ML14318A830

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Acceptance of Requested Licensing Action License Amendment Request to Modify Reactor Coolant System Pressure Isolation Check Valve Technical Specification Maximum Allowable Leakage Limits
ML14318A830
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 11/18/2014
From: John Lamb
Plant Licensing Branch 1
To: Pacilio M
Exelon Generation Co, Exelon Nuclear
John Lamb, NRR/DORL 415-3100
References
TAC MF5108
Download: ML14318A830 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 18, 2014 Michael J. Pacilio Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

THREE MILE ISLAND NUCLEAR STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO MODIFY REACTOR COOLANT SYSTEM PRESSURE ISOLATION CHECK VALVE TECHNICAL SPECIFICATION MAXIMUM ALLOWABLE LEAKAGE LIMITS (TAC NO. MF5108)

Dear Mr. Pacilio:

By letter dated October 30, 2014, (Agencywide Documents Access and Management System Accession No. ML14304A083), Exelon Generation Company, LLC requested an amendment to Renewed Facility Operating License No. DPR-50 for Three Mile Island Nuclear Station (TMI),

Unit 1. The proposed amendment would modify the Technical Specification (TS) Table 3.1.6.1, "PRESSURE ISOLATION CHECK VALVES BETWEEN THE PRIMARY COOLANT SYSTEM

& LPIS [Low Pressure Injection System]," maximum allowable leakage limits.

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 Title 10 of the Code of Federal Regulations (1 0 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 it does provide technical information in sufficient detail to enable the NRC 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 NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate

M. Pacilio acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

If you have any questions, please contact me at (301) 415-3100 or via e-mail at John. Lamb@nrc.gov.

~Y.~

Lamb, Senior Project Manager icensing Branch 1-2 n of Operating Reactor Licensing of Nuclear Reactor Regulation Docket No. 50-289 cc: Distribution via Listserv

ML14318A830 OFFICE LPL 1-2/PM LPL3-1/LA LPL 1-2/BC LPL 1-2/PM NAME Jlamb A Baxter MKhanna Jlamb DATE 11/17/14 11/17/14 11/14/14 11/18/14