L-2023-004, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Huma Factors Results
ML23017A226 | |
Person / Time | |
---|---|
Site: | Turkey Point ![]() |
Issue date: | 01/17/2023 |
From: | Strand D Florida Power & Light Co |
To: | Office of Nuclear Reactor Regulation, Document Control Desk |
Shared Package | |
ML23017A225 | List: |
References | |
L-2023-004 | |
Download: ML23017A226 (1) | |
Text
L-2023-004 10 CFR 50.90 Framatome Inc. Proprietary (Not proprietary when separated from Attachments 1 through 5)
January 17, 2023 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington DC 20555-0001 RE: Turkey Point Nuclear Plant, Unit 3 and 4 Docket Nos. 50-250 and 50-251 Renewed Facility Operating Licenses DPR-31 and DPR-41 Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of Human Factors Results Summary Reports and System Level Failure Modes and Effects (FMEA) Analysis
References:
- 1. Florida Power & Light Company letter L-2022-120, Turkey Point Nuclear Plant, Units 3 & 4, License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project, July 30, 2022 (ADAMS Accession No. ML22213A045)
- 2. Florida Power & Light Company letter L-2022-166, Turkey Point Nuclear Plant, Units 3 & 4, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project, October 5, 2022 (ADAMS Accession No. ML22278A076)
Per Reference 1, and pursuant to 10 CFR Part 50.90, Florida Power & Light Company (FPL) submitted a request to amend Subsequent Renewed Facility Operating Licenses DPR-31 and DPR-41 for Turkey Point Nuclear Plant Units 3 and 4 (Turkey Point), respectively. The proposed license amendments replace the Reactor Protection System (RPS), Engineered Safety Features Actuation System (ESFAS), and Nuclear Instrumentation System (NIS) with digital systems that are based on the Framatome Tricon Programmable Logic Controller (PLC) Version 10 digital based platform.
In Reference 2, FPL provided supplemental information in support of the license amendment request and agreed to submit by January 16, 2023, additional documents the NRC determined was necessary to complete its acceptance review. This letter provides the following attachments:
- 1. Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS Results Summary Report
- 2. System Level Failure Modes and Effects Analysis In addition, the following documents are available for NRC viewing on the NextEra Online Reference Portal.
As discussed on January 17, 2023, with NRC Project Manager, Michael L. Marshall Jr., versions of these documents will be submitted on the docket within 30 days of this letter.
- 1. Functional Requirements Analysis, Functional Allocation and Task Analysis - RPS / ESFAS / NIS and Distributed Control System (DCS) Results Summary Report
- 2. Functional Requirements Analysis, Functional Allocation and Task Analysis Diverse Actuation System (DAS) and Distributed Control System (DCS) Results Summary Report
- 3. Operating Experience Review Results Summary Report Florida Power & Light Company 9760 SW 344th Street, Homestead, FL 33035
Turkey Point Nuclear Plant L-2022-004 Docket Nos 50-250 and 50-251 Page 2 of 2 Attachments 1 and 2 contain information that Framatome, Incorporated, considers to be proprietary in nature. Pursuant to 10 CFR 2.390(a)(4), FPL requests that the proprietary information be withheld from public disclosure. The request is supported by two affidavits signed by Framatome, Incorporated, the owner of the information, in Attachment 3. The affidavits set 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. Correspondence with respect to the proprietary aspects of this information or the supporting Framatome affidavits should be addressed to Mr. Phillip Opsal, Manager, Product Licensing for Framatome, 3315 Old Forest Road, Lynchburg, Virginia 24501.
Attachments 4 and 5 contain the redacted versions of Attachments 1 and 2.
This supplement does not alter the conclusions provided in Reference 1 that the proposed change does not involve a significant hazards consideration pursuant to 10 CFR 50.92, and that there are no significant environmental impacts associated with the proposed change.
This letter contains no new or revised regulatory commitments.
Should you have any questions regarding this submission, please contact Mr. Kenneth Mack, Fleet Licensing Manager, at 561-904-3635.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the 17th day of January 2023.
Sincerely, Dianne Strand Dianne Strand General Manager, Regulatory Affairs Attachments (5) 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
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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. 51-9355272-002, Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS). 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 from 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(c), 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 January 9, 2023.
Philip A. Opsal Manager, Product Licensing Framatome Inc.
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. 51-9330940-001, FPL Digital Modernization Project (F.505454)
FMEA - RPS/ESFAS/NIS. 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 from 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(c), 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 January 17, 2023.
Philip A. Opsal Manager, Product Licensing Framatome Inc.
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Framatome Inc.
RESULTS
SUMMARY
REPORT Document No.: 51 - 9355272 - 002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS Proprietary information contained within has been placed in brackets.
The technical content was not changed as attested to by the following individuals:
Preparer: Tom Geary Reviewer: Phil Opsal Approver: Brian Haynes Signature and Date Signature and Date Signature and Date Page 1 of 41
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS 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 Pages/Sections Name and P/LP, R/LR, M, Signature Date Prepared/Reviewed/
Title/Discipline A-CRF, A Approved or Comments Thomas Geary TB GEARY 1/7/2023 LP All Project Engineer Jacek Nowakowski JK NOWAKOWSKI 1/7/2023 LR All Project Engineer Brian Haynes BM HAYNES Project Engineering 1/8/2023 A All Manager 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 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 1/8/2023 Page 2
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS Record of Revision Revision Pages/Sections/
Brief Description / Change Authorization No. Paragraphs Changed 000 All Initial issuance 001 All Comments from F.505454-OUT-0763-000 incorporated Changed the IOS reference for DIHA05 and DIHA06 from IOS17 to 002 2.4, Table 2-3 IOS16.
Updated the description for PIHA02.
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS Table of Contents Page
1.0 INTRODUCTION
........................................................................................................................... 6 1.1 Background ....................................................................................................................... 6 1.2 Purpose and Approach...................................................................................................... 7 1.3 Scope ................................................................................................................................ 7 1.4 Relationships Between HFE documents ........................................................................... 7 1.5 Terms and Definitions ....................................................................................................... 8 1.6 Acronyms ........................................................................................................................ 10 2.0 TIHA RESULTS .......................................................................................................................... 12 2.1 Applicable OEs ................................................................................................................ 12 2.2 New and Modified IHAs ................................................................................................... 13 2.2.1 Risk-Important Human Actions ......................................................................... 13 2.2.2 Deterministically Identified Important Human Actions ...................................... 18 2.2.3 Potential Important Human Actions (PIHA) ...................................................... 21 2.3 New and Modified IOS .................................................................................................... 21 2.4 Treatment of IHAs in the HFE Program .......................................................................... 25
3.0 CONCLUSION
S .......................................................................................................................... 39
4.0 REFERENCES
............................................................................................................................ 40 Page 4
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS List of Tables Page Table 2-1: Operating Experience 032 Summary Table ................................................................................... 13 Table 2-2: Important Operating Sequences potentially modified due to the RPS/ESFAS/NIS upgrade ................................................................................................................................................ 22 Table 2-3: TIHA Master Table for RPS/ESFAS/NIS ........................................................................................ 27 List of Figures Page Figure 1-1: Relationships between HFE Documents ......................................................................................... 8 Figure 2-1: TIHA Development process ............................................................................................................. 12 Figure 2-2: Protection System Component Replacement Scope (Reference 3) ......................................... 15 Page 5
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1.0 INTRODUCTION
1.1 Background
Florida Power and Light (FPL) has contracted Framatome to provide digital system replacements for safety related systems at Turkey Point Plant (PTN) Units 3&4. Per DI&C-ISG-06 Section B.1.4 (Reference 1) a human factors assessment is required when a licensee is changing the Main Control Room (MCR) or other interface with which operations and maintenance personnel will be interacting. The Human Factors Engineering (HFE)
Plan (Reference 2) identifies the HFE activities for the PTN 3&4 Safety Related (SR) Digital Modernization Project (hereafter the project).
