ML110950297

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Memorandum Regarding LIC-109 Acceptance Review of Palisades LAR for Primary Coolant System Pressure-Temperature Limits
ML110950297
Person / Time
Site: Palisades Entergy icon.png
Issue date: 04/04/2011
From: Mahesh Chawla
Plant Licensing Branch III
To: Patricia Anderson, Kuemin J
Entergy Operations
chawla M
References
TAC ME5806
Download: ML110950297 (1)


Text

From:

Chawla, Mahesh Sent:

Monday, April 04, 2011 3:51 PM To:

KUEMIN, JAMES L; Anderson, Paula Cc:

Purtscher, Patrick; Mitchell, Matthew; Pascarelli, Robert; Parks, Benjamin; Ulses, Anthony; Lingam, Siva; Boyle, Patrick; Ellegood, John; Taylor, Thomas; Lerch, Robert; Giessner, John

Subject:

LIC-109 Acceptance Review of Palisades LAR for Primary Coolant System Pressure-Temperature Limits - ME 5806 By letter dated March 7, 2011 (ADAMS Accession No. ML110730082), Entergy Nuclear Operations, Inc. (ENO)(the licensee) submitted a license amendment request for Palisades Nuclear Plant (PNP). The proposed amendment would add an applicability period of 42.1 effective full power years (EFPY) to TS LCO 3.4.3, figures 3.4.3-1 and 3.4.3-2 which contain the pressure-temperature (P/T) limit curves for primary coolant system (PCS) heatup and cooldown, and LCO 3.4.12 figure 3.4.12-1, which contains the low temperature overpressure protection (LTOP) setpoint limit curve.

The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff=s acceptance review of this amendment. 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 staff to proceed with 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. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. If you have any questions, please contact me

@(301) 415-8371 or Mahesh.chawla@nrc.gov. Thanks Mahesh Chawla, Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation