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MONTHYEARML1006302372010-03-0303 March 2010 Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.6.3, Containment Isolation Valves Limiting Condition for Operation Project stage: Acceptance Review ML1021703352010-11-0303 November 2010 Issuance of Amendment No. 190, Revise Technical Specification 3.6.3, Containment Isolation Valves, Limiting Condition for Operation Project stage: Approval 2010-11-03
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Category:Acceptance Review Letter
MONTHYEARML21294A0792021-10-22022 October 2021 Withdrawal of Requested Licensing Action License Amendment and Regulatory Exemption for Risk-Informed Approach to Address Generic Safety Issue 191 & Respond to Generic Letter 2004-02 ML18143B3922018-05-21021 May 2018 Acceptance Review - License Amendment Request for Revision to Emergency Plan ML17132A3632017-05-15015 May 2017 Acceptance of Requested Licensing Action License Amendment Request for the Transition to Westinghouse Core Design and Safety Analyses in Addition to Adopting of Alternative Source Term ML12321A3092012-11-16016 November 2012 Acceptance Review for License Amendment Request, Revise Paragraph 2.C(5)(a) of Facility Operating License NPF-42 and the Updated Safety Analysis Report for a Deviation from Appendix R for Volume Control Tank Outlet Valves ML12286A0452012-10-11011 October 2012 Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement 3.8.1.10 to Increase Voltage Limit for Diesel Generator Load Rejection Test ML12200A0812012-07-18018 July 2012 Acceptance Review Email, License Amendment Request to Revise Physical Security License Condition to Support Cyber Security Plan Implementation Schedule Change ML1116101862011-06-10010 June 2011 Acceptance Review Email, License Amendment Request, Administrative Changes to Technical Specification 5.3, Unit Staff Qualifications ML1100502262011-01-0505 January 2011 Acceptance Review Email, License Amendment Request, Revise TS 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Temporary Alternate Repair Criterion ML1031900982010-11-15015 November 2010 Acceptance Review Email, License Amendment Request, Correction of Typographical Error in Technical Specification 5.7.2, Administrative Controls High Radiation Area ML1021702992010-08-0505 August 2010 Acceptance Review Email License Amendment Request for Approval of the Cyber Security Plan ML1013700912010-05-20020 May 2010 Non-Acceptance with Opportunity to Supplement License Amendment Request, Revise Approved Fire Protection Program to Remove High/Low Pressure Designation from Pressurizer Power Operated Relief Valves ML1013702642010-05-14014 May 2010 Acceptance Review E-mail, License Amendment Request to Revise TS 3.3.2, Engineered Safety Feature Actuation System Instrumentation, Table 3.3.2-1 to Identify Functions and Modes for Reactor Trip P-4 Interlock Function ML1006302372010-03-0303 March 2010 Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.6.3, Containment Isolation Valves Limiting Condition for Operation ML1002505762010-01-25025 January 2010 Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.8.4, DC Sources - Operating, for Battery Connection Resistance Acceptance Criteria ML1000702452010-01-0707 January 2010 Acceptance Review E-mail, Exemption from 10 CFR Part 73 Physical Security Requirements ML0935800682009-12-23023 December 2009 Acceptance Review E-mail License Amendment Request to Revise Technical Specification 3.8.1, AC Sources-Operating. ML0915902212009-06-0808 June 2009 Acceptance Review Email, License Amendment Request, Revise Technical Specifications 5.5.9, Steam Generator Program, and 5.6.10, Steam Generator Tube Inspection Report, for Permanent Alternate Repair Criteria ML0908901552009-03-30030 March 2009 Acceptance Review Email, License Amendment Request, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0829102482008-10-15015 October 2008 Acceptance Review Email, Relief Request 13 R-06, Alternatives to Requirements of ASME Code, Section XI for Class 1 Piping Welds Examined from Inside Reactor Vessel ML0826102092008-09-17017 September 2008 Acceptance Review Email, License Amendment Request to Revise Technical Specifications 3.3.2 and 3.7.2, and Addition of TS 3.7.19 ML0826101852008-09-17017 September 2008 Acceptance Review Email, License Amendment Request to Revise Technical Specification 3.5.2, ECCS - Operating, in Accordance with TSTF-325A ML0825403192008-09-10010 September 2008 Acceptance Review Email Re Application to Revise Technical Specification 3.3.2 - Wolf Creek ML0713805112007-05-29029 May 2007 Acceptance Review of Licensee'S Application for Main Steam and Feedwater Isolation System Controls Modification 2021-10-22
[Table view] Category:E-Mail
MONTHYEARML24263A0832024-09-19019 September 2024 NRR E-mail Capture - Acceptance Review Wolf Creek Revision to Technical Specification to Adopt TSTF-569-A, Revision 2, Revision of Response Time Testing Definitions ML24250A0252024-09-0606 September 2024 NRR E-mail Capture - Acceptance Review Wolf Creek Revision to Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)) (Fq Methodology) ML23360A1562023-12-26026 December 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise the Ventilation Filter Testing Program in Technical Specifications ML23166A0622023-06-15015 June 2023 NRR E-mail Capture - Acceptance Review - Wolf Creek Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded post-tensioning System Components ML23090A1042023-03-31031 March 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ML23090A0072023-03-31031 March 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request for Relief for Follow-Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface ML23080A0652023-03-21021 March 2023 NRR E-mail Capture - Wolf Creek Generating Station Evacuation Time Estimate Analysis Review ML23026A0222023-01-25025 January 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise Technical Specifications to Adopt Technical Specification Task Force (TSTF)-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements ML23009A4082023-01-0909 January 2023 NRR E-mail Capture - Acceptance Review Wolf Creek Request to Revise TS to Adopt Technical Specification Task Force (TSTF)-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22361A0052022-12-27027 