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| | issue date = 09/27/2007 | | | issue date = 09/27/2007 |
| | title = Requests for Additional Information for the Review of the Wolf Creek Generating Station, Unit 1, License Renewal Application | | | title = Requests for Additional Information for the Review of the Wolf Creek Generating Station, Unit 1, License Renewal Application |
| | author name = Rodriguez V M | | | author name = Rodriguez V |
| | author affiliation = NRC/NRR/ADRO/DLR/RLRB | | | author affiliation = NRC/NRR/ADRO/DLR/RLRB |
| | addressee name = Garrett T J | | | addressee name = Garrett T |
| | addressee affiliation = Wolf Creek Nuclear Operating Corp | | | addressee affiliation = Wolf Creek Nuclear Operating Corp |
| | docket = 05000482 | | | docket = 05000482 |
| | license number = | | | license number = |
| | contact person = Rodriguez V M NRR/DLR/RLRB 415-3703 | | | contact person = Rodriguez V NRR/DLR/RLRB 415-3703 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
| | page count = 7 | | | page count = 7 |
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Category:Letter
MONTHYEARML24025A0992024-01-25025 January 2024 Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML24018A0792024-01-22022 January 2024 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed Nshcd and Opportunity for a Hearing (EPID L-2024-LLA-0007) (Letter) ML24018A1382024-01-18018 January 2024 Inservice Inspection Request for Information ML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 IR 05000482/20230042024-01-11011 January 2024 Integrated Inspection Report 05000482/2023004 ML23356A0722024-01-0404 January 2024 Supplemental Information Needed for Acceptance of Requested Licensing Actions Exemption from Specific 10 CFR Part 73N Requirements (EPID L-2023-LLE-0048) (Redacted Version) WO 23-0002, Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-0082023-12-26026 December 2023 Operating Corp., Summary of Actions Implemented for EA-18-165, Confirmatory Order, NRC Inspection Report 05000482/2019010 and NRC Investigation Report 4-2018-008 ML23348A3662023-12-18018 December 2023 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482 2024012) and Request for Information ML23334A2502023-11-30030 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23299A2662023-11-29029 November 2023 Issuance of Amendment No. 238 Modified Implementation Date of License Amendment No. 237 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23325A2112023-11-20020 November 2023 Submittal of Request for Exemption from Specific Provisions in 10 CFR 73.55 ML23320A2772023-11-16016 November 2023 License Amendment Request to Revise Ventilation Filter Testing Program Criteria in Technical Specification 5.5.11.b and Administrative Correction of Absorber in Technical Specification 5.5.11 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23305A3472023-11-0101 November 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML23292A3592023-10-19019 October 2023 License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 ML23292A3572023-10-19019 October 2023 Operating Corporation, Request for Correction in Response to Issuance of Amendment No. 237 and Corresponding Safety Evaluation ML23277A2772023-10-11011 October 2023 Regulatory Audit Summary Concerning Review of Request Number CI3R-01 for Proposed Alternative Inspection Frequency for Containment Unbonded Post Tensioning System Components ML23284A2392023-10-11011 October 2023 NRC Initial Operator Licensing Examination Approval 05000482/2023301 ML23276B4552023-10-0303 October 2023 Technical Specification 5.6.8 Post Accident Monitoring (PAM) Report ML23264A8682023-09-21021 September 2023 Independent Spent Fuel Storage Installation Registration of Dry Storage Canister WC-EOS-37PTH-008-B4L, WC-EOS-37PTH-007-B4L, and WC-EOS-37PTH-002-B4L ML23256A2062023-09-14014 September 2023 Withdrawal of Requested Licensing Action Exemption from Specific 10 CFR Part 73 Requirements ML23165A2502023-08-31031 August 2023 Issuance of Amendment No. 237 Request for Deviation from Fire Protection Requirements ML23243A0002023-08-31031 August 2023 Wolf Generating Station - Withdrawal of Request for Exemption from Specific 10 CFR Part 73 Requirements IR 05000482/20230052023-08-23023 