L-2022-073, Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004

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Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004
ML22123A231
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 05/03/2022
From: Lesniak T
Florida Power & Light Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML22123A230 List:
References
L-2022-073 51-9348245-000
Download: ML22123A231 (186)
v • d • e


Text

Official Use Only - Proprietary Information May 3, 2022 L-2022-073 10 CFR 50.90 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D C 20555-0001 RE: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Subsequent Renewed Facility Operating License DPR-31 and DPR-41 Turkey Point Units 3 & 4 Diversity and Defense-In-Depth Evaluation (03), Framatome Document No. 51-9324096-004

Reference:

1. NRC Standard Review Plan Branch Technical Position 7-19, "Guidance for Evaluation of Defense-In-Depth and Diversity to Address Common Cause Failure Due to Latent Design Defects in Digital Safety Systems," Revision 8, dated January, 2021 .

Florida Power and Light (FPL) hereby submits for NRC review, the enclosed Defense-in-Depth and Diversity (D3) Evaluation for Turkey Point Units 3 and 4 (Turkey Point). As discussed during an April 13, 2022 pre-application meeting (ADAMS Accession No. ML22102A198), the D3 evaluation is being submitted in advance of FPL's proposed Reactor Protection System (RPS), Engineered Safety Feature Actuation System (ESFAS) and Nuclear Instrumentation System (NIS) Digital Instrument and Control (l&C)

Modernization license amendment request (LAR) for Turkey Point. FPL plans to submit the LAR in the second quarter of 2022.

In Reference 1, the NRC requires licensees to provide a D3 assessment of the proposed digital l&C system which demonstrates that any vulnerabilities to common -cause failures have been adequately addressed .

In the enclosed D3 assessment, FPL has evaluated for defense-in-depth and diversity, the applicable design basis events identified in the Turkey Point Updated Final Safety Analysis Report (UFSAR) . of this letter contains an affidavit from Framatome, Inc., (Framatome), the owner of the D3 Evaluation in Attachment 3, which supports a request for withholding from public disclosure pursuant to 10 CFR 2.390(a)(4). The affidavit sets forth the basis on which the information may be withheld from public disclosure by the Nuclear Regulatory Commission (Commission) and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.390 of the Commission's regulations. Accordingly ,

FPL requests that the information wh ich is proprietary to Framatome be withheld from publ ic disclosure pursuant to 10 CFR 2.390(a)(4). Correspondence with respect to the proprietary aspects of this information or the supporting Framatome affidavit should be addressed to Mr. Phillip Opsal, Manager, Product Licensing for Framatome, 3315 Old Forest Road, Lynchburg, Virginia 24501. Attachment 2 contains Framatome Document No. 51-9348245-000, which is the redacted (non-proprietary) version of the D3 Evaluation . Attachment 3 contains Framatome Document No. 51-9324096-004, wh ich is the proprietary version of the D3 Evaluation . Attachment 3 may not be reproduced or copied in whole or in part, shall not be furnished to others without the express written consent of Framatome, and is not to be used in any way which is or may be detrimental to Framatome. Attachment 3 and any copies that may have been made must be returned to Framatome upon request. Attachments 1 and 2 are suitable for public dissemination.

Florida Power & Light Company 9760 SW 344th Street, Homestead, FL 33035 Official use Only - Proprietary Information When Attachment 3 to this document is removed, this document is decontrolled.

Official use Only - Proprietary Information Turkey Point Nuclear Plant L-2022-073 Docket Nos. 50-250 and 50-251 Page 2 of 2 This letter contains no regulatory commitments.

Should you have any questions regarding this submission, please contact Mr. Michael J. Davis, Fleet Licensing Manager, at 319-851-7032.