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 ML22251A1312022-09-0808 September 2022 NRR E-mail Capture - Acceptance Review - Wolf Creek Request for Deviation from Fire Protection Program Requirements to Allow Use of Portable Lighting ML22215A2742022-08-0202 August 2022 Inservice Inspection Request for Information ML22208A1322022-07-27027 July 2022 NRR E-mail Capture - Wolf Creek Table of Contents LAR ML22166A3222022-06-14014 June 2022 August 2022 Emergency Preparedness Exercise Inspection - Request for Information ML22131A0522022-05-11011 May 2022 NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek Inservice Inspection Relief Request for Reactor Pressure Vessel Head Penetration Nozzles with Peened Surface 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 ML22026A4392022-01-26026 January 2022 NRR E-mail Capture - Wolf Creek Acceptance Review Results - Removal of TS Table of Contents (L-2022-LLA-0008) 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 ML21309A0332021-11-0505 November 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Revision of Technical Specification 3.8.1, AC Sources - Operating ML21307A4202021-11-0303 November 2021 NRR E-mail Capture - Acceptance Review - 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 ML21259A0652021-09-16016 September 2021 NRR E-mail Capture - Draft Supplemental Information Needed for Acceptance - Wolf Creek License Amendment and Exemption Requests Regarding 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 ML21189A0252021-07-0101 July 2021 NRR E-mail Capture - Acceptance Review - Wolf Creek Request Revision to the Emergency Plan Related to on-shift Staffing ML21230A3922021-05-19019 May 2021 May 19, 2021 Dricks Response to Gurdziel Letter Dated May 13, 2021 - August 17, 2021 ML21102A3342021-04-12012 April 2021 Email 4-12-21 RFI for In-Office Rvw of Recent RERP and a Related EPIP Change ML21064A0342021-03-0404 March 2021 NRR E-mail Capture - Wolf Creek Generating Station Upcoming Steam Generator Tube Inservice Inspection ML20353A2712020-12-18018 December 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Allow Use of a Blind Flange ML20349A3092020-12-14014 December 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request for Change to Owner Licensee Names ML20297A3022020-10-22022 October 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI 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 ML20191A0222020-07-0606 July 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Request in Support of Replacement Engineered Safety Features Transformers with Load Tap Changers ML20162A1642020-06-0909 June 2020 Email June 9, 2020 - RFI in Preparation for Wolf Creek EP Program Inspection ML20149K4272020-05-22022 May 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek License Amendment Request Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ML20133J8972020-05-12012 May 2020 12 May 2020 E-mail - RFI for NRC In-Office Inspection of Recent Wcngs Eplan_Eal Changes ML20132A3442020-05-11011 May 2020 NRR E-mail Capture - Acceptance Review - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML20009E4802020-01-0909 January 2020 Relief Request to Utilize Code Case N-666-1 for Wolf Creek Generating Station - Request for Additional Information ML19273A0232019-09-30030 September 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, ML19268B7172019-09-25025 September 2019 NRR E-mail Capture - Acceptance Review - Inservice Inspection (ISI) Program Relief Request to Use Code Case N-666-1 ML19261A2272019-09-18018 September 2019 NRR E-mail Capture - Regulatory Audit Plan - Wolf Creek Generating Station License Amendment Request to Revise Technical Specification 3.3.5 ML19255H3032019-09-12012 September 2019 NRR E-mail Capture - Acceptance Review - Relief Request I4R-07 to Utilize Code Case N-513-4 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 ML19274D2752019-07-31031 July 2019 Request for Information-IR 05000482 2019-004, Dated 7/31/2019 ML19203A2362019-07-19019 July 2019 LTR-19-0291 Tom Gurdziel, E-mail July 18, 2019, Confirmatory Order on Wolf Creek ML19112A1772019-04-22022 April 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ML19091A0362019-03-29029 March 2019 NRR E-mail Capture - Acceptance Review - License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange 2024-09-06
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From: Singal, Balwant Sent: Wednesday, March 03, 2010 10:28 PM To: 'Hooper Diane M' Cc: 'Wideman Steven G'
Subject:
Acceptance of Application to Revise Technical Specification 3.6.3, "Containment Isolation Valves," - TAC ME3279 Diane: By letter dated January 28, 2010, Wolf Creek Nuclear Operating Corporation submitted a license amendment request for Wolf Creek Generating Station (WCGS). The amendment request proposes changes to the WCGS Technical Specifications (TSs) Limiting Condition for Operation (LCO) of TS 3.6.3, "Containment Isolation Valves." It also proposes to add a Note to LCO 3.6.3 to allow the reactor coolant pump seal injection valves to be considered OPERABLE with the valves open and power removed.
The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.
If you have any questions, please contact me.
Balwant K. Singal Senior Project Manager (Comanche Peak and Wolf Creek)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222 The image cannot be displayed. Your computer may not have enough memory to open the image, or the image may have been corrupted. Restart your computer, and then open the file again. If the red x still appears, you may have to delete the image and then insert it again.
E-mail Properties Mail Envelope Properties (192BB59294514E41B5305C3C8286760806BAF2A553)
Subject:
Acceptance of Application to Revise Technical Specification 3.6.3, "Containment Isolation Valves," - TAC ME3279 Sent Date: 3/3/2010 10:27:47 PM Received Date: 3/3/2010 10:27:00 PM From: Singal, Balwant
Created By: Balwant.Singal@nrc.gov
Recipients:
dihoope@WCNOC.com ('Hooper Diane M')
Tracking Status: None stwidem@WCNOC.com ('Wideman Steven G')
Tracking Status: None
Post Office:
HQCLSTR02.nrc.gov
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MESSAGE 12002 3/3/2010 image001.jpg 1693
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