Specifically, this Results Summary Report (RSR) applies to the Reactor Protection System (RPS), Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and related Distributed Control System (DCS) interface (hereafter referred as RPS/ESFAS/NIS) modernization. The scope of the modification includes installation of a Framatome Tricon Programmable Logic Controller (PLC), Version 10 digital based platform in the systems (Reference 3).
As a part of the modernization, several significant physical changes are being made to the MCR. Some of these changes are described in the MCR Design Change Description (Reference 8) but all HSI changes associated with this scope can be summarized as follows:
- Replacement of the existing NIS indications and controls located in the NIS cabinets with four touchscreen Safety Video Display Units (SVDUs). The SVDUs will become the primary interface to the RPS and ESFAS protection systems and NIS controls where critical plant parameters and system status information is displayed. Due to the installation of a Tricon peer-to-peer network, selected information from the voter trains will be available on the associated protection channel SVDUs. Channel bypass and Resistance Temperature Detector (RTD) calibration previously accomplished with Eagle 21 man-machine interface will be implemented using Tricon and SVDU.
- Removal and replacement of existing analog instruments currently displayed on vertical panel C03 with six touchscreen non-safety related Video Display Units (VDUs).
- Relocation of the existing reactor protection logic status lights on vertical panel C05; this logic status information will be available on the SVDUs in the NIS cabinets and/or the VDUs in the C03 panel. A new status light is added in panel C03 to alert the operators of any change in the protection logic status lights.
- Numerous annunciators are being added, spared, and re-configured to provide both the required process alarms as well as diagnostic trouble alarms for all systems. The DCS is being utilized to monitor the health of the Tricon systems and will actuate new trouble annunciators on the G panel.
Included with the RPS/ESFAS/NIS scope of the Digital Modernization Project, the DCS will also be modified.
These modifications are described briefly below (Reference 4):
- Addition of Tricon-DCS communications interfaces and associated data, graphics and logic.
- Implementation of process parameter indications required to be diverse from the Tricon platform.
- Relocation of auxiliary nuclear instrumentation functions to the DCS: new controls and indications associated with NIS source range audio count rate, NIS power range detector comparator and defeat, and NIS power range power mismatch bypass functions previously in cabinet QR62 are added to the DCS.
- Addition of a Diverse Actuation System (DAS)
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS The NIS, previously a standalone system implemented in 4 channel divisions, is included in the protection channel sets that perform logic, setpoint comparison, and command features based on inputs from Nuclear Instrument (NI) measurement and signal conditioning components utilizing the existing detectors and cabling (Reference 3). The activities presented in this RSR have been performed following the methodologies described in the HFE Analysis Implementation Plan (IP) for the systems considered in the License Amendment Request (LAR); the HFE Analysis IP (Reference 10) was developed using guidance in NUREG-0711 (Reference 9).
1.2 Purpose and Approach The purpose of this RSR is to document the results of the Treatment of Important Human Actions (TIHA) for the modernization of the RPS/ESFAS/NIS.
The main objective of the TIHA element is to identify new or modified important human actions derived from the modification and provide them a special consideration when addressing the applicable HFE elements. For that purpose, the general approach followed to perform TIHA was:
- 1. Review of the RPS/ESFAS/NIS modernization documentation (References 3, 8 and 23) to identify if existing IHAs are modified, or new IHAs are identified.
- 2. Identify current Important Human Actions (IHAs) applicable to the modernization of the RPS/ESFAS/NIS and the consequent modifications on the DCS.
- 3. Evaluate how the affected IHAs are addressed in the rest of the HFE Program.
The methodology, processes and activities followed to implement TIHA are described in the HFE Analysis Implementation Plan (Reference 10).
1.3 Scope The scope of TIHA is established in the HFE Analysis Implementation Plan (Reference 10) and is focused on the Important Human Actions (IHAs) and related Important Operating Sequences (IOSs) associated with the RPS/ESFAS/NIS design modifications described in Section 1.1.
As described in Section 1.5, there are differences between new and modified concepts derived from the digital modification process, which are described in the performance of the TIHA process (IHAs, IOSs, etc.). Refer to Section 1.5 for the definition of these terms.
1.4 Relationships Between HFE documents This RSR is hierarchically dependent on the HFE Analysis Implementation Plan (Reference 10) and at the same level as the HFE Verification and Validation (V&V) RSRs and the HSI Design and HSI Design RSR that will be developed in subsequent phases of the project. Results provided in this RSR serve as inputs for the HSI Design activities, which in turn, are inputs for the HFE V&V RSR of the RPS/ESFAS/NIS. Because of the iterative nature of the HFE process, conclusions drawn from the HFE V&V RSR may impact the system HSI Design and/or this HFE Analysis RSR. Additional information on how this document may impact HSI design and HFE V&V activities can be found in the HSI Design IP (Reference 26) and HFE V&V IP (Reference 25) respectively.
The relationship between this document and other HFE deliverables is shown in Figure 1-1, where this document is represented under the category of HFE Analysis RSRs. The overall project deliverables structure for the entire HFE Program can be observed in the HFE Plan (Reference 2).
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS Figure 1-1: Relationships between HFE Documents HFE PLAN HFE HSI DESIGN ANALYSIS HFE V&V IP IP IP HFE HFE V&V ANALYSIS HSI DESIGN RSRs RSRs HSI DESIGN RSR 1.5 Terms and Definitions The following terms and definitions apply to this plan:
- 1. Human Factors Engineering (HFE) - Application of methods and knowledge about human capabilities and limitations to designing and modifying the plant, its systems and equipment to reasonably assure that such design is compatible with the attributes of the personnel who operate, maintain and support them.
- 2. Human-System Interface (HSI) - The point of contact between the human operator and the physical devices.
- 3. Implementation Plan (IP) - Document that describes the proposed methodology for conducting an HFE element, which is reviewed by the Nuclear Regulatory Commission (NRC) Staff to reasonably assure that it will generate acceptable results that satisfy the staffs review criteria.
- 4. Important Human Action (IHA) - Human action most important to safety that meets either risk or deterministic criteria.
- 5. Important Operating Sequence (IOS) - Operating sequence that contains one or more Important Human Actions
- 6. Input - Documents and databases which may be consulted during the corresponding Project HFE Program element performance.
- 7. Modified concept - where concept refers to different items of the analysis (important human action, important operating sequence, etc.). Modified refers to aspects that have changed due to this Design Modifications project.
- 8. New concept - where concept refers to different items of the analysis (important human action, important operating sequence, etc.). New refers to aspects incorporated that did not exist before this Design Modifications project.
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- 9. NUREG - Series Publications of Reports or brochures on regulatory decisions, results of research, results of incident investigations, and other technical and administrative information thar are prepared by the United States NRC Staff or its Contractors.
