ML22070B120: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:NRC Consideration of IEEE Standard 1819 on Risk-Informed Categorization of Electrical
{{#Wiki_filter:NRC Consideration of IEEE Standard 1819 on Risk-Informed Categorization of Electrical  
& Electronic Equipment Sheila Ray, P.E.
& Electronic Equipment Sheila Ray, P.E.
NRC March 16, 2022 Agenda
NRC March 16, 2022


Time/Duration To p i c Speaker
Agenda Time/Duration Topic Speaker 1:30 PM Welcome and Introductions NRC 1:35 PM Opening Remarks NRC/NEI/IEEE 1:45 PM Discussion NRC/NEI/BWROG/PWROG/IEEE 4:00 PM Opportunity for Public Comments Members of the Public 4:20 PM Closing Remarks NRC/NEI/IEEE 4:30 PM Adjourn Meeting 2


1:30 PM Welcome and Introductions NRC
Opening Remarks 3


1:35 PM Opening Remarks NRC/NEI/IEEE
Topics of Discussion
 
1:45 PM Discussion NRC/NEI/BWROG/PWROG/IEEE
 
4:00 PM Opportunity for Public Comments Members of the Public
 
4:20 PM Closing Remarks NRC/NEI/IEEE
 
4:30 PM Adjourn Meeting Opening Remarks Topics of Discussion
* Background
* Background
* Feedback Received
* Feedback Received
* Potential/Possible NRC Path Forward
* Potential/Possible NRC Path Forward
* Feedback on NRC Approaches
* Feedback on NRC Approaches 4


===Background===
===
* The NRC continues to transform to realize our vision ofbecoming a modern, risk-informed regulator to continu e meeting our important safety and security mission.
Background===
* 10 CFR 50.69, Risk -Informed Categorization and Tof Structures, Systems and Components (SSC) for Nuc learreatment Power Reactors.
* The NRC continues to transform to realize our vision of becoming a modern, risk-informed regulator to continue meeting our important safety and security mission.
- Regulatory Guide (RG) 1.201, Revision 1, (Tfor Categorizing Structures, Systems, and Components inrial Use) Guidelines Nuclear Power Plants According to Their Safety Significance,
* 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components (SSC) for Nuclear Power Reactors.
* Endorses NEI 00-04, Revision 0, 10 CFR 50.69 SSC Categorizatio nGuideline
- Regulatory Guide (RG) 1.201, Revision 1, (Trial Use) Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance,
* Endorses NEI 00-04, Revision 0, 10 CFR 50.69 SSC Categorization Guideline
* NRC performed a periodic review of RG 1.201 in 2015
* NRC performed a periodic review of RG 1.201 in 2015
- Identified technical and regulatory enhancements for a futurerevision
- Identified technical and regulatory enhancements for a future revision 5
 
===
Background===
* IEEE Std. 1819-2016, IEEE Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities
- Methods to categorize electrical and electronic components using a risk-informed process and identifies how the categorization results relate to Class 1E/non-Class 1E classifications.
- Standardized and accepted method for alternate treatment of categorized components commensurate with their safety significance.
6


===Background===
===
* IEEE Std. 1819-2016, IEEE Standard for RiskInformed Categorization and Treatment of-Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities
Background===
- Methods to categorize electrical and electroniccomponents using a risk-informed process and identifies how the categorization results relate to Class 1E/non-Class 1E classifications.
* The intent of IEEE Std. 1819-2016, as delineated in the History section of the standard, aims to provide guidance for establishing a methodology for the categorization of electrical and electronic systems and components (EESCs) for nuclear power plant licensees/operators that choose to adopt regulations, such as 10 CFR 50.69, that provide for risk analysis and categorization of electrical and electronic components and appropriate treatment or that choose to establish facility prioritization, effectiveness, or optimization processes supporting risk-informed decision-making.
- Standardized and accepted method for alternatetreatment of categorized components commensurate with their safety significance.
7


===Background===
===
* The intent of IEEE Std. 1819in the History section of the standard, aims to-2016, as delineated provide guidance for establishing a methodology for the categorization of electrical and electronic systems and components (EESCs) for nuclear power plant licensees/operators that choose to adopt regulations, such as 10 CFR 50.69, that provide for risk analysis and categorization of electrical and electronic components and appropriate treatment or that choose to establish facility prioritization, effectiveness, or optimization processes supporting risk-informed decision-making.
Background===
* IEEE Std. 1819 provides guidance on specific electrical and electronic equipment including:
- Circuit breakers
- Busbars, cables, and transformers
- Distribution panels and relay panels 8


===Background===
Industry Feedback Received
* IEEE Std. 1819 provides guidance on specific electrical and electronic equipment including:
- Circuit breakers
- Busbars, cables, and transformers
- Distribution panels and relay panels Industry Feedback Received
* IEEE letter to NRC dated 10/15/2019
* IEEE letter to NRC dated 10/15/2019
- IEEE NPEC provided a list of IEEE nuclear standards for which IEEE requests NRC give priority for endorsement
- IEEE NPEC provided a list of IEEE nuclear standards for which IEEE requests NRC give priority for endorsement
- IEEE Std. 1819-2016 was included due to the increased emphasis on risk-informed categorization within the NRC.
- IEEE Std. 1819-2016 was included due to the increased emphasis on risk-informed categorization within the NRC.
Industry Feedback Received (Cont d)
9
 
