ML24324A196
| ML24324A196 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/26/2024 |
| From: | John Lamb NRC/NRR/DORL/LPL2-1 |
| To: | Southern Nuclear Operating Co |
| References | |
| EPID L-2024-LRM-0129 | |
| Download: ML24324A196 (1) | |
Text
November 26, 2024 LICENSEE:
Southern Nuclear Operating Company, Inc.
FACILITY:
Vogtle Electric Generating Plant, Units 3 and 4
SUBJECT:
SUMMARY
OF NOVEMBER 18, 2024, OBSERVATION PRE-SUBMITTAL MEETING HELD WITH SOUTHERN NUCLEAR OPERATING COMPANY, INC.,
REGARDING A PROPOSED LICENSE AMENDMENT REQUEST TO CHANGE TECHNICAL SPECIFICATIONS RELATED TO ENGINEERED SAFETY FEATURE ACTUATION SYSTEM ACTUATION LOGIC FOR VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4 (EPID L-2024-LRM-0129)
On November 18, 2024, an Observation meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Southern Nuclear Operating Company, Inc. (SNC, the licensee). The purpose of the meeting was for SNC to describe its plan to submit a license amendment request (LAR) for Vogtle Electric Generating Plant (Vogtle), Units 3 and 4.
SNC is proposing to move Surveillance Requirements (SRs) from Technical Specifications (TS) 3.3.15, Engineered Safety Feature Actuation System (ESFAS) Actuation Logic - Operating, and TS 3.3.16, Engineered Safety Feature Actuation System (ESFAS) Actuation Logic -
Shutdown.
A list of attendees is provided as an Enclosure.
On November 5, 2024 (Agencywide Documents and Access Management System (ADAMS)
Accession No. ML24315A001), the meeting was noticed on the NRC public webpage.
The NRC staff opened the meeting with introductory remarks and a roll call of the attendees.
The SNC representative presented slides contained in ML24317A003, and supplemental presentation material are contained in ML24317A249 and ML24317A274.
SNC representatives discussed the following topics: (1) background design, (2) proposed TS changes, (3) summary, and (4) discussion.
The current Vogtle, Units 3 and 4, TSs are contained in ADAMS under ML14100A106 and ML14100A135, respectively. The current TS Bases are contained in ADAMS under ML23165A219.
The following are the current SRs for TS 3.3.15:
The following are the current SRs for TS 3.3.16:
SNC proposes to make the following changes from Surveillance Requirement (SR) moves to new TS Limiting Conditions for Operation (LCO) with associated Conditions, Required Actions, and Completion Times:
Current SR Move to TS SR 3.3.15.1 - Verify pressurizer heater circuit breakers trip open.
TS 3.4.18 (new LCO), Pressurizer Heater Circuit Breakers SR 3.3.15.2 - Verify reactor coolant pump breakers trip open, TS 3.5.9 (new LCO), Reactor Coolant Pump Breaker SR 3.3.15.3 - Verify main feedwater and startup feedwater pump breakers trip open.
TS 3.7.3 (new SR), Main Feedwater Pump Breaker TS 3.7.7 (new SR) Startup Feedwater Pump Breaker SR 3.3.15.4 - Verify auxiliary spray and purification line isolation valves actuate to the isolation position.
TS 3.4.19 (new LCO) Auxiliary Spray and Purification Line Isolation Valves SR 3.3.16.1 - Verify reactor coolant pump breakers trip open.
TS 3.5.9 (new LCO), Reactor Coolant Pump Breaker SR 3.3.16.2 - Verify CVS letdown isolation valves actuate to the isolation position.
TS 3.4.20 (new LCO) CVS Letdown Isolation Valves The following are new LCOs that do not currently exist in the Vogtle, Units 3 and 4, TSs:
TS 3.4.18, Pressurizer Heater Circuit Breakers, TS 3.4.19, Auxiliary Spray and Purification Line Isolation Valves, TS 3.4.20, CVS Letdown Isolation Valves, and TS 3.5.9, Reactor Coolant Pump Breaker.
The proposed TS mark-ups are ML24317A274, and proposed TS Bases are ML24317A249.
SNC representatives stated that the TS 3.4.18, Pressurizer Heater Circuit Breakers, would (1) retain Action for one circuit breaker (i.e., Division) to restore to OPERABLE status in 6-hours, (2) retain Action for two circuit breakers (i.e., Divisions) and default Action to exit the applicability, (3) include Actions Note allowing separate condition entry for each pressurizer heater, and (4) the proposed moved SR to this TS adds exception for breaker maintained in the tripped condition.
SNC representatives stated that the TS 3.5.9, Reactor Coolant Pump Breakers, would (1) retain TS 3.3.15 and TS 3.3.16 Actions to restore to OPERABLE status in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, respectively, (2) MODES 1, 2, 3, and 4: retain two reactor coolant pump (RCP) breakers (i.e., Divisions) and default Action to exit the Applicability, (3) MODES 5 and 6: revise two RCP Breakers (i.e., Divisions) and default Action to immediate trip affected RCP Breaker(s) to accomplish the safety function, (4) include Actions Note allowing separate condition entry for each RCP, and (5) the proposed moved SRs to this TS adds exception for breaker maintained in the tripped condition.