- 10. Project HFE Program Element / Element - Each of the twelve parts in which a Project HFE Program based on NUREG-0711 (Reference 9) is divided.
- 11. Results Summary Report (RSR) - Document that summarizes the results of a completed HFE element (or activity belonging to an HFE element) and includes the complete results or cites documents/files that contain them.
- 12. Scenario - Operational sequence in which several tasks are performed under certain circumstances and operational condition because of an event or plant mode.
- 13. Step - Each of the parts in which a specific IP methodology is divided to develop it.
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS 1.6 Acronyms AFW Auxiliary Feedwater AP Administrative Procedure D3 Diversity and Defense in Depth DAS Diverse Actuation System DBA Design Basis Accident DIHA Deterministically Identified Important Human Action EOP Emergency Operating Procedure ESFAS Engineered Safety Features Actuation System FPL Florida Power and Light HA Human Action HFE Human Factors Engineering HHSI High Head Safety Injection HRA Human Reliability Analysis HSI Human-System Interface IHA Important Human Action IOS Important Operating Sequence IP Implementation Plan LOCA Loss of Coolant Accident MCB Main Control Board MCR Main Control Room MFW Main Feedwater MSIV Main Steam Isolation Valve MSLB Main Steam Line Break NI Nuclear Instrument NIS Nuclear Instrumentation System OI Operating Instruction PIHA Potential Important Human Actions PLC Programmable Logic Controller PORV Power Operated Relief Valve PTN Turkey Point Plant PZR Pressurizer RCO Reactor Control Operator RCP Reactor Coolant Pump RCS Reactor Coolant System RHR Residual Heat Removal RIHA Risk-Important Human Action RPS Reactor Protection System RSR Result Summary Report RTD Resistance Temperature Detector SBLOCA Small Break Loss of Coolant Accident SBO Station Blackout SG Steam Generator Page 10
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS SGTR Steam Generator Tube Rupture SI Safety Injection SR Safety Related SSGFW Standby Steam Generator Feedwater SVDU Safety Video Display Unit SWCCF Software Common Cause Failure SyRS System Requirement Specification TCA Time Critical Action TIHA Treatment of Important Human Actions TSA Time Sensitive Action UFSAR Updated Final Safety Analysis Report V&V Verification and Validation VDU Video Display Unit Page 11
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS 2.0 TIHA RESULTS TIHA results are obtained following the process depicted in Figure 2-1 and described in the HFE Analysis IP (Reference 10).
Figure 2-1: TIHA Development process Sources for IHAs Step 1:
Identify new/
TCA/TSA modified IHAs Program RIHAs PRA/HRA Deterministic Analyses DIHAs HFE program Step 3:
elements PIHAs TIHA Treatment in the HFE Program Step 2:
Identify new/modified IOSs Results from TIHA include:
- the list of new and modified IHAs;
- the list of new and modified IOSs; and
- how IHAs and/or IOSs are considered during the execution of the rest of the HFE Program activities, as established in the HFE Analysis IP (Reference 10).
These results are described in the following sections.
2.1 Applicable OEs The Operating Experience Review (OER) results provided in the OER RSR (Reference 5), concluded that from all the Operating Experiences (OEs) identified for the project, the following OE should be addressed during the development of the TIHA for RPS/ESFAS/NIS. Below, an explanation of how the OE is addressed is provided:
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS Table 2-1: Operating Experience 032 Summary Table 2.2 New and Modified IHAs IHAs are obtained using a combination of probabilistic and deterministic analyses, and categorized, according to their origin, as Risk-Important Human Actions (RIHA) or Deterministically Identified Important Human Actions (DIHA), respectively. Additionally, the performance of the HFE program elements may result in the identification of IHAs that may have passed unnoticed on previous probabilistic or deterministic analyses. These are called Potential Important Human Actions (PIHA).
The following sub-sections presents the results for each type of IHA.
2.2.1 Risk-Important Human Actions The main impact on [ ] due to the modernization derives from the changes in the MCR vertical panel C03. This panel currently displays analog and digital instrumentation related to (Reference 8):
- Reactor Coolant Pump (RCP) Control and Indication
- Reactor and Reactor Coolant System (RCS) Protection
- Reactor / RCS Monitors
- Reactor Systems Monitoring & Controls
- Steam Generator (SG) Protection Controls As described in the RPS/ESFAS/NIS System Requirement Specification (SyRS) (Reference 3), these are operator interfaces for the existing RPS and ESFAS. This instrumentation will be removed and replaced with six non-safety related VDUs. Some additional instruments will be relocated to facilitate placement of the new VDUs.
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS The existing analog NIS indications and controls will be removed, and a SVDU with touchscreen functionality will be installed in each of the four NIS cabinets (QR59-QR62) behind the reactor control operator (RCO) workstation. The SVDUs will become the primary interface to the RPS and ESFAS protection systems and NIS controls where critical plant parameters and system status information are displayed.
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS Figure 2-2: Protection System Component Replacement Scope (Reference 3)
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS 2.2.2 Deterministically Identified Important Human Actions As described in the HFE Analysis IP (Reference 10), DIHAs are identified as part of the deterministic analyses performed to evaluate plant response under certain transients and postulated accidents. [
]
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS 2.2.3 Potential Important Human Actions (PIHA)
New IHAs that relates to the operation of the RPS/ESFAS/NIS may be identified during the execution of:
- The RPS/ESFAS/NIS during the applicable HFE element activities.
- TIHA for other systems under the project scope, as described in the HFE Plan (Reference 2).
Those IHAs will be coded as PIHAs, as described in the HFE Analysis IP (Reference 10). Those PIHAs will be considered and documented in the corresponding RSR; the final list of IHAs (Table 2-3) will be updated accordingly.
2.3 New and Modified IOS This section summarizes the list of IOSs which were identified together with the IHAs presented in Section 2.2.
The IOSs are codified as described in the HFE Analysis IP (Reference 10) and presented in Table 2-2. This table includes the following information:
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS 2.4 Treatment of IHAs in the HFE Program As described in Section 2.2.1, all the RIHAs identified for the RPS/ESFAS/NIS upgrade are impacted in the same manner: all of them require the monitoring of plant parameters indications which are currently located in MCR vertical panel C03 or the NIS cabinets. These indications are going to be removed and displayed on one of the six VDUs that will be located on C03 or on the SVDUs that will be located on the NIS cabinets. [
]
- the compliance of the new HSI design with HFE principles established in NUREG-0700 (Reference 24) will be verified following the process described in the V&V IP (Reference 25)
- the related IOSs for each RIHA are candidates for HFE validation to evaluate the human performance with the new HSI. IOSs become inputs to the sampling of operational conditions activity from the HFE V&V element, as described in the HFE V&V IP (Reference 25). [
]
DIHAs identified in Section 2.2.2 for the RPS/ESFAS/NIS upgrade are impacted by the project modifications in two ways:
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Document No.: 51-9355272-002 Treatment of Important Human Actions - RPS/ESFAS/NIS and DCS Table 2-3 presents the TIHA Master Table for the RPS/ESFAS/NIS. As described in the HFE Analysis IP (Reference 10), this table [ ]
which are presented in Sections 2.2, 2.3 and 2.4. [
]
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3.0 CONCLUSION
S This RSR documents the results of the TIHA element for the RPS/ESFAS/NIS, as a part of the HFE Analysis phase established in the HFE Plan (Reference 2) for the PTN 3&4 SR Digital Modernization Project. HFE Analysis activities are governed by the HFE Analysis Implementation Plan (Reference 10).