Industry Feedback Received (Contd)
* NRC presentation to PWROG, Risk Management Committee, dated 8/18/2021
* NRC presentation to PWROG, Risk Management Committee, dated 8/18/2021
- NRC discussed the potential endorsement of IEEE Std. 1819-2016
- NRC discussed the potential endorsement of IEEE Std. 1819-2016
- NRC identified potential endorsement paths
- NRC identified potential endorsement paths
- NRC discussed potential updates to RG 1.201 Industry Feedback Received (Cont d)
- NRC discussed potential updates to RG 1.201 10
 
Industry Feedback Received (Contd)
* Nuclear Energy Institute (NEI) letter to NRC, dated 10/6/2021
* Nuclear Energy Institute (NEI) letter to NRC, dated 10/6/2021
- NEI recommends the NRC to not pursue endorsement of IEEE Std 1819-2016
- NEI recommends the NRC to not pursue endorsement of IEEE Std 1819-2016
* Pressurized Water Reactor Owner s Group (PWROG) and Boiling Water Reactor Owner s Group (BWROG) letter to NRC, dated 10/27/2021
* Pressurized Water Reactor Owners Group (PWROG) and Boiling Water Reactor Owners Group (BWROG) letter to NRC, dated 10/27/2021
- Both Owner s Groups (OGs) recommend the NRC to not pursue endorsement of IEEE Std. 1819-2016 Industry Feedback Received (Cont d)
- Both Owners Groups (OGs) recommend the NRC to not pursue endorsement of IEEE Std. 1819-2016 11
 
Industry Feedback Received (Contd)
* IEEE NPEC letter to NRC, dated 3/6/2022
* IEEE NPEC letter to NRC, dated 3/6/2022
- IEEE recommends and supports the NRC endorsement of IEEE 1819-2016 as a standard that is used in conjunction with other industry guidance Possible NRC Paths Forward
- IEEE recommends and supports the NRC endorsement of IEEE 1819-2016 as a standard that is used in conjunction with other industry guidance 12
 
Possible NRC Paths Forward
* Not endorse IEEE Std. 1819-2016
* Not endorse IEEE Std. 1819-2016
* Endorse IEEE Std. 1819-2016 in a new RG
* Endorse IEEE Std. 1819-2016 in a new RG
- Endorse in full
- Endorse in full
- Endorse in part (e.g., clarifications and/or sections notendorsed)
- Endorse in part (e.g., clarifications and/or sections not endorsed)
* Endorse IEEE Std. 1819-2016 in an existing RG 1.201,Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance
* Endorse IEEE Std. 1819-2016 in an existing RG 1.201, Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance
- Endorse in full
- Endorse in full
- Endorse in part (e.g., clarifications and/or sections notendorsed)
- Endorse in part (e.g., clarifications and/or sections not endorsed) 13
 
Feedback Requested
Feedback Requested
* Path forward and rationale
* Path forward and rationale  
- Challenges and Benefits
- Challenges and Benefits
* Current guidance
* Current guidance
- Is current guidance adequate in the electrical arena?
- Is current guidance adequate in the electrical arena?  
- Any areas for refinement in those tools?
- Any areas for refinement in those tools?
* Implementation guidance
* Implementation guidance
- Are there industry implementation challenges where the IEEE standard may alleviate these challenges?
- Are there industry implementation challenges where the IEEE standard may alleviate these challenges?
14
 
Questions?
Questions?
15
Acronyms
Acronyms
* BW RO G - Boiling Water Reactor Owner s Group
* BWROG - Boiling Water Reactor Owners Group
* CFR - Code of Federal Regulations
* CFR - Code of Federal Regulations
* EESC - Electrical and Electronic systems and components
* EESC - Electrical and Electronic systems and components
Line 97: Line 110:
* NPEC - Nuclear Power Engineering Committee
* NPEC - Nuclear Power Engineering Committee
* NRC - Nuclear Regulatory Commission
* NRC - Nuclear Regulatory Commission
* PWRO G - Pressurized Water Reactor Owner s Group
* PWROG - Pressurized Water Reactor Owners Group
* RG - Regulatory Guide
* RG - Regulatory Guide
* SSC - system, structure, or component
* SSC - system, structure, or component
* Std. - Standard References
* Std. - Standard 16
 
References
* RG 1.201, Revision 1: ML061090627
* RG 1.201, Revision 1: ML061090627
* NEI 00- 04, Revision 0: ML052910035
* NEI 00-04, Revision 0: ML052910035
* Periodic Review of RG 1.201: ML15091A788
* Periodic Review of RG 1.201: ML15091A788
* IEEE letter to NRC dated 10/15/2019: ML22060A012
* IEEE letter to NRC dated 10/15/2019: ML22060A012
Line 110: Line 125:
* PWROG and BWROG letter to NRC, dated 10/27/2021:
* PWROG and BWROG letter to NRC, dated 10/27/2021:
ML21300A176
ML21300A176
* IEEE NPEC letter to NRC, dated 3/6/2022: ML22066A768 Discussion Public Comments Closing Remarks}}
* IEEE NPEC letter to NRC, dated 3/6/2022: ML22066A768 17
 
