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| {{#Wiki_filter:Michael T. Boyce Vice President Engineering May 12, 2022 ET 22-0009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 | | {{#Wiki_filter:Michael T. Boyce Vice President Engineering |
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| | May 12, 2022 ET 22-0009 |
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| | U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 |
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| ==Reference:== | | ==Reference:== |
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| ==Subject:== | | ==Subject:== |
| Docket No. 50-482: Withdrawal of 10 CFR 50.55a Request I4R-09, Relief from Examination of Reactor Vessel Flange Threads Commissioners and Staff: | | Docket No. 50-482: Withdrawal of 10 CFR 50.55a Reque st I4R-09, Relief from Examination of Reactor Vessel Flange Threads |
| The purpose of this submittal is to withdraw Wolf Creek Nuclear Operating Corporation (WCNOC) 10 CFR 50.55a Request originally provided by the Reference. The Reference transmitted 10 CFR 50.55a Request I4R-09 for an alternative to the requirement of the American Society of Mechanical Engineers (ASME) Code, Section XI, Examination Category B-G-1, Item Number B6.40, Threads in Flange, to perform ultrasonic examinations of threads in reactor pressure vessel closure flange connections every inservice inspection (ISI) interval. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.147, Revision 20 was effective as of April 4, 2022. | | |
| In this revision, ASME Section XI Code Case N-864 was conditionally approved by the NRC. | | Commissioners and Staff: |
| Code Case N-864 allows that reactor pressure vessel threads in flange examinations be performed in at least every third 10-year ISI interval. The conditions include that monitoring and maintenance activities must be performed and documented to monitor the condition of the reactor pressure vessel threads in flange for signs of degradation and to mitigate any degradation that occurs. WCNOC plans to evaluate the use of this Code Case and implement appropriate necessary actions to meet these conditions. Therefore, WCNOC is withdrawing the proposed request and is no longer seeking NRC review and approval of I4R-09. | | |
| P.O. Box 411 l Burlington, KS 66839 l 620-364-8831 | | The purpose of this submittal is to withdraw Wolf Creek Nuclear Operating Corporation (WCNOC) 10 CFR 50.55a Request originally provided by the Reference. Th e Reference transmitted 10 CFR 50.55a Request I4R-09 for an alternative to the requirement of the American Society of Mechanical Engineers (ASME) Code, Section XI, Examination Categ ory B-G-1, Item Number B6.40, Threads in Flange, to perform ultrasonic examinations of threads in reactor pressure vessel closure flange connections every inservice inspection (I SI) interval. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.147, Revision 20 was e ffective as of April 4, 2022. |
| | In this revision, ASME Section XI Code Case N-864 was condition ally approved by the NRC. |
| | Code Case N-864 allows that reactor pressure vessel threads in flange examinations be performed in at least every third 10-year ISI interval. The co nditions include that monitoring and maintenance activities must be performed and documented to moni tor the condition of the reactor pressure vessel threads in flange for signs of degradation and to mitigate any degradation that occurs. WCNOC plans to evaluate the use of this Code Case and implement appropriate necessary actions to meet these conditions. Therefore, WCNOC i s withdrawing the proposed request and is no longer seeking NRC review and approval of I4R -09. |
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| | P.O. Box 411 l Burlington, KS 66839 l 620-364-8831 ET 22-0009 Page 2 of 2 |
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| | This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-8831 x8687, or Ron Benham at (620) 364-4204. |
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| | Sincerely, |
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| | Michael T. Boyce |
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| | MTB/rlt |
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| ET 22-0009 Page 2 of 2 This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-8831 x8687, or Ron Benham at (620) 364-4204.
