ML18163A395
| ML18163A395 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 06/13/2018 |
| From: | Nuclear Energy Institute |
| To: | Office of Nuclear Reactor Regulation |
| Golla J | |
| References | |
| Download: ML18163A395 (28) | |
Text
NRC-Industry MP4 ISG-06 R2 Tabletop Hope Creek Power Range Neutron Monitor NUMAC Digital Upgrade Pre-Application Coordination Meeting June 13-14, 2018 Industry MP4 Team
MP4 Tabletop Presentation Purpose 2 2
The purpose of this presentation is to exercise the draft DI&C-ISG-06 Revision 2 process for the Pre-Application Coordination Meeting. This presentation is based loosely on the Hope Creek PRNMS Phase 0 meeting presentation dated September 11, 2013 but is not associated with Hope Creek Generating Station (HCGS).
HCGS kindly gave their permission for use of this file.
Agenda - Nonproprietary 3 Meeting Purpose and Introductions 3 ISG-06 Rev. 2 Alternate Review process alignment Project Information and PRNM Design Concept/Architecture Plant Impacts GEH Topical Report and Development Program Additional NRC Topics of Interest Plant Specific Action Items (PSAIs)
Vendor Oversight Plan (VOP)
Tool for file sharing PRNM Project Schedule/Milestones Summary Questions, Discussion and Feedback (Public Presentation)
Conclusion (Public Presentation)
Pre-Application Coordination Meeting Purpose 4 4
- To present the design concept and demonstrate how it addresses NRC requirements and policy regarding key issues.
- To gain alignment on use of ISG-06 Alternate Review process and submittal/review process.
- To solicit Staff feedback prior to LAR submittal to facilitate a more efficient NRC review.
Introductions 5 Utility / Vendor Team 5 Kenneth Knaide - PSEG Director of Engineering - (Not) Hope Creek Robert Gallaher - PSEG PRNM Project Manager Chuck Lukacsy - PSEG Operations Keith Swing - PSEG System Engineer Ron Veideman - PSEG Lead Engineer Participants listed here Dave Heinig - PSEG Design Engineer Brian Thomas - PSEG Principal Licensing Engineer Robert Hoffman - PSEG Licensing Engineer Kahlim Miller - GEH Project Manager Larry Chi - GEH Chief Engineer Frank Novak - GEH PRNM Technical Lead Sara Rudy - GEH Licensing Engineer
ISG-06 Alignment - Use of AR Process 6 LAR to be submitted for review under Alternate Review (AR) process 6 AR process licensee prerequisites LAR will describe licensees Vendor Oversight Plan. GEH development process is consistent with (and conforms to) the 2015 version of NQA-1, Part II, Subpart 2.7.
- TR was reviewed/approved by the NRC October 1995
- Proposed modification scope is within the scope of the TRs applicability
- TR vendor (i.e., GEH) will perform detailed software design, implementation, and testing Licensee Commitments in Consideration of Early License Amendment Issuance
- LAR will include commitment to complete life cycle activities under the licensees QA program Precedent LAR Similar to Columbia PRNM upgrade; incorporating RAIs and NRC feedback Review of Columbia SE as precedent
ISG-06 Alignment - Fundamental Design Principles 7 The platform and system architecture discussion will address 7
the ISG-06 Rev. 2 Section 2.6, Fundamental Design Principles:
Redundancy Independence Deterministic Behavior Defense in Depth and Diversity
PRNM LAR Needs and Benefits 8 Needs. 8 Upgrade existing analog system to provide increased reliability, Reduce maintenance work on existing system, Address long-term obsolescence issues, and Increase operational flexibility.
