ML20021A380

Updated E-mail 1/21/2020; Acceptance Review Determination: Proposed License Amendment City Water and Condensate Storage Tank Technical Specifications

ML20021A380
Person / Time
Site:	Indian Point
Issue date:	01/21/2020
From:	Richard Guzman NRC/NRR/DORL/LPL1
To:	Mirzai M Entergy Nuclear Operations
Guzman R
References
EPID L-2019-LLA-0262
Download: ML20021A380 (2)

Text

From: Guzman, Richard To: Mirzai, Mahvash Cc: RidsNRRLIC109 Resource

Subject:

RE: Indian Point Unit No. 3 - Acceptance Review Determination: Proposed License Amendment Re: City Water and Condensate Storage Tank Technical Specifications (EPID: L-2019-LLA-0262)

Date: Tuesday, January 21, 2020 3:13:42 PM Ms. Mirzai, As we discussed, the estimated review completion date was revised to June 2020 as shown updated below. This message supersedes the original message sent on December 30, 3019 and will be added to ADAMS as an official agency record.

Sincerely,

~~~~~~~~~~~~

Rich Guzman Sr. PM, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov From: Guzman, Richard Sent: Monday, December 30, 2019 6:35 AM To: Mirzai, Mahvash <mmirzai@entergy.com>

Cc: RidsNRRLIC109 Resource <RidsNRRLIC109.Resource@nrc.gov>; Danna, James

<James.Danna@nrc.gov>; Mackaman, Clyde D <cmackam@entergy.com>; Dahl, George

<gdahl@entergy.com>

Subject:

Indian Point Unit No. 3 - Acceptance Review Determination: Proposed License Amendment Re: City Water and Condensate Storage Tank Technical Specifications (EPID: L-2019-LLA-0262)

Ms. Mirzai, By letter dated November 21, 2019 (ADAMS Accession No. ML19325E913), Entergy Nuclear Operations, Inc. (the licensee) submitted a license amendment request (LAR) for Indian Point Unit No. 3 (IP3), proposing changes to Technical Specification (TS) 3.7.7, "City Water," Surveillance Requirement (SR) 3.7.7.2 and TS 3.7.6, Condensate Storage Tank (CST), Required Action A.1.

Specifically, the proposed amendment would revise TS SR 3.7.7.2 to allow one of the backflow preventer isolation valves on the IP3 CW Header Supply to be maintained closed when in the Modes of Applicability for TS LCO 3.7.7 (i.e., during Modes 1, 2, and 3, and Mode 4 when the steam generators are relied upon for heat removal), provided the requirements of TS LCO 3.7.6 are met. The proposed change would eliminate intrusion of CW into the Auxiliary Feedwater (AFW) system and the CST due to leak-by past a downstream isolation valve and allow removal of a temporary modification that provides continuous flushing of the 33 AFW pump suction line. In addition, the proposed amendment would revise TS 3.7.6, Required Action A.1 to require the closed backflow

preventer isolation valve on the IP3 CW Header Supply to be re-opened immediately in the event the CST is declared inoperable.

The purpose of this e-mail is to provide the results of the Nuclear Regulatory Commission (NRC) staffs acceptance review of this LAR. 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.

The NRC staff has reviewed your application and concluded that it provides 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.

Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> to complete. The NRC staff expects to complete this review by June 2020. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager. These estimates are based on the NRC staffs initial review of the application and they could change, due to several factors including requests for additional information, and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.

Please contact me if you have any questions. A copy of this email will be made publicly available in ADAMS.

~~~~~~~~~

Rich Guzman Sr. PM, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: 301-415-1030