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4.0 REFERENCES
The following documents were used as sources of information for this plan. Unless otherwise stated the Framatome Administrative Procedures (APs) and Operating Instruction (OIs) will be the latest issued revision. For other references, the controlling revision is identified on the Master Configuration List (MCL) or Technical Requirements List (TRL). References identified with an (*) are maintained within the Turkey Point Records System and are not retrievable from Framatome Records Management.
- 1. U.S. NRC Digital Instrumentation and Control Interim Staff Guidance, Licensing Process, DI&C-ISG-06.
- 2. [ ]
- 3. [ ]
- 4. [
]
- 5. [
]
- 6. [
]
- 7. [
]
- 8. [
]
- 9. NUREG-0711, Human Factors Engineering Program Review Model, Revision 3.
- 10. [
]
- 11. *Florida Power and Light, Turkey Point Plant, Time Critical Operator Action Program, Procedure No. 0-ADM-232.
- 12. *Florida Power and Light, Turkey Point Unit 3&4, Post-Initiator Human Reliability Analysis for Turkey Point - Internal Events, Document No. PTN-BFJR-09-013.
- 13. *Florida Power and Light, Turkey Point Unit 3&4, Pre-Initiator Human Reliability Analysis (HRA) for Turkey Point, Document No. PTN-BFJR-09-011.
- 14. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-E-2, Faulted Steam Generator Isolation.
- 15. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-E-3, Steam Generator Tube Rupture.
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- 16. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-ONOP-041.5, Pressurizer Pressure Control Malfunction.
- 17. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-FR-P.1, Response to Imminent Pressurized Thermal Shock Condition.
- 18. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-E-0, Reactor Trip or Safety Injection.
- 19. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-ECA-0.0, Loss of All AC Power.
- 20. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-FR-H.1, Response to Loss of Secondary Heat Sink.
- 21. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-ES-1.2, Post LOCA Cooldown and Depressurization.
- 22. *Florida Power and Light, Turkey Point Unit 3&4, Updated FSAR.
- 23. [
]
- 24. NUREG-0700, Human-System Interface Design Review Guidelines, Revision 3.
- 25. [
]
- 26. [
]
- 27. [
]
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Framatome Inc.
ENGINEERING RECORD DOCUMENT Document No.: 51 - 9330940 - 001 FPL Digital Modernization Project (F.505454)
FMEA - RPS/ESFAS/NIS Framatome Inc.
This document has been redacted and no longer contains Framatome Proprietary Information.
This redacted version is Non-Proprietary.
Proprietary information contained within brackets and proprietary markings have been removed.
Other than removal of proprietary information, technical content was not changed as attested to by the following individuals:
Preparer: Ron Jarrett Reviewer: Steve Kane Approver: Brian Haynes Signature and Date Signature and Date Digitally signed by KANE Steven Signature and Date JARRETT Ronald Digitally signed by JARRETT Ronald Date: 2023.01.17 08:56:28 -05'00' KANE Steven Date: 2023.01.17 09:19:59
-05'00' HAYNES Brian Digitally signed by HAYNES Brian Date: 2023.01.17 07:10:42 -08'00' Page 1 of 947
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FMEA - RPS/ESFAS/NIS 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 Pages/Sections P/LP, Name and Prepared/Reviewed/
Signature R/LR, M, Date Title/Discipline Approved or A-CRF, A Comments RA JARRETT John Hefler for JW HEFLER 1/17/2023 P Sections 1 - 8 Project Engineer / Licensing Ron Jarrett RA JARRETT 1/17/2023 LP All Project Engineer / Licensing Ted Quinn T QUINN R All Project Engineer / Licensing 1/17/2023 Mohamed Hasanin M HASANIN 1/17/2023 P Appendices 1 - 8 Project Engineer Taha AbdelNaeem TI ABDELNAEEM 1/17/2023 LR All Project Lead / Technical Lead Michael Bailey M BAILEY R All Project Engineer/ Licensing 1/17/2023 T QUINN Larry Erin for LE ERIN A All Licensing Lead 1/17/2023 Brian Haynes BM HAYNES 1/17/2023 A All Project Engineering Manager 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 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 1/17/2023 Page 2
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FMEA - RPS/ESFAS/NIS Record of Revision Revision Pages/Sections/
No. Paragraphs Changed Brief Description / Change Authorization 000 All Initial Issue 001 All pages Resolution of FPL DRCS comments for 51-9330940 Revision 000 RPS/ESFAS/NIS Tricon FMEA Page 3
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FMEA - RPS/ESFAS/NIS Table of Contents 1 INTRODUCTION .......................................................................................................................... 18 1.1 Purpose and Application ...................................................................................................... 18 1.1.1 Regulatory Criteria ................................................................................................... 19 1.1.1.1 Regulatory Guide 1.53, Application of the Single-Failure Criterion (Reference 3) ............................................................................................. 19 1.1.1.2 Regulatory Guide 1.153, Criteria for Safety Systems (Reference 5) ........... 19 1.1.1.3 NRC Standard Review Plan, NUREG 800, Section 7 (Reference 1) .......... 19 1.1.1.4 IEEE Std. 603-1991 (Reference 12) ........................................................... 19 1.1.1.5 IEEE Std. 379-2000 (Reference 10) ........................................................... 20 1.1.1.6 IEEE Std 352-1987, IEEE Guide for General Principles of Reliability Analysis (Reference 9) ............................................................................... 20 1.1.1.7 IEEE Std 7-4.3.2-2003, IEEE Standard Criteria for Digital Computers in Safety Systems (Reference 8).................................................................... 20 1.1.1.8 NRC ISG-04 Revision 1, Interim Staff Guidance on Highly-Integrated Control Rooms - Communications Issues (HICRc), March 2009................ 20 1.1.2 FMEA Purpose......................................................................................................... 21 1.1.3 FMEA Applications ................................................................................................... 21 1.2 Analysis Phases .................................................................................................................. 21 1.3 Boundary of Analysis (Scope).............................................................................................. 22 1.4 Definitions............................................................................................................................ 22 2 REQUIREMENTS ......................................................................................................................... 25 2.1 Compliance ......................................................................................................................... 25 2.2 Turkey Point 3 & 4 Requirements Documents Used for FMEA ............................................ 25 3 METHODOLOGY ......................................................................................................................... 27 Page 4
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Page 4 ANALYSIS .................................................................................................................................... 38 4.1 System Definition................................................................................................................. 38 Page 6
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Page 5 FMEA TABLES USAGE.............................................................................................................. 149 5.1 FMEA Appendices 1 through 8 .......................................................................................... 149 6 RESULTS ................................................................................................................................... 157 Page 9
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Page 7 REFERENCES ........................................................................................................................... 172 7.1 Nuclear Regulatory Commission (NRC) Documents .......................................................... 172 7.2 Institute of Electrical and Electronic Engineers (IEEE) Standards ...................................... 172 7.3 Electric Power Research Institute (EPRI)........................................................................... 172 7.4 International Electrotechnical Institute (IEC) ...................................................................... 172 7.5 Framatome Documents ..................................................................................................... 173 7.6 Triconex/Schneider Documents ......................................................................................... 174 7.7 Vendor Documents ............................................................................................................ 174 7.8 Florida Power and Light Documents .................................................................................. 174 7.8.1 Procedures (For Information Only - not used as FMEA design input) .................... 175 7.8.2 Not Used ................................................................................................................ 175 7.8.3 Drawings Used in FMEA Appendices 1-8............................................................... 175 8 ACRONYMS & ABBREVIATIONS .............................................................................................. 176 Page 11
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FMEA - RPS/ESFAS/NIS EXECUTIVE
SUMMARY
This System Level Failure Modes and Effects Analysis (FMEA) is issued in support of the Reactor Protection System, Engineered Safety Feature Actuation System and Nuclear Instrumentation System (RPS/ESFAS/NIS) replacements for Florida Power and Light (FPL) Turkey Point Units 3 and 4. The purpose of this document is to evaluate the proposed design at requirements phase, detailed design phase, and post factory acceptance test (if changes are made) to industry, and regulatory requirements defined in the License Amendment Request (LAR), Reference 58 and supporting documents This document includes information identified in the LAR to satisfy NRC review requirements that were not available when the LAR was submitted to the NRC.