Needs and Benefits included Benefits.The GEH NUMAC PRNM Implementation at Hope Creek will provide:
Enhanced APRM features to improve system operation - use of Operator Display Assemblies Automated system surveillance testing - built-in auto-calibration and self-test functions
- 1/2 scram reduction; managing risk, eliminate use of extender card and INOP inhibit button Highly reliable and accurate system functions Familiarity w/ NUMAC chassis (operation & troubleshooting- leak detection, MSL rad monitors)
Reduced number of components
GEH NUMAC Configuration 9 2-out-of-4 Logic Chassis 9 Average Power Range Monitor (APRM) Chassis with Option III and DSS-CD Stability functions Rod Block Monitor (RBM) Chassis Control Room Operator Display Assemblies (ODAs)
NUMAC Interface Computer (NIC)
Quad Low Voltage Power Supplies (QLVPS)
Similar to NUMAC PRNM Systems at:
Nine Mile Unit 2 Susquehanna Units 1 and 2 Peach Bottom Unit 1 and 2 Limerick Unit 1 and 2 Brown's Ferry Unit 1, 2, 3 Monticello Grand Gulf Columbia (LAR submitted for approval)
Etc(more than 30 installed systems)
Existing System Comparison 10 Subsystem Existing PRNM System NUMAC PRNM System Safety Function Upscale Flux Trip Upscale Flux Trip 10 Simulated Thermal Power Trip Simulated Thermal Power Trip Setdown Flux Trip Setdown Flux Trip OPRM trip provided by ABB OPRM system OPRM trip LPRM - 43 LPRM strings, 172 LPRM detector Signals No Change Flow - Four Flow channels, 8 Flow Transmitters - Four Flow channels, 8 Flow Transmitters
- Flow channels A&C provide input to APRM A, C, E - Each flow channel provides input to 1 APRM channel Each APRM selects the low input
- Flow channels B&D provide input to APRM B, D, F Each APRM selects the low input APRM - 6 APRM Channels - 4 APRM Channels
- 21 or 22 LPRM inputs signals to each APRM channel - 4 LPRM NUMACs coupled with associated APRM channel to
- LPRM Groups A & B are not used by APRMs process all LPRM input signals
- Eight outputs to RPS - 43 LPRM inputs signals to each APRM channel
- APRM A - RPS Channel A1 - All LPRM detectors used by the APRMs
- APRM B - RPS Channel B1 - Eight outputs to RPS
- APRM C - RPS Channel A2 - Voter A1 - RPS Channel A1
- APRM D - RPS Channel B2 - Voter B1 - RPS Channel B1
- APRM E - RPS Channel A1, A2 - Voter A2 - RPS Channel A2
- APRM F - RPS Channel B1, B2 - Voter B2 - RPS Channel B2
- Two bypass switches - One bypass switch OPRM - ABB BWROG Option III stability solution - GE BWROG Option III and GEH DSS-CD stability solutions RBM - 2 RBMs, Flow-biased setpoints - 2 RBMs, Power-biased setpoints (Full ARTS implementation)
PRNM Architecture & Interface Systems 11 GEH Proprietary 11 Discrete Contacts Fiber TCP/IP B Firewall B
Reactor Manual Rod Select Serial Word NUMAC A A Interface Control RBM Channel Computer TCP/IP System Plant Computer GEH Proprietary Analog 0-1V Discrete Fiber Analog 0-1V Meters &
Contacts Recorders D
C B
Operator Analog A Display 172 LPRM 0-3mA APRM Channel GEH Proprietary Assemblies Detectors includes OPRM Fiber RBM GEH Proprietary GEH Fiber Analog APRM (2) 8 Recirculation 4-20mA Proprietary Loop Flow Fiber Transmitters B2 B2 Bypass A2 A2 Switch B1 B1 A1 Discrete Contacts A1 B2 Reactor Mode 2 Out of 4 Voter RPS A2 Switch Discrete Contacts B1 Discrete Contacts A1 Denotes fiber-optic RRCS cable
PRNM Preparation and Issue Identification 12 Industry Lessons-Learned applied 12 Critical Digital Review completed HCGS Digital Program assessment completed TS Amendment removing APRM OPCON 5 operability requirement implemented Procedure Development Plan To support FAT To enhance Digital Program/Processes Potential future projects assessed for PRNM upgrade implications To identify / mitigate / resolve issues early
PRNM Upgrade Plant Impacts 13 TS impacts 13 FSAR impacts Calibration and surveillance testing impacts Plant staff impacts Setpoint Calculations PSEG Digital Lifecycle Program Procedure impact: NMS and RBM operating procedures, system operating and abnormal operating procedures, maintenance procedures, surveillance procedures, and alarm response procedures.