August 2023 Updated Inspection Plan for Wolf Creek Nuclear Operating Corporation, Unit 1 (Report 05000482/2023005) - Mid-Cycle Letter 2023 ML23232A0012023-08-19019 August 2023 Revision of One Procedure That Implements the Radiological Emergency Response Plan (Rerp). Includes EPP 06-009, Rev. 13 ML23221A3932023-08-0909 August 2023 Submittal of Request for Exemption from Specific 10 CFR Part 73 Requirements ML23220A4222023-08-0808 August 2023 Supplement to License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ML23201A1212023-08-0707 August 2023 Issuance of Amendment No. 236 Revision to Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML23130A2902023-07-26026 July 2023 Issuance of Amendment No. 235 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections IR 05000482/20230022023-07-11011 July 2023 Integrated Inspection Report 05000482/2023002 ML23167A0042023-06-26026 June 2023 Audit Plan to Support Review of Request for Alternative Containment Inservice Inspection Frequency IR 05000482/20234012023-06-21021 June 2023 Security Baseline Inspection Report 05000482/2023401 ML23171B1312023-06-20020 June 2023 Additional Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML23151A4162023-05-31031 May 2023 Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) ET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components WO 23-0014, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23132A1532023-05-12012 May 2023 Transmittal of 2022 Annual Financial Reports WM 23-0009, Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1)2023-05-10010 May 2023 Financial Assurance Requirements for Decommissioning Nuclear Power Reactors 10 CFR 50.75(f)(1) ML23135A1172023-05-0808 May 2023 Redacted Version of Revision 36 to Updated Safety Analysis Report ML23117A2112023-04-27027 April 2023 Annual Exposure Report (2022) ML23117A1342023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report Report 46 2024-01-04
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22361A0052022-12-27027 December 2022 NRR E-mail Capture - Request for Additional Information Wolf Creek Request for Deviation from Fire Protection Program Requirements ML22321A2662022-11-16016 November 2022 January 2023 Emergency Preparedness Program Inspection - Request for Information ML22307A1372022-11-0202 November 2022 August 2022 Emergency Preparedness Exercise Inspection Unresolved Item - Request for Information ML22249A2552022-06-29029 June 2022 Request for Information for an NRC Post-Approval Site Inspection for License Renewal 05000482/2022012 ML22165A0882022-06-14014 June 2022 Information Request, Security IR 2022403 ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22055A1142022-02-23023 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Request to Revise Diesel Generator Completion Time ML22045A4512022-02-14014 February 2022 NRR E-mail Capture - Request for Additional Information - Wolf Creek Steam Generator Inspection Report 24th Refueling ML22025A3612022-01-21021 January 2022 PI&R RFI Final ML21327A2602021-11-23023 November 2021 NRR E-mail Capture - Request for Additional Information - Wolf Creek Revision of Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21271A1952021-09-28028 September 2021 E-mail 9-28-21 RFI for Wc EP Inspection Nov 2021 ML21253A0902021-09-23023 September 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment and Regulatory Exemption for a Risk-Informed Approach to Address GSI-191 (EPIDs L-2021-LLA- 0152 and L-2021-LLE-0039) ML21221A1282021-08-0505 August 2021 NRR E-mail Capture - Urgent: Draft Request for Additional Information - Wolf Creek one-time Request for Exemption from the Biennial Emergency Preparedness Exercise ML21132A1032021-05-12012 May 2021 Document Request List, Paperwork Reduction Act Statement ML20302A4782020-10-28028 October 2020 OPC R1 Request for Information ML20262A7512020-09-17017 September 2020 NRR E-mail Capture - Requests for Additional Information: Wolf Creek Amendment Request to Modify Technical Specification Surveillance Frequency Consistent with TSTF-425 ML20195A2712020-07-13013 July 2020 Generation Station - Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2020012) and Request for Information ML20133J8972020-05-12012 May 2020 