ML18046A707
| ML18046A707 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/15/2018 |
| From: | NRC |
| To: | NRC/NRO/DNRL/LB4 |
| References | |
| Download: ML18046A707 (5) | |
Text
1 Vogtle PEmails From:
Comar, Manny Sent:
Thursday, February 15, 2018 12:51 PM To:
Vogtle PEmails
Subject:
ACCEPTANCE FOR REVIEW OF SOUTHERN NUCLEAR OPERATING COMPANYS LICENSE AMENDMENT REQUEST LAR-18-004 (Technical Specification Applicability Changes to Support Pressurizer Safety Valve Operability)
Attachments:
Acceptance Letter - VEGP Units 3 and 4 - LAR 18-044.docx
Hearing Identifier:
Vogtle_COL_Docs_Public Email Number:
220 Mail Envelope Properties (DM2PR09MB0622E05E3BCB7BE8B390A5E2FCF40)
Subject:
ACCEPTANCE FOR REVIEW OF SOUTHERN NUCLEAR OPERATING COMPANYS LICENSE AMENDMENT REQUEST LAR-18-004 (Technical Specification Applicability Changes to Support Pressurizer Safety Valve Operability)
Sent Date:
2/15/2018 12:50:43 PM Received Date:
2/15/2018 12:50:46 PM From:
Comar, Manny Created By:
Manny.Comar@nrc.gov Recipients:
"Vogtle PEmails" <Vogtle.PEmails@nrc.gov>
Tracking Status: None Post Office:
DM2PR09MB0622.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 8
2/15/2018 12:50:46 PM Acceptance Letter - VEGP Units 3 and 4 - LAR 18-044.docx 27088 Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received:
February 15, 2018 Mr. Brian H. Whitley, Director Regulatory Affairs Southern Nuclear Operating Company, Inc.
42 Inverness Center Parkway BIN B237 Birmingham, AL 35242
SUBJECT:
ACCEPTANCE REVIEW OF SOUTHERN NUCLEAR OPERATING COMPANYS REQUEST FOR LICENSE AMENDMENT FOR THE VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4:
TECHNICAL SPECIFICATION APPLICABILITY CHANGES TO SUPPORT PRESSURIZER SAFETY VALVE OPERABILITY (LAR 18-004)
Dear Mr. Whitley:
By letter dated January 31, 2018 (Agencywide Documents Access and Management System Accession No. ML18031B131), Southern Nuclear Operating Company (SNC/licensee) submitted a request for a License Amendment Request (LAR)18-004 for the Combined License (COL) Numbers NPF-91 and NPF-92, for Vogtle Electric Generating Plant (VEGP) Units 3 and 4, respectively.
The amendment requests proposed changes to Technical Specifications (TS) 3.4.6, Pressurizer Safety Valve, Applicability to require the pressurizer safety valves (PSVs) to be operable when the TS 3.4.14, Low Temperature Overpressure Protection, is not required to be operable. A conforming change to the TS 3.4.6 Actions is also proposed. Additional TS changes necessary to support PSV operability are proposed for consistency with the TS 3.4.6 change.
The request also proposes moving TS Limiting Condition for Operation Notes regarding reactor coolant pump starts from TS 3.4.4, Reactor Coolant System (RCS) Loops, 3.4.8, Minimum RCS Flow, and 3.4.14 to TS 3.4.3 RCS Pressure / Temperature Limits. These controls are addressed in proposed changes to COL Appendix A, Technical specifications.
The purpose of this letter is to provide the results of the 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.
Consistent with Title 10 of the Code of Federal Regulations (10 CFR) 50.90, an amendment to the license must fully describe the changes requested, and follow as far as applicable, the form prescribed for original applications. Section 52.79 of the 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 against the regulatory requirements and has 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.
If you have any questions, please contact me at (301) 415-3863 or Manny.Comar@nrc.gov.
Sincerely, R/A Manny Comar, Senior Project Manager Licensing Branch 4 Division of New Reactor Licensing Office of New Reactors Docket Nos.: 52-025 52-026