L-2023-010, Supplemental Information Regarding License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project - Submittal of RPS / ESFAS / Nis
| ML23041A341 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/10/2023 |
| From: | Strand D Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| Shared Package | |
| ML23041A340 | List: |
| References | |
| L-2023-010 | |
| Download: ML23041A341 (1) | |
Text
L-2023-010 10 CFR 50.90 Framatome Inc. Proprietary (Not proprietary when separated from Attachments 1, 2 and 3)
February 10, 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 RPS / ESFAS / NIS and Distributed Control System (DCS),
Diverse Actuation System (DAS) and DCS, and Operating Experience Results Summary Reports
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)
- 3. Florida Power & Light Company letter L-2023-004, Turkey Point Nuclear Plant, Units 3 & 4, 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, January 17, 2023 (ADAMS Accession No. ML23017A226)
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 were necessary to complete its acceptance review.
In Reference 3, FPL notified the NRC of the availability on NextEras online reference portal the documents listed below and agreed to submit versions of the documents within 30 days of the Reference 3 submittal. The attachments to this letter provide the following documents:
- 1. Functional Requirements Analysis, Functional Allocation and Task Analysis - RPS / ESFAS / NIS and Distributed Control System (DCS) Results Summary Report Florida Power & Light Company 9760 SW 344th Street, Homestead, FL 33035
Turkey Point Nuclear Plant L-2022-010 Docket Nos 50-250 and 50-251 Page 2 of 2
- 2. Functional Requirements Analysis, Functional Allocation and Task Analysis Diverse Actuation System (DAS) and DCS Results Summary Report
- 3. Operating Experience Review Results Summary Report Attachments 1, 2 and 3 contain information considered to be proprietary by Framatome, Incorporated.
Pursuant to 10 CFR 2.390(a)(4), FPL requests the proprietary information be withheld from public disclosure. Attachment 4 provides three affidavits signed by Framatome, Incorporated, the owner of the information, in support of the withholding requests. The affidavits set forth the basis upon which 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 5, 6 and 7 contain redacted versions of Attachments 1, 2 and 3.
This supplemental information provided in this submittal does not alter the conclusions 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 10th day of February 2023.
Sincerely, rfJr c..--.. s~
Dianne Strand General Manager, Regulatory Affairs Florida Power & Light Company Attachments (7) 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
Turkey Point Nuclear Plant L-2023-010 Docket Nos 50-250 and 50-251 Attachment 4 ATTACHMENT 4 SUPPLEMENTAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST 274 REACTOR PROTECTION SYSTEM, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, AND NUCLEAR INSTRUMENTATION SYSTEM REPLACEMENT PROJECT FRAMATOME, INCORPORATED AFFIDAVITS (3) IN SUPPORT OF PUBLIC WITHHOLDING PURSUANT TO 10 CFR 2.390 (6 pages follow)
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. 51-9355274-003 Functional Requirements Analysis, Functional Allocation and Task Analysis - Reactor Protection System (RPS), Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (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 February 7, 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. 51-9355273-004, Functional Requirements Analysis, Functional Allocation and Task Analysis - Diverse Actuation System (DAS) and Distributed Control System (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 f or 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 February 7, 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. 51-9354906-003, Results Summary Report, Operating Experience Review (License Amendment Request Version). 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 f or 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 February 7, 2023.
Philip A. Opsal Manager, Product Licensing Framatome Inc.
Turkey Point Nuclear Plant L-2023-010 Docket Nos 50-250 and 50-251 Attachment 5 ATTACHMENT 5 SUPPLEMENTAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST 274 REACTOR PROTECTION SYSTEM, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, AND NUCLEAR INSTRUMENTATION SYSTEM REPLACEMENT PROJECT FUNCTIONAL REQUIREMENTS ANALYSIS, FUNCTIONAL ALLOCATION AND TASK ANALYSIS -
RPS / ESFAS / NIS AND DISTRIBUTED CONTROL SYSTEM (DCS)
RESULTS
SUMMARY
REPORT (147 pages follow)
(REDACTED)
20004-026 (08/12/2020)
Framatome Inc.
RESULTS
SUMMARY
REPORT Document No.: 51 - 9355274 - 003 Functional Requirements Analysis, Functional Allocation and Task Analysis - Reactor Protection System (RPS), Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (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: Steve Kane Approver: Brian Haynes Signature and Date Signature and Date Signature and Date Page 1 of 147
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Document No.: 51-9355274-003 Functional Requirements Analysis, Functional Allocation and Task Analysis - Reactor Protection System (RPS),
Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (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 LP All Project Engineer 2/2/2023 Jacek Nowakowski JK NOWAKOWSKI LR All Project Engineer 2/2/2023 Brian Haynes BM HAYNES A All 2/2/2023 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 RO JAWOROWSKI Ron Jaworowski Project Manager 2/3/2023 Page 2
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Record of Revision Revision Pages/Sections/
Brief Description / Change Authorization No. Paragraphs Changed 000 All Initial issuance Incorporate comments from F.505454-OUT-0764-000 DRCS Combined 001 All comments Title Page Modified proprietary data declaration.
Footnotes were automatically renumbered to be sequential (no revision bars 002 Various shown).
7.0 Added revisions to references 2, 4-9, 15 and 36-39.
Record of Revision Corrected description of title page change in Rev 002.
Title Page Modified proprietary data declaration.
2.1 Rephrased bullets 1 and 2 to align with the OER.
003 5.4.1 Rephrased bullet 1 to align with the OER.
7.0 Updated revisions of references 5 and 8.
Appendix B Updated to align with the OER.
Page 3
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Table of Contents Page
1.0 INTRODUCTION
........................................................................................................................... 9 1.1 Background ....................................................................................................................... 9 1.2 Purpose and Approach.................................................................................................... 10 1.3 Scope .............................................................................................................................. 11 1.4 Relationships Between HFE documents ......................................................................... 11 1.5 Terms and Definitions ..................................................................................................... 12 1.6 Acronyms ........................................................................................................................ 14 2.0 APPLICABLE OPERATING EXPERIENCES AND IMPORTANT HUMAN ACTIONS ............... 16 2.1 Applicable OEs ................................................................................................................ 16 2.2 Applicable IHAs ............................................................................................................... 18 3.0 FUNCTIONAL REQUIREMENTS ANALYSIS RESULTS ........................................................... 19 3.1 System Functions and Functional Requirements ............................................................ 19 3.1.1 RPS System Functions and Functional Requirements ..................................... 19 3.1.2 ESFAS System Functions and Functional Requirements ................................ 21 3.1.3 NIS System Functions and Functional Requirements ...................................... 22 3.1.4 DCS System Functions and Functional Requirements..................................... 23 3.2 Systems Modification Impact on Functional Breakdown ................................................ 24 4.0 FUNCTIONAL ALLOCATION RESULTS .................................................................................... 26 4.1 Existing Functional Allocation.......................................................................................... 27 4.2 Systems Modification Impact on Functional Allocation ................................................... 29 5.0 TASK ANALYSIS RESULTS....................................................................................................... 29 5.1 Systems Modification Impact on Operator Tasks ........................................................... 30 5.2 HSI requirements ............................................................................................................ 46 5.3 Scenarios ........................................................................................................................ 62 5.3.1 Scenarios impacted by new and modified tasks ............................................... 62 5.3.2 Scenarios resulted from Treatment of Important Human Actions ..................... 64 5.3.3 Additional scenarios ......................................................................................... 66 5.4 Operating Sequence Diagrams ....................................................................................... 66 5.4.1 Rationale for selecting scenarios for OSD development .................................. 67 5.4.2 Operating Sequence Diagrams Development Notes and Assumptions ........... 68
6.0 CONCLUSION
S .......................................................................................................................... 70
7.0 REFERENCES
............................................................................................................................ 74 APPENDIX A. TASK RECORD SHEETS ................................................................................ 77 Page 4
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Table of Contents (continued)
Page APPENDIX B. DESCRIPTION OF APPLICABLE OE ............................................................ 124 APPENDIX C. OPERATING SEQUENCE DIAGRAMS ......................................................... 131 APPENDIX D. PANEL C03 INDICATIONS ............................................................................ 138 APPENDIX E. DIVERSE INDICATIONS ................................................................................ 141 Page 5
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS)
List of Tables Page Table 5-1: Evaluation of the RPS/ESFAS/NIS upgrade impact on existing system tasks
[ ] .......................................................................................... 33 Table 5-2: Additional modified RPS/ESFAS/NIS tasks identified from the review of the SyRSs/SRS ......................................................................................................................................... 43 Table 5-3: Summary of HSI requirements ......................................................................................................... 47 Table 5-4: Scenarios from TA .............................................................................................................................. 63 Table 5-5: IOS applicable to TA .......................................................................................................................... 64 Table 5-6: Additional Scenarios........................................................................................................................... 66 Table A-1: TRS for ESFAS-T01 [ ] .......................................................................... 77 Table A-2: TRS for ESFAS-T02 [ ] ........................................................................... 79 Table A-3: TRS for NIS-T01 [ ] ................................................................................. 81 Table A-4: TRS for NIS-T02 [ ] ................................................ 84 Table A-5: TRS for NIS-T03 [ ] ............................................................. 86 Table A-6: TRS for NIS-T04 [ ] ........................................ 87 Table A-7: TRS for NIS-T05 [ ] ........................................................... 89 Table A-8: TRS for NIS-T06 [ ] .................................... 91 Table A-9: TRS for NIS-T07 [ ] ...................................................... 93 Table A-10: TRS for NIS-T08 [ ]......................................... 95 Table A-11: TRS for NIS-T09 [ ] ............................... 99 Table A-12: TRS for NIS-T10 [ ] .......................... 101 Table A-13: TRS for NIS-T11 [ ] ................................................... 103 Table A-14: TRS for NIS-T12 [ ] .................................................................................. 104 Table A-15: TRS for NIS-T13 [ ] ............................................................. 105 Table A-16: TRS for NIS-T14 [ ] ........................................ 107 Table A-17: TRS for NIS-T15 [ ] ................................................. 108 Table A-18: TRS for NIS-T16 [ ] ........................................................................... 109 Table A-19: TRS for RPS-ESFAS-NIS-T01 [ ] ................................................. 110 Table A-20: TRS for RPS-ESFAS-NIS-T02 [ ] ................ 112 Table A-21: TRS for RPS-ESFAS-NIS-T03 [
] ..................................................................................................................................... 114 Table A-22: TRS for RPS-ESFAS-NIS-T04 [ ] ......................... 116 Page 6
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List of Tables (continued)
Page Table A-23: TRS for RPS-ESFAS-NIS-T05 [ ] ..................................................... 118 Table A-24: TRS for RPS-ESFAS-NIS-T06 [ ] .............................................................. 120 Table A-25: TRS for RPS-ESFAS-NIS-T07 [ ] ................................ 121 Table A-26: TRS for GEN-T01 [ ] .............................. 122 Table A-27: TRS for GEN-T02 [ ] ...................................................... 123 Table B-1: OER Analysis Results ..................................................................................................................... 124 Table D-1: Panel C03 Indications (Reference 15) .......................................................................................... 138 Table E-1: Diverse indications from TRICON (Reference 36) ...................................................................... 141 Page 7
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List of Figures Page Figure 1-1: Relationships between HFE Documents ....................................................................................... 12 Figure 3-1: FRA Development Process.............................................................................................................. 19 Figure 3-2: Protection System Component Replacement Scope (Reference 7) ......................................... 25 Figure 4-1: FA Development Process ................................................................................................................ 27 Figure 5-1: TA Development Process ................................................................................................................ 30 Page 8
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS)
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 7).
