ML070390010

Updated Inservice Inspection Program for Second 10-Year Interval and Requests for Relief Nos. PDI-2, PDI-4, and SNBR-1

ML070390010
Person / Time
Site:	Watts Bar
Issue date:	02/07/2007
From:	James Smith Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PDI-2, PDI-4, SNBR-1
Download: ML070390010 (150)

Text

February 7, 2007 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

In the Matter of ) Docket No. 50-390 Tennessee Valley Authority )

WATTS BAR NUCLEAR PLANT (WBN) UNIT 1 - UPDATED INSERVICE INSPECTION (ISI) PROGRAM FOR SECOND 10-YEAR INTERVAL AND REQUESTS FOR RELIEF NOS. PDI-2, PDI-4 AND SNBR-1

References:

1) TVA letter to NRC dated August 23, 2001, Browns Ferry Nuclear Plant (BFN), Units 2 and 3, Sequoyah Nuclear Plant (SQN), Units 1 and 2, and Watts Bar Nuclear Plant (WBN),

Unit 1 - American Society of Mechanical Engineers (ASME)Section XI, Inservice Inspection (ISI) Program Request for Relief -

No. PDI-2 Replacement Submittal

2) NRC letter to TVA dated September 19, 2001, Browns Ferry Nuclear Plant, Units 2 and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Unit 1 - American Society of Mechanical EngineersSection XI, Inservice Inspection Program Request for Relief Nos. PDI-1 and PDI-2 (TAC Nos. MB1260, MB1263-1268)

3) TVA letter to NRC dated February 23, 2005, Browns Ferry Nuclear Plant (BFN), Units 2 and 3, Sequoyah Nuclear Plant (SQN), Units 1 and 2, and Watts Bar Nuclear Plant (WBN),

Unit 1 - American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Relief Request to Use ASME Section XI, Appendix VIII and Performance Demonstration Initiative (PDI) for Reactor Vessel Flange Welds-PDI-4

U.S. Nuclear Regulatory Commission Page 2 February 7, 2007

4) NRC Letter to TVA dated August 2, 2005, Browns Ferry Nuclear Plant Units 1, 2 and 3, Sequoyah Nuclear Plant Units 1 and 2, and Watts Bar Nuclear Plant Unit 1 - Inservice Inspection Program Relief Request PDI-4 (TAC Nos. MC6232, MC6233, MC6234, MC6235, MC6236, and MC6237)

5) TVA letter to NRC dated February 7, 1996, Watts Bar Nuclear Plant (WBN) - 10 CFR 50.55(a)(3) Request for Relief from Certain American Society of Mechanical Engineers (ASME)Section XI Requirements for Snubbers

6) NRC letter to TVA dated August 11, 1997, Evaluation of Inservice Inspection Program Snubber Relief Request for the Watts Bar Nuclear Plant (TAC NO. M94762)

Pursuant to 10 CFR 50.55(a)(3)(i), TVA is submitting three relief requests for WBNs second 10-year ISI interval. contains relief request PDI-2 which proposes an alternative to ASME Section XI 2001 Edition through the 2003 Addenda, Examination Category B-D, Full Penetration Welded Nozzles in Vessels - Inspection Program B, Items No. B3.90, Examination Requirements/Figures IWB-2500-7, for the examination volumes of the Class 1 reactor vessel pressure retaining nozzle-to-vessel welds. TVA submitted a similar request for relief for the WBN first 10-year ISI interval (Reference 1) which was approved in the Reference 2 letter. contains relief request PDI-4 which proposes an alternative to ASME Section XI, paragraph IWA-2232 of the ASME Section XI 2001 Edition through the 2003 Addenda, for use of Appendix VIII and Performance Demonstration Initiative (PDI) methodologies for performance of the ultrasonic examination of reactor pressure vessel shell-to-flange welds in lieu of the requirement of Appendix I and the associated Article 4 of ASME Section V. TVA Submitted a similar request for relief for the WBN first 10-year ISI interval (Reference 3) which was approved in the Reference 4 letter.

U.S. Nuclear Regulatory Commission Page 3 February 7, 2007 contains relief request SNBR-1 which proposes an alternative to the ASME Section XI requirements related to examination and testing of snubbers. TVA proposes to continue to perform the snubber examination and testing plans currently defined in the WBN Unit 1 Technical Requirements Manual (TR 3.7.3). The proposed relief is a continuation of the previously approved relief request from WBNs first 10-year inspection interval. TVA Submitted a similar request for relief for the WBN first 10-year ISI interval (Reference 5) which was approved in the Reference 6 letter. provides an information copy of WBNs updated ISI program for the second 10-year inspection interval. This program has been updated to comply with the 2001 Edition and the 2003 Addenda of the ASME Section XI Code. Pursuant to 10 CFR 50.55a(g)(4)(ii), ISI programs are required to be updated every 10 years to meet the requirements of the latest NRC approved Edition and Addenda of ASME Section XI which is in effect 12 months prior to the start of the next 120-month inspection interval. TVA plans to submit future requests for relief for WBNs ISI program as ISIs are performed and limitations identified during WBNs second 10-year inspection interval.

WBN Unit 1 will start the second 10-year ISI interval on May 27, 2007. TVA will provide the new Request for Alternative for the WBN Unit 1 second 10-year ISI interval Risk-Informed Inservice Inspection (RI-ISI) program by a separate transmittal. The second ten-year ISI program submitted by this letter does not include the RI-ISI methodology/results.

There are no regulatory commitments associated with this submittal. If you have any questions concerning this matter, please call me at (423) 365-1824.

Sincerely, Original signed by J. D. Smith Manager, Site Licensing and Industry Affairs (Acting)

Enclosure cc: See Page 4

U.S. Nuclear Regulatory Commission Page 4 February 7, 2007 Enclosures cc (Enclosures):

NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. Brendan T. Moroney, Project Manager U.S. Nuclear Regulatory Commission MS 08G9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303

U.S. Nuclear Regulatory Commission Page 5 February 7, 2007 JDS:BJT Enclosures cc (Enclosures):

NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. Brendan T. Moroney, Senior Project Manager U.S. Nuclear Regulatory Commission MS 08G9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 A. S. Bhatnagar, LP 6A-C R. H. Bryan, BR 4X-C J. E. Hinman, ADM 1B-WBN A. M. Hinson, EQB 2A-WBN M. J. Lorek, MOB 2R-WBN M. T. McFadden, ADM 1Q-WBN NSRB Support, LP 5M-C (including Advisors)

J. E. Semelsberger, EQB 2W-WBN K. W. Singer, LP 6A-C M. D. Skaggs, ADM 1V-WBN E. J. Vigluicci, WT 6A-K B. A. Wetzel, BR 4X-C K. W. Whittenburg, SP2B-C Sequoyah Licensing Files, OPS 4C-SQN EDMS, WT 3B-K M:\SUBMIT\

ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN)

UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

SECTION XI INSERVICE INSPECTION (ISI) PROGRAM SECOND TEN-YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF PDI-2 TVA requests approval for an alternative to ASME Section XI 2001 Edition through the 2003 Addenda, for the Second 10-year interval at Watts Bar Unit 1. Specifically, Examination Category B-D, Full Penetration Welded Nozzles in Vessels - Inspection Program B, Items No. B3.90, Examination Requirements/Figures IWB-2500-7, requiring the examination coverage of 1/2t beyond the edge of the weld, change to 1/2 beyond the edge of the weld.

EXECUTIVE

SUMMARY

Watts Bar Unit 1 ISI program requirements for the examination volumes of the Class 1 reactor vessel pressure-retaining nozzle-to-vessel welds (Examination Category B-D, Items No. B3.90 -

Inspection Program B) are shown in Figures IWB-2500-7(a) through (b) of the ASME Section XI Code 2001 Edition, 2003 Addenda.

These figures require that licensees perform examinations of the weld volumes and the adjacent vessel or nozzle base metal material regions equivalent to one-half (1/2) the vessel shell thickness beyond the end of the welds boundary.

The extent of the examination volume for a given nozzle-to-vessel weld dictates the exam time and the amount of radiation dose exposure of the personnel involved. Historical improvements in the ultrasonic examination techniques and the qualifications of the examiners in accordance with the Section XI Appendix VIII has reduced the necessity of having the nozzle-to-vessel weld exam volumes be as large as currently required in Figures IWB-2500-7 (a) through (d). TVA proposes to reduce the required examination volumes extent (next to the widest part of the weld) from one-half of the shell thickness to one-half (1/2) inch beyond the boundary of the weld.

The reduction of the exam volume in lieu of the current ASME Section XI Code required examination volumes will result in a reduction of examination time and the associated examination personnel radiation exposure while maintaining an acceptable level of quality and safety. Except for the proposed reduced E1-1

examination volumes, TVA will continue to perform the volumetric examinations in accordance with the other specific aspects and requirements of the ASME Code for these exams. Accordingly, pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested to use the reduced examination volumes in lieu of the requirements shown in ASME Section XI Figures, IWB-2500-7 (a) through (d).

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

ASME Class 1, Reactor Pressure Vessel (RPV) Pressure-retaining Nozzle-To-Vessel welds.

ASME SECTION XI CODE EDITION/ADDENDA:

The applicable ASME Section XI Code of Record for the second Watts Bar Unit 1 inservice inspection interval is the 2001 Edition with addenda through the 2003 Addenda with amendments specified in 10CFR50.55a.

CODE REQUIREMENTS:

In accordance with the Watts Bar Unit 1 ISI Program, the ASME Section XI Code-of-Record rules for Inservice Inspection of Nuclear Power Plant Components; the requirements for nozzle-to-vessel weld examination volume shown in Section XI, Subsection IWB, Examination Category B-D Full Penetration Welds of Nozzles in Vessels - Inspection Program B, Code Item Number B3.90, with Figures IWB-2500-7(a) and IWB-2500-7(b) are applicable.

REQUIREMENT FROM WHICH RELIEF IS REQUESTED:

The specific Code requirement from which relief is requested is the requirement to perform the volumetric examination of the indicated nozzle-to-vessel welds in accordance with the examination volume requirements shown in ASME Section XI Subsection IWB, Figures IWB-2500-7(a) and (b). Pursuant to 10 CFR 50.55a(a)(3)(i), relief is requested to perform the Code examination on a reduced volume of 1/2 inch beyond the widest part of the boundary of the deposited weld material in lieu of the requirements of ASME Section XI Figures IWB-2500-7(a) and IWB-2500-7(b). When performing the examinations of nozzle-to-vessel welds, TVA will comply with the special requirements imposed in 10 CFR 50.55a(b)(2)(xv)(K)(1) and 10 CFR 50.55a(b)(2)(xv)(K)(2).

These requirements dictate that the examination scanning processes must also be performed in such a manner to detect flaws oriented axially with the nozzle.

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BASIS FOR RELIEF:

Inservice examination of selected Reactor Pressure Vessel (RPV) nozzle-to-vessel welds at TVA nuclear plants is currently performed in accordance with the requirements of 10 CFR 50.55a, plant Technical Requirements, and the associated ASME Section XI ISI Program Codes-of-Record Editions and Addenda of the ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components. The 2001 Edition through the 2003 Addenda of ASME Section XI invokes the examination volume requirements of Figures IWB-2500-7(a) and IWB-2500-7(b).

Under the Appendix VIII procedures the required examinations will be performed using procedures which provide for a rigorous methodology for ultrasonic examinations.

JUSTIFICATION FOR GRANTING RELIEF:

The examination volume required by IWB-2500-7(a) and (b) for the reactor vessel pressure retaining nozzle-to-vessel welds extends far beyond the weld and the heat effected zones into the base metal, and is unnecessarily large. This extends examination time significantly, increases the radiation exposure of exam support personnel, and results in no net increase in safety; as the additional area being examined is a base-metal region of the reactor vessel shell or nozzle wall areas where industry experience has shown service-induced cracks are not prone to occurring. In addition, these regions have been extensively examined during the fabrication and installation periods before the vessels were put in service and during the inservice examinations already performed.

The reduction of UT examination volumes adjacent to the widest part of the weld from one-half of the vessel wall thickness to one-half (1/2) inch beyond the weld boundary eliminates base metal material volume to be examined that was extensively examined during construction and preservice examinations, where applicable; and, eliminates areas which are not located in the high-stressed areas of the weld geometry. The high-stressed areas of the various nozzle-to-vessel weld configurations and areas where flaws are most likely to initiate are adequately addressed and contained in the examination volume defined by the area 1/2 inch beyond the weld boundary.

In addition, use of these proposed examination boundaries will be conducted in conjunction with TVAs programmatic implementation of the mandated use of ASME Section XI, Appendix VIII. Watts Bar Unit 1 will implement these requirements in accordance with the requirements shown in ASME Section XI Appendix VIII as required in paragraphs 10 CFR 50.55a(b)(2)(xiv), (xv), (xvi) and (xxiv);

and in 10 CFR 50.55a(g)(6)(ii)(C). These procedures will ensure E1-3

that the performance-based UT methodologies used and the techniques will be qualified and examination personnel will be certified by a performance demonstration.

The use of the reduced examination volumes in lieu of the identified ASME Section XI referenced requirements could reduce on-vessel examination time and a reduction of examination support personnel radiation exposure. The personnel radiation exposure is dependent upon the choice of RPV examination equipment (i.e.

automated versus manual) and by the degree of plant RPV contamination and/or decontamination conducted prior to the exam.

In conclusion, use of the reduced examination volume requirements in conjunction with the application of the Appendix VIII implementing PDI program will provide sufficient assurance that RPV nozzle-to-vessel welds have remained free of service induced flaws or identify such flaws prior to failure. The application of the PDI techniques will enhance quality of the UT examinations and ensure plant safety and pressure boundary reliability.

Therefore, the proposed alternative provides for an acceptable level of quality and safety and, pursuant to 10 CFR 50.55a(a)(3)(i), relief to use the reduced examination volumes may be granted.

ALTERNATIVE EXAMINATIONS:

TVA will perform the examinations of the RPV nozzle-to-vessel welds as follows:

Ultrasonic examinations of the RPV nozzle-to-vessel welds in accordance with the requirements of ASME Section XI Appendix VIII with examination volumes to include regions up to 1/2 inch beyond the weld boundary.

In accordance with the requirements shown in ASME Section XI Appendix VIII of the 2001 Edition, as amended by the Final Rule and as required in paragraphs 10 CFR 50.55a(b)(2)(xiv), (xv), and (xvi); and in 10 CFR 50.55a(g)(6)(ii)(C) through the use of the EPRI PDI program document, PDI Program Description, as allowed in the discussion on the Final Rule published in the Federal Register.

Continued periodic system pressure tests of the RPV per ASME Section XI requirements of Table IWB-2500-1, for Category B-P items.

IMPLEMENTATION SCHEDULE:

Upon approval by the NRC Staff, TVA will implement the provisions of this request during the Second Ten-Year Inservice Inspection E1-4

Interval for Watts Bar Unit 1 and conduct the next scheduled RPV nozzle-to-vessel weld examinations accordingly.

PRECEDENTS Similar relief has been submitted by TVA for Browns Ferry Units 2 and 3, Sequoyah Units 1 and 2, and Watts Bar Unit 1 power plants by letters dated February 23, July 9, and August 23, 2001. TVAs request for relief was subsequently approved by NRC letter dated September 19, 2001.

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Enclosure 2 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN)

UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

SECTION XI INSERVICE INSPECTION (ISI) PROGRAM SECOND TEN-YEAR INSERVICE INSPECTION INTERVAL REQUEST FOR RELIEF PDI-4 TVA requests approval for an alternative to ASME Section XI, paragraph IWA-2232 of the ASME Section XI 2001 Edition through the 2003 Addenda, for the second 10-year interval at Watts Bar Nuclear (WBN) Unit 1. Specifically, for use of Appendix VIII and Performance Demonstration Initiative (PDI) methodologies for performance of the ultrasonic examination of reactor pressure vessel shell-to-flange welds in lieu of the requirement of Appendix I and the associated Article 4, ASME Section V EXECUTIVE

SUMMARY

In accordance with 10 CFR 50.55a(a)(3)(i), TVA is requesting relief from the specific requirements of performing the volumetric examination of the reactor pressure vessel (RPV) circumferential shell-to-flange weld at Watts Bar Unit 1 in accordance with the requirement of Appendix I of Section XI. In addition, the guidance of Regulatory Guide (RG) 1.150, Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations, Revision 1, was historically applied.

In lieu of the requirements of Appendix I and its associated sub-requirements of Article 4 of Section V, WBN Unit 1 will use the techniques, personnel, and equipment qualified to meet the requirements of ASME Section XI Appendix VIII, Supplements 4 and 6 of the 2001 Edition through the 2003 Addenda, as administered by the Electric Power Research Institutes (EPRI)

Performance Demonstration Initiative (PDI) processes. WBN plans to use the proposed alternative during the next regularly scheduled RPV examinations to be performed at or near the end of the Second 10-year ISI Program interval. This proposed alternative represents the best available methodology in qualification of equipment and personnel performing ultrasonic examinations and uses an examination process that has provided and will provide the highest practical quality and greatest amount of coverage for the performance of the shell-to-flange weld examinations. As such, the proposed alternative methodology provides an acceptable level of quality and safety. In addition, the approval of this relief results in savings in the cost of performing the examinations, with not having to incorporate the use of two different sets of examination equipment, and also E2-1

results in lower personnel radiation exposure from not having to use a different methodology for the shell-to-flange weld.

Note that this request for relief is similar to the request granted during the First 10 Year Interval submitted initially in a letter from TVA to the NRC, dated February 23, 2005 and approved by the Staff in a letter dated August 2, 2005 (Ref.

ML051730487).

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

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

APPLICABLE CODE EDITION AND ADDENDA FOR THE GIVEN EXAM The applicable ASME Section XI Code Edition and Addenda of Record for Watts Bar Unit 1 second inservice inspection interval is the 2001 Edition with addenda through the 2003 Addenda with applicable amendments from 10CFR50.55a.

CODE REQUIREMENTS FROM WHICH RELIEF IS REQUESTED:

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

Further, in accordance with Appendix I, paragraph I-2110(b)

Ultrasonic examination of reactor vessel-to-flange welds, closure head-to-flange welds, and integral attachment welds shall be conducted in accordance with Article 4 of Section V, except that alternative examination beam angles may be used.

RELIEF REQUESTED:

Pursuant to 10 CFR 50.55a(a)(3)(i), TVA requests relief from performing the designated vessel shell-to-flange weld examination in accordance with the requirements of ASME Section XI, paragraph IWA-2232, Appendix I, and the associated Article 4 of Section V methodology in accordance with paragraph I-2110(b).

BASIS FOR RELIEF:

In accordance with ASME Section XI, Subarticle IWA-2232, TVA is required to perform ultrasonic examinations (UT) of the RPV upper E2-2

shell-to-flange welds using Section XI, Appendix I, which in turn requires the use of the NDE methodologies and processes of ASME Section V, Article 4. In addition, the guidance of RG-1.150, Revision 1, was historically applied. The above listed welds are the only circumferential shell welds in the RPV that are not examined in accordance with the requirements of ASME Section XI, Appendix VIII, as mandated in 10 CFR 50.55a with the issuance of the rule change shown in the Federal Register Notice 64 FR 51370, dated September 22, 1999. This rule change mandated the use of ASME Section XI, Appendix VIII, Supplements 4 and 6 for the conduct of RPV examinations. It has been stated in EPRI PDI coordination meetings between the PDI committee members and the NRC Staff representatives that the NRC Staff expectations are that licensees should submit requests for relief to use the more technically advanced Appendix VIII/PDI processes for the shell-to-flange weld exams, in lieu of the Section XI Appendix I and its associated Section V, Article 4 processes.

