation shall consider the cumulative effects of previous reevaluations. The reevaluation shall determine if any changes to the examination selections need to be made, by evaluation of the following:

A. plant design changes (e.9., physical: new piping or equipment installation; programmatic: power uprating/18 to 24 month fuel cycle; and procedural:

operating procedure changes),

B. changes in postulated conditions or assumptions (e.9., check valve seat leakage is greater than previously assumed)

C. examination results (e.9., discovery of leakage or flaws)

D. piping failures (e.9., plant-specific or industry occurrences of through-wall or through-weld leakage, failure due to a new degradation mechanism, or a non-postulated mechanism)

E. PRA updates that would increase the scope of CC N-716-1 paragraph (2)(a)(5)

(e.9., new initiating events, new system functions, more detailed model used, and initiating event and failure data changes), and F. the impact of '1 through 5 above on the change-in risk evaluation.

Expedited program updates should be performed to address significant PRA changes or the occurrence of significant plant events. Significant plant events may include such events as pipe ruptures, earthquakes, or severe operational transients.

7.12.6 Performance Monitoring The Program Owner will maintain an awareness of input changes. The WBN site control processes that provide input into the RI-lSl program have been enhanced to include the appropriate guidance. After each inspection period, the effects of the changes will be evaluated to determine if a change to the Program is required. A report will be prepared for reviedapproval of lSl/NDE Supervisor documenting the review.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 50 of 174 7.12.6 Performance Monitoring (continued)

The Rl-lSl program will be updated, if required, during the subsequent inspection period. The lSl Program Engineer, with possible assistance from industry RI-IS!

experts, will review proposed Rl-lsl program changes and provide program oversight. The following provides additional guidance supplementing the requirements stated in paragraph7.12.5for the an overview of the Rl-lsl program inputs.

Plant Design Feature Changes Design changes have the potential to change piping configuration and alter stress calculations which were used as input to the calculations performed in support of the RI-lSl program. New systems and branch piping will be evaluated for inclusion into the scope of the Rl-lsl program. Consequently, the Design Control program will be revised to recognize Rl-lSl and to ensure impact is appropriately evaluated during design preparation, review, and implementation. The existing design impact review process will also be used to ensure the impact of design changes on Rl-lSl has been appropriately considered prior to final approval. The calculations supporting the Rl-lSI program will be entered into TVA's calculation tracking program to ensure appropriate predecessors and inputs are identified and considered during design change preparation and review.

Plant PRA Changes Since the PRA forms the basis for the RI-ISI program, any changes to the PRA or risk significance determination will be evaluated for impact on the Rl-lSl program.

C. Plant Procedure Changes Changes to plant procedures that affect lSl, such as system operating parameters, test intervals, or the ability of plant operations to perform actions associated with accident mitigation shall be considered in any Rl-lSl program update. Additionally, changes in procedures that affect component inspection intervals, valve lineups, or operational modes of equipment shall also be assessed for their impact on changes in postulated failure mechanism initiation or Core Damage Frequency (CDF).

A.

B.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISIINDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 51 of 174 7.12.6 Performance Monitoring (continued)

D. Equipment Performance Changes Equipment performance changes shall be reviewed with system engineers and maintenance to ensure that changes in performance parameters (e.9., valve leakage, increased pump testing, and vibration problems) are considered in the Rl-lsl program update. Specific attention shall be paid to these type conditions if not previously assessed in the qualitative inputs to the component selections of the RI-ISI program. Adverse equipment performance will be evaluated for changes to the Rl-lSI inspection scope.

E. Examination Results When scheduled RI-lSl program NDE examinations, pressure tests and corresponding W-2 visual examinations for leakage have been completed, and unacceptable flaws, evidence of service related degradation, or indications of leakage have been identified, these conditions shall be evaluated in accordance with plant procedures as applicable to determine the adequacy of the scope of the inspection program and update the Rl-lSl program as applicable.

!ndividual Plant and lndustry Failure lnformation The Program Owner will consider applicable piping failures or degradations identified by the site's corrective action program. lndustry awareness will be maintained through the sites Operating Experience program, NRC Generic Letters and Bulletins, site participation in Pressurized Water Reactor Owners Group initiatives, and participation in the ASME Section Xl Code committee activities.

Program Review The Manager of Engineering Programg will provide the oversight role for the Rl-lsl program. Other affected departments will be invited to the inspection period reviews. As with past reviews, personnel possessing expertise in Rl-lSl evaluation and lSl inspection/evaluation, will be present during the presentation, and the review of the above items when the inspection period reviews occur.

F.

G.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 52 of 174 Data Package: Page _

8.0 PERFORMANCE Date t1] OBTAIN Unit Supervisor (US), or designee, approval to perform this lnstruction on the Surveillance Task Sheet.

l2l RECORD start date and time on Surveillance Task Sheet.

13] INDICATE the current lSl lnterval and Period and whether the current Refueling Outage is the first, second, or third of the Period.

A. lsl lnterval 3, Period 1 tr lsl lnterval 3, Period 2 n lsl lnterval 3, Period 3 tr B. First RFO of Period tr Second RFO of Period El Third RFO of Period n C. Fuel Cycle/RFO Number:

I4l lF Step 8.0[3]8 indicates that this is the first or third Refueling Outage of the current lSl Period, THEN ATTACH the FinalApproved lSl Scan Plan with record numbers of all examinations completed during this refueling outage to the Data Package, and VERIFY that all planned/scheduled examinations were completed, as required.

t5] lF Step 8.0[3]8 indicates that this is the second Refueling Outage of the current lSl Period, THEN PERFORM the following:

A. ATTACH the Final Approved lSl Scan Plan with record numbers of all examinations completed during this refueling outage to the Data Package.

B. ATTACH the Final Approved ISI Scan Plan with record numbers of all examinations completed during the previous refueling outage to the Data Package.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1 -TRl-0-1 0.3 Rev. 0001 Paqe 53 of 174 Data Package: Page 8.0 PERFORMAN CE (contin ued)

VERIFY that examinations documented on the attached Final Approved lsl Scan Plans satisfy the required number of examinations in each Exam Category as shown in Appendix A.

VERIFY that examinations documented on the attached Final Approved lsl Scan Plans satisfy the required number of examinations in each Exam Category as shown in Appendix B.

VERIFY that examinations documented on the attached Final Approved ISI Scan Plans satisfy the required number of examinations in each Exam Category as shown in Appendix C.

VERIFY that examinations documented on the attached Final Approved lsl Scan Plans satisfy the required number of examinations in each Exam Category as shown in Appendix D.

VERIFY that examinations documented on the attached Final Approved lsl Scan Plans satisfy the required number of examinations in each Exam Category as shown in Appendix E.

lF Step 8.0[3] indicates that this is any Refueling Outage other than the SECOND Refueling Outage of the THIRD lSl Period of the current lSl lnterval, THEN, ATTACH the Final Approved lsl Scan PIan with record numbers of all examinations completed during this refueling outage to the Data Package, and VERIFY that all planned/scheduled examinations as identified on Appendix F were completed, as required.

Date C.

D.

E.

F.

G.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 54 of 174 Data Package: Page 8.0 PERFORMANCE (continued)

17) lF Step 8.0[3]8 indicates that this is the SECOND Refueling Outage of the THIRD lSl Period of the current lS! lnterval, THEN PERFORM the following:

A. ATTACH the Final Approved lSl Scan Plan with record numbers of all examinations completed during any refueling outage of the current lSl lnterva! that documents completion of the required examination of valves shown on Appendix F to the Data Package.

B. VERIFY that examinations documented on the attached Final Approved lSl Scan Plan satisfy the required number of examinations in each Exam Category as shown in Appendix F.

t8l VERIFY that all successive examinations as shown on Appendix H that were required to be performed during the Fuel Cycle/Refueling Outage number recorded in Step 8.0[3]C have been completed, and ATTACH the Final Approved lSl Scan Plan of successive examinations completed during this refueling outage to the Data Package.

19] VERIFY that all augmented examinations as shown on Appendix K required to be performed during the Fuel Cycle/Refueling Outage number recorded in Step 8.0[3]C have been completed, and ATTACH the FinalApproved lS! Scan Plan with record numbers of all of augmented examinations completed during this refueling outage to the Data Package.

t10l VERIFY that all examinations that did not achieve essentially 100% coverage during the Fuel Cycle/Refueling Outage number recorded in Step 8.0[3]C have been documented in accordance with NPG-SPP-09.1, and ATTACH documentation of limited examinations completed during this refueling outage to the Data Package.

t11l RECORD completion date and time on the Surveillance Task Sheet.

Date

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 55 of 174 Data Package: Page 9.0 RECORDS 9.1 QA Records Date The Data Package is a QA record, is handled in accordance with the Document Control and Records Management Program, and contains the following:

A. Completed parts of Section 8.0.

B. Surveillance Task Sheet.

C. Approved lSl Scan Plans.

D. Other sheets added during the performance.

9.2 Non-QA Records None

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 56 of 174 Appendix A (Page 1 ot 221 Examination Summary Table for ASME Class 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B.A Pressure Retaining Welds in Reactor Vessel B-A 81.10 RV Shell Welds 81.11 RV Shell Welds Circumferential UT 4

100Yo 4

Deferral Permissible 0

0 4

Note 7 rsr-0427-c B-A 81.20 RV Head Welds 81.21 RV Head Welds Circumferential UT 2 (closure head and lower head) 1 00% of accessible length 2

Deferral Permissible 0

0 2

Note 7 cHM-2549-c rst-0427-C 81.22 RV Head Welds Meridional UT 6

Meridional welds 100% of accessible lenght 6

Deferral Permissible 0

0 6

Note 7 tsr-0427-c B-A 81.30 RV Shell-to-Flange Weld UT 1

1AA%

1 Partial Deferral 0

0 1

Note 7 tsl-0427-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 57 of 174 Appendix A (Page 2 ot 221 Examination Summary Table for ASME Class 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B-A 81.40 RV Head-to-Flange Weld MT CC N-747 1 (divided into 2 halves) 1A00 2

Deferral Permissible 0

0 2

Note 7 cHM-2549-C B-A 81.50 RV Beltline Repair Areas

>1Ao/o Wall B.B Pressure Retaining Welds in Vessels Other than Reactor Vessels B-B 823A Pressurizer Shell-to-Head Welds B.2.11 Pressu rizer Circ. Shellto-Head Welds UT 2

1jAa/o 2

Deferal Not Permissible 0

1 1

cHM-257A-C

WBN Unit 1 UNIT l ASME SECTION X! ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 58 of 174 Appendix A (Page 3 of 221 Examination Summary Table for ASME Class I Components

WBN Unit 1 UNIT l ASME SECTION X! ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 59 of 174 Appendix A (Page 4 ot 221 Examination Summary Table for ASME Glass 1 Components

WBN I UNIT 1 ASME SECTION XI ISI/NDE I1.TRI.O.1O.3 Unit 1 I

PROGRAM THIRD INTERVAL lRev. 0001 Paqe 60 of 174 Appendix A (Page 5 ot 221 Examination Summary Table for ASME Class 1 Components

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 61 of 174 Appendix A (Page 6 ot 221 Examination Summary Table for ASME Class 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PER!OD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B-D 83.1 00 RV Nozzle lnside Radius Section VT-1 per cc N-648-1 8

100o/o 8

Deferral Permissible 0

0 8

Note 7 rsr-0427-c B-D 83.1 1 0 Pressu rizer Nozzle-to-Vessel Welds UT 6

1 00%

6 Deferral Not Permissible 0

5 1

cHM-2570-C B-D 83.1 20 Pressurizer Nozzle lnside Radius Section

[50. 55a(b)(2 Xxxi )(A] )

UT or VT (enhanced) 6 10Ao/o 6

Deferral Not Permissible 0

5 1

cHM-2570-C B-D 83.1 40 SG Primary Side Nozzle lnside Radius Section

[50.55a(b)(2XxxiXA])

UT or VT (enhanced)

I 1A0%

I Deferral Not Permissible 4

0 4

cHM-2660-C

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 62 of 174 Appendix A (Page 7 ot 221 Examination Summary Table for ASME Class 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO-

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED !N THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B.F Pressure Retaining Dissimilar Metal Welds -- subsumed by Risk-lnformed Program B-G.1 Pressure Retaining Boltitrg, Greater Than 2" in Diameter B-G-1 86.1 0 RV Closure Head Nuts VT-1 1 set of 54 100%

1 Deferral Permissible 0

0 1

rst-0427-c B.G-1 86.20 RV Closure Studs UT6 1 set of 54 100%

1 Defenal Permissible 0

0 1

rsr-0427-c B-G-1 86.40 RV Threads in Flange UT 1 set of 54 1A0o/o 1

Deferral Permissible 0

0 1

tst-0427-c

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paqe 63 of 174 Appendix A (Page 8 ot 221 Examination Summary Table for ASME Class 1 Components DESCRIPTION RV Closure Washers (no Bushings)

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 64 of 174 Appendix A (Page 9 ot 221 Examination Summary Table for ASME CIass 1 Components DESCRIPTION

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paqe 65 of 174 Appendix A (Page 10 ot22l Examination Summary Table for ASME Glass 1 Components

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 66 of 174 Appendix A (Page 11 ot22l Examination Summary Table for ASME CIass 1 Gomponents EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B.G.2 Pressure Retaining Bolting,2" and Less in Diameter B-G-2 F7.20 Pressu rizer Bolts, Studs, and Nuts VT-1 1 Manway I

'l 6 Bolts

}Yo 1 Manway 16 Bolts I

Deferral Not Permissible when dis-assembled or removed when dis-assembled or removed when dis-assembled or removed cHM-2570-C B.G-2 87.30 SG Bolts, Studs, and Nuts VT-1 4SGt2 Manways /

16 bolts ea.

O%SG selected by B-B 1SG/2 Manways /

16 bolts ea.