The System Level FMEA covers the Tricon platform components, Nuclear Instrumentation signal conditioning components, interfaces with actuated components, Framatome Safety Video Display Units (SVDU), Framatome supplied miscellaneous equipment and evaluates Turkey Point specific functions and conditions. The initial issue of the FMEA is made during the platform development Requirements Phase. A revised document will be issued to reflect the completed as-delivered system. The scope of the first issuance includes information identified in the LAR to satisfy NRC review requirements that were not available when the LAR was submitted to the NRC. The second issuance is a revision based on completion of detailed design information.
The FMEA will be maintained under Framatome configuration management and change control processes throughout the platform development, including implementation and testing.
The FMEA is a systematic qualitative analysis following the guidance of IEEE Std. 352, IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems. The primary objectives are to identifying credible failure modes, evaluating the consequences and effects of failures associated with single failure criteria, IEEE Std. 379-2000, and to document that failures in systems credited for redundancy are detectable. The acceptance criteria for redundancy and independence are defined in conformance standards IEEE Std 603-1991 (Reference 12) and IEEE 7-4.3.2 - 2003 (Reference 8) and guidance standards as defined in the RPS/ESFAS/NIS System Requirements Specification (Reference 18). NRC ISG-04 (Reference 7) is a committed standard for digital system and communication acceptance criteria.
The RPS/ESFAS/NIS Replacement project includes a Diversity & Defense in Depth (D3) Evaluation (Reference 25) which assumes a beyond design basis software common cause failure (SWCCF) of the Tricon platform. This evaluation identifies plant control functions and indications to be available in the event of a Protection System SWCCF. This document includes evaluation of D3 required controls and indication for independence as defined in the D3 Evaluation.
The initial issue of this FMEA provides the additional information identified in LAR and documents an early assessment of the proposed design. The conclusions of the initial issue are subject to modification as detailed design is completed.
Functional failures that could result from the RPS/ESFAS/NIS replacement were examined in the FMEA as documented in the Appendices. Failures were considered down to the component, module, and system levels and included evaluation of adverse effects to system critical functions. Based on the FMEA, it is concluded that critical functions required for performing protective actions during normal and abnormal conditions will continue to be performed for all identified single failure modes.
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FMEA - RPS/ESFAS/NIS The initial issue of the FMEA identifies the following failure modes based on the Turkey Point Unit 3 and 4 RPS/ESFAS/NIS FMEDA (Reference 41).
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FMEA - RPS/ESFAS/NIS BACKGROUND Framatome has been contracted to Florida Power & Light to design, develop, test, and install replacement Reactor Protection, Engineered Safety Feature Actuation, and Nuclear Instrumentation systems using a Tricon Programmable Logic Controller (PLC) platform. Framatome developed a License Amendment Request for FPL and provides support for NRC review of the LAR. The content of the LAR was based on the Alternate Review Process described in ISG-06 Revision 2. The LAR (Reference 58) was submitted by FPL to the NRC on July 30th 2022.
The RPS/ESFAS/NIS replacement system is a [
] are maintained with the same functions performed maintaining the original redundancy, independence, and power sources as the Current systems. The existing plant design includes the use of safety related sensors for [ ] These dependencies are not modified, and no new dependencies are created. The existing design basis for the protection systems is maintained.
The existing analog Nuclear Instrumentation System is a standalone channelized redundant system that conditions signals from the detectors, interfaces with the reactor trip voters, provides indication and alarm features, and provides signals to the rod control system. The signal conditioning function is being replaced with [ ] that are manufactured by Framatome and provided as basic components. The signal conditioning chassis interface with the measurement channels and the logic and setpoint comparisons are performed in the same Tricon Systems as the rest of the protection system field sensor inputs. The remaining functions performed by the existing system will be performed by the Tricon system, non-safety related functions are implemented in non-safety systems. For additional detail on the NIS replacement functional allocation, refer to the Basis of Design Document (Reference 34)
Channel to Train interdivision wired communications transfer Reactor Trip and Engineered Safety Feature Actuation signals from the channels to the Trains. Digital communications between Tricon systems in different divisions is implemented for the purpose of providing information to be displayed on multidivisional displays. Digital communications from each of the Tricon systems in the Protection System to the existing Distributed Control System are implemented for the purposes of monitoring the Tricon systems, performance of non-safety functions, display of information and condition alarming.
A Diversity & Design in Depth (D3) evaluation was performed postulating a software common cause failure within the protection system. The evaluation demonstrated that the beyond design basis event could be mitigated through automatic actions performed by diverse actuation systems and operator actions using indications and controls diverse from the Tricon protection system platform.
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FMEA - RPS/ESFAS/NIS 1 INTRODUCTION This document establishes the applicable criteria, requirements, and methods for a FMEA and provides the evaluation, documents the conclusions and tracks implementation items. The guidance of IEEE Std 352, IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems, is used for formatting and content of the FMEA.
The initial issue of this System Level FMEA provides additional information identified in the LAR and documents an early assessment of the proposed design. The conclusions of this initial issue are subject to modification as detailed design activities are completed.
The information to supplement the LAR initial submittal as identified in Section 3.12.2 of the LAR as follows:
This document is prepared in accordance with the Project Management Plan (PMP) (Reference 16) and Framatomes Quality Assurance Program (Reference 17).
1.1 Purpose and Application The LAR identified that some information described in ISG-06 Revision 2 was not available at the time of submittal. This document serves to provide the information identified in Section 3.12.2 of the LAR, System Level FMEA and will be submitted to the NRC as supplemental information to the LAR.
This document is also an analysis implemented in stages and used by Framatome to evaluate the proposed replacement system and document conformance to the committed standards IEEE Std. 603-1991, IEEE Std. 7-4.3.2- 2003, and NRC ISG-04, Rev 1 for redundancy, independence, and detectability of failures.
This System Level FMEA is a systematic qualitative analysis of the RPS/ESFAS/NIS design with the primary objectives of identifying credible failure modes, evaluating the consequence and effects of failures, and verifying that the design satisfies single-failure criterion applicable to the replacement RPS/ESFAS/NIS.