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 15) 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 summarized briefly below (Reference 4) and expanded in Section 3.2:
- 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 Page 9
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS)
- Addition of a Diverse Actuation System (DAS): this particular modification is addressed in a specific RSR for DAS (Reference 5)
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 7). 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 6) was developed using guidance in NUREG-0711 (Reference 3).
1.2 Purpose and Approach The purpose of this RSR is to document the results for the Functional Requirements Analysis (FRA), Functional Allocation (FA) and Task Analysis (TA) for the RPS/ESFAS/NIS as part of the Human Factors Engineering (HFE) Analysis for the project.
In the context of the systems modifications, the main purpose of FRA&FA is to identify changes implemented under this project that potentially:
- Introduce new system functions needed to accomplish plant functions.
- Potentially affect system functions that enable achievement of these functions.
- Change the allocation of existing functions achieved by automatic or manual means.
- Define changes or additions to components or software to achieve functions.
To do this, the general approach to perform FRA&FA is:
- Identification of current functional breakdown (system functions and functional requirements) and allocation.
- Review of the system modernization documentation.
- Identification of how each level of analysis is impacted by the modernization - identification of new and/or modified functions, functional requirements, changes in allocation, etc.
The TA provides:
- A basis for confirming or modifying the Human-System Interface (HSI) indications, alarms, and controls.
- Basic information for modifying procedures and training.
- Confirmation of requirements specified for the detail design.
- The basis to verify and later validate that human-performance requirements do not result in excessive operator workload.
To do this, the general approach to perform TA is:
- Identification of operator tasks.
- Review of the system modernization documentation.
- Identification of how each level of analysis (activity, task, scenario) is impacted by the modernization.
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The methodology, processes and activities followed to implement these analyses are described in the HFE Analysis Implementation Plan (Reference 6).
1.3 Scope Scope of the FRA&FA and TA is established in the HFE Analysis Implementation Plan (Reference 6) and is focused on the new and modified functions and tasks associated with the RPS/ESFAS/NIS design modifications under consideration. Impact of elimination of system functions, system functionalities and tasks are also addressed in the analysis. The consequences over the DCS in terms functionalities, screens, HFE needs (alarms, controls, and indications) are also in the scope of the analysis.
The manual control and monitoring tasks to be performed by the operators in the event of a TRICON Software Common Cause Failure (SWCCF) are addressed in this document. Automatic actions performed by the new DAS and related tasks are analyzed and documented in DAS FRA&FA and TA RSR (Reference 5).
The RSR for RPS/ESFAS/NIS and DCS and the RSR for DAS (automatic functions added as functions to the DCS) and DCS, are addressed in separate documents (the present document and Reference 5) but collectively address additions and changes to the control room interface and system functions and functionalities. The Functional Requirements Analysis and Functional Allocation analyses consider the changes that effect both documents. The two documents together address the scope of additions and changes implemented under the project.
The HFE Program Plan (Reference 2) initially planned two RSRs:
- 1. FRA&FA and TA RSR for RPS/ESFAS/NIS
- 2. FRA&FA and TA RSR for DAS and DCS Impacts and HFE needs on DCS came out while doing RPS/ESFAS/NIS analysis, so it was decided to keep them in the same document as a logical result of the analysis. Therefore, the title and scope for the first RSR now includes the DCS too.
- 1. FRA&FA and TA RSR for RPS/ESFAS/NIS and DCS
- 2. FRA&FA and TA RSR for DAS and DCS From this point of the document, it is important to differentiate between new and modified concept, which is applicable for many of the concepts used through the document (function, task, scenario, etc.). Refer to Section 1.5 for the definition of these terms.
1.4 Relationships Between HFE documents This RSR is hierarchically dependent of the HFE Analysis Implementation Plan (Reference 6) and at the same level as the HFE Verification and Validation (V&V) RSRs and the HSI Design and HSI Design RSR. 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 37) and HFE V&V IP (Reference 38) respectively.
The relationship of this document with 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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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. Activity - Single operator action over a plant component, an interface element, or a communication device.
It can also refer to the specific action of a thought process that the operator must carry out.
- 2. HFE Operating Experience Review (OER) Issue - Human performance issue identified during the Operating Experience (OE) search and potentially applicable to any of the HFE elements of the Project HFE Program.
- 3. 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.
- 4. Human-System Interface (HSI) - The point of contact between the human operator and the physical devices.
- 5. 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.
- 6. Important Human Action (IHA)- Human action most important to safety that meets either risk or deterministic criteria.
- 7. Important Operating Sequence (IOS) - Operating sequence that contains one or more Important Human Actions.
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- 8. Input - Documents and databases which may be consulted during the corresponding Project HFE Program element performance.
- 9. 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.
- 10. 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.
- 11. 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.
- 12. Operating Sequence Diagram (OSD) - Graphic representation of the operator tasks sequence during a scenario.
- 13. Project HFE Program Element / Element - Each of the twelve parts in which a Project HFE Program based on NUREG-0711 (Reference 3) is divided.
- 14. 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.
- 15. Scenario - Operational sequence in which several tasks are performed under certain circumstances and operational condition because of an event or plant mode.
- 16. Step - Each of the parts in which a specific IP methodology is divided to develop it.
- 17. System function - the natural action or intended purpose of a system in a specific role. Usually refers to plant system functions that aim to fulfill plant goals.
- 18. System functionality - refers to the system capabilities that enable the system to fulfill its function(s).
- 19. Task - Group of activities with a common objective which can partially or completely fulfill a function.
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS) 1.6 Acronyms ACRP Audio Count Rate Panel AFD Axial Flux Difference AFW Auxiliary Feedwater ALT Actuation Logic Testing ARP Annunciator Response Procedure AP Administrative Procedure CAP Corrective Action Program CET Core Exit Thermocouple COT Channel Operational Test CVCS Chemical and Volume Control System D3 Diversity and Defense in Depth DAS Diverse Actuation System DBA Design Basis Accident DCS Distributed Control System DIHA Deterministic Important Human Action EOP Emergency Operating Procedure ESF Engineered Safety Features ESFAS Engineered Safety Features Actuation System FA Functional Allocation FDC Field Device Controller FPL Florida Power and Light FRA Functional Requirements Analysis GOP General Operating Procedure HFE Human Factors Engineering HHSI High Head Safety Injection HSI Human-System Interface I&C Instrumentation and Control IHA Important Human Action IOS Important Operating Sequence IP Implementation Plan LOCA Loss of Coolant Accident MCB Main Control Board MCL Master Configuration List MCR Main Control Room MSIV Main Steam Isolation Valve NI Nuclear Instrument NIS Nuclear Instrumentation System NOP Normal Operating Procedures OER Operating Experience Review OI Operating Instruction ONOP Off-normal Operating Procedure Page 14
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OSP Operations Surveillance Procedure PLC Programmable Logic Controller PORV Power Operated Relief Valve PTN Turkey Point Plant PWR Pressurized Water Reactor RCCA Rod Control Cluster Assembly RCP Reactor Coolant Pump RCS Reactor Coolant System RIHA Risk-Important Human Action RO Reactor Operator RPS Reactor Protection System RTP Reactor Thermal Power RSR Result Summary Report RT Reactor Trip RTD Resistance Temperature Detector RTP Rated Thermal Power SBLOCA Small-Break Loss of Coolant Accident SD System Description SFCP Surveillance Frequency Control Program SG Steam Generator SGTR Steam Generator Tubes Rupture SI Safety Injection SM Shift Manager SMI Surveillance and Maintenance Instructions SR Safety Related SRS Software Requirement Specification SVDU Safety Video Display Unit SWCCF Software Common Cause Failure SyRS System Requirement Specification TA Task Analysis TCM Tricon Communication Module TIHA Treatment of Important Human Actions TRL Technical Requirements List TRS Task Record Sheet UFSAR Updated Final Safety Analysis Report US Unit Supervisor V&V Verification and Validation VDU Video Display Unit VPA Vertical Panel A VPB Vertical Panel B Page 15
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS) 2.0 APPLICABLE OPERATING EXPERIENCES AND IMPORTANT HUMAN ACTIONS As part of the HFE Planning and Analysis activities of NUREG-0711 (Reference 3), the HFE Analysis IP (Reference 6) establishes an Operating Experience Review (OER) to identify and review HFE-related safety issues. The OER provides information on the past performance of predecessor designs of the systems being changed.
The HFE Analysis IP (Reference 6) also establishes the execution of the Treatment of Important Human Action (TIHA) to identify and evaluate human actions needed to manage the plant under multiple event sequences.
Specific treatment of each Important Human Action (IHA) and Important Operating Sequences (IOS) must be addressed during the execution of the HFE Program elements.
The first step of the FRA, FA and TA process is the review of OEs and IHAs applicable to the execution of element (see Figure 3-1, Figure 4-1 and Figure 5-1). Sources for applicable OEs and IHAs are the OER Result Summary Report (RSR) (Reference 8) and TIHA RSR (Reference 9), respectively.
The following subsections list the applicable OEs and IHAs and describe how they are treated during the execution of the FRA, FA and TA:
2.1 Applicable OEs No OEs applicable to the development of FRA and FA were identified in the OER results. For the Task Analysis, the following disposition and actions have been performed in accordance with the initial HFE evaluation performed in the OER activity (Reference 8):
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APPENDIX B provides context information about the OEs that are applicable to this analysis per Reference 8.
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS) 2.2 Applicable IHAs TIHA results documented in the TIHA RSR (Reference 9) concluded that the IHAs listed below are applicable to the execution of TA for RPS/ESFAS/NIS modification; none of the IHAs identified in the TIHA RSR (Reference 9) are applicable to the execution of the FRA and FA.
