ML17027A019

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NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI Regarding LAR to Revise TS 5.5.14 (MF8483 and MF8484)
ML17027A019
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 01/26/2017
From: Dietrich A
Plant Licensing Branch III
To: Kish H
Indiana Michigan Power Co
References
MF8483, MF8484
Download: ML17027A019 (3)


Text

NRR-PMDAPEm Resource From: Dietrich, Allison Sent: Thursday, January 26, 2017 3:26 PM To: hlkish@aep.com Cc: 'dmburgoyne@aep.com'

Subject:

D.C. COOK UNITS 1 AND 2 - RAI regarding LAR to revise TS 5.5.14 (MF8483 and MF8484)

Attachments: D.C. Cook Units 1 and 2 - leak rate RAI.pdf By letter dated October 18, 2016 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML16294A257), Indiana Michigan Power Company (I&M) submitted a license amendment request for the Donald C. Cook Nuclear Plant, Units 1 and 2. The proposed change would clarify the existing containment leak rate testing pressure criteria of Technical Specification 5.5.14b.

The U.S. Nuclear Regulatory Commission staff has reviewed your submittal. The staff has determined that additional information is needed in order to complete the review, as described in the attached request for additional information (RAI). The draft RAI was sent to I&M via electronic mail on January 13, 2017. A clarification telephone conference was held on January 26, 2017. Please provide your response by February 27, 2017.

Please let me know if you have any questions or concerns.

Sincerely, Allison W. Dietrich, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-2846 1

Hearing Identifier: NRR_PMDA Email Number: 3293 Mail Envelope Properties (Allison.Dietrich@nrc.gov20170126152600)

Subject:

D.C. COOK UNITS 1 AND 2 - RAI regarding LAR to revise TS 5.5.14 (MF8483 and MF8484)

Sent Date: 1/26/2017 3:26:28 PM Received Date: 1/26/2017 3:26:00 PM From: Dietrich, Allison Created By: Allison.Dietrich@nrc.gov Recipients:

"'dmburgoyne@aep.com'" <dmburgoyne@aep.com>

Tracking Status: None "hlkish@aep.com" <hlkish@aep.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1058 1/26/2017 3:26:00 PM D.C. Cook Units 1 and 2 - leak rate RAI.pdf 548202 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE TS 5.5.14 CONTAINMENT LEAKAGE RATE TESTING PROGRAM DONALD C. COOK NUCLEAR PLANT UNIT NOS. 1 AND 2 DOCKET NOS. 50-315 AND 50-316 CAC NOS. MF8483 AND MF8484 By application dated October 18, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16294A257), Indiana Michigan Power Company (I&M) requested changes to the Technical Specifications (TSs) for the Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 (CNP). The proposed change would clarify the existing containment leak rate testing pressure criteria of TS 5.5.14b.

SBPB-RAI-1 ANSI 56.8-2002 establishes Pa as the calculated peak accident pressure, and limits the Containment Leakage Rate Testing Program pressure to less than or equal to 1.1 Pa. As stated in the license amendment request (LAR), the calculated Pa for CNP is 10.37 pounds per square inch gauge (psig) for Unit 1, and 10.78 psig for Unit 2. I&M has requested to use 12 psig as Pa for the Containment Leakage Rate Testing Program, which is greater than 1.1 times the CNP calculated peak accident pressure for both units. The LAR states that this will not result in a significantly larger differential pressure to seal components whose characteristics result in improved sealing based on increased pressure. However, a test pressure greater than 1.1 Pa may affect test results in a non-conservative manner.

x Demonstrate how testing at a pressure of 12 psig, which is greater than 1.1 Pa, is acceptable as an exception to the standard.