Letter Sequence Draft RAI |
---|
|
|
MONTHYEARAEP-NRC-2014-09, License Amendment Request to Revise Technical Specification Section 5.5.14, Containment Leakage Rate Testing Program2014-03-0707 March 2014 License Amendment Request to Revise Technical Specification Section 5.5.14, Containment Leakage Rate Testing Program Project stage: Request ML14111A0032014-04-17017 April 2014 NRR E-mail Capture - D.C. Cook Units 1 and 2 - Acceptance Review of LAR to Revise TS 5.5.14, Containment Leakage Rate Testing Project stage: Acceptance Review ML14246A4512014-08-25025 August 2014 NRR E-mail Capture - Donald C. Cook Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information (Emcb) Change to TS 5.5.14 by Adopting NEI 94-01, Revision 3-A Project stage: Draft RAI ML14246A4992014-08-26026 August 2014 NRR E-mail Capture - Donald C. Cook Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information (Scvb) Change to TS 5.5.14 by Adopting NEI 94-01, Revision 3-A Project stage: Draft RAI AEP-NRC-2015-07, Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 5.5.14, Containment Leakage Rate Testing Program, to Use NEI-94-01, Revision 3-A..2015-01-15015 January 2015 Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 5.5.14, Containment Leakage Rate Testing Program, to Use NEI-94-01, Revision 3-A.. Project stage: Response to RAI ML15037A0122015-02-0303 February 2015 NRR E-mail Capture - Request for Additional Information (RAI) - Donald C.Cook Nuclear Plant Units and 2 - LAR to Revise TS 5.5.14 - Containment Integrated Leak Rate Testing - MF3568/69 Project stage: RAI AEP-NRC-2015-25, Response to RAI Regarding License Amendment Request to Revise Technical Specification 5.5.14, Containment Leakage Rate Testing Program, to Use NEI-94-01, Revision 3-A as Regulatory Guidance Versus Current NEI-94-01, Rev. 02015-02-20020 February 2015 Response to RAI Regarding License Amendment Request to Revise Technical Specification 5.5.14, Containment Leakage Rate Testing Program, to Use NEI-94-01, Revision 3-A as Regulatory Guidance Versus Current NEI-94-01, Rev. 0 Project stage: Response to RAI ML15072A2642015-03-30030 March 2015 Issuance of Amendments Containment Leakage Rate Testing Program (TACs MF3568 and MF3569) Project stage: Approval 2014-08-26
[Table View] |
Similar Documents at Cook |
---|
Category:E-Mail
MONTHYEARML23361A1022023-12-21021 December 2023 Security Rule Exemption Request - ISFSI Docket No. Reference ML23321A1222023-11-17017 November 2023 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - License Amendment Request Regarding Neutron Flux Instrumentation ML23052A1502023-02-21021 February 2023 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request Regarding Neutron Flux Instrumentation ML22307A2532022-11-0303 November 2022 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Verbal Authorization of Relief Request ISIR-5-06 Regarding Alternative to N-729-6 for RPV Head Visual Examination ML22122A0902022-04-29029 April 2022 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-554, Revision 1 ML22250A6712022-02-16016 February 2022 Outline Submittal Notification Email DC-Cook 2022 ML21341A6252021-12-0707 December 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-577, Revision 1 ML21307A3352021-11-0303 November 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Final RAI - License Amendment Request Regarding Containment Water Level Instrumentation ML21236A0262021-08-23023 August 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Acceptance of License Amendment Regarding Changes to Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements ML21140A3052021-05-20020 May 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request ISIR-4-11, Impractical Examinations for the Fourth 10-Year ISI Interval ML21113A2812021-04-23023 April 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request Regarding Containment Water Level Instrumentation ML21089A0222021-03-24024 March 2021 DC Cook Power Operated Valves (POV) Preliminary Request for Information ML21082A0262021-03-22022 March 2021 Acceptance of Relief Request ISIR-4-11, Impractical Examinations for the Fourth 10-Year ISI Interval ML21049A2682021-02-16016 February 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Final RAI - License Amendment Request for One-Time Extension Containment Type a ILRT ML21026A3472021-01-26026 January 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year Interval ML21008A4742021-01-0808 January 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Acceptance of License Amendment Request for One-Time Extension Containment Type a ILRT ML20366A1012020-12-31031 December 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Acceptance of License Amendment Request for One-Time Deferral of Steam Generator Inspection ML20316A0152020-11-0606 November 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year Interval ML20318A0202020-10-16016 October 2020 NRR E-mail Capture - Regarding Public Comment on D.C. Cook, Unit 1 Request for Relief from Nozzle Inspections, Code Case N-729 ML20318A0192020-10-15015 October 2020 NRR E-mail Capture - (External_Sender) Supplemental Public Comment on D.C. Cook, Unit 1 Request for Relief