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{{#Wiki_filter:Modernization Plan #1D BTP 7-19 Update Public Meeting NRC Staff Presentation August 29, 2019
 
Agenda
* Description of Changes Proposed for BTP 7-19
* Discussion with and feedback from NEI/Stakeholders
* Next Actions
* Schedule 2
 
Major Changes in Proposed BTP
* Reorganization of BTP to align review guidance with acceptance criteria
* Clarification of applicability
* Incorporation of categorization scheme and graded approach for addressing CCF in DI&C systems
  - D3 Assessment
  - Qualitative assessment
* Clarification of criteria for addressing spurious operation
* Clarification of criteria for manual system level actuation 3
 
Process Flow for CCF Assessment
* Determine category of proposed DI&C system (i.e., A1, A2, B1, B2)
* Identify any integration or interconnectivity of the proposed DI&C system with other categories of systems
* If A1 system, perform D3 assessment
  - Use of means to eliminate CCF from further consideration
  - Use of diverse means
  - Use of analysis to demonstrate consequences of CCF is within acceptable limits
* If A2 or B1 system (or integrated B2 system), perform qualitative assessment 4
 
Spurious Operation
* Evaluate potential for spurious operation due to CCF in DI&C system
* Evaluation should focus on those spurious operations that may induce initiating events that can challenge plant safety
* Design features or defensive measures can be credited to reduce scope of evaluation 5
 
Manual System Level Actuation and Indications SRM-SECY-93-087 Positions 3 and 4 Clarifications
* Refers to the displays and manual controls described in Position 4 of the SRM on SECY-093-87
* Displays and manual controls necessary to monitor and perform system level actuation of safety critical functions
* Need to be located within the main control room
* Displays and controls provided for Position 4 can be credited as diverse means for addressing Position 3 6
 
Still Under Consideration Industry Feedback Requested
* How Leak-Before-Break (LBB) criteria can be credited in excluding large break LOCAs and MSLB events from evaluation
* Need feedback from industry regarding crediting LBB
  - Applicability to PWRs and BWRs
  - What operator or maintenance actions will be taken if a leak is detected to allow LBB to be credited for exclusion of the two events 7
 
Next Steps and Schedule Milestones Activity                                                                                  Completion Date A.1  Begin revision to draft BTP 7-19                                                          In progress A.2  Category 2 public meeting to discuss the direction of draft BTP 7-19                      Completed April 4, 2019 A.3  Category 2 public meeting to discuss topic focused areas of BTP 7-19                      Completed June 26, 2019 A.4  Finalize draft BTP 7-19 for staff review                                                  Completed August 19, 2019 A.5  Final Category 2 public meeting to discuss BTP 7-19 prior to NRC review and concurrence August 29, 2019 A.6  Agency review and concurrence on draft BTP 7-19 in preparation for public comment        October 2019 period A.7  ACRS Subcommittee Meeting                                                              November 2019 A.8  Issue Draft BTP 7-19 for public comment period (60 day comment period)                  December 2019 Public meeting, if needed - January 2020 A.9  Public comment period ends                                                              February 2020 A.10 Public Comment/ACRS Comment Resolution Complete                                          March 2020 A.11 ACRS Full Committee Meeting                                                                April 2020 A.12 Prepare Final BTP 7-19 Concurrence                                                          May 2020 Receive OMB Clearance Approval (non-major rule determination)
A.13 Issuance of Final BTP 7-19                                                                  June 2020 8
 
Questions 9
 
Acronyms
* BTP: Branch Technical Position
* BWR: Boiling Water Reactor
* CCF: Common Cause Failure
* D3: Defense-in-Depth and Diversity
* DI&C: Digital Instrumentation and Controls
* LBB: Leak-Before-Break
* LOCA: Loss of Coolant Accident
* MSLB: Main Steamline Break
* NEI: Nuclear Energy Institute
* PWR: Pressurized Water Reactor
* SRM: Staff Requirements Memorandum 10}}

