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| | number = ML17054C235 | | | number = ML17054C235 |
| | issue date = 01/17/2017 | | | issue date = 01/17/2017 |
| | title = Wolf Creek, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WOG-93-066 | | | title = License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WOG-93-066 |
| | author name = | | | author name = |
| | author affiliation = Wolf Creek Nuclear Operating Corp | | | author affiliation = Wolf Creek Nuclear Operating Corp |
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| {{#Wiki_filter:L r UNirf.D STATU NUCLEAR REGULATORY COMMISSION WASHINOTO | | {{#Wiki_filter:r UNirf.D STATU Attachment to WOG-93-066 NUCLEAR REGULATORY COMMISSION WASHINOTO ... 0 C. %0551 March 10, 1993 Mr. Lawrence A. Walsh, Chairman Westinghouse Owners croup North Atlantic Energy Services corporation P. 0. Sox JOO seabrook, NH OJ874 |
| ... 0 C. %0551 Mr. Lawrence A. Walsh, Chairman Westinghouse O wners croup March 10, 1993 North Atlantic Energy Services corporation P. 0. Sox JOO seabrook, NH OJ874 Attachment to WOG-93-066 | |
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| ==Dear Mr. Walsh:== | | ==Dear Mr. Walsh:== |
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| ==SUBJECT:==
| | SUBJECT : Westinghouse owners Croup-Steam Generator Tube |
| Westinghouse owners Croup-Steam Generator Tube Uncovery Issue | | ~ Uncovery Issue |
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| ==References:== | | ==References:== |
| (l) WCAP-13247, "Report on the methodoloqy tor th@ resolution of the steam qenerator tube uncovery iasu*." dated March 1992. (2) letter !rom Lawrence A. Walsh to Robert c. Jones, "Westinghousa Owners croup -Steam generator tube uncovery issue," dated March 31, l9SJ2. (J) Memorandum from LeMoine J. cunningham to Robert C. Jcnes, "WCAP-1J247," report on the methodoloqy
| | (l) WCAP-13247, "Report on the methodoloqy tor th@ resolution of the steam qenerator tube uncovery iasu*." dated March 1992. |
| !or the resolution ot the steam generator tube uncovery issue," submitted by Westinghouse Owners Croup dated 14, 1992. In July 1987, North Anna Unit 1 steam generator tube rupture 1ndicated that the apex of the steam generator tubes may have been partially uncovered for 10-15 minutes. In response to concerns expressed by the NRC staff, the Westinghouse owners Group (WOG) initiated | | (2) letter !rom Lawrence A. Walsh to Robert c. |
| & program in to if the iodine release resulting from partial uncovery of qenerator tubes during a steam generator tube rupture (SCTR) event or other limiting event can have a s1gnificant safety impact on Westinghouse plants. As discussed in your letter of March 31, 1992 (Ref. 2), we understand that WOG has completed its work on this matter, and that WCAP-13247 (Ref. 1) demonstrates that a significant safety issue does not for Westinghouse facilities. | | Jones, "Westinghousa Owners croup - Steam generator tube uncovery issue," dated March 31, l9SJ2. |
| Based on our review of WCAP-13247, it is our understanding that Westinghouse performed representative SGTR analyses using the LOFTTR2 computer code to characterize the thermal and hydraulic response to various SGTR scenarios for representative plants and | | (J) Memorandum from LeMoine J . cunningham to Robert C. Jcnes, "WCAP-1J247," report on the methodoloqy !or the resolution ot the steam generator tube uncovery issue," submitted by Westinghouse Owners Croup dated Septemb~r 14, 1992. |
| ) . ) to provide boundary conditions tor the mixture level model. The represQntative plants used !or the analyses were a !our-loop plant with model steam generators and a two-loop plant with model 44 tteam generators.