Gernt~,Regulatory Affairs Florida Power & Light cc: USNRC Regional Administrator, Region II USNRC Project Manager, Turkey Point Nuclear Plant USNRC Senior Resident Inspector, Turkey Point Nuclear Plant Ms. Cindy Becker, Florida Department of Health (Attachments 1 and 2 only)

Attachments

1. Affidavit for Attachment 3 to this letter: Florida Power and Light Turkey Point Unit 3 & 4 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004
2. Florida Power and Light Turkey Point Unit 3 & 4 Diversity and Defense-In-Depth Evaluation (D3),

Framatome Document No. 51-9348245-000 (Non-Proprietary Version)

3. Florida Power and Light Turkey Point Unit 3 & 4 Diversity and Defense-In-Depth Evaluation (D3),

Framatome Document No. 51-9324096-004 (Proprietary Version)

Official use Only - Proprietary Information When Attachment 3 to this document is removed, this document is decontrolled.

ATTACHMENT 1:

Affidavit for Attachment 3: Florida Power and Light Turkey Point Unit 3 & 4 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9324096-004

AFFI DAVIT

1. My name is Philip A. Opsal. I am Manager, Product Licensing for Framatome Inc. (formally known as AREVA Inc.), and as such I am authorized to execute this Affidavit.
2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
3. I am familiar with the Framatome information contained in Framatome Document No. 51-9324096-004, Diversity and Defense-In-Depth Evaluation Florida Power &

Light Co. Turkey Point Unit 3 & 4 Digital Modernization. Information contained in this Document has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.

4. This Document contains information of a proprietary and confidential nature and is of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in this Document as proprietary and confidential.
5. This Document has been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in this Document be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding f rom disclosure is requested qualifies under 10 CFR 2.390(a)(4) Trade secrets and commercial or financial information.
6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:

(a) The information reveals details of Framatomes research and development plans and programs or their results.

(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.

(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.

(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.

(e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.

The information in this Document is considered proprietary for the reasons set forth in paragraphs 6(b), 6(d), and 6(e) above.

7. In accordance with Framatomes policies governing the protection and control of information, proprietary information contained in this Document has been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on April 27, 2022.

Philip A. Opsal

ATTACHMENT 2:

Florida Power and Light Turkey Point Unit 3 & 4 Diversity and Defense-In-Depth Evaluation (D3), Framatome Document No. 51-9348245-000 (Non-Proprietary Version)

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Framatome Inc.

ENGINEERING INFORMATION RECORD Document No.: 51 - 9348245 - 000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Page 1 of 180

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Safety Related? YES NO Does this document establish design or technical requirements? YES NO Does this document contain assumptions requiring verification? YES NO Does this document contain Customer Required Format? YES NO Signature Block P/LP, Pages/ s Name and R/LR, M, Prepared/Reviewed/

Title/Discipline Signature A-CRF, A Date Approved or Comments Jerry Mauck J MAUCK LP All Licensing Engineer 4/28/2022 Ted Quinn T QUINN P All Licensing Engineer 4/28/2022 Taha AbdelNaeem TI ABDELNAEEM LR All 4/28/2022 Project Lead/Technical Lead John DiBartolomeo T QUINN R All Independent Design Review 4/28/2022 (Delegated to Ted Quinn per email)

Brian Haynes BM HAYNES A All Licensing Manager 4/29/2022 Georgia Dikeakos G DIKEAKOS A All Engineering Manager 4/29/2022 Note: P/LP designates Preparer (P), Lead Preparer (LP)

M designates Mentor (M)

R/LR designates Reviewer (R), Lead Reviewer (LR)

A-CRF designates Project Manager Approver of Customer Required Format (A-CRF)

A designates Approver/RTM - Verification of Reviewer Independence N/A if not applicable Project Manager Approval of Customer References (N/A if not applicable)

Name Title (printed or typed) (printed or typed) Signature Date Ron Jaworowski Project Manager RO JAWOROWSKI 4/29/2022 Page 2 of 180

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Record of Revision Revision Pages/Sections/

No. Paragraphs Changed Brief Description / Change Authorization 000 Entire document Non-Proprietary version of 51-9324096-004.

