Letter Sequence Acceptance Review |
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TAC:ME1393, Steam Generator Tube Integrity (Approved, Closed) |
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MONTHYEARML0915901672009-04-30030 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) Project stage: Request ML0915305402009-04-30030 April 2009 Attachment 5, WCAP-17071-NP, H: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model F), Non-Proprietary Project stage: Request CP-200900748, WCAP-17072-NP, Rev. 0, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model D5)2009-05-31031 May 2009 WCAP-17072-NP, Rev. 0, H*: Alternate Repair Criteria for the Tubesheet Expansion Region in Steam Generators with Hydraulically Expanded Tubes (Model D5) Project stage: Other ET 09-0016, Revision to Technical Specifications 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criterion2009-06-0202 June 2009 Revision to Technical Specifications 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for a Permanent Alternate Repair Criterion Project stage: Request 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 Project stage: Acceptance Review ML0916701542009-06-0808 June 2009 Comanche Peak - License Amendment Request 09-007, Model D5 Steam Generator Alternate Repair Criteria Project stage: Other ML0921002002009-08-11011 August 2009 Request for Additional Information License Amendment Request, Revise Technical Specifications 5.5.9 and 5.6.10 for Permanent Alternate Repair Criteria Project stage: RAI ML0921006342009-08-18018 August 2009 Request for Clarification Request for Withholding Information from Public Disclosure (5/4/2009 Affidavit Executed by J. Gresham, Westinghouse) Project stage: Withholding Request Acceptance ML0924500952009-08-25025 August 2009 Response to Request for Additional Information Related to License Amendment Request for a Permanent Alternate Repair Criterion to Technical Specification 5.5.9, Steam Generator (SG) Program Project stage: Response to RAI ET 09-0024, Response to Request for Clarifications in Response to Application for Withholding Proprietary Information from Public Disclosure2009-09-0303 September 2009 Response to Request for Clarifications in Response to Application for Withholding Proprietary Information from Public Disclosure Project stage: Request ET 09-0023, Response to Request for Additional Information Related to License Amendment Request for a Permanent Alternate Repair Criterion to Technical Specification 5.5.9, Steam Generator Program2009-09-0303 September 2009 Response to Request for Additional Information Related to License Amendment Request for a Permanent Alternate Repair Criterion to Technical Specification 5.5.9, Steam Generator Program Project stage: Response to RAI ET 09-0025, Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report2009-09-15015 September 2009 Revision to Technical Specification (TS) 5.5.9, Steam Generator (SG) Program, and TS 5.6.10, Steam Generator Tube Inspection Report Project stage: Request ML0925102942009-09-25025 September 2009 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0926703602009-10-16016 October 2009 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0927506062009-10-19019 October 2009 Issuance of Amendment No. 186, Modify Technical Specification 5.5.9, Steam Generator Program, and TS 5.6.10, Steam Generator Tube Inspection Report, for Alternate Repair Criteria Project stage: Approval ML0933604592009-12-0909 December 2009 Transmittal of Unresolved Issues Regarding Permanent Alternate Repair Criteria for Steam Generators Project stage: Other 2009-06-08
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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
MONTHYEARML24296A0632024-10-22022 October 2024 NRR E-mail Capture - Acceptance Review Wolf Creek License Amendment and Exemption Requests for a risk-informed Resolution to GSI-191 ML24263A0832024-09-19019 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 2024-09-06
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From: Singal, Balwant Sent: Monday, June 08, 2009 9:53 AM To: Hooper Diane M Cc: Wideman Steven G
Subject:
Acceptance of Application to Revise Technical Specifications 5.5.9 and 5.6.10-TAC ME1393 Diane:
By letter dated June 2, 2009, Wolf Creek Nuclear Operating Corporation (WCNOC) submitted a license amendment request for Wolf Creek Generating Station (WCGS). The proposed amendment would revise Technical Specifications (TS) 5.5.9 to exclude portions of the tube below the top of the steam generator tubesheet from periodic steam generator tube inspections and to revise TS 5.6.10 to provide reporting requirements specific to the permanent alternate repair criteria. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs 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.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with 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. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-3016.
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 display ed. Your computer may not hav e enough memory to open the image, or the image may hav e been corrupted. Restart y our computer, and then open the file again. If the red x still appears, y ou may hav e to delete the image and then insert it again.
E-mail Properties Mail Envelope Properties ()
Subject:
Acceptance of Application to Revise Technical Specifications 5.5.9 and 5.6.10- TAC ME1393 Sent Date: 6/8/2009 9:33:56 AM Received Date: 6/8/2009 9:53:00 AM 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:
Files Size Date & Time MESSAGE 12088 6/8/2009 image001.jpg 1693 Options Expiration Date:
Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received: