Letter Sequence Other |
|---|
|
|
MONTHYEARML0704601592007-02-15015 February 2007
Draft RAI Re. RTS and ESFAS Instrumentation Amendment
Project stage: Draft RAI
ML0716505082007-06-18018 June 2007
Request for Additional Information Proposed Amendment on Bypass Test Capability of Certain Instrumentation
Project stage: RAI
ML0722002602007-07-25025 July 2007
Response to Request for Additional Information Regarding Technical Specification Change to Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System Instrumentation
Project stage: Response to RAI
ML0729006352007-10-0909 October 2007
Partial Withdrawal Regarding Technical Specification Change to Reactor Trip System (RTS) Instrumentation and Engineered Safety Feature Actuation System (ESFAS) Instrumentation
Project stage: Other
ML0735204032007-12-17017 December 2007
Technical Specifications, Issuance of Amendment RTS and ESFAS Bypass Testing Capability
Project stage: Approval
ML0732312272007-12-17017 December 2007
License Amendment, Issuance of Amendment RTS and ESFAS Bypass Testing Capability
Project stage: Approval
2007-02-15
[Table View] |
Similar Documents at Cook |
|---|
Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024
Integrated Inspection Report 05000315/2023004 and 05000316/2023004
ML24004A1582024-01-19019 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024
Emergency Plan Revision 48
AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023
Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor
ML23352A3502023-12-19019 December 2023
Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML23338A2642023-12-0505 December 2023
Confirmation of Initial License Examination
AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023
Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation
IR 05000315/20234042023-11-0606 November 2023
Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404
ML23310A1152023-11-0606 November 2023
Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002
IR 05000315/20234032023-09-19019 September 2023
Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403
IR 05000315/20230112023-08-31031 August 2023
Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011
ML23242A1832023-08-30030 August 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004
AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023
Annual Report of Loss-of-Coolant Accident Evaluation Model Changes
IR 05000315/20234022023-08-11011 August 2023
Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402
AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023
Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation
IR 05000315/20230022023-07-24024 July 2023
Integrated Inspection Report 05000315/2023002 and 05000316/2023002
ML23178A2422023-06-28028 June 2023
Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III
IR 05000315/20230122023-06-22022 June 2023
Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012
IR 05000315/20235012023-06-21021 June 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501
AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023
Core Operating Limits Report
ML23159A0192023-06-13013 June 2023
Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2
AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023
Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations
AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023
Renewable Operating Permit
AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023
Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump
AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023
Annual Radiological Environmental Operating Report
ML23131A3282023-05-11011 May 2023
D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404
IR 05000315/20230012023-05-0303 May 2023
Integrated Inspection Report 05000315/2023001 and 05000316/2023001
AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023
Annual Radioactive Effluent Release Report
ML23117A0062023-04-27027 April 2023
Review of the Spring 2022 Steam Generator Tube Inspections Report
ML23114A1142023-04-25025 April 2023
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023
Annual Report of Individual Monitoring for 2022
AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023
Notification of Ph Non-Compliance for Turbine Room Sump
AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023
Annual Report of Property Insurance
AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023
Decommissioning Funding Status Report
ML23076A0212023-03-20020 March 2023
Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011
IR 05000315/20234012023-03-16016 March 2023
Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401
ML23066A1882023-03-0707 March 2023
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant
IR 05000315/20220062023-03-0101 March 2023
Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006)
IR 05000315/20220042023-02-0101 February 2023
Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion
AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023
Form OAR-1, Owner'S Activity Report
IR 05000315/20230102023-01-31031 January 2023
Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010
AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023
Request for Approval of Change Regarding Neutron Flux Instrumentation
ML22363A5622023-01-0404 January 2023
Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles
AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022
Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring
AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022
Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in
ML22340A1392022-11-30030 November 2022
Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports
IR 05000315/20220112022-11-0404 November 2022
Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011
IR 05000315/20220032022-10-28028 October 2022
Integrated Inspection Report 05000315/2022003 and 05000316/2022003
AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022
U1C31 Steam Generator Tube Inspection Report
AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022
Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06
2024-01-08
[Table view] |
Text
Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place Bridgman, Ml 49106 POWIERO AERcom A unit of American Electric Power October 9, 2007 AEP:NRC:7331-05 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001
SUBJECT:
Donald C. Cook Nuclear Plant Unit I and Unit 2 Docket Nos.: 50-315 and 50-316 Partial Withdrawal Regarding Technical Specification Change to Reactor Trip System (RTS) Instrumentation and Engineered Safety Feature Actuation System (ESFAS) Instrumentation (TAC Nos. MD3159 and MD3160)
References:
- 1. Letter from Mark A. Peifer, Indiana Michigan Power Company (I&M), to U. S.