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Table of Contents 1 EXECUTIVE

SUMMARY

............................................................................................................ 8 2 TURKEY POINT UNIT 3&4 DIGITAL UPGRADE PROJECT .................................................... 10 2.1 Scope ........................................................................................................................... 10 2.2 Objectives ..................................................................................................................... 11 2.3 Regulatory Position....................................................................................................... 11 Page 4 of 180

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Table of Contents (continued)

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization 1 EXECUTIVE

SUMMARY

The Turkey Point Nuclear Power Plant Unit 3&4 Reactor Protection System (RPS)/Engineered Safety Features Actuation System (ESFAS)/Nuclear Instrumentation System (NIS) upgrade project is currently being completed by Framatome and Florida Power and Light (FPL) under Contract [1]. The digital upgrade replicates the safety functions currently implemented on the analog equipment. The upgrade design and configuration are based on digital control products designed and manufactured by Framatome and its industry partners. However, the installation of digital-based RPS/ESFAS/NIS systems presents a concern that a postulated Software Common Cause Failure (SWCCF) of a common digital safety platform might propagate across multiple trains and channels such that it defeats the required safety functions. The Diversity and Defense-in-Depth (D3) assessment documented herein demonstrates that there will be sufficient defense-in-depth and diversity to cope with a postulated SWCCF to the Triconex PLC (Tricon) digital platform in the RPS/ESFAS/NIS systems. [

]

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization In summary, this Turkey Point Unit 3&4 D3 assessment has followed the applicable guidance provided in BTP 7-19, Rev 8 [3]. Solutions for all transients and accidents when postulating a SWCCF to the RPS/ESFAS Tricon digital platform has been provided as discussed in Sections 4 and 5 of this report. The conclusion section (6) of this report reiterates these findings and provides more details regarding diversity and defense-in-depth.

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization 2 TURKEY POINT UNIT 3&4 DIGITAL UPGRADE PROJECT 2.1 Scope With the advent of digital technology being implemented as part of safety systems (e.g., the Reactor Protection System and Engineered Safeguard Features Actuation System) in both operating and plants under construction, a concern has been identified that a postulated SWCCF of these software-based safety platforms could propagate across multiple trains and channels in a manner that would defeat the required safety functions. The NRC regulatory guidance for this concern is detailed in BTP 7-19 [3]. FPL is implementing digital technology in the Turkey Point Unit 3&4 RPS and ESFAS. Therefore, Framatome conducted a D3 evaluation and provides documented results herein demonstrating that there will be sufficient defense-in-depth and diversity to cope with a postulated SWCCF to the RPS/ESFAS software based digital platforms.

The guidance within BTP 7-19 [3] is discussed below and demonstrates that, for the replacement digital system, the acceptance criteria of BTP 7-19 [3] are met. [

]

The BTP 7-19 [3] guidance and the assessment process are discussed in the following sections of this report.

[

]

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization The Diversity and Defense-in-Depth Evaluation is a SAFETY-RELATED document under the Framatome and Turkey Point Unit 3&4 Quality Programs.

2.2 Objectives The objective of the D3 assessment is to eliminate potential vulnerabilities of the RPS/ESFAS upgrade to a postulated RPS/ESFAS SWCCF within these systems by [

]

2.3 Regulatory Position The Turkey Point Unit 3&4 RPS/ESFAS upgrade project is being designed and implemented to meet current regulatory requirements and guidance. [

]

Based on experience in previous detailed reviews, the NRC staff has established acceptance guidelines for D3 assessments as described in BTP 7-19 [3]. Further guidance was established through the efforts of the Digital Instrumentation and Control (DI&C) Task Working Group No. 2 on D3 with the development of DI&C-ISG-02

[7], Task Working Group No. 2: Diversity and Defense-in-Depth Issues Interim Staff Guidance, Revision 2.