| | cc: S. S. Lee (NRC) |
| Sincerely, Michael T. Boyce MTB/rlt cc: S. S. Lee (NRC)
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| S. A. Morris, (NRC) | | S. A. Morris, (NRC) |
| G. E. Werner (NRC) | | G. E. Werner (NRC) |
| Senior Resident Inspector (NRC)}} | | Senior Resident Inspector (NRC)}} |
Letter Sequence Request |
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EPID:L-2022-LLR-0043, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads (Withdrawn, Closed) |
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Category:Letter
MONTHYEARIR 05000482/20244202024-10-31031 October 2024 Security Baseline Inspection Report 05000482/2024420 ML24296B1902024-10-22022 October 2024 10 CFR 50.55a Requests for the Fifth Ten-Year Interval Inservice Testing Program 05000482/LER-2024-001-01, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-10-22022 October 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing 05000482/LER-2024-002, Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve2024-10-21021 October 2024 Technical Specification Required Shutdown Due to Inoperable Auxiliary Feedwater Discharge Valve ML24284A2842024-10-10010 October 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) ML24283A0752024-10-0909 October 2024 Notification of Commercial Grade Dedication Inspection (05000482/2025012) and Request for Information ML24199A1712024-09-17017 September 2024 Issuance of Amendment No. 241 Revise Ventilation Filter Testing Program Criteria and Administrative Correction of Absorber in Technical Specification 5.5.11 ML24260A0712024-09-12012 September 2024 License Amendment Request for a Risk-Informed Resolution to GSI-191 IR 05000482/20240102024-09-10010 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000482/2024010 (Public) ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24248A0762024-09-0404 September 2024 Containment Inservice Inspection Program Third Interval, Second Period, Refueling Outage 26 Owner’S Activity Report ML24248A2492024-09-0404 September 2024 Inservice Inspection Program Fourth Interval, Third Period, Refueling Outage 26 Owner’S Activity Report ML24241A2212024-08-29029 August 2024 Notice of Enforcement Discretion for Wolf Creek Generating Station ML24240A2642024-08-27027 August 2024 Corporation - Request for Notice of Enforcement Discretion Regarding Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000482/20240052024-08-14014 August 2024 Updated Inspection Plan for Wolf Creek Generating Station (Report 05000482/2024005) ML24227A5562024-08-14014 August 2024 Application to Revise Technical Specifications to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24213A3352024-07-31031 July 2024 License Amendment Request to Revise Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology), to Implement the Methodology from WCAP-17661-P-A, Revision 1. ML24206A1252024-07-24024 July 2024 Revision of Three Procedures and Two Forms That Implement the Radiological Emergency Response Plan (RERP) IR 05000482/20240022024-07-18018 July 2024 Integrated Inspection Report 05000482/2024002 05000482/LER-2024-001, Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing2024-07-0202 July 2024 Mode 3 Entry with One Auxiliary Feedwater Pump Train Inoperable Due to Missed Post-Maintenance Testing IR 05000482/20244012024-07-0202 July 2024 Security Baseline Inspection Report 05000482/2024401 ML24178A3672024-06-26026 June 2024 Correction to 2023 Annual Radioactive Effluent Release Report – Report 47 ML24178A4142024-06-26026 June 2024 Revision of One Procedure and One Form That Implement the Radiological Emergency Response Plan (RERP) ML24162A1632024-06-11011 June 2024 Operating Corporation – Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000482/2024010) ML24150A0562024-05-29029 May 2024 Foreign Ownership, Control or Influence (FOCI) Information – Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML23345A1602024-05-0909 May 2024 Revision of Safety Evaluation for Amendment No. 237 Request for Deviation from Fire Protection Requirements ML24089A2622024-04-29029 April 2024 Financial Protection Levels ML24118A0022024-04-27027 April 2024 Wolf Generating Nuclear Station - 2023 Annual Radiological Environmental Operating Report ML24118A0032024-04-27027 April 2024 2023 Annual Radioactive