PROPOSED ALTERNATIVES TVA proposes to use the procedures, personnel, and equipment qualified to meet the requirements of ASME Section XI Appendix VIII, Supplements 4 and 6 as administered by the Electric Power Research Institutes (EPRI) Performance Demonstration Initiative (PDI), to conduct the required vessel-to-flange weld examinations.

JUSTIFICATION FOR GRANTING RELIEF:

ASME Section V, Article 4, describes the required techniques to be used for the UT of welds in ferretic pressure vessels with wall thicknesses greater than 2 inches. The techniques were first published in ASME Section V in the 1974 Edition, summer 1975 Addenda. The calibration techniques, recording criteria and flaw sizing methods are based upon the use of a distance-amplitude-correction curve (DAC) derived from machined reflectors in a basic calibration block. UT performed in accordance with Section V, Article 4, used recording thresholds of 50 percent DAC for the outer 80 percent of the required examination volume and 20 percent DAC from the clad/base metal interface to the inner 20 percent margin of the examination volume. Indications detected in the designated exam volume portions, with amplitudes below these thresholds, were therefore not required to be recorded.

Use of the Appendix VIII/PDI processes would enhance the quality of the examination results reported because the detection sensitivity is more conservative and the procedure requires the examiner to evaluate all indications determined to be flaws regardless of their associated amplitude. The recording thresholds in Section V, Article 4, requirements and in the guidelines of RG-1.150, Revision 1, are generic and somewhat E2-3

arbitrary and do not take into consideration such factors as flaw orientation, which can influence the amplitude of UT responses.

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

UT performed in accordance with the Section V, Article 4 processes requires the use of beam angles of 0o, 45o, 60o, and 70o with recording criteria that precipitates equipment changes.

Having to perform these process changes is time consuming and results in increased radiation exposure for the examination personnel. Having to comply with the specific ASME Section XI, Appendix I requirements for the RPV circumferential shell-to-flange weld, when the data is obtained using a less technically advanced process, results in an examination that does not provide a compensating increase in quality and safety for the higher costs and personnel exposures involved.

For future RPV shell-to-flange weld examinations TVA does not anticipate any less coverage than the required minimum of 90 percent of coverage. However, if any such limitations are encountered during the conduct of the examinations, separate individual relief requests will be submitted, as needed.

Procedures, equipment, and personnel qualified through the Appendix VIII, Supplements 4 and 6 PDI programs have shown to have a high probability of detection of flaws and are generally considered superior to the techniques employed earlier for RPV examinations. This results in increased reliability of RPV inspections and conditions where an acceptable level of quality and safety is provided with the proposed alternative methodologies. Accordingly, approval of this alternative evaluation process is requested pursuant to 10 CFR 50.55a(a)(3)(i).

IMPLEMENTATION SCHEDULE AND DURATION:

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Upon approval by the NRC staff, TVA will implement the provisions of this request during the second ten-year inservice inspection interval for Watts Bar Unit 1.

PRECEDENTS Note that this request for relief is similar to the request granted during the first 10-year interval submitted initially in a letter from TVA to the NRC, dated February 23, 2005 and approved by the Staff in a letter dated August 2, 2005 (Ref. ML051730487).

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Enclosure 3 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT (WBN)

UNIT 1 AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

SECTION XI INSERVICE INSPECTION (ISI) PROGRAM SECOND TEN-YEAR INSERVICE INSPECTION INTERVAL SNUBBER REQUEST FOR RELIEF SNBR-1 Summary: Pursuant to 10CFR50.55a(a)(3)(i), TVA is requesting relief from the identified ASME Section XI requirements related to examination and testing of snubbers. TVA proposes to continue to use the examination and testing plans currently defined in the Technical Requirements Manual (TR 3.7.3). The current Technical Requirements Manual requirements have been promulgated and approved by NRC, while ASME Section XI imposes overlapping requirements which do not enhance the quality or safety of the subject snubber examination and testing.

Components: Component/piping snubbers Code Class: 1, 2 and 3 Examination Category: F-A (snubber examination only, N/A for snubber testing)

Item Number: F1.10, F1.20, F1.30, and F1.40 (snubber examination only, N/A for snubber testing)

Code Requirement: ASME Boiler and Pressure Vessel Code,Section XI, 2001 Edition, 2003 Addenda, Subarticles:

IWA-4530(b), preservice inspection and testing IWF-5200(a) and (b), preservice examinations and tests IWF-5300(a) and (b) inservice examination and testing in accordance with the first Addenda to ASME/ANSI OM-1987, Part 4, with OMa-1988.

IWF-5400 Repairs and Replacements of snubbers shall be in accordance with the first Addenda to ASME/ANSI OM-1987, Part 4, with OMa-1988.

IWA-6210(c), records and reports E3-1

IWA-6230 requires inservice inspection summary reports for snubbers to be filed with the regulatory authority.

IWA-6240, summary report submittal IWA-2110 requires Authorized Nuclear Inservice Inspector (ANII) involvement for snubber examination and testing Code Requirement From Which Relief is Requested: In accordance with 10CFR50.55a(a)(3)(i), relief is requested from the ASME Section XI 2001 Edition, 2003 addenda, requirement for preservice and inservice examinations and tests for snubbers, and repair/replacement examinations and tests of snubbers:

IWA-4530(b) requires preservice inspection and testing to be in accordance with IWF-5200 following repair/replacement of a snubber.

IWF-5200(a) and (b) requires preservice examinations and tests in accordance with ASME/ANSI OM Part 4, 1987 Edition, OMa-1988 Addenda, using the VT-3 visual examination method in accordance with IWA-2213.

IWF-5300(a) and (b) requires inservice examinations and tests in accordance with ASME/ANSI OM Part 4, 1987 Edition, OMa-1988 Addenda, using the VT-3 visual examination method in accordance with IWA-2213.

IWF-5400 references IWF-5200 for snubber examination and test requirements following repair or replacement.

IWA-6210(c) requires the preparation of preservice and inservice inspection summary reports for Class 1 and 2 snubbers.

IWA-6230 requires the preparation of an inservice inspection summary report (snubbers) after each refueling outage.

IWA-6240, requires the submittal of summary reports (snubbers) to the regulatory authority.

IWA-2110, Duties of the Inspector (for involvement for snubber examination and testing).

Basis For Relief: Watts Bar Nuclear Plant (WBN) Unit 1 is required to update to the 2001 Edition, 2003 Addenda, of ASME Section XI for WBNs second ten-year ISI inspection interval. ASME Section XI Class 1, 2 and 3 equivalent snubbers are examined and tested in accordance with Watts Bar Nuclear (WBN) Plant Technical Requirements Manual (TRM), TR 3.7.3 which was prepared in accordance with the guidance given by NRC in Generic Letter 90-09.

The scope for snubbers examined and tested in accordance with TR E3-2

3.7.3 is not limited by line size or other applicable code exemptions and includes a numerically greater population of snubbers than the Section XI program. Examination and testing of the snubbers in accordance with both ASME Section XI and the plant TRM would result in a duplication of effort utilizing different standards and require the preparation of a separate program and associated procedures. This would result in additional cost and unnecessary radiological exposure. In addition, the personnel performing snubber visual examinations would also be required to be certified in accordance with the American Society of Nondestructive Testing (ASNT) SNT-TC-1A, Personnel Qualification and Certification in Nondestructive Testing, and ASME/ASNT-CP-189, which is an additional certification as compared to the task training qualification required to perform the TRM required examinations and testing of snubbers. The existing TRM program for examination and testing of snubbers was promulgated and accepted by NRC.

The implementation of OM-1987, Part 4, with OMa-1988 Addenda would require WBN to initiate a snubber examination and testing program which would increase the manpower and potentially the radiation exposure to implement, when compared to the existing TRM mandated snubber program, without a compensating increase in the level of quality and safety.

Alternate Examinations: The WBN TRM, TR 3.7.3, requirements will be utilized for the examination and testing of snubbers for preservice, inservice, and repair/replacement activities. The procedures utilized for these examinations are: 1-TRI-0-5, Snubber Visual Inspection; 1-TRI-0-7, Snubber Functional Testing (Mechanical Snubbers); and 1-TRI-0-8, Snubber Functional Testing (Paul Monroe Snubbers). The snubber visual examinations include the pin-to-pin area inclusive of applicable snubbers.

Testing of repaired and replaced snubbers will be performed in accordance with TR 3.7.3, Note 2.

A comprehensive list of snubbers is maintained in Technical Instruction TI-203, Snubber Program. Other related procedures include: Maintenance Instruction (MI) 0.044, Removal and Reinstallation of Mechanical Snubbers and MI-0.05 Fluid Sampling and Maintenance for Paul Monroe Snubbers.

Snubber examination and testing data will be maintained in accordance with the requirements of TR 3.7.3, procedure SPP-3.1, Corrective Action Program, and implementing procedures 1-TRI-0-5, 1-TRI-0-7, and 1-TRI-0-8.

The areas inclusive of the pins back to building structure and to the component/piping being supported will remain in the ASME Section XI examination boundary and IWF-5200(c) and IWF-5300(c)

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will be met through ASME Section XI preservice examination and/or scheduled inservice examinations, as applicable, for the second interval.

Justification For The Granting Of Relief: The current program, as defined by TR 3.7.3, provides for a level of quality and safety equal to that provided by OM Code 1987, Part 4, with OMa-1988 Addenda (referenced by ASME Section XI, 2001 Edition, 2003 Addenda).

Examination, testing, repair and replacement of snubbers are currently performed in accordance with TR 3.7.3, which utilizes the guidance provided by NRC in Generic Letter 90-09. The OM Code referenced by ASME Section XI has a different basis for examination (failure mode groups) and testing plans (10 percent, 37, or 55).

It is impractical to implement both plans because of the resulting duplication of examination and testing efforts and different requirements for snubber quantities subject to examination or test, actually examined and/or tested, and sample expansion requirements.

This would result in additional cost and unnecessary radiological exposure. The existing TRM program for examination and testing of snubbers has been promulgated and accepted by NRC. The differences in the two programs could create confusion when selecting test samples, applying acceptance criteria, corrective actions, and examination schedules for failed snubbers. This situation could increase the possibility of applying the wrong action, thus creating a nonconformance, an inoperability or even a violation of a TRM requirement.

To eliminate any misinterpretation or confusion in administering overlapping requirements for snubbers, and to remove the possibility of applying contradicting requirements to the same snubber(s), WBN proposes to examine and test snubbers in accordance with WBN TR 3.7.3.

Subarticle IWF-5400 provides the requirements for repair and replacement of snubbers to be in accordance with OM Code 1987, Part 4, with OMa-1988 Addenda. Specifically, OM Code 1987, Part 4, with OMa-1988 Addenda, Sections 1.5.6, Snubber Maintenance or Repair and 1.5.7, Snubber Modification and Replacement require repaired and replaced snubbers to meet the visual examination requirements of Paragraph 2.3.1.2 and the operability test requirements of Paragraph 3.2.11. Section 1.5.6 also requires an evaluation of the maintenance or repair activity and Section 1.5.7 requires a suitability evaluation on the replacement/modified snubber. TR 3.7.3 (Note 2) requires replacement snubbers and snubbers which have repairs which might affect the functional test results to be tested to meet the functional test criteria prior to installation.

Procedure 1-TRI-0-5 provides visual examination criteria for installation of a snubber after repair or replacement. The ASME E3-4

Section XI repair/replacement program at WBN documents the suitability of repairs/replacements per IWA-4160.

ASME Section XI VT-3 certification required by personnel performing snubber visual examinations is an additional certification as compared with the TRM program training qualifications. Personnel performing the TRM required visual examinations are process qualified to perform the examinations and testing required by the TRM and implemented by the referenced procedures. This training currently includes a visual test associated with face mask fit and specific training on the acceptance criteria associated with procedure 1-TRI-0-5. Additional visual acuity verification for personnel performing snubber visual examinations will include visual acuity requirements that meet ASME Section XI. The training and documentation of personnel to the visual acceptance criteria, specified in the TRM implementing procedures, provides an acceptable level of quality and safety.

Because relief is sought from the ASME Section XI snubber examination and test requirements, there will be no ASME Section XI snubber examination and test activities to require ANII involvement. The WBN TRM snubber program does not require the use of an ANII for examination and test requirements. The ANII will not be involved in the TRM required visual examination or testing activities performed in lieu of the ASME Code requirements. A snubber program manager provides oversight of the TRM snubber program implementation for both visual examination and functional testing. This oversight includes both review and evaluation of visual examination and functional testing data to ensure TRM requirements are met. The snubber program manager provides an acceptable level of quality and safety without ANII involvement in those activities. ANII involvement in other repair and replacement snubber activities, as required by IWA-2110(g) and (h) and implemented by the WBN ASME Section XI Repair and Replacement Program will be maintained.

Subarticle IWA-6230 and OM Code 1987, Part 4, with OMa-1988 Addenda, Sections 2.3 and 3.3 provide requirements for ASME Section XI inservice examination and test documentation for snubbers and a summary report of examinations and testing. Under the alternate requirements for snubbers, there will be no ASME Section XI inservice examination and testing to document in a summary report.

TR 3.7.3 is implemented by implementing procedures / instructions 1-TRI-0-5, 1-TRI-0-7, and 1-TRI-0-8. These instructions, written and approved in accordance with the TVA Nuclear Quality Assurance Program, include data sheets for documenting the visual examination and functional test data and results, and provide for documentation of nonconforming results and evaluation of those results. The completed data sheets are QA records and are controlled and maintained in accordance with the WBN QA records program. These records are available onsite for review and inspection. The QA E3-5

records documenting snubber visual examinations and functional tests provide an acceptable level of quality and safety when compared to the requirements of ASME Section XI and OM-1987, Part 4, with OMa-1988 Addenda.

Based on the justification provided, the WBN method of examination and testing of snubbers, in accordance with TR 3.7.3 will provide an acceptable level of quality and safety. Therefore, pursuant to 10CFR50.55a(a)(3)(i), TVA requests that relief be granted from the 2001 Edition, 2003 addenda of ASME Section XI Code requirements related to inservice examination and testing for snubbers.

See Attachment for a table that compares OM Code requirements and TRM requirements.

Implementation Schedule: TR 3.7.3 will be implemented during the second ten-year ASME Section XI inspection interval for snubber examination and testing in lieu of the ASME Code Section XI requirements listed above.

Previous NRC Approval:

Reference NRC Letter, Evaluation of Inservice Inspection Program Snubber Relief Request for Watts Bar Nuclear Plant (TAC NO. M94672), dated August 11, 1997, for approval of WBN first interval snubber program relief request.

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Attachment Comparison of ASME OM-4 and WBN TRM Section 3.7.3 Requirements Criteria ASME/ANSI OM Part 4 - WBN TR 3.7.3 87a88 Inservice Examination

1. Visual Paragraph 2.3.1.1, WBN TRM 3.7.3 requires Examination Visual Examination, that visual inspections states that snubber shall verify that there visual examinations are:

shall identify (1) no visible impaired functional indications of damage or ability due to impaired operability; physical damage, (2) attachments to the leakage, corrosion, or foundation or supporting degradation. structure are functional; and (3) fasteners for attachment of the snubber to the component and to the snubber anchorage are functional.

2. Visual Paragraph 2.3.2.2 WBN TRM 3.7.3 provides Examination provides examination snubber visual Interval interval frequency and inspection interval Frequency additional examination frequency.

requirements.

3. Method of IWF-5200(a) and IWF- WBN TRM 3.7.3 snubber Visual 5300(a) requires use inspections are Examination of the VT-3 visual performed by personnel examination method who are specifically described in IWA-2213. trained and certified to perform snubber visual examinations. Visual acuity of inspectors is also verified.

4. Subsequent Paragraph 2.3.2 WBN TRM 3.7.3 provides a Examination provides guidance for snubber visual Intervals inservice examination inspection interval intervals based on the based on the number of number of unacceptable unacceptable snubbers snubbers discovered. discovered. These requirements are similar to NRC GL 90-09.

5. Failure Section 2.3.4 states WBN TRM 3.7.3 Evaluation that snubbers not requirements for visual meeting examination examination failures are and acceptance comparable to OM-4, criteria shall be Section 2.3.4.

evaluated to determine the cause of unacceptability.

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Criteria ASME/ANSI OM Part 4 - WBN TR 3.7.3 87a88 Inservice Operability Test

1. Inservice Paragraph 3.2.1.1, WBN TRM 3.7.3 states Operability Operability Test, that snubbers shall be Test states that snubber functionally tested Requirements operational readiness either in place or in a tests shall verify bench test.

activation, release It also requires a rate, and breakaway functional test to force or drag force by verify activation in either an in-place or tension and bench test. compression, and force required to initiate or maintain motion within the specified range in both directions of travel for mechanical snubbers.

2. Snubber Paragraph 3.2.3 states WBN TRM 3.7.3 states Sample Size that each defined test that at least 10 plan group shall use percent of the total of either a 10 percent each type of snubber sampling plan; a "37 shall be functionally testing sample plan;" tested either in place or a "55 testing or in a bench test.

sample plan" during each refueling outage.

3. Additional The snubbers which WBN TRM 3.7.3 requires an Sampling have been found additional 10 percent of unacceptable per the hydraulic snubbers or testing criteria shall another sample of 19 mechanical snubbers to be be subject to tested.

paragraph 3.2.3.1 (b),

which states that the additional sample size must be at least one-half the size of the initial sample size of the defined test plan group of snubbers.

4. Failure Paragraph 3.2.4.1 WBN TRM 3.7.3 states Evaluation states that snubbers that, if a snubber not meeting the being functionally operability testing tested either fails to acceptance criteria in lock up or fails to paragraph 3.2.1 shall move (i.e., is frozen be evaluated to in place), the cause of determine the cause of failure will be the failure. evaluated. If the failure is caused by E3-8

the manufacturer or design deficiency, all snubbers of the same type subject to the same defect shall be functionally tested.

5. Test Failure Paragraph 3.2.4.2 WBN TRM 3.7.3 states Mode Groups states that that the unacceptable unacceptable snubbers may be snubber(s) shall be categorized into categorized into failure mode group(s).

failure mode group(s). A failure mode group A test failure mode shall include all group(s) shall include unacceptable snubbers all unacceptable that have a given snubbers that have a failure mode and all given failure mode, other snubbers subject and all other snubbers to that same failure subject to the same mode.

failure mode.

6. Corrective Paragraph 3.2.5.1 WBN TRM 3.7.3 requires Actions states that that inoperable for 10 unacceptable snubbers snubbers be repaired, Percent shall be repaired, modified, or replaced Sample Plan modified, or replaced. before operability can be restored.