SNC representatives stated that the TS 3.7.3, Main Feedwater Isolation Valves (MFIVs) and Main Feedwater Control Valves (MFCVs), and TS 3.7.7, Startup Feedwater Isolation and Control Valves, would (1) retain Action to restore to OPERABLE the Main and Startup Feedwater Pump breaker in 6-hours, (2) retain default Action to exit the applicability, (3) apply Actions Note allowing separate condition entry for each pump, and (4) the proposed moved SR to this TS adds exception for breaker maintained in the tripped condition.
SNC representatives stated that the TS 3.3.19, Auxiliary Spray and Purification Line Isolation, would (1) retain Action for one or two valves (i.e., one Division) to restore to OPERABLE in 6-hours, (2) revise Action for three valves (i.e., Two Divisions) and default Action to include an option to isolate the flow path (accomplishes the assumed safety function), and (3) include Actions two Notes to allow flow paths to be un-isolated intermittently under administrative control and separate condition entry for each flow path.
SNC representatives said that the TS 3.4.20, CVS Letdown Isolation Valves, would (1) retain TS 3.3.16 Action For one valve to restore to OPERABLE status in 72-hours, (2) revise Action For two valves (i.e., two Divisions) and default Action to initiate Action immediately to isolate the CVS letdown flow path, which accomplishes the assumed safety function, and (4) include Actions two Notes to allow flow paths to be un-isolated intermittently under administrative control and separate condition entry for each flow path.
SNC indicated that the proposed LAR will be deterministic, and it will not be risk informed.
SNC stated that the proposed LAR is expected to be submitted to the NRC in the fourth quarter of 2024 with a request that the NRC staff complete its review within 12 months after the acceptance review.
The NRC staff asked the following questions:
TS 3.3.15 LCO discusses four divisions, and the Condition A discusses one division inoperable. How does that relate to the new TS 3.4.18? How many divisions do the pressurizer heaters have?
What is the functional difference in the wording from TS 3.3.15 and TS 3.3.16 to the proposed changes?
Will TS 3.3.15 and TS 3.3.16 remain the same except that there will be no SRs?
When and how would SNC enter TS 3.3.15 and TS 3.3.16?
SNC is proposing to remove the SRs from TS 3.3.15 and TS 3.3.16 and moving the SRs to new TSs or existing TSs. Is SNC also modifying other TSs?
How does the safety analysis compare with the proposed new TSs?
Closing Remarks There was one member of the public in attendance.
The NRC staff did not make any regulatory decisions during the meeting. Once received, the NRC staff will perform a thorough review of the proposed LAR. The NRC staff will make any regulatory decisions in writing in a timely manner. Public Meeting Feedback forms were available, but no comments were received.
The meeting adjourned at 1:50 pm Eastern Time (ET).
Please direct any inquiries to me at John.Lamb@nrc.gov or 301-415-3100.
/RA/
John G. Lamb, Senior Project Manager Plant Licensing Branch, II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 52--025 and 52-026
Enclosure:
List of Attendees cc w/encls: Distribution via Listserv
Enclosure LIST OF ATTENDEES NOVEMBER 18, 2024, PRE-SUBMITTAL MEETING WITH SOUTHERN NUCLEAR COMPANY REGARDING A PROPOSED LICENSE AMENDMENT REQUEST TO MOVE SURVEILLANCE REQUIREMENTS RELATED TO ENGINEERED SAFETY FEATURE ACTUATION SYSTEM ACTUATION LOGIC VOGTLE ELECTRIC GENERATING PLANT, UNITS 3 AND 4 ATTENDEE REPRESENTING John G. Lamb U.S. Nuclear Regulatory Commission (NRC)
Mike Markley NRC Robert Beaton NRC Gokul Vasudevamurthy NRC Raul Hernandez NRC Norbert Carte NRC Christina Antonescu NRC Tarico Sweat NRC Nicholas Soliz NRC Vijay Goel NRC Ken Lowery Southern Nuclear Operating Company (SNC)
Ryan Joyce SNC William Howell SNC Thomas Joseph SNC Greg Crosby SNC Eddie Grant SNC Dan Williamson SNC Susan Sterritt Public
PKG ML24317A006 Meeting Notice ML24315A001 Meeting Summary ML24324A196 SNC Slides ML24317A003, ML24317A233, and ML24317A249 OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DSS/SNSB/BC DORL/LPL2-1/BC DORL/LPL2-1/PM NAME JLamb KGoldstein DMurdock (A)
MMarkley JLamb DATE 11/18/2024 11/20/2024 11/25/2024 11/26/2024 11/26/2024