12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes ML20009E4802020-01-0909 January 2020 Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information ML19346E6052019-11-0404 November 2019 Target Set Request for Information for Week of November 4, 2019 ML19224A5242019-08-12012 August 2019 NRR E-mail Capture - Request for Additional Information - License Amendment Request to Revise Wolf Creek Generating Station Technical Specification 3.3.5 ML18304A1052018-11-0505 November 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses and Alternative Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) ML18282A6402018-10-0909 October 2018 NRR E-mail Capture - Request for Additional Information - Wolf Creek Generating Station License Amendment Request for Revision to the Emergency Plan ML18270A0942018-10-0404 October 2018 Request for Additional Information License Amendment Request for Transition to Westinghouse Methodology for Selected Accident and Transient Analyses ML18207A4332018-07-24024 July 2018 NRR E-mail Capture - (External_Sender) Draft Request for Additional Information Relief Request from ASME Code N-666-1 Alternate Repair of Essential Service Water Piping Wolf Creek Generating Station, Unit 1 EPID No.:L-2018-LLR-0101 ML18116A6132018-04-25025 April 2018 Operating Corporation - Notification of Inspection (NRC Inspection Report 05000482/2018002) and Request for Information ML17331A1782017-12-0404 December 2017 Request for Additional Information License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternate Source Term (CAC No. MF9307; EPID L-2017-LLA-0211) ML17291A7102017-10-17017 October 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17265A0142017-09-21021 September 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses ML17170A3152017-06-19019 June 2017 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000482/2017008) and Request for Information ML17166A0382017-06-14014 June 2017 NRR E-mail Capture - Request for Additional Information - License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term ML17052A0282017-02-15015 February 2017 NRR E-mail Capture - Wolf Creek Generating Station - Official EAL RAIs ML16319A4282016-11-14014 November 2016 NRR E-mail Capture - Request for Additional Information (RAI) - Relief Requests 13R-14 and 13R-15 ML16300A2662016-10-21021 October 2016 Request for Additional Information - Relief Request I3R-13 Regarding Weld Examination Coverage IR 05000482/20160022016-08-0303 August 2016 NRC Integrated Inspection Report 05000482/2016002 ML16110A3722016-04-25025 April 2016 Request for Additional Information, License Amendment Request to Revise Technical Specification (TS) 4.2.1 and TS 5.6.5 to Allow Use of Optimized Zirlo as Approved Fuel Rod Cladding ML16020A1392016-01-15015 January 2016 Notification of NRC Component Design Bases Inspection (05000482/2016007) and Initial Request for Information ML15135A4862015-05-14014 May 2015 Wc 2015007 17T RFI ML15082A0052015-03-27027 March 2015 Request for Additional Information, Round 2, Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML15079A0762015-03-23023 March 2015 Request for Additional Information, Round 2, Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML15040A6252015-02-10010 February 2015 Request for Additional Information, License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process ML14323A5742014-12-0404 December 2014 Request for Additional Information, License Amendment Request to Revise Fire Protection Program Related to Alternative Shutdown Capability as Described in USAR ML14230A7572014-08-21021 August 2014 Request for Additional Information, Relief Request I3R-10, Alternative from Pressure Test Requirements of ASME Code Section XI, IWC-5220, Third 10-Year Inservice Inspection Interval ML14206A0122014-08-0101 August 2014 Request for Additional Information, Relief Requests I3R-08, RPV Interior Attachments and I3R-09, RPV Pressure-Retaining Welds, Exam Interval Extensions, Third 10-year Inservice Inspection Interval ML14197A3362014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-11, Alternative from Pressure Test Requirements of ASME Code Section XI IWC-5220, Third 10-Year Inservice Inspection Interval ML14148A3872014-06-0202 June 2014 Request for Additional Information