ML14363A491

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DC Cook Nuclear Plant, Units 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action to Adopt TSTF-490, Rev.0, Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Sp
ML14363A491
Person / Time
Site: Cook  
Issue date: 01/16/2015
From: Mahesh Chawla
Plant Licensing Branch III
To: Weber L
Indiana Michigan Power Co
Chawla M
References
TAC MF5184, TAC MF5185
Download: ML14363A491 (4)


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 January 16, 2015

SUBJECT:

DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2-SUPPLEMENTAL INFORMATION NEEDED FOR 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, Indiana Michigan Power Company (I&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, I&M proposes to revise the CNP Units 1 and 2 licensing basis and TS to adopt the alternative source term as allowed in Title 10 of the Code of Federal Regulations (1 0 CFR) 50.67.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (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 NRC 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 TSs) 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 address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to 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.

In order to make the application complete, the NRC staff requests that I&M supplement the application to address the information requested in the enclosure by February 13, 2015. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.

The information requested and associated time frame in this letter, were discussed with your licensing staff on January 8, 2015. If you have any questions, please contact the D.C. Cook Project Manager, Mahesh Chawla, at (301) 415-8371.

Docket Nos. 50-315 and 50-316

Enclosure:

Supplemental Information Request cc w/encl: Distribution via Listserv Sincerely, CluJ} Lim~_

Mahesh Chawla, Project Manager Plant Licensing Branch 3-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

SUPPLEMENTAL INFORMATION NEEDED AMENDMENT REQUEST INDIANA MICHIGAN POWER COMPANY DONALD C.COOK NUCLEAR PLANT UNITS NOS.1 AND 2 DOCKET NOS. 50-314 AND 50-315 By letter dated November 14, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession Number ML14324A209), Indiana Michigan Power Company (I&M, the licensee) submitted a license amendment request (LAR) for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2 to adopt Technical Specifications Task Force (TSTF)-490, Revision 0, and implement full-scope alternative source term (AST).

In the LAR, the thermal-hydraulic inputs to the accident dose calculations have changed from the values in the current licensing basis (CLB). However, there is no description of the thermal hydraulic (TH) analysis and no references are provided for the CLB. On December 12, 2014, a teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of the licensee to get further clarification on the CLB and the various values utilized in calculation of the AST. However, during the discussion, the licensee only provided a general methodology of adoption of the various terms from the CLB. The licensee stated that they are still relying on their existing CLB and TH analyses; however they are extracting different values to input into the dose calculations.

To begin a review of this amendment, the NRC staff requires a description of the TH analysis.

The licensee will need to describe how they used their CLB analysis to generate new inputs to the accident dose calculations. After receiving this information, the staff will proceed to complete the acceptance review of the LAR. The NRC staff is also requesting an opportunity to do the site audit of the analyses to verify the information provided by the licensee.

Enclosure

ML14363A491 OFFICE DORL/LPL3-1/PM DORLILPL3-1/PM DORL/LPL3-1/LA NAME ADietrich MChawla MHenderson DATE 01/09/2015 01/13/2015 01/12/2015 OFFICE DRA/ARCB/BC NRR/DORLILPL3-1 /BC NRR/DORL/LPL3-1 /PM NAME UShoop DPelton MChawla DATE 01/15/2015 01/16/2015 01/16/2015