Deferral Not Permissible when dis-assembled or removed when dis-assembled or removed when dis-assembled or removed cHM-2660-C B.G-2 87.50 Piping Bolts, Studs, and Nuts

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 67 of 174 Appendix A (Page 12 ot 221 Examination Summary Table for ASME Class 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER 87.50 CVCS VT.1 4

connections 00h 4

Deferral Not Permissible when dis-assembled or removed when dis-assembled or removed when dis-assembled or removed tst-0050-c 87.50 RCS VT-1 5

connections o%

5 Deferral Not Permissible when dis-assembled or removed when dis-assembled or removed when dis-assembled or removed lst-0365-c 87.50 SIS VT-1 4

connections 0%

4 Deferral Not Permissible when dis-assembled or removed when dis-assembled or removed when dis-assembled or removed cHM-2758-C B-G.2 87.60 Pumps Bolts, Studs, and Nuts VT-1 4 Pumps I 2 sets / 1 set 12 bolts and 1 set 8 bolts Pump(s) selected for exam under B-L-2 1 set 12 bolts and 1set8 bolts Deferral Not Permissible 2

when dis-assembled or removed when dis-assembled or removed rst-0447-c B-G.2 E7.74 Valves Bolts, Studs, and Nuts See Note 2 at end of Appendix A

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 68 of 174 Appendix A (Page 13 ot 221 Examination Summary Table for ASME Class 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B-7.70 RCS VT-1 3 Valves (1 group)

Valve(s) selected for exam under 8.M.2 At least 1 valve per group (1)

Deferral Not Permissible when dis-assembled or removed when dis-assembled or removed when dis-assembled or removed rsr-0365-c B7.74 RHRS VT-1 8 Valves (4 groups)

Valve(s) selected for exam under B-M-2 At least 1 valve per group (4)

Deferral Not Permissible when dis-assembled or removed when dis-assembled or removed when dis-assembled or removed cHM-2636-C 87.74 SIS VT.1 18 Valves (3 groups)

Valve(s) selected for exam under B.M-2 At least 1 valve per group (3)

Deferral Not Permissible when dis-assembled or removed when dis-assembled or removed when dis-assembled or removed cHM-2758-C B.J Pressure Retaining Welds in Piping -- subsumed by Risk-lnformed Program B.K Welded Attachments for Vessels, Piping, Pumps, and Valves

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 69 of 174 Appendix A (Page 14ot22l Examination Summary Table for ASME Glass 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B.K 810.10 Pressure Vessels Welded Attachments Surface 810.10 Pressu rizer Support Skirt MT 1

See Note 3 at end of Appendix A 1

Deferral Not Permissible whenever component support deformation is identified 0

0 1

cHM-257A-C

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 70 of 174 Appendix A (Page 15of22l Examination Summary Table for ASME Class 1 Components

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 71 of 174 Appendix A (Page 16 ot 221 Examination Summary Table for ASME CIass 1 Components

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 72 of 174 Appendix A (Page 17 ot 221 Examination Summary Table for ASME Class 1 Components DESCRIPTION

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 73 of 174 Appendix A (Page 18 ot 221 Examination Summary Table for ASME Class 1 Gomponents EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B-L.2 Pump Casings B.L-2 il2.24 Reactor Coolant Pump Casing Internal Surfaces VT-3 4

1 Pump in each group 1

When Dis-assembled When disassembled When disassembled When disassembled lsl-0048-c 8.M.2 Valve Bodies B-M.2 812.50 Valves (greater than 4 NPS)

Body lnternal Surfaces Visual See Note 2 at end of Appendix A.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paoe 74 of 174 Appendix A (Page 19ot22l Examination Summary Table for ASME CIass 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PER!OD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER 812.50 RCS VT-3 3 (One Group)

N/A 1 valve per group (1)

Only when disassembled Only when disassembled Only when disassembled Only when disassembled rsr-0365-c H-12.50 RHRS VT-3 8 (Four Groups)

N/A 1 valve per group (4)

Only when disassembled Only when disassembled Only when disassembled Only when disassembled cHM-2636-C B-12.50 SIS VT-3 18 (Three Groups)

NIA 1 valve per group (3)

Only when disassembled Only when disassembled Only when disassembled Only when disassembled cHM-2758-C B-N.1 lnterior of Reactor Vessel B.N-1 81 3.1 0 RV lnterior Accessible Areas VT-3 1

100Yo At 3 year intervals 1 (each period)

Deferral Not Permissible 1

1 1

ISt-0427-C B.N.2 Welded Core Support Structure and lnterior Attachments to Reactor Vessels

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI IS!/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 75 of 174 Appendix A (Page 2O ot 221 Examination Summary Table for ASME Class 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B.N-2 813.60 RV Interior Attachments Beyond Beltline Region VT-3 1(6 locations)

Accessible Welds 1

Deferral Permissible 0

0 1

lsr-0427-c B.N.3 Removable Core Support Structures B-N-3 813.70 RV Core Support Structure Accessible Surfaces VT.3 1

Accessible Surfaces 1

Deferral Permissible 0

0 1

tst-0427-c B-O Pressure Retaining Welds in Control Rod Housing B-O B-14.20 RV Welds in CRD Housings UT or PT 78 CRD Housings /

20 Peripheral Housings 10o/o of Peripheral Housings 2

Deferral Permissible 0

0 2

cHM-2684-C

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 76 of 174 Appendix A (Page 21 ot 221 Examination Summary Table for ASME Class 1 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINE D DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER B-P System Leakage Testing (See Notes & 5))

Note 1: For Examination Category B-K, Piping, Pump, and Valve welded Attachments the percentage examinod during an inspection interval is 10% of the welded attachments associated with the component supports selected for examination under IWF-2510 on non-exempt piping (per system basis). There are 2 piping supports with welded attachmenb and both were selected. 1O% of 2 would require 1 welded attachment to be selected or 50% of total. 100% of the required areas of each selected welded attachment are requirsd to be examined.

Note 2: Reierence Appendix F for valve groupings and the list of valves subject b Examination Category'B-G-2 or B-M-2 as applicable.

Note 3: For Examination Category B-K, Pressure Vessels Welded Attachments only one welded attachment of one of multiple vesssls is required to be examined. For single vessels, only one welded attachment shall be selected for examination. 1 of 5 wsldsd attachments is scheduled for the pressurizer or 20% of total. 100% of tho required areas of each slected welded attachment are required to be examined.

Note 4: Examination Category B-P Period and lnterval Systom Leakage Testing is implemented psr the System Pressure Test Program, Tl-100.008.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paoe 77 of 174 Appendix A (Page 22 ot 221 Examination Summary Table for ASlUlE Class 1 Components Note 5: Additional examinations associated with Category B-P defined in ASME Section Xl Code Case N-722-1, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 600/84182" and required by 10 CFR 50.55a(g)(6)(ii)(E) is implement per "Appendix K, Augmented Examinations', ofthis procedure.

Note 6: When bolts or studs are removed for examination, surface examination meeting the acceptance standards of IWB-3515 may be substituted for volumetric examination (Ref. Note 7 Category B-G-1).

Note 7: Request for Altemative, 13-lsl41, grants and extension of the '10 year Reactor Pressure Vessel examination requirements to 20 years. The welds included in this extension are B-A [81.11, B'l-2'l,81.22,81.30, 81.40], B-D [83.90, 83.'1001. The 20 year examinations will be required atthe end ofthe Third 10 Year lnterval.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISUNDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 78 of 174 Appendix B (Page 1 of 19)

Examination Summary Table for ASME Class 2 Components NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL Pressure Retaining Welds in Pressure Vessels Volumetric orPTifS 0.2 inches thick Pressure Retaining Shell Circumferential Welds

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 79 of 174 Appendix B (Page 2 of 19)

Examination Summary Table for ASME Class 2 Components

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 80 of 174 Appendix B (Page 3 of 19)

Examination Summary Table for ASME Class 2 Components DESCRIPTION

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 81 of 174 Appendix B (Page 4 of 19)

Examination Summary Table for ASME Class 2 Components

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TR!-0-1 0.3 Rev. 0001 Paqe 82 of 174 Appendix B (Page 5 of 19)

Examination Summary Table for ASME Class 2 Components

WBN Unit 1 UNIT l ASME PROGRAM SEGTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 83 of 174 Appendix B (Page 6 of 19)

Examination Summary Table for ASME CIass 2 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER C-B c2.2A Nozzles without reinforcing plate in vessels greater than 112" nom. thick C-B c2.21 Nozzles-to-shell Welds > NPS 4 Surface and Volumetric c2.21 Steam Generator MT&UT 8 (2 per SG)

All nozzles at terminal ends of piping runs in 1 vessel 2

(One FW and one AFW)

Each lnspection lnterval 1

1 0

CHM-2660.C

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 84 of 174 Appendix B (Page 7 of 19)

Examination Summary Table for ASME Glass 2 Components

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 85 of 174 Appendix B (Page 8 of 19)

Examination Summary Table for ASME Class 2 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER c-B c2.30 Nozzles with Reinforcing Plate in Vessels > 112" nom.

thickness C-B c2.31 Reinforcing Plate Welds to Nozzle and Vessel Surface C-B c2.32 Nozzle-to-Shell (or Head) Weld when inside of Vessel is Accessible Volumetric

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 86 of 174 Appendix B (Page 9 of 19)

Examination Summary Table for ASME Glass 2 Components DESCRIPTION Pressure Vessels Welded Attachments

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 87 of 174 Appendix B (Page 10 of 19)

Examination Summary Table for ASME CIass 2 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER c3.1 0 Residual Heat Removal Heat Exchanger PT 4 (2 lAs on each RHRHX)

See Note 2 at the end of Appendix B.

llAon one RHRHX Each lnspection lnterval and whenever component support deformation is identified 0

1 0

CHM.2662-C c3.10 Containment Spray Heat Exchanger PT 2(1 lAon each CSHX)

See Note 2 at the end of Appendix B.

llAon one CSHX Each lnspection lnterval whenever component support deformation is identified 0

0 1

lsl-0371-c c3.10 Seal Water Heat Exchanger PT 1

See Note 2 at the end of Appendix B.

llAon one SWHX Each lnspection lnterval whenever component support deformation is identified 0

0 1

rsr-0484-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISIINDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paoe 88 of 174 Appendix B (Page 11 of19)

Examination Summary Table for ASME Class 2 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

% TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE

!NTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER c3.10 Seal Water Filter PT 1

See Note 2 at the end of Appendix B.

llAon ONE SWF Each lnspection lnterval and whenever component support deformation is identified 0

1 0

rsr-0487-c c3.10 Seal Water lnjection Filter PT 2 (1 lAs on each swlF)

See Note 2 at the end of Appendix B.

llAon ONC SWIF Each lnspection lnterval and whenever component support deformation is identified 1

0 0

rsr-0486-c c3.10 Boron Injection Tank PT 4 (1 BtT t4 lAs)

See Note 2 at the end of Appendix B.

1 lA on the BIT Each lnspection lnterval and whenever component support deformation is identified 0

1 0

rst-0053-c C.C c3.20 Piping Weld Attachments Surface

WBN Unit 1 UNIT l ASME PROGRAM SEGTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0,3 Rev. 0001 Paqe 89 of 174 Appendix B (Page 12 of 19)

Examination Summary Table for ASME Class 2 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER c3.20 AFWS MT 8

See Note 1 at end of Appendix B (10Yo\\

1 Each lnspection lnterval and whenever component support deformation is identified 1

0 0

tst-0062-c c3.20 CSS PT B

See Note 1 at end of Appendix B (10%)

0 Each lnspection lnterval and whenever component support deformation is identified 0

0 0

tst-0423-c c3.20 CVCS PT 23 See Note 1 at end of Appendix B (10%)

1 Each lnspection lnterval and whenever component support deformation is identified 1

0 0

tst-0424-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 90 of 174 Appendix B (Page 13 of 19)

Examination Summary Table for ASME Class 2 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER c3.2A MSS MT 8

See Note 1 at end of Appendix B (10%)

0 Each lnspection lnterval and whenever component support deformation is identified 0

0 0

lst-001 1-c c3.20 RHRS PT 6

See Note 1 at end of Appendix B (10%)

0 Each lnspection lnterval and whenever component support deformation is identified 0

0 0

rsr-0020-c rsr-01a7-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 91 of 174 Appendix B (Page 14 of 19)

Examination Summary Table for ASME Class 2 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER c3.20 SIS PT 30 See Note 1 at end of Appendix B (10o/o) 1 Each lnspection lnterval and whenever component support deformation is identified 1

0 0

rsr-0021-c rsr-0440-c C.C c3.30 Pump Welded Attachments Surface c3.30 Centrifugal Charging Pump (ccP)

PT 2 (4 welds on each ccP)

See Note 1 at end of Appendix B (10%)

0 Each lnspection lnterval and whenever component support deformation is identified 0

0 0

rsr-01 18-c

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 92 of 174 Appendix B (Page 15 of 19)

Examination Summary Table for ASME CIass 2 Components

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paoe 93 of 174 Appendix B (Page 16 of 19)

Examination Summary Table for ASME GIass 2 Components DESCRIPTION Pressure Vessel Bolts and Studs

>2" diameter

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 94 of 174 Appendix B (Page 17 of 19)

Examination Summary Table for ASME Class 2 Components DESCRIPTION

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 95 of 174 Appendix B (Page 18 of 19)

Examination Summary Table for ASME Class 2 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER c-F-1 Pressure Retaining Welds in Austenitic Stainless Stee! or High Alloy Piping -- subsumed by Risk-lnformed Program c-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Pipihg --

subsumed by Risk-lnformed Program C-H System Leakage Testing (See Note 3))

Note l: For Examination Category C-C, Piping, Pump, and Valve Welded Attachments the percentage examined during an inspection interval is based on 10% of the welded attachmenE associated with the component supports selected for examination under IWF-2510. Only 13 Class 2 piping supports were selected with welded attachments. As such, 2 piping welded attachments require examination. WBN-1 has scheduled 3 piping wsldod attachmentrs. 3 of 83 welded attachments is 3.6%. Only 2 Class 2 pump supports were selected with welded atlachments. As such, one pump's welded attachmenb requires examination. WBN-1 has scheduled I pump's (RHR-1A) welded attiachmenE. 1of 4 is25olo. 100% of the required areas of each selected welded attachment are required to be examined.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 96 of 174 Appendlx B (Page 19 of 19)

Examinatlon Summary Table for ASirE Cla$ 2 Components Note 2: For Examination Category C-C, Pressure Vessel lntegral Attachments only one integral attachment of only one of the multiple vessels of similar design, function, and service is required to be examined. 6 of 14 is 42.8%. 100% ofthe required areas of each selected welded attachment are required to be examined.

Note 3: Examination Category GH Period and lnterval System Leakage Testing is implementsd per the System Pressure Test Prcgram, Tl-100.008.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paoe 97 of 174 Appendix G (Page 1 of 10)

Examination Summary Table for ASME Glass 3 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER D.A Integral Attachments for Class 3 Vessels, Pipitrg, Pumps, and Valves D.A D1.10 Pressure Vessels Welded Attachments Visual D1.10 Containment Spray Heat Exchanger (csHX)

VT-1 2(1 lAon each CSHX)

See Note 2 at the end of Appendix C.

All lAs on 1 CSHX Each

!nspection lnterval and whenever component support deformation is identified 0

0 All lAs on 1 CSHX rsr-0371-c D1.10 Nonregenerative Letdown Heat Exchanger (NRLHX)

VT-1 1

See Note 2 at the end of Appendix c.

All lAs on the NRLHX Each lnspection lnterval and whenever component support deformation is identified 0

All lAs on the NRLHX 0

tst-0497-c

WBN Unit 1 UNIT l ASME PROGRAM SEGTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 98 of 174 Appendix G (Page 2 of 10)

Examination Summary Table for ASME Class 3 Gomponents EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER D1.10 Component Cooling Surge Tank (CCST)

VT-1 1

See Note 2 at the end of Appendix C.

All lAs on the CCST Each lnspection lnterval and whenever component support deformation is identified 0

All lAs on the CCST 0

rst-0496-c D1.10 Essential Raw Cooling Water System Strainer (ERCWS)

VT-1 4 (two ERCWS with 2 lAs each)

See Note 2 at the end of Appendix C.

All lAs on one ERCWS Each Inspection lnterval and whenever component support deformation is identified All IAs on one ERCWS 0

0 rsr-0489-c D1.10 Component Cooling Heat Exchanger (ccHX)

VT-1 3

See Note 2 at the end of Appendix C.

All lAs on 1 CCHX Each lnspection lnterval and whenever component support deformation is identified 0

All lAs on CCHX 1

0 lsr-0494-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 99 of 174 Appendix C (Page 3 of 10)

Examination Summary Table for ASME CIass 3 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER D1.10 Fuel Pool Cooling and Cleaning System Spent Fuel Pit Heat Exchanger (FPCCHX)

VT-1 2 (1 lA per FPCCHX)

See Note 2 at the end of Appendix C.

All lAs on 1

FPCCHX Each lnspection lnterval and whenever component support deformation is identified 0

0 All IAs on 1

FPCCHX rsr-0372-c D1.10 RHR Heat Exchanger (RHRSHX)

VT-1 2 (1 lA per RHRSHX)

See Note 2 at the end of Appendix C.

All lAs on 1

RHRSHX Each Inspection lnterval and whenever component support deformation is identified 0

0 Al! lAs on 1

RHRSHX CHM-2662-C D1.10 Seal Water Heat Exchanger (swHX)

VT.1 1

See Note 2 at the end of Appendix C.

All lAs on the SWHX Each lnspection lnterval and whenever component support deformation is identified All lAs on the SWHX 0

0 rst-0484-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paqe 100 of 174 Appendix C (Page 4 of 10)

Examination Summary Table for ASME Class 3 Gomponents EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER D1.10 High Pressure Fire Protection Strainer (HPFPS)

VT-1 2 (1 IA per HPFPS)

See Note 2 at the end of Appendix C.

All lAs on 1 HPFPS Each lnspection lnterval and whenever component support deformation is identified All lAs on 1 HPFPS 0

0 rsl-05a2-c D-A D1.24 Piping Welded Attachments Visual D1.24 AFWS VT-1 2

See Note 1 at end of Appendix C (10%)

1 Each lnspection lnterval and whenever component support deformation is identified 0

0 1

ISI-0111-C

WBN Unit 1 UNIT l ASME PROGRA]UI SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 101 of 174 Appendix C (Page 5 of 10)

Examination Summary Table for ASME GIass 3 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED !N THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER D1.20 CCS VT.1 53 See Note 1 at end of Appendix C (10%)

6 Each lnspection lnterval and whenever component support deformation is identified 2

2 2

tst-0252-c D1.20 ERCWS VT-1 158 See Note 1 at end of Appendix C (10%)

16 Each lnspection lnterval and whenever component support deformation is identified 5

5 6

rs!-0112-c D1.20 FPCS VT-1 11 See Note 1 at end of Appendix C (10%)

2 Each lnspection lnterval and whenever component support deformation is identified 1

1 0

rsr-01 10-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 102 of 174 Appendix C (Page 6 of 10)

Examination Summary Table for ASME Glass 3 Components EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED !N THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER D1.20 HPFPS VT-1 12 See Note 1 at end of Appendix C (10%)

2 Each Inspection lnterval and whenever component support deformation is identified 0

1 1

rsr-0500-c D-A D1.30 Pumps Welded Attachments Visual

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paoe 103 of 174 Appendix G (Page 7 of 10)

Examination Summary Table for ASME CIass 3 Components DESCRIPTION

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 104 of 174 Appendix C (Page 8 of 10)

Examination Summary Table for ASME Class 3 Components DESCRIPTION

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 105 of 174 Appendix C (Page 9 of 10)

Examination Summary Table for ASME Class 3 Components

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TR!-0-1 0.3 Rev. 0001 Paqe 106 of 174 Appendlx C (Page l0 of l0)

Examinatlon Summary Table for ASME Class 3 Components Note 'l: For Examination Category D-A, Piping, Pump and Valve lntegral Attachments the percentage examined during an inspection interval is based on 10% of the integral attachments on non-exempt piping (per system basis) or whenever component support degradation is identified. 27 of 236 were selected or 1 1.4% (the higher number due to system proration and rounding.) 100% of the required areas of each selected weldod attachment are required to be examined.

Note 2: for Examination Category D-A, Pressure Vessel lntegral Attachmentrs the attachments of only one of the multiple vessels of similar design, function, and seMce shall be required to be examined. 9of 18 were selected or50% ofthe total.

10070 of the required areas of each selected welded attachment are required to be examined.

Note 3: Examination Category DB, Period and lnterval System Leakage Testing, is implemented per the System Pressure Test Program, Tl-100.008.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 107 of 174 Appendix D (Page 1 of 201 Examination Summary Table for ASME CIass 1,2, and 3 Gomponent Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F.A Supports F-A F1.10X (See Note 1)

Class 1 Piping Supports Visual Class 1 CVC Piping Supports F1.10A CVCS VT-3 19 25o/o 5

Each lnspection lnterual 1

2 2

!sr-0026-c rsr-0063-c F1.1 0B CVCS VT.3 19 25%

5 Each lnspection lnterval 2

1 2

!sr-0026-c tsr-0063-c F1.1 0C CVCS VT-3 2

25o/o 1

Each lnspection lnterval 0

0 1

rsr-0026-c tst-0063-c F1.1 0D CVCS VT-3 20 25o/o 5

Each lnspection lnterval 2

2 1

tst-0026-c rsr-0063-c Class 1 RCS Piping Supports

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 108 of 174 Appendix D (Page 2 ot 201 Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.10A RCS VT-3 13 25o/o 3

Each lnspection lnterval 1

1 1

rsr-0364-c F1.1 0B RCS w-3 6

25o/o 2

Each lnspection lnterval 1

1 0

lst-0364-c Fl.1 0c RCS VT-3 10 254/o 3

Each lnspection lnterval 1

1 1

rsr-0364-c F1.10D RCS VT-3 13 254/,

3 Each lnspection lnterval 0

1 2

rsr-0364-c Class 1 RCS Main Piping Supports mtlNiiffi

iIili-ii\\Gttttffi S,\\rii*iisIt*l*:i:i$E*St{9I.1{,!Si*s.riSiiilill}iiiiri$ii ffi siitiin:$51ffi [t$IIft *IHffi li$s'iii$.titl tttlntt:[tWri::Ilg:StlttssSI::

i*+*lillitith'iN6$tiiiiSi+:Sii$siiirc$iiiiii.ii*S.rliiiiiiiigii ry F1.1 0B RCS Main VT.3 4

254/0 1

Each lnspection lnterval 1

0 0

tst-0124-c rst-0438-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paqe 109 of 174 Appendix D (Page 3 of 20)

Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.1 0C RCS Main VT.3 2

25o/o 1

Each lnspection lnterval 0

0 1

rst-0124-c rsr-0438-c Class 1 RHR Piping Supports F1.10A RHRS VT-3 4

25o/o 1

Each lnspection lnterual 1

0 0

rsl-0020-c F1.1 0B RHRS VT.3 6

254/o 2

Each lnspection lnterva!

0 0

2 rsr-0020-c F1.10C RHRS VT.3 3

25%

1 Each lnspection lnterval 0

1 0

rst-0020-c F1.1 0D RHRS VT.3 14 25o/o 4

Each lnspection lnterval 1

1 2

tst-0020-c Class 1 SIS Piping Supports

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paqe 1 10 of 174 Appendix D (Page 4 ot 201 Examination Summary Table for ASME Class 1, 2, and 3 Gomponent Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.10A SIS VT-3 44 25o/o 11 Each lnspection lnterval 3

4 4

ISI-0021-C F1.1 0B SIS VT-3 62 250/

16 Each lnspection lnterval 5

5 6

rsr-0021-c F1.10C SIS VT.3 8

254/a 2

Each lnspection lnterval 1

1 0

rsr-0021-c F1.10D SIS VT.3 47 25%

12 Each lnspection lnterval 4

4 4

rsr-0021-c F.A F1.2AX (See Note 1)

Class 2 Piping Supports Visual Class 2 AFWS Piping Supports F1.204 AFWS VT.3 49 15o/o 7

Each lnspection lnterval 2

3 2

tst-0062-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 111 of 174 Appendix D (Page 5 of 20)

Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED

!N THE FIRST PERIOD NUMBER TO BE EXAMINED !N THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.20B, AFWS VT-3 46 15o/o 7

Each lnspection lnterval 2

2 3

tst-0062-c Fl.20C AFWS VT-3 7

15o/o 1

Each lnspection lnterval 0

0 1

tst-0062-c F1,2OD AFWS VT-3 12 15o/o 2

Each lnspection lnterval 0

1 1

rst-0062-c Class 2 CSS Piping Supports F1,2OA CSS VT-3 68 15o/o 10 Each lnspection lnterual 4

3 3

rst-0423-c F1.20B, CSS VT-3 2A 154/o 3

Each lnspection lnterval 1

1 1

rst-0423-c F1.20C CSS VT-3 7

15o/o 1

Each lnspection lnterval 0

1 0

rsr-0423-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1,TRl-0-l 0.3 Rev. 0001 Paqe 112 of 174 Appendix D (Page 6 of 20)

Examination Summary Table for ASME Glass 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.20D CSS VT-3 22 15o/o 3

Each lnspection lnterval 1

0 2

rsr-0423-c Class 2 CVCS Piping Supports F1.204 CVCS VT-3 106 154/o 16 Each lnspection lnterval 5

5 6

tst-0424-c F1.20B, CVCS VT-3 123 15%

18 Each lnspection lnterval 6

4 8

tst-0424-c F1.20C CVCS VT-3 11 15o/o 2

Each lnspection lnterual 0

1 1

rst-0424-c F1,2OD CVCS VT-3 16 15o/o 3

Each lnspection lnterval 1

0 1

rst-0424-c Class 2 FWS Piping Supports F1.2AA FWS VT-3 55 154/o I

Each lnspection lnterval 3

3 2

tst-0062-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 113 of 174 Appendix D (Page 7 ot 2Ol Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED

!N THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.20B, FWS VT-3 26 15o/o 4

Each lnspection lnterval 1

1 2

rst-0062-c F1.20C FWS VT-3 6

1sa/o 1

Each lnspection lnterval 1

0 0

ISI.OO62-C F1.20D FWS VT-3 42 15o/o 6

Each lnspection lnterval 1

3 2

rsr-0062-c Class 2 MSS Piping Supports F1.2AA MSS VT-3 19 15o/o 3

Each lnspection lnterual 1

1 1

tst-001 1-c F1.20B, MSS VT.3 1

15o/o 1

Each lnspection lnterval 0

0 1

rsr-0011-c F1.20C MSS VT-3 12 15o/o 2

Each lnspection lnterval 0

1 1

rsr-001 1-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-l 0.3 Rev. 0001 Paqe 114 of 174 Appendix D (Page 8 of 20)

Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.20D MSS VT-3 23 15%

3 Each lnspection lnterval 1

1 1

lst-001 1-c Class 2 RHRS Piping Supports F1.20A RHRS VT-3 90 15o/o 14 Each lnspection lnterual 4

5 5

rsr-0020-c rsr-0107-c F1.2AB RHRS VT.3 25 154/o 4

Each lnspection lnterval 2

1 1

rsr-0020-c rst-0107-c F1.zAC RHRS VT.3 22 15o/o 3

Each lnspection lnterval 1

1 1

rsr-00za-c ISI-01A7-C F1.20D RHRS VT-3 33 15%

5 Each lnspection lnterval 2

1 2

rst-0020-c tst-01a7-c Class 2 SIS Piping Supports F1.20A SIS VT-3 130 15o/o 2A Each lnspection lnterual 6

7 7

rsr-0021-c rsr-0440-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 115 of 174 Appendix D (Page 9 of 20)

Examination Summary Table for ASME GIass 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.2AB SIS VT.3 135 15o/o 20 Each lnspection lnterval 7

6 7

ISI-OO21.C lsr-0440-c F1.2AC SIS VT-3 19 15o/o 3

Each lnspection lnterual 1

1 1

rsr-0021-c rsr-0440-c F1.20D SIS VT-3 40 15o/o 6

Each lnspection lnterval 2

2 2

tst-0021-c ISI-0440-C F.A F1.30X (See Note 1)

Class 3 Piping Supports Visual CIass 3 AFWS Piping Supports F1.30A AFWS VT-3 2A 10o/o 2

Each lnspection lnterval 0

1 1

rsr-01 1 1-c F1.308 AFWS VT-3 16 1Ao/o 2

Each lnspection lnterval 1

0 1

rst-o111-c

WBN Unit 1 UNIT l ASME PROGRAM SEGTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 116 of 174 Appendix D (Page 10 of 20)

Examination Summary Table for ASME Class 1,2, and 3 Gomponent Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.30C AFWS VT-3 6

10o/o 1

Each lnspection lnterval 0

1 0

rsr-01 1 1-c F1.30D AFWS VT-3 7

100h 1

Each lnspection lnterval 1

0 0

rst-o111-c Class 3 CCS Piping Supports F1.30A CCS VT-3 415 10o/o 42 Each lnspection lnterval 14 14 14 rsr-0252-c F1.308 CCS VT-3 108 100/,