Effluent Release Report - Report 47 ML24113A1882024-04-19019 April 2024 Foreign Ownership, Control or Influence Information - Change to Lists of Owners, Officers, Directors and Executive Personnel - Form 405F Amendment ML24109A1842024-04-18018 April 2024 Cycle 27 Core Operating Limits Report ML24109A1212024-04-18018 April 2024 (WCGS) Form 5 Exposure Report for Calendar Year 2023 IR 05000482/20240012024-04-17017 April 2024 Integrated Inspection Report 05000482/2024001 ML24114A1442024-04-15015 April 2024 Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37 ML24106A1482024-04-15015 April 2024 Notification of Inspection (NRC Inspection Report 05000482/2024003) and Request for Information ML24098A0052024-04-0707 April 2024 2023 Annual Environmental Operating Report ML24089A0972024-03-29029 March 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24089A1352024-03-29029 March 2024 10 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes ML24074A3312024-03-14014 March 2024 Missed Quarterly Inspection Per 40 CFR 266 Subpart N IR 05000482/20240122024-03-11011 March 2024 Fire Protection Team Inspection Report 05000482/2024012 ML24080A3452024-03-11011 March 2024 7 of the Wolf Creek Generating Station Updated Safety Analysis Report ML24016A0702024-03-0808 March 2024 Issuance of Amendment No. 240 Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML24068A1992024-03-0707 March 2024 Changes to Technical Specification Bases - Revisions 93 and 94 ML24066A0672024-03-0505 March 2024 4-2022-024 Letter - OI Closure to Licensee ML24061A2642024-03-0101 March 2024 Revision of Two Procedures That Implement the Radiological Emergency Response Plan (RERP) for Wolf Creek Generating Station (WCGS) Commissioners IR 05000482/20230062024-02-28028 February 2024 Annual Assessment Letter for Wolf Creek Generating Station Report 05000482/2023006 ML24059A1702024-02-28028 February 2024 Annual Fitness for Duty Program Performance Report, and Annual Fatigue Report for 2023 ML24026A0212024-02-27027 February 2024 Issuance of Amendment No. 239 Modified Implementation Date of License Amendment No. 238 ML24050A0012024-02-19019 February 2024 (Wcgs), Revision of One Form That Implements the Radiological Emergency Response Plan (RERP) 2024-09-06
[Table view] |
Text
Michael T. Boyce Vice President Engineering
May 12, 2022 ET 22-0009
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Reference:
Letter ET 22-0003, dated April 6, 2022, from M. T. Boyce, WCNOC, to USNRC
Subject:
Docket No. 50-482: Withdrawal of 10 CFR 50.55a Reque st I4R-09, Relief from Examination of Reactor Vessel Flange Threads
Commissioners and Staff:
The purpose of this submittal is to withdraw Wolf Creek Nuclear Operating Corporation (WCNOC) 10 CFR 50.55a Request originally provided by the Reference. Th e Reference transmitted 10 CFR 50.55a Request I4R-09 for an alternative to the requirement of the American Society of Mechanical Engineers (ASME) Code,Section XI, Examination Categ ory B-G-1, Item Number B6.40, Threads in Flange, to perform ultrasonic examinations of threads in reactor pressure vessel closure flange connections every inservice inspection (I SI) interval. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.147, Revision 20 was e ffective as of April 4, 2022.
In this revision, ASME Section XI Code Case N-864 was condition ally approved by the NRC.
Code Case N-864 allows that reactor pressure vessel threads in flange examinations be performed in at least every third 10-year ISI interval. The co nditions include that monitoring and maintenance activities must be performed and documented to moni tor the condition of the reactor pressure vessel threads in flange for signs of degradation and to mitigate any degradation that occurs. WCNOC plans to evaluate the use of this Code Case and implement appropriate necessary actions to meet these conditions. Therefore, WCNOC i s withdrawing the proposed request and is no longer seeking NRC review and approval of I4R -09.
P.O. Box 411 l Burlington, KS 66839 l 620-364-8831 ET 22-0009 Page 2 of 2
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-8831 x8687, or Ron Benham at (620) 364-4204.
Sincerely,
Michael T. Boyce
MTB/rlt
cc: S. S. Lee (NRC)
S. A. Morris, (NRC)
G. E. Werner (NRC)
Senior Resident Inspector (NRC)