| | In July 1987, North Anna Unit 1 steam generator tube rupture 1ndicated that the apex of the steam generator tubes may have been partially uncovered for 10-15 minutes. In response to concerns expressed by the NRC staff, the Westinghouse owners Group (WOG) initiated & program in ~9e8 to de~ermine if the iodine release resulting from partial uncovery of ste~~ qenerator tubes during a steam generator tube rupture (SCTR) event or other limiting event can have a s1gnificant safety impact on Westinghouse plants. As discussed in your letter of March 31, 1992 (Ref. 2), we understand that th~ WOG has completed its work on this matter, and that WCAP-13247 (Ref. 1) demonstrates that a significant safety issue does not ~xist for Westinghouse facilities. |
| These plants were selected model 51 and model 44 steam generators expected to be most susceptible to tube uncovery during an event. Westinghouse pertormed the LOFTTR2 analyaes tor the following accident scenarios: (a) SGTR with a stuck-open PORV; (b) SGTR with a modulating PORV; and (c) SGTR with a cycling safety valve. The stuck-open PORV case resulted in the highest steam release and consequently the greatest of!site dose consequences. | | Based on our review of WCAP-13247, it is our understanding that Westinghouse performed representative SGTR analyses using the LOFTTR2 computer code to characterize the thermal and hydraulic response to various SGTR scenarios for representative plants and L |
| The results ot these LOFTTR2 ar.alyses were then used as boundary conditions to the gen*ratvr watec level tor the duration of these events. The results o! iodine release calculation indicated the SGTR analysis with a stuck-open PORV yields the highest iodine release with only about 1\ ot the release being attributable to steam generator tube uncovery. | | |
| Thus, Westinghouse concluded that the ettect o! tube uncovery is esaentially negligible tor the transient, and that the design basis SGTR analysis methodology remains valid. Based on our review ot your submittal, we believe that the WOG program repre3ents a comprehensive e!tort to address the staff's concerns. | | to provide boundary conditions tor the mixture level model. The represQntative plants used !or the analyses were a !our-loop plant with model ~l steam generators and a two-loop plant with model 44 tteam generators. These plants were selected beca~** |
| The assumptions and parameters used in the iodine transport are consistent with the criteria established by the staff in the Standard Review Plan (Section 15.6.3), and the Westinqhouae demonstrate that the e!!ects of partial steam tube uncovery on the iodine release !or SGTR and non-SGTR events is negligible. | | model 51 and model 44 steam generators a~e expected to be most susceptible to tube uncovery during an event. Westinghouse pertormed the LOFTTR2 analyaes tor the following accident scenarios: (a) SGTR with a stuck-open PORV; (b) SGTR with a modulating PORV; and (c) SGTR with a cycling safety valve. The stuck-open PORV case resulted in the highest steam release and consequently the greatest of!site dose consequences. The results ot these LOFTTR2 ar.alyses were then used as boundary conditions to com~ute the st~am gen*ratvr watec level tor the duration of these events. The results o! ~he iodine release calculation indicated th~t the SGTR analysis with a stuck-open PORV yields the highest iodine release with only about 1\ ot the release being attributable to steam generator tube uncovery. Thus, |
| Therefore, we agree your position on this and consider this issue to be resolved. | | ) Westinghouse concluded that the ettect o! tube uncovery is esaentially negligible tor the limi~inq transient, and that the curr~nt design basis SGTR analysis methodology remains valid. |
| Thank-you tor your attention and efforts in resolving this matter. Sincerely, C.tcfl4f.t Reactor Systems Branch Division of Systems Safety and Analysis cc: | | Based on our review ot your submittal, we believe that the WOG program repre3ents a comprehensive e!tort to address the staff's concerns. The assumptions and parameters used in the iodine transport quanti!icati~n are consistent with the criteria established by the staff in the Standard Review Plan (Section |
| A. Engel (TU Electric) | | . ) |
| ----*-*---}} | | 15.6.3), and the Westinqhouae a~alysea demonstrate that the e!!ects of partial steam ~enerator tube uncovery on the iodine release !or SGTR and non-SGTR events is negligible. Therefore, we agree ~ith your position on this ~atter and consider this issue to be resolved. |
| | Thank-you tor your attention and efforts in resolving this matter. |
| | Sincerely, C.tcfl4f.t Reactor Systems Branch Division of Systems Safety and Analysis cc: .t~; voyt:ell:.~q\0, A. Engel (TU Electric) |
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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:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24018A2482024-01-18018 January 2024 License Amendment Request to Modify the Implementation Date of License Amendment No. 238 ML23331A4972023-11-27027 November 2023 Supplement to License Amendment Request to Modify the 90-Day Implementation of License Amendment No. 237 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 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 ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML23045A1952023-02-14014 February 2023 Transmittal of the National Pollution Discharge Elimination System Permit Renewal Application for Wolf Creek Generating Station I-NE07-PO02 ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22353A5552022-12-15015 December 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 WO 21-0015, License Amendment Request (LAR) for Revision to the Emergency Plan2021-05-25025 May 2021 License Amendment Request (LAR) for Revision to the Emergency Plan WM 21-0005, Supplement to License Amendment Request for Change to Owner Licensee Names2021-05-24024 May 2021 Supplement to License Amendment Request for Change to Owner Licensee Names ML21070A0582021-03-11011 March 2021 Changes to Technical Specification Bases - Revisions 82, 83, 84, and 85 WO 20-0050, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange2020-11-10010 November 2020 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange WM 20-0006, (WCGS) - License Amendment Request for Change to Owner Licensee Names2020-11-0404 November 2020 (WCGS) - License Amendment Request for Change to Owner Licensee Names ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) WO 20-0029, License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2020-04-20020 April 2020 License Amendment Request to Revise Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies WO 19-0033, License Amendment Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System2019-08-29029 August 2019 License Amendment Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System WO 19-0031, Supplement 1 to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-08-0808 August 2019 Supplement 1 to Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ML19052A5462019-04-0101 April 2019 Issuance of Amendment No. 220 Revision to the Emergency Plan ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 WO 18-0044, Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-11-15015 November 2018 Clean Revised Technical Specification Pages for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term WO 18-0034, Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-08-0909 August 2018 Operating Corp., Additional Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ML18135A1462018-05-0909 May 2018 Attachments I to V: Evaluation of Proposed Changes, Emergency Plan Change Summary, ERO Position Matrix, Summary of Shift Staffing and Letter of Consultation and Concurrence from Off-Site Response Organizations Ack of Opportunity WO 18-0016, License Amendment Request for Revision to the Emergency Plan2018-05-0909 May 2018 License Amendment Request for Revision to the Emergency Plan ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ML17363A1422017-12-19019 December 2017 License Amendment Request (LAR) for Revision to the Emergency Plan (Attachments and Enclosures) WM 17-0021, Updated Request for Consent to Indirect Transfer of Control2017-09-0505 September 2017 Updated Request for Consent to Indirect Transfer of Control WO 17-0026, Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses2017-03-22022 March 2017 Errata for License Amendment Request for Transition to Westinghouse Core Design and Safety Analyses ML17054C2232017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed COLR Changes ET 17-0001, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses, Enclosure 10 - CAW-16-45002017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses, Enclosure 10 - CAW-16-4500 ML17054C2272017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Alternative Source Term, Rev 1 ML17054C2362017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses, Enclosure 9 - CAW-16-4499 ML17054C2192017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Evaluation ML17054C2352017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WOG-93-066 ML17054C2302017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - A-3788, Technical Report, Appendix a, Fission Product Removal Effectiveness of Chemical Additives in PWR Containment Sprays ML17054C2332017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - CAW-92-287 ML17054C2202017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Changes ML17054C2262017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WCAP-18083-NP, Rev 0, Westinghouse Revised Thermal Design Procedure Uncertainty Calculations. ML17054C2222017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Proposed Technical Specification Bases Changes ML17054C2322017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - OG-92-25, Steam Generator Tube Uncovery Issue ML17054C2212017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Revised Technical Specification Pages ML17054C2292017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Responses to NRC RAIs on August 2013 Methodology Transition LAR Submittal NEI 99-01, Wolf Creek Nuclear Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors2016-09-30030 September 2016 Wolf Creek Nuclear Operating Corporation Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors 2024-01-18
[Table view] Category:Topical Report
MONTHYEARML17054C2362017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses, Enclosure 9 - CAW-16-4499 ML17054C2352017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WOG-93-066 ML17054C2262017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WCAP-18083-NP, Rev 0, Westinghouse Revised Thermal Design Procedure Uncertainty Calculations. ML17054C2292017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Responses to NRC RAIs on August 2013 Methodology Transition LAR Submittal ML17054C2332017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - CAW-92-287 ML17054C2302017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - A-3788, Technical Report, Appendix a, Fission Product Removal Effectiveness of Chemical Additives in PWR Containment Sprays ET 17-0001, License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses, Enclosure 10 - CAW-16-45002017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses, Enclosure 10 - CAW-16-4500 ML17054C2272017-01-17017 January 2017 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - Alternative Source Term, Rev 1 ML17054C2242014-01-17017 January 2014 License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses - WCAP-17658-NP, Rev 1, Transition of Methods