This interim staff guidance (ISG) was developed with extensive review of D3 issues including both internal review within the NRC and external input through public meetings with representatives from industry, vendors, and the public. In addition, NUREG/CR-6303 [6] was published to provide guidance on certain D3 concerns such as diversity. In summary, while the NRC considers a software common cause failure (SWCCF) in digital systems to be beyond design basis, nuclear Power Plants (NPPs) must be protected against the effects of PIEs with a concurrent SWCCF in the digital protection system.

The following Points 1, 2, 3, and 4 of the NRC position in SRM-SECY-93-087 [8] apply to digital system modifications within operating and new plants, and were used by NRC to develop the D3 assessment guidelines in BTP 719 [3]:

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1. The applicant shall assess the defense-in-depth and diversity of the proposed instrumentation and control system to demonstrate that vulnerabilities to common-mode failures have adequately been addressed.
2. In performing the assessment, the vendor or applicant shall analyze each postulated common-mode failure for each event that is evaluated in the accident analysis section of the safety analysis report (SAR) using best-estimate methods. The vendor or applicant shall demonstrate adequate diversity within the design for each of these events.
3. If a postulated common-mode failure could disable a safety function, then a diverse means, with a documented basis that the diverse means is unlikely to be subject to the same common-mode failure, shall be required to perform either the same function or a different function. The diverse or different function may be performed by a non-safety system if the system is of sufficient quality to perform the necessary function under the associated event conditions.
4. A set of displays and controls located in the main control room shall be provided for manual, system-level actuation of critical safety functions and monitoring of parameters that support the safety functions.

The displays and controls shall be independent and diverse from the safety computer system identified in items 1 and 3 above.

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization The NRC identified four echelons of defense in NUREG/CR-6303 [6]:

Echelon 1

  • Control System - The control system echelon usually consists of equipment that is not safety-related, that is used in the normal operation of an NPP, and routinely prevents operations in unsafe regimes of NPP operations.

Echelon 2

  • Reactor Trip System - The Reactor Trip System (RTS) echelon consists of safety-related equipment designed to reduce reactivity rapidly in response to an uncontrolled excursion.

Echelon 3

  • Engineered Safety Features Actuation System (ESFAS) - The ESFAS echelon consists of safety-related equipment that removes heat or otherwise assists in maintaining the integrity of the three physical barriers to radioactive release (cladding, vessel and reactor coolant system pressure boundary, and primary containment) and the logic components used to actuate this safety-related equipment, usually referred to as the ESF Actuation System (ESFAS), and controls.

Echelon 4

  • Monitoring and Indicator System - The monitoring and indicator system echelon consists of sensors, safety parameter displays, data communication systems, and independent manual controls relied upon by operators to respond to NPP operating events.

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization SRP Chapter 18, Appendix A, Section 1A [10] states in part:

The basis for the specific time margin used in the analysis should be justified and documented.

Insights from the HFE program, especially the OER and Human Reliability Analysis, should be used. The identification of potential errors, error detection methods, and error recovery paths in event trees may be used to provide estimates of how much margin should be added to the operator response time estimates.

For complex situations and for actions with limited margin, such as less than 30 minutes between time available and time required, a more focused staff review will be performed.

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization 4.3 Spurious RPS/ESFAS Actuations NUREG-800, Chapter 7, BTP 7-19, [3] states the following concerning postulated spurious actuations caused by a SWCCF:

The evaluation of potential spurious operations is an important part of the overall D3 assessment for a proposed DI&C system to ensure that spurious operations do not lead to events with unacceptable consequences. Although a spurious operation is not always anticipated, it can be detected because this type of failure is normally self-announcing through instrumentation on the actuated system. However, in some circumstances a spurious operation may not occur until a particular signal or set of signals is present. In these cases, rather than occurring immediately upon system startup, the spurious operation would occur only under certain plant conditions. Such a spurious operation is still self-announcing (by the actuated system), even if failure did not occur on initial test Page 110 of 180