from Nozzle Inspections, Code Case N-729 ML20289A7122020-10-15015 October 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 1 - Verbal Authorization of Relief Request ISIR-5-04 Regarding Alternative to N-729-6 for RPV Head Visual Examination ML20290A4252020-10-15015 October 2020 Verbal Authorization of Relief Request ISIR-5-04 Regarding Alternative to N-729-6 for RPV Head Visual Examination ML20318A0182020-10-0909 October 2020 NRR E-mail Capture - (External_Sender) Public Comment on D.C. Cook, Unit 1 Request for Relief from Nozzle Inspections, Code Case N-729 ML20289A1192020-10-0909 October 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of Relief Request for Alternative to N-729-4 for RPV Head Visual Examination ML20181A4122020-06-29029 June 2020 NRR E-mail Capture - Final RAI - D.C. Cook 1 - One-Time Extension, Containment Type a ILRT Frequency ML20149K6272020-05-28028 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment and Exemptions Regarding UFSAR 10 CFR 50.71(e)(4) Update Schedule (Epids: L-2020-LLA-0100, L-2020-LLE-0052, L-2020-LLE-0053) ML20149K4332020-05-26026 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-567, Revision 1 ML20141L8112020-05-20020 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of Relief Request Regarding Impracticality for Inservice Inspection for Certain Welds ML20141L6062020-05-20020 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-541, Revision 2 ML20136A5162020-05-15015 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance of License Amendment Request to Revise Technical Specifications Consistent with TSTF-412, Revision 3 ML20133J9662020-05-11011 May 2020 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 1 - Acceptance of License Amendment Regarding Changes to Reactor Vessel Heatup and Cooldown Curves and Low Temperature Overpressure Protection System Requirements ML20232B4562020-04-27027 April 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Fragility Questions ML20232B4432020-03-25025 March 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Plant Response Model Questions ML19345F9382019-12-0909 December 2019 D.C. Cook 50.54(f) SPRA Submittal - Completeness Review Done and Path Forward ML19333B8042019-11-29029 November 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Adopt TSTF-569 (L-2019-LLA-0248) ML19309F9212019-11-0505 November 2019 Request for Eportal Access for Audit Review of the DC Cook SPRA Supporting Documents ML19270E7372019-09-26026 September 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Adopt TSTF-421, Reactor Coolant Pump Flywheel Inspection Program ML19207A4642019-07-26026 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Delete Diesel Generator Load Test Resistor Banks ML19204A0962019-07-23023 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Request for Additional Information Related to Unit 2 Leak Before Break Analysis and Deletion of Containment Humidity Monitors for Unit Nos. 1 and 2 ML19211C3032019-07-0303 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 & 2 - Request for Additional Information Related to LAR to Address NSAL-15-1 ML19175A3032019-06-24024 June 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Acceptance Review for LAR to Revise Battery Monitoring and Maintenance TS ML19092A4802019-04-0202 April 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Adopt TSTF-563 ML19092A4792019-04-0202 April 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Address Issues Identified in Westinghouse Document NSAL-15-1 ML19084A0002019-03-20020 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19072A1432019-03-12012 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19011A1382019-01-11011 January 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Revise Environmental Technical Specifications (L-2018-LLA-0570) ML19011A3512019-01-11011 January 2019 NRR E-mail Capture - Request for Additional Information DC Cook Unit 1 Leak Before Break Amendment ML19009A5402019-01-0909 January 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Revise Battery Monitoring and Maintenance TS ML18313A0802018-11-0808 November 2018 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI for RPV Threads in Flange Alternative ML18275A0532018-10-0101 October 2018 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Acceptance Review for LAR to Revise Battery Monitoring and Maintenance TS 2023-02-21
[Table view] |
Text
NRR-PMDA-ECapture Resource From: Beltz, Terry Sent: Monday, August 25, 2014 10:26 AM To: Helen L Etheridge Cc: Terry L Curtiss (tlcurtiss@aep.com); Joe Tanko (jmtanko@aep.com);
'mkscarpello@aep.com'; Danielle M Burgoyne (dmburgoyne@aep.com); Pelton, David; Chawla, Mahesh; Farzam, Farhad
Subject:
D. C. Cook Nuclear Plant, Units 1 and 2 - Draft Requests for Additional Information re:
Change to TS 5.5.14 by Adopting NEI 94-01, Revision 3-A (TAC Nos. MF3568 and MF3569)
Dear Ms. Etheridge:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 7, 2014, Indiana Michigan Power Company (the licensee) submitted a license amendment request proposing changes to Technical Specification 5.5.14, Containment Leakage Rate Testing Program, for the Donald C. Cook Nuclear Plant, Units 1 and 2.