for Core Design and Safety Analyses - Licensing Report. ML13177A2842013-06-30030 June 2013 WCAP-17678-NP, Supplement 1, Revision 1, Wolf Creek Generating Station Supplemental Information for Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report, Part 1 of 3 ML13177A2862013-06-30030 June 2013 WCAP-17678-NP, Supplement 1, Revision 1, Wolf Creek Generating Station Supplemental Information for Post-Fukushima NTTF 2.3 Seismic Walkdown Submittal Report, Part 2 of 3 ML0915901672009-04-30030 April 2009 Enclosure II - Westinghouse Electric Company LLC, WCAP-17071-NP, H*: Alternate Repair Criteria for the Resrad Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F) ET 08-0005, Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls2008-01-18018 January 2008 Response to Request for Additional Information Relating to Replacement of the Main Steam and Feedwater Isolation Valves and Controls ML0715502262007-05-31031 May 2007 WCAP-15791-NP, Revision 2, Draft, Risk-Informed Evaluation of Extensions to Containment Isolation Valve Completion Times. ML0628904202006-08-30030 August 2006 WCAP-16589-NP, Rev 0, Structural Integrity Evaluation of Reactor Vessel Upper Head Penetrations to Support Continued Operation: Wolf Creek. ML0627703602006-07-31031 July 2006 to Topical Report WCAP-16308-NP, Pressurized Water Reactor Owners Group 10 CFR 50.69 Pilot Program - Categorization Process - Wolf Creek Generating Station. ML0423902142004-08-20020 August 2004 Westinghouse Owners Group Request to Withdraw WCAP-16168-NP, Risk-Informed Extension of Reactor Vessel In-Service Inspection Interval, (PA-MSC-0120) ML0332302252003-11-12012 November 2003 Submittal of WCAP-16084-NP, Development of Risk-Informed Safety Analysis Approach and Pilot Application. ML0310600762003-04-0808 April 2003 Submittal of Test Results for Withdrawal of Surveillance Capsule X from Reactor Vessel 2017-01-17
[Table view] |
Text
r UNirf.D STATU Attachment to WOG-93-066 NUCLEAR REGULATORY COMMISSION WASHINOTO ... 0 C. %0551 March 10, 1993 Mr. Lawrence A. Walsh, Chairman Westinghouse Owners croup North Atlantic Energy Services corporation P. 0. Sox JOO seabrook, NH OJ874
Dear Mr. Walsh:
SUBJECT : Westinghouse owners Croup-Steam Generator Tube
~ Uncovery Issue
References:
(l) WCAP-13247, "Report on the methodoloqy tor th@ resolution of the steam qenerator tube uncovery iasu*." dated March 1992.
(2) letter !rom Lawrence A. Walsh to Robert c.
Jones, "Westinghousa Owners croup - Steam generator tube uncovery issue," dated March 31, l9SJ2.
(J) Memorandum from LeMoine J . cunningham to Robert C. Jcnes, "WCAP-1J247," report on the methodoloqy !or the resolution ot the steam generator tube uncovery issue," submitted by Westinghouse Owners Croup dated Septemb~r 14, 1992.
In July 1987, North Anna Unit 1 steam generator tube rupture 1ndicated that the apex of the steam generator tubes may have been partially uncovered for 10-15 minutes. In response to concerns expressed by the NRC staff, the Westinghouse owners Group (WOG) initiated & program in ~9e8 to de~ermine if the iodine release resulting from partial uncovery of ste~~ qenerator tubes during a steam generator tube rupture (SCTR) event or other limiting event can have a s1gnificant safety impact on Westinghouse plants. As discussed in your letter of March 31, 1992 (Ref. 2), we understand that th~ WOG has completed its work on this matter, and that WCAP-13247 (Ref. 1) demonstrates that a significant safety issue does not ~xist for Westinghouse facilities.
Based on our review of WCAP-13247, it is our understanding that Westinghouse performed representative SGTR analyses using the LOFTTR2 computer code to characterize the thermal and hydraulic response to various SGTR scenarios for representative plants and L
to provide boundary conditions tor the mixture level model. The represQntative plants used !or the analyses were a !our-loop plant with model ~l steam generators and a two-loop plant with model 44 tteam generators. These plants were selected beca~**
model 51 and model 44 steam generators a~e expected to be most susceptible to tube uncovery during an event. Westinghouse pertormed the LOFTTR2 analyaes tor the following accident scenarios: (a) SGTR with a stuck-open PORV; (b) SGTR with a modulating PORV; and (c) SGTR with a cycling safety valve. The stuck-open PORV case resulted in the highest steam release and consequently the greatest of!site dose consequences. The results ot these LOFTTR2 ar.alyses were then used as boundary conditions to com~ute the st~am gen*ratvr watec level tor the duration of these events. The results o! ~he iodine release calculation indicated th~t the SGTR analysis with a stuck-open PORV yields the highest iodine release with only about 1\ ot the release being attributable to steam generator tube uncovery. Thus,
) Westinghouse concluded that the ettect o! tube uncovery is esaentially negligible tor the limi~inq transient, and that the curr~nt design basis SGTR analysis methodology remains valid.
Based on our review ot your submittal, we believe that the WOG program repre3ents a comprehensive e!tort to address the staff's concerns. The assumptions and parameters used in the iodine transport quanti!icati~n are consistent with the criteria established by the staff in the Standard Review Plan (Section
. )
15.6.3), and the Westinqhouae a~alysea demonstrate that the e!!ects of partial steam ~enerator tube uncovery on the iodine release !or SGTR and non-SGTR events is negligible. Therefore, we agree ~ith your position on this ~atter and consider this issue to be resolved.
Thank-you tor your attention and efforts in resolving this matter.
Sincerely, C.tcfl4f.t Reactor Systems Branch Division of Systems Safety and Analysis cc: .t~; voyt:ell:.~q\0, A. Engel (TU Electric)
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