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization 7 ABBREVIATIONS AND ACRONYMS Acronyms/Abbreviations Description 2-o-o-4 Two out of four 2-o-o-3 Two out of three A/D Analog to Digital ADV Atmospheric Dump Valves AECL Atomic Energy of Canada Limited AFW Auxiliary Feedwater AMSAC ATWS Mitigating System Actuation Circuitry ANS American Nuclear Society ANSI American National Standards Institute AOO Anticipated Operational Occurrence ASD Atmospheric Steam Discharge ASME American Society of Mechanical Engineers ATWS Anticipated Transient Without Scram B&PV Boiler and Pressure Vessel BE Best Estimate BIT Boron Injection Tank BOL Beginning of Life BTP Branch Technical Position CCF Common Cause Failure CCW Component Cooling Water CFCU Containment Fan Coil Unit CFR Code of Federal Regulations CLOF Complete Loss of Flow CR Control Room CS Containment Spray CVCS Chemical and Volume Control System D/A Digital to Analog D3 Defense-In-Depth and Diversity Evaluation

[ ] [ ]

DBA Design Basis Accident

[ ] [ ]

DI&C Digital Instrumentation and Control DNB Departure from Nucleate Boiling DNBR Departure from Nucleate Boiling Ratio EAB Exclusion Area Boundary Page 165 of 180

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Acronyms/Abbreviations Description ECCS Emergency Core Cooling System EDG Emergency Diesel Generator EMC Electromagnetic Compatibility EMI/RFI Electromagnetic Interference/Radio Frequency Interference EOL End of Life EOP Emergency Operations Procedure EPRI Electric Power Research Institute EPU Extended Power Uprate ESFAS Engineered Safety Features Actuation System ETA External Termination Assembly FCG Fatigue Crack Growth FPL Florida Power and Light Framatome Framatome USA FT Foot FWLB Feedwater Line Break GDC Generic Design Criteria GL Generic Letter GPM (gpm) Gallons Per Minute HFE Human Factors Engineering HFP Hot Full Power HHSI High Head Safety Injection HVAC Heating, Ventilation and Air Conditioning I&C Instrumentation and Control I/A Intelligent Automation - Foxboro-Schneider ICW Intake Cooling Water IEC International Electrotechnical Commission IEEE Institute of Electrical and Electronic Engineers ISG Interim Staff Guidance LBB Leak-Before-Break LBLOCA Large Break LOCA LCO Limiting Condition of Operation LHSI Low Head Safety Injection LOCA Loss of Coolant Accident LOL Loss of Load LONF Loss of Normal Feedwater LOOP Loss of Offsite Power LPZ Low Population Zone Page 166 of 180

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Acronyms/Abbreviations Description MCB Main Control Board MCC Motor Control Center MCR Main Control Room mDNBR Minimum Departure from Nuclear Boiling Ratio MFW Main Feedwater MG Motor Generator MOV Motor Operated Valve MSIV Main Steam Isolation Valve MSLB Main Steam Line Break MSSV Main Steam Safety Valve MSS Main Steam System MTC Moderator Temperature Coefficient MTTF Mean-Time-To-Failure NGAID Next Generation Differential Analog Input NGDO Next Generation Digital Output NIS Nuclear Instrumentation System NPP Nuclear Power Plant NR Narrow Range NRC United States Nuclear Regulatory Commission NSR Non-Safety Related OTT Overtemperature Delta-T PA Postulated Accident PCT Peak Clad Temperature PFD Probability of Failure on Demand PIE Postulated Initiating Event PLC Programmable Logic Controller PLOF Partial Loss of Flow PMP Project Management Plan PORV Pilot Operated Relief Valve (definition); or Power Operated Relief Valve PQP Project Quality Plan PRA Probabilistic Risk Analysis PRMS Process Radiation Monitoring System PRZ Pressurizer PSIG Pounds Per Square Inch Gage PSV Pressurizer Safety Valve Turkey Point Unit 3&4 Plant Turkey Point Nuclear Plant Unit 3&4 QA Quality Assurance Page 167 of 180