Specifically, the proposed to revise TS 5.5.14 by adopting Nuclear Energy Institute (NEI) 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J. If approved, the proposed amendment would allow the next Type A containment integrated leak rate testing (ILRT) to be performed within 15 years from the last ILRT, as opposed to the current 10-year interval, and would allow successive ILRTs to be performed at 15-year intervals. Additionally, the proposed amendment would revise the maximum interval for the performance of Type C local leakage rate tests to a 75-month interval.
The NRC staff in the Mechanical & Civil Engineering Branch (EMCB) of the Office of Nuclear Reactor Regulation is currently reviewing your submittal. The staff has determined that additional information is required to complete its review. Draft requests for additional information (RAIs) are provided below.
You may accept these draft RAIs as formal requests for additional information and respond to the questions by October 1, 2014. Alternatively, you may seek further clarification and discuss the contents of the RAIs with the NRC staff in a conference call, including any change to the proposed response date.
Please let me know if you have any questions or concerns.
Sincerely, TERRY A. BELTZ, SENIOR PROJECT MANAGER U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 Mail Stop: O-8D15 Phone: (301) 415-3049 Terry.Beltz@nrc.gov DRAFT REQUESTS FOR ADDITIONAL INFORMATION MECHANICAL & CIVIL ENGINEERING BRANCH OF THE OFFICE OF NUCLEAR REACTOR REGULATION 1
REGARDING A LICENSE AMENDMENT REQUEST FOR THE DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 TO REVISE TECHNICAL SPECIFICATION SECTION 5.5.14, CONTAINMENT LEAKAGE RATE TESTING PROGRAM INDIANA MICHIGAN POWER COMPANY DOCKET NOS. 50-315 AND 50-316 (TAC NOS. MF3568 AND MF3569)
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing the Indiana Michigan Power Company (the licensee) license amendment request (LAR) application dated March 7, 2014 (Agencywide Documents Access and Management System Accession No. ML14071A435), for the Donald C. Cook Nuclear Plant (CNP), Units 1 and 2. The LAR would revise CNP Technical Specifications Section 5.5.14 Containment Leakage Rate Testing Program. Specifically, the proposed amendment would allow the next containment integrated leak rate testing (ILRT) to be performed within 15 years from the last ILRT, as opposed to the current 10-year interval, and would allow successive ILRTs to be performed at 15-year intervals. Additionally, the proposed amendment would revise the maximum interval for the performance of Type C local leakage rate tests to a 75-month interval.
The NRC staff in the Mechanical & Civil Engineering Branch (EMCB) of the Office of Nuclear Reactor Regulation has determined that the additional information requested below is needed to complete its review.
RAI-EMCB-1 The licensee states in its LAR that in the second 10-year interval, which commenced March 1, 2010, a glycol pipe penetration in CNP Unit 1 had a large amount of wet discoloration due to condensation below the insulated piping. It was also noted in the LAR that this area has been classified as an augmented examination per Category E-C for continued monitoring with a VT-1 visual examination during successive inspection periods.
Please provide and discuss the results of examinations related to this condition that have been completed during the second 10-year containment in-service inspection program.
RAI-EMCB-2 At CNP Units 1 and 2, are bellows used on penetrations through primary containment pressure-retaining boundaries?
If the bellows are pressure-retaining boundaries, then please provide information on their location, inspection, testing, and operating experience with regard to detection of leakage through the penetration bellows.
RAI-EMCB-3 Please discuss the highlights of findings from recent inspections from the CNP Units 1 and 2 containment coating inspection program, and any actions taken to disposition them.
RAI-EMCB-4 2
Please discuss NRC Information Notice 2014-07, Degradation of Leak-Chase Channel Systems for Floor Welds of Metal Containment Shell and Concrete Containment Metallic Liner, as it may apply to CNP Units 1 and 2.
If applicable, discuss the operating experience, inspection results, and any corrective actions taken.
3