11 Each lnspection lnterual 3

4 4

rsr-0252-c F1.30C CCS VT-3 2A 10o/o 2

Each lnspection lnterval 1

0 1

lst-0252-c F1.30D CCS VT-3 5

lAYo 1

Each lnspection lnterval 0

1 0

rsr-0252-c Class 3 ERCWS Piping Supports

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 117 of 174 Appendix D (Page 11 ot20l Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.30A ERCWS VT-3 429 10%

43 Each lnspection lnterval 14 14 15 rsr-0112-c F1.308 ERCWS VT-3 449 1Ao/o 45 Each lnspection lnterval 16 15 14 tst-0112-c F1.30C ERCWS VT-3 20 10%

2 Each lnspection

!nterval 1

1 0

tst-0112-c F1.30D ERCWS VT-3 24 104/o 2

Each lnspection lnterval 1

1 0

lsl-0112-c Class 3 FPCS Piping Supports F1.30A FPCS VT-3 38 10%

4 Each lnspection lnterval 1

1 2

rsr-01 10-c F1.30B FPCS VT-3 23 10o/o 2

Each lnspection lnterval 1

1 0

rs!-01 10-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paqe 1 18 of 174 Appendix D (Page 12ot20l Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.30C FPCS VT-3 11 10%

1 Each lnspection lnterval 0

1 0

rsr-01 10-c F1.30D FPCS VT-3 6

1Ao/o 1

Each lnspection lnterval 0

0 1

rst-01 10-c Class 3 HPFPS Piping Supports F1.30A HPFPS VT-3 97 1Aa/o 10 Each lnspection lnterval 3

3 4

rsr-0500-c F1.308 HPFPS VT-3 55 1Ao/o 6

Each lnspection lnterval 2

2 2

ISI.O5OO-C F1.30C HPFPS VT-3 2

10o/o 1

Each lnspection lnterval 0

0 1

rsr-0500-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paqe 119 of 174 Appendix D (Page 13 of 20)

Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F-A F1.40X (See Note 2)

Class 1, 2, or 3 supports other than piping supports Visual Supports on one or one of multiple components Class 1 Equipment F1.414 CVCS VT-3 1

100%

1 Each lnspection lnterual 1

0 0

rsr-0026-c F1.41B, Class 1 Reactor Vessel VT.3 Reactor Vessel

/ 1 support Ail Reactor Vessel / 1 support Each lnspection lnterval 0

0 Reactor Vessel / 1 support lst-0427-c F1.41B, Class 1 CRDM Seismic Support VT-3 Reactor Vessel

/ 1 support Ail Reactor Vessel / 1 support Each lnspection lnterval 0

0 Reactor Vessel / 1 support N/A F1.41B Class 1 Pressu rizer VT.3 Pressurizer I 2 supports Ail Pressurizer I 2 supports Each lnspection lnterval 0

Pressurizer I 1 support (seismic)

Pressurizer I 1 support (skirt)

CHM-2570-C F1.41B, Class 1 Steam Generator VT-3 4SG/1 support each One SG OneSG/1 support Each lnspection lnterval 0

0 OneSG/1 support CHM-2660-C

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-l 0.3 Rev. 0001 Paqe 120 of 174 Appendix D (Page 14 ot 201 Examination Summary Table for ASME Glass 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAM!NED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.41B, Class 1 Reactor Coolant Pump VT.3 4RCP/1 support each One Pump 1 RCP/1 support Each lnspection lnterval 0

1 RCP/1 support 0

tsl-0446-c Class 1 Valves Note: Schedule the F1.40X exam with the corresponding system F1.10X exams.

F1.41D CVCS VT-3 5

1004/o 5

Each lnspection lnterval 1

2 2

rsr-0026-c F1.41D RCS VT-3 3

1O0o/o 3

Each lnspection lnterval 1

1 1

rst-0364-c Class 2 Equipment F1.42B Class 2 Steam Generator VT-3 4SGs/1 support each 1SG 1 SG support Each lnspection lnterval 1SG support 0

0 CHM-2660-C F1.42B, Class 2 RHR Heat Exchanger VT.3 2 RHRHX I 1 support each 1

RHRHX 1 RHRHX support Each lnspection lnterual 0

1 RHRHX support 0

cHM-2662-C F1.42B, Class 2 CSS Heat Exchanger VT-3 2CSHX/1 support each 1 CSHX 1 CSHX support Each lnspection lnterual 0

0 1 CSHX support tst-0371-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paqe 121 of 174 Appendix D (Page 15 of 20)

Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAM!NED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.42B, Class 2 Seal Water Heat Exchanger VT.3 Seal Water Heat Exch / 1 support AI!

Seal Water Heat Exch suppoft Each lnspection lnterval 0

Seal Water Heat Exch support 0

rst-0484-c Fl.42B, Class 2 Seal Water Filter VT-3 Seal Water Filter / 1 support Ail Sea! Water Filter support Each lnspection lnterval 0

Seal Water Filter support 0

lst-0487-c F1.42B, Class 2 Seal Water lnjection Filter VT.3 2 Seal Water lnjection Filters

/ 1 support Ail 1 Seal Water lnjection Filter support Each lnspection lnterval 1 Seal Water lnjection Filter suppoft 0

0

!sl-0486-c F1.42B' Class 2 Boron lnjection Tank (Brr)

VT-3 BIT / 1 support Ail BIT support Each lnspection lnterval 0

BIT support 0

rsr-0053-c F1.42B, Class 2 RHR Pump VT-3 2RHRP/1 support each 1 Pump 1 RHRP support Each lnspection lnterval 0

0 1 RHRP support rst-0117-c F1,42B, Class 2 Centrifugal Charging Pump VT-3 2CCP I 1 support each 1 Pump 1 CCP support Each lnspection lnterual 1 CCP support 0

0 rst-01 18-c F1,42B Class 2 Safety lnjection Pump VT.3 2StP/1 support each l Pump 1 SIP support Each lnspection lnterval 0

1 SIP support 0

rsr-012a-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-l 0.3 Rev. 0001 Paqe 122 of 174 Appendix D (Page 16 of 20)

Examination Summary Table for ASME Class 1,2, and 3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.42B, Class 2 Containment Spray Pump VT.3 2CSP/1 support each 1 Pump 1 CSP support Each lnspection lnterval 0

0 1 CSP support rsr-0483-c Glass 2 Valves Note: Schedule the F1.40X exam with the corresponding system F 1.zAX exams.

F1.424 CSS w-3 2

lAAo/o 2

Each lnspection lnterual 1

0 1

rst-0423-c F1,42C CSS w-3 1

10}o/o 1

Each lnspection lnterual 0

1 0

tsr-0423-c F1.42D CVCS VT-3 3

100%

3 Each lnspection lnterual 1

1 1

lsr-0424-c F1.42D FWS VT.3 2

100%

2 Each lnspection lnterual 0

1 1

rst-0062-c F1.42D SIS VT-3 2

10a%

2 Each lnspection lnterval 1

0 1

tsr-0440-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 123 of 174 Appendix D (Page 17 ot 201 Examination Summary Table for ASME Class 1,2, and 3 Gomponent Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED !N THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER Glass 3 Equipment F1.438 Class 3 Motor Driven Auxiliary Feedwater Pump (MDAFWP)

VT-3 2 (1 support on each MDAFWP) 1 Pump 1

MDAFWP support Each lnspection lnterval 0

0 1

MDAFWP support rsr-0492-c F1.438 Class 3 Turbine Driven Auxiliary Feedwater Pump (TDAFWP)

VT.3 1

1 Pump 1

TDAFWP support Each lnspection lnterval 0

0 1

TDAFWP support tst-0493-c F1.438 Class 3 Component Cooling Surge Tank (ccsr)

VT-3 1

Ail CCST support Each lnspection lnterval 0

CCST support 0

rsr-0496-c F,I.438 Class 3 CCS Heat Exchanger (CCHX) w-3 3 (1 support on each CCHX) 1 CCHX l CCHX support Each Inspection lnterval 0

1 CCHX suppod 0

rsr-0494-c F1.438 Class 3 CCS Water Pumps (CCSWP)

VT-3 5 (1 support on each CCSWP) 1 CCSWP l CCSWP support Each lnspection lnterval 0

l CCSWP support 0

tst-0495-c F1.438 Class 3 Nonregenerative Letdown Heat Exchanger (NRLHX)

VT-3 1

AII NRLHX support Each lnspection lnterual 0

NRLHX support 0

rsr-0497-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 124 of 174 Appendix D (Page 18 of 20)

Examination summary Table for ASME class 1,2, and 3 component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.438 Class 3 RHR Heat Exchanger Secondary Side (RHRHX)

VT-3 2 (1 support on each RHRHX) 1 RHRHSHX 1

RHRHSHX support Each lnspection lnterval 0

0 1

RHRHSHX support CHM-2662-C F1.43B Class 3 Containment Spray Heat Exchanger (csHX)

VT-3 2 (1 support on each CSHX) 1 CSHX 1 CSHX support Each lnspection lnterval 0

0 1 CSHX support lst-0371-c F1.438 Class 3 ERCW Pump (ERCWP)

VT-3 8 (1 support on each ERCWP) 1 ERCWP l ERCWP support Each lnspection lnterual 0

0 l ERCWP support ISI-O4B8.C F1.43B Class 3 ERCW Screen Wash Pump (ERCWSWP)

VT-3 4 (1 support on each ERCWSWP) 1 ERCWSWP 1

ERCWSWP support Each lnspection lnterval 0

1 ERCWSWP support 0

lsr-0490-c F1.438 Class 3 ERCW Strainer (ERCWS)

VT-3 4(1 support on each ERCWS) 1 ERCWS l ERCWS support Each lnspection lnterval l ERCWS support 0

0 lst-0489-c F1.43B Class 3 FPCC Spent Fuel Pit Heat Exchanger (FPCCHX)

VT.3 2 (1 support on each FPCCHX) 1 FPCCHX 1

FPCCHX support Each lnspection lnterval 1

FPCCHX support 0

0 rst-0372-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 125 of 1 74 Appendix D (Page 19 of 20)

Examination Summary Table for ASME Class 1, 2, and3 Component Supports EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD NUMBER OF COMPONENTS IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREOENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER F1.438 Class 3 FPCC Spent Fuel Pit Pumps (FPCCP)

VT-3 3(1 support on each FPCCP) 1 FPCCP 1 FPCCP support Each lnspection lnterval 0

1 FPCCP support 0

tsr-048s-c F1.438 Class 3 HPFP Pumps (HPFPP)

VT.3 4 (1 support on each HPFPP) 1 HPFPP 1 HPFPP support Each lnspection lnterval 1 HPFPP support 0

0 rsr-0501-c F1.43B Class 3 HPFP Strainers (HPFPS)

VT.3 2 (1 support on each HPFPS) 1 HPFPS 1 HPFPS support Each lnspection lnterva!

1 HPFPS support 0

0 tst-0502-c F1.438 Class 3 Seal Water Heat Exchanger (swHX)

VT-3 1

Ail SWHX support Each lnspection lnterual 0

SWHX support 0

lsr-0484-c

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-o-l 0.3 Rev. 0001 Paoe 126 of 174 Appendlx D (Pags 20 of 20)

Examination Summary Table for ASilIE Class 1, 2, and 3 Component Supports Note 1: ln accordance with Table IWF-250G 1, ltem Numbers have been categorized to idenfiry support types by component support tunction as follows (the 'y in F1.YoX is t, 2, or 3 as appropriate for the associated piping classification):

Item No. F'l.YoA - one direciional restraints (Function A)

Itsm No. F'l.YoB - multidirectional restraints (Function B)

Item No. F'l.YoC - variable supports such as: springs and constant force (Function C)

Item No. F'l.YoD - snubbers (Function D), portions of supports that contain snubbers, but outside of the snubber pins Note 2: ln accordance with Table IWF-250G 1, ltem Numbers have b6on categorized to identiry support types by component support function as follows (the.Y' in F1.4YX is 1, 2, or 3 as appropriate for the associated piping classification):

Item No. F1.4YA - one directional restraints (Function A)

Item No. Fl.4YB - multidirectional restraints (Function B)

Itom No. Fl.4YC - variable supports such as: springs and constant force (Function C)

Item No. Fl.4YD - snubbers (Function D), portions of supports that contain snubbers, but outside of the snubber pins

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 127 of 174 Appendix E (Page 1 ot 4l Examination Summary Table for Risk-lnformed Piping Welds EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD (see Notes 1&2)

NUMBER OF COMPONENT S IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED !N THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER R.A High-Safety-Significant Piping Structural Elements R-A R1.11 Welds Subject to Thermal Fatigue Volumetric 7A 35.7%

25 Deferral Not Permissible 6

11 8

N/A R1.11s Socket and Branch Connection (NPS 2 and srnaller) Welds Subject to Thermal Fatigue Volumetric NT-2 35 54.2%

See Note 2

19 Deferral Not Permissible 0 See Note 2 0 See Note 2

19 Volumetric Exams See Note 2

N/A R1.11l 15 Welds Subject to Thermal Fatigue and Primary Water Stress Corrosion Cracking (PWSCC)

Volumetric 1

100%

1 Deferral Not Permissible 0

1 0

N/A

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 128 of 174 Appendix E (Page 2 ot 4l EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD (see Notes 1&Z)

NUMBER OF COMPONENT S IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER R1.111 16 Welds Subject to Thermal Fatigue and Subject to lntergranular or Transgranular Stress Corrosion Cracking (IGSCC, TGSCC)

Volumetric 4

50%

2 Deferral Not Permissible 2

0 0

N/A R1.'l 1/

16s Socket and Branch Connection (NPS 2 and smaller) Welds Subject to Thermal Fatigue and Subject to lntergranular or Transgranular Stress Corrosion Cracking (IGSCC, rGSCC) vT-2 4

Ao/o 0

Deferral Not Permissible 0

0 0

N/A

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 129 of 174 Appendix E (Page 3 of 4)

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 130 of 174 Appendix E (Page 4 ot 4l EXAM CAT.

ITEM NO.

DESCRIPTION EXAM METHOD (see Notes 1&2)

NUMBER OF COMPONENT S IN ITEM NO.

%TOBE EXAMINED DURING INTERVAL NUMBER TO BE EXAMINED IN THE INTERVAL FREQENCY OF EXAMINATION OR DEFERRAL OF INSPECTION TO END OF INTERVAL NUMBER TO BE EXAMINED IN THE FIRST PERIOD NUMBER TO BE EXAMINED IN THE SECOND PERIOD NUMBER TO BE EXAMINED IN THE THIRD PERIOD ISI DRAWING NUMBER R1.20s Socket and Branch Connection (NPS 2 and smaller)

Welds not Subject to a Damage Mechanism vT-2 442 4Yo See Note 2 18 Deferral Not Permissible See Note 2

See Note 2 See Note 2

N/A Nob 1: As defined in Code Case N-716-1.