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Acronyms/Abbreviations Description QSPDS Qualified Safety Parameter Display System RCCA Rod Cluster Control Assembly RCP Reactor Coolant Pump RCS Reactor Coolant System RG Regulatory Guide RHR Residual Heat Removal RPS Reactor Protection System RTB Reactor Trip Breaker RTP Rated Thermal Power RTS Reactor Trip System RWAP Rod Withdrawal at Power RWSC Rod Withdrawal Sub Critical RWST Refueling Water Storage Tank SAR Safety Analysis Report SBLOCA Small Break LOCA SCMP Software Configuration Management Plan SDP Software Development Plan SER Safety Evaluation Report SG Steam Generator SGTR Steam Generator Tube Rupture SGTR Steam Generator SI Safety Injection SIA Structural Integrity Associates SMT Surface Mount Technology SQAP Software Quality Assurance Plan SR Surveillance Requirement SRP Standard Review Plan Std Standard SVDU Flat Panel Display - Safety Video Display Unit SVVP Software Verification and Validation Plan SWCCF Software Common Cause Failure SWGR Switchgear Tavg Temperature-Average TCM Tricon Communication Module TI Test Interval TLAA Time-Limited Aging Analysis TMR Triple Modular Redundant Page 168 of 180

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Acronyms/Abbreviations Description TR Topical Report (non-EPRI references); or Technical Report Tricon Triconex PLC TS Technical Specifications TSAP Test Specimen Application Program UF Under Frequency UFSAR Updated Final Safety Analysis Report UV Under Voltage V&V Verification and Validation VAC Volt AC VCT Volume Control Tank WR Wide Range 8 GLOSSARY OF TERMS The following definitions are provided for special terms used in this document.

Term Definition Anticipated operational Those conditions of normal operation which are expected to occur one or more times occurrence (AOO) (10 CFR Part during the life of the nuclear power unit and include but are not limited to loss of the 50 Appendix A) turbine generator set, isolation of the main condenser, and loss of offsite power.

Common-mode failure (CMF) Causally related failures of redundant or separate equipment. CMF embraces all (NUREG/CR-6303) causal relations, including severe environments, design errors, calibration and maintenance errors, and consequential failures.

Design basis accident (DBA) Occurrences that are not expected to occur but are postulated because their (NUREG/CR 6303) consequences would include the potential for the release of significant amounts of radioactive material.

Diverse component or system A component or system that duplicates the function of another component or system (IEC 880) by employing different physical construction or different principles of operation.

Diversity & Defense-in-Depth A concentric arrangement of protective barriers or means, all of which must be (D3) breached before a hazardous material or dangerous energy can adversely affect human beings or the environment.

Echelons of defense Specific applications of the principle of defense-in-depth to the arrangement of (NUREG/CR 6303) instrumentation and control systems attached to a nuclear reactor for the purpose of operating the reactor or shutting it down and cooling it.

Redundant component or system A piece of equipment or system that duplicates the essential function of another piece (IEEE 379) of equipment or system to the extent that either may perform the required function, regardless of the state of operation or failure of the other.

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Document No.: 51-9348245-000 Diversity and Defense-in-Depth Evaluation Florida Power & Light Co. Turkey Point Unit 3&4 Digital Modernization Term Definition Single Failure Criterion (IEEE The safety systems shall perform all required safety functions for a design basis event 379) in the presence of the following:

  • Any single detectable failure within the safety systems concurrent with all identifiable but non-detectable failures.
  • All failures caused by the single failure.
  • All failures and spurious actions that cause, or are caused by, the design basis event requiring the safety function.
  • The single failure could occur prior to, or at any time during, the design basis event for which the safety function is required to function.

9 REFERENCES Page 170 of 180

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