1. Bert Yates 1
George Gilbert (Bert) Yates
25 Coach Line Drive
O’Fallon, MO 63368
636-675-7607
ggyates11@gmail.com
Areas of Expertise
Regulatory Affairs: License Amendments (50.59, 50.90); Improved Technical Specifications
(ITS), Led Training Seminars on ITS Chapters 1.0 & 3.0; ITS Bases; Final Safety Analysis
Report (FSAR) Updates; Reportability Evaluations (50.72 and 50.73); Licensee Event Reports;
50.46 Reporting; EOP Revisions; Setpoint Calculations; Digital Control System Modifications;
License Renewal; ISFSI; Callaway Unit 2 COLA; NFPA-805; FLEX modifications and recovery
procedures
Operability Determinations, Operator Action Time Justifications
Environmental and Seismic Qualification of Equipment
Professional Experience
Callaway Plant
Callaway Licensing Lead Engineer – 1993-2015
Split Report LA103 1993-1995 (relocated 33 LCOs from the Technical Specifications
(TS) to FSAR Chapter 16 (Callaway’s TRM-equivalent))
Improved Technical Specification (ITS) Conversion for Callaway, Wolf Creek,
Comanche Peak, Diablo Canyon 1995-2000
Wrote ITS Chapter 2.0, 3.1, 3.3 Conversion Documents for All Four Plants
Answered all RAIs on those chapters
Wrote Callaway ITS Chapters 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5
Answered all RAIs on those chapters
Callaway LA133 implemented April 2000
2. Bert Yates 2
I&C Business Unit Lead (one of two I&C leads) Callaway Refuel 14 SG Replacement Outage
Shortest 4-loop SG Replacement Outage, 63.5 days, November 2005
Setpoint Calculations in support of RTD Bypass Modification, SG Replacement using TSTF-493
style nominal trip setpoint footnotes (RTS and ESFAS), Pressurizer Pressure Transmitter
Replacement, Original SG Mid-Deck Plate Errors, Cable Insulation Resistance Environmental
Error Allowances
Operator Action Justifications in contesting yellow and white ROP findings (justifications for
action response times, procedure-based success likelihood, and training/knowledge success
paths)
AP1000 Technical Specifications (e.g., used them to replace E-bar definition in Callaway’s
Technical Specifications with Dose Equivalent Xe)
Contributor and qualified reviewer for Callaway’s successful License Renewal Amendment,
NFPA-805 amendment (I revised the FP License Condition and FSAR.), FLEX modifications
and recovery procedures, and the ISFSI Technical Specifications
Contributor and qualified reviewer for Callaway Unit 2 COLA under 10 CFR Part 52 (Due to
Missouri State law prohibiting AFUDC, the NRC’s review of the Unit 2 COLA was terminated
prior to the 10 CFR 52.99 ITAAC phase when it became clear that legislative efforts to change
the law on construction work in progress would not bear fruit. The project was also made more
difficult by a decision to pursue the Areva EPR which does not have a 10 CFR 52 design
certification.)
Lead Engineer on Digital Feedwater (DFW) Control Modification – NEI 01-01 and NEI 96-07
guidance found to be inadequate. I postulated a DFW common cause software failure that led to
increased feedwater flow that had to be reanalyzed for the increased secondary heat removal
transient (FSAR Section 15.1) and increased flooding in the hazard analysis for the main steam
tunnel equipment.