The initial issue of this System Level FMEA is made near the end of the platform development life cycle Requirements Phase. This is the first issuance of two planned issuances and evaluates the proposed system replacement based on requirements phase information along with existing Turkey Point drawings for system interfaces to plant sensors, hardwired switches, indicators, and actuated components. The second issuance of the FMEA includes the detailed design and failure modes and effects represented in the tables in Appendices are based on source documents that can be categorized as:
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FMEA - RPS/ESFAS/NIS The commitment to standards and regulatory documents and the use of guidance documents are defined in the System Requirements Specification, Attachment 7.7 to the LAR, and are further described herein.
1.1.1 Regulatory Criteria This FMEA addresses regulatory and industry criteria including but not limited to:
1.1.1.1 Regulatory Guide 1.53, Application of the Single-Failure Criterion (Reference 3)
Endorses IEEE Std. 379-2000.
1.1.1.2 Regulatory Guide 1.153, Criteria for Safety Systems (Reference 5)
Endorses IEEE Std. 603-1991.
1.1.1.3 NRC Standard Review Plan, NUREG 800, Section 7 (Reference 1)
The NUREG was used for informational guidance.
1.1.1.4 IEEE Std. 603-1991 (Reference 12)
The IEEE standard was used to address:
- 1. Single Failure, Clause 5.1.
IEEE Std. 603-1991 Clause 5.1 invokes IEEE Std. 379-1988. This project uses IEEE Std. 379-2000 per LAR Section 3.12.
- 2. Effects of a single random failure in a non-safety system, Clause 5.6.3.3.
- 3. Control/Protection Interaction, Clause 6.3.
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FMEA - RPS/ESFAS/NIS 1.1.1.5 IEEE Std. 379-2000 (Reference 10)
The standard was used to address:
1.1.1.6 IEEE Std 352-1987, IEEE Guide for General Principles of Reliability Analysis (Reference 9)
Endorsed by IEEE 379-2000 as guidance to develop FMEAs.
1.1.1.7 IEEE Std 7-4.3.2-2003, IEEE Standard Criteria for Digital Computers in Safety Systems (Reference 8)
Annex D will also be used as guidance (not endorsed by RG 1.152 (Reference 4)) and includes a lifecycle approach.
1.1.1.8 NRC ISG-04 Revision 1, Interim Staff Guidance on Highly-Integrated Control Rooms -
Communications Issues (HICRc), March 2009 Used for analysis of digital communications, faults and failures.
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FMEA - RPS/ESFAS/NIS 1.1.2 FMEA Purpose FMEA purpose includes but is not limited to:
1.1.3 FMEA Applications FMEA applications include but are not limited to:
1.2 Analysis Phases The FMEA will consist of two phases:
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FMEA - RPS/ESFAS/NIS 1.3 Boundary of Analysis (Scope)
The Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project at Turkey Point Units 3 and 4 includes:
- Replacement of the RPS with a Triconex Triple Mode Redundant (TMR) digital control system.
- Replacement of the ESFAS with a Triconex TMR digital control system.
- Replacement of the Nuclear Instrumentation (NI) Power Range (PR), Intermediate Range (IR), and Source Range signal processing chassis. Refer to Framatome NIS FMEA (References 33, 36, and 37).
- Addition of the MCR SVDUs
- Addition of Diverse Actuation System (DAS). This FMEA does not include the DAS, which is covered in a separate analysis.
- Independence of the backup indication required to support Operation actions by the D3 Analysis (Reference 25).
The FMEA scope includes a detailed analysis for all hardware and software functions as defined by SyRS provided for the replacement RPS/ESFAS/NIS. All credible hardware failure modes for the replacement equipment are within the scope.
The analysis boundary is illustrated in Figure 4-42. The specific FMEA boundary is described in Section 4.4. [
]
1.4 Definitions IEEE Std. 603-1991 (Reference 12) unless noted otherwise:
- Channel: An arrangement of components and modules as required to generate a single protective action signal when required by a generating station condition. A channel loses its identity where single protective action signals are combined.
- Class 1E: The safety classification of the electric equipment and systems that are essential to emergency reactor shutdown, containment isolation, reactor core cooling, and containment and reactor heat removal or are otherwise essential in preventing significant release of radioactive material to the environment.
- Component: The largest entity of hardware for which data are most generally collected and expected to be reliable (for example, pump with motor, valve with operator, amplifier, pressure transmitter). It is generally an off-the-shelf item procured by the system designer as a basic building block for his system (IEEE Std. 100-2000).
- Common-cause failure: Multiple failures attributable to a common cause (IEEE Std. 379-2000).
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FMEA - RPS/ESFAS/NIS
- Detectable failures: Failures that can be identified through periodic testing or that can be revealed by alarm or anomalous indication. Component failures that are detected at the channel, division, or system level are detectable failures.
NOTE: Identifiable but nondetectable failures are failures identified by analysis that cannot be detected through periodic testing or revealed by alarm or anomalous indication.
- Division: The designation applied to a given system or set of components that enables the establishment and maintenance of physical, electrical, and functional independence from other redundant sets of components.
- Failure: The termination of the ability of an item to perform its required function (IEEE Std. 379-2000).
- Module: An electronic circuit assembly that connects to one or more slots on the backplane. It is removable from and replaceable in a backplane assembly via connectors (IEEE Std. 100-2000).
- Power sources: The electrical and mechanical equipment and the interconnections necessary to generate or convert power.
- Protection system: That part of the sense and command features involved in generating the signals used primarily for the reactor trip system and engineered safety features.
- Protective action: Initiation of a signal within the sense and command features or the operation of equipment within the execute features for the purpose of accomplishing a safety function.
- Redundant equipment or system: A piece of equipment or a system that duplicates the essential function of another piece 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.
NOTE: Redundancy can be accomplished by using identical equipment, equipment diversity, or functional diversity.
- Safety function: One of the processes or conditions (e.g., emergency negative reactivity insertion, post-accident heat removal, emergency core cooling, post-accident radioactivity removal, and containment isolation) essential in maintaining plant parameters within acceptable limits established for a design basis event.
NOTE: A safety function is achieved by the completion of all required protective actions by the reactor trip system or the engineered safety features, or both, concurrent with the completion of all required protective actions by the auxiliary supporting features.
- Safety group: A given minimal set of interconnected components, modules, and equipment that can accomplish a safety function.
- Safety System: A system that is relied upon to remain functional during and following design basis events to ensure: (i) the integrity of the reactor coolant pressure boundary, (ii) the capability to shut down the reactor and maintain it in a safe shutdown condition, or (iii) the capability to prevent or mitigate the consequences of accidents that could result in potential off-site exposures comparable to 10 CFR Part 100 guidelines.
NOTE: The electrical portion of the safety systems, which perform safety functions, is classified as Class IE.
- Shared systems: Structures, systems, and components that can perform functions for more than one unit in multiunit stations.
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FMEA - RPS/ESFAS/NIS NOTE: This definition includes the following:
a) Systems that are simultaneously shared by both units.
b) Time sequential sharing or systems that would be shared by two units at different times, according to the sequence of events.
c) Systems that would only be used by one unit at any given time, but that could be disconnected from that unit and placed in the other unit on demand.
- Single Failure Criterion (IEEE Std. 603-1991 Clause 5.1, Single-failure criterion).
The safety systems shall perform all safety functions required for a design basis event in the presence of the following:
o Any single detectable failure within the safety systems concurrent with all identifiable but nondetectable failures.
o All failures caused by the single failure.
o All failures and spurious system 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 system is required to function. The single-failure criterion applies to the safety systems whether control is by automatic or manual means. IEEE Std 379-2000 provides guidance on application of the single failure criterion.
