ML14246A451

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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
ML14246A451
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 08/25/2014
From: Beltz T
Plant Licensing Branch III
To: Etheridge H
American Electric Power Co, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
Chawla M
References
TAC MF3568, TAC MF3569
Download: ML14246A451 (3)


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.

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