Related to Flood Hazard Reevaluation Report for Recommendation 2.1 of the Near-Term Task Force Review of the Insights from the Fukushima Dai-Ichi Accident ML14111A1002014-04-30030 April 2014 Request for Additional Information, Nrr/Dss/Srxb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14083A4002014-04-0303 April 2014 Request for Additional Information, Nrr/Dra/Arcb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14058A0882014-03-0505 March 2014 Request for Additional Information, Nrr/De/Eeeb, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term ML14027A1622014-01-28028 January 2014 Redacted, Request for Additional Information, Round 2, License Amendment Request to Approve Transition to Westinghouse Core Design and Safety Analysis and Adoption of Full Scope Alternate Source Term 2022-06-29
[Table view] |
Text
September 27, 2007
Mr. Terry J. Garrett Vice President Engineering Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION
Dear Mr. Garrett:
By letter dated September 27, 2006, Wolf Creek Nuclear Operating Corporation submitted an application pursuant to 10 CFR Part 54, to renew the operating license for Wolf Creek Generating Station, Unit 1, for review by the U.S. Nuclear Regulatory Commission (NRC or the staff). The staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review. These requests for additional information were discussed with Lorrie Bell, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3703 or e-mail VMR1@nrc.gov. Sincerely, /RA/
Verónica M. Rodríguez, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation
Docket No. 50-482
Enclosure:
Requests for Additional Information
cc w/encl: See next page
ML072680037 OFFICE LA:DLR PM:RLRB:DLR BC:RLRB:DLR NAME SFigueroa VRodríguez RAuluck DATE 09/25/07 09/27/07 09/27/07 Letter to T. Garrett From V. Rodriguez Dated September 27, 2007 DISTRIBUTION:
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE WOLF CREEK GENERATING STATION, UNIT 1, LICENSE RENEWAL APPLICATION
HARD COPY DLR RF E-MAIL: PUBLIC SSmith (srs3) SDuraiswamy RidsNrrDlr RidsNrrDlrRlra RidsNrrDlrRlrb RidsNrrDlrRlrc RidsNrrDlrReba RidsNrrDlrRebb RidsNrrDciCvib RidsNrrDciCpnb RidsNrrDraAfpb RidsNrrDeEmcb RidsNrrDeEeeb RidsNrrDssSrxb RidsNrrDssSbpb RidsNrrDssScvb RidsOgcMailCenter ------------- VRodriguez CJacobs JDonohew GPick, RIV SCochrum, RIV CLong, RIV
Wolf Creek Generating Station cc: Jay Silberg, Esq. Pillsbury Winthrop Shaw Pittman, LLP 2300 N Street, NW Washington, DC 20037 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-7005 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 311 Burlington, KS 66839
Chief Engineer, Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, KS 66604-4027
Office of the Governor State of Kansas Topeka, KS 66612 Attorney General 120 S.W. 10 th Avenue, 2 nd Floor Topeka, KS 66612-1597 County Clerk Coffey County Courthouse 110 South 6 th Street Burlington, KS 66839 Chief, Radiation and Asbestos Control Section Kansas Department of Health and Environment Bureau of Air and Radiation 1000 SW Jackson, Suite 310 Topeka, KS 66612-1366 Vice President Operations/Plant Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 Supervisor Licensing Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 U.S. Nuclear Regulatory Commission Resident Inspectors Office/Callaway Plant 8201 NRC Road Steedman, MO 65077-1032 Kevin J. Moles, Manager Regulatory Affairs Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
Lorrie I. Bell, Project Manager Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839
Enclosure WOLF CREEK GENERATING STATION, UNIT 1 LICENSE RENEWAL APPLICATION REQUESTS FOR ADDITIONAL INFORMATION (RAI)
The license renewal application (LRA) states that the Steam Generator Tube Integrity aging management program (AMP) is consistent, with exceptions, to the Generic Aging Lessons Learned (GALL) Report. The GALL Report states, in part, that the degradation management program in Nuclear Energy Institute (NEI) 97-06, "Steam Generator Tube Integrity," is adequate to manage the effects of aging of the steam generator tubes. NEI 97-06 references guideline documents developed by the Electric Power Research Institute (EPRI) for managing areas important to steam generator tube integrity, including tube inspections.
The LRA discusses several exceptions taken to the EPRI guidelines. With respect to these exceptions, the staff requests that the applicant address the following:
RAI B2.1.8-1 The LRA states that the rotating pancake probe is used to inspect from 3 inches above to 3 inches below the top of the tubesheet and that the bobbin probe is used to inspect the entire engagement length of the hydraulically expanded tubesheet region. However, the bobbin probe is not qualified for inspection in this area. The application also states that there was a one-cycle license amendment request to use an alternate tube repair criteria which, in part, eliminated the need to inspect near the tube ends on the hot-leg side of the steam generator.
The EPRI guidelines indicate that the full length of the steam generator tubes requires an inspection with an inspection technique qualified for each region of the tube.
The staff requests that the applicant clarify this exception to the GALL Report and the EPRI guidelines. For example, clarify whether the exception being taken to the EPRI guidelines is that the entire tube is not inspected or whether Wolf Creek Generating Station (WCGS) is not inspecting the portions of the tube required to be inspected with techniques capable of detecting flaws that may be occurring in that region. The staff notes that the tube is required to be inspected with the objective of detecting flaws of any type and that may satisfy the applicable tube repair criteria (WCGS technical specification 5.5.9.d). As a result, if cracking of the tube could occur at various locations within the tubesheet, these areas should be inspected with techniques capable of finding these flaws (and consistent with the sampling and tube integrity requirements of the technical specifications). The staff notes that inspection near the tube ends on the hot-leg side of the steam generator is not required for refueling outage fifteen and the subsequent operating cycle (since this portion of tube is explicitly exempted from the inspection requirements in the technical specifications).
2 RAI B2.1.8-2
The LRA states that the bobbin probe is used to detect primary water stress corrosion cracking at tube dents in support plates and stress corrosion cracking in free span regions. However, the bobbin probe is not qualified for detection of these degradation mechanisms when the voltage of the dent exceeds certain threshold values.
The EPRI guidelines indicate that the full length of the steam generator tubes requires an inspection with an inspection technique qualified for each region of the tube.
The staff requests that the applicant clarify the nature of this exception to the GALL Report and EPRI guidelines since the WCGS technical specifications require, in part, to (a) perform an assessment of the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what locations; and (b) to inspect the tubes with the objective of detecting flaws that may satisfy the applicable tube repair criteria.
In light of these requirements, if WCGS concludes that primary water stress corrosion cracking could occur at tube dents in support plates or outer diameter stress corrosion cracking could occur in free span regions, these regions should be inspected with techniques capable of finding these forms of degradation.
RAI B2.1.8-3
The LRA indicates that the EPRI guidelines require that if active damage mechanisms are identified then all steam generators shall be examined at the end of each fuel cycle. The application also states that although WCGS currently has one active damage mechanism (i.e., wear at anti-vibration bars), only two steam generators are inspected at each refueling outage on an alternating basis so that each steam generator is examined every other refueling outage.
The staff requests that the applicant confirm that WCGS has verified the acceptability of this approach each outage by confirming that tube integrity will be maintained for the period of time between the planned inspections of the steam generators (consistent with the technical specification requirements).
RAI B2.1.8-4 The LRA states that structural integrity limits consistent with Regulatory Guide 1.121, "Bases for Plugging Degraded PWR Steam Generator Tubes" are applied as part of the Steam Generator Tube Integrity AMP. The staff requests that the applicant confirm that the AMP also includes the structural integrity limits contained within the WCGS technical specifications.