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Enclosure 4 WATTS BAR NUCLEAR PLANT (WBN)

UNIT 1 (INFORMATION COPY)

INSERVICE INSPECTION (ISI) PROGRAM FOR SECOND 10-YEAR INTERVAL

Watts Bar Nuclear Plant Unit 1 Technical Requirements Instruction 1-TRI-0-10.2 ASME SECTION XI ISI/NDE PROGRAM Revision 0000 Quality Related Level of Use: Information Use Effective Date: 05-27-2007 Responsible Organization: SCE, System Eng - Component Prepared By: John Lewis Approved By: K. A. Lovell

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 2 of 125 Current Revision Description Initial issue.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 3 of 125 Table of Contents

1.0 INTRODUCTION

.......................................................................................................... 5 1.1 Purpose ........................................................................................................................ 5 1.2 Scope (Applicability) ..................................................................................................... 5 1.3 Codes of Record and Code Cases ............................................................................... 6 1.3.1 Current Code Requirements ........................................................................... 6 1.3.2 Current Code Cases ....................................................................................... 7 1.3.3 History of ISI and PSI Programs ..................................................................... 7 1.4 Frequency Inspection Intervals and Inspection Periods................................................ 8 1.5 Technical Requirements Fulfilled and Modes ............................................................... 8 1.6 Owner Statement .......................................................................................................... 9 2.0 DEVELOPMENTAL REFERENCES ............................................................................ 9 2.1 WBN Unit 1 Technical Surveillance Requirement 3.4.5.1 and 3.4.5.2. ......................... 9 2.2 WBN Final Safety Analysis Report ............................................................................... 9 2.3 NRC Documents........................................................................................................... 9 2.4 ASME Reference Documents ..................................................................................... 10 2.5 Plant Procedures and Instructions .............................................................................. 10 2.6 ISI Drawings (See Appendix F)................................................................................... 12 2.7 Abbreviations .............................................................................................................. 12 3.0 PREREQUISITES AND PRECAUTIONS ................................................................... 12 3.1 Prerequisites............................................................................................................... 12 3.2 Precautions................................................................................................................. 12 4.0 SPECIAL TOOLS AND EQUIPMENT ........................................................................ 13 5.0 ACCEPTANCE STANDARDS ................................................................................... 13 6.0 QUALIFICATIONS OF NDE PERSONNEL................................................................ 13 7.0 IMPLEMENTATION AND RESPONSIBILITIES......................................................... 13 7.1 NDE Examinations...................................................................................................... 14 7.2 Components Subject to Examination .......................................................................... 14 7.3 Notification of Indication.............................................................................................. 18 7.4 Additional Examinations for ASME Code Class 1, 2, and 3 ........................................ 18 7.5 Corrective Action Program and Successive Examinations ......................................... 22

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 4 of 125 Table of Contents (continued) 7.6 Configuration Changes ............................................................................................... 23 7.7 Calibration Standards ................................................................................................. 23 7.8 Records and Reports .................................................................................................. 24 7.9 Requests for Relief (RFR)........................................................................................... 24 7.10 Scan Plan ................................................................................................................... 24 7.11 Augmented Examinations ........................................................................................... 25 Appendix A: ISI Planning/Scheduling Table for ASME Class 1 Components.............................................................................................. 26 Appendix B: ISI Planning/Scheduling Table for ASME Class 2 Components.............................................................................................. 53 Appendix C: ISI Planning/Scheduling Table for ASME Class 3 Components.............................................................................................. 77 Appendix D: ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports ............................................................................... 85 Appendix E: Class 1 (B-M-2) and 2 (C-G) Valve Listings........................................... 105 Appendix F: ISI Drawing List....................................................................................... 110 Appendix G: Schedule of Successive Examinations................................................. 113 Appendix H: Notification of Additional Sample Results Form.................................. 114 Appendix I: Requests for Relief ................................................................................. 115 Appendix J: Augmented Examinations...................................................................... 116 Appendix K: Source Notes........................................................................................... 125

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 5 of 125

1.0 INTRODUCTION

1.1 Purpose In 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 SPP-9.1, Part A, ASME Section XI Inservice Inspection and Augmented Nondestructive Examinations. This program is organized to comply with the inservice inspection (ISI) nondestructive examination (NDE) requirements of the 2001 Edition, 2003 Addenda Edition 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 Instruction (TRI) employed to obtain data via NDE of ASME Section XI 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. It shall serve as TVA's ISI/NDE plan and schedule in accordance with the requirements of IWA-1400 for the WBN Unit 1 second ISI interval.

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

1.2 Scope (Applicability)

This program outlines details for planning and implementing the second ISI/NDE inspection interval for ASME Section XI Code Class 1, 2, and 3 equivalent components at WBN Unit 1 in accordance with IWA-2432, Inspection Program B.

Elements of ASME Section XI, such as Pump and Valve Testing, Snubber Inservice Examination and Testing (specifically the inservice testing requirements of IWF-5000), Repair and Replacements, System Pressure Tests (including the associated Categories B-P, C-H, D-A, D-B, and D-C, VT-2 Visual Examinations), and Steam Generator Tube Examinations (Examination Category B-Q) are covered by other procedures.

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

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 6 of 125 1.2 Scope (Applicability) (continued)

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

1.3 Codes of Record and Code Cases 1.3.1 Current Code Requirements The WBN Unit 1 Code of Record for the second inspection interval is the 2001 Edition, 2003 Addenda of the ASME Boiler and Pressure Vessel Code,Section XI, Division 1 in accordance with 10 CFR 50.55a(g)(4).

10CFR50.55a mandated additional requirements and/or exceptions are listed below along with the applicable 10CFR50 reference:

A. The extent of examination for Examination Category B-J welds shall be in accordance with the 1974 Edition, Summer 1975 Addenda of ASME Section XI

- 10CFR50.55a(b)(2)(ii). Extent of examination is defined as the criteria for the selection of the Class 1 Category B-J welds to be examined. The extent of examination specifies the length of weld to be examined.

B. IWB-1220 of ASME Section XI 1989 Edition shall be used for the exemption of Class 1 equivalent piping - 10CFR50.55a(b)(2)(xi).

C. IWA-2220 of the ASME Section XI 2001 Edition, 2003 Addenda that allows the use of an ultrasonic examination method is prohibited -

10CFR50.55a(b)(2)(xxii).

D. Appendix VIII and supplements to Appendix VIII and Appendix I Article I-3000 of ASME Section XI 2001 Edition will be used - 10CFR50.55a(b)(2)(xxiv) and 10CFR50.55a(b)(2)(xiv, xv, and xvi are required) (Refer to relief requests PDI-2 and PDI-4 in section 7.9).

E. When qualifying visual examination personnel for VT-3 visual examination under paragraph IWA-2317 of ASME Section XI 2001 Edition, 2003 Addenda, the proficiency of training must be demonstrated by administering an initial qualification examination and administering subsequent re-examinations on 3-year intervals - 10CFR50.55a(b)(2)(xviii)(C).

F. Level I and II nondestructive examination personnel shall be recertified on a 3 year interval in lieu of the 5 year interval in IWA-2314(a) and IWA-2314(b) of ASME Section XI 2001 Edition, 2003 Addenda - 10CFR50.55a(b)(2)(xviii)(A).

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 7 of 125 1.3.1 Current Code Requirements (continued)

G. The provisions for substitution of alternate examination methods, a combination of methods, or newly developed techniques in IWA-2240, ASME Section XI 1997 Addenda, must be applied. The provisions in IWA-2240 of the ASME Section XI 2001 Edition, 2003 Addenda are not approved for use -

10CFR50.55a(b)(2)(xix).

1.3.2 Current Code Cases Code cases used shall be implemented in their entirety unless approved by NRC or stated in Regulatory Guide (RG) 1.147. The following Code Cases have been accepted for use by the NRC in RG 1.147 and will be used during implementation of this program:

A. Code Case N-460, Alternative Examination Coverage for Class 1 and Class 2 Welds,Section XI, Division 1.

B. Code Case N-526, Alternative Requirements for Successive Inspections of Class 1 and 2 Vessels,Section XI, Division 1. Available for use starting with Revision 12 of this TRI.

C. Code Case N-586, Alternative Additional Examinations Requirements for Class 1, 2, and 3 Piping, Components, and Supports,Section XI, Division 1.

Available for use starting with Revision 12 of this TRI. This code case is acceptable for use subject to the following NRC RG 1.147 conditions: the engineering evaluations addressed under Item (a) and the additional examinations addressed under Item (b) shall be performed during this outage.

If the additional examinations performed under Item (b) reveal indications exceeding the applicable acceptable criteria of Section XI, the engineering evaluations and the examinations shall be further extended to include additional evaluations and examinations at this outage.

1.3.3 History of ISI and PSI Programs A Preservice Inspection Program was performed in accordance with Technical Instruction (TI) 50A, ASME Section XI Preservice Inspection 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 ISI 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.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 8 of 125 1.4 Frequency Inspection Intervals and Inspection Periods The inservice examinations required by ASME Section XI 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 ISI examinations required by ASME Section XI, Division 1, during this inspection interval for Unit 1 shall follow Inspection Program B of IWA-2432. The inspection interval may be decreased or extended by as much as one year in accordance with IWA-2430(d). In 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(e).

The first inspection interval was extended by one year and the second interval is being decreased by one year. The one year decrease in the second interval will occur during the second inspection period.

Second Inspection Interval Period durations are:

• First Inspection Period - May 27, 2007 through May 26, 2010

• Second Inspection Period - May 27, 2010 through May 26, 2013

• Third Inspection Period - May 27, 2013 through May 26, 2016 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 schedule that complies with IWA-2432; IWB-2412, Program B and Table IWB-2412-1; IWC-2412, Program B and Table IWC-2412-1; IWD-2412, Program B and Table IWD-2412-1; and IWF-2410 and Table IWF-2410-2 Inspection Program B.

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.

1.5 Technical Requirements Fulfilled and Modes Performance of this TRI satisfies the following Technical Surveillance Requirements:

SURVEILLANCE APPLICABLE MODES PERFORMANCE MODES REQUIREMENT TSR 3.4.5.1 ALL MODES MODES 5 and 6 TSR 3.4.5.2 ALL MODES ALL MODES

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 9 of 125 1.6 Owner Statement Owner: Tennessee Valley Authority Address of Corporate Office: Chattanooga Office Complex 1101 Market Street Chattanooga, Tennessee 37402-2801 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 Commercial Operation Date: May 27, 1996 2.0 DEVELOPMENTAL REFERENCES 2.1 WBN Unit 1 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, Inservice Inspection of ASME Code Class 1 Components D. Section 5.4.4.4, Inservice Inspection (Reactor Vessel and Appurtenances)

E. Section 6.6, Inservice Inspection of ASME Code Class 2 and 3 Components 2.3 NRC Documents A. 10 CFR Part 50.55a(g), Codes and Standards, Inservice Inspection Requirements B. 10 CFR Part 50.2, Definitions C. Regulatory Guide 1.14, Reactor Coolant Pump Flywheel Integrity D. Regulatory Guide 1.26, Quality Group Classification and Standards for Water, Steam, and Radioactive Waste Containing Components of Nuclear Power Plants

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 10 of 125 2.3 NRC Documents (continued)

E. Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability ASME Section XI Division 1 F. Regulatory Guide 1.150, Ultrasonic Testing of Reactor Vessel Welds during Preservice and Inservice Examinations 2.4 ASME Reference Documents A. ASME Boiler and Pressure Vessel Code,Section XI, Division 1, 2001 Edition, 2003 Addenda (including portions of 1974 Edition, Summer 1975 Addenda; 1997 Addenda; 1989 Edition, and 2001 Edition as mandated by 10CFR50.55a)

B. ASME Section XI Code Cases as listed in Section 1.3 2.5 Plant Procedures and Instructions A. Standard Programs and Processes, Department Procedures, and Site Standard Practices

1. NADP-1, Conduct of Quality Assessment and Inspection

2. MMDP-11, Erection of Scaffolds/Temporary Work Platforms and Ladders

3. SPP-2.4, Records Management

4. SPP-3.1, Corrective Action Program

5. SPP-3.5, Regulatory Reporting Requirements

6. SSP-5.2, ALARA Program

7. SPP-5.4, Chemical Traffic Control

8. SPP-6.1, Work Order Process Initiation

9. SPP-6.4, Measuring and Test Equipment

10. SPP-6.5, Foreign Material Control

11. SPP-7.2, Outage Management

12. SPP-8.1, Conduct of Testing

13. SPP-8.2, Surveillance Test Program

14. SPP-9.1, ASME Section XI

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 11 of 125 2.5 Plant Procedures and Instructions (continued)

15. SPP-9.3, Plant Modifications and Engineering Change Control B. Plant Instructions

1. RCI-128, ALARA Program Implementation

2. TI-12.07, Containment Access C. WBN Maintenance and Technical Instructions

1. MI-0.002, Valve Maintenance

2. MI-0.014, Pressure Retaining Bolted Connections

3. MI-68.001, Disassembly and Reassembly of the Reactor Pressure Vessel and Attachments

4. MI-68.004, Reactor Coolant Pump Seal Inspection or Replacement

5. MI-68.06, Removal, Inspection and Maintenance of Reactor Coolant Pump Rotating Element

6. MI-68.007, Removal and Installation of Steam Generator Primary Manway Covers

7. MI-68.013, Removal and Replacement of Pressurizer Safety Valves

8. MI-68.14, Removal and Replacement of Pressurizer Manway Cover

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

10. MI-68.021, Pressurizer PORV Maintenance

11. TI-203, Snubber Program D. Inspection 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 Inservice ASME Section XI Examinations

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 12 of 125 2.6 ISI Drawings (See Appendix F) 2.7 Abbreviations ALARA As Low As Reasonably Achievable ASNT American Society for Nondestructive Testing ASME American Society of Mechanical Engineers CFR Code of Federal Regulations DCRM Document Control and Records Management IEP Inspection and Examination Procedures ISI Inservice Inspection NDE Nondestructive Examination NRC Nuclear Regulatory Commission RADPRO Radiation Protection RFR Request for Relief RWP Radiation Work Permit SI Surveillance Instruction SPP Standard Processes and Procedures WO 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 TRI, a WO may be used. This WO shall be processed in accordance with SPP-6.1. 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 (RWP)/ALARA 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 MMDP-11.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 13 of 125 3.2 Precautions (continued)

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

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 Instruction TI-12.07, Containment Access, and SPP-6.5, Foreign Material Control.

4.0 SPECIAL TOOLS AND EQUIPMENT Equipment shall be specified by individual NDE Procedures.

5.0 ACCEPTANCE STANDARDS The acceptance criteria shall be in accordance with IWA-3000 and the individual NDE Procedures of IEP-100.

Evaluations of examinations in accordance with IWB-3132.3, IWB-3142.4, IWC-3122.3, or IWC-3132.3 shall be submitted to the NRC. This information shall be submitted with the Inservice Inspection Summary Report or, if deemed necessary, a separate report shall be submitted. The evaluations shall be documented on or referenced on the Notification of Indication.

6.0 QUALIFICATIONS OF NDE PERSONNEL Personnel performing NDE operations shall be qualified and certified in accordance with IWA-2300, IEP-200, and IEP-300.

7.0 IMPLEMENTATION AND RESPONSIBILITIES Any revisions to this program initiated by other groups shall be submitted to ISI/NDE for approval prior to incorporating the revisions into this program.

Responsibilities shall be in accordance with SPP-9.1, Part A.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 14 of 125 7.1 NDE Examinations A. NDE methods shall be in accordance with IWA-2200 of ASME Section XI and this program as scheduled in Appendices A-D.

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

C. In 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.

D. When less than the required code examination volume or area is examined, the percentage examined shall be documented on the examination data sheet. The cause of the limitation shall be clearly specified and documented on the examination data sheet. The examination with less than the required ASME Section XI Code examination volume or area shall be handled as a request for relief in accordance with SPP-9.1, Part A.

7.2 Components Subject to Examination A. ASME Class 1 Equivalent Components Subject to Examination (IWB)

1. The ASME Class 1 equivalent systems subject to examination are:

Chemical and Volume Control System; Reactor Coolant System; Reactor Coolant System Main Loop; Residual Heat Removal System; and Safety Injection System. The specific components subject to examination are identified on drawings listed in Appendix F, ISI Drawings List.

2. Components are scheduled for examination in accordance with ASME Section XI, 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 E.

3. The rules of IWB-1220 (a), (b),and (c) have been used to establish exemption criteria for components (piping uses 1989 Edition per 10CFR50.55a(b)(2)(xi)) and establish the numbers in Appendix A.

4. Examination Category B-A, B-B, B-D, B-F, B-G-1, B-G-2, B-K, B-M-1, B-L-2, B-M-2, B-N-1, B-N-2, B-N-3 and B-O components shall be selected for examination in accordance with Table IWB-2500-1, 2001 Edition, 2003 Addenda of ASME Section XI.

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5. Category B-J circumferential welds shall be selected to provide a 25 percent sample this interval. WBN does not have stress level calculations as required for selection per Table IWB-2500-1, Examination Category B-J, Note: (1)(b). The Code basis for this method of selection of Item Numbers B9.11, B9.21, B9.22, B9.31, B9.32, and B9.40 is Table IWB-2500-1, Examination Category B-J, 2001 Edition 2003 Addenda of Section XI except the extent of examination is determined by the requirements of Table IWB-2500 and Table IWB-2600, Examination Category B-J, 1974 Edition with Addenda through Summer 1975 as allowed by 10 CFR50.55a(b)(2)(ii).

6. Examination requirements for ASME Class 1 equivalent component supports, Examination Category F-A, shall be in accordance with ASME Section XI Subsection IWF. See Section 7.2.D.

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

8. Examination coverage of ASME Class 1 equivalent welds will be in accordance with Code Case N-460 unless impractical due to original plant design. In this case the examination will be processed in accordance with Section 7.9.

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

1. ASME Class 2 equivalent systems subject to examination are:

Containment Spray System; Feedwater System; High Pressure Safety Injection System (includes Containment Spray, Chemical Volume Control, Safety Injection and Residual Heat Removal,); Main Steam System; Residual Heat Removal System; and Safety Injection System. The specific components subject to examination are identified on drawings listed in Appendix F, ISI Drawings List.

2. Components are scheduled for examination in accordance with ASME Section XI, Table IWC-2500-1, 2001 Edition 2003 Addenda of ASME Section XI. 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. ASME Class 2 valves subject to examination are listed in Appendix E.

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

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4. Examination Category C-A, C-B, C-C, C-D, C-F-1, C-F-2 and C-G components shall be selected for examination in accordance with Table IWC-2500-1.

5. Examination requirements for ASME Class 2 equivalent component supports, Examination Category F-A, shall be in accordance with ASME Section XI Subsection IWF. See Section 7.2.D.

6. Examination coverage of ASME Class 2 equivalent welds will be in accordance with Code Case N-460 unless impractical due to original plant design. In this case the examination will be processed in accordance with Section 7.9.

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

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

1. ASME Class 3 equivalent systems subject to examination are: 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 F, ISI Drawings List.

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

3. Examination requirements for ASME Class 3 equivalent component supports, Examination Category F-A, shall be in accordance with ASME Section XI Subsection IWF. See Section 7.2.D.

D. Component Supports Subject to Examination (IWF)

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 7.2.D.2. These component and piping supports are within the systems identified in sections 7.2.A.1, 7.2.B.1, and 7.2.C.1. The specific supports subject to examination are identified on ISI Drawings listed in Appendix F.

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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 examination by IWB-1220, IWC-1220, and IWD-1220, 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 and including the snubber pins in accordance with IWF-5300(c). The snubber is outside the examination boundary. The examination/testing of snubbers is covered by the Snubber Inservice Testing Program. Refer to section 7.9 for snubber request for relief.

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.

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

When determining equipment support boundaries, consideration is to be given to include miscellaneous steel for each equipment support.

Acceptance range for support settings shall be calculated in accordance with Inspection 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. If 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.

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d. Support Function D - Either hydraulic or mechanical snubbers.

7.3 Notification of Indication Whenever an unacceptable inservice examination indication is discovered, an NOI shall be initiated in accordance with SPP-9.1, Part A. The NOI is to be used to:

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

B. Notify ISI/NDE Representative of indications that exceed the acceptance criteria of Article IWX-3000 of the ASME Section XI 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 II of the NOI Form; to provide the ISI/NDE Representative a method of determining if additional and/or successive examinations are required in accordance with the Code.

7.4 Additional Examinations for ASME Code Class 1, 2, and 3 After a Notification of Indication (NOI) has been dispositioned and returned to the ISI/NDE Representative (reference Section 7.3), the NOI shall be evaluated to determine if additional examinations shall be required in accordance with ASME Section XI 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 and within the same system. The initial sample is the sample scheduled for examination at a particular outage for Section XI credit.