Use of GEH PRNMS TR 14 GEH PRNMS TR SE Report approved both the platform and application14 development process GEH Digital Lifecycle Process - current platform deviates from the approved PRNMS TR:
APRM Upscale/OPRM Upscale, APRM INOP Function Logic Time to Calculate Flow-biased Trip Setpoint Abnormal Conditions Leading to Inoperative Status OPRM Pre-Trip Alarms Increased Instrument Security PRNM System Input Power Source Minor software changes below level of detail of LTR
- Lower level product enhancements (e.g., software change to support more efficient SR testing) and
- Error corrections in software
Application Development Process 15 Case 1: If an NRC approved application development process15 exists:
NRC has already approved the application development process in the topical report and the underlying regulations have not changed since topical report approval, then ISG-6 Section D.4 has been addressed Case 2: If no NRC approved application development process exists:
The licensee has evaluated the vendors application development process and determined that the process is consistent with ISG-6 Section D.4 The LAR will describe the application development process consistent with ISG-6 Section D.4 At the Pre-application Coordination Meeting, one of these two cases will be discussed to address Section D.4. For GE PRNMS, it is Case 1. Note that this is a unique example in that it was NRC reviewed as part of a LAR for Hope Creek PRNM.
Additional NRC Topics of Interest 16 Data Communication (DI&C-ISG-04) 16 Diversity and Defense in Depth (BTP 7-19)
Secure Development & Operational Environment (RG 1.152)
Human Factors Considerations Application or Plant Specific Application Items Vendor (Technical) Oversight Plan The example Digital System Topic slides following are included to demonstrate level of detail
Data Communication (DI&C-ISG-04) 17 Interdivisional Communications 17 PRNM design includes no channel-to-channel communications Supports the safety function of the system (voting)
PRNM includes NSR-to-SR communications Analysis will evaluate PRNM vs. 20 points in ISG-04 Command Prioritization Not applicable - the priority module (RPS) is not digital No diverse actuation signals are combined in PRNM Multidivisional Control & Display Stations ODAs are NSR, and utilize one-way communication from APRM/RBM NUMACs No control functions
Diversity and Defense in Depth (BTP 7-19) 18 Schedule for D3 Analysis submittal 18 Prior to or with the LAR Preliminary review of HCGS UFSAR Chapter 15 shows significant overlap with CGS analysis Only minor Chapter 15 deltas were identified Will address all 9 criteria in BTP 7-19 Rev 6 Will rely on built-in diversity with other plant systems No requirement for a diverse actuation system is anticipated
EMC Compliance (RG 1.180) 19 PSEG procedures require EMC compliance for emissions 19 and susceptibility Per PSEG procedure, EPRI TR-102323 and RG 1.180 contain acceptable testing standards PRNM is qualified to RG 1.180 limits HCGS environment is bounded by EPRI TR-102323 PRNM is located in a radio exclusion zone Comparison of equipment qualification to the plant specific envelope requirements Pre-qualified equipment, equipment to be qualified
Secure Development and Operational Environment (RG 1.152) 20 GEH PSEG SDOE report is expected to be very similar to CGS 20 report Report details GEH SDOE program from Concept through Test phases SOE after turnover of system to PSEG covered by PSEG Cyber Security Program (CSP)
HCGS is compliant with NRC approved cyber security plan License Amendments No. 189 and 192 SDOE Considerations PRNM will be at cyber security Level 4 CRIDS and 3DM remain at Level 3 - Application Firewall between Levels 3 & 4 Data Diodes installed between Level 3 and 2 - eliminating outside attacks from impacting Level 3 & 4 systems.
