ML15056A163

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DC Cook, Units 1 & 2 - Acceptance of Requested Licensing Action to Adopt TSTF-490, REV.0, Deletion of E-Bar Definition & Revision to Reactor Coolant System Specific Activity Technical Specification & Implement Full-Scope Alternative Source
ML15056A163
Person / Time
Site: Cook  
Issue date: 03/03/2015
From: Mahesh Chawla
Plant Licensing Branch III
To: Weber L
Indiana Michigan Power Co
Chawla M
References
TAC MF5184, TAC MF5185
Download: ML15056A163 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Lawrence J. Weber Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, Ml 49106 March 3, 2015

SUBJECT:

DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 -ACCEPTANCE OF REQUESTED LICENSING ACTION TO ADOPT TSTF-490, REV.O, "DELETION OF E-BAR DEFINITION AND REVISION TO REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY TECHNICAL SPECIFICATION" AND IMPLEMENT FULL-SCOPE ALTERNATE SOURCE TERM (TAC NOS. MF5184 AND MF5185)

Dear Mr. Weber:

By letter dated November 14, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML14324A209), Indian Michigan Power Company (l&M) (the licensee), submitted a license amendment request for Donald C.Cook Nuclear Plant (CNP),

Units 1 and 2. The proposed license amendment request (LAR) would replace the current CNP Units 1 and 2 technical specification (TS) 3.4.16 limit on reactor coolant system (RCS) gross specific activity with a new limit on RCS noble gas specific activity. The noble gas specific activity limit would be based on a new dose equivalent Xe-133 definition that would replace the current E Bar average disintegration energy definition. In addition, the current dose equivalent 1-131 definition would be revised to allow the use of additional thyroid dose conversion factors.

Additionally, l&M proposes to revise the CNP Units 1 and 2 licensing basis and TSs to adopt the alternative source term (AST) as allowed in Title 10 of the Code of Federal Regulations ( 10 CFR) 50.67.

The U.S. Nuclear Regulatory Commission (NRC) staff requested supplemental information needed by letter dated January 16, 2015 (ADAMS Accession No. ML14363A491), to complete the acceptance review of the subject license amendment request. The licensee provided the requested supplemental information by letter dated February 12, 2015 (ADAMS Accession No. ML14363A491).

The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the staff to complete its _detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of 10 CFR, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of

technical information required. This section stipulates that the submittal addresses the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRG staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRG staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRG staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRG staff's detailed technical review by separate correspondence.

If you have any questions, please contact the D.C.Cook Project Manager, Mahesh Chawla, at (301) 415-8371.

Docket Nos. 50-315, 50-316 cc: Distribution via Listserv Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 3-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

ML15056A163 OFFICE DORL/LPL3-1 /PM DORL/LPL3-1/LA DSS/SRXB/BC NAME MChawla MHenderson CJackson DATE 02/26/15 02/26/15 03/02/15 OFFICE DRNARCB/BC DORL/LPL3-1 /BC DORL/LPL3-1 /PM NAME US hoop DPelton MChawla DATE 03/02/15 03/03/15 03/03/15