A. Additional Examinations for Class 1 Equivalent Components (IWB)

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

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1. Examinations of the initial sample that reveal indications exceeding the acceptance standards of table IWB-3410-1 shall be extended to include additional examinations in the same outage 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 NB-5300, as documented in QA records, shall be acceptable).

2. The first additional examination sample shall include an additional number of items included in the inspection item equal to the number of items that were scheduled for the current 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. If the first additional examinations of Section 7.4.A.2 reveal indications exceeding the acceptance standards of Table IWB-3410-1, except where IWB-3131(b) is applicable, further additional examinations shall be performed during the 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.A.2 or 7.4.A.3 were completed, the examinations shall be performed as originally scheduled in accordance with IWB-2400.

B. Additional Examinations for Class 2 Equivalent Components (IWC)

Additional examinations for Class 2 equivalent components (IWC) shall be selected per 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 XI credit.

1. Examinations 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-3112(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).

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2. The first additional sample shall include an additional number of items included in the inspection item equal to 20% 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. If the first additional examinations of Section 7.4.B.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.B.2 or 7.4.B.3 were completed, the examinations shall be performed as originally scheduled in accordance with IWC-2400.

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

Additional examinations for Class 3 equivalent components (IWD) shall be in accordance with IWD-2430. The initial sample is the sample scheduled for examination at a particular outage for ASME Section XI credit.

1. Examinations performed in accordance with Table IWD-2500-1 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.

2. The first additional sample shall include an additional 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. If 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.

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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.

D. Additional Examinations for Component Supports (IWF)

Additional examinations for component supports (IWF) shall be in accordance with IWF-2430. The initial sample is the sample scheduled for examination at a particular outage for ASME Section XI credit.

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 to include additional supports within the system, equal in number and of the same type and function as those scheduled for examination during the inspection period.

2. When the first additional examination sample of section 7.4.D.1 reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400 and that require corrective action, the examinations shall be further extended to include additional examinations during the current outage.

The component supports within the system of the same type and function as in section 7.4.D.1.

3. When the second additional sample of section 7.4.D.2 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 and 7.4.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.

4. When the third additional sample of section 7.4.D.3 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

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After completion of the additional examinations, ASME Section XI Code requirements for additional examinations are complete. If 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 this and /or other systems.

Site Engineering shall be notified by using the Notification of Additional Sample Results Form in Appendix H. Included 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 NOIs, and any other pertinent information.

7.5 Corrective Action Program and Successive Examinations Corrective actions required as a result of ISI examinations shall be handled in accordance with SPP-3.1.

A. Successive Examinations - Class 1 Equivalent Components Areas containing flaw indications or relevant conditions evaluated in accordance with IWB-3132.3 or IWB 3142.4 and SPP-3.1 that qualify for continued service shall be reexamined during the next three inspection periods listed in the inspection schedules. If 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 G.

B. Successive Examinations - Class 2 Equivalent Components Components with flaw indications evaluated in accordance with IWC-3122.3 or IWC-3132.3 and SPP-3.1 that qualify for continued service shall be reexamined during the next inspection period listed in the inspection schedule. If 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 G.

C. Successive Examinations for Class 3 Equivalent Components

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Components with flaw indications or relevant conditions evaluated in accordance with IWD-3000 and SPP-3.1 that qualify for continued service shall be re-examined during the next inspection period listed in the inspection schedule. If 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 G.

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

When a component support is accepted for continued service in accordance with IWF-3112.2 or IWF-3122.2 the 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 G.

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

7.6 Configuration Changes When modifications are made to existing piping or components, drawings shall be reviewed and revised by ISI/NDE Representative to identify the piping configuration, welds, and components that shall be included in or deleted from the ASME Section XI ISI/NDE Program.

If 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. ISI/NDE Representative shall be responsible for reviewing the proposed change, revising and issuing the drawing as necessary in accordance with SPP-9.1, Part A.

7.7 Calibration Standards Calibration blocks used for ultrasonic examination shall be in accordance with SPP-9.1, Part A and IEP-203.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 24 of 125 7.8 Records and Reports Records and reports shall be prepared in accordance with SPP-9.1, Part A.

7.9 Requests for Relief (RFR)

When TVA has determined that Code requirements or examinations are impractical, TVA shall submit written requests for relief (RFR) to the NRC with information to support the need for relief and any proposed alternate examinations. The impractical Code requirements or relief situation shall be identified as a part of the examination schedule tables (Appendix A-D) in this program and references to a particular RFR shall be included. Requests for relief shall be prepared in accordance with SPP-9.1.

Requests for relief listings are included in Appendix I.

7.10 Scan Plan A computerized data base system will be utilized for status and Section XI credit of completed ISI examinations and those augmented examinations which have been integrated with the ASME Section XI ISI/NDE Program. The data base is utilized to provide a scan plan. A scan plan is the primary scheduling document 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 nonoutage activities. Responsibilities for preparing, maintaining, and approving the data base and scan plans shall be in accordance with SPP-9.1, Part A.

During implementation phases (usually outage periods), it may become necessary to revise the scan plan. Scan plan revisions can be initiated by ISI/NDE Representative, ISO, or by other personnel involved with the implementation of the scan plan. All changes shall be coordinated with an ISI/NDE Representative and, as needed, with the appropriate plant planning and scheduling personnel for facilitating the use of supporting craft personnel. Work/change control during outage periods shall be in accordance with SPP-7.2. Revisions to the scan plan shall be controlled in the same manner as the original (see SPP-9.1, Part A). 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 revisions on the scan plan.

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

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 25 of 125 7.11 Augmented Examinations Augmented examinations are performed in addition to ASME Section XI code requirements. The augmented examinations may be required by the NRC or be self-imposed by TVA. Typical sources include generic letters, IE bulletins, technical specifications, vendor recommendations, and industry experience. SPP-9.1, Part A provides requirements for requesting augmented examinations. Appendix J provides a description and schedule for augmented examinations currently integrated with the ISI Program.

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-A Pressure Retaining Welds in Reactor Vessel B-A B1.10 RV Shell Welds B1.11 RV Shell Welds UT 4 100% 4 Deferral 0 0 4 ISI-0427-C Circumferential Permissible B1.12 RV Shell Welds Volumetric None 100% N/A Deferral N/A N/A N/A Longitudinal Permissible B-A B1.20 RV Head Welds B1.21 RV Head Welds UT 2 (closure 100% of 2 Deferral 0 0 2 CHM-2549-C Circumferential head and accessible Permissible ISI-0427-C length lower head)

B1.22 RV Head Welds UT 6 100% of 6 Deferral 0 0 6 ISI-0427-C Meridional Meridional accessible Permissible length welds B-A B1.30 RV Shell-to- UT 1 100% 1 Partial 0 0 1 ISI-0427-C Flange Weld Deferral

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-A B1.40 RV Head-to- MT & UT 1 100% 1 Partial 1/2 of weld 1/2 of weld 0 CHM-2549-C Flange Weld Deferral B-A B1.50 RV Beltline Repair Areas

>10% Wall B1.51 RV Repair Volumetric None All N/A Deferral N/A N/A N/A Welds Beltline Permissible Region B-B Pressure Retaining Welds in Vessels Other than Reactor Vessels B-B B2.10 Pressurizer Shell-to-Head Welds B2.11 Pressurizer UT 2 100% 2 Deferral Not 0 1 1 CHM-2570-C Circ. Shell-to- Permissible Head Welds B2.12 Pressurizer UT 2 / 1 foot 1 foot of 2 / 1 foot Deferral Not 0 1 foot 1 foot CHM-2570-C Shell-to-Head (one each Permissible Intersecting longitudinal Long Weld weld)

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-B B2.20 Pressurizer Head Welds B2.21 Pressurizer Volumetric None One weld N/A Deferral Not N/A N/A N/A N/A Head Welds per head Permissible Circumferential B2.22 Pressurizer Volumetric None One weld N/A Deferral Not N/A N/A N/A N/A Head Welds per head Permissible Meridional B-B B2.30 SG Primary Side Head Welds B2.31 SG Primary Volumetric None One weld N/A Deferral Not N/A N/A N/A N/A Side Head per head Permissible Welds Circumferential B2.32 SG Primary Volumetric None One weld N/A Deferral Not N/A N/A N/A N/A Side Head per head Permissible Welds Meridional

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-B B2.40 SG Tubesheet- UT 4 SG / 1 100% 1 Deferral Not 1 0 0 CHM-2660-C to-Head Weld weld each Permissible B-B B2.50 Heat Exch Primary Side Head Welds B2.51 Heat Exch Volumetric None One weld N/A Deferral Not N/A N/A N/A N/A Primary Side per head Permissible Head Welds, Circumferential B2.52 Heat Exch Volumetric None One weld N/A Deferral Not N/A N/A N/A N/A Primary Side per head Permissible Head Welds, Meridional B-B B2.60 Heat Exch Volumetric None One weld N/A Deferral Not N/A N/A N/A N/A Primary Side per Permissible Shell group, Tubesheet-to- 100%

Head Welds

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-B B2.70 Heat Exch Volumetric None One foot N/A Deferral Not N/A N/A N/A N/A Primary Side of one Permissible Shell, Long. weld per Welds group B-B B2.80 Heat Exch Volumetric None One weld N/A Deferral Not N/A N/A N/A N/A Primary Side per group Permissible Shell, at each Tubesheet-to- end Shell Welds B-D Full Penetration Welds of Nozzles in Vessels B-D B3.90 RV Nozzle-to- UT 8 100% 8 Deferral 0 0 8 ISI-0427-C Vessel Welds Permissible B-D B3.100 RV Nozzle UT 8 100% 8 Deferral 0 0 8 ISI-0427-C Inside Radius Permissible Section B-D B3.110 Pressurizer UT 6 100% 6 Deferral Not 0 5 1 CHM-2570-C Nozzle-to- Permissible Vessel Welds

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-D B3.120 Pressurizer UT or VT 6 100% 6 Deferral Not 0 5 1 CHM-2570-C Nozzle Inside (enhanced) Permissible Radius Section B-D B3.130 SG Primary Volumetric None 100% N/A Deferral Not N/A N/A N/A N/A Side Nozzle- Permissible Vessel Welds B-D B3.140 SG Primary UT or VT 8 100% 8 Deferral Not 4 0 4 CHM-2660-C Side Nozzle (enhanced) Permissible Inside Radius Section B-D B3.150 Heat Exch Volumetric None 100% N/A Deferral Not N/A N/A N/A N/A Primary Side Permissible Nozzle-to-Vessel Welds B-D B3.160 Heat Exch Volumetric None 100% N/A Deferral Not N/A N/A N/A N/A Primary Side Permissible Nozzle Inside Radius Section

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 32 of 125 Appendix A (Page 7 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-F Pressure Retaining Dissimilar Metal Welds B-F B5.10 RV Nozzle-to- PT & UT 8 100% 8 Deferral 2 2 4 ISI-0427-C SE DM Butt Permissible Welds NPS 4 or Larger B-F B5.20 RV Nozzle-to- Surface None 100% N/A Deferral N/A N/A N/A N/A SE DM Butt Permissible Welds Less than NPS 4 B-F B5.30 RV Nozzle-to- Surface None 100% N/A Deferral N/A N/A N/A N/A SE DM Socket Permissible Welds B-F B5.40 Pressurizer PT & UT 6 100% 6 Deferral Not 2 2 2 CHM-2570-C Nozzle-to-SE Permissible DM Butt Welds NPS 4 or Larger B-F B5.50 Pressurizer Surface None 100% N/A Deferral Not N/A N/A N/A N/A Nozzle-to-SE Permissible DM Butt Welds less than NPS 4

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 33 of 125 Appendix A (Page 8 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-F B5.60 Pressurizer Surface None 100% N/A Deferral Not N/A N/A N/A N/A Nozzle-to-SE Permissible DM Socket Welds B-F B5.70 SG Nozzle-to- PT & UT 12 100% 12 Deferral Not 4 4 4 CHM-2547-C SE DM Butt Permissible Welds NPS 4 or Larger B-F B5.80 SG Nozzle-to- Surface None 100% N/A Deferral Not N/A N/A N/A N/A SE DM Butt Permissible Welds less than NPS 4 B-F B5.90 SG Nozzle-to- Surface None 100% N/A Deferral Not N/A N/A N/A N/A SE DM Socket Permissible Welds B-F B5.100 Heat Exch PT & UT None 100% N/A Deferral Not N/A N/A N/A N/A Nozzle-to-SE Permissible DM Welds NPS 4 or Larger

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 34 of 125 Appendix A (Page 9 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-F B5.110 Heat Exch Surface None 100% N/A Deferral Not N/A N/A N/A N/A Nozzle-to-SE Permissible DM Butt Welds less than NPS 4 B-F B5.120 Heat Exch Surface None 100% N/A Deferral Not N/A N/A N/A N/A Nozzle-to-SE Permissible DM Socket Welds B-G-1 Pressure Retaining Bolting, Greater Than 2 in Diameter B-G-1 B6.10 RV Closure VT-1 54 100% 54 Deferral 0 0 54 ISI-0427-C Head Nuts Permissible B-G-1 B6.20 RV Closure UT 54 100% 54 Deferral 0 0 54 ISI-0427-C Studs Permissible B-G-1 B6.40 RV Threads in UT 54 100% 54 Deferral 0 0 54 ISI-0427-C Flange Permissible B-G-1 B6.50 RV Closure VT-1 54 100% 54 Deferral 0 0 54 ISI-0427-C Washers (no Permissible Bushings)

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 35 of 125 Appendix A (Page 10 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-G-1 B6.60 Pressurizer Volumetric None 100% N/A Deferral N/A N/A N/A N/A Bolts and Studs Permissible B-G-1 B6.70 Pressurizer Visual None 100% N/A Deferral N/A N/A N/A N/A Flange Surface Permissible (disassembled)

B-G-1 B6.80 Pressurizer Visual None 100% N/A Deferral N/A N/A N/A N/A Nuts, Bushings, Permissible and Washers B-G-1 B6.90 SG Bolts and Volumetric None 100% N/A Deferral N/A N/A N/A N/A Studs Permissible B-G-1 B6.100 SG Flange Visual None 100% N/A Deferral N/A N/A N/A N/A Surface Permissible (disassembled)

B-G-1 B6.110 SG Nuts, Visual None 100% N/A Deferral N/A N/A N/A N/A Bushings, and Permissible Washers B-G-1 B6.120 Heat Exch Bolts Volumetric None 100% N/A Deferral N/A N/A N/A N/A and Studs Permissible

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 36 of 125 Appendix A (Page 11 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-G-1 B6.130 Heat Exch Visual None 100% N/A Deferral N/A N/A N/A N/A Flange Surfaces Permissible (disassembled)

B-G-1 B6.140 Heat Exch Nuts, Visual None 100% N/A Deferral N/A N/A N/A N/A Bushings, and Permissible Washers B-G-1 B6.150 Piping Bolts and Volumetric None 100% N/A Deferral N/A N/A N/A N/A Studs Permissible B-G-1 B6.160 Piping Flange Visual None 100% N/A Deferral N/A N/A N/A N/A Surfaces Permissible (disassembled)

B-G-1 B6.170 Piping Nuts, Visual None 100% N/A Deferral N/A N/A N/A N/A Bushings, and Permissible Washers B-G-1 B6.180 RCP Bolts and UT 4 Pumps / Pump 1 set of 24 Deferral When pump When pump When pump ISI-0447-C selected for is is is Studs 24 bolts per bolts Permissible exam under disassembled disassembled disassembled Pump B-L-2

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 37 of 125 Appendix A (Page 12 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-G-1 B6.190 RCP Flange VT-1 4 Pumps Pump 1 Pump Deferral when dis- when dis- when dis- ISI-0447-C selected for Surface Permissible assembled assembled assembled exam under (disassembled) B-L-2 B-G-1 B6.200 RCP Nuts, Visual None Pump N/A Deferral N/A N/A N/A N/A selected for Bushings, and Permissible exam under Washers B-L-2 B-G-1 B6.210 Valve Bolts and Volumetric None Valve(s) N/A Deferral N/A N/A N/A N/A selected for Studs Permissible exam under B-M-2 B-G-1 B6.220 Valve Flange Visual None Valve(s) N/A Deferral N/A N/A N/A N/A selected for Surface Permissible exam under (disassembled) B-M-2 B-G-1 B6.230 Valve Nuts, Visual None Valve(s) N/A Deferral N/A N/A N/A N/A selected for Bushings, and Permissible exam under Washers B-M-2 B-G-2 Pressure Retaining Bolting, 2 and Less in Diameter B-G-2 B7.10 RV Bolts, Studs, VT-1 None 100% N/A Deferral Not N/A N/A N/A N/A and Nuts Permissible

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-G-2 B7.20 Pressurizer VT-1 1 Manway / 100% 1 Manway Deferral Not 0 1 Manway 0 CHM-2570-C Bolts, Studs, 16 Bolts / 16 Bolts Permissible and Nuts B-G-2 B7.30 SG Bolts, VT-1 4 SG / 2 100% 1 SG / 2 Deferral Not 1 Manway 0 1 Manway CHM-2660-C Studs, and Nuts Manways / 1 SG Manways / Permissible 16 bolts ea. 16 bolts ea.

