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EPID:L-2023-LRM-0104, Summary of December 11, 2023, Meeting with Duke Energy to Discuss a Shearon Harris Nuclear Power Plant, Unit 1 Planned Exemption Request Related to Turbine Control System and Reactor Protection System Circuitry (Open) |
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Category:Meeting Summary
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2024-05-01
[Table view] |
Text
February 12, 2024
LICENSEE: Duke Energy
FACILITIES: Shearon Harris Nuclear Power Plant, Unit 1
SUBJECT:
SUMMARY
OF DECEMBER 11, 2023, MEETING WITH DUKE ENERGY TO DISCUSS A SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 PLANNED EXEMPTION REQUEST RELATED TO TURBINE CONTROL SYSTEM AND REACTOR PROTECTION SYSTEM CIRCUITRY (EPID NO. L-2023-LRM-0104)
On December 11, 2023, a virtual observation public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Duke Energy (Duke, the licensee). The purpose of the meeting was to discuss a planned license amendment request to be submitted under Risk-Informed Process for Evaluations (RIPE) related to the Turbine Control System (TCS) and Reactor Protection System (RPS) circuitry for the Shearon Harris Nuclear Power Plant, Unit 1 (Harris). The meeting notice and agenda, dated November 21, 2023, are available in the Agencywide Documents Access and Management System (ADAMS) Accession No. ML23325A076. A list of attendees is provided in the enclosure.
The licensee presented slides (ML23341A152) and discussed the following:
Description of the issue o Licensee received a green non-cited violation:
Performance deficiency - failure to ensure independence between the TCS circuits and trains of RPS circuits.
System Design and Operation:
o RPS - generates signals that acuate a reactor trip.
o Engineered Safety Features Actuation System (ESFAS) - generates signals that actuate engineered safety features.
o TCS - non-safety related, controls valve position, speed and/or load of turbine.
Current Licensing Basis:
o Updated Final Safety Analysis Report, Section 8.3.1.2.30 - Cables and conduits routed in non-Category I structures associated with safety related functions or anticipatory trips (i.e., turbine trip on reactor trip, reactor trip on turbine trip, loss of feedwater) are designed to meet Institute of Electrical and Electronics Engineers (IEEE)-Standard 279-1971 including redundancy, separation, and single failure criteria
Application of RIPE Process:
o Applicable guidance documents.
o RIPE Process Criteria:
Technically acceptable Probabilistic Risk Assessment (PRA):
Technical Specification Task Force Traveler (TSTF)-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.
Integrated Decision-Making Panel (IDP).
Implementation of Title 10 of the Code of Federal Regulations (10 CFR) 50.69, Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors.
o PRA Analysis PRA Model Consistent with model utilized for Risk-Informed Completion Time Program.
Includes high winds hazard.
Does not quantitively asses seismic or external flooding hazards.
based on meeting screening criteria.
Strategy Quantitative Risk Assessment to calculate change in core damage frequency (CDF) and large early release frequency (LERF).
Single basic event to reflect a potential common cause event for the functions susceptible to impacts of the current circuitry configuration.
Hot short within the portion of the RPS and solid state protection system (SSPS) circuitry in proximity to the TCS circuitry is the surrogate failure mode.
The targets of interest from which to assess potential impacts to the associated cables are selected to be the 48 Volt SSPS power supplies utilized for the SSPS cabinets.
PRA Results meet the RIPE criteria for minimal safety impact.
NRC staff discussed the following:
How do you conclude that electromagnetic interference and radio frequency interference affects would demonstrate that no credi ble events would impact from components fulfilling their design basis functions?
How many RPS/SSPS/ESFAS safety system channels are in Cabinet G that potentially be affected?
Redundancy should be considered, and licensee should be able to show, under worst case conditions (even if proven not credible), still have ability to trip reactor and turbine.
Does the IDP document contain discussion of diversity and redundancy related to losing ability to trip reactor and/or turbine?
Is the focus of the exemption only Cabinet G and cables inside that cabinet which terminate at the same location?
Would any cabling downstream of the Cabinet G be subject to the exemption request?
After Cabinet G, are the cables in separate cable trays?
Are you only using manual actions (to trip) for defense in depth purposes?
Does your evaluation show that there are no credible events that would impact both cables in Cabinet G?
Are there other measures in place if the automatic turbine trip may not be available under worst case conditions, even though evaluations may determine it is not credible?
There were four members of the public in attendance.
Please direct any inquiries to me at 301-415-3867, or Michael.Mahoney@nrc.gov.
Sincerely,
/RA/
Michael Mahoney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Docket No. 50-400
Enclosure:
List of Attendees
cc: Listserv
LIST OF ATTENDEES
DECEMBER 11, 2023, PUBLIC MEETING WITH DUKE ENERGY
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1
PLANNED EXEMPTION REQUEST RELATED TO TURBINE CONTROL SYSTEM AND
REACTOR PROTECTION SYSTEM CIRCUITRY TO BE SUBMITTED UNDER THE
RISK-INFORMED PROCESS FOR EVALUATIONS
Name Organization Michael Mahoney U.S. Nuclear Regulatory Commission (NRC)
John Hughey NRC Michelle Kichline NRC Ming Li NRC Antonios Zoulis NRC Demtrius Murray NRC Siva Lingham NRC
Dennis Earp Duke Energy (Duke)
Andrew Lipetzky Duke Ryan Treadway Duke Brian Mayall Duke Jennifer Varnedoe Duke Nick Burgess Duke Nick Martenelli Duke
Roy Linthicum Public - Constellation Frank Hope Public Mary Miller Public Thomas Jaeger Public
Enclosure
Package: ML24011A162 Meeting Notice: ML23325A076 Meeting Summary: ML24011A165 NRC-001 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DORL/LPL2-2/BC NRR/DORL/LPL2-2/PM NAME MMahoney ABaxter DWrona MMahoney DATE 02/06/2024 02/06/2024 02/08/2024 02/12/2024