Note 2: Socket welds (any size) and branch pipe conneclions (NPS 2 and smaller) in examination Category R-A roquire a VT-2 each refueling outage (Class 1) oreach period (Class 2 and 3), per Code Case N-716-1, Table 1, Notes 9 & 10. Socket welds associated with thermalfatigue (R1.11s) additionally requirc a volumetric examination of the piping base materialwithin 0.5 inch of the toe of the weld. The Class 1 VT-2 examination for these Socket welds and smsll (NPS 2 and smaller) branch pipe connections will be performed and recorded as part of 1-TRl-6&6, System Leakage Test Reactor Coolant System and 1-TRl-68-90r, Reactor Coolant I GYear End of lnterval System Leakage Test.

WBN Unit 1 UNIT l ASME PROGRAM SECTION X! ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 131 of 174 Appendix F (Page 1 ot 2)

Glass 1(B-M-21 Valve Listing NOTES

1) Examination is limited to at teast one valve in each group of valves per interval.

2) Examination of valve pressure retaining bolting (B-G-2) should also be performed during the B-M-2 exam CLASS 1 EXAMINATION CATEGORY B-M.2 VALVE LISTING SYS VALVE ISI DRAWING SIZE (in.)

TYPE FUNCTION GROUP VENDOR VENDOR DRAWING SIS FCV-63-067 cHM-2758-C-10 10 GATE ISOLATION 1

WESTINGHOUSE 115E013 SIS FCV-63-080 cHM-2758-C-09 10 GATE ISOLATION 1

WESTINGHOUSE 115E013 SIS FCV-63-98 cHM-2758-C-08 10 GATE ISOLATION 1

WESTINGHOUSE 115E013 SIS FCV-63-1 18 cHM-2758-C-07 10 GATE ISOLATION 1

WESTINGHOUSE 115E013 SIS63-558 cHM-2758-C-10 6

CKV PSIV 2

WESTINGHOUSE 934D185 SIS63-559 cHM-2758-C-08 6

CKV PSIV 2

WESTINGHOUSE 934D185 SIS63-632 cHM-2758-C-08 6

CKV PSIV 2

WESTINGHOUSE 934D185 SIS63-633 cHM-2758-C-07 6

CKV PSIV 2

WEST!NGHOUSE 934D185 SIS63-634 cHM-2758-C-09 6

CKV PSIV 2

WESTINGHOUSE 934D185 SIS63-635 cHM-27s8-C-10 6

CKV PSIV 2

WESTINGHOUSE 934D185 SIS63-560 cHM-2758-C-07 10 CKV PSIV 3

WESTINGHOUSE 934D 187 SIS63-561 cHM-2758-C-08 10 CKV PS!V 3

WESTINGHOUSE 934D 187 SIS63-562 cHM-2758-C-09 10 CKV PSIV 3

WESTINGHOUSE 934D 187 SIS63-563 cHM-2758-C-10 10 CKV PSIV 3

WESTINGHOUSE 934D 187

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-l 0.3 Rev. 0001 Paqe 132 of 174 Appendix F (Page 2 ot 2l Glass 1(B-M-21 Valve Listing CLASS 1 EXAMINATION CATEGORY 8.M.2 VALVE LISTING SYS VALVE ISI DRAWING SIZE (in.)

TYPE FUNCTION GROUP VENDOR VENDOR DRAWING SIS63-622 cHM-2758-C-A7 10 CKV PSIV 3

WESTINGHOUSE 934D 187 SIS63-623 cHM-2758-C-08 10 CKV PSIV 3

WESTINGHOUSE 934D 187 SIS63-624 cHM-2758-C-09 10 CKV PSIV 3

WESTINGHOUSE 934D 187 SIS63-625 cHM-2758-C-10 10 CKV PSIV 3

WESTINGHOUSE 934D 187 RHR 63-640 cHM-2636-C-07 8

CKV PSIV 4

WESTINGHOUSE 934D186 RHR 63-643 cHM-2636-C-08 8

CKV PSIV 4

WESTINGHOUSE 934D186 RHR 63-641 cHM-2636-C-07 6

CKV PSIV 5

WESTINGHOUSE 934D185 RHR 63-644 cHM-2636-C-08 6

CKV PSV 5

WESTINGHOUSE 934D185 RCS68-563 rst-0365-c-01 6

RELIEF RELIEF VALVE 6

CROSBY DSCAs6964 RCS68-564 rsr-0365-c-01 6

RELIEF RELIEF VALVE 6

CROSBY DSCA56964 RCS 68-s65 rsr-0365-c-01 6

RELIEF RELIEF VALVE 6

CROSBY DSCAs6964 RHR FCV-74-O1 cHM-2636-C-01 14 GATE PSIV 7

WESTINGHOUSE 115E622 RHR FCV-74-42 cHM-2636-C-01 14 GATE PSIV 7

WESTINGHOUSE 115E622 RHR FCV-74-08 cHM-2636-C-01 10 GATE PSIV 8

WESTINGHOUSE 1167E79 RHR FCV-74-09 cHM-2636-C-01 10 GATE PSIV 8

WESTINGHOUSE 1167E79

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 133 of 174 Appendix G (Page 1 of 5) lSl Drawing List List of Aoolicable Flow Diaorams Drawino Series Svstem Descriotion 1-47W801 Main & Reheat Steam & Steam Generator Blowdown (TVA Class B) 1-47W803 Feedwater & Auxiliary Feedwater (TVA Class B & C) 1-47W809 Chemical & Volume Control (TVA Class A & B) 1-47W8'10 Residual Heat Removal (TVA Class A & B) 1-47W811 Safety lnjection (TVA Class A & B) 1-47W812 Containment Spray (TVA Class B) 1-47W813 Reactor Coolant (TVA Class A) 1-47W814 lce Condenser (exempt) 1-47W819 Primary Water (exempt) 1-47W830 Waste Disposal (exempt) 147W832 Raw Water - Yard (TVA Class C) 1-47W845 Essential Raw Cooling Water (TVA Class B & C) 1-47W850 Fire Protection & Raw Service Water (TVA Class C) 1-47W851 Floor & Equipment Drains (exempt) 1-47W855 Fuel Pool Cleaning & Cooling (TVA Class C) 1-47W856 Demineralized Water & Cask Decon (exempt) 1-47W859 Component Cooling (TVA Class B & C) 147W862 Steam Generator Layup Water Treatment (exempt) 1-47W865 Heating & Air Conditioning (exempt) lSl Drawinos List Drawino Series Svstem Description CHM-2547-C Reactor Coolant Main Loop Piping Weld Locations CHM-2549-C ReactorVesselClosure CHM-2570-C Pressurizer CHM-2636-C Residual Heat Removal Piping Weld Locations CHM-2660-C Steam Generator CHM-2662-C Residual Heat Removal Heat Exchanger ChannelWelds CHM-2669-C Main steam Piping Weld Locations CHM-2671-C Feedwater Piping Weld Locations CHM-2684-C Upper head Penetrations CHM-2685-C Auxiliary Head Adapter CHM-2758-C Safety lnjection System Piping lSl-0005-C Chemical and Volume Control Piping Weld Locations

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paoe 134 of 174 D[?winq Series tst-0011-c ISI-OO2A-C rsr-0021-c tsr-0026-c rsr-0048-c ISI-OOsO-C

!sr-0053-c lsr-0062-c rsr-0063-c rsr-0081-c rsr-0082-c ISt-0107 -C rsr-01 10-c tst-0111-c tst-0112-c tst-0117-c tst-01 18-c rsr-01 19-c rsr-012a-c tst-0124-c rst-0252-c rsr-0364-c rst-0365-c tst-0371-c rsr-0372-c rsr-0375-c ISI-O4OO-C rst-0421-c rst-0423-c ISI.O424-C tst-0427-c rsr-0438-c rst-0439-c tst-0440-c tst-0446-c rst-0447-c Appendix G (Page 2 of 5) lsl Drawing List Svstem Description Main steam Piping Support Locations Residual Heat Removal Piping Support Locations Safety lnjection Piping Support Locations Chemical and Volume Control Piping Support Locations Reactor Coolant Pump Case Weld Locations CVCS Seal Water lnjection Piping Weld Locations Boron lnjection Tank Weld and Support Locations Feedwater Piping Support Locations CVCS Seal Water lnjection Piping Support Locations Main steam Relief Valve Feedwater Check Valve Residual Heat Removal Piping Support Locations (HPSI portion)

Fuel Pool Cooling and Cleaning Piping Support Locations Auxiliary Feedwater Support Locations Essential Raw Cooling Water Piping Support Locations Residual Heat Removal Pump Supports Centrifugal Charging Pump Supports Reciprocating Charging Pump Supports Safety lnjection Pump Supports Pressurizer Surge Line Piping Supports Component Cooling Piping Support Locations Reactor Coolant Piping Support Locations Reactor Coolant Piping Weld Locations Containment Spray Heat Exchanger Support Details Spent Fuel Pit Heat Exchanger Support Locations High Pressure Safety lnjection Piping Weld Locations Containment Spray Piping Weld Locations High Pressure Safety lnjection Excluded Piping Weld Locations Containment Spray Piping Support Locations Chemical and Volume Control Piping Support Locations (HPSI portion)

Reactor Vessel Reactor Coolant Main Loop Piping Support Locations Piping Support Examination Boundaries Safety lnjection Piping Support Locations (HPSI portion)

Reactor Coolant Pump Supports Reactor Coolant Pump Main Flange Bolt Circle

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 135 of 174 Drawinq Series rsr-0483-c lsr-0484-c rsr-0485-c rsr-0486-c rsl-0487-c ISI-0488-C rsr-0489-c rst-0490-c rsr-0492-c rsr-0493-c rsr-0494-c tst-0495-c rsr-0496-c tst-0497-c tst-0500-c ISr-0501-C tsr-0502-c rsr-0508-c Drawino Series cHM-2547-C CHM-2549-C CHM-2570-C CHM-2636-C CHM-2660-C CHM-2662-C CHM-2669-C cHM-2671-C cHM-2684-C CHM-2685-C CHM.2758-C lsr-0005-c P-r"aw"[ng s.g;tgs ts!-0011-c rst-0012-c Appendix G (Page 3 of 5) lsl Drawing List Svstem Description Containment Spray Pump Support Locations Seal Water lnjection Heat Exchanger Support Locations Spent Fuel Pool Pumps Support Locations Seal Water lnjection Filter Support Locations Seal Water Filter Support Locations ERCW Pumps Support Locations ERCIV Strainer Support Locations ERCW Screen Wash Pumps Support Locations Motor Driven Auxiliary Feedwater Pumps Support Locations Turbine Driven Auxiliary Feedwater Pump Support Locations Component Cooling Heat Exchanger Support Locations Component Cooling Water Pumps Support Locations Component Cooling Surge Tank Support Locations Non-Regenerative Letdown Heat Exchanger Support Locations High Pressure Fire Protection Piping Support Locations HPFP Pump Support Locations HPFP Strainer Support Locations Steam Generator Blowdown Piping Weld Locations ISI Drawinqs List Syste.m Description Reactor Coolant Main Loop Piping Weld Locations Reactor Vessel Closure Pressu rizer Residual Heat Remova! Piping Weld Locations Steam Generator Residual Heat Removal Heat Exchanger Channel Welds Main steam Piping Weld Locations Feedwater Piping Weld Locations Upper head Penetrations Auxiliary Head Adapter Safety lnjection System Piping Chemical and Volume Control Piping Weld Locations

$-y"p"t.e.glP-"e"s"qr!p"ti"pn Main steam Piping Support Locations Control Rod Drive Housing

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!st-0020-c rsr-0021-c rsr-0026-c rsr-0048-c ISI-OO5O-C rsl-0053-c tst-0062-c tst-0063-c rsr-0081-c rsl-0082-c lsl-0107 -c tst-01 10-c tst-0111-c rsr-0112-c ISr-0117-C rst-01 18-c lsr-01 19-c ISI-0120-C rsr-0124-c rsr-0252-c lsr-0364-c ts!-0365-c rsr-0371-c rst-0372-c tsr-0375-c tst-0400-c lsr-0421-c rsr-0423-c tst-0424-c rsr-0427-c ISr-0438-C tsr-0439-c rst-0440-c rsr-0446-c tst-0447-c Drawing Series tsr-0483-c rst-0484-c Appendix G (Page a of 5) lSI Drawing List Residual Heat Removal Piping Support Locations Safety lnjection Piping Support Locations Chemical and Volume Control Piping Support Locations Reactor Coolant Pump Case Weld Locations CVCS Seal Water lnjection Piping Weld Locations Boron lnjection Tank Weld and Support Locations Feedwater Piping Support Locations CVCS Seal Water Injection Piping Support Locations Main steam Relief Valve Feedwater Check Valve Residual Heat Removal Piping Support Locations (HPSI portion)

Fuel Pool Cooling and Cleaning Piping Support Locations Auxiliary Feedwater Support Locations Essential Raw Cooling Water Piping Support Locations Residual Heat Removal Pump Supports Centrifugal Charging Pump Supports Reciprocating Charging Pump Supports Safety Injection Pump Supports Pressurizer Surge Line Piping Supports Component Cooling Piping Support Locations Reactor Coolant Piping Weld Locations Reactor Coolant Piping Support Locations Containment Spray Heat Exchanger Support Details Spent Fuel Pit Heat Exchanger Support Locations High Pressure Safety lnjection Piping Weld Locations Containment Spray Piping Weld Locations High Pressure Safety lnjection Excluded Piping Weld Locations Containment Spray Piping Support Locations Chemical and Volume Control Piping Support Locations (HPSI portion)

Reactor Vessel Reactor Coolant Main Loop Piping Support Locations Piping Support Examination Boundaries Safety lnjection Piping Support Locations (HPSI portion)

Reactor Coolant Pump Supports Reactor Coolant Pump Main Flange Bolt Circle System Pescriotion Containment Spray Pump Support Locations Seal Water lnjection Heat Exchanger Support Locations

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 137 of 174 tst-0485-c rsr-0486-c rst-0487-c rsr-0488-c rsr-0489-c tsl-0490-c

!sr-0492-c rsr-0493-c rst-0494-c rsl-0495-c tst-0496-c tst-0497-c rsr-0500-c rsr-0501-c rsr-0502-c rsr-0508-c Appendix G (Page 5 of 5) lsl Drawing List Spent Fuel Pool Pumps Support Locations Seal Water Injection Filter Support Locations Seal Water Filter Support Locations ERCW Pumps Support Locations ERCW Strainer Support Locations ERCW Screen Wash Pumps Support Locations Motor Driven Auxiliary Feedwater Pumps Support Locations Turbine Driven Auxiliary Feedwater Pump Support Locations Component Cooling Heat Exchanger Support Locations Component Cooling Water Pumps Support Locations Component Cooling Surge Tank Support Locations Non-Regenerative Letdown Heat Exchanger Support Locations High Pressure Fire Protection Piping Support Locations HPFP Pump Support Locations HPFP Strainer Support Locations Steam Generator Blowdown Piping Weld Locations

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Pabe 138 of 174 Appendix H (Page 1 of 1)

Schedule of Successive Examinations COMPONENT IDENTIFIER PROGRAM REFERENCE SECTION EXAM METHOD EXAM CAT CYCLE FLAW INITIALLY DETECTED FIRST SUCCESSlVE PERIOD SECOND SUCCESSIVE PERIOD TH!RD SUCCESSIVE PERIOD ISI DRAWING (Reserved )

WBN UNIT l ASME SECTION XI ISI/NDE I1.TRI.O.1 0.3 Unit 1 PROGRAM THIRD INTERVAL IRev. 0001 Paqe 139 of 174 Appendix I (Page 1 of 1)

Notification of Additional Sample Results Form TO:

FROM:

Plant/Unit Component lD Code Category Transmittal Number:

System Exam Method(s) lnitial Sample NOI Number 1st Additional Sample NOI Number 2nd Additional Sample NOI Number Drawing Number Evaluation/Recommendation Prepared By:

Coordinated with lSl/NDE Representative:

Prepared By Eva I uation/Recomme nd ation (attach additional information if needed)

Additional Components to be Examined

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Requests for Relief RFR No.