B-G-2 B7.40 Heat Exch VT-1 None 100% None Deferral Not N/A N/A N/A N/A Bolts, Studs, Permissible and Nuts B-G-2 B7.50 Piping Bolts, Studs, and Nuts B7.50 CVCS VT-1 4 When dis- 4 Deferral Not 1 or when 1 or when 2 or when ISI-0050-C assembled disassembled disassembled disassembled connections Permissible B7.50 RCS VT-1 5 When dis- 5 Deferral Not 1 or when 2 or when 2 or when ISI-0365-C assembled disassembled disassembled disassembled connections Permissible B7.50 RHRS VT-1 None When dis- N/A Deferral Not N/A N/A N/A N/A assembled Permissible

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 39 of 125 Appendix A (Page 14 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B7.50 SIS VT-1 4 When dis- 4 Deferral Not 1 or when 1 or when 2 or when CHM-2758-C assembled disassembled disassembled disassembled connections Permissible B-G-2 B7.60 Pumps Bolts, VT-1 4 Pumps / 2 Pump(s) 1 set 12 Deferral Not When dis- When dis- 1 set 12 ISI-0447-C selected for Studs, and Nuts sets / 1 set bolts and 1 Permissible assembled assembled bolts and 1 exam under 12 bolts and B-L-2 set 8 bolts set 8 bolts 1 set 8 bolts or when disassembled B-G-2 B7.70 Valves Bolts, See Note 2 at end of Studs, and Nuts Appendix A B7.70 CVCS VT-1 None Valve(s) N/A Deferral Not N/A N/A N/A N/A selected for Permissible exam under B-M-2 B7.70 RCS VT-1 1 Group / Valve(s) At least 1 Deferral Not 0 or when 0 or when 1 valve in ISI-0365-C selected for disassembled disassembled 3 Valves valve per Permissible group or exam under when B-M-2 group (1) disassembled

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 40 of 125 Appendix A (Page 15 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B7.70 RHRS VT-1 4 Groups / Valve(s) At least 1 Deferral Not 1 valve in 1 valve in 1 1 valve in CHM-2636-C selected for 8 Valves valve per Permissible 1 group or group or when each of 2 exam under when disassembled B-M-2 group (4) groups or disassembled (not in 1st when period) disassembled (not in 1st or 2nd period)

B7.70 SIS VT-1 3 Groups / Valve(s) At least 1 Deferral Not 1 valve in 1 valve in 1 1 valve in CHM-2758-C selected for 18 Valves valve per Permissible 1 group or group or when 1 group or exam under when disassembled when B-M-2 group (3) disassembled (not in 1st disassembled period) (not in 1st or 2nd period)

B-J Pressure Retaining Welds in Piping B-J B9.10 Piping Welds NPS 4 or Larger B-J B9.11 Piping Circ. Surface Welds NPS 4 or and Larger Volumetric B9.11 RCS Main PT & UT 45 25% 11 Deferral Not 4 4 3 CHM-2547-C Permissible

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 41 of 125 Appendix A (Page 16 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B9.11 RCS PT & UT 66 25% 17 Deferral Not 6 5 6 ISI-0365-C Permissible B9.11 RV Aux Head PT & UT 12 25% 3 Deferral Not 0 0 3 CHM-2684-C Adapter Welds Permissible CHM-2685-C B9.11 RHRS PT & UT 60 25% 15 Deferral Not 5 5 5 CHM-2636-C Permissible B9.11 SIS PT & UT 102 25% 26 Deferral Not 9 9 8 CHM-2758-C Permissible B-J B9.20 Piping Welds less than NPS 4 B-J B9.21 Circumferential Surface Welds other than PWR HPSI B9.21 CVCS PT 97 25% 24 Deferral Not 8 8 8 ISI-0005-C Permissible ISI-0050-C B9.21 RCS PT 10 25% 2 Deferral Not 0 2 0 CHM-2547-C Permissible

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B9.21 RCS Main PT 4 25% 1 Deferral Not 1 0 0 ISI-0365-C Permissible B-J B9.22 Circumferential PT 50 10% 6 Deferral Not 0 0 6 CHM-2758-C Welds in PWR Permissible HPSI B-J B9.30 Branch Pipe Connection Welds B-J B9.31 Branch Pipe Surface Connection and Welds NPS 4 or Volumetric Larger B9.31 CVCS PT & UT None 25% N/A Deferral Not N/A N/A N/A N/A Permissible B9.31 RCS PT & UT 2 25% 0 Deferral Not 0 0 0 ISI-0365-C Permissible B9.31 RCS Main PT & UT 1 25% 1 Deferral Not 1 0 0 CHM-2547-C Permissible

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 43 of 125 Appendix A (Page 18 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B9.31 RHRS PT & UT 3 25% 1 Deferral Not 0 1 0 CHM-2636-C Permissible B9.31 SIS PT & UT 5 25% 1 Deferral Not 0 0 1 CHM-2758-C Permissible B-J B9.32 Branch Pipe Surface Connection Welds Less than NPS 4 B9.32 CVCS PT 3 25% 1 Deferral Not 1 0 0 ISI-0005-C Permissible B9.32 RCS PT 3 25% 1 Deferral Not 0 1 0 ISI-0365-C Permissible B9.32 RCS Main PT 21 25% 5 Deferral Not 1 0 4 CHM-2547-C Permissible B9.32 RHRS PT 2 25% 1 Deferral Not 0 1 0 CHM-2636-C Permissible B9.32 SIS PT 13 25% 3 Deferral Not 1 2 0 CHM-2758-C Permissible

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 44 of 125 Appendix A (Page 19 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-J B9.40 Piping Socket Surface Welds B9.40 CVCS PT 122 25% 31 Deferral Not 10 11 10 ISI-0050-C Permissible B9.40 RCS PT 54 25% 14 Deferral Not 5 4 5 ISI-0365-C Permissible B9.40 RCS Main PT 20 25% 5 Deferral Not 2 1 2 CHM-2547-C Permissible B9.40 RHRS PT 18 25% 4 Deferral Not 1 1 2 CHM-2636-C Permissible B9.40 SIS PT 253 25% 63 Deferral Not 21 21 21 CHM-2758-C Permissible B-K Welded Attachments for Vessels, Piping, Pumps, and Valves B-K B10.10 Pressure Surface Vessels Welded Attachments

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 45 of 125 Appendix A (Page 20 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B10.10 Reactor Vessel MT None See Note 3 N/A Deferral Not N/A N/A N/A N/A at end of Permissible Appendix A whenever component support deformation is identified B10.10 Pressurizer MT 1 See Note 3 1 Deferral Not 0 0 1 CHM-2570-C at end of Support Skirt Permissible Appendix A whenever component support deformation is identified B10.10 Pressurizer MT 1 Prz / 4 IAs See Note 3 0 Deferral Not 0 0 0 CHM-2570-C at end of Seismic Lugs (Support Permissible Appendix A Skirt whenever component Selected) support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 46 of 125 Appendix A (Page 21 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B10.10 Steam MT None See Note 3 N/A Deferral Not N/A N/A N/A N/A at end of Generator Permissible Appendix A whenever component support deformation is identified B-K B10.20 Piping Welded Surface Attachments B10.20 CVCS Surface None See Note 1 N/A Deferral Not N/A N/A N/A N/A at end of Permissible Appendix A whenever component support deformation is identified B10.20 RCS PT 2 See Note 1 1 Deferral Not 1 0 0 ISI-0364-C at end of Permissible Appendix A whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 47 of 125 Appendix A (Page 22 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B10.20 RCS Main Surface None See Note 1 N/A Deferral Not N/A N/A N/A N/A at end of Permissible Appendix A whenever component support deformation is identified B10.20 RHRS Surface None See Note 1 N/A Deferral Not N/A N/A N/A N/A at end of Permissible Appendix A whenever component support deformation is identified B10.20 SIS Surface None See Note 1 N/A Deferral Not N/A N/A N/A N/A at end of Permissible Appendix A whenever component support deformation is identified

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-K B10.30 Pumps Welded Surface None See Note 1 N/A Deferral Not N/A N/A N/A N/A at end of Attachments Permissible Appendix A whenever component support deformation is identified B-K B10.40 Valve Welded Surface None See Note 1 N/A Deferral Not N/A N/A N/A N/A at end of Attachments Permissible Appendix A whenever component support deformation is identified B-L-1 Pressure Retaining Welds in Pump Casings B-L-1 B12.10 Reactor Coolant VT-1 4 1 Pump 1 Deferral 0 0 1 ISI-0048-C Pump Casing in each Permissible Welds group B-L-2 Pump Casings

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 49 of 125 Appendix A (Page 24 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-L-2 B12.20 Reactor Coolant VT-3 4 1 Pump 1 When Dis- When When When ISI-0048-C disassembled disassembled disassembled Pump Casing in each assembled Internal group Surfaces B-M-1 Pressure Retaining Welds in Valve Bodies B-M-1 B12.30 Valves (less Surface None 1 Valve N/A Deferral N/A N/A N/A N/A than 4 NPS) in each Permissible Body Welds group B-M-1 B12.40 Valves (NPS 4 Volumetric None 1 Valve N/A Deferral N/A N/A N/A N/A or larger) Body in each Permissible Welds group B-M-2 Valve Bodies B-M-2 B12.50 Valves (greater Visual See Note 2 at end of Appendix A.

than 4 NPS)

Body Internal Surfaces B12.50 CVCS VT-3 None 1 valve in At least 1 Only when N/A N/A N/A N/A each group (when dis- valve per disassembled assembled) group (0)

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ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B12.50 RCS VT-3 One Group 1 valve in At least 1 Only when Only when Only when Only when ISI-0365-C each group disassembled disassembled disassembled (when dis- valve per disassembled assembled) group (1)

B12.50 RHRS VT-3 Four 1 valve in At least 1 Only when Only when Only when Only when CHM-2636-C each group disassembled disassembled disassembled Groups (when dis- valve per disassembled assembled) group (4)

B12.50 SIS VT-3 Three 1 valve in At least 1 Only when Only when Only when Only when CHM-2758-C each group disassembled disassembled disassembled Groups (when dis- valve per disassembled assembled) group (3)

B-N-1 Interior of Reactor Vessel B-N-1 B13.10 RV Interior VT-3 1 100% 1 (each Deferral Not 1 1 1 ISI-0427-C Accessible At 3 year period) Permissible Areas intervals B-N-2 Integrally Welded Core Support Structure and Interior Attachments to Reactor Vessels B-N-2 B13.50 RV Interior Visual None Accessible N/A Deferral N/A N/A N/A N/A Attachments Welds Permissible Within Beltline Region

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 51 of 125 Appendix A (Page 26 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER B-N-2 B13.60 RV Interior VT-3 6 Accessible 6 Deferral 0 0 6 ISI-0427-C Attachments Welds Permissible Beyond Beltline Region B-N-3 Removable Core Support Structures B-N-3 B13.70 RV Core VT-3 1 Accessible 1 Deferral 0 0 1 ISI-0427-C Support Surfaces Permissible Structure Accessible Surfaces B-O Pressure Retaining Welds in Control Rod Housing B-O B14.10 RV Welds in UT or PT 78 CRD 10% of 2 Deferral 0 0 2 CHM-2684-C CRD Housings Housings / Peripheral Permissible 20 Housings Peripheral Housings

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 52 of 125 Appendix A (Page 27 of 27)

ISI Planning/Scheduling Table for ASME Class 1 Components Note 1: For Examination Category B-K, Piping, Pump, and Valve Integral Attachments the percentage examined during an inspection interval is based on 10% of the integral attachments on non-exempt piping (per system basis). 100% of the required areas of each selected welded attachment are required to be examined.

Note 2: Reference Appendix E for valve groupings and the list of valves subject to Examination Category B-G-2 or B-M-2 as applicable.

Note 3: For Examination Category B-K, Pressure Vessels Integral Attachments only one integral attachment of one of multiple vessels is required to be examined. 100% of the required areas of each selected welded attachment are required to be examined.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 53 of 125 Appendix B (Page 1 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C-A Pressure Retaining Welds in Pressure Vessels C-A C1.10 Pressure Volumetric Retaining Shell or PT if <

Circumferential 0.2 inches Welds thick C1.10 Residual Heat UT 2 RHRHX / All in 1 1 Each 0 1 0 CHM-2662-C vessel at Removal Heat 1 weld per Inspection dis-Exchanger RHRHX continuity Interval C1.10 Containment UT 2 CSHX / All in 1 1 Each 0 0 1 ISI-0371-C vessel at Spray Heat 1 weld per Inspection dis-Exchanger CSHX continuity Interval C1.10 Seal Water PT 1 All in 1 1 Each 1 0 0 ISI-0484-C vessel at Heat Exchanger Inspection dis-continuity Interval C1.10 Seal Water Volumetric None All in 1 N/A Each N/A N/A N/A N/A vessel at Filter Inspection dis-continuity Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 54 of 125 Appendix B (Page 2 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C1.10 Seal Water Volumetric None All in 1 N/A Each N/A N/A N/A N/A vessel at Injection Filter Inspection dis-continuity Interval C1.10 Boron Injection Volumetric None All in 1 N/A Each N/A N/A N/A N/A vessel at Tank Inspection dis-continuity Interval C-A C1.20 Pressure Volumetric Retaining Head or PT if <

Circumferential 0.2 inches Welds thick C1.20 Steam UT 4 SG / 1 Head-to- 1 Each 0 0 1 CHM-2660-C Shell Weld Inspection Generator weld per SG in 1 vessel Interval C1.20 Residual Heat UT 2 RHRHX / Head-to- 1 Each 0 1 0 CHM-2662-C Shell Welds Inspection Removal Heat 1 weld per in 1 vessel Interval Exchanger RHRHX C1.20 Containment UT 2 CSHX / 1 Head-to- 1 Each 0 0 1 ISI-0371-C Shell Welds Inspection Spray Heat weld per in 1 vessel Interval Exchanger CSHX

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 55 of 125 Appendix B (Page 3 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C1.20 Seal Water PT 1 Head-to- 1 Each 0 0 1 ISI-0484-C Shell Welds Inspection Heat Exchanger in 1 vessel Interval C1.20 Seal Water PT 2 Head-to- 2 Each 2 0 0 ISI-0375-C Shell Welds Inspection Filter in 1 vessel Interval C1.20 Seal Water UT 2 SWIF / 1 Head-to- 1 Each 1 0 0 ISI-0375-C Shell Welds Inspection Injection Filter weld per in 1 vessel Interval SWIF C1.20 Boron Injection UT 2 Head-to- 2 Each 0 2 0 ISI-0053-C Shell Welds Inspection Tank in 1 vessel Interval C-A C1.30 Tubesheet-to- Volumetric Shell Weld or PT if <

0.2 inches thick C1.30 Steam UT 4 SG / 1 Tubesheet- 1 Each 0 0 1 CHM-2660-C to-Shell Inspection Generator weld per SG Weld in 1 Interval vessel

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 56 of 125 Appendix B (Page 4 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C1.30 Residual Heat Volumetric None Tubesheet- N/A Each N/A N/A N/A N/A to-Shell Removal Heat Inspection Weld in 1 Exchanger vessel Interval C1.30 Containment Volumetric None Tubesheet- N/A Each N/A N/A N/A N/A to-Shell Spray Heat Inspection Weld in 1 Exchanger vessel Interval C1.30 Seal Water Volumetric None Tubesheet- N/A Each N/A N/A N/A N/A to-Shell Heat Exchanger or Surface Inspection Weld in 1 vessel Interval C1.30 Seal Water Volumetric None Tubesheet- N/A Each N/A N/A N/A N/A to-Shell Filter or Surface Inspection Weld in 1 vessel Interval C1.30 Seal Water Volumetric None Tubesheet- N/A Each N/A N/A N/A N/A to-Shell Injection Filter Inspection Weld in 1 vessel Interval C-B Pressure Retaining Nozzle Welds in Vessels

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 57 of 125 Appendix B (Page 5 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C-B C2.10 Nozzles in vessels less than or equal to 1/2 nom thick C-B C2.11 Nozzle-to-Shell (or Surface Head) Weld > NPS 4 in Vessels <= 1/2 thick C2.11 Seal Water PT None All nozzles N/A Each N/A N/A N/A N/A at terminal Inspection Heat Exchanger ends of Interval piping runs in 1 vessel C2.11 Seal Water PT None All nozzles N/A Each N/A N/A N/A N/A at terminal Inspection Filter ends of Interval piping runs in 1 vessel C-B C2.20 Nozzles without reinforcing plate in vessels greater than 1/2 nom. thick C-B C2.21 Nozzles-to-shell Surface Welds > NPS 4 and Volumetric

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 58 of 125 Appendix B (Page 6 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C2.21 Steam MT & UT 4 SG / 1 FW All nozzles 2 Each 0 0 2 CHM-2660-C at terminal Generator and 1 AFW Inspection ends of (One FW piping runs Interval and one in 1 vessel AFW)

C2.21 Residual Heat PT & UT 2 RHRHX / All nozzles 2 Each 2 0 0 CHM-2662-C at terminal Removal Heat 2 nozzles Inspection ends of Exchanger each piping runs Interval in 1 vessel C2.21 Boron Injection PT & UT 2 All nozzles 2 Each 0 2 0 ISI-0053-C at terminal Tank Inspection ends of piping runs Interval in 1 vessel C2.21 Seal Water Surface None All nozzles N/A Each N/A N/A N/A N/A at terminal Injection Filter and Inspection ends of Volumetric piping runs Interval in 1 vessel C-B C2.22 Nozzle Inside Volumetric Radius Section Nozzle > 12 NPS

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 59 of 125 Appendix B (Page 7 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C2.22 Steam UT 4 SG / 1 FW All nozzles 1 Each 0 0 1 CHM-2660-C at terminal Generator nozzle per Inspection ends of SG piping runs Interval in 1 vessel C2.22 Residual Heat UT 2 RHRHX / All nozzles 2 Each 2 0 0 CHM-2662-C at terminal Removal Heat 2 nozzles Inspection ends of Exchanger each piping runs Interval in 1 vessel C2.22 Boron Injection Volumetric None All nozzles N/A Each N/A N/A N/A N/A at terminal Tank Inspection ends of piping runs Interval in 1 vessel C-B C2.30 Nozzles with Reinforcing Plate in Vessels > 1/2 nom.

thickness C-B C2.31 Reinforcing Plate Surface Welds to Nozzle and Vessel

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 60 of 125 Appendix B (Page 8 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C2.31 Containment PT 2 CSHX / 2 All nozzles 2 Each 0 0 2 ISI-0371-C at terminal Spray Heat nozzles Inspection ends of Exchanger each piping runs Interval in 1 vessel C-B C2.32 Nozzle-to-Shell (or Volumetric Head) Weld when inside of Vessel is Accessible C2.32 Containment UT 2 CSHX / 2 All nozzles 2 Each 0 2 0 ISI-0371-C at terminal Spray Heat nozzles Inspection ends of Exchanger each piping runs Interval in 1 vessel C-B C2.33 Nozzle-to-Shell (or Visual None All nozzles N/A Each N/A N/A N/A N/A Head) Weld when at terminal Inspection inside of Vessel is ends of Inaccessible piping runs Period in 1 vessel C-C Welded Attachments for Vessels, Piping, Pumps, and Valves C-C C3.10 Pressure Surface Vessels Welded Attachments

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 61 of 125 Appendix B (Page 9 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C3.10 Steam Surface None See Note 2 N/A Each N/A N/A N/A N/A at the end Generator Inspection of Appendix B. Interval and whenever component support deformation is identified C3.10 Residual Heat PT 2 RHRHX / See Note 2 1 IA on Each 0 1 0 CHM-2662-C at the end Inspection Removal Heat 2 IAs on one of Appendix Interval and Exchanger each B. RHRHX whenever component support deformation is identified C3.10 Containment PT 2 CSHX / 1 See Note 2 1 IA on Each 0 0 1 ISI-0371-C at the end Inspection Spray Heat IA on each one CSHX of Appendix Interval and Exchanger B. whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 62 of 125 Appendix B (Page 10 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C3.10 Seal Water PT 1 SWHX / 2 See Note 2 1 IA on Each 0 0 1 ISI-0484-C at the end Inspection Heat Exchanger IAs one of Appendix Interval and B. SWHX whenever component support deformation is identified C3.10 Seal Water PT 1 SWF / 4 See Note 2 1 IA on Each 1 0 0 ISI-0487-C at the end Inspection Filter IAs one SWF of Appendix Interval and B. whenever component support deformation is identified C3.10 Seal Water PT 2 SWIF / 3 See Note 2 1 IA on Each 0 1 0 ISI-0486-C at the end Inspection Injection Filter IAs on each one SWIF of Appendix Interval and B. whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 63 of 125 Appendix B (Page 11 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C3.10 Boron Injection PT 1 BIT / 4 IAs See Note 2 1 IA on the Each 0 1 0 ISI-0053-C at the end Inspection Tank BIT of Appendix Interval and B. whenever component support deformation is identified C-C C3.20 Piping Weld Surface Attachments C3.20 AFWS MT 8 See Note 1 1 Each 1 0 0 ISI-0062-C at end of Inspection Appendix B Interval and (10%) whenever component support deformation is identified C3.20 CSS PT 8 See Note 1 1 Each 0 0 1 ISI-0423-C at end of Inspection Appendix B Interval and (10%) whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 64 of 125 Appendix B (Page 12 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C3.20 CVCS PT 23 See Note 1 3 Each 1 1 1 ISI-0424-C at end of Inspection Appendix B (10%) Interval and whenever component support deformation is identified C3.20 FWS Surface None See Note 1 N/A Each N/A N/A N/A N/A at end of Inspection Appendix B Interval and (10%) whenever component support deformation is identified C3.20 MSS MT 8 See Note 1 1 Each 0 1 0 ISI-0011-C at end of Inspection Appendix B Interval and (10%) whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 65 of 125 Appendix B (Page 13 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C3.20 RHRS PT 6 See Note 1 1 Each 0 0 1 ISI-0020-C at end of Inspection ISI-0107-C Appendix B Interval and (10%) whenever component support deformation is identified C3.20 SIS PT 30 See Note 1 3 Each 1 1 1 ISI-0021-C at end of Inspection ISI-0440-C Appendix B Interval and (10%) whenever component support deformation is identified C-C C3.30 Pump Welded Surface Attachments C3.30 Centrifugal PT 2 CCP / 4 See Note 1 All IAs on Each 0 1 CCP 0 ISI-0118-C at end of Inspection Charging Pump IAs on each one CCP Appendix B Interval and (4 IAs)