As described in the TIHA RSR (Reference 9), the proposed treatment for these IHAs [
]
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Following the criteria described in Section 5.4.1, [
]
3.0 FUNCTIONAL REQUIREMENTS ANALYSIS RESULTS The FRA addresses the new or modified functions resulting from the integration and modification of plant systems.
The process followed is depicted in Figure 3-1 and is described in the HFE Analysis IP (Reference 6).
Figure 3-1: FRA Development Process Step 1: Step 2: Step 3: Step 4:
Review applicable Identify system Identify functional Evaluate system OEs and IHAs functions requirements modifications impact FRA results are described in the following subsections related to the following steps:
- Section 2.0 presents the results from Step 1
- Section 3.1 presents the results from Steps 2 and 3
- Section 3.2 presents the results from Step 4 3.1 System Functions and Functional Requirements Although, the RPS, ESFAS and NIS system will be integrated in the same Tricon v.10 digital platform, from a functional perspective they can be treated as independent systems. The modification does not add high-level functions that aims to fulfill plant goals to the RPS/ESFAS and NIS. Therefore, to evaluate the modified ones, this section presents the existing system functions and functional requirements for:
- RPS (see Subsection 3.1.1),
- ESFAS (see Subsection 3.1.2),
- NIS (see Subsection 3.1.3), and
- DCS (see Subsection 3.1.4).
3.1.1 RPS System Functions and Functional Requirements Page 19
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]
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NIS-F02: [ ]
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NIS-F03: [ ]
3.1.4 DCS System Functions and Functional Requirements The DCS at PTN 3&4 is based on the Foxboro DCS platform. The existing architecture consists of [
]
DCS-F01: [ ]
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS) 3.2 Systems Modification Impact on Functional Breakdown To evaluate the impact of the modification on the systems functional breakdown described in Section 3.1, the following documentation has been reviewed to understand the extent of the planned modification:
The RPS/ESFAS/NIS modification is planned such that it maintains the same 4 channels and 2 trains division physical separation implemented in the existing RPS, ESFAS, and NIS. The Safety Related functions performed in each division are the same as existing systems (Reference 7). [
]
The RPS/ESFAS/NIS SyRS (Reference 7) also establishes that the existing field sensors that are input into the RPS and ESFAS, [
]
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Figure 3-2: Protection System Component Replacement Scope (Reference 7)
The new platform will also include self-diagnostics capabilities (Reference 7). This is in agreement with FPL goals and expectations for the modification described in SPEC-IC-108 (Reference 16), that establishes that the upgraded systems will have increased capabilities, enhanced self-diagnostics and increased monitoring capability. Alarms and information will be included in the MCR to alert the operators of component trouble or failure, so they are aware that the system functions identified in Section 3.1 are available.
Associated with the RPS/ESFAS/NIS scope of the Digital Modernization Project, the DCS modifications are summarized as follows (Reference 4):
- Addition of Tricon-DCS communications interfaces and associated data, graphics and logic Page 25
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS) o Data includes process parameters and alarms, protection system statuses, setpoints and constants, and data credited for cyber security.
o New Tricon health/diagnostic graphics and annunciation.
o Replication of RPS/ESFAS Safety Video Display Unit (SVDU) graphics in the DCS.
o Logic for automated sensor channel checks.
o Addition of non-safety Video Display Units (VDUs) on Main Control Room (MCR) panel C03.
o Addition of monitoring logic for new DAS power supplies.
o Relocation of points currently hardwired to the DCS over to the Tricon-DCS communication interface.
- Implementation of process parameter indications required to be diverse from the Tricon platform.
- Relocation of auxiliary nuclear instrumentation functions to the DCS (Source Range audible count rate and Power Range deviation alarms).
These modifications affect mainly the DCS architecture and HSI, [
]
4.0 FUNCTIONAL ALLOCATION RESULTS The FA consists of assigning a responsible agent (human or automation) to each function identified in the execution of the FRA.
The process followed is depicted in Figure 4-1 and is described in the HFE Analysis IP (Reference 6).
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Figure 4-1: FA Development Process Step 1: Step 2: Yes Step 3:
New Review applicable Classify functions Perform allocation function?
OEs and IHAs from FRA process No Step 4:
Evaluate system modifications impact As described in Section 3.2, [ ]
Therefore, the FA process is limited to the Steps 1, 2 and 4 depicted in Figure 4-1 (execution of Step 3 is not applicable).
FA results are described in the following subsections related to the following steps:
- Section 2.0 presents the results from Step 1
- Section 4.1 presents the results from Step 2
- Section 4.2 presents the results from Step 4 4.1 Existing Functional Allocation As described in the HFE Analysis IP (Reference 6), [
]
The allocation for each system function identified in Section 3.1 is presented below:
RPS-F01: [ ]
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ESFAS-F01: [
]
NIS-F01: [ ]
NIS-F02: [ ]
NIS-F03: [ ]
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DCS-F01: [ ]
4.2 Systems Modification Impact on Functional Allocation
[
] Initiation and performance of protective actions must be automatic, as established in the plant UFSAR Chapter 7 (Reference 11), which is maintained after the upgrade. As depicted in Figure 3-2, existing manual initiation of reactor trip and protective actions is not modified due to the project.
The replacement of existing NIS indications and controls by four Safety Video Display Units (SVDUs) and the inclusion of the NIS in the protection channel sets [
] The reactor trip and ESFAS, Permissives and interlocks logics are not modified as a result of the modification.
The allocation of DCS high-level functions [ ] Main impact on the DCS is the addition of DAS; impact on the FA for specific DAS functions is documented in the FRA&FA and TA RSR for DAS (Reference 5).
5.0 TASK ANALYSIS RESULTS The objective of TA is to identify the task requirements for accomplishing the functions allocated to plant personnel or in other words how the functions are controlled.
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The process followed is depicted in Figure 5-1 and it is described in the HFE Analysis IP (Reference 6).
Figure 5-1: TA Development Process Step 1: Step 3: Step 5:
Step 2: Step 4:
Review applicable Evaluate system Develop OSD Identify tasks Identify scenarios OEs and IHAs modifications impact (as applicable)
TA results are described in the following subsections related to the following steps:
- Section 2.0 presents the results from Step 1
- Section 5.1 presents the results from Step 2 and Step 3
- Section 5.2 presents a summary of HSI requirements obtained from the tasks narratives (see APPENDIX A)
- Section 5.3 presents the results from Step 4
- Section 5.4 presents the results from Step 5 5.1 Systems Modification Impact on Operator Tasks This section presents the results of the evaluation performed to identify the RPS/ESFAS/NIS new and modified tasks due to the system upgrade.
The identification of existing tasks related to the operation of the RPS/ESFAS/NIS to determine if and how they are affected by the system modification is based on the review of different inputs and analysis results. The process and inputs used are described below:
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All the task modified due to the system upgrade (change in task narrative, relation of activities and/or HSI requirements) are codified following the coding structure presented in the HFE Analysis IP (Reference 6):
[SysID1]-[SysID2]--T[n] System function identification (TaskID)
SysID = System identification defined by System documentation. If the task contains activities from different systems, both systems will be included. (i.e., RPS-ESFAS-T01) n = Correlative number beginning with 1 for each system Page 32
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Table 5-1: Evaluation of the RPS/ESFAS/NIS upgrade impact on existing system tasks [ ]
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Table 5-2: Additional modified RPS/ESFAS/NIS tasks identified from the review of the SyRSs/SRS Page 43
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To summarize, the evaluation concluded that the modified and new tasks for the RPS/ESFAS/NIS upgrade are the following (see Table 5-1 and Table 5-2):
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS) 5.2 HSI requirements As described in the HFE Analysis IP (Reference 6), a summary table to collect all HSI requirements that resulted from the analysis is prepared (see Table 5-3). [
] Details on how these requirements are met in the design are provided in the HSI Design RSR (see HSI Design IP (Reference 37) for details) and other design documents.
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[
]
Note 2: the activity and its requirement is applicable to Protection Channel Sets CHI, CHII, CHIII and CHIV, and analog inputs.
Note 3: a list of typical diagnostic alarms is included in the MCR Design Change Description (Reference 15).
Note 4: the activity and its requirement are applicable to the process variables that are input to the RPS/ESFAS/NIS channels Note 5: detail of all RPS/ESFAS logic status lights relocated from panel C05 is included in the MCR Design Change Description (Reference 15).
Note 6: the list of diverse indications is included in APPENDIX E.
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Engineered Safety Features Actuation System (ESFAS), Nuclear Instrumentation System (NIS) and Distributed Control System (DCS) 5.3 Scenarios This section identifies scenarios that are impacted by the modification. The results constitute a list of selectable scenarios for the HFE V&V, Procedure Development and Training Program Development activities.
Scenarios impacted by the modification are identified based on:
5.3.1 Scenarios impacted by new and modified tasks The list of scenarios modified by the tasks identified in Section 5.1 is provided in Table 5-4. Per scenario, the specific tasks that impact the scenario are indicated.
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Table 5-4: Scenarios from TA Page 63
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] because they include additional HFE impacts to evaluate besides the ones in Section 5.3.1 and Section 5.3.2.
Table 5-6: Additional Scenarios 5.4 Operating Sequence Diagrams An OSD is a graphical representation of tasks sequences that considers a preliminary staffing of activities and their estimated duration. It aims to show the relationship of the actions that the different operators must perform to evaluate the total duration of the sequence, operators workload, and possible conflicts related to the execution of certain actions.
In this case, this representation is done at task level, since it groups activities that must be performed uninterruptedly and are assigned to a single operator.
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It must be noted that, at this stage of the program, task times has been estimated based on general PWR technology knowledge and a conservative safety perspective. Therefore, conclusions from this analysis are preliminary and total duration of tasks and sequences should be confirmed by PTN 3&4 operations and fully evaluated jointly during the HFE V&V activities.
The final purpose of the OSD is to complement HFE V&V activities, providing a summary of scenarios to be validated.
The OSDs in APPENDIX C show the sequential tasks per operator for each OS. Each OSD column is read from top to bottom. Finally, height of each task representation within the diagram considers its estimated duration.
All the figures include the time scale used in the representation.
5.4.1 Rationale for selecting scenarios for OSD development Note that this selection of scenarios does not exclude any other from the Sampling of Operational Conditions for the validation activities (HFE V&V). For that activity, all modified scenarios identified in Section 5.3 are inputs. [ ]
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6.0 CONCLUSION
S This RSR documents the results for the FRA, FA and TA elements for 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 6).
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The RPS/ESFAS/NIS modification description provided in the SyRSs (Reference 4 and 7) and the MCR Design Change Description (Reference 15) was reviewed to evaluate if these functions are modified due to the project.
