ML16056A253

From kanterella
Jump to navigation Jump to search

Acceptance of License Amendment Request to Change the Emergency Plan by Revising the Emergency Action Level Scheme
ML16056A253
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 02/26/2016
From: Blake Purnell
Plant Licensing Branch III
To: Boles B
FirstEnergy Nuclear Operating Co
Purnell B
References
CAC MF7364
Download: ML16056A253 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 26, 2016 Mr. Brian D. Boles Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-DB-3080 5501 N. State Route 2 Oak Harbor, OH 43449-9760

SUBJECT:

DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 -ACCEPTANCE OF LICENSE AMENDMENT REQUEST TO CHANGE THE EMERGENCY PLAN BY REVISING THE EMERGENCY ACTION LEVEL SCHEME (CAC NO. MF7364)

Dear Mr. Boles:

By application dated February 17, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16049A513), FirstEnergy Nuclear Operating Company (FENOC) submitted a license amendment request for Davis-Besse Nuclear Power Station (DBNPS), Unit No. 1. The proposed amendment would change the emergency plan for DBNPS by revising the emergency action level scheme based on the Nuclear Energy lnstitute's (NEl's) guidance in NEI 99-01, Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors."

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

B. Boles If you have any questions, please contact me at (301) 415-1380.

Sincerely, 15~ ~

Blake Purnell, Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-346 cc: Distribution via Listserv

ML16056A253 OFFICE DORL/LPL3-2/PM DORL/LPL3-2/LA DORL/LPL3-2/BC (A) DORL/LPL3-2/PM NAME BPurnell SRohrer JPoole BPurnell DATE 2/25/2016 2/25/2016 2/26/2016 2/26/2016