ML20092K957: Difference between revisions

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==Subject:==
==Subject:==
Millstone Power Station, Unit No. 2 - Acceptance Review Determination Re: LAR to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation (EPID L-2020-LLA-0039)
Millstone Power Station, Unit No. 2 - Acceptance Review Determination Re: LAR to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation (EPID L-2020-LLA-0039)
Date:            Wednesday, April 01, 2020 2:41:42 PM Mr. Sinha, By letter dated March 3, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20065K976), Dominion Energy Nuclear Connecticut, Inc. (the licensee) submitted a license amendment request for the Millstone Power Station, Unit No.
Date:            Wednesday, April 01, 2020 2:41:42 PM Mr. Sinha, By {{letter dated|date=March 3, 2020|text=letter dated March 3, 2020}} (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20065K976), Dominion Energy Nuclear Connecticut, Inc. (the licensee) submitted a license amendment request for the Millstone Power Station, Unit No.
: 2. The proposed amendment would revise Action 3 in TS Table 3.3-11, "Accident Monitoring Instrumentation," to address unnecessary restrictions for monitoring valve position when any of the three valve position monitoring indications (i.e., Instruments 4, 5 and 6) become inoperable. The table would be revised, in part, to add an alternate method for determining if there is loss of coolant through a power-operated relief valves (PORV) or pressurizer safety valve (PSV) flow path, in the event that any of the instruments identified in the current action statement are not available.
: 2. The proposed amendment would revise Action 3 in TS Table 3.3-11, "Accident Monitoring Instrumentation," to address unnecessary restrictions for monitoring valve position when any of the three valve position monitoring indications (i.e., Instruments 4, 5 and 6) become inoperable. The table would be revised, in part, to add an alternate method for determining if there is loss of coolant through a power-operated relief valves (PORV) or pressurizer safety valve (PSV) flow path, in the event that any of the instruments identified in the current action statement are not available.
The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this proposed licensing action. 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 purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this proposed licensing action. 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.

Latest revision as of 01:30, 25 September 2022

Acceptance Review Determination (E-mail Dated 4/1/2020) LAR to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation
ML20092K957
Person / Time
Site: Millstone Dominion icon.png
Issue date: 04/01/2020
From: Richard Guzman
NRC/NRR/DORL/LPL1
To: Sinha S
Dominion Energy Nuclear Connecticut
Guzman R
References
EPID L-2020-LLA-0039
Download: ML20092K957 (2)


Text

From: Guzman, Richard To: Shayan Sinha Cc: RidsNRRLIC109 Resource; Danna, James

Subject:

Millstone Power Station, Unit No. 2 - Acceptance Review Determination Re: LAR to Revise Technical Specification Table 3.3-11, Accident Monitoring Instrumentation (EPID L-2020-LLA-0039)

Date: Wednesday, April 01, 2020 2:41:42 PM Mr. Sinha, By letter dated March 3, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20065K976), Dominion Energy Nuclear Connecticut, Inc. (the licensee) submitted a license amendment request for the Millstone Power Station, Unit No.

2. The proposed amendment would revise Action 3 in TS Table 3.3-11, "Accident Monitoring Instrumentation," to address unnecessary restrictions for monitoring valve position when any of the three valve position monitoring indications (i.e., Instruments 4, 5 and 6) become inoperable. The table would be revised, in part, to add an alternate method for determining if there is loss of coolant through a power-operated relief valves (PORV) or pressurizer safety valve (PSV) flow path, in the event that any of the instruments identified in the current action statement are not available.

The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this proposed licensing action. 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),

whenever a holder of an operating license under this part desires to amend the license, application for an amendment must be filed with the Commission fully describing 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, as supplemented, 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. If additional information is needed, you will be advised by separate correspondence.

Based on the information provided in your submittal, as supplemented, the NRC staff has estimated that this licensing request will take approximately 320 hours0.0037 days <br />0.0889 hours <br />5.291005e-4 weeks <br />1.2176e-4 months <br /> to complete. The NRC staff expects to complete this review by April 2021 (i.e., approximately 12 months). 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, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.

If you have any questions, please contact me.

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

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