[
]
Functional requirements related to functions availability will be modified. The installation of a Tricon digital-based platform will change the parameters, signals and/or equipment that provide information on the availability of the I&C system. New annunciators that alert the operators of system unavailability will be installed in panel G of the MCR (Reference 15); typical causes of system unavailability that actuates the annunciators are listed in Reference 15 and will be detailed in design documents. Besides, the installation of enhanced system capabilities, such as the system self-diagnostics reduces the functional requirements needed to evaluate the system functions availability and has an impact on operators role as described in the FA results.
Section 4.1 identifies the current allocation for the functions listed above. [
]
Based on the FA results and supported by plant procedures, existing tasks were identified and evaluated against the modifications description provided by the system SyRSs (Reference 4 and 7) and the MCR Design Change Description (Reference 15). The evaluation of each existing task is provided in Table 5-1. New tasks were also identified related to system maintenance and surveillance. [
]
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These tasks are codified as described in HFE Analysis IP (Reference 6). A TRS is developed per task to describe the task narrative. TRSs are included in APPENDIX A. [
] additional inputs and requirements for the HSI Design are described in the HSI Design IP (Reference 37).
Besides the tasks listed above, [
]
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The results of modified scenarios constitute a list of selectable scenarios for the HFE V&V, Procedure Development and Training Program Development activities. Besides, the list of scenarios was evaluated to select scenarios to develop OSDs. [ ]
OSDs are included in APPENDIX C. The OSDs include tasks that are new or modified by the project (codified tasks which are depicted in bold letters) and existing tasks which are expected to be executed as always (depicted in italics) and which are sometimes grouped to simplify the OSD development. Tasks durations are estimated based on general PWR technology and a conservative safety perspective, and they should be confirmed by PTN 3&4 operations and fully evaluated jointly during the HFE V&V activities. [
] these group of tasks are not modified, and their duration have no impact on OSD conclusions, so the duration was not included to simplify the development and OSD depiction.
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From the OSDs the following conclusions can be drawn:
7.0 REFERENCES
The following lists documents 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. NUREG-0711, Human Factors Engineering Program Review Model, Revision 3.
- 4. [
]
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- 5. [
]
- 6. [
]
- 7. [
]
- 8. [
]
- 9. [
]
- 10. *Florida Power and Light, Turkey Point Nuclear Station, System Description No. 063, Reactor Protection and Safeguards Actuation System (SYS. 049, 063).
- 11. *Florida Power and Light, Turkey Point Unit 3&4, Updated FSAR.
- 12. *Florida Power and Light, Turkey Point Unit 3&4, Logic diagram 5610-M-401-126 (SH. 2,10, 12, 13, 14).
- 13. *Florida Power and Light, Turkey Point Unit 3&4, Logic diagram 5610-T-L1 SH. 11.
- 14. *Florida Power and Light, Turkey Point Nuclear Station, System Description No. 004, Excore Nuclear Instrumentation (SYS. 059A).
- 15. [
]
- 16. Florida Power and Light, Engineering Procurement Specification - PTN3&4 RPS/ESFAS and SR Control Systems Replacements, SPEC-IC-108 Revision 2.
- 17. *Florida Power and Light, Turkey Point Unit 3&4, Logic diagram 5610-T-L1 SH. 21.
- 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)-GOP-503, Cold Shutdown to Hot Standby.
- 20. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-GOP-301, Hot Standby to Power Operation.
- 21. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-GOP-103, Power Operation to Hot Standby.
- 22. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-GOP-305, Hot Standby to Cold Shutdown.
- 23. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-ARP-097.CR.C, Control Room Response -
Panel C.
- 24. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-ARP-097.CR.H, Control Room Response -
Panel H.
- 25. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-E-1, Loss Of Reactor Or Secondary Coolant.
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- 26. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-FR-H.1, Response To Loss Of Secondary Heat Sink.
- 27. *Florida Power and Light, Turkey Point Unit 3&4, Logic diagram 5613-T-L1 SH. 2.
- 28. *Florida Power and Light, Turkey Point Unit 3&4, Logic diagram 5610-T-L1 SH. 16.
- 29. *Florida Power and Light, Turkey Point Unit 3&4, Logic diagram 5610-T-L1 SH. 17.
- 30. *Florida Power and Light, Turkey Point Unit 3&4, Technical Specifications.
- 31. *Florida Power and Light, Turkey Point Unit 3&4, 3-OSP-059.1 Rev.5, Source Range Nuclear Instrumentation Analog Channel Operational Test.
- 32. *Florida Power and Light, Turkey Point Unit 3&4, 3-OSP-059.2A Rev.3, Intermediate Range Nuclear Instrumentation Analog Channel Operational Test For N35.
- 33. *Florida Power and Light, Turkey Point Unit 3&4, 3-OSP-059.2B Rev.3, Intermediate Range Nuclear Instrumentation Analog Channel Operational Test For N36.
- 34. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-ARP-097.CR.G, Control Room Response -
Panel G.
- 35. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-ARP-097.CR.B, Control Room Response - Panel B.G.
- 36. [
]
- 37. [
]
- 38. [
]
- 39. [
]
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APPENDIX A. TASK RECORD SHEETS Table A-1: TRS for ESFAS-T01 [ ]
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Table A-2: TRS for ESFAS-T02 [ ]
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Table A-3: TRS for NIS-T01 [ ]
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Table A-4: TRS for NIS-T02 [ ]
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Table A-5: TRS for NIS-T03 [ ]
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Table A-6: TRS for NIS-T04 [ ]
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Table A-7: TRS for NIS-T05 [ ]
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Table A-8: TRS for NIS-T06 [ ]
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Table A-9: TRS for NIS-T07 [ ]
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Table A-10: TRS for NIS-T08 [ ]
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Table A-11: TRS for NIS-T09 [ ]
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Table A-12: TRS for NIS-T10 [ ]
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Table A-13: TRS for NIS-T11 [ ]
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Table A-14: TRS for NIS-T12 [ ]
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Table A-15: TRS for NIS-T13 [ ]
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Table A-16: TRS for NIS-T14 [ ]
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Table A-17: TRS for NIS-T15 [ ]
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Table A-18: TRS for NIS-T16 [ ]
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Table A-19: TRS for RPS-ESFAS-NIS-T01 [ ]
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Table A-20: TRS for RPS-ESFAS-NIS-T02 [ ]
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Table A-21: TRS for RPS-ESFAS-NIS-T03 [ ]
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Table A-22: TRS for RPS-ESFAS-NIS-T04 [ ]
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Table A-23: TRS for RPS-ESFAS-NIS-T05 [ ]
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Table A-24: TRS for RPS-ESFAS-NIS-T06 [ ]
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Table A-25: TRS for RPS-ESFAS-NIS-T07 [ ]
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Table A-26: TRS for GEN-T01 [ ]
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Table A-27: TRS for GEN-T02 [ ]
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APPENDIX B. DESCRIPTION OF APPLICABLE OE Table B-1: OER Analysis Results Page 124
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APPENDIX C. OPERATING SEQUENCE DIAGRAMS This appendix presents the OSDs for the scenarios selected in Section 5.4.
An OSD is a graphical representation of tasks sequences that considers a preliminary staffing of activities and its estimated duration. It aims to show the relationship of the actions that the different operators must perform to evaluate the total duration of the sequence, operators workload, and possible conflicts related to the execution of certain actions.
In this case, this representation is done at task level, since it groups activities that must be performed uninterruptedly and are assigned to a single operator.
It must be noted that at this stage of the program, relevant information for the task duration evaluation was not available, such as the plant response time or the interface navigation time. Therefore, conclusions from this analysis are preliminary and total duration of tasks and sequences should be fully evaluated during V&V activities. The estimation of the tasks duration has been performed based on a systematic approach that assigns an average duration to each activity depending on its nature. The activity duration has been obtained through a series of tests using a generic Pressurized Water Reactor (PWR) simulator and TECNATOM experience in plant operation .
The final purpose of the OSD is to complement V&V activities, providing a summary of a scenario evaluation for further analysis.
The following figures show for the sequential tasks per operator: Unit Supervisor (US), Reactor Operators (ROs), Auxiliary Operator (AO) and I&C engineer. Finally, height of each task representation within the diagram considers its estimated duration. All the figures include the time scale used in the representation. Last figure of this Appendix includes the legend of symbols used in the OSDs.
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APPENDIX D. PANEL C03 INDICATIONS Table D-1: Panel C03 Indications (Reference 15)
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APPENDIX E. DIVERSE INDICATIONS Table E-1: Diverse indications from TRICON (Reference 36)
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Turkey Point Nuclear Plant L-2023-010 Docket Nos 50-250 and 50-251 Attachment 6 ATTACHMENT 6 SUPPLEMENTAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST 274 REACTOR PROTECTION SYSTEM, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, AND NUCLEAR INSTRUMENTATION SYSTEM REPLACEMENT PROJECT FUNCTIONAL REQUIREMENTS ANALYSIS, FUNCTIONAL ALLOCATION AND TASK ANALYSIS DIVERSE ACTUATION SYSTEM (DAS) AND DISTRIBUTED CONTROL SYSTEM (DCS)
RESULTS
SUMMARY
REPORT (79 pages follow)
(REDACTED)
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Framatome Inc.
RESULTS
SUMMARY
REPORT Document No.: 51 - 9355273 - 004 Functional Requirements Analysis, Functional Allocation and Task Analysis - Diverse Actuation System (DAS) and Distributed Control System (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: Steve Kane Approver: Brian Haynes Signature and Date Signature and Date Signature and Date Page 1 of 79
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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 LP All Project Engineer 2/2/2023 Jacek Nowakowski JK NOWAKOWSKI 2/2/2023 LR All Project Engineer Brian Haynes BM HAYNES A All 2/2/2023 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 RO JAWOROWSKI Ron Jaworowski Project Manager 2/2/2023 Page 2
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Record of Revision Revision Pages/Sections/
Brief Description / Change Authorization No. Paragraphs Changed 000 All Initial issuance Document revision to incorporate comments from:
001 All
- F.505454-OUT-0760-000 DRCS Combined comments Final Title page Modified proprietary data declaration.
002 7.0 Added revisions to references 2, 4-6, 8-11, 13-14 and 16.
Corrected all table captions from Table 7-n to Table A-n.
003 Appendix A Table of Contents updated accordingly.
Record of Revision Corrected description of title page change in Rev 002.
Title Page Modified proprietary data declaration.
004 2.1 Rephrased bullet 1 to align with the OER.
7.0 Updated revisions of references 8 and 9.
Appendix B Updated to align with the OER.