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FMEA - RPS/ESFAS/NIS 2 REQUIREMENTS 2.1 Compliance This document complies with applicable USNRC Regulatory Guides and Industry Requirements in Section 1.1.1. This analysis addresses industry standards and regulatory guidance to demonstrate compliance with applicable requirements.
Information is provided to supplement the LAR, descriptive information, analysis, compliance requirements, and validation bases are provided in the applicable topical sections.
Descriptive information is provided to document the basis for system design features of redundancy, independence, separation, and compliance with single failure criterion used in the FMEA.
Detailed analysis is provided in the Appendices to demonstrate that credible RPS/ESFAS/NIS hardware failure modes are detectable and that the design complies with the single failure criterion. The analysis methodology is described in Section 3, FMEA Methodology, the analysis is provided in Section 4, Analysis, and in Appendix 1 through Appendix 8, with the conclusions and a summary of the results presented in Section 6, Results.
2.2 Turkey Point 3 & 4 Requirements Documents Used for FMEA The following document types were used to develop this FMEA.
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FMEA - RPS/ESFAS/NIS 3 METHODOLOGY This section describes the methodology used to perform the FMEA.
LAR identified supplemental information is provided in specific sub-sections in Section 4.
Section 4 provides the basis for the FMEA represented in the attachments, including explanatory figures and tables.
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FMEA - RPS/ESFAS/NIS 4 ANALYSIS 4.1 System Definition The RPS and ESFAS are classified Class 1E Nuclear Safety-Related. The RPS and ESFAS perform functions necessary to assure one or more of the following:
- The integrity of the RCS pressure boundary.
- The capability to shut down the reactor and to maintain it in a safe shutdown condition.
- The capability to prevent or mitigate the consequences of accidents which may result in off-site exposures comparable to those set forth in 10 CFR Part 100 (Reference 6) guidelines.
- The integrity of the reactor core.
- The integrity of the Containment Building.
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FMEA - RPS/ESFAS/NIS 5 FMEA TABLES USAGE 5.1 FMEA Appendices 1 through 8 The purpose of this section is to provide a key to understanding the methods used to document the FMEA in the Appendices.
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FMEA - RPS/ESFAS/NIS 7 REFERENCES All listed FPL references are maintained within Turkey Point Nuclear Records System and are not retrievable from Framatome Records Management. These are acceptable references per Framatome Administrative Procedure 0402-01, Attachment 7. See page 2 for Project Manager Approval of customer references.
7.1 Nuclear Regulatory Commission (NRC) Documents
- 1. NUREG-0800, Standard Review Plan, Revision 4, June 1997 Chapter 7, Instruments &
Controls
- 2. Branch Technical Position 7-19, Guidance for Evaluation of Defense-in-Depth and Diversity in Digital Computer-Based Instrumentation and Control Systems, Rev 8, 01/2021
- 3. Regulatory Guide 1.53, Application of the Single-Failure Criterion to Safety Systems, Revision 2, November 2003
- 4. Regulatory Guide 1.152, Criteria for Use of Computers in Safety Systems of Nuclear Power Plants, Revision 3
- 5. Regulatory Guide 1.153, Criteria for Safety Systems, Revision 1, June 1996.
- 6. 10 CFR 100, Reactor Site Criteria
- 7. NRC ISG-04 Revision 1, Interim Staff Guidance on Highly-Integrated Control Rooms -
Communications Issues (HICRc), March 2009 7.2 Institute of Electrical and Electronic Engineers (IEEE) Standards
- 8. IEEE Std 7-4.3.2-2003, IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations
- 9. IEEE Std 352-1987, IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
- 10. IEEE Std 379-2000, IEEE Standard Application of the Single- Failure Criterion to Nuclear Power Generating Station Safety Systems
- 11. IEEE Std 384-1992, IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits.
- 12. IEEE Std 603-1991, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
- a. IEEE Std 603-1991, Correction 01/30/1995 7.3 Electric Power Research Institute (EPRI)
- 13. Deleted.
- 14. Deleted.
7.4 International Electrotechnical Institute (IEC)
- 15. IEC 61508, Functional safety of electrical/electronic/programmable electronic safety-related Systems - Part 5: Examples of methods for the determination of safety integrity levels, Ed 2.0, 04/2010 Page 172
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FMEA - RPS/ESFAS/NIS 7.5 Framatome Documents
- 16. Framatome Inc, Doc No. 102-9321586-004, Turkey Point Units 3&4 RPS/ESFAS/NIS Project Management Plan (PMP)
- 18. Framatome Inc, Doc. No. 08-9321046-005, RPS/ESFAS/NIS System Requirements Specification
- 19. Deleted
- 20. Framatome Inc, Doc. No. 08-9321050-002, Hardware Requirement Specification -
RPS/ESFAS/NIS
- 21. Deleted
- 22. Framatome Inc, Doc. No. 02-9321047-D-009, U3 RPS/ESFAS/NIS System Architecture Drawings.
- 23. Deleted
- 24. Deleted
- 25. Framatome Inc, Doc. No. 51-9324096-004, Turkey Point Unit 3&4 Diversity and Defense-ln-Depth Evaluation
- 26. Framatome, Inc, Doc 51-9324222-008, Turkey Point 1E Digital Modernization Equipment Qualification Plan
- 27. Framatome, Inc, Doc. No. 183-9325514-006, FPL Digital Modernization Project RPS/ESFAS/NIS Unit 3 IO List
- 28. Framatome, Inc, Doc. No. 183-9325515-002, FPL Digital Modernization Project RPS/ESFAS/NIS Unit 4 IO List
- 30. Framatome Inc, Doc. No. 02-9347677-D-001, Power Range Signal Conditioning NFI-SCA-PR Major Component Configuration Diagram
- 31. Framatome Inc, Doc. No. 02-9347680-D-003, Intermediate Range Signal Conditioning NFI-SCA-IR Major Component Configuration Diagram
- 32. Framatome Inc, Doc. No. 02-9347681-D-002, Source Range Signal Conditioning NFI-SCA-SR Major Component Configuration Diagram
- 33. Deleted
- 34. Framatome NIS Basis of Design Document Framatome Inc., Doc. No. 51-9346405-001, PTN U3/U4 Excore Nuclear Instrumentation System (NIS) Basis of Design Description (BODD)
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- 40. Deleted
- 41. Framatome, Inc, Doc. No. 38-9327603-001, Failure Modes and Effects Analysis (FMEA) for TRICON V10 PLC
- 42. Framatome, Inc, Doc. 51-9332976-001, FMEDA Implementation RPS/ESFAS/NIS
- 43. Deleted 7.6 Triconex/Schneider Documents
- 44. Triconex Doc. No. 9700077-022, Planning and Installation Guide
- 45. Triconex Approved Topical Report, 7286-545-1-A, Revision 4
- 46. NTX-SER-09-10, COMPLIANCE WITH NRC INTERIM GUIDANCE ISG-2 and ISG-4
- 47. NTX-SER-10-14, TRICON V10 CONFORMANCE TO REGULATORY GUIDE 1.152
- 48. Schneider Electric, USSVDU2-FMEA-XXSR-0001, North America Nuclear SVDU 2.0 Development Project Qualification Failure Modes and Effects Analysis, Rev 00
- 49. Deleted
- 50. Schneider Electric, 9700088 016, Tricon V9-V11 Systems Communication Guide
- 51. Triconex, 9600164-545, Equipment Qualification Summary Report, Rev 3
- 52. Schneider Electric, 9600336-546, SVDU 2.0 Development Project Equipment Qualification Summary Report, Rev 0 7.7 Vendor Documents
- 53. Weed ULTRA Model N7030 RTD and N7040 Thermocouple Analog Transmitter Product Datasheet
- 54. Phoenix-Contact 2702663 Coupling relay - PSR-PS23-1NO-1NC-24VDC-SC Datasheet
- 55. Phoenix Contact 2966197 Relay Module - PLC-RSC-120UC/21 Datasheet
- 56. Phoenix Contact 2866763 Quint PS/1AC/24DC/10 Power Supply Data Sheet (103128_en_05) 7.8 Florida Power and Light Documents
- 57. Deleted
- 58. FPL Letter L-2022-120 to NRC dated July 30, 2022, Turkey Point Nuclear Plant, Units 3 & 4, License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project (ADAMS Accession No. ML22213A045)
- 59. FPL Letter L-2022-166, dated October 5, 2022, Response to Request for Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project
- 60. Turkey Point Units 3 and 4 Technical Specifications (R236)
- 61. D3 Evaluation NRC Audit Question Response (AQ-8) to NRC Question EICB-8 dated 1/15/2023 Page 174
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- 62. 3-EOP-E-0_016, Reactor Trip or Safety Injection
- 63. Deleted.
