ML18348A617

Withdrawal of Requested Licensing Action to Adopt TSTF-425, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force (RITSTF) Initiative 5B Revision 3

ML18348A617
Person / Time
Site:	Palisades
Issue date:	12/14/2018
From:	Kimberly Green Plant Licensing Branch III
To:	Entergy Nuclear Operations
Green K,
References
EPID L-2018-LLA-0258
Download: ML18348A617 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 14, 2018 Vice President, Operations Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant 27780 Blue Star Memorial Highway Covert, Ml 49043-9530

SUBJECT:

PALISADES NUCLEAR PLANT - WITHDRAWAL OF REQUESTED LICENSING ACTION TO ADOPT TECHNICAL SPECIFICATIONS TASK FORCE TSTF-425, "RELOCATE SURVEILLANCE FREQUENCIES TO LICENSEE CONTROL-RISK-INFORMED TECHNICAL SPECIFICATION TASK FORCE (RITSTF)

INITIATIVE SB" REVISION 3 (EPID L-2018-LLA-0258)

Dear Sir or Madam:

By letter dated September 27, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18270A320), Entergy Operations, Inc. submitted a license amendment request for Palisades Nuclear Plant. The proposed amendment would modify the Palisades Nuclear Plant Technical Specifications (TS) by relocating specific surveillance frequencies to a licensee-controlled program with the implementation of Technical Specifications Task Force (TSTF) Traveler TSTF-425, "Relocate Surveillance Frequencies to Licensee Control - RITSTF [Risk-Informed TSTF] Initiative Sb," Revision 3, in accordance with Nuclear Energy Institute (NEI) 04-10, Revision 1, "Risk-Informed Technical Specifications Initiative Sb, Risk-Informed Method for Control of Surveillance Frequencies." 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. 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 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.

By letter dated December 14, 2018 (ADAMS Accession No. ML18348A421 ), you requested to withdraw the application from NRC review. The NRC acknowledges your request to withdraw the application. The NRC staff activities on the review have ceased and the associated EPID number has been closed.

The NRC staff notes that its review to date has identified that your application did not provide the following technical information in sufficient detail to enable the staff to complete its detailed review. Therefore, if you decide to re-submit the request, it must include the following information:

1. For Facts and Observations (F&Os) SY-83-01 and QU-A3-01:

a. a description of the specific actions performed as part of the probabilistic risk assessment update process to resolve the F&O, or

b. if an update to resolve the F&O was not performed:

i. a detailed justification of why the F&O has no impact on the application, or ii. a description and justification of the evaluation which will be performed on a case-by-case surveillance test Interval basis to address the impact of the unresolved F&O.

2. For F&Os HR-G?-01 and QU-C1-01:

a. a statement that describes that a focused-scope peer-review was conducted against the standard supporting requirements, as endorsed and clarified in Regulatory Guide 1.200, "An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities," Revision 2, related to the implementation of the human reliability analysis dependency analysis, and

b. a description of all of the F&Os resulting from the focused-scope peer review, and for each F&O, a disposition of the F&O for the application.

If you have any questions, please contact me at (301) 415-1627.

Sincerely, K~~

Kimberly Green, Senior Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-255 cc: Listserv

ML18348A617 OFFICE DORL/LPL3/PM DORL/LPL3/LA DRA/APLA/BC DORL/LPL3/BC DORL/LPL3/PM NAME Kimberly Green !Betts SRosenberg David Wrona Kimberly Green DATE 12/14/2018 12/14/2018 12/4/2018 12/14/2018 12/14/2018