(CCP) (10%) whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 66 of 125 Appendix B (Page 14 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C3.30 Reciprocating Surface None See Note 1 N/A Each N/A N/A N/A N/A at end of Inspection Charging Pump Appendix B Interval and (10%) whenever component support deformation is identified C3.30 Containment Surface None See Note 1 N/A Each N/A N/A N/A N/A at end of Inspection Spray Pump Appendix B Interval and (10%) whenever component support deformation is identified C3.30 Residual Heat PT 2 RHRP / 3 See Note 1 All IAs on Each 0 0 1 RHRP ISI-0117-C at end of Inspection Removal Pump IAs on each one RHRP Appendix B Interval and (3 IAs)

(RHRP) (10%) whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 67 of 125 Appendix B (Page 15 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C3.30 Safety Injection Surface None See Note 1 N/A Each N/A N/A N/A N/A at end of Inspection Pump Appendix B Interval and (10%) whenever component support deformation is identified C-C C3.40 Valve Welded Surface None See Note 1 N/A Each N/A N/A N/A N/A at end of Inspection Attachments Appendix B Interval and (10%) whenever component support deformation is identified C-D Pressure Retaining Bolting greater than 2-inches in Diameter C-D C4.10 Pressure Vessel Volumetric or Surface when Bolts and Studs dis-

>2 diameter assembled C4.10 Steam Volumetric or None 100% of one N/A Each N/A N/A N/A N/A Surface when connection of Generator 1 component Inspection dis- Interval assembled

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 68 of 125 Appendix B (Page 16 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C4.10 Residual Heat Volumetric or None 100% of one N/A Each N/A N/A N/A N/A Surface when connection of Removal Heat 1 component Inspection dis- Interval Exchanger assembled C4.10 Containment Volumetric or None 100% of one N/A Each N/A N/A N/A N/A Surface when connection of Spray Heat 1 component Inspection dis- Interval Exchanger assembled C4.10 Seal Water Volumetric or None 100% of one N/A Each N/A N/A N/A N/A Surface when connection of Heat Exchanger 1 component Inspection dis- Interval assembled C4.10 Seal Water Volumetric or None 100% of one N/A Each N/A N/A N/A N/A Surface when connection of Filter 1 component Inspection dis- Interval assembled C4.10 Seal Water Volumetric or None 100% of one N/A Each N/A N/A N/A N/A Surface when connection of Injection Filter 1 component Inspection dis- Interval assembled C4.10 Boron Injection UT or MT 1 BIT / 1 100% of one 1 Each 0 1 0 ISI-0053-C connection of Tank connection 1 component Inspection (16 bolts) Interval (16 bolts)

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 69 of 125 Appendix B (Page 17 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C-D C4.20 Piping Bolts and Volumetric or None 100% of one N/A Each N/A N/A N/A N/A Surface when connection of Studs > 2 dia. 1 component Inspection dis- Interval assembled C-D C4.30 Pumps Bolts Volumetric or None 100% of one N/A Each N/A N/A N/A N/A Surface when connection of and Studs > 2 1 component Inspection dis- Interval dia. assembled C-D C4.40 Valves Bolts Volumetric or None 100% of one N/A Each N/A N/A N/A N/A Surface when connection of and Studs > 2 1 component Inspection dis- Interval dia. assembled C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High See Note 3 at the end of Appendix B.

Alloy Piping C-F-1 C5.10 Piping welds >= 3/8 nom. wall thickness for piping > NPS 4 C-F-1 C5.11 Circumferential Surface Weld and Volumetric

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 70 of 125 Appendix B (Page 18 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C5.11 CSS PT & UT 197 7.5% 16 Each 5 5 6 ISI-0375-C Inspection ISI-0400-C Interval ISI-0421-C C5.11 CVCS PT & UT 61 7.5% 5 Each 1 2 2 ISI-0375-C Inspection ISI-0421-C Interval C5.11 RHRS PT & UT 290 7.5% 22 Each 8 6 8 CHM-2636-C Inspection ISI-0421-C Interval C5.11 SIS PT & UT 285 7.5% 22 Each 7 7 8 CHM-2758-C Inspection ISI-0375-C Interval C-F-1 C5.20 Piping welds > 1/5 nom. wall thickness for piping >= NPS 2 and <= NPS 4 C-F-1 C5.21 Circumferential Surface Weld and Volumetric

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 71 of 125 Appendix B (Page 19 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C5.21 CSS PT & UT 1 7.5% 0 Each 0 0 0 ISI-0400-C Inspection Interval C5.21 CVCS PT & UT 394 7.5% 32 Each 11 10 11 ISI-0375-C Inspection Interval C5.21 RHRS PT & UT 41 7.5% 4 Each 1 0 3 ISI-0375-C Inspection ISI-0421-C Interval C5.21 SIS PT & UT 241 7.5% 19 Each 6 6 7 ISI-0375-C Inspection ISI-0421-C Interval C-F-1 C5.30 Socket Welds Surface C5.30 CSS PT 24 7.5% 2 Each 1 0 1 ISI-0375-C Inspection Interval C5.30 CVCS PT 295 7.5% 24 Each 8 8 8 ISI-0375-C Inspection Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 72 of 125 Appendix B (Page 20 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C5.30 RHRS PT 4 7.5% 1 Each 0 0 1 ISI-0375-C Inspection Interval C5.30 SIS PT 280 7.5% 21 Each 7 7 7 ISI-0375-C Inspection Interval C-F-1 C5.40 Pipe Branch Connections of Branch Piping >=

NPS 2 C-F-1 C5.41 Circumferential Surface Welds C5.41 CSS PT 4 7.5% 1 Each 0 0 1 ISI-0400-C Inspection Interval C5.41 CVCS PT 3 7.5% 1 Each 1 0 0 ISI-0375-C Inspection Interval C5.41 RHRS PT 6 7.5% 1 Each 0 1 0 ISI-0375-C Inspection Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 73 of 125 Appendix B (Page 21 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C5.41 SIS PT 8 7.5% 1 Each 0 0 1 ISI-0375-C Inspection Interval C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel Piping See Note 3 at the end of Appendix B.

C-F-2 C5.50 Piping welds >= 3/8 nominal thickness for piping > NPS 4 C-F-2 C5.51 Circumferential Surface Welds and Volumetric C5.51 FWS MT & UT 286 7.5% 24 Each 8 8 8 CHM-2671-C Inspection Interval C5.51 MSS MT & UT 139 7.5% 12 Each 4 4 4 CHM-2669-C Inspection Interval C-F-2 C5.60 Piping welds >1/5 nominal wall thickness for piping

>= NPS 2 and <=

NPS 4

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 74 of 125 Appendix B (Page 22 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C-F-2 C5.61 Circumferential Surface Welds and Volumetric C5.61 AFWS MT & UT 156 7.5% 12 Each 4 4 4 CHM-2671-C Inspection Interval C-F-2 C5.70 Socket Welds Surface None 7.5% N/A Each N/A N/A N/A N/A Inspection Interval C-F-2 C5.80 Pipe Branch Connection of branch piping >=

NPS 2 C-F-2 C5.81 Circumferential Surface Weld C5.81 AFWS MT None 7.5% N/A Each N/A N/A N/A N/A Inspection Interval C5.81 FWS MT None 7.5% N/A Each N/A N/A N/A N/A Inspection Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 75 of 125 Appendix B (Page 23 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C5.81 MSS MT None 7.5% N/A Each N/A N/A N/A N/A Inspection Interval C-G Pressure Retaining Welds in Pumps and Valves C-G C6.10 Pump Casing Surface None 100% of N/A Each N/A N/A N/A N/A welds in Inspection Weld component Interval s in piping runs examined under C-F C-G C6.20 Valve Body Surface See Note 4 at the end of Welds Appendix B C6.20 FWS MT 10 100% of 1 Each 0 1 0 ISI-0082-C welds in Inspection one valve in Interval piping runs examined under C-F

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 76 of 125 Appendix B (Page 24 of 24)

ISI Planning/Scheduling Table for ASME Class 2 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER C6.20 MSS MT 20 100% of 1 Each 1 0 0 ISI-0081-C welds in Inspection one valve in Interval piping runs examined under C-F Note 1: For Examination Category C-C, Piping, Pump, and Valve Integral Attachments the percentage examined during an inspection interval is based on 10% of the integral attachments associated with the component supports selected for examination under IWF-2510. 100% of the required areas of each selected welded attachment are required to be examined.

Note 2: For Examination Category C-C, Pressure Vessel Integral Attachments only one integral attachment of only one of the multiple vessels of similar design, function, and service is required to be examined. 100% of the required areas of each selected welded attachement are required to be examined.

Note 3: Selection includes 7.5% of all welds not exempted by IWC-1220 distributed by Item Number and system in this Exam Category, but not including welds excluded by wall thickness.

Note 4: Reference Appendix E for the listing of valves subject to Examination Category C-G.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 77 of 125 Appendix C (Page 1 of 8)

ISI Planning/Scheduling Table for ASME Class 3 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER D-A Integral Attachments for Class 3 Vessels, Piping, Pumps, and Valves D-A D1.10 Pressure Vessels Visual Integrally Welded Attachments D1.10 Containment VT-1 2 CSHX See Note 2 All IAs on Each 0 0 All IAs on ISI-0371-C Spray Heat at the end 1 CSHX Inspection 1 CSHX Exchanger of Appendix C. Interval and (CSHX) whenever component support deformation is identified D1.10 Nonregenerative VT-1 1 NRLHX See Note 2 All IAs on Each 0 All IAs on 0 ISI-0497-C Letdown Heat at the end the Inspection the NRLHX Exchanger of Appendix C. NRLHX Interval and (NRLHX) whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 78 of 125 Appendix C (Page 2 of 8)

ISI Planning/Scheduling Table for ASME Class 3 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER D1.10 Component VT-1 1 CCST See Note 2 All IAs on Each 0 All IAs on 0 ISI-0496-C Cooling Surge at the end the CCST Inspection the CCST Tank (CCST) of Appendix C. Interval and whenever component support deformation is identified D1.10 Essential Raw VT-1 4 ERCWS See Note 2 All IAs on Each All IAs on 0 0 ISI-0489-C Cooling Water at the end one Inspection one System Strainer of Appendix C. ERCWS Interval and ERCWS (ERCWS) whenever component support deformation is identified D1.10 Component VT-1 3 CCHX See Note 2 All IAs on Each 0 All IAs on 1 0 ISI-0494-C Cooling Heat at the end 1 CCHX Inspection CCHX Exchanger of Appendix C. Interval and (CCHX) whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 79 of 125 Appendix C (Page 3 of 8)

ISI Planning/Scheduling Table for ASME Class 3 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER D1.10 Fuel Pool Cooling VT-1 2 FPCCHX See Note 2 All IAs on Each 0 0 All IAs on ISI-0372-C and Cleaning at the end 1 Inspection 1 System Spent of Appendix C. FPCCHX Interval and FPCCHX Fuel Pit Heat whenever Exchanger component (FPCCHX) support deformation is identified D1.10 RHR Heat VT-1 2 RHRSHX See Note 2 All IAs on Each 0 0 All IAs on CHM-2662-C Exchanger at the end 1 Inspection 1 (RHRSHX) of Appendix C. RHRSHX Interval and RHRSHX whenever component support deformation is identified D1.10 Seal Water Heat VT-1 1 SWHX See Note 2 All IAs on Each All IAs on 0 0 ISI-0484-C Exchanger at the end the SWHX Inspection the SWHX (SWHX) of Appendix C. Interval and whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 80 of 125 Appendix C (Page 4 of 8)

ISI Planning/Scheduling Table for ASME Class 3 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER D1.10 High Pressure VT-1 2 HPFPS See Note 2 All IAs on Each All IAs on 0 0 ISI-0502-C Fire Protection at the end 1 HPFPS Inspection 1 HPFPS Strainer (HPFPS) of Appendix C. Interval and whenever component support deformation is identified D-A D1.20 Piping Integrally Visual Welded Attachments D1.20 AFWS VT-1 24 See Note 1 3 Each 0 1 2 ISI-0111-C at end of Inspection Appendix C Interval and (10%) whenever component support deformation is identified D1.20 CCS VT-1 54 See Note 1 6 Each 2 2 2 ISI-0252-C at end of Inspection Appendix C Interval and (10%) whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 81 of 125 Appendix C (Page 5 of 8)

ISI Planning/Scheduling Table for ASME Class 3 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER D1.20 ERCWS VT-1 158 See Note 1 16 Each 5 5 6 ISI-0112-C at end of Inspection Appendix C Interval and (10%) whenever component support deformation is identified D1.20 FPCS VT-1 11 See Note 1 2 Each 1 1 0 ISI-0110-C at end of Inspection Appendix C Interval and (10%) whenever component support deformation is identified D1.20 HPFPS VT-1 8 See Note 1 1 Each 0 1 0 ISI-0500-C at end of Inspection Appendix C Interval and (10%) whenever component support deformation is identified D-A D1.30 Pumps Integrally Visual Welded Attachments

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 82 of 125 Appendix C (Page 6 of 8)

ISI Planning/Scheduling Table for ASME Class 3 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER D1.30 Motor Driven VT-1 None See Note 1 N/A Each N/A N/A N/A N/A Auxiliary at end of Inspection Feedwater Pump Appendix C Interval and (10%) whenever component support deformation is identified D1.30 Turbine Driven VT-1 None See Note 1 N/A Each N/A N/A N/A N/A Auxiliary at end of Inspection Feedwater Pump Appendix C Interval and (10%) whenever component support deformation is identified D1.30 Component VT-1 None See Note 1 N/A Each N/A N/A N/A N/A Cooling System at end of Inspection Pump Appendix C Interval and (10%) whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 83 of 125 Appendix C (Page 7 of 8)

ISI Planning/Scheduling Table for ASME Class 3 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER D1.30 ERCW Pump VT-1 None See Note 1 N/A Each N/A N/A N/A N/A at end of Inspection Appendix C Interval and (10%) whenever component support deformation is identified D1.30 ERCW Screen VT-1 None See Note 1 N/A Each N/A N/A N/A N/A Wash Pump at end of Inspection Appendix C Interval and (10%) whenever component support deformation is identified D1.30 FPCCS Spent VT-1 None See Note 1 N/A Each N/A N/A N/A N/A Fuel Pit Pumps at end of Inspection Appendix C Interval and (10%) whenever component support deformation is identified

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 84 of 125 Appendix C (Page 8 of 8)

ISI Planning/Scheduling Table for ASME Class 3 Components NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER D1.30 High Pressure VT-1 None See Note 1 N/A Each N/A N/A N/A N/A Fire Protection at end of Inspection Pumps Appendix C Interval and (10%) whenever component support deformation is identified D-A D1.40 Valve Integrally VT-1 None See Note 1 N/A Each N/A N/A N/A N/A Welded at end of Inspection Attachments Appendix C Interval and (10%) whenever component support deformation is identified Note 1: For Examination Category D-A, Piping, Pump and Valve Integral 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. 100% of the required areas of each selected welded attachment are required to be examined.

Note 2: for Examination Category D-A, Pressure Vessel Integral Attachments the attachments of only one of the multiple vessels of similar design, function, and service shall be required to be examined.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 85 of 125 Appendix D (Page 1 of 20)

ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F-A Supports F-A F1.10X Class 1 Piping Visual (See Supports Note 1)

Class 1 CVC Piping Supports F1.10A CVCS VT-3 19 25% 5 Each 1 2 2 ISI-0026-C Inspection ISI-0063-C Interval F1.10B CVCS VT-3 19 25% 5 Each 2 1 2 ISI-0026-C Inspection ISI-0063-C Interval F1.10C CVCS VT-3 2 25% 1 Each 0 0 1 ISI-0026-C Inspection ISI-0063-C Interval F1.10D CVCS VT-3 20 25% 5 Each 2 2 1 ISI-0026-C Inspection ISI-0063-C Interval Class 1 RCS Piping Supports

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 86 of 125 Appendix D (Page 2 of 20)

ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.10A RCS VT-3 13 25% 4 Each 1 1 2 ISI-0364-C Inspection Interval F1.10B RCS VT-3 6 25% 2 Each 1 1 0 ISI-0364-C Inspection Interval F1.10C RCS VT-3 10 25% 3 Each 1 1 1 ISI-0364-C Inspection Interval F1.10D RCS VT-3 13 25% 4 Each 1 1 2 ISI-0364-C Inspection Interval Class 1 RCS Main Piping Supports F1.10A RCS Main VT-3 0 25% 0 Each 0 0 0 ISI-0124-C Inspection ISI-0438-C Interval F1.10B RCS Main VT-3 4 25% 1 Each 1 0 0 ISI-0124-C Inspection ISI-0438-C Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 87 of 125 Appendix D (Page 3 of 20)

ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.10C RCS Main VT-3 2 25% 1 Each 0 0 1 ISI-0124-C Inspection ISI-0438-C Interval F1.10D RCS Main VT-3 0 25% 0 Each 0 0 0 ISI-0124-C Inspection ISI-0438-C Interval Class 1 RHR Piping Supports F1.10A RHRS VT-3 4 25% 1 Each 1 0 0 ISI-0020-C Inspection Interval F1.10B RHRS VT-3 6 25% 2 Each 0 0 2 ISI-0020-C Inspection Interval F1.10C RHRS VT-3 3 25% 1 Each 0 1 0 ISI-0020-C Inspection Interval F1.10D RHRS VT-3 14 25% 4 Each 1 1 2 ISI-0020-C Inspection Interval Class 1 SIS Piping Supports

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 88 of 125 Appendix D (Page 4 of 20)

ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.10A SIS VT-3 44 25% 11 Each 3 4 4 ISI-0021-C Inspection Interval F1.10B SIS VT-3 62 25% 16 Each 5 5 6 ISI-0021-C Inspection Interval F1.10C SIS VT-3 8 25% 2 Each 1 1 0 ISI-0021-C Inspection Interval F1.10D SIS VT-3 47 25% 12 Each 4 4 4 ISI-0021-C Inspection Interval F-A F1.20X Class 2 Piping Visual (See Supports Note 1)

Class 2 AFWS Piping Supports F1.20A AFWS VT-3 51 15% 8 Each 3 3 2 ISI-0062-C Inspection Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 89 of 125 Appendix D (Page 5 of 20)

ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.20B AFWS VT-3 45 15% 7 Each 2 2 3 ISI-0062-C Inspection Interval F1.20C AFWS VT-3 7 15% 1 Each 0 0 1 ISI-0062-C Inspection Interval F1.20D AFWS VT-3 11 15% 2 Each 0 1 1 ISI-0062-C Inspection Interval Class 2 CSS Piping Supports F1.20A CSS VT-3 68 15% 11 Each 4 3 4 ISI-0423-C Inspection Interval F1.20B CSS VT-3 20 15% 3 Each 1 1 1 ISI-0423-C Inspection Interval F1.20C CSS VT-3 7 15% 2 Each 0 1 1 ISI-0423-C Inspection Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 90 of 125 Appendix D (Page 6 of 20)

ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.20D CSS VT-3 22 15% 4 Each 1 1 2 ISI-0423-C Inspection Interval Class 2 CVCS Piping Supports F1.20A CVCS VT-3 105 15% 16 Each 5 5 6 ISI-0424-C Inspection Interval F1.20B CVCS VT-3 123 15% 19 Each 6 6 7 ISI-0424-C Inspection Interval F1.20C CVCS VT-3 11 15% 2 Each 0 1 1 ISI-0424-C Inspection Interval F1.20D CVCS VT-3 17 15% 3 Each 1 1 1 ISI-0424-C Inspection Interval Class 2 FWS Piping Supports F1.20A FWS VT-3 55 15% 9 Each 3 3 3 ISI-0062-C Inspection Interval

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.20B FWS VT-3 26 15% 4 Each 1 1 2 ISI-0062-C Inspection Interval F1.20C FWS VT-3 6 15% 1 Each 1 0 0 ISI-0062-C Inspection Interval F1.20D FWS VT-3 42 15% 7 Each 2 3 2 ISI-0062-C Inspection Interval Class 2 MSS Piping Supports F1.20A MSS VT-3 19 15% 3 Each 1 1 1 ISI-0011-C Inspection Interval F1.20B MSS VT-3 1 15% 0 Each 0 0 0 ISI-0011-C Inspection Interval F1.20C MSS VT-3 12 15% 2 Each 0 1 1 ISI-0011-C Inspection Interval

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.20D MSS VT-3 23 15% 4 Each 1 1 2 ISI-0011-C Inspection Interval Class 2 RHRS Piping Supports F1.20A RHRS VT-3 90 15% 14 Each 4 5 5 ISI-0020-C Inspection ISI-0107-C Interval F1.20B RHRS VT-3 25 15% 4 Each 2 1 1 ISI-0020-C Inspection ISI-0107-C Interval F1.20C RHRS VT-3 22 15% 4 Each 1 1 2 ISI-0020-C Inspection ISI-0107-C Interval F1.20D RHRS VT-3 33 15% 5 Each 2 1 2 ISI-0020-C Inspection ISI-0107-C Interval Class 2 SIS Piping Supports F1.20A SIS VT-3 129 15% 20 Each 6 7 7 ISI-0021-C Inspection ISI-0440-C Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 93 of 125 Appendix D (Page 9 of 20)

ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.20B SIS VT-3 131 15% 20 Each 7 6 7 ISI-0021-C Inspection ISI-0440-C Interval F1.20C SIS VT-3 19 15% 3 Each 1 1 1 ISI-0021-C Inspection ISI-0440-C Interval F1.20D AFWS VT-3 40 15% 6 Each 2 2 2 ISI-0021-C Inspection ISI-0440-C Interval F-A F1.30X Class 3 Piping Visual (See Supports Note 1)

Class 3 AFWS Piping Supports F1.30A AFWS VT-3 90 10% 10 Each 3 3 4 ISI-0111-C Inspection Interval F1.30B AFWS VT-3 61 10% 7 Each 2 2 3 ISI-0111-C Inspection Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 94 of 125 Appendix D (Page 10 of 20)

ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.30C AFWS VT-3 12 10% 2 Each 0 1 1 ISI-0111-C Inspection Interval F1.30D AFWS VT-3 20 10% 3 Each 1 1 1 ISI-0111-C Inspection Interval Class 3 CCS Piping Supports F1.30A CCS VT-3 415 10% 42 Each 14 14 14 ISI-0252-C Inspection Interval F1.30B CCS VT-3 109 10% 11 Each 3 4 4 ISI-0252-C Inspection Interval F1.30C CCS VT-3 20 10% 2 Each 1 0 1 ISI-0252-C Inspection Interval F1.30D CCS VT-3 5 10% 1 Each 0 1 0 ISI-0252-C Inspection Interval Class 3 ERCWS Piping Supports

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.30A ERCWS VT-3 424 10% 43 Each 14 14 15 ISI-0112-C Inspection Interval F1.30B ERCWS VT-3 446 10% 46 Each 15 15 16 ISI-0112-C Inspection Interval F1.30C ERCWS VT-3 20 10% 2 Each 1 1 0 ISI-0112-C Inspection Interval F1.30D ERCWS VT-3 23 10% 3 Each 1 1 1 ISI-0112-C Inspection Interval Class 3 FPCS Piping Supports F1.30A FPCS VT-3 39 10% 4 Each 1 1 2 ISI-0110-C Inspection Interval F1.30B FPCS VT-3 23 10% 3 Each 1 1 1 ISI-0110-C Inspection Interval

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 96 of 125 Appendix D (Page 12 of 20)

ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.30C FPCS VT-3 11 10% 2 Each 0 1 1 ISI-0110-C Inspection Interval F1.30D FPCS VT-3 5 10% 1 Each 0 0 1 ISI-0110-C Inspection Interval Class 3 HPFPS Piping Supports F1.30A HPFPS VT-3 98 10% 10 Each 3 3 4 ISI-0500-C Inspection Interval F1.30B HPFPS VT-3 50 10% 6 Each 2 2 2 ISI-0500-C Inspection Interval F1.30C HPFPS VT-3 0 10% 0 Each 0 0 0 ISI-0500-C Inspection Interval F1.30D HPFPS VT-3 0 10% 0 Each 0 0 0 ISI-0500-C Inspection Interval

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F-A F1.40X Class 1, 2, or 3 Visual Supports on one or one of (See supports other multiple Note 2) than piping components supports Class 1 Equipment F1.41B Class 1 Reactor VT-3 Reactor Vessel All Reactor Each 0 0 Reactor ISI-0427-C Vessel / 1 support Vessel / 1 Inspection Vessel / 1 support Interval support F1.41B Class 1 VT-3 Pressurizer / 2 All Pressurizer / Each 0 Pressurizer / 1 Pressurizer / CHM-2570-C Pressurizer supports 2 supports Inspection support 1 support Interval (seismic) (skirt)

F1.41B Class 1 Steam VT-3 4 SG / 1 One SG One SG / 1 Each 0 0 One SG / 1 CHM-2660-C Generator support each support Inspection support Interval F1.41B Class 1 Reactor VT-3 4 RCP / 1 One 1 RCP / 1 Each 0 1 RCP / 1 0 ISI-0446-C Coolant Pump support each support Inspection support Pump Interval Class 1 Valves Note: Schedule the F1.40X exam with the corresponding system F1.10X exams.

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.41A CVCS VT-3 1 100% 1 Each 1 0 0 ISI-0026-C Inspection Interval F1.41D CVCS VT-3 5 100% 5 Each 1 2 2 ISI-0026-C Inspection Interval F1.41D RCS VT-3 3 100% 3 Each 1 1 1 ISI-0364-C Inspection Interval Class 2 Equipment F1.42B Class 2 Steam VT-3 4 SGs / 1 1 SG 1 SG support Each 1 SG 0 0 ISI-2660-C Generator support each Inspection support Interval F1.42B Class 2 RHR VT-3 2 RHRHX / 1 1 1 RHRHX Each 0 1 RHRHX 0 CHM-2662-C Heat Exchanger support each support Inspection support RHRHX Interval F1.42B Class 2 CSS Heat VT-3 2 CSHX / 1 1 CSHX 1 CSHX Each 0 0 1 CSHX ISI-0371-C Exchanger support each support Inspection support Interval F1.42B Class 2 Seal VT-3 Seal Water All Seal Water Each 0 Seal Water 0 ISI-0484-C Water Heat Heat Exch / 1 Heat Exch Inspection Heat Exch Exchanger support support Interval support

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.42B Class 2 Seal VT-3 Seal Water All Seal Water Each Seal Water 0 0 ISI-0487-C Water Filter Filter / 1 Filter support Inspection Filter support support Interval F1.42B Class 2 Seal VT-3 2 Seal Water All 1 Seal Water Each 1 Seal Water 0 0 ISI-0486-C Water Injection Injection Filters Injection Inspection Injection Filter / 1 support Filter support Interval Filter support F1.42B Class 2 Boron VT-3 BIT / 1 support All BIT support Each 0 BIT support 0 ISI-0053-C Injection Tank Inspection (BIT) Interval F1.42B Class 2 RHR VT-3 2 RHRP / 1 1 Pump 1 RHRP Each 0 0 1 RHRP ISI-0117-C Pump support each support Inspection support Interval F1.42B Class 2 VT-3 2 CCP / 1 1 Pump 1 CCP Each 1 CCP 0 0 ISI-0118-C Centrifugal support each support Inspection support Charging Pump Interval F1.42B Class 2 Safety VT-3 2 SIP / 1 1 Pump 1 SIP support Each 0 1 SIP 0 ISI-0120-C Injection Pump support each Inspection support Interval F1.42B Class 2 VT-3 2 CSP / 1 1 Pump 1 CSP Each 0 0 1 CSP ISI-0483-C Containment support each support Inspection support Spray Pump Interval

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.42B Class 2 VT-3 1 PDP / 1 1 Pump None Each N/A N/A N/A ISI-0119-C Reciprocating support (pump Inspection Charging Pump abandoned) Interval Class 2 Valves Note: Schedule the F1.40X exam with the corresponding system F1.20X exams.

F1.42A CSS VT-3 2 100% 2 Each 1 0 1 ISI-0423-C Inspection Interval F1.42C CSS VT-3 1 100% 1 Each 0 1 0 ISI-0423-C Inspection Interval F1.42D CVCS VT-3 3 100% 3 Each 1 1 1 ISI-0424-C Inspection Interval F1.42D FWS VT-3 2 100% 2 Each 0 1 1 ISI-0062-C Inspection Interval F1.42D SIS VT-3 2 100% 2 Each 1 0 1 ISI-0440-C Inspection Interval Class 3 Equipment

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.43B Class 3 Motor VT-3 2 MDAFWP / 1 Pump 1 Each 0 0 1 ISI-0492-C Driven Auxiliary 1 support Inspection MDAFWP MDAFWP Feedwater Pump each Interval (MDAFP) support support F1.43B Class 3 Turbine VT-3 1 TDAFWP / 1 Pump 1 Each 0 0 1 ISI-0493-C Driven Auxiliary 1 support Inspection TDAFWP TDAFWP Feedwater Pump each Interval (TDAFP) support support F1.43B Class 3 Component VT-3 CSST / 1 All CCST Each 0 CCST 0 ISI-0496-C Cooling Surge Tank support Inspection support support (CCST) Interval F1.43B Class 3 CCS Heat VT-3 3 CCHX / 1 1 CCHX 1 CCHX Each 0 1 CCHX 0 ISI-0494-C Exchanger (CCHX) support each Inspection support support Interval F1.43B Class 3 CCS Water VT-3 5 CCSWP / 1 1 1 CCSWP Each 0 1 CCSWP 0 ISI-0495-C Pumps (CCSWP) support each Inspection CCSWP support support Interval F1.43B Class 3 VT-3 1 NRLHX / 1 All NRLHX Each 0 NRLHX 0 ISI-0497-C Nonregenerative support Inspection support support Letdown Heat Interval Exchanger (NRLHX)

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.43B Class 3 RHR Heat VT-3 3 RHRHSHX 1 1 Each 0 0 1 CHM-2662-C Exchanger / 1 support RHRHSHX RHRHSHX Inspection RHRHSHX Secondary Side each support Interval support (RHRHSHX)

F1.43B Class 3 VT-3 2 CSHX / 1 1 CSHX 1 CSHX Each 0 0 1 CSHX ISI-0371-C Containment Spray support each Inspection support support Heat Exchanger Interval (CSHX)

F1.43B Class 3 ERCW VT-3 8 ERCWP / 1 1 1 ERCWP Each 0 0 1 ERCWP ISI-0488-C Pump (ERCWP) support each Inspection ERCWP support support Interval F1.43B Class 3 ERCW VT-3 4 1 1 Each 0 1 0 ISI-0490-C Screen Wash Pump ERCWSWP / ERCWSWP ERCWSWP Inspection ERCWSWP (ERCWSWP) 1 support support Interval support each F1.43B Class 3 ERCW VT-3 4 ERCWS / 1 1 1 ERCWS Each 1 ERCWS 0 0 ISI-0489-C Strainer (ERCWS) support each Inspection ERCWS support support Interval F1.43B Class 3 FPCC VT-3 2 FPCCHX / 1 1 Each 1 0 0 ISI-0372-C Spent Fuel Pit Heat 1 support Inspection FPCCHX FPCCHX FPCCHX Exchanger each Interval (FPCCHX) support support

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports NUMBER TO FREQENCY OF EXAMINATION

% TO BE BE OR DEFERRAL NUMBER TO NUMBER TO BE NUMBER TO NUMBER OF EXAMINED EXAMINED OF INSPECTION BE EXAMINED EXAMINED IN BE EXAMINED EXAM ITEM EXAM COMPONENTS DURING IN THE TO END OF IN THE FIRST THE SECOND IN THE THIRD ISI DRAWING CAT. NO. DESCRIPTION METHOD IN ITEM NO. INTERVAL INTERVAL INTERVAL PERIOD PERIOD PERIOD NUMBER F1.43B Class 3 FPCC VT-3 3 FPCCP / 1 1 FPCCP 1 FPCCP Each 0 1 FPCCP 0 ISI-0485-C Spent Fuel Pit support each Inspection support support Pumps (FPCCP) Interval F1.43B Class 3 HPFP VT-3 4 HPFPP / 1 1 HPFPP 1 HPFPP Each 1 HPFPP 0 0 ISI-0501-C Pumps (HPFPP) support each Inspection support support Interval F1.43B Class 3 HPFP VT-3 2 HPFPS / 1 1 HPFPS 1 HPFPS Each 1 HPFPS 0 0 ISI-0502-C Strainers (HPFPS) support each Inspection support support Interval F1.43B Class 3 Seal Water VT-3 SWHX / 1 All SWHX Each 0 SWHX 0 ISI-0484-C Heat Exchanger support Inspection support support (SWHX) Interval Class 3 Valves Note: Schedule the F1.40X exam with the corresponding system F1.30X exams.

F1.43A AFWS VT-3 1 100% 1 Each 1 0 0 ISI-0111-C Inspection Interval F1.43D AFWS VT-3 3 100% 3 Each 0 2 1 ISI-0111-C Inspection Interval

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ISI Planning/Scheduling Table for ASME Class 1, 2, and 3 Component Supports Note 1: In accordance with Table IWF-2500-1, Item Numbers have been categorized to identify support types by component support function as follows (the Y in F1.Y0X is 1, 2, or 3 as appropriate for the associated piping classification):

Item No. F1.Y0A - one directional restraints (Function A)

Item No. F1.Y0B - multidirectional restraints (Function B)

Item No. F1.Y0C - variable supports such as: springs and constant force (Function C)

Item No. F1.Y0D - snubbers (Function D)

Note 2: In accordance with Table IWF-2500-1, Item Numbers have been categorized to identify 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. F1.4YB - multidirectional restraints (Function B)

Item No. F1.4YC - variable supports such as: springs and constant force (Function C)

Item No. F1.4YD - snubbers (Function D)

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 105 of 125 Appendix E (Page 1 of 5)

Class 1 (B-M-2) and 2 (C-G) Valve Listings Notes:

1. Examination is limited to at least 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 TYPE FUNCTION GROUP VENDOR VENDOR DRAWING (in.)

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-63-118 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 WESTINGHOUSE 934D185 SIS63-634 CHM-2758-C-09 6 CKV PSIV 2 WESTINGHOUSE 934D185 SIS63-635 CHM-2758-C-10 6 CKV PSIV 2 WESTINGHOUSE 934D185 SIS63-560 CHM-2758-C-07 10 CKV PSIV 3 WESTINGHOUSE 934D187 SIS63-561 CHM-2758-C-08 10 CKV PSIV 3 WESTINGHOUSE 934D187 SIS63-562 CHM-2758-C-09 10 CKV PSIV 3 WESTINGHOUSE 934D187 SIS63-563 CHM-2758-C-10 10 CKV PSIV 3 WESTINGHOUSE 934D187 SIS63-622 CHM-2758-C-07 10 CKV PSIV 3 WESTINGHOUSE 934D187 SIS63-623 CHM-2758-C-08 10 CKV PSIV 3 WESTINGHOUSE 934D187

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Class 1 (B-M-2) and 2 (C-G) Valve Listings CLASS 1 EXAMINATION CATEGORY B-M-2 VALVE LISTING SYS VALVE ISI DRAWING SIZE TYPE FUNCTION GROUP VENDOR VENDOR DRAWING (in.)

SIS63-624 CHM-2758-C-09 10 CKV PSIV 3 WESTINGHOUSE 934D187 SIS63-625 CHM-2758-C-10 10 CKV PSIV 3 WESTINGHOUSE 934D187 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 PSIV 5 WESTINGHOUSE 934D185 RCS68-563 ISI-0365-C-01 6 RELIEF RELIEF VALVE 6 CROSBY DSCA56964 RCS68-564 ISI-0365-C-01 6 RELIEF RELIEF VALVE 6 CROSBY DSCA56964 RCS68-565 ISI-0365-C-01 6 RELIEF RELIEF VALVE 6 CROSBY DSCA56964 RHR FCV-74-01 CHM-2636-C-01 14 GATE PSIV 7 WESTINGHOUSE 115E622 RHR FCV-74-02 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

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Class 1 (B-M-2) and 2 (C-G) Valve Listings CLASS 2 EXAMINATION CATEGORY C-G VALVE LISTING SYS CLASS VALVE ISI DRAWING WELD ISI VALVE SIZE TYPE MANUFACTURER VENDOR DRAWING NUMBER NUMBER DRAWING MSS 2 1-512 CHM-2669-C-04 MSVS-512 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-513 CHM-2669-C-04 MSVS-513 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-514 CHM-2669-C-04 MSVS-514 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-515 CHM-2669-C-04 MSVS-515 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-516 CHM-2669-C-04 MSVS-516 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-517 CHM-2669-C-03 MSVS-517 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-518 CHM-2669-C-03 MSVS-518 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-519 CHM-2669-C-03 MSVS-519 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-520 CHM-2669-C-03 MSVS-520 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-521 CHM-2669-C-03 MSVS-521 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-522 CHM-2669-C-01 MSVS-522 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-523 CHM-2669-C-01 MSVS-523 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-524 CHM-2669-C-01 MSVS-524 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-525 CHM-2669-C-01 MSVS-525 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-526 CHM-2669-C-01 MSVS-526 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-527 CHM-2669-C-02 MSVS-527 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-528 CHM-2669-C-02 MSVS-528 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-529 CHM-2669-C-02 MSVS-529 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-530 CHM-2669-C-02 MSVS-530 ISI-0081-C-01 6 SRV DRESSER 3NC-040 MSS 2 1-531 CHM-2669-C-02 MSVS-531 ISI-0081-C-01 6 SRV DRESSER 3NC-040

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Class 1 (B-M-2) and 2 (C-G) Valve Listings CLASS 2 EXAMINATION CATEGORY C-G VALVE LISTING SYS CLASS VALVE ISI DRAWING WELD ISI VALVE SIZE TYPE MANUFACTURER VENDOR DRAWING NUMBER NUMBER DRAWING FWS 2 3-638 CHM-2671-C-06 FWVS-638 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001 FWS 2 3-644 CHM-2671-C-06 FWVS-644 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001 FWS 2 3-645 CHM-2671-C-06 FWVS-645 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001 FWS 2 3-652 CHM-2671-C-05 FWVS-652 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001 FWS 2 3-655 CHM-2671-C-05 FWVS-655 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001 FWS 2 3-656 CHM-2671-C-05 FWVS-656 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001 FWS 2 3-669 CHM-2671-C-07 FWVS-669 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001 FWS 2 3-670 CHM-2671-C-07 FWVS-670 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001 FWS 2 3-678 CHM-2671-C-08 FWVS-678 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001 FWS 2 3-679 CHM-2671-C-08 FWVS-679 ISI-0082-C-01 6 CKV BORG WARNER 455KAB1-001

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Class 1 (B-M-2) and 2 (C-G) Valve Listings