Component RFR Requested RFR Description Status PDI.4 RPV shell-to-flange weld Use ASME Section Xl Appendix Vlll for examination of the RPV shell-to-flange weld in lieu of Appendix l.

Submitted for both WBN-1 & -

2 by TVA-Io-NRC Letter CNL-16-A74. See below for text of PDt-4.

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Augmented Examinations The following augmented examinations have been requested to be included in the lSl Program by the responsible organization listed. A summary of the augmented examinations are listed below and a detailed description follows this page.

NOTE When augmented examinations of welds do not interrogate greater than g0% of the examination volume, the basis and/or requirements for performing the exam shal! be reviewed to determine if the limited exam requires a UFSAR change, 50.59 screening review, or request for relief to ensure acceptability.

1.0 REACTOR COOLANT PUMP FLYWHEEL 1.1 Examination Requirements and Schedule:

A. Perform a surface or volumetric examination at approximately 20-year intervals.

Responsible Organization: Gomponent Engineering ln lieu of Regulatory Guide 1.14 Position C.4.b(1) and C.4.b(2), a qualified in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius, or a surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the removed flywheels may be conducted at approximately 20-year lnspection lntervals coinciding with the lSl schedule as required by ASME Section Xl per Technical Specification Change TS-01-13. The original 10-year lSl lnspection lnterval was changed to 20-year lnspection lntervals per Technical Specification Change TS-WBN-'l3-03. This examination is performed in accordance with WBN Technical Specifications and satisfies Surveillance Requirement 4.0.5.c.

The flywheel consists of 2 plates, approximately 7 inches thick each, bolted together.

Each plate is fabricated from vacuum degassed A-533, GR. B, Class 1, steel.

1.2 Augmented Requirements Summary A. Source Documents 1. Technical Specification SR 5.7.2.10 (TS-WBN-13-03)

2. FSAR Subsection 5.2.6

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Augmented Exam inations Augmented Requirements Summ ary (continued)

B. Associated Documents

1. NRC Nofrce for Availability published on October 22,2003 (68 FR 60422),

2. NRC Nofice for Comment published on June 24,2003 (68 FR 37590),

3. TSFF-4121, WCAP-15666-A, "Extension of Reactor Coolant Pump Flywheel Examination,"

4. The related NRC safety evaluation (SE) dated May 05, 2003.

5. Regulatory Guide 1.14, Revision 1, August 1975

6. NCO 920032003 - Commitment to include RCP Flywheel inspection in lSl program Frequency 20-year lnspection lntervals (the provisions of SR 4.0.2 are not applicable).

The examinations are conducted in conjunction with reactor coolant pump maintenance and controlled by maintenance procedure.

Purpose ldentification of cracks in the base material especially cracks emanating from structural discontinuities. Cracking causes a concern about high-energy missiles inside containment that could potentially damage, and cause the simultaneous failure of multiple trains of redundant safety-related systems.

Scope lnner bore of the flywheel to the circle one-half of the outer radius OR exposed surfaces of the removed flywheel.

Method Qualified in-place ultrasonic examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius: OR, surface examination (magnetic particle and/or liquid penetrant) of exposed surfaces of the removed flywheel.

C.

D.

E.

F.

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Augmented Examinations 1.2 AugmentedRequirementsSummary(continued)

G. lndustry Code or Standard ASME Section Xl, Subarticle IWA-2200 H. Acceptance Criteria or Standard Evidence of cracking requires evaluation in accordance with Regulatory Position C.2.f per Regulatory Guide 1.14 paragraph 4.b.(4).

l.

ReportingRequirements This augmented examination does not require a special report unless the examination reveals a flaw. The acceptance criteria should conform to the recommendations of Regulatory Position C.2.F in Regulatory Guide 1.14 l4.b(4)1. lf the examination and evaluation indicate an increase in flaw size or growth rate greater than predicted for the service life of the flywheel, the results of the examination and evaluation should be submitted to the NRC for evaluation. Refer to Regulatory Guide 1.14 for information to be included.

Report any indication of cracking to the lSl Program Owner for the lSl Final Report. A Notification of lndication Report shall be required.

J. Regulatory Basis

1. Technical Specification SR 5.7.2.10 (TS-WBN-13-03)

2. FSAR Subsection 5.2.6 2,0 THIS SECTION INTENTIONALLY LEFT BLANK.

3.0 EXAMINATION OF PIPING WELDS WITH MULTIPLE WELD REPAIRS 3.1 Examination Requirement and Schedule:

Perform ultrasonic examination of welds with multiple weld repairs as scheduled each refueling outage.

Responsible Organization Mechanical/Nuclear Engineering

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Augmented Examinations 3.1 Examination Requirement and Schedule: (continued)

During the 7th refueling outage inservice inspection of Sequoyah Nuclear Plant's Unit 2, an lntergranular Stress Corrosion Crack (IGSCC) exceeding the acceptance standards of ASME Section Xl was discovered in a safety injection system weld.

Problem evaluation report (PER) SQ961154 was written and the cause of the indication was attributed to multiple weld repairs performed over the life of the weld.

As part of the corrective active, WBN reviewed the weld monitoring program for welds with 4 or more weld repairs. These welds are listed in the table below and are to be examined under this augmented requirement.

3.2 Augmented Requirements Summary A. Source Document

1. Problem Evaluation Report (PER) SQ961154 B. Associated Documents None C. Frequency Examinations shall be performed in accordance with Table 3-1 below.

D. Purpose Assess the identified welds for evidence of IGSCC E. Scope For identification of welds within the scope of this section of augmented examinations, see Table 3-1 below.

F. Method Ultrasonic Examination per NDE procedure N-UT-64 using IGSCC techniques during the first refueling outage and during following outages.

G. lndustry Code or Standard ASME Section Xl

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Augmented Exam inations 3.2 Augmented Requirements Summary (continued)

H. Acceptance Criteria or Standard ASME Section Xl

l.

ReportingRequirements

1. The results are to be submitted to the Materials Section for evaluation.

Materials will evaluate results and make additional recommendations as required.

2. Report any indication of cracking to the lSl Program Owner for the lSl Final Report. A Notification of lndication Report shall be required.

J. Regulatory Basis None.

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Augmented Examinations Augmented Requirements Summary (continued)

Table 3-1 Examine Weld in Refueling Outage 2nd lnt.

Hllttt::ltlll ffi,iiilliiii 3'd lnt.

4th lnt.

lSl Weld Number lSl Drawing Number Pipe Dia.

Wall Thick.

12 14 15 16 17 18 19 21 22 CVCF-D036-1OH ts!-0005-c-01 3"

0.438" X

X X

srF-D076-04 tst-0421-c-05 8"

0.322" X

X X

slF-D078-03 rsl-0375-c-13 24" 0.375" X

x x

x srF-D079-01 lst-0375-c-12 24" 0.375" X

X X

stF-D079-1 1 lsl-0375-c-12 16" 0.375" X

X X

stF-D079-1 1A rst-0375-c-12 16" 0.375" X

X X

X x

stF-D087-11 cHM-2758-C-05 8"

0.906" X

x X

x stF-D087-12 cHM-2758-C-05 8"

0.906" X

X X

sf F-D092-1s cHM-2758-C-10 o

0.719" X

X X

x

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Augmented Examinations EXAMINATION OF ALLOY 600 WELDS ASME Code Gase N-729-1 RPV Head ln response to leaks and nozzle cracking in PWR plants, the NRC issued an Order on February 11,2003 entitled, "lssuance of Order Establishing Interim lnspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors." The NRC Order has since been superseded by ASME Code Case (CC) N-729-1 as conditioned by 10 CFR 50.55a. The visual, surface, and volumetric examinations and examination frequencies are ASME Code requirements, in accordance with 10 CFR 50.55a, and will be performed in accordance with CC N-729-1. Reference Exam Category B-P.

History During the first performance of the augmented inspection required by NRC Order 03-009, RFO8, Areva identified that the coverage for Thermal Couple Column (TCC) #74was limited to 0.91" below the lowest point of the J-groove weld. Revision 1 of Order EA-03-009 required the inspection include to 1.O-inch below the lowest point at the toe of the J-groove weld (on a horizontal plane perpendicular to the nozzle axis). The configuration of the TCC was the reason for the limited available examination area. Request for Relaxation to EA-03-009 was submitted to the NRC on 3/3/08. The NRC Safety Evaluation, docket number 50-390, provided acceptance of the requested relaxation, and allowed use of the proposed alternative inspection area for future inspections, until the order was replaced or rescinded. Reference ADAMS Accession number ML040220181.

During the second performance of the augmented examination in accordance with ASME Code Case N-729-1, RFO12, Areva obtained 100o/o coverage on each CRDM nozzle except nozzles 66,72,73, and 74.The examination volume coverage on nozzles 66,72, and 73 was 98% and on nozzle 74 was 97o/o.The examination volume on all nozzles meets the requirements of "essentially looo/o" of the ASME Code Case N-729-1 as modified by 10CFR50.50.55a.

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Augmented Examinations 4.1.1 Augmented Requirements Summary A. Source Document ASME CC N-729-1, "Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds, Section Xl, Division 1" (Approval Date: March 28,2006),

with the conditions in 10 CFR 50.55a(gXO)(iiXD).

B. Associated Document 10 CFR 50.55a(g)(6xii)(D) Augmented lSl requirements: Reactor vessel head inspections.

Westinghouse Technical Bulletin 07-2 Revision 3 C. Frequency

1. Examinations shall be performed in accordance with Table 4-1 below

2. The examinations listed in Table 1 of CC N-729-1 shall be performed completely, once, as a baseline examination. These examinations shall include all nozzles.

3. lnservice examination frequencies are based on calculated RIY (Reinspection Years calculation compliant with paragraph -2410 of CC N-729-1) and the result of previous examinations. Per 10 CFR 50.55a(gXOXii)(DX5), if flaws attributed to PWSCC are identified, whether acceptable or not for continued service under Paragraphs -3130 or -3140 of ASME CC N-729-1, the re-inspection interval must be each refueling outage.

4. Note 9 of CC N-729-1 shall not be implemented. [10 CFR

50. 55a(s )(6)( i iX DX2)l D. Purpose Assess the presence of PWSCC in reactor vessel upper heads with nozzles with pressure-retaining partial-penetration welds installed.

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Augmented Examinations Augmented Requirements Summary (continued)

E.

Scope Visual Examinations - Outer surface of the Upper Reactor Vessel Head defined by Figure 1 of CC N-729-1.

Volumetric/Surface Examinations - Partial penetration wetds on Nozzles and the Upper Reactor Vessel Head.

ln parallel with the volumetric examination or surface examination to be performed on the RPV head penetration nozzles, the thermal sleeve shall be examined for evidence of material thinning in accordance with Westinghouse Technical Bulletin TB 07-2. The exam should inspect the sleeved penetrations in the two outermost concentric rows of penetrations.

Additionally, as part of the volumetric examination of the RPV head penetrations, the CRDM Head Penetration Adaptor areas where the thermal sleeve centering pads (guide pads) are located sha!! be examined to the extent possible for evidence of any thinning. Areas of thinning shall be identified and documented.

NOTE Appendix l, Analysis Procedure for Alternative Examination Area or Volume Definition, of ASME CC N-729-1 must not be implemented without prior NRC approval. [10 CFR 50.55a(s)(6XiiXD)(6)I F.

Method Visual examination areas defined by Figure 1 on CC N-729-1 of the outer surface of the Reactor Vessel Head.

Volumetric and/or surface examinations of essentially 100 percent of the required volume or equivalent surface examination of essentially 100 percent of the subject J-groove welds. A demonstrated volumetric or surface leak path assessment through all J-groove welds shall be performed. lf a surface examination is being substituted for a volumetric examination of a portion of a penetration nozzle that is below the toe of the J-groove weld, the surface examination shall be of the inside and outside wetted surface of the penetration nozzle not examined volumetrically. [10 cFR 50.55a(gXoXiiXDX3)l 1.

2.

1.

2.

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Augmented Examinations 4.1.1 Augmented RequirementsSummary(continued)

G. lndustry Code or Standard ASME Section Xl,2007 Edition with the 2008 Addenda as supplemented by'10 CFR 50.55a(gXOXiiXDX4) which restricts the use of Section Xl, Appendix Vlll requirements to ASME Section Xl,2004 Edition for examination requirements when using CC N-729-1. [10 CFR 50.55a(gX6XiiXDX4)]

H. Acceptance Criteria or Standard Evidence of flaws attributable to PWSCC. Flaws (acceptable or not acceptable for continued service) attributed to PWSCC require re-inspection intervals each refueling outage. [1 0 CFR 50.55a(g)(6)(iiXDXS)]

L Reporting Requirements Report any indication of PWSCC flaws to the lSl Program Owner and Section Xl Owner for the 90 day report. A notice of indication shall be required.

