ML15035A133

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TAC No. MF5193 - Acceptance of Requested Licensing Action License Amendment Request-Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change
ML15035A133
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 02/04/2015
From: Bhalchandra Vaidya
Plant Licensing Branch 1
To: David Gudger, Reynolds R
Exelon Generation Co
Vaidya B, NRR/DORL/LPL1-1, 415-3308
References
TAC MF5193
Download: ML15035A133 (1)


Text

From: Vaidya, Bhalchandra Sent: Wednesday, February 04, 2015 9:20 AM To: 'David.Gudger@exeloncorp.com'; Reynolds, Ronnie J.:(GenCo-Nuc)

(Ronnie.Reynolds@exeloncorp.com)

Cc: Beasley, Benjamin; Elliott, Robert; Dennig, Robert; Chernoff, Margaret; Woodyatt, Diana; Thorp, John; Singh, Gursharan; Bucholtz, Kristy; Shoop, Undine

Subject:

Nine Mile Point Nuclear Station Unit No. 2; , TAC No. MF5193 -

ACCEPTANCE OF REQUESTED LICENSING ACTION RE: License Amendment Request-Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change

SUBJECT:

Nine Mile Point Nuclear Station Unit No. 2; Docket No. 50-410 Renewed Facility Operating License No. NPF-69 License Amendment Request - Primary Containment Isolation Instrumentation Technical Specification Allowable Value Change (TAC No. MF5193)

By letter dated November 17, 2014, Exelon Generation Company, LLC (EGC) submitted a license amendment request (LAR) for Nine Mile Point Nuclear Station Unit No. 2. The proposed amendment would revise the NMP2 Technical Specification (TS) Allowable Value for the Main Steam Line Tunnel Lead Enclosure Temperature-High instrumentation from an ambient temperature dependent (variable setpoint) to ambient temperature independent (constant Allowable Value). The changes would delete Surveillance Requirement (SR) 3.3.6.1.2 and revise the Allowable Value for Function 1.g on Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation." In addition, the associated Bases will be revised.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs 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 (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 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 staffs 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 NRC staffs detailed technical review by separate correspondence.

If you have any questions, please contact me at (301) 415-3308.

Bhalchandra K. Vaidya Licensing Project Manager

NRC/NRR/DORL/LPL1-1 (301)-415-3308 (O) bhalchandra.vaidya@nrc.gov