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 110 of 125 Appendix F (Page 1 of 3)

ISI Drawing List List of Applicable Flow Diagrams Drawing Series System Description 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) 1-47W810 Residual Heat Removal (TVA Class A & B) 1-47W811 Safety Injection (TVA Class A & B) 1-47W812 Containment Spray (TVA Class B) 1-47W813 Reactor Coolant (TVA Class A) 1-47W814 Ice Condenser (exempt) 1-47W819 Primary Water (exempt) 1-47W830 Waste Disposal (exempt) 1-47W832 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) 1-47W862 Steam Generator Layup Water Treatment (exempt) 1-47W865 Heating & Air Conditioning (exempt)

ISI Drawings List Drawing Series System Description CHM-2547-C Reactor Coolant Main Loop Piping Weld Locations CHM-2549-C Reactor Vessel Closure 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 Channel Welds CHM-2669-C Mainsteam Piping Weld Locations CHM-2671-C Feedwater Piping Weld Locations CHM-2684-C Upperhead Penetrations CHM-2685-C Auxiliary Head Adapter CHM-2758-C Safety Injection System Piping ISI-0005-C Chemical and Volume Control Piping Weld Locations

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 111 of 125 Appendix F (Page 2 of 3)

ISI Drawing List Drawing Series System Description ISI-0011-C Mainsteam Piping Support Locations ISI-0012-C Control Rod Drive Housing ISI-0020-C Residual Heat Removal Piping Support Locations ISI-0021-C Safety Injection Piping Support Locations ISI-0026-C Chemical and Volume Control Piping Support Locations ISI-0048-C Reactor Coolant Pump Case Weld Locations ISI-0050-C CVCS Seal Water Injection Piping Weld Locations ISI-0053-C Boron Injection Tank Weld and Support Locations ISI-0062-C Feedwater Piping Support Locations ISI-0063-C CVCS Seal Water Injection Piping Support Locations ISI-0081-C Mainsteam Relief Valve ISI-0082-C Feedwater Check Valve ISI-0107-C Residual Heat Removal Piping Support Locations (HPSI portion)

ISI-0110-C Fuel Pool Cooling and Cleaning Piping Support Locations ISI-0111-C Auxiliary Feedwater Support Locations ISI-0112-C Essential Raw Cooling Water Piping Support Locations ISI-0117-C Residual Heat Removal Pump Supports ISI-0118-C Centrifugal Charging Pump Supports ISI-0119-C Reciprocating Charging Pump Supports ISI-0120-C Safety Injection Pump Supports ISI-0124-C Pressurizer Surge Line Piping Supports ISI-0252-C Component Cooling Piping Support Locations ISI-0364-C Reactor Coolant Piping Weld Locations ISI-0365-C Reactor Coolant Piping Support Locations ISI-0371-C Containment Spray Heat Exchanger Support Details ISI-0372-C Spent Fuel Pit Heat Exchanger Support Locations ISI-0375-C High Pressure Safety Injection Piping Weld Locations ISI-0400-C Containment Spray Piping Weld Locations ISI-0421-C High Pressure Safety Injection Excluded Piping Weld Locations ISI-0423-C Containment Spray Piping Support Locations ISI-0424-C Chemical and Volume Control Piping Support Locations (HPSI portion)

ISI-0427-C Reactor Vessel ISI-0438-C Reactor Coolant Main Loop Piping Support Locations ISI-0439-C Piping Support Examination Boundaries ISI-0440-C Safety Injection Piping Support Locations (HPSI portion)

ISI-0446-C Reactor Coolant Pump Supports ISI-0447-C Reactor Coolant Pump Main Flange Bolt Circle

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ISI Drawing List Drawing Series System Description ISI-0483-C Containment Spray Pump Support Locations ISI-0484-C Seal Water Injection Heat Exchanger Support Locations ISI-0485-C Spent Fuel Pool Pumps Support Locations ISI-0486-C Seal Water Injection Filter Support Locations ISI-0487-C Seal Water Filter Support Locations ISI-0488-C ERCW Pumps Support Locations ISI-0489-C ERCW Strainer Support Locations ISI-0490-C ERCW Screen Wash Pumps Support Locations ISI-0492-C Motor Driven Auxiliary Feedwater Pumps Support Locations ISI-0493-C Turbine Driven Auxiliary Feedwater Pump Support Locations ISI-0494-C Component Cooling Heat Exchanger Support Locations ISI-0495-C Component Cooling Water Pumps Support Locations ISI-0496-C Component Cooling Surge Tank Support Locations ISI-0497-C Non-Regenerative Letdown Heat Exchanger Support Locations ISI-0500-C High Pressure Fire Protection Piping Support Locations ISI-0501-C HPFP Pump Support Locations ISI-0502-C HPFP Strainer Support Locations ISI-0508-C Steam Generator Blowdown Piping Weld Locations

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 113 of 125 Appendix G (Page 1 of 1)

Schedule of Successive Examinations COMPONENT PROGRAM EXAM EXAM CYCLE FIRST SECOND THIRD ISI DRAWING IDENTIFIER REFERENCE METHOD CAT FLAW SUCCESSIVE SUCCESSIVE SUCCESSIVE SECTION INITIALLY PERIOD PERIOD PERIOD DETECTED 1-62A-038 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A ISI-0063-C-02 1-01A-304 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A ISI-0011-C-01 1-03A-456 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A ISI-0062-C-07 1-03A-412 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A ISI-0062-C-06 1-03A-403 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A ISI-0062-C-06 1-03A-367 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A ISI-0062-C-05 1-03A-457 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A ISI-0062-C-07 1-03A-409 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A ISI-0062-C-06 03B-1AFW- 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A ISI-0111-C-04 R221 SGH-1-1 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A CHM-2660-C-03 SGH-1-2 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A CHM-2660-C-03 SGH-1-3 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A CHM-2660-C-03 SGH-1-4 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A CHM-2660-C-03 SGH-2-1 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A CHM-2660-C-03 SGH-2-2 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A CHM-2660-C-03 SGH-2-3 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A CHM-2660-C-03 SGH-2-4 7.2.D.6 VT-3 F-A N/A CYCLE 8 N/A N/A CHM-2660-C-03

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Notification of Additional Sample Results Form TO: Transmittal Number:

FROM:

Plant/Unit System Component ID Code Category Exam Method(s)

Initial Sample NOI Number 1st Additional Sample NOI Number 2nd Additional Sample NOI Number Drawing Number Prepared By Evaluation/Recommendation (attach additional information if needed)

Additional Components to be Examined Evaluation/Recommendation Prepared By:

Coordinated with ISI/NDE Representative:

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 115 of 125 Appendix I (Page 1 of 1)

Requests for Relief RFR No. Component RFR Requested RFR Description Status PDI-2 RPV pressure retaining Reduce the examination volume to 1/2 beyond the widest edge of the Submitted in second ten-year nozzle-to-vessel welds deposited weld metal. interval update.

PDI-4 RPV shell-to-flange weld Use ASME Section XI Appendix VIII for examination of the RPV shell- Submitted in second ten-year to-flange weld in lieu of Appendix I. interval update.

SNBR-1 Class 1, 2, and 3 snubbers Utilize existing TRM program, TI-203, for snubber preservice/inservice Submitted in second ten-year examination and testing in lieu of IWF-5000. interval update.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 116 of 125 Appendix J (Page 1 of 9)

Augmented Examinations The following augmented examinations have been requested to be included in the ISI Program by the responsible organization listed. A summary of the augmented examinations are listed below and a detailed description follows this page.

1.0 Reactor Coolant Pump Flywheel Examination Requirements and Schedule:

A. Perform an in-place ultrasonic examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals during the refueling or maintenance outages.

B. Perform a surface examination of all exposed surfaces and complete ultrasonic examination at approximately 10-year intervals during the plant shutdown coinciding with the ISI schedule as required by Section XI.

Responsible Organization: Component Engineering The augmented examination requirements of the reactor coolant pump flywheel are included in Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1; (1) an in-place ultrasonic examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals during the refueling or maintenance shutdown coinciding with the ISI schedule as required by Section XI of the ASME Code, and (2) a surface examination of all exposed surfaces (exposed areas are considered as those areas accessible for examination without having to remove the flywheel from the housing) and complete ultrasonic examination at approximately 10-year intervals during the plant shutdown coinciding with the ISI schedule as required by Section XI of the ASME Code. This examination is performed in accordance with WBN Technical Surveillance Requirement 3.4.5.1.

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. If 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. The examination results shall be included in the augmented section of the ISI Summary Report.

The flywheel consists of 2 plates, approximately 5 inches and 8 inches thick, bolted together. Each plate is fabricated from vacuum degassed A-533, GR. B, Class 1, steel.

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Augmented Examinations 1.0 Reactor Coolant Pump Flywheel (continued)

The 3-year in place RCP examinations shall be recorded using the RCP motor serial number and exam ID:

RCP Motor S/N - BOREKEY (i.e., 4S-81P352 - BOREKEY)

For the 10-year exam, the IDs shall be:

RCP Motor S/N - SUR (i.e., 4S-81P352 - SUR)

RCP Motor S/N - VOL (i.e., 4S-81P352 - VOL) 2.0 RCCA Guide Tube Support Pins Examination Requirement and Schedule: replace the Guide Pins in the Cycle 8 refueling outage.

Responsible Organization: Mechanical/Nuclear Engineering In accordance with Westinghouse Infogram IG95-12A and WCAP 15271 Revision 0, several utilities have reported the existence of indications in the replacement guide tube support pins. The operation time of the reporting plants varies, but based on operating life at other utilities including Sequoyah, indications potentially could appear in the heats of material used at WBN from 58,900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> to 97,000 operating hours. Current estimates show WBN accumulating 58,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of full power operation by the Cycle 5 refueling outage (Fall,, 2003) and 94,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> by the Cycle 8 refueling outage (Spring, 2008).

The present plan is to replace the guide pins during the cycle 8 refueling outage.

This work is coordinated by the Refuel Floor Group.

3.0 Examination of Piping Welds with Multiple Weld Repairs Examination Requirement and Schedule: perform ultrasonic examination of welds with multiple weld repairs as scheduled each refueling outage.

Responsible Organization: Mechanical/Nuclear Engineering

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 118 of 125 Appendix J (Page 3 of 9)

Augmented Examinations 3.0 Examination of Piping Welds with Multiple Weld Repairs (continued)

During the 7th refueling outage inservice inspection of Sequoyah Nuclear Plants Unit 2, an indication exceeding the acceptance standards of ASME Section XI 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.

Each of these welds will be ultrasonically examined and evaluated per NDE procedure N-UT-64 during the first refueling outage and during following outages at the frequency provided in the table below. The results are to be submitted to the Materials Section for evaluation. Materials will evaluate results and make additional recommendations as required. The examination results will be included in the augmented section of the Site Final Report.

Examine Weld in Refueling Outage ISI Weld Number ISI Drawing Number Pipe Wall 8 9 10 11 12 13 14 Dia. Thick.

CVCF-D036-10H ISI-0005-C-01 3 0.438 X X X SIF-D076-04 ISI-0421-C-05 8 0.322 X X X SIF-D078-03 ISI-0375-C-13 24 0.375 X X SIF-D079-01 ISI-0375-C-12 24" 0.375 X X SIF-D079-11 ISI-0375-C-12 16 0.375 X X SIF-D079-11A ISI-0375-C-12 16 0.375 X X SIF-D087-11 CHM-2758-C-05 8 0.906 X X X X X SIF-D087-12 CHM-2758-C-05 8 0.906 X X X X X SIF-D092-15 CHM-2758-C-10 6 0.719 X X X X 4.0 Examination of Alloy 600 Welds Examination Requirement and Schedule:

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Augmented Examinations 4.0 Examination of Alloy 600 Welds (continued)

A. Reactor Pressure Vessel (RPV) Head

1. Perform a bare metal visual examination of 100% of the RPV head surface (including 360o around each RPV head penetration nozzle) beginning in the cycle 5 or 6 refueling outage and thereafter at least every third refueling outage or every 5 years, whichever occurs first.

2. Perform either 2a, 2b, or 2c at least once before February 10, 2008 and thereafter at least every four refueling outages or every seven years, whichever occurs first.

a. Perform ultrasonic testing of each RPV head penetration nozzle (i.e.,

nozzle base material) as described in the revised NRC Order EA 009 Section IV.C.(5)(b)(i), OR

b. Perform eddy current testing or dye penetrant testing of the entire wetted surface of the J-groove weld and RPV head penetration nozzle base material as described in the revised NRC Order EA-03-009 Section IV.C.(5)(b)(ii), OR

c. Perform a combination of a and b to cover equivalent volumes, surfaces and leak paths of the RPV head penetration nozzle base material and J-groove weld as described in the revised NRC Order EA-03-009 Section IV.C.(5)(b)(iii).

B. RPV Bottom Head

1. Perform a visual examination (VT-3 resolution as a minimum) under insulation of the RPV bottom head penetrations and surrounding area each refueling outage.

C. Pressurizer

1. Perform a visual examination of the nozzle safe end welds each refueling outage beginning in the cycle 6 refueling outage.

Responsible Organization: Mechanical/Nuclear Engineering

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 120 of 125 Appendix J (Page 5 of 9)

Augmented Examinations 4.0 Examination of Alloy 600 Welds (continued)

Boric acid leaks on and around the reactor pressure vessel (RPV) and alloy 600 nozzle cracking issues within the PWR nuclear industry has lead to both NRC mandated examinations and the need to evaluate performance of additional examinations beyond the ASME Section XI requirements on the RPV head, RPV bottom head and pressurizer nozzles. The requirements for Alloy 600 issues are maintained in Business Practice BP-257, Integrated Material Issues Management Plan. This augmented examination section briefly describes those examinations and inspections that should be coordinated and scheduled with the standard ISI examinations performed by Inspection Services Organizations each refueling outage.

A. RPV Head In response to leaks and nozzle cracking in PWR plants, the NRC issued an Order on February 11, 2003 entitled, Issuance of Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors. The Order requires specific inspection of the RPV head and associated penetration nozzles. A revised Order was issued February 20, 2004 which addresses revisions to bare metal visual inspection, penetration nozzle inspection coverage, flexibility in combination of non-destructive examination methods, flaw evaluation, and requirements for plants which have replaced their RPV head. WBN is classified in the Low susceptibility category to PWSCC-related degradation in accordance with the Order. The following examinations will be performed to meet the Orders inspection requirements defined in Section C.3:

1. A bare metal visual examination of 100% of the RPV head surface (including 3600 around each RPV head penetration nozzle) was performed beginning in the cycle 5 refueling outage. Thereafter, the inspection shall be performed at least every third refueling outage or every five years, whichever occurs first. This inspection will be performed in accordance with NDE procedure N-VT-17, Visual Examination for Leakage of PWR Reactor Head Penetrations, by a VT-2 certified inspector. Any questionable indications or evidence of boron will be inspected by a Metallurgical Engineer.

2. Inspection of the head penetration nozzles shall be performed as described in either 2a, 2b or 2c. Either of these inspections must be completed at least once before February 10, 2008 and thereafter at least every four refueling outages or every seven years, whichever occurs first. The inspection requirements are either:

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 121 of 125 Appendix J (Page 6 of 9)

Augmented Examinations 4.0 Examination of Alloy 600 Welds (continued)

a. Perform ultrasonic testing of each RPV head penetration nozzle (i.e.,

nozzle base material) as described in the revised NRC Order EA 009 Section IV.C.(5)(b)(i), OR

b. Perform eddy current testing or dye penetrant testing of the entire wetted surface of the J-groove weld and RPV head penetration nozzle base material as described in the revised NRC Order EA-03-009 Section IV.C.(5)(b)(ii), OR

c. Perform a combination of a and b to cover equivalent volumes, surfaces and leak paths of the RPV head penetration nozzle base material and J-groove weld as described in the revised NRC Order EA-03-009 Section IV.C.(5)(b)(iii).

The inspection results shall be forwarded to Site Mechanical/Nuclear Engineering. For each inspection required above, Site Mechanical/Nuclear Engineering shall submit a report to Site Licensing detailing the inspection results within 30 days after returning the plant to operation. In accordance with Section E of the Order, Site Licensing shall submit the report to the NRC within 60 days after returning the plant to operation.

B. RPV Bottom Head A visual examination shall be performed on the bottom head penetrations and surrounding area each refueling outage. The insulation panels will be removed as required to perform a visual examination in accordance with NDE procedure N-VT-17, Visual Examination for Leakage of PWR Reactor Head Penetrations. WBN shall notify the NRC in writing of any changes to this inspection requirement as required in the NRC Letter Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity (TAC No MC0576.)

The inspection results shall be forwarded to Site Mechanical/Nuclear Engineering. The results shall be included in the augmented section of the ISI Summary Report.

C. Pressurizer

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Augmented Examinations 4.0 Examination of Alloy 600 Welds (continued)

The pressurizer spray, safety, relief and surge nozzles are considered highly susceptible due to the operating temperature and should be examined to ensure no leakage. An augmented visual examination shall be performed on the nozzle to safe-end welds each refueling outage. The examination will be performed in accordance with NDE procedure N-VT-19, Visual Inspection of Alloy 600/82/182 Pressure Boundary Components. The inspections shall begin in the cycle 6 refueling outage. It is permissible to substitute a PDI qualified ultrasonic examination (ASME Section XI, Appendix VIII) of the subject weld in lieu of the visual examination provided greater than 90% coverage can be obtained.

The inspection results shall be forwarded to Site Mechanical/Nuclear Engineering. The results shall be included in the augmented section of the ISI Summary Report.

5.0 Examination of Clad Areas in Reactor Vessel Inlet Nozzles and Accumulator Tank # 3 Examination Requirements and Schedule:

A. Reactor Pressure Vessel

1. Perform a visual examination on the ground clad areas in Loop 2 and 3 inlet nozzles during the 10-year ISI reactor vessel examination.

B. Accumulator Tank #3

1. 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.

Responsible Organization: Mechanical/Nuclear Engineering A. Reactor Vessel Inlet Nozzles

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Augmented Examinations 5.0 Examination of Clad Areas in Reactor Vessel Inlet Nozzles and Accumulator Tank # 3 (continued)

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).

During the remote visual portion of the reactor vessel 10-year ISI inspection, specific attention will be given to the unclad areas in the Loops 2 and 3 inlet nozzles for any evidence of wall deterioration. These areas should be specifically noted in the scope of inspection with the contract inspector. The examination results will not require a special report but will be included as part of the reactor vessel 10-year inspection report.

B. Accumulator Tank #3 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.

Beginning in the cycle 6 refueling outage and every other refueling outage thereafter, an ultrasonic examination shall be performed from the outside of accumulator tank #3 at the areas of the bottom head described below (reference vendor drawing 1097E08):

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.

AREA DESCRIPTION a 2 wide band below the orange peel plate to shell weld

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 124 of 125 Appendix J (Page 9 of 9)

Augmented Examinations 5.0 Examination of Clad Areas in Reactor Vessel Inlet Nozzles and Accumulator Tank # 3 (continued) 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 3/4 sample nozzle in the bottom head The examination should be performed in accordance with NDE procedure N-UT-24. The results shall be forwarded to mechanical engineering for evaluation. The examination results shall be included in the augmented section of the Site Final Report.

WBN ASME SECTION XI ISI/NDE PROGRAM 1-TRI-0-10.2 Unit 1 Rev. 0000 Page 125 of 125 Appendix K (Page 1 of 1)

Source Notes Source Note Source Document Summary 1 NCO 920032003 Commitment to include RCP Flywheel inspection in ISI program 2 WH INFOGRAM 95-12A Consider/develop plans for long term inspection of Guide Tube Support Pins 3 PER SQ 961154 Safety Injection System Weld Flaw