Gain Adjustment Factor (GAF) uploads performed through the Application Firewall
Human Factors Considerations 21 21operator For PRNMS, there are no safety critical or accident mitigating actions Important operator tasks remain unchanged; therefore, there is no impact to task dynamics, complexity, or workload for the operations staff Two new actions related to the Simulated Thermal Power (STP) setpoint of the NUMAC APRMS and each has sufficient time to complete them Upgrade does not impact reactor operating parameters or the functional requirements of the APRM system System will continue to provide information, enforce control rod blocks, and initiate reactor scrams under appropriate specified conditions as before
Human Factors Considerations 22 The PRNM back panel equipment and NUMAC ODA has been 22 designed to meet NUREG-0700 to the extent practicable Integrated system validation is not warranted, since no change in important human actions for the replacement hardware.
Plant Specific Action Items (PSAIs) 23 23 All PSAIs included as part of the generic approval of the GE Licensing Topical Report, NEDO-31439-A (October 1990), will be addressed as part of the LAR.
Vendor Oversight Plan (VOP) 24 LAR will include a project-specific VOP description per ISG-0624 R2 Section C.2.2.1 VOP includes participation by project stakeholders to ensure vendor compliance with their processes, including V&V, requirements traceability, configuration management, testing, software quality assurance, etc.
- Vendor Oversight activities include the following:
Initial audit and review Periodic audits (which includes witness of critical testing or V&V activities)
Routine design reviews for technical and process compliance
Sharepoint Site for file sharing 25 25 HCGS and GEH have established an electronic reading room for use in file sharing with NRC.
PRNM Project Schedule / Milestones 26 26 Pre-Application Coordination Meeting September 2013 LAR Submittal 2nd Qtr 2015 Amendment / SE June 2016 Install Spring 2017
Project Milestones/Timeline 27 27 Schedule will be provided - above just a placeholder
Acronym List 28 3DM - 3DMONICORETM (core monitoring system)
ABB - ASEA Brown Boveri NSR - Non Safety Related ODAs - Operator Display Assemblies 28 AFT - As Found Tolerance OPRM - Oscillation Power Range Monitor ALT - As Left Tolerance PRNM - Power Range Neutron Monitor APRM - Average Power Range Monitor PSEG - Public Service Electric and Gas BTP - Branch Technical Position QLVPS - Quad Low Voltage Power Supplies CAP - Corrective Action Program RAI - Request for Additional Information CCF - Common Cause Failure RBM - Rod Block Monitor CGS - Columbia Generating Station RG - Regulatory Guide CRIDS - Control Room Integrated Display System (Hope RMCS - Reactor Manual Control System Creek Process Plant Computer System) RPS - Reactor Protection System DSS-CD - Detect and Suppress Solution - Confirmation RRCS - Redundant Reactivity Density Control System D3 - Diversity, Defense in Depth RTS - Reactor Trip System ESFAS - Engineered Safety Feature Actuation System Rx - Reactor FAT - Factory Acceptance Testing SE - Safety Evaluation GAF - Gain Adjustment Factor SDOE - Secure Development and Operational GEH - General Electric Hitachi Nuclear Energy Environmental HW - Hardware SRM - Source Range Monitor INPO - Institute of Nuclear Power Operations SW - Software IRM - Intermediate Range Monitor TSTF - Technical Specification Task Force ISG - Interim Staff Guidance LAR - License Amendment Request LPRM - Local Power Range Monitor LTR - Licensing Topical Report NIC - NUMAC Interface Computer NRC - U. S. Nuclear Regulatory Commission NUMAC - Nuclear Measurement Analysis and Control