J. Regulatory Basis 10 CFR 50.55a(g)(6XiiXD) "Augmented lSl requirements: Reactor vessel head inspections.

4.2 ASME Code Case N-722-1 4.2.1 AugmentedRequirementsSummary A. Source Document ASME CC N-722-1, 'Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 6001821182 Materials" B. Associated Document 10 CFR 50.55a(g)(6xiiXE) Augmented lSl requirements: Reactor coolant pressure boundary visual inspections.

C. Frequency ln accordance with CC N-722-1. (See Table 4-1 Alloy-600 Examination Schedule)

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Augmented Examinations 4.2.1 AugmentedRequirementsSummary(continued)

D. Purpose ldentification of the presence of pressure boundary leakage.

E. Scope Applicable CC N-722-1, ltem Numbers:

1. 815.80, RPV bottom mounted instrument penetrations

2. 815.90 RPV Hot leg nozzle-to-pipe connections; and

3. 815.95 RPV Cold leg nozzle-to-pipe connections.

NOTE

1. RPV Nozzle-to-safe end welds and Pressurizer Nozzle-to-safe end welds have received MSIP and Code Case N-722-1 no longer applies to these welds per 10 cFR 50.55a(gX6XiiXEXl ).

2. Head Adapter Welds require a VE examination once an interval per Code Case N-722-1 ltem 81 5.215 (cold leg full penetration welds on piping). A UT examination may be substituted per Note 5 of Code Case N-722-1 and Note 3 of Code Case N-770-'1.

F. Method

1. Direct VE of the bare metal surface, or alternatively,

2. VE performed with the insulation in place using remote visual examination equipment that provides resolution of the component metal surface equivalent to a bare metal direct VE.

3. The Visual Examination shall be performed by aVT-2 examiner who has completed at least four (4) hours of additional training in detection of borated water leakage from Alloy 6001821182 components and the resulting boric acid corrosion of adjacent ferritic steel components

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Augmented Examinations Augmented Requi rements Summary (continued)

4. lf a visual examination determines that leakage is occurring from a specific item listed in Table 1 of ASME Code Case N-722-1that is not exempted by the ASME Code, Section Xl, IWB-1220(b\\(1), additional actions must be performed to characterize the location, orientation, and length of a crack or cracks in Alloy 600 nozzle wrought material and location, orientation, and length of a crack or cracks in Alloy 821182 butt welds. Alternatively, licensees may replace the Alloy 6001821182 materials in all the components under the item number of the leaking component per 10 CFR 50.55a(g)(6)(iiXEX2).

lf the actions in paragraph (4) of this section determine that a flaw is circumferentially oriented and potentially a result of primary water stress corrosion cracking, licensees must perform non-visual NDE inspections of components that fall under that ASME Code Case N-722-1 item number.

The number of components inspected must equal or exceed the number of components found to be leaking under that item number. lf circumferential cracking is identified in the sample, non-visual NDE must be performed in the remaining components under that item number per 10 CFR 50.55a(s)(6Xii)(EX3).

lf ultrasonic examinations of butt welds are used to meet the NDE requirements in paragraphs (4) or (5) of this section, they must be performed using the appropriate supplement of Section Xl, Appendix Vlll, of the ASME BPV Code per 10 CFR 50.55a(gXOXiiXE)(4).

lndustry Code or Standard ASME Section X12007 Edition with the 2008 Addenda Acceptance Criteria or Standard Absence of evidence of pressure leakage.

Reporting Requirements Report any indication of PWSCC leakage to the lSl Program Owner and Section Xl Owner for the 90 day report. A notice of indication shall be required.

Regulatory Basis 1 0 cFR 50.s5a(gx6xii)(E) 5.

6.

G.

H.

l.

J.

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Augmented Examinations ASME Code Case N-770-l History Pressurizer The pressurizer spray, safety, relief and surge nozzles have been mitigated, using a mechanical stress improvement (MSIP) process. Inspections are required, post mitigation, in accordance with ASME Code Case (CC) N-770-1. Code Case N-770-1 defines these welds as Inspection ltem D, uncracked butt weld mitigated with stress improvements. These welds have no known cracks based on examination by personnel using procedures in conformance with qualified UT techniques that meet the requirements of Section -2500 of Code Case N-770-1, and that have been treated with an acceptable stress improvement process. Based on Table 1, examine all welds within 10 years following stress improvement application. Since multiple welds are mitigated in the same inspection period, examinations shall be spread throughout years 3 through 10 following application, similar to provisions in -2410(c).

Examine all welds no sooner than the third refueling outage and no later than 10 years following MSIP. Examination volumes that show no indication of cracking shall be placed into a population to be examined on a sample basis. Twenty-five percent of this population shall be added to the lSl Program in accordance with -

2410 and shall be examined once each inspection interval (10). lf more than one type of stress improvement is used, the population of each type of stress improved welds shall be established and 25o/o of each type shall be added to the lSl Program in accordance with -2410 and shall be examined once each inspection interval.

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Augmented Examinations ASME Code Case N-770-l (continued)

RPV Nozzle-to-Safe End Welds RV Hot Legs The reactor vessel hot leg nozzles have been mitigated, using a mechanical stress improvement (MSIP) process. lnspections are required, post mitigation, in accordance with ASME Code Case (CC) N-770-1. Code Case N-770-1 defines these welds as lnspection ltem D, uncracked butt weld mitigated with stress improvements. These welds have no known cracks based on examination by personnel using procedures in conformance with qualified UT techniques that meet the requirements of Section -2500 of Code Case N-770-1, and that have been treated with an acceptable stress improvement process. Based on Table 1, examine all welds within 10 years following stress improvement application. Since multiple welds are mitigated in the same inspection period, examinations shall be spread throughout years 3 through 10 following application, similar to provisions in -2410(c).

Examine all welds no sooner than the third refueling outage and no later than 10 years following MSIP. Examination volumes that show no indication of cracking shall be placed into a population to be examined on a sample basis. Twenty-five percent of this population shall be added to the lSl Program in accordance with -

2410 and shall be examined once each inspection interval (10). If more than one type of stress improvement is used, the population of each type of stress improved welds shall be established and 25o/o of each type shall be added to the lSl Program in accordance with -2410 and shall be examined once each inspection interval.

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Augmented Examinations ASME Code Case N-770-l (continued)

RV Gold Legs The reactor vessel cold leg nozzles have been mitigated, using a mechanical stress improvement (MSIP) process. lnspections are required, post mitigation, in accordance with ASME Code Case (CC) N-770-1. Code Case N-770-1 defines these welds as lnspection ltem D, uncracked butt weld mitigated with stress improvements. These welds have no known cracks based on examination by personnel using procedures in conformance with qualified UT techniques that meet the requirements of Section -2500 of Code Case N-770-1, and that have been treated with an acceptable stress improvement process. Based on Table 1, examine all welds within 10 years following stress improvement application. Since multiple welds are mitigated in the same inspection period, examinations shal! be spread throughout years 3 through 10 following application, similar to provisions in -2a10@).

Examine all welds no sooner than the third refueling outage and no later than 10 years following MSIP. Examination volumes that show no indication of cracking shall be placed into a population to be examined on a sample basis. Twenty-five percent of this population shall be added to the lSl Program in accordance with -

2410 and shall be examined once each inspection interval (10). lf more than one type of stress improvement is used, the population of each type of stress improved welds shall be established and 25o/o of each type shall be added to the lSl Program in accordance with -241A and shall be examined once each inspection interval.

Auxiliary Head Adapter Piping There are four auxiliary head adapters that originally were the nozzle connections for the upper head injection (UHl) system. Since these nozzles were originally part of a piping system rather than a CRDM aftachment, the dissimilar metal butt welds (B-J welds) are required to be inspected in accordance with ASME Code Case N-770-1, as prescribed by 10 CFR 50.55a(g)(6XiiXF). This includes the dissimilar metal nozzle-to pipe girth welds above the head penetration and the nozzle-to-head connections.

Code Case N-770-1 defines lnspection ltem B as Unmitigated butt weld at Cold Leg operating temperature > 525"F (274C) and < 580"F (304'C). These locations have been examined by personnel using procedures in conformance with qualified UT techniques and techniques that meet the requirements of CC N-770-1, Section -

2500. lnspection ltem B welds shall be volumetrically inspected every second inspection period not to exceed 7 years (See Note 1).

!n addition to this volumetric examination, ASME Code visual examinations, in accordance with CC N-770-1, are required to be performed on each cold leg nozzle once per interval.

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Augmented Exam inations NOTE Subsequent lnservice lnspection of Unmitigated Welds With lnside Surface Connected Planar Flaws A. lf planar surface flaws are detected in the butt weld/base metal inside surface, this weld shall be reexamined at the shorter frequency of every refueling outage or the frequency determined by the crack growth analysis of CC N-770-1, -3132.3.

B. This weld shall be subsequently examined at the frequency required by (a) unless mitigated.

4.3.1 Augmented Requirements Summary A. Source Document Code Case N-770-1, "Additional Examinations for PWR Pressure Retaining Welds in Class 1 Components Fabricated with Alloy 6001821182 Materials" B. Associated Documents

1. 10 CFR 50.55a(g)(6xii)(F) "Augmented lSl requirements: Examination requirements for Class 1 piping and vessel nozzle dissimilar-meta! butt welds"

2. WCAP-15988-NP

3. MRP 2003-039

4. NRC Bulletin 2004-01

5. ASME Section X!2007 Edition with the 2008 Addenda

6. CR 855584 and WBN PER 850540 (Head Adapter Piping)

C. Frequency As required by Code Case N-770-1. (See Table 4-1 Alloy-600 Examination Schedule)

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Augmented Exam inations Augmented Requirements Summary (continued)

Replace the first two sentences of Extent and Frequency of Examination for lnspection ltem D in Table 1 of Code Case N-770-1 with, "Examine all welds no sooner than the third refueling outage and no later than 10 years following stress improvement application." Replace the first two sentences of Note (11XbX2) in Code Case N-770-1 with, "The first examination following weld inlay, onlay, weld overlay, or stress improvement for lnspection Items D through K must be performed as specified." 10 CFR 50.55a(g)(6XiiXFXg)

Purpose Detection of unacceptable growth of known PWSCC Cracking Scope For identification of welds within the scope of this section of augmented examinations, see Table 4-1 below.

Method Ultrasonic Examination procedures and personnel qualification in accordance with Appendix Vlll of ASME Section Xl (2007 Edition with 2008 Addenda).

The axial examination coverage requirements of Paragraph-2500(c) may not be considered to be satisfied unless essentially 100 percent coverage is achieved. 10 CFR 50.55a(gX6XiiXFX4)

Visual (VE) examination performed by a W-2 examiner who has completed at least four (4) hours of additional training in detection of borated water leakage from Alloy 6001821182 components and the resulting boric acid corrosion of adjacent ferritic steel components.

Industry Code or Standard ASME Section Xl, 2007 Edition with the 2008 Addenda Acceptance Criteria or Standard Code Case N-770-1 -3000.

D.

E.

F.

G.

1.

2.

H.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0,1 0.3 Rev. 0001 Paqe 158 of 174 Appendix K (Page 18 of 33)

Augmented Examinations 4.3,1 Augmented Requirements Summary (continued)

For any mitigated weld whose volumetric examination detects growth of existing flaws in the required examination volume that exceed the previous IWB-3600 flaw evaluations or new flaws, a report summarizing the evaluation, along with inputs, methodologies, assumptions, and causes of the new flaw or flaw growth is to be provided to the NRC prior to the weld being placed in service other than modes 5 or 6. 10 CFR 50.55a(s)(6xii)(F)(6)

l.

ReportingRequirements Report any indication of PWSCC leakage or flaws to the ISI Program Owner and Section Xl Owner for the 90 day report. A notice of indication shall be required.

J. Regulatory Basis 10 CFR 50.55a(g)(6XiiXF) "Augmented lSl requirements: Examination requirements for Class 1 piping and nozzle dissimilar-metal butt welds"

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 159 of 174 Appendix K (Page 19 of 33) 4.3.1 Ausmented Requirements summary,*i::;nted Examinations Table 4-1 Alloy-600 weld examinaiion schedule (includes ASME Code and Augmented Examinations) 2nd lnt.

3'o lnt.

4th lnt.

RFOS RFO9 RFOlO RFO1 1 RFO12 RFO14 RFO15 RFO16 RFO17 RFO18 RFO19 RFO21 RF022 RF023 RFO24 RF025 RF026

$::!:iiillii i$iimI RPV top head (N-729-1)

Bare Metal Visual vT-2 VE VT-2 w-2 VE VT-2 w-2 VE w-2 vT-2 VE vT-2 Volumetric UT UT UT UT RPV bottom head (N-722-11 Bare Metal Visual w-2 VE VE VE VE VE VE Pressu rizer (N-770-1)

WP-1o-SE UT1 UT UT WP-1 1-SE UT1 UT WP-12-SE UT1 UT WP-13-SE UT1 UT UT WP-14.SE UT1 UT WP-,Is-SE UT1 UT

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3rd lnt.

4th lnt.

RFOS RFO9 RFO1 O RFO11 RFO12 RFO14 RFO15 RFO16 RFO17 RFO18 RFO19 RFO21 RF022 RF023 RFO24 RF025 RFo26 ffi RPV Cold Leg Noz (N-770-1)

N11-SE VE UT UT1 UT N12.SE VE UT UT1 UT N13.SE VE UT UT1 UT N14-SE VE UT UT1 UT RPV Hot Leq Noz (N-770-1)

N1s.SE UT UT VE VE UT1 UT N16-SE UT UT VE VE UT1 UT N17-SE UT UT VE VE UT1 UT N18.SE UT UT VE VE UT1 UT

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Augmented Examinations 4.3.1 AugmentedRequirementsSummary(continued)

Table 4-1 Alloy-600 weld examinAtion schedule (includes ASME Code and Augmented Examinations) 2nd lnt.

$$ffiWffii 3'd lnt.

4th lnt.