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Table of Contents Page
1.0 INTRODUCTION
........................................................................................................................... 7 1.1 Background ....................................................................................................................... 7 1.2 Purpose and Approach...................................................................................................... 7 1.3 Scope ................................................................................................................................ 8 1.4 Relationships Between HFE documents ........................................................................... 9 1.5 Terms and Definitions ....................................................................................................... 9 1.6 Acronyms ........................................................................................................................ 11 2.0 APPLICABLE OPERATING EXPERIENCES AND IMPORTANT HUMAN ACTIONS ............... 12 2.1 Applicable OEs ................................................................................................................ 12 2.2 Applicable IHAs ............................................................................................................... 13 3.0 FUNCTIONAL REQUIREMENTS ANALYSIS RESULTS ........................................................... 14 3.1 Systems Modification Impact on Functional Breakdown ................................................ 14 4.0 FUNCTIONAL ALLOCATION RESULTS .................................................................................... 16 4.1 Functional Allocation for the DAS new functions............................................................. 17 5.0 TASK ANALYSIS RESULTS....................................................................................................... 19 5.1 Systems Modification Impact on Operator Tasks ........................................................... 19 5.2 HSI requirements ............................................................................................................ 22 5.3 Scenarios ........................................................................................................................ 35
6.0 CONCLUSION
S .......................................................................................................................... 37
7.0 REFERENCES
............................................................................................................................ 39 APPENDIX A. TASK RECORD SHEETS ................................................................................ 41 APPENDIX B. DESCRIPTION OF APPLICABLE OE .............................................................. 74 Page 4
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List of Tables Page Table 5-1: New operator tasks for the DAS ....................................................................................................... 20 Table 5-2: Summary of HSI requirements ......................................................................................................... 24 Table 5-3: Scenarios affected by the installation of DAS ................................................................................ 35 Table A-1: TRS for DAS-T01 [ ] .............................................................................. 41 Table A-2: TRS for DAS-T02 [ ] ............................................................................ 43 Table A-3: TRS for DAS-T03 [ ] ..................................................... 45 Table A-4: TRS for DAS-T04 [ ] ..................................................................... 47 Table A-5: TRS for DAS-T05 [ ] ............................................................... 50 Table A-6: TRS for DAS-T06 [ ] .................................................................................... 53 Table A-7: TRS for DAS-T07 [ ] ............................................................................... 56 Table A-8: TRS for DAS-T08 [ ] ............................................ 58 Table A-9: TRS for DAS-T09 [ ] ...................................... 61 Table A-10: TRS for DAS-T10 [ ] ........................................ 64 Table A-11: TRS for DAS-T11 [
] ................................................................................................................................................. 66 Table A-12: TRS for DAS-T12 [ ] ............................................... 67 Table A-13: TRS for DAS-T13 [ ] .............................................................................. 69 Table A-14: TRS for DAS-T14 [ ] ..................................................... 70 Table A-15: TRS for DAS-T15 [ ] ................................................................................... 71 Table A-16: TRS for DAS-T16 [ ] ......................................................................... 72 Page 5
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List of Figures Page Figure 1-1: Relationships between HFE Documents ................................................................................ 9 Figure 3-1: FRA Development Process .................................................................................................. 14 Figure 4-1: FA Development Process ..................................................................................................... 16 Figure 4-2: Function Allocation Flowchart Based on NUREG/CR-3331 (Reference 8) Guidelines ........ 18 Figure 5-1: TA Development Process ..................................................................................................... 19 Page 6
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1.0 INTRODUCTION
1.1 Background
Florida Power and Light (FPL) has contracted Framatome to provide digital system replacement 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 Main Control Room (MCR) or other interfaces with which operations and maintenance 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 new Diverse Actuation System (DAS). The need for a new DAS is related to the modernization of the Reactor Protection System (RPS), Engineered Safety Features Actuation System (ESFAS) and Nuclear Instrumentation System (NIS) (hereafter referred as RPS/ESFAS/NIS) to a digital-based system (Reference 3). The Diversity and Defense-in-Depth (D3) evaluation (Revision 004 of Reference 4) of the RPS/ESFAS/NIS modernization concluded that the installation of digital-based RPS/ESFAS/NIS systems presents a licensing 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. As a consequence, the D3 Evaluation defines automatic protective functions that must be implemented in a platform diverse from the Tricon (the new DAS) to mitigate this event.
The DAS is not a standalone system; it will exist as a set of new functions within the overall DCS architecture (Reference 5). However, for HFE analysis purposes, it will be treated as a system.
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)
(Reference 6); the HFE Analysis IP was developed using guidance in NUREG-0711 (Reference 7).
1.2 Purpose and Approach The purpose of this RSR is to document the results of the Functional Requirements Analysis (FRA), Functional Allocation (FA) and Task Analysis (TA) for the DAS as part of the HFE Analysis for the project.
In the context of the systems modifications, the main purpose of FRA&FA is to identify changes implemented under this project that potentially:
- Introduce new system functions needed to accomplish plant functions.
- Potentially affect system functions that enable achievement of these functions.
- Change the allocation of existing functions achieved by automatic or manual means.
- Define changes or additions to components or software to achieve functions.
To do this, the general approach to perform FRA&FA is:
- Identification of current functional breakdown (system functions and functional requirements) and allocation.
- Review of the system modernization documentation.
- Identification of how each level of analysis is impacted by the modernization - identification of new and/or modified functions, functional requirements, changes in allocation, etc.
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The TA provides:
- A basis for confirming or modifying the Human-System Interface (HSI) indications, alarms, and controls.
- Basic information for modifying procedures and training.
- Confirmation of requirements specified for the detail design.
- The basis to verify and later validate that human-performance requirements do not result in excessive operator workload.
To do this, the general approach to perform TA is:
- Identification of operator tasks.
- Review of the system modernization documentation.
- Identification of how each level of analysis (activity, task, scenario) is impacted by the modernization.
The methodology, processes and activities followed to implement these analyses are described in the HFE Analysis Implementation Plan (Reference 6).
1.3 Scope Scope of the FRA&FA and TA is established in the HFE Analysis Implementation Plan (Reference 6) and is focused on the new and modified functions and tasks associated with the DAS design modifications under consideration. The DAS is implemented as a set of new functions on the Foxboro DCS platform. As part of the project, the DCS will be also modified to implement a series of modifications associated with the RPS/ESFAS/NIS portion of the project (Reference 5). HFE Analysis results associated with those modifications to the DCS as well as manual control and monitoring tasks to be performed by the operators in the event of a TRICON Software Common Cause Failure (SWCCF) are documented in the FRA&FA and TA RSR for the RPS/ESFAS/NIS and DCS (Reference 8).
The RSR for RPS/ESFAS/NIS and DCS and the RSR for DAS (automatic functions added as functions to the DCS) and DCS, are addressed in separate documents (the present document and Reference 8) but collectively address additions and changes to the control room interface and system functions and functionalities. The Functional Requirements Analysis and Functional Allocation analyses consider the changes that effect both documents. The two documents together address the scope of additions and changes implemented under the project.
The HFE Program Plan (Reference 2) initially planned two RSRs:
- 1. FRA&FA and TA RSR for RPS/ESFAS/NIS
- 2. FRA&FA and TA RSR for DAS and DCS Impacts and HFE needs on DCS came out while doing RPS/ESFAS/NIS analysis, so it was decided to keep them in the same document as a logical result of the analysis. Therefore, the title and scope for the first RSR now includes the DCS too.
- 1. FRA&FA and TA RSR for RPS/ESFAS/NIS and DCS
- 2. FRA&FA and TA RSR for DAS and DCS From this point of the document, it is important to differentiate between new and modified concept, which is applicable for many of the concepts used through the document (function, task, scenario, etc.). Refer to section 1.5 for the definition of these terms.
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Document No.: 51-9355273-004 Functional Requirements Analysis, Functional Allocation and Task Analysis - Diverse Actuation System (DAS) and Distributed Control System (DCS) 1.4 Relationships Between HFE documents This RSR is hierarchically dependent of the HFE Analysis Implementation Plan (Reference 6) and at the same level as the HFE Verification and Validation (V&V) RSRs and the HSI Design and HSI Design RSR. 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 DAS/DCS. 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
- 14) and HFE V&V IP (Reference 16) respectively.
The relationship of these documents with 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).
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. Activity - Single operator action over a plant component, an interface element, or a communication device.
It can also refer to the specific action of a thought process that the operator must carry out.
- 2. HFE Operating Experience Review (OER) Issue - Human performance aspect identified during the Operating Experience (OE) search and potentially applicable to any of the HFE elements of the Project HFE Program.
- 3. 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.
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- 4. Human-System Interface (HSI) - The point of contact between the human operator and the physical devices.
- 5. 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 generates acceptable results that satisfy the staffs review criteria.
- 6. Important Human Action (IHA) - Human action most important to safety that meets either risk or deterministic criteria.
- 7. Important Operating Sequence (IOS) - Operating sequence that contains one or more Important Human Actions.
- 8. Input - Documents and databases that may be consulted during the corresponding Project HFE Program element performance.
- 9. 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 modification.
- 10. New concept - where concept refers to different items of the analysis (important human action, important operating sequence, etc.). New refers to aspects that did not exist before modification.
- 11. NUREG - Series Publications of Reports or brochures on regulatory decisions, results of research, results of incident investigations, and other technical and administrative information that are prepared by the United States NRC Staff or its Contractors.
- 12. Operating Sequence Diagram (OSD) - Graphic representation of the operator tasks sequence during a scenario.
- 13. Preliminary Validation - Each of the tests conducted and grouped in time as stages that allow meaningful aggregation, summation, or comparison of results to support interim or final validation conclusions; and which are conducted from early (conceptual) to detailed stages of design development
- 14. Project HFE Program Element / Element - Each of the twelve parts in which a Project HFE Program based on NUREG-0711 (Reference 7) is divided.
- 15. 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.
- 16. Scenario - Operational sequence in which several tasks are performed under certain circumstances and operational condition because of an event or plant mode.
- 17. Staged validation testing approach - Specific approach for validating systems through a series of successive, coordinated activities performed at multiple points or periods during the development or modification of a control room design.
- 18. System function - the natural action or intended purpose of a system in a specific role.
- 19. System functionality - refers to the system capabilities that enable the system to fulfill its function(s).
- 20. Task - Group of activities with a common objective which can partially or completely fulfill a function.
