Letter Sequence Request |
---|
|
|
MONTHYEARML0720603752007-07-17017 July 2007 Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Containment Inservice Inspection Program Project stage: Request ML0728904582007-10-16016 October 2007 Draft RAI Re. Extension of Cisi Interval Project stage: Draft RAI ML0733206112007-11-16016 November 2007 Containment Inservice Inspection Interval Extension Request for Additional Information Project stage: Request ML0804206812008-03-28028 March 2008 Approval of Alternative to Extend the Containment Inservice Inspection Interval by About 18 Months Project stage: Other 2007-11-16
[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, MI 49106 AEP.com A unit of American Electric Power November 16, 2007 AEP:NRC:7055-06 10 CFR 50.55a Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-PI-17 Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 Containment Inservice Inspection Interval Extension Request for Additional Information
References:
- 1. Letter from J. N. Jensen, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Proposed Alternative to the American Society of Mechanical Engineers Code,Section XI, Containment Inservice Inspection Program," AEP:NRC:7055-02, dated July 17, 2007 (ML072060375).
- 2. Electronic mail from P. S. Tam, NRC, to M. K. Scarpello, I&M, "D. C. Cook -
Draft RAI re. Extension of CISI Interval (TAC MD6083, MD6084)," dated October 16, 2007 (ML072890458).
In Reference 1, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, requested Nuclear Regulatory Commission (NRC) approval of a proposed alternative to the American Society of Mechanical Engineers Code,Section XI, Containment Inservice Inspection (CISI) Program. Specifically, I&M requested an extension of CNP's current interval by approximately eighteen months to enable the CISI program to be coincident with CNP's Inservice Inspection Program.
In Reference 2, the NRC requested additional information regarding I&M's request. The attachment to this letter provides I&M's response to the request for additional information.
A47m
U. S. Nuclear Regulatory Commission AEP:NRC:7055-06 Page 2 This letter contains no new 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 RGV/rdw Attachment c: R. Aben - Department of Labor and Economic Growth J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne, w/o attachment J. T. King - MPSC, w/o attachment MDEQ - WHMD/RPMWS, w/o attachment NRC Resident Inspector P.S. Tam - NRC Washington DC
Attachment to AEP:NRC:7055-06 Containment Inservice Inspection Interval Extension Request for Additional Information In Reference 1, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, requested Nuclear Regulatory Commission (NRC) approval of a proposed alternative to the American Society of Mechanical Engineers Code (ASME),
Section. XI, Containment Inservice Inspection (CISI) Program. Specifically, I&M requested an extension of CNP's current interval by approximately eighteen months to enable the CISI program to be coincident with CNP's Inservice Inspection Program.
In Reference 2, the NRC requested additional information regarding I&M's request. The following provides I&M's response to the request for additional information.
NRC Request 1 In Section 5.0 of the attachment to the 7/17/07 letter, I&M proposed that the first intervalfor the Containment In-service Inspection (CISI) be extended approximately 18 months from September 9, 2008 to March 1, 2010. The extension will permit I&M to achieve a common interval start date and a common In-service Inspection (ISI) code with the 1SI program. I&M also states that the code of recordfor the updated (2010) 1SI and CISI programs will be the latest edition incorporated by reference in 10 CFR 50.55a(b)(2) twelve months prior to March 1, 2010. These statements imply that March 1, 2010 applies to both Units 1 and 2.
Pleaseprovide a table showing the current and proposed Units 1 and 2 ISI and CISI inspection interval dates and to clarify the statement relative to the code of record in the first paragraphof Section 5.0, "ProposedAlternative and Basisfor Use."
I&M Response to Request 1 Table 1 provides the requested information.
NRC Request 2 The second paragraph of Section 5.0 of the attachment states that there are no augmented examination areasfor either Unit 1 or Unit 2. This statement indicates that all surface areas (e.g., leak chase channels, sump liner) listed in IWE-1240 as likely areas requiringaugmented examination and other areas such as space between ice baskets and the liner have been found acceptable and were not inspected in accordancewith the augmented examination requirements of Table IWE 2500-1. Pleaseprovide further information relative to this statement, IWE-1240 and the Examination Category E C of Table IWE-2500-1 as applicable to the CNP Units 1 and 2.
Attachment to AEP:NRC:7055-06 Page 2 I&M Response to Request 2 There is no evidence of containment liner accessible areas experiencing accelerated degradation in either unit. Most of the liner plate behind the ice condensers is inaccessible. The ice baskets and interior of the ice condenser are separated from the containment liner by a paneled wall with a gap between the wall and the liner. There are inspection ports in the ice condenser that are used to monitor conditions of the containment liner behind the ice condenser. The liner in the area of the inspection ports shows no evidence of corrosion or accelerated degradation.
NRC Request 3 Please confirm and provide pertinent information that the examination and tests (requiredby the CISI program) performed during recent inspections have. satisfied the acceptance standards contained within Articles IWE-3000 and IWL-3000.
I&M Response to Request 3 The recent examination results of the containment liner have satisfied the code acceptance criteria. The overall condition of the containment liners of both containments is very good following the implementation of a coatings inspection and maintenance program that supplements the ASME Code,Section XI examinations. The concrete examinations on both unit containments have been completed with the use of a crane and man-basket that provided a means to thoroughly examine the exterior concrete. There. were no conditions that would adversely impact the structural integrity of either containment structure.
References:
- 1. Letter from J. N. Jensen, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2, Proposed Alternative to the American Society of Mechanical Engineers Code,Section XI, Containment Inservice Inspection Program," ?AEP:NRC:7055-02, dated July 17, 2007 (ML072060375).
- 2. Electronic mail from P. S. Tam, NRC, to M. K. Scarpello, I&M, "D. C. Cook -
Draft RAI re. Extension of CISI Interval (TAC MD6083, MD6084)," dated October 16, 2007 (ML072890458).
Attachment to AEP:NRC:7055-06 Page 3 Table 1 Current and Proposed ISI and CISI Intervals Next Inspection Interval Start Proposed Inspection Interval Extended Period Examinations Program Date Start Date (Current Requirement) Start Date ISI Program examinations are not impacted by the ISI 3/1/2010 (Units I and 2) 3/1/2010 (Units I and 2) 1interval extension CISI 9/9/2008 (Units 1 and 2) 3/1/2010 (Units 1 and 2) ASME Section XI, 1992 Edition/Addenda IWE examinations that are performed during a typical inspection period Category E-A, Item Number El. 11: General visual examination of accessible surfaces Category E-D, Item Number E5.30: VT-3 visual examination of moisture barriers Category E-G, Item Number E8.10, Note 2:
VT-1 visual examinations of bolting during maintenance disassemblies Note: IWL examinations were completed in 2007 and will remain on a five year schedule