Nuclear Regulatory Commission (NRC) Document Control Desk, "Technical Specification Change to Reactor Trip System (RTS) Instrumentation and Engineered Safety Feature Actuation System (ESFAS) Instrumentation,"
AEP:NRC:6331-04, dated September 15, 2006 (ML062710309).
- 2. Letter from Peter S. Tam, NRC, to Mano K. Nazar, I&M, "D. C. Cook Nuclear Plant (DCCNP), Units 1 & 2 - Request for. Additional Information Regarding Proposed Amendment Involving Bypass Testing Capability of Certain Instrumentation (TAC MD3159 and MD3160)," dated June 18, 2007 (ML071650508).
- 3. Letter from Joseph N. Jensen, I&M, to U. S. NRC Document Control Desk, "Response to Request for Additional Information Regarding Technical Specification Change to Reactor Trip System (RTS) Instrumentation and Engineered Safety Feature Actuation System (ESFAS) Instrumentation,"
AEP:NRC:7331-01, dated July 25, 2007 (ML072200260).
Dear Sir or Madam:
By Reference 1, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, proposed to amend Facility Operating Licenses DPR-58 and DPR-74.
I&M proposed to modify Technical Specifications (TS) to adopt NUREG-1431, Revision 3, "Standard Technical Specifications, Westinghouse Plants," (STS) wording in TS 3.3.1, Reactor Trip System (RTS) Instrumentation, and TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS)
Instrumentation, for plants with installed bypass test capability.
Ao-.o
U. S. Nuclear Regulatory Commission AEP;NRC:7331-05 Page 2 I&M has installed the first stage of a modification for bypass test capability in Unit 1 and Unit 2 for some TS Functions other than those for the Nuclear Instrumentation System (NIS). Bypass test capability for NIS Functions was planned for the second stage of the modification. I&M no longer plans to install the second stage in either unit and is withdrawing this portion of the license amendment request, as discussed below.
I&M has elected to withdraw the proposed changes to Unit 1 and Unit 2 TS 3.3.1, "Reactor Trip System Instrumentation," Condition C, Required Action C.1 Note. A list of TS Functions that had, or were planned to have, installed bypass test capability was provided in Reference 1, Enclosure 2, Section 2.0. This list remains valid with the exception of TS 3.3.1, Function 2, Power Range Neutron Flux, and Function 3, Power Range Neutron Flux - High Positive Rate, which are the TS Functions for which I&M no longer plans to install bypass test capability. Therefore, the proposed changes that are withdrawn are those documented in Reference 1, Attachments IA through 2B, TS 3.3.1, Condition C, Required Action C.1 Note, on Page 3.3.1-1 of both the Unit I and Unit 2 TS.
The enclosure provides an affirmation affidavit pertaining to this letter.
Copies of this letter and its enclosure are being transmitted to the Michigan Public Service Commission and Michigan Department of Environmental Quality in accordance with the requirements of 10 CFR 50.91.
This letter contains no new or revised regulatory commitments. Should you have any questions, please contact Ms. Susan D. Simpson, Regulatory Affairs Manager, at (269) 466-2428.
Sincerely, Joseph N. Jensen Site Vice President KAS/jen Enclosure c: J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne J. T. King- MPSC MDEQ - WHMD/RPMWS NRC Resident Inspector P. S. Tam - NRC Washington, DC
Enclosure to AEP:NRC:7331-05 AFFIRMATION I, Joseph N. Jensen, being duly sworn, state that I am Site Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.
Indiana Michigan Power Company Joseph N., Jensen Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS ___ DAY OF 2007 My Commission Expires Commissionpry Public My 1O ,