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Document No.: 51-9355273-004 Functional Requirements Analysis, Functional Allocation and Task Analysis - Diverse Actuation System (DAS) and Distributed Control System (DCS) 1.6 Acronyms AFW Auxiliary Feedwater ARP Annunciator Response Procedure D3 Diversity and Defense-in-Depth DAS Diverse Actuation System DCS Distributed Control System EOP Emergency Operating Procedure ESF Engineered Safety Feature ESFAS Engineered Safety Features Actuation System FA Functional Allocation FBM Field Bus Module FCP Field Control Processor FPL Florida Power and Light FRA Functional Requirements Analysis FW Feedwater HFE Human Factors Engineering HHSI High Head Safety Injection HSI Human-System Interface I&C Instrumentation and Control IHA Important Human Action IOS Important Operating Sequence IP Implementation Plan ISV Integrated System Validation LOCA Loss of Coolant Accident MCR Main Control Room NIS Nuclear Instrumentation System OER Operating Experience Review OSD Operating Sequence Diagram PTN Turkey Point Plant PV Preliminary Validation RCCA Rod Control Cluster Assembly RO Reactor Operator RPS Reactor Protection System RSR Result Summary Report RTP Reactor Thermal Power SBLOCA Small Break Loss of Coolant Accident SG Steam Generator SGTR Steam Generator Tube Rupture SI Safety Injection Page 11
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SR Safety Related SVDU Safety Video Display Unit SWCCF Software Common Cause Failure SyRS System Requirement Specification TA Task Analysis TIHA Treatment of Important Human Actions TRS Task Record Sheet UFSAR Updated Final Safety Analysis Report US Unit Supervisor V&V Verification and Validation VDU Video Display Unit 2.0 APPLICABLE OPERATING EXPERIENCES AND IMPORTANT HUMAN ACTIONS As part of the HFE Planning and Analysis activities of NUREG-0711 (Reference 3), the HFE Analysis IP (Reference 6) establishes an Operating Experience Review (OER) to identify and review HFE-related safety issues. The OER provides information on the past performance of predecessor designs of the systems and components being changed or added.
The HFE Analysis IP (Reference 6) also establishes the execution of the Treatment of Important Human Action (TIHA) to identify and evaluate human actions needed to manage the plant under multiple event sequences.
Specific treatment of each Important Human Action (IHA) and Important Operating Sequences (IOS) must be addressed during the execution of the HFE Program elements.
The first step of each analysis process is the review of OEs and IHAs applicable to the execution of FRA, FA and TA (see Figure 3-1, Figure 4-1 and Figure 5-1, respectively). Sources for applicable OEs and IHAs are the OER Result Summary Report (RSR) (Reference 9) and TIHA RSR (Reference 10), respectively.
The following subsections list the applicable OEs and IHAs and describe how they are treated during the execution of the FRA, FA and TA:
2.1 Applicable OEs The following OEs identified in the OER RSR (Reference 9) have been considered during the development of TA for DAS; applicable OEs to the development of FRA and FA were not identified in the OER results:
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APPENDIX B provides context information about the OEs that are applicable per Reference 9.
2.2 Applicable IHAs
[
]
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Document No.: 51-9355273-004 Functional Requirements Analysis, Functional Allocation and Task Analysis - Diverse Actuation System (DAS) and Distributed Control System (DCS) 3.0 FUNCTIONAL REQUIREMENTS ANALYSIS RESULTS The FRA addresses the new or modified functions resulting from the integration and modification of plant systems.
The process followed is depicted in Figure 3-1 and is described in the HFE Analysis IP (Reference 6).
Figure 3-1: FRA Development Process Step 1: Step 2: Step 3: Step 4:
Review applicable Identify system Identify functional Evaluate system OEs and IHAs functions requirements modifications impact FRA results are described in the following subsections related to the following steps:
- Section 2.0 presents the results from Step 1
- Section 3.1 presents the results from Steps 2, 3 and 41 3.1 Systems Modification Impact on Functional Breakdown The DAS is a new system and therefore, all its functions are new. To identify these new system functions, the following documentation has been reviewed to understand the extent of the planned modification:
The DAS will duplicate2 a subset of the protective functions performed by the RPS and ESFAS (Reference 5).
Consequently, the DAS functions are equivalent to those existing for the RPS and ESFAS, which are documented in the RSR for the RPS/ESFAS/NIS modification (Reference 8). [
]
1 The DAS is a new I&C system; there are not existing functions associated with this system.
2
[ ] DAS.
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Document No.: 51-9355273-004 Functional Requirements Analysis, Functional Allocation and Task Analysis - Diverse Actuation System (DAS) and Distributed Control System (DCS) 3 These functional requirements are presented descriptively; reference for specific plant equipment or components IDs (transmitters, breaker, etc.) are not included nor needed for the analysis.
4
[
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Document No.: 51-9355273-004 Functional Requirements Analysis, Functional Allocation and Task Analysis - Diverse Actuation System (DAS) and Distributed Control System (DCS) 4.0 FUNCTIONAL ALLOCATION RESULTS The FA consists of assigning a responsible agent (human or automation) to each function identified in the execution of the FRA.
The process followed is depicted in Figure 4-1 and is described in the HFE Analysis IP (Reference 6).
Figure 4-1: FA Development Process Step 1: Step 2: Yes Step 3:
New Review applicable Classify functions Perform allocation function?
OEs and IHAs from FRA process No Step 4:
Evaluate system modifications impact As described in Section 3.1, [ ] Therefore, following the process in Figure 4-1, the FA process consists in the execution of the Steps 1, 2 and 3 (Step 4 is not applicable). FA results are described in the following sub-sections5.
5
[
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[ ] FA results are described in the following subsections related to the following steps:
- Section 2.0 presents the results from Step 1
- Section 4.1 presents the results from Step 3 4.1 Functional Allocation for the DAS new functions As described in the HFE Analysis IP (Reference 6), [
]
The allocation process is based on the guidelines depicted in Figure 4-2, and the philosophy of operation of the DAS; the system performs protective functions that replicate RPS and actuates select ESFAS functions, and, therefore, the allocation of these functions is the same as for the equivalent RPS and ESFAS functions.
[
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Figure 4-2: Function Allocation Flowchart Based on NUREG/CR-3331 (Reference 8) Guidelines The allocation of each function identified in Section 3.1 is presented below:
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Document No.: 51-9355273-004 Functional Requirements Analysis, Functional Allocation and Task Analysis - Diverse Actuation System (DAS) and Distributed Control System (DCS) 5.0 TASK ANALYSIS RESULTS The objective of TA is to identify the task requirements for accomplishing the functions allocated to plant personnel or in other words how the functions are controlled.
The process followed is depicted in Figure 5-1 and is described in the HFE Analysis IP (Reference 6)
Figure 5-1: TA Development Process Step 1: Step 3: Step 5:
Step 2: Step 4:
Review applicable Evaluate system Develop OSD Identify tasks Identify scenarios OEs and IHAs modifications impact (as applicable)
TA results are described in the following subsections related to the following steps:
- Section 2.0 presents the results from Step 1
- Section 5.1 presents the results from Step 2 and Step 3
- Section 5.3 presents the results from Step 4 and Step 5
- Section 5.2 presents a summary of HSI requirements obtained from the tasks narratives (see APPENDIX A) 5.1 Systems Modification Impact on Operator Tasks All tasks are codified for tracking purposes within the analysis, following the coding structure presented in the HFE Analysis IP (Reference 6):
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[SysID1]-[SysID2]--T[n] System function identification (TaskID)
SysID = System identification defined by System documentation.
n = Correlative number beginning with 1 for each system These results are presented in Table 5-1. This table includes the following information:
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] Details on how Page 22
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Note 1 - the summary of DAS actuations alarms that drive the annunciator are listed in the MCR Design Change Description (Reference 11).
[
]
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Document No.: 51-9355273-004 Functional Requirements Analysis, Functional Allocation and Task Analysis - Diverse Actuation System (DAS) and Distributed Control System (DCS) 5.3 Scenarios The tasks identified in Section 5.1 are included in operating sequences that must be executed in the event of certain scenarios. Those scenarios are identified in this section. Sources used to define the scenarios include:
The list of scenarios is shown in Table 5-3:
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6.0 CONCLUSION
S This RSR documents the results for the FRA, FA and TA elements for DAS, 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 6).
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The scenarios identified are input to the HFE V&V activities. Final list of scenarios to be validated during the execution of Preliminary Validations (PVs) and Integrated System Validation (ISV) of the staged validation testing approach will result from the Sampling of Operational Condition6.
The execution of these scenarios will require guidance of operating procedures to address new operating conditions from the failure of the RPS/ESFAS/NIS platform. Plant procedures should be reviewed, and new procedures might be needed to address the new scenarios and new tasks described in the RSR.
Finally, a summary of HSI requirements for DAS HSI Design is provided in Table 5-2.
7.0 REFERENCES
The following lists documents 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. Florida Power and Light, Engineering Procurement Specification - PTN3&4 RPS/ESFAS and SR Control Systems Replacements, SPEC-IC-108 Revision 2.
- 4. [
]
6
[ ]
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- 5. [
]
- 6. [
]
- 7. NUREG-0711, Human Factors Engineering Program Review Model, Revision 3.
- 8. [
]
- 9. [
]
- 10. [
]
- 11. [
]
- 12. *Florida Power and Light, Turkey Point Unit 3(4), 3(4)-EOP-E-0 Rev. 18, Reactor Trip or Safety Injection.
- 13. [
]
- 14. [
]
- 15. *Florida Power and Light, Annunciator Response Procedure, Control Room Response - Panel D, Procedure No. 3(4)-ARP-097.CR.D.
- 16. [
]
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APPENDIX A. TASK RECORD SHEETS Table A-1: TRS for DAS-T01 [ ]
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Table A-2: TRS for DAS-T02 [ ]
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Table A-3: TRS for DAS-T03 [ ]
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Table A-4: TRS for DAS-T04 [ ]
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Table A-5: TRS for DAS-T05 [ ]
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Table A-6: TRS for DAS-T06 [ ]
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Table A-7: TRS for DAS-T07 [ ]
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Table A-8: TRS for DAS-T08 [ ]
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Table A-9: TRS for DAS-T09 [ ]
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Table A-10: TRS for DAS-T10 [ ]
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Table A-11: TRS for DAS-T11 [ ]
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Table A-12: TRS for DAS-T12 [ ]
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Table A-13: TRS for DAS-T13 [ ]
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Table A-14: TRS for DAS-T14 [ ]
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Table A-15: TRS for DAS-T15 [ ]
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Table A-16: TRS for DAS-T16 [ ]
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APPENDIX B. DESCRIPTION OF APPLICABLE OE Page 74
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Turkey Point Nuclear Plant L-2023-010 Docket Nos 50-250 and 50-251 Attachment 7 ATTACHMENT 7 SUPPLEMENTAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST 274 REACTOR PROTECTION SYSTEM, ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, AND NUCLEAR INSTRUMENTATION SYSTEM REPLACEMENT PROJECT OPERATING EXPERIENCE REVIEW RESULTS
SUMMARY
REPORT (72 pages follow)
(REDACTED)
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Framatome Inc.
RESULTS
SUMMARY
REPORT Document No.: 51 - 9354906 - 003 Operating Experience Review (License Amendment Request Version)
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: Steve Kane Approver: Brian Haynes Signature and Date Signature and Date Signature and Date Page 1 of 72
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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 LP All Project Engineer 2/2/2023 Jacek Nowakowski JK NOWAKOWSKI Project Engineer 2/2/2023 LR All Brian Haynes BM HAYNES Project Engineering 2/2/2023 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 N/A N/A N/A N/A Page 2
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Record of Revision Revision Pages/Sections/
Brief Description / Change Authorization No. Paragraphs Changed 000 All Initial Issuance Document revision to incorporate comments from DRCS:
- DRCS_51-9354906_IB 001 All
- Cross-comments from DRCS Non-LAR OER review Tech Writer review comments incorporated Title page and 2.1 Modified proprietary data declaration.
002 4.0 Added revisions to references 1, 2, and 4-6.
Record of Revision Corrected description of title page change in Rev 002.
Title Page Modified proprietary data declaration.
1.2 Updated 4th bullet to add "or describe the types of OE identified."
1.6 Added HFEITS.
2.1 Added statement about confidential data.
003 2.1.1 Deleted list of stations from which relevant OE was used.
2.3 Added statement about confidential data.
3.0 Rephrased bullets 4, 5 and 8.
Appendix A Added a note addressing OE reviewed but not described within the report.
Appendix C Updated to align with Section 2 and App A.
Appendix D Updated to align with Section 2 and App A.
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Table of Contents Page
1.0 INTRODUCTION
........................................................................................................................... 6 1.1 Background ....................................................................................................................... 6 1.2 Purpose and Objectives .................................................................................................... 6 1.3 Scope ................................................................................................................................ 6 1.4 Relationships Between HFE documents ........................................................................... 8 1.5 Terms and Definitions ....................................................................................................... 8 1.6 Acronyms ........................................................................................................................ 10 2.0 ANALYSIS RESULTS ................................................................................................................. 11 2.1 Step 1: OER Planning, Search, and Screening............................................................... 11 2.1.1 Information Screening ...................................................................................... 13 2.2 Step 2: PTN 3&4 Operator Questionnaire & Interviews .................................................. 14 2.3 Step 3: Review and Analysis ........................................................................................... 15 2.4 Step 4: OE Treatment in the HFE Program..................................................................... 16
3.0 CONCLUSION
S AND RECOMMENDATIONS ........................................................................... 16
4.0 REFERENCES
............................................................................................................................ 19 APPENDIX A. OE SEARCHING RESULTS ............................................................................ 20 APPENDIX B. SAMPLE QUESTIONNAIRE ............................................................................ 22 APPENDIX C. HFE OER ANALYSIS RESULTS ..................................................................... 33 APPENDIX D. DESCRIPTION OF APPLICABLE OE .............................................................. 51 Page 4
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List of Tables Page Table 1-1: Project HFE-Related Modifications (LAR Systems) ........................................................................ 7 Table A-1: OE Searching Results ....................................................................................................................... 20 Table C-1: OER Analysis Results ....................................................................................................................... 33 Table D-1: OER Analysis Results ....................................................................................................................... 51 List of Figures Page Figure 1-1: Relationships between HFE documents .......................................................................................... 8 Figure 2-1: OER Development process ............................................................................................................. 11 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. In the context of the human factors engineering (HFE) evaluation required when a licensee is changing Main Control Room (MCR) or other interface with which operation personnel will be interacting, a specific HFE Plan (Reference 1) identifies the HFE activities for the PTN 3&4 Safety Related (SR) Digital Modernization Project (hereafter the project).
More specifically, one of the Human Factors Engineering (HFE) activities to be performed is the Operating Experience Review (OER), an element of the Project HFE Plan (Reference 1) prepared to identify HFE-related safety issues. Using proven systematic analysis techniques, important lessons learned from past operational experiences will be obtained for application in the design process. The OER provides the design team with information on the past performance of predecessor designs of the systems being changed.
The identification and resolution of OER issues identified in the OER process may create changes to the function allocation, automation, Human-System Interface (HSI) equipment design, procedures, training, etc., as applicable. It is during the OER process that HFE-related issues identified in previous designs are considered for the modification process. For this reason, information gathered during the performance of the OER process inputs to other Project HFE Program elements.
The activities presented in this Result Summary Report (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 2) was developed using guidance in NUREG-0711 (Reference 3).
1.2 Purpose and Objectives The purpose of this RSR is to describe and present the results obtained from the process followed in the execution of the OER. The objectives of this RSR are the following:
- To list all sources of Operating Experience (OE) information reviewed that were considered for OER analysis.
- To describe the PTN 3&4 operators interviews process
The methodology, processes and activities followed to execute the OER are described in the HFE Analysis IP (Reference 2).
1.3 Scope The scope of the OER is established in the HFE Analysis IP (Reference 2) and is focused on the review of OEs related to the systems and modifications in Table 1-1.
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Table 1-1: Project HFE-Related Modifications (LAR Systems)
Item LAR System Modifications 1 Reactor Protection System (RPS) Functions provided in Reactor Protection, Engineered Safety Engineered Safety Features Feature Actuation System, and Nuclear Instrumentation Actuation System (ESFAS) Systems are combined into a single platform. Analog portions of the systems are replaced with digital.
Nuclear Instrumentation System (NIS) Indicators and status lights on control boards from multiple divisions are replaced with video displays.
New Safety Video Display Units (SVDU) are installed in the existing Excore NIS panels in the control room surveillance area for displaying safety related information and allowing access to trip or bypass functions, change constants and setpoints, and to facilitate maintenance.
Diagnostic monitoring of the Protection System by the Distributed Control System (DCS) is performed, surveillance requirements are reduced or modified.
Non-safety monitoring and alarm functions currently performed in safety systems are relocated to the DCS.
Indications that are diverse from the Tricon platform includes existing control room indicators and indicators that will be moved to the non-safety video display units for use in the event of a Tricon platform common cause failure. Additional operator actions are credited to mitigate a software common cause failure event.
2 Distributed Control System (DCS) The addition of a Diverse Actuation System (DAS) that automatically trips the reactor and starts Safety Injection Pumps to mitigate a protection system common cause failure.
Indications of process measurements on control board displays from different divisions.
Performs automated channel checks based on serial data from the Protection Systems.
Monitors and alarms failures of components within the safety systems.
New non-safety related Video Display Units (VDU) are replacing the instruments and recorders on the main control board vertical panel A.
The approach of the OER element is to use the scope of the modification described in the RSP/ESFAS/NIS System Requirements Specification (SyRS) (Reference 4) and DAS SyRS (Reference 5), and which is summarized in Table 1-1, to define search criteria for:
- Plant specific OEs related to HFE for the currently installed systems. This includes RPS, ESFAS, NIS and related DCS.
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- OEs at other nuclear power plant facilities that have performed similar modifications or installed the same types of components.
- OEs from Industry Event Reports for modifications or installation of automated and digital systems that would have benefitted from the application of Technical Conscience.
1.4 Relationships Between HFE documents This RSR is hierarchically dependent of the HFE Analysis IP (Reference 2) 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 produced in later stages of the HFE Program. Results provided in this RSR serve as inputs for the HSI Design activities, which in turn, are inputs for the HFE V&V RSRs. 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.
The relationship of these documents with other HFE deliverables is shown in Figure 1-1. The overall project deliverables structure for the entire HFE Program can be observed in the HFE Plan (Reference 1).
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 RSR:
- 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. HFE OER issue - Human performance aspect identified during the OE search and potentially applicable to any of the HFE elements of the Project HFE Program.
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- 3. Human-System Interface (HSI) - The point of contact between the human operator and the physical devices.
- 4. Implementation Plan - 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.
- 5. NUREG - Series Publications of Reports or brochures on regulatory decisions, results of research, results of incident investigations, and other technical and administrative information that are prepared by the United States NRC Staff or its Contractors.
- 6. Program Element / Element - Each of the twelve parts in which the Project HFE Program based on NUREG-0711 is divided.
- 7. Results Summary Report - 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.
- 8. Step - Each of the four parts in which the methodology is divided into.
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Document No.: 51-9354906-003 Operating Experience Review (License Amendment Request Version) 1.6 Acronyms ADAMS Agencywide Documents Access and Management System AFD Axial Flux Difference CAP Corrective Action Program DAS Diverse Actuation System DCS Distributed Control System EBLS Emergency Bus Load Sequencer EC Engineering Change ESFAS Engineered Safety Features Actuation System ETI Elapsed Time Indicator FA Function Allocation FAT Factory Acceptance Test FPL Florida Power & Light FRA Functional Requirements Analysis GL Generic Letter HFE Human Factors Engineering HFEITS Human Factors Engineering Issue Tracking System HIC Hand Indicating Controller HMI Human Machine Interface HSI Human System Interface I&C Instrumentation and Control IER INPO Event Report IN Information Notice INPO Institute of Nuclear Power Operation IP Implementation Plan IRIS Industry Reporting and Information System JIT Just-in Time LAR License Amendment Request LER Licensee Event Report MCR Main Control Room NIS Nuclear Instrumentation System NRC Nuclear Regulatory Commission O&MR Operations and Maintenance Reminder OE Operating Experience OER Operating Experience Review ONS Oconee Nuclear Station PAMS Post-Accident Monitoring System PTN Turkey Point Plant QSPDS Qualified Safety Parameter Display System RCO Reactor Control Operator RCP Reactor Coolant Pump Page 10
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RO Reactor Operator RPS Reactor Protection System RSR Result Summary Report SEN Significant Event Notification SER Significant Event Report SI Safety Injection SOER Significant Operating Experience Report SR Safety Related SRO Senior Reactor Operator SVDU Safety Video Display Unit SyRS System Requirements Specification TA Task Analysis TCA Time Critical Action TCOA Time Critical Operator Action TCS Turbine Control System TIHA Treatment of Important Human Actions TSA Time Sensitive Action V&V Verification and Validation VDU Video Display Unit VPA Vertical Panel A 2.0 ANALYSIS RESULTS OER results are obtained following the process depicted in Figure 2-1 and described in the HFE Analysis IP (Reference 2).
Figure 2-1: OER Development process Step 1:
OER Planning, Search and Screening Step 3: Step 4:
Review and OE Treatment in Analysis the HFE Program Step 2:
PTN 3&4 Operator interviews 2.1 Step 1: OER Planning, Search, and Screening This step consists of defining a list of OE sources and search terms aimed at finding OEs potentially applicable to the Systems from Table 1-1. Once both are concluded, following the OER methodology (Reference 2), the next activity is to conduct the search and list the OER findings.