Various Refueling Outage assignments (Reactor Vessel Head Crew, Control Room Shutdown
Safety Risk Assessments-Qualitative)
Wrote and Implemented all Risk-Informed License Amendments at Callaway
Wrote and Implemented over 100 Callaway License Amendments
Major Amendments included: Cycle 2 and Cycle 3 OFA and VANTAGE 5 fuel change;
5% Plant Uprating; TSTF-358 SR 3.0.3 Relaxation; TSTF-359 LCO 3.0.4 MODE
3. Bert Yates 3
Change Relaxation; PORV Upgrade and Pressurizer Safety Valve Tolerance Relaxation
(required reanalysis of Inadvertent ECCS event crediting operator action times of less
than 10 minutes); Replacement SG LA168 including pre-TSTF-493 setpoint footnotes
and TSTF-449 SG Tube Program Relaxations (1500-page LAR); several Boron Dilution
Mitigation System amendments to ITS 3.3.9; added new LCO to Chapter 3.1 to address
Rod Withdrawal from Subcriticality Crediting Power Range Neutron Flux-Low in
MODE 3; ECCS LCO 3.0.3 Valves and Seal Injection and ECCS Throttle Valves; High
Density Polyethylene Piping Replacement for Class 3 ESW Service (one-time 14-day
Completion Time and ASME Relief Request); wrote common WCAP-14333/15376 RTS
and ESFAS LAR for Callaway, Wolf Creek, Comanche Peak, and Diablo Canyon to
relax Completion Times, Bypass Testing, and Surveillance Frequencies; UHS LA202
(saved Callaway from being required to resize UHS at estimated cost of $40M); Non-TS
Electrical Room Cooling (drafted new TS 3.7.20 and LAR yet to be submitted for
Callaway and Wolf Creek)
Wrote and Implemented over 500 Callaway FSAR Change Notices
Responsible for FSAR Sections 3.6-3.11 (hazard analyses, seismic design, EQ), Chapter
6 (containment analyses, ECCS, control room habitability), Chapter 7 (I&C), Chapter 15
(accident analyses with emphasis on LOCA and analyses that credit operator actions such
as SGTR and Inadvertent ECCS), Chapter 16 (Callaway TRM-equivalent)
Callaway Environmental and Seismic Qualification Lead Engineer – 1982-1993
Project Lead on EQ, Seismic, PVORT (Pump and Valve Operability Review Team) Near
Term Operating License Audits 1982-1984
Responsible for closing out Open Items in NUREG-0830 SER Supplements 3 and 4 in
support of Callaway Low Power and Full Power Operating Licenses
Designed and tested (with Patel Engineers, Huntsville, AL) a core exit thermocouple
splice to fulfill Callaway’s License Condition on full 50.49 compliance prior to 11/30/85
Master EQ File Development, Qualified Life Determinations, Developed Initial
Preventive Maintenance Intervals and Configuration Controls tied to EQ (Raychem,
Limitorque, Terminal Blocks, etc.), Region III Inspection Lead – 1982-1993
4. Bert Yates 4
Generic Letter 88-20 IPE and IPEEE Submittal Lead – 1988-1993
Human Error Analysis, Electrical Equipment HVAC Dependency, Containment Ultimate
Strength Interface with Bechtel Corp., Wrote “Bad Actor” Relay Seismic Report
River Bend
Regulatory Guide Position Development; Corrected Emergency Diesel Generator Loading and
Radiological Dose Assessment Chi/Q Work in Initial River Bend Operating License (OL)
Application (FSAR) 1980-1982
Work History
June 1980 – April 1982 Gulf States Utilities
River Bend Nuclear Station (BWR)
Initial Plant Licensing
April 1982 – November 2015 Ameren Missouri
Callaway Plant (PWR)
Initial and Ongoing Plant Licensing, Equipment
Qualification
1980-1982 Assistant Engineer, Gulf States Utilities (River Bend)
1982-1985 Assistant Engineer, Union Electric Company (Callaway)
1985-1991 Engineer, Union Electric Company (Callaway)
Callaway Environmental and Seismic Qualification Lead Engineer – 1982-1992
1992-2001 Senior Engineer, Union Electric Company (Callaway)
Callaway Licensing Lead Engineer – 1993-2015
2001-2007 Consulting Engineer, Union Electric Company (Callaway)
2007-2015 Principal Engineer, Ameren Missouri (Callaway)
5. Bert Yates 5
Education
Bachelor of Science, Nuclear Engineering, Summa Cum Laude, 1980
University of Missouri – Rolla
Applications of Reliability and Risk Analysis with Emphasis on Nuclear Power Plants, George
Washington University, October 1980
Nuclear Power Reactor Safety Course, M.I.T., July 1981
Westinghouse PWR Information Course, July 1982
Nuclear EQ Seminar, Wyle Labs, June 1982
Westinghouse Station Nuclear Engineer, October 1983
Seismic Qualification Users Group Relay Evaluation Training Course, November 1992
Other
EPRI EQ Advisory Group and EPRI First Use Award
Licensing Chairman of PWR Owners Group 2007-2009 (major projects included PAMS
Relaxation, MODE 4 End State)
Technical Specification Task Force 2007-2009 (representing Westinghouse NSSS plants)
NEI TIP Award for UHS Re-Analysis, 2015
35+ years nuclear power plant experience