- 64. Deleted.
- 65. 3-ONOP-049.1, Deviation or Failure of Safety-Related Or Reactor Protection Channels
- 66. Deleted.
- 67. Deleted.
- 68. Deleted.
7.8.2 Not Used 7.8.3 Drawings Used in FMEA Appendices 1-8 Reference drawings used in the FMEA tables are identified in the Appendices in the individual evaluations in which they were used rather than in this section to minimize potential for conflict as the drawings are modified and reissued in the detailed design.
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FMEA - RPS/ESFAS/NIS 8 ACRONYMS & ABBREVIATIONS Acronym Meaning 1/2 1 out of 2 coincidence logic 1/3 1 out of 3 coincidence logic 1/4 1 out of 4 coincidence logic 2/2 2 out of 2 coincidence logic 2/3 2 out of 3 coincidence logic 2/4 2 out of 4 coincidence logic T RCS differential temperature ACOT Analog Channel Operational Test AFW Auxiliary Feedwater AI Analog input ALT Actuation Logic Test AMSAC ATWS Mitigation System Actuation Circuitry ANS American Nuclear Society AO Analog Output AOO Anticipated Operational Occurance ATWS Anticipated Transient Without Scram BTP Branch Technical Position CCF Common Cause Failure CFR Code of Federal Regulations CH/SL/PT Triconex chassis/slot/point module assignment COT Channel Operational Test CPS Counts per Second CPU Central Processing Unit CSR Cable Spreading Room D3 Diversity and Defense-in-Depth Evaluation DAS Diverse Actuation System DCS Distributed Control System DDPS Digital Data Processing System DI Discrete (Digital) Input DO Discrete (Digital) Output dP Differential Pressure DT Differential RCS Temperature (Thot-Tcold)
DTTA Delta T/Taverage (T/Tavg)
ECP Engineering Change Package EFT Electrical Fast Transient EHC Electro-Hydraulic Control EMI Electromagnetic Interference Page 176
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FMEA - RPS/ESFAS/NIS Acronym Meaning EPRI Electric Power Research Institute EQ Equipment Qualification ESD Electrostatic Discharge ESF Engineered Safety Feature ESFAS Engineered Safety Feature Actuation System FMEA Failure Modes and Effects Analysis ETP External Termination Panel FPL (FP&L) Florida Power & Light FTP Field Termination Panel GDC General Design Criteria HSI Human System Interface HRS Hardware Requirements Specification I&C Instrument & Control IEEE Institute of Electrical and Electronic Engineers I/O (IO) Input/Output IR Intermediate Range IVV (IV&V) Independent Verification and Validation LAR License Amendment Request LCO Limiting Condition for Operation LOCA Loss of Coolant Accident MCR Main Control Room mA milliampere MP Main Processor MSS Median Signal Select NI Nuclear Instrumentation NIS Nuclear Instrumentation System NR Narrow Range NSR Non-Safety Related OOR Out of Range OPDT Overpower Delta Temperature OTDT Overtemperature Delta Temperature P&IG Triconex Planning & Installation Guide P2P Peer-to-Peer PLC Programmable Logic Controller PMA Process Measurement Accuracy PRXM Primary Remote Extender Module PTC Positive Temperature Coefficient PZR Pressurizer Page 177
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FMEA - RPS/ESFAS/NIS Acronym Meaning RCP Reactor Coolant Pump RCS Reactor Coolant System RFI Radio Frequency Interference RPS Reactor Protection System RSA Redundant Sensor Algorithm RT Reactor Trip Rx Reactor RXM Remote Extender Module RTD Resistance Temperature Detector RTP Rated Thermal Power RTS Reactor Trip System SAP Safety Application Protocol SCA Signal Conditioning Assembly SD Self Diagnostic SDO Supervised Digital Output SE Safety Evaluation SG Steam Generator SI Safety Injection SLI Steam Line Isolation SOE Sequence of Events SR Safety Related SVDU Safety Video Display Unit SWCCF Software Common Cause Failure SyRS System Requirements Specification TAP Test Access Point Tavg Average RCS Temperature (Thot+Tcold)/2 TCM Triconex Communication Module Tcold RCS Cold Leg Temperature Thot RCS Hot Leg Temperature UFSAR Updated Final Safety Analysis Report USNRC United States Nuclear Regulatory Commission UV Undervoltage V&V Verification & Validation VAC Volts Alternating Current VDC Volts Direct Current WR Wide Range Page 178
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FMEA - RPS/ESFAS/NIS APPENDICES Failure Modes and Effects Analysis (FMEA) Evaluation Tables Table of Contents Page Appendix 1 Failure Modes and Effects Analysis (FMEA) RPS Channel I ............................ 1-1 Appendix 2 Failure Modes and Effects Analysis (FMEA) RPS Channel II ........................... 2-1 Appendix 3 Failure Modes and Effects Analysis (FMEA) RPS Channel III .......................... 3-1 Appendix 4 Failure Modes and Effects Analysis (FMEA) RPS Channel IV .......................... 4-1 Appendix 5 Failure Modes and Effects Analysis (FMEA) RPS Voter A(B) ........................... 5-1 Appendix 6 Failure Modes and Effects Analysis (FMEA) Safeguards (ESFAS) Voter Train A(B) .......................................................................................................... 6-1 Appendix 7 Failure Modes and Effects Analysis (FMEA) RPS SVDU .................................. 7-1 Appendix 8 Failure Modes and Effects Analysis (FMEA) Miscellaneous Items.................... 8-1 Page 179
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FMEA - RPS/ESFAS/NIS Appendix 7 Failure Modes and Effects Analysis (FMEA) RPS SVDU Page 7-1
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FMEA - RPS/ESFAS/NIS Appendix 8 Failure Modes and Effects Analysis (FMEA) Miscellaneous Items Page 8-1
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