The different sources of OE used to perform the HFE-related issue search are the following:
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- Institute of Nuclear Power Operations (INPO) specific databases and documents. The main search is conducted within the documents submitted by INPO such as the ones listed below. This data is not addressed in the report due to confidentiality obligations.
o INPO Event Reports (IER), levels 1 to 4 o Significant Operating Experience Reports (SOERs) o Significant Event Reports (SERs) o Significant Event Notifications (SENs) o Topical Reports o Operations and Maintenance Reminders (O&MRs) o Operating Experience Digests o Tracking Trends o Analysis Digests o Reports o Just-In Time (JIT) Training Briefing Material o Good practices
- U.S. NRC sources such as:
o ADAMS (Agencywide Documents Access and Management System) database o NRC Generic Letters o Information Notices o NUREG-/CR-6400: Human Factors Engineering (HFE) Insights for Advanced Reactors Based Upon Operating Experience o The Licensee Event Reports (LER)
- Turkey Points Corrective Actions Program (CAP)
The OER search terms are mainly focused on the systems and associated modifications described in Table 1-1 and their potential impact on human performance. The initial OER search was based on the information gathered from the project design modifications, the list of search terms defined in the HFE Analysis IP (Reference 2) with additional refinement based on evaluation of the HFE concepts as described in the HFE Analysis IP (Reference 2). The initial search using the terms provided in the HFE Analysis IP (Reference 2) resulted in plenty of OEs, with a great number of them deemed non-applicable to the project. To narrow the search, a combination of keywords was used. The following keywords and keyword combinations are those that provided potentially applicable results for further evaluation in the screening sub-step:
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All the potentially applicable OEs that resulted from the search terms listed above are included in APPENDIX A. The appendix includes a table (see Table A-1) that indicates the OEs IDs per source (INPO, NRC and PTN 3&4 CAP).
2.1.1 Information Screening The purpose of the screening process is to filter the results previously collected to obtain the OEs relevant to the Project HFE Program as presented in the HFE Analysis IP (Reference 2). OEs information is screened to select appropriate information related to potential precursor incidents in order to take measures to prevent significant events at analogous installed modifications or similar design inconsistencies. The screening is performed within the documents' compilation from the previous step (Section 2.1).
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Document No.: 51-9354906-003 Operating Experience Review (License Amendment Request Version) if the information is applicable to the project. All the OEs identified correspond to implications or actions which apply to the design modifications, similar equipment and systems, potential combinations or unfortunate situations that may lead to a non-desirable event.
The screening criteria is based on HFE design process (design implementation, design approaches, etc.),
personnel role and work design (levels and types of automation, work practices and task design, task allocation to crew members, teamwork, crew communication and coordination, supervision; important human actions and potential for error, task location, training, etc.), HSI design and technologies employed (alarm presentation, operator aids and support systems, procedure design and implementation, control room layout and environment, control room panels design, etc.) and unanticipated situations that may lead to the same undesired event.
The screening process resulted in a list of filtered OEs from the initial search. Those OEs found not applicable to the project in the screening are not further analyzed on the subsequent steps of the methodology.
This list of HFE OEs applicable to the modification of systems from Table 1-1 serves as input to the Step 3 (Review and Analysis) of the process, as depicted in Figure 2-1. In that step, the OEs descriptions are analyzed to identify related HFE causes and identify which HFE element might be affected (see Section 2.3).
2.2 Step 2: PTN 3&4 Operator Questionnaire & Interviews A Questionnaire and subsequent follow-up interviews of PTN 3&4 operations staff members were conducted to gain further insight on the systems being modified.
This step begins with the development of a Questionnaire that is distributed to the operations staff at PTN 3&4 in the following roles:
The questionnaire includes general questions and specific questions to each of the systems being modified, and addresses, at a minimum, the following topics:
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The Questionnaire was distributed [ ] A sample questionnaire is in APPENDIX B. After the questionnaires were filled out and returned, the HFE team reviewed all answers provided to identify relevant topics applicable to expand on during the interviews. [
]
Once the interviews were conducted, the results were analyzed again to identify applicable OEs to the project, considering the scope of the modifications described in Table 1-1. Those OEs serve as input to the Step 3, together with the list of potentially applicable OEs from Step 1.
2.3 Step 3: Review and Analysis This step corresponds with the analysis of all the OEs classified as applicable in the previous two steps. The review consists of reading and analyzing the OE description to identify related HFE causes and identify which HFE element might be affected and, consequently, whether lessons learned related to certain actions should be incorporated into the project.
OEs resulted from steps 1 and 2 that are applicable to the scope of this RSR are classified as follows:
- Not Applicable - Although the OE was initially categorized as potentially applicable to the project, the review has shown there are no issues or concerns that have an impact on the Turkey Point 3 & 4 design modifications, operation, procedures, or maintenance plans.
- Information Only - Good background information that might inform a decision, but the document does not have any direct and specific impact on the project activities.
- Action Required - A specific response or action is required by an individual or organization to address a concern.
Each OE found to be applicable that derives into actions is then related to the HFE Program Elements. [
]
APPENDIX C provides a summary for each applicable OE and where each should be addressed within the HFE Program, and APPENDIX D includes descriptions for each applicable OE. Some data is not addressed in the report due to confidentiality obligations.
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Document No.: 51-9354906-003 Operating Experience Review (License Amendment Request Version) 2.4 Step 4: OE Treatment in the HFE Program This step is based on an HFE assessment for all the HFE OEs whose classification corresponds to action required. The purpose of the HFE evaluation is determining how the lesson learned from the incidents might be incorporated into the corresponding Project HFE Program element.
The summary table in APPENDIX C indicates the potential applicability to the different elements from the HFE Program. The HFE team reevaluates and analyzes the OE results during the execution of the affected HFE element(s). The treatment and actions implemented are documented in the RSR of each HFE element.
All OEs will be tracked using the HFEITS and evaluated in the HFE activities as applicable. [
]
3.0 CONCLUSION
S AND RECOMMENDATIONS This section provides main conclusions and recommendations after all HFE OEs have been analyzed:
- 1. The following general conclusions, which are directly based on the results of the review and analysis and HFE treatment steps, may be drawn to be considered during the project:
- A total of [ ] have been identified during the search for both LAR and non-LAR scope.
Performance of the screening step yielded [ ] which were considered potentially applicable to the systems from Table 1-1; and, therefore, subjected to further analysis to evaluate how those documented lessons learned might be incorporated into the project in terms of human performance.
- The completion of the HFE analysis process reveals these elements are important to enhancing human performance: supervision, personnel training, clear understanding of procedures and their use, pre-job briefing, and an environment that encourages personnel to carry out their work in a thoughtful, deliberate manner, using self-verification techniques to prevent human errors.
- 2. The Human Factors V&V is the Project HFE Program Element most impacted by the applicable OEs (see APPENDIX C). This fact implies that the test and evaluations performed under the HFE V&V shall consider these aspects to finally verify and validate that the human performance is adequate from HFE perspective.
- 3. Operator Interview OE Results are focused on issues related to the past design; these OEs should be generally addressed during the execution of the Human System Interface Design, as well as during V&V activities to verify that the OE was addressed during the design phase of the project.
- 4. Three guides developed by INPO have been found to be applicable, though for information only.
Description of this OE is included in the HFEITS in accordance with the HFE Analysis IP (Reference 2)
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- 6. The recommendations that target the Procedures Development element are the following, and shall be considered by the procedure writers responsible for updating the affected procedures by the design modifications:
- 7. The following should be considered during Training Program Development by the team responsible for training material updating:
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- 8. There are several applicable OEs related to Operations crew failing to notice in due time the status of trip bypasses and permissive in MCR [
]
- 9. New and modified task should flow down to Procedures and Training Program Development. [
]
- 10. [ ] describes a situation in which the operations crews were unable to meet the design basis required time for a Time Critical Action (TCA) [
]
- 11. Regarding the results from the interviews, the following should be considered through the program:
The OEs have shown that the V&V element should consider [
] to set the operating conditions to be validated during the tests [
]
In the light of the above OEs, operators ability to [
] should be under evaluation during validations.
The new disposition of [
] are going to be addressed from Task Analysis to the V&V tests.
Operators provided insights about current [
] are going to be addressed in the context of this modification.
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4.0 REFERENCES
The following lists documents used as sources of information for this plan. References identified with an (*) are maintained within PTN 3&4 Records System and are not retrievable from Framatome Records Management. Unless otherwise stated the [ ] will be the latest issued revision. For other references, the controlling revision is identified on the [
]
- 1. [ ]
- 2. [
]
- 3. NUREG-0711, Human Factors Engineering Program Review Model, Revision 3.
- 4. [
]
- 5. [
]
- 6. [
]
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APPENDIX A. OE SEARCHING RESULTS Table A-1: OE Searching Results Page 20
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In addition to the table, [ ] have been incorporated as a result of the review process: [
]
Note that [ ] documents and [ ] were reviewed and evaluated for relevance to the Turkey Point Digital Modernization Project. Applicable OE has been entered into the project HFEITS in accordance with HFE Analysis IP (Reference 2).
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APPENDIX B. SAMPLE QUESTIONNAIRE INTRODUCTION AND GENERAL INSTRUCTIONS Turkey Point Units 3&4 (PTN 3&4) are upgrading non-safety and safety related systems in the Main Control Room (MCR) by replacing them with digital systems. As part of this project, a questionnaire will be issued to [ ] followed by an interview to expound upon the answers received from the questionnaires.
This questionnaire will capture Operating Experiences associated with the current systems and components planned for the digital upgrades at Turkey Point.
Both this questionnaire and subsequent interviews will be anonymous (names will not be published on any report and/or any other documentation of the project). The HFE team will maintain a separate confidential log in the event that clarification of a response is necessary.
The intent of the following questions is to gather specific information on operating experiences from those who use and/or maintain the systems being modified. [
]
In completing the questionnaire, if a question is not applicable to your position, please identify as Not Applicable.
Please complete the following questionnaire directly on the Word version or print it and fill it out manually, as preferred.
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- 1. BASIC GENERAL DATA Name _________________________________ Date_______________
Present position (mark the applicable one):
[
]
Current License if applicable (mark the applicable one):
[ ]
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APPENDIX C. HFE OER ANALYSIS RESULTS Table C-1: OER Analysis Results Page 33
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APPENDIX D. DESCRIPTION OF APPLICABLE OE Table D-1: OER Analysis Results Page 51
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