RFOS RFO9 RFO1 O RFO11 RFO12 lt::*-r,rilt:siG{!\\l itLT.liiillF.iiit',tli RFO14 RFO15 RFO16 RFO17 RFO18 RFO19 RFO21 RF022 RFO23 RFO24 RFO25 RF026 uHt (N-722-1 & N-77A-1 UPIAH-213-A UT2 UTA/E3 UT UPIAH-213-B UT2 UTruE3 UT UPIAH.213-C UT2 UTAIEs UT UPIAH-213-D UT2 UTA/E3 UT UPIAH-4.A UT2 UTA/E3 UT UPIAH-4-B UT2 UTA/E3 UT UPIAH-4-C UT2 UTA/E3 UT UPIAH.4-D UT2 UTruE3 UT Table Note 1: MSIP applld; 10 CFR 50.55a(gXGXiiXE) does not rquirs Code Case N-722-'l tor MSIP apptied wetds Table Note 2: UHI piping added to Alloy 600 Prcgram Teble Note 3: UT e)@m moEtlng Not 5 of Cod6 Case N-722-1 and Not 3 of Code Case N-77GI may b used in lieu of VE exam (UT is requirod by N-77G.1 ).

WBN Unit 1 UNIT l ASME SECTION XI ISI/NDE PROGRAM THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 162 of 174 4.3.1 Appendix K (Page 22 ot 331 Augmented Examinations Augmented Requirements Summary (continued)

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 163 of 174 5.0 5.1 5.1.1 Appendix K (Page 23 of 33)

Augmented Examinations EXAMINATION OF CLAD AREAS IN REACTOR VESSEL INLET NOZZLES AND AGCUMULATOR TANK # 3 Responsible Organization Mechanical/Nuclear Engineering Reactor Pressure Vessel Perform a visual examination on the ground clad areas in Loop 2 and 3 inlet nozzles during the 10-year lSl reactor vessel examination.

History Prior to plant start-up, one area in Loop 2 inlet nozzle and two areas in Loop 3 inlet nozzle had the stainless steel cladding removed to validate flaw depth sizing. After cladding removal and validation of the flaw depth sizing, a metallurgical evaluation recommended the three areas without cladding be left in an unclad condition. A summary of the information concerning this issue is discussed in the July 30, 2003 letter to the NRC (reference T04 030730 825).

Augmented Requ irements Summary A. Source Document Summary of the information concerning this issue is discussed in the July 30, 2003 letter to the NRC (reference T04 030730 825).

Associated Document

1. Westinghouse Report WAT-D-4494

2. NRC's 1982 Safety Evaluation Report Frequency Perform during the 10-year lS! reactor vessel examination (See Table.)

Purpose To assess changes in the one area in Loop 2 inlet nozzle and two areas in Loop 3 inlet nozzle where the cladding has been ground.

Scope B.

C.

D.

E.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paoe 164 of 174 Appendix K (Page 24 of 331 Augmented Examinations 5.1.1 Augmented Requirements Summary(continued)

Ground clad areas in Loop 2 and 3 reactor vessel inlet nozzles. These areas should be specifically noted in the scope of inspection with the contract inspector.

F. Method VT-3 Visual Examination performed remotely. Al! equipment, personnel, and processes are per Code Category B-N-1.

G. lndustry Code or Standard ASME Section Xl2007 Edition with 2008 Addenda H. Acceptance Criteria or Standard During the remote visual portion of the reactor vessel 10-year lSl inspection, specific attention will be given to the unclad areas in the Loops 2 and 3 inlet nozzles for any evidence of wall deterioration.

l.

ReportingRequirements The examination results will not require a special report but will be included as part of the reactor vessel 1O-year inspection report. Provide a report of examination results to Mechanical/Nuclear Engineering for information/evaluation as required.

J. Regulatory Basis Summary of the information concerning this issue is discussed in the July 30, 2003 letter to the NRC (reference T04 030730 825),

5.2 Accumulator Tank #3 Perform an ultrasonic examination of clad cracking areas in the bottom head of accumulator tank #3 beginning in the cycle 6 refueling outage and every other refueling outage thereafter.

History

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 165 of 174 Appendix K (Page 25 of 33)

Augmented Examinations 5.2 Accumulator Tank #3 (continued)

Flaw indications in the cladding of the safety injection accumulator tank #3 were identified and documented in PER WBPER920252 dated November 2,1992.

Attempts to repair the indications were made by removing the cladding containing the indications and replacing it with weld metal. However, excavation to remove the indications and shrinkage stresses from welding continually generated new indications in the sensitized cladding in adjacent areas previously free of indications.

After a review of this information as documented in PER 03-0129850-000, mechanical engineering has recommended the areas described below be examined to determine that the vessel wall is not deteriorating as a result of the cladding cracks.

5.2.1 Augmented RequirementsSummary A. Source Document PER 03-0129850-000 B. Associated Document PER WBPER92O252 C. Frequency Every other Refueling Outage D. Purpose To determine that the vessel wall is not deteriorating as a result of the cladding cracks.

E. Scope Areas a, b, c, and d as identified in Table 5-2 and sketch.

F. Method Ultrasonic Examination. All inspection areas are on the orange peel plate section with the 3/4" sample nozzle. Area "a" is accessed outside the tank support ring and remaining areas accessed under the support ring.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 166 of 174 Appendix K (Page 26 of 33)

Augmented Examinations 5.2.1 AugmentedRequirementsSummary(continued)

G. lndustry Code or Standard UT Thickness examination per ASME Section V H. Acceptance Criteria or Standard Assess the identified areas of the Accumulator tank for evidence wall thinning

l.

ReportingRequirements The examination results will not require a special report but will be included as part of the refueling outage lSl inspection report. A report of examination results will be provided to Mechanical/Nuclear Engineering for information/evaluation, as required.

J. Regulatory Basis Table 5-l: Clad areas in RPV nozzles and #3 Accumulator Tank 2nd lnt.

3'd lnt.

4'h tnt.

RFO1 O RFO1 1 RFO12 RFO14 RFO15 RFO16 RFO17 RFO18 RFO19 RFO21 RFO22 RPV Nozzles VT VT Acc. Tank 3 UT UT UT UT UT UT

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Augmented Examinations Augmented Requirements Summary (continued)

TI[I(HE.TFIJIIE The examination should be performed in accordance with NDE procedure N-UT-24. The results shall be forwarded to mechanical engineering for evaluation. Report any indication of cracking to the lSl Program Owner for the lSl Fina! Report. A Notification of lndication Report shall be required.

Table 5-2: Examination Areas for Accumulator Tank #3 AREA DESCRIPTION a

2" wide band below the orange peel plate to shell weld b

2" x 10" area to the left of the vertical orange peel plate weld c

2" x 15" area above the horizontal orange peel plate to bottom head dollar plate weld d

6" radius area around the 314" sample nozzle in the bottom head ffiPE-FLTTE EOITTffiffiFLJTTE

WBN Unit 1 UNIT l ASME PROGRAM SECTION X! ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 168 of 174 Appendix K (Page 28 of 33)

Augmented Examinations 6.0 MATERIALS RELIABILITY PROGRAM MANAGEMENT OF THERMAL FATIGUE IN NORMALLY STAGNANT NON.ISOLABLE REACTOR COOLANT SYSTEM BRANCH LINES (MRP-146)

Five examination locations were selected for MRP-146. MRP-146 requires inspections of small-bore piping on branches of reactor coolant system piping. At Watts Bar, five such locations exist.

Responsible Organization: Civil Engineering 6.1.1 AugmentedRequirementsSummary A. Source Document:

1. NRC Bulletin 88-08 (Farley) and NRC Bulleting 88-08 Supplement 1 (Tihange) - Thermal Stresses in Piping Connected to Reactor Cooling Systems

2. NRC Bulletin 88 Pressurizer Surge Line Thermal Stratification

3. MRP-146 - Materials Reliability Program: Management of Thermal Fatigue in Normally Stagnant Non-lsolable Reactor Coolant System Branch Lines B. Associated Document None.

C. Frequency:

The Crossover Drains have an inspection frequency of every odd number refueling outage.

The Boron lnjection Lines have an inspection frequency of every outage.

D. Scope:

1. Three Crossover Drains:

RCF-B-T001-003 (Loop 1) or MRP-146-DR-1 RCF-B-T002-003 (Loop 2) or MRP-146-DR-2 RCF-B-T004-018 (Loop 4) or MRP-1 46-DR-4

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 169 of 174 6.1.1 Appendix K (Page 29 of 33)

Augmented Examinations Augmented Requirements Summary (continued)

(Note: ln the Risk-lnformed lSl application, these welds were additionally selected for examination. The MRP examinations are schedule under the MRP Number and the Rl-lSl Examinations are schedule under the RCF Number.)

2. Two Boron injection lines:

SIF-B-T058-01 (Loop 1 ) or MRP-1 46-CL-1 SIF-B-T1 1 3-01 (Loop 2) or MRP-146-CL-2 (Note: In the Risk-lnformed lSl application, these welds were additionally selected for examination. The MRP examinations are schedule under the MRP Number and the Rl-lsl Examinations are schedule under the SIF Number. The Boron lnjection Lines were examined due to the insufficient detection of leakage by acoustic monitoring.)

Method:

Ultrasonic Examination to the requirements of ASME Section Xl Examinations of circumferential butt welds shall be performed by the ultrasonic (UT) examination method. The extent of examination shall include the lower one-third volume of the welds and base metal adjacent to each weld for a distance of two wall thicknesses where accessible (fittings, elbow intrados, and valves may prevent full circumference examination).

lndustry Code or Standard:

ASME Section Xl,2007 Edition with the 2008 Addenda MRP-146 - Materials Reliability Program for Management of Thermal Fatigue in Normally Stagnant Non-lsolable Reactor Coolant System Branch Lines, Revision 1 G. Acceptance Criteria or Standard Circumferential Butt Welds and fittings - ASME Section Xl2007 Edition with 20OB Addenda, IWB-3514 or IWC-3514 for Class 1 and 2 welds, respectively E.

F.

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Augmented Examinations 6.1.1 AugmentedRequirementsSummary(continued)

H. Reporting Requirements Report any indication of cracking to the lSl Program Owner for the lSl Final Report. A Notification of lndication Report shall be required

l.

Regulatory Basis:

1. NRC Bulletin 88-08 (Farley) and NRC Bulletin 88-08 Supplement 1 (Tihange) - Thermal Stresses in Piping Connected to Reactor Cooling Systems

2. NRC Bulletin 88-011 - Pressurizer Surge Line Thermal Stratification

WBN Unit 1 UNIT l ASME PROGRAM SECTION X! ISI/NDE THIRD INTERVAL 1-TRl-0-1 0.3 Rev. 0001 Paqe 171 of 174 7.0 7.1.1 Appendix K (Page 31 of 33)

Augmented Examinations STEAM GENERATOR LATERAL SUPPORT EXAMINATION (WAT-D-l2064)

Westinghouse has recommended inspecting the SG upper lateral support splice bolts each outage via WAT-D-12064.

Responsible Organization: Civil Engineering History During the April 2014 Watts Bar Unit 1 outage, a visual inspection was conducted on the bolts in the splice joints on the steam generator upper lateral support, which identified multiple loose bolts and several broken bolts. Subsequently Westinghouse was provided with the inspection report results for SG 2 and SG 3 with a request for recommendations, which included further inspection activity. The inspection recommendations of Westinghouse are included in the requirements of the following augmented program.

Augmented Requirements Summary A. Source Document Westinghouse Engineering Letter WAT-D-12064, SG Upper Lateral Support Splice Bolts, dated April 1 1,2014 B. Associated Document TVA Visual Examination ReportVT-14-192 (SG2 Upper Support)

TVA Visual Examination Report VT-14-193 (SG3 Upper Support)

C. Frequency Description Exam Method Number of Components

%Tobe examined Number to be Examined lnspection Frequency lSl Drawing Class 2 Steam Generator Lateral Support Bolting w-3 4SGs/1 support each 100o/o 4SG suppon Every Outage cHM-2660-C

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paoe 172 of 174 Appendix K (Page 32 of 33)

Augmented Examinations 7.1.1 Augmented Requirements Summary(continued)

D.

Purpose:

To verify that each splice bolt is sufficiently tight to bring the connection plates into "firm contact" or "snug tight." "Snug-tight" is defined as the "full effort of an ironworker using an ordinary spud wrench." !t does not include "pumping" or "bouncing" to further tighten the bolts once "full effort tightening" has been achieved. Nor does it include obtaining a"114 turn" once the bolt is hand tight.

To verify the associated locking device is properly in place and has not been damaged.

E. Scope Each bolt associated with the splice joints of each steam generator upper lateral support.

F. Method:

VT-3 visual examination of the bolting without disassembly and associated joint.

Verification of the "snug tight" condition by attempted tightening of the bolt with a spud wrench or other similar tool.

G. lndustry Code or Standard ASME Section Xl2007 with the 2008 Addenda. This examination of the splice bolts is not a requirement of the ASME Section X!; however, the examination of the bolted joint in compliance with the ASME Section XI Code forms the basis for one component of acceptance for the bolted connection.

H. Acceptance Criteria or Standard:

ASME Section Xl, IWF-3410 Verification of "snug tight" tension of the bolt.

WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 173 of 174 7.1.1 Appendix K (Page 33 of 33)

Augmented Exam inations Augmented Requirements Summary (continued)

Reporting Requirements An inspection report detailing the results of examination of each bolt shall be prepared and provided to Civil Engineering. The report will be by bolt and provide descriptions of any conditions that do not satisfy the requirements of IWF-3410. lf the bolt is not "snug tight", it shall be returned to "snug tight" condition per this procedure (See "Purpose" paragraph above). The extent of rotation of the bolt shall be recorded and reported as part of the report. Report any indication of cracking to the lSl Program Owner. A Notification of lndication Report shall be required Regulatory Basis None l.

J.

7 WBN Unit 1 UNIT l ASME PROGRAM SECTION XI ISI/NDE THIRD INTERVAL 1-TRI-0-1 0.3 Rev. 0001 Paqe 174 of 174 Source Notes (Page 1 of 1)

Source Note Source Document Summarv 1

NCO 920032003 Commitment to include RCP Flywheel inspection in lSl program 2

WH INFOGRAM 95-12A Consider/develop plans for long term inspection of Guide Tube Support Pins 3

PER SQ 961154 Safety lnjection System Weld Flaw

Person / Time
ML17212A550
Site:	Watts Bar (NPF-090)
Issue date:	07/31/2017
From:	Simmons P Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17212A550 (185)
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ML17212A550

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Subject:

Enclosures:

1.0 INTRODUCTION

Purpose:

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