Revision as of 22:56, 7 October 2019

Draft BTP 7-19 Revision Presentation- August 29, 2019
ML19240A327
Person / Time
Issue date: 08/28/2019
From: Tekia Govan
NRC/NRR/DIRS/IRGB
To:
Govan T, 415-6197, NRR/DIRS
References
Download: ML19240A327 (10)


Text

Modernization Plan #1D BTP 7-19 Update Public Meeting NRC Staff Presentation August 29, 2019

Agenda

  • Description of Changes Proposed for BTP 7-19
  • Discussion with and feedback from NEI/Stakeholders
  • Next Actions
  • Schedule 2

Major Changes in Proposed BTP

  • Reorganization of BTP to align review guidance with acceptance criteria
  • Clarification of applicability
  • Incorporation of categorization scheme and graded approach for addressing CCF in DI&C systems

- D3 Assessment

- Qualitative assessment

  • Clarification of criteria for addressing spurious operation
  • Clarification of criteria for manual system level actuation 3

Process Flow for CCF Assessment

  • Determine category of proposed DI&C system (i.e., A1, A2, B1, B2)
  • Identify any integration or interconnectivity of the proposed DI&C system with other categories of systems
  • If A1 system, perform D3 assessment

- Use of means to eliminate CCF from further consideration

- Use of diverse means

- Use of analysis to demonstrate consequences of CCF is within acceptable limits

  • If A2 or B1 system (or integrated B2 system), perform qualitative assessment 4

Spurious Operation

  • Evaluate potential for spurious operation due to CCF in DI&C system
  • Evaluation should focus on those spurious operations that may induce initiating events that can challenge plant safety
  • Design features or defensive measures can be credited to reduce scope of evaluation 5

Manual System Level Actuation and Indications SRM-SECY-93-087 Positions 3 and 4 Clarifications

  • Refers to the displays and manual controls described in Position 4 of the SRM on SECY-093-87
  • Displays and manual controls necessary to monitor and perform system level actuation of safety critical functions
  • Need to be located within the main control room
  • Displays and controls provided for Position 4 can be credited as diverse means for addressing Position 3 6

Still Under Consideration Industry Feedback Requested

  • Need feedback from industry regarding crediting LBB

- Applicability to PWRs and BWRs

- What operator or maintenance actions will be taken if a leak is detected to allow LBB to be credited for exclusion of the two events 7

Next Steps and Schedule Milestones Activity Completion Date A.1 Begin revision to draft BTP 7-19 In progress A.2 Category 2 public meeting to discuss the direction of draft BTP 7-19 Completed April 4, 2019 A.3 Category 2 public meeting to discuss topic focused areas of BTP 7-19 Completed June 26, 2019 A.4 Finalize draft BTP 7-19 for staff review Completed August 19, 2019 A.5 Final Category 2 public meeting to discuss BTP 7-19 prior to NRC review and concurrence August 29, 2019 A.6 Agency review and concurrence on draft BTP 7-19 in preparation for public comment October 2019 period A.7 ACRS Subcommittee Meeting November 2019 A.8 Issue Draft BTP 7-19 for public comment period (60 day comment period) December 2019 Public meeting, if needed - January 2020 A.9 Public comment period ends February 2020 A.10 Public Comment/ACRS Comment Resolution Complete March 2020 A.11 ACRS Full Committee Meeting April 2020 A.12 Prepare Final BTP 7-19 Concurrence May 2020 Receive OMB Clearance Approval (non-major rule determination)

A.13 Issuance of Final BTP 7-19 June 2020 8

Questions 9

Acronyms

  • BTP: Branch Technical Position
  • BWR: Boiling Water Reactor
  • CCF: Common Cause Failure
  • D3: Defense-in-Depth and Diversity
  • DI&C: Digital Instrumentation and Controls
  • LOCA: Loss of Coolant Accident
  • MSLB: Main Steamline Break
  • NEI: Nuclear Energy Institute
  • PWR: Pressurized Water Reactor
  • SRM: Staff Requirements Memorandum 10