ML21013A336

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December 17, 2020, Summary of Category 1 Public Pre-Application Meeting with Entergy Operations,Inc. Regarding Proposed LAR to Adopt Risk-Informed TS Allowed Outage Times for Waterford Steam Electric Station, Unit 3
ML21013A336
Person / Time
Site: Waterford Entergy icon.png
Issue date: 01/26/2021
From: Audrey Klett
Plant Licensing Branch IV
To:
Klett A
Shared Package
ML21013A344 List:
References
EPID L-2020-LRM-0110
Download: ML21013A336 (27)
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Text

January 26, 2021 LICENSEE:

Entergy Operations, Inc.

FACILITY:

Waterford Steam Electric Station, Unit 3

SUBJECT:

SUMMARY

OF DECEMBER 17, 2020, CATEGORY 1 PUBLIC PRE-APPLICATION MEETING WITH ENTERGY OPERATIONS, INC.

REGARDING PROPOSED LICENSE AMENDMENT REQUEST TO ADOPT RISK-INFORMED TECHNICAL SPECIFICATION ALLOWED OUTAGE TIMES FOR WATERFORD STEAM ELECTRIC STATION, UNIT 3 (EPID L-2020-LRM-0110)

On December 17, 2020, the U.S. Nuclear Regulatory Commission (NRC) staff held a virtual Category 1 public meeting with representatives from Entergy Operations, Inc. (the licensee) and its contractors. The purpose of the meeting was to discuss the licensees plans to submit a license amendment request for the Waterford Steam Electric Station, Unit 3 (Waterford 3),

regarding adopting risk-informed allowed outage times (RIAOTs) in the technical specifications (TSs). The meeting notice and agenda, dated December 3, 2020, are available in the NRCs Agencywide Documents Access and Management System (ADAMS) under Accession No. ML20339A393. Enclosure 1 provides a list of attendees.

During the meeting, the licensee presented its plans to submit a license amendment request, which, if approved, would incorporate RIAOTs into the TSs. Enclosure 2 contains the licensees presentation slides. The licensee stated that its request will be based on Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF [Risk-Informed TSTF] Initiative 4b, dated July 2, 2018 (ADAMS Accession No. ML18183A493). The Commission issued a final model safety evaluation approving TSTF-505, Revision 2, on November 21, 2018 (ADAMS Accession No. ML18269A041). The licensee stated that many of its TS limiting conditions for operation (LCOs) match those in NUREG-1432, Revision 4, Standard Technical Specifications [STS] -

Combustion Engineering Plants (ADAMS Accession No. ML12102A165). Some LCOs have corresponding LCOs in the STSs with minor differences, whereas some LCOs are site-specific with no STS counterpart. The licensee then presented which TSs will be included in the application, and categorized them into four groups: (1) identical or nearly identical to LCOs within the scope of TSTF-505, Revision 2, (2) LCOs within the scope of TSTF-505, Revision 2, with some differences but still meeting scope criteria, (3) LCOs excluded from the scope of TSTF-505, Revision 2, but the reason for their exclusion does not apply to the sites LCOs, and (4) site-specific LCOs that meet the criteria.

The licensee provided an overview of its probabilistic risk analyses (PRAs), including a status of its peer reviews and findings and observations. The licensee stated that it plans to submit its application in January 2021 and will request the NRC to complete its review within 12 months.

The NRC staff inquired about the history of the peer reviews for the licensees PRA models and encouraged the licensee to submit clear information in the license amendment request. The NRC staff asked whether the licensee had confirmed that all conditions for which a RIAOT is to be applied were conditions where the design basis success criteria could still be fulfilled with the remaining available equipment (i.e., a RIAOT will not be used for any condition where there is a loss of specified safety function). The licensee stated that it did not believe that a RIAOT was assigned to any such conditions, and that it will reevaluate all conditions to ensure that Table E1-1 in the license amendment request indicates when a design basis function may be unavailable. The NRC staff also asked if a RIAOT would be applied to conditions that did not affect core damage frequency (CDF) or large early release frequency (LERF). The question was reformulated as to whether there were any RIAOT calculations that only used the generic seismic penalty factor. The licensee stated that all conditions to which a RIAOT will be applied will affect CDF or LERF. The NRC staff encouraged the licensee to provide clear information in Table E1-1 on design criteria and PRA modeling considerations.

The NRC staff requested the licensee to summarize the analysis performed to identify key assumptions and sources of uncertainty and how this analysis is documented. The licensee stated that assumptions and sources of uncertainty were identified from two primary sources:

PRA notebooks for the Waterford 3 PRA and Electric Power Research Institute reports. The licensee stated that the analysis process to reduce the compiled list of assumptions and sources of uncertainty down to the list of key assumptions and sources of uncertainty for the application is documented in a plant report developed specifically for the TSTF-505 application.

The NRC staff asked the licensee if its application will consider external hazards. The licensee stated that seismic risk will be considered using the seismic penalty. The NRC staff commented that the seismic penalty (i.e., seismic CDF and seismic LERF) calculation should be based on site-specific seismic information.

The NRC staff also inquired whether credit for FLEX was taken in the licensees PRA. The licensee explained that only permanently installed FLEX equipment is credited in the PRA models used for this application.

The NRC staff did not make any regulatory decisions or commitments at the meeting. No members of the public identified themselves at the meeting.

Please direct any inquiries to me at 301-415-0489 or by e-mail to Audrey.Klett@nrc.gov.

/RA/

Audrey L. Klett, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382

Enclosures:

1. List of Attendees
2. Licensee Presentation cc: Listserv

List of Attendees

LIST OF ATTENDEES DECEMBER 15, 2020, VIRTUAL PUBLIC MEETING WITH ENTERGY OPERATIONS, INC., ET AL.

WATERFORD STEAM ELECTRIC STATION, UNIT 3, PRE-APPLICATION MEETING TO ADOPT RISK-INFORMED TECHNICAL SPECIFICATION COMPLETION TIMES U.S. Nuclear Regulatory Commission Steven Alferink, NRR1/DRA2/APLC3 Khadijah West, NRR/DSS/STSB Odunayo Ayegbusi, NRR/DRA/APLB4 Brian Wittick, NRR/DSS/SCPB Mihaela Biro, NRR/DRA/APLA5 De Wu, NRR/DRA/APLC Angela Buford, NRR/DEX6/EMIB7 Steve Dinsmore, NRR/DRA/APLA PNNL Jennifer Dixon-Herrity, NRR/DORL8/LPL49 Steve Short Jonathan Evans, NRR/DRA/APLA Mark Wilk Fred Forsaty, NRR/DSS10/SNSB11 Brian Green, NRR/DRO12/IOLB13 Entergy Operations, Inc.

Bernard Grenier, NRR/DRA/APLB Nicholas Allen Nicholas Hansing, NRR/DEX/EMIB Remy DeVoe Raul Hernandez, NRR/DSS/SCPB14 Ronald Gaston Edmund Kleeh, NRR/DEX/EEEB15 Wesley Johnson Audrey Klett, NRR/DORL/LPL4 Howard (Cecil) Mahan Ed Miller, NRR/DORL/LPL2-116 John Schrage Sunwoo Park, NRR/DRA/APLC William Steelman Bob Pascarelli, NRR/DRA/APLA Mark Thigpen Sheila Ray, NRR/DEX/EEEB Jay Robinson, NRR/DRA/APLB Jensen Hughes, Inc.

Andrea Russell, NRR/DSS/STSB17 Alan Harris Thomas Scarbrough, NRR/DEX/EMIB Andrew Spotts Gursharan Singh, NRR/DEX/EICB18 Keith Tetter, NRR/DRA/APLC Members of the Public Brett Titus, NRR/DEX/EEEB None introduced Shilp Vasavada, NRR/DRA/APLC 1 Office of Nuclear Reactor Regulation 2 Division of Risk Assessment 3 PRA Licensing Branch C 4 PRA Licensing Branch B 5 PRA Licensing Branch A 6 Division of Engineering and External Hazards 7 Mechanical Engineering and Inservice Testing Branch 8 Division of Operating Reactor Licensing (DORL) 9 Plant Licensing Branch IV 10 Division of Safety Systems 11 Nuclear Systems Performance Branch 12 Division of Reactor Oversight 13 Operator Licensing and Human Factors Branch 14 Containment and Plant Systems Branch 15 Electrical Engineering Branch 16 Plant Licensing Branch II-1 17 Technical Specifications Branch 18 Instrumentation and Controls Branch

Licensee Presentation

Waterford 3 Risk-Informed Allowed Outage Time (RIAOT)

License Amendment Request NRC Pre-submittal Meeting December 17, 2020

Participants Entergy

  • Ron Gaston, Director Fleet Regulatory Assurance
  • Paul Wood, Waterford 3 Manager, Regulatory Assurance
  • Billy Steelman, Waterford 3 Manager, Design Engineering
  • Richard French, Waterford 3 Project Manager
  • Wes Johnson, Corporate PRA Supervisor
  • Mark Thigpen, Waterford 3 PRA Engineer
  • Remy DeVoe, Waterford 3 Regulatory Assurance
  • Alan Harris, Jensen Hughes, Licensing Consultant
  • Andy Spotts, Jensen Hughes, PRA Consultant 2

Agenda Introduction/Opening Remarks Waterford 3 LAR Overview TSTF-505 Revision 2

  • TECHNICAL SPECIFICATIONS TASK FORCE TRAVELER TSTF-505, REVISION 2 PROVIDE RISK-INFORMED EXTENDED COMPLETION TIMES - RITSTF INITIATIVE 4B 3

Waterford 3 LAR Overview TSTF-505 Revision 2 Revision 2 issued November 2018 Removes provision for total loss of function Less detailed explanations provided on why certain Limited Conditions for Operation (LCOs) are excluded from previous revisions.

Section 2.3 scope criterion 18 referenced in LAR for site-specific LCOs:

Restored to OPERABLE Channel placed in TRIP Isolate Inoperable isolation valve 4

Waterford 3 Applicability Waterford 3 is a Combustion Engineering Custom Tech Spec plant.

Many LCOs match NUREG-1432 Revision 4, Standard Technical Specifications - Combustion Engineering Plants Some LCOs have corresponding LCOs in Standard Technical Specification (STS), with minor differences Some LCOs are site-specific with no STS counterpart 5

Technical Specifications (TS) to Include The following slides will show which TS are in the scope of LAR, separated into 4 groups:

1. Identical or nearly Identical to LCO in scope of TSTF-505 Rev 2.
2. LCO in scope of TSTF-505 Rev 2, with some differences, while still meeting scope criteria
3. LCO is excluded from scope of TSTF-505 Rev 2, but reason for exclusion does not apply to Waterford 3 LCO.( for example, 30 day completion time in STS)
4. Waterford 3 site specific LCO that meets criteria 6

Technical Specifications (TS) to Include Identical or nearly Identical to LCO in scope of TSTF-505 Rev 2.

7 Technical Specification LCO LCO Title 3.4.3.1 Pressurizer 3.5.2 ECCS Subsystems - Modes 1, 2, and 3 3.7.1.5 Main Steam Line Isolation Valves (MSIVs) 3.7.12 Essential Services Chilled Water System

Technical Specifications (TS) to Include Identical or nearly Identical to LCO in scope of TSTF-505 Rev 2 (EXAMPLE) 8

Technical Specifications (TS) to Include LCO in scope of TSTF-505 Rev 2, with some differences, while still meeting scope criteria 9

Technical Specification LCO LCO Title 3.3.1 Reactor Protective Instrumentation 3.3.2 Engineered Safety Features Actuation System Instrumentation 3.6.1.3 Containment Air Locks 3.6.1.7 Containment Ventilation System 3.6.3 Containment Isolation Valves 3.6.2.1 Containment Spray System 3.6.2.2 Containment Cooling 3.7.1.2 Emergency Feedwater System 3.7.1.7 Atmospheric Dump Valves 3.7.3 Component Cooling Water and Auxiliary Component Cooling Water Systems 3.8.1.1 A.C. Sources 3.8.2.1 D.C. Sources 3.8.3.1 Onsite Power Distribution Systems

Technical Specifications (TS) to Include LCO in scope of TSTF-505 Rev 2, with some differences, while still meeting scope criteria-EXAMPLE 10

Technical Specifications (TS) to Include LCO is excluded from scope of TSTF-505 Rev 2, but reason for exclusion does not apply to Waterford 3 LCO.

11 Technical Specification LCO LCO Title 3.7.1.3 Condensate Storage Pool 3.7.6.1 Control Room Emergency Air Filtration System 3.7.6.3 Control Room Air Temperature - Operating

Technical Specifications (TS) to Include LCO is excluded from scope of TSTF-505 Rev 2, but reason for exclusion does not apply to Waterford 3 LCO.-EXAMPLE 12

Technical Specifications (TS) to Include Waterford 3 site specific LCO that meets criteria 13 Technical Specification LCO LCO Title 3.4.3.2 Auxiliary Spray 3.7.1.6 Main Feedwater Isolation Valves 3.7.4 Ultimate Heat Sink

Technical Specifications (TS) to Include Waterford 3 site specific LCO that meets criteria-EXAMPLE 14

Technical Specifications (TS) to Include Waterford 3 site specific LCO that meets criteria-EXAMPLE 15

Technical Specifications (TS) to Include Complete List of TS included in LAR 16 Technical Specification LCO LCO Title 3.3.1 Reactor Protective Instrumentation 3.3.2 Engineered Safety Features Actuation System Instrumentation 3.4.3.1 Pressurizer 3.4.3.2 Auxiliary Spray 3.5.2 ECCS Subsystems - Modes 1, 2, and 3 3.6.1.3 Containment Air Locks 3.6.1.7 Containment Ventilation System 3.6.3 Containment Isolation Valves 3.6.2.1 Containment Spray System 3.6.2.2 Containment Cooling 3.7.1.2 Emergency Feedwater System 3.7.1.3 Condensate Storage Pool 3.7.1.5 Main Steam Line Isolation Valves (MSIVs) 3.7.1.6 Main Feedwater Isolation Valves 3.7.1.7 Atmospheric Dump Valves 3.7.3 Component Cooling Water and Auxiliary Component Cooling Water Systems 3.7.4 Ultimate Heat Sink 3.7.6.1 Control Room Emergency Air Filtration System 3.7.6.3 Control Room Air Temperature - Operating 3.7.12 Essential Services Chilled Water System 3.8.1.1 A.C. Sources 3.8.2.1 D.C. Sources 3.8.3.1 Onsite Power Distribution Systems

Probabilistic Risk Analyses (PRA) Status PRA Peer Reviews 17 RG 1.200 PRA Peer Review (Westinghouse Owners Group August 2009).

Fire PRA Peer Review Against Section 4 of the ASME/ANS Standard (Westinghouse Owners Group February 2011)

Focused Scope Fire PRA Peer Review Against Section 4 of the ASME/ANS Standard (URS Corporation - September 2012) 2nd Focused Scope Fire PRA Peer Review of Fire PRA Against Section 4 of the ASME/ANS Standard (URS Corporation - May 2013)

Waterford 3 Finding Level F&O Independent Technical Review (October 2017)

Waterford 3 Internal Flood/LERF Focused Scope Peer Review (August 2019)

Probabilistic Risk Analyses (PRA) Status PRA Baseline Values 18 Hazard Model Baseline Baseline CDF LERF At Power Internal Events Rev6 3.03E-06 3.04E-08 Internal Fire Rev6 Fire 2.01E-05 2.05E-07 Internal Flood Rev6 Flood 1.49E-06 7.47E-09 Seismic Bounding Estimate 3.20E-06 3.20E-07 Total 2.78E-05 5.63 E-07

Schedule Schedule Plan to submit LAR January 2021 Requesting 12 month approval 19

Closing Remarks

ML21013A344 (Package)

ML21013A336 (Summary and Enclosure 1)

ML21013A337 (Enclosure 2, Licensee Presentation Slides)

OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DRA/APLA/BC NAME AKlett PBlechman RPascarelli DATE 01/26/2021 01/15/2021 01/26/2021 OFFICE NRR/DSS/STSB/BC NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME VCusumano JDixon-Herrity AKlett DATE 01/26/2021 01/26/2021 01/26/2021

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