Discussion 18
 
Public Comments 19
 
Closing Remarks 20}}

Latest revision as of 17:47, 27 November 2024

NRC Consideration of IEEE Std - 1819
ML22070B120
Person / Time
Issue date: 03/16/2022
From: Sheila Ray
NRC/NRR/DEX/EEEB
To:
Ray, S; Roche-Rivera, R
Shared Package
ML22070B114 List:
References
Download: ML22070B120 (20)


Text

NRC Consideration of IEEE Standard 1819 on Risk-Informed Categorization of Electrical

& Electronic Equipment Sheila Ray, P.E.

NRC March 16, 2022

Agenda Time/Duration Topic Speaker 1:30 PM Welcome and Introductions NRC 1:35 PM Opening Remarks NRC/NEI/IEEE 1:45 PM Discussion NRC/NEI/BWROG/PWROG/IEEE 4:00 PM Opportunity for Public Comments Members of the Public 4:20 PM Closing Remarks NRC/NEI/IEEE 4:30 PM Adjourn Meeting 2

Opening Remarks 3

Topics of Discussion

  • Background
  • Feedback Received
  • Potential/Possible NRC Path Forward
  • Feedback on NRC Approaches 4

=

Background===

  • The NRC continues to transform to realize our vision of becoming a modern, risk-informed regulator to continue meeting our important safety and security mission.
  • 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components (SSC) for Nuclear Power Reactors.

- Regulatory Guide (RG) 1.201, Revision 1, (Trial Use) Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance,

  • NRC performed a periodic review of RG 1.201 in 2015

- Identified technical and regulatory enhancements for a future revision 5

=

Background===

  • IEEE Std. 1819-2016, IEEE Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities

- Methods to categorize electrical and electronic components using a risk-informed process and identifies how the categorization results relate to Class 1E/non-Class 1E classifications.

- Standardized and accepted method for alternate treatment of categorized components commensurate with their safety significance.

6

=

Background===

  • The intent of IEEE Std. 1819-2016, as delineated in the History section of the standard, aims to provide guidance for establishing a methodology for the categorization of electrical and electronic systems and components (EESCs) for nuclear power plant licensees/operators that choose to adopt regulations, such as 10 CFR 50.69, that provide for risk analysis and categorization of electrical and electronic components and appropriate treatment or that choose to establish facility prioritization, effectiveness, or optimization processes supporting risk-informed decision-making.

7

=

Background===

  • IEEE Std. 1819 provides guidance on specific electrical and electronic equipment including:

- Circuit breakers

- Busbars, cables, and transformers

- Distribution panels and relay panels 8

Industry Feedback Received

  • IEEE letter to NRC dated 10/15/2019

- IEEE NPEC provided a list of IEEE nuclear standards for which IEEE requests NRC give priority for endorsement

- IEEE Std. 1819-2016 was included due to the increased emphasis on risk-informed categorization within the NRC.

9

Industry Feedback Received (Contd)

  • NRC presentation to PWROG, Risk Management Committee, dated 8/18/2021

- NRC discussed the potential endorsement of IEEE Std. 1819-2016

- NRC identified potential endorsement paths

- NRC discussed potential updates to RG 1.201 10

Industry Feedback Received (Contd)

  • Nuclear Energy Institute (NEI) letter to NRC, dated 10/6/2021

- NEI recommends the NRC to not pursue endorsement of IEEE Std 1819-2016

  • Pressurized Water Reactor Owners Group (PWROG) and Boiling Water Reactor Owners Group (BWROG) letter to NRC, dated 10/27/2021

- Both Owners Groups (OGs) recommend the NRC to not pursue endorsement of IEEE Std. 1819-2016 11

Industry Feedback Received (Contd)

  • IEEE NPEC letter to NRC, dated 3/6/2022

- IEEE recommends and supports the NRC endorsement of IEEE 1819-2016 as a standard that is used in conjunction with other industry guidance 12

Possible NRC Paths Forward

- Endorse in full

- Endorse in part (e.g., clarifications and/or sections not endorsed)

  • Endorse IEEE Std. 1819-2016 in an existing RG 1.201, Guidelines for Categorizing Structures, Systems, and Components in Nuclear Power Plants According to Their Safety Significance

- Endorse in full

- Endorse in part (e.g., clarifications and/or sections not endorsed) 13

Feedback Requested

  • Path forward and rationale

- Challenges and Benefits

  • Current guidance

- Is current guidance adequate in the electrical arena?

- Any areas for refinement in those tools?

  • Implementation guidance

- Are there industry implementation challenges where the IEEE standard may alleviate these challenges?

14

Questions?

15

Acronyms

  • BWROG - Boiling Water Reactor Owners Group
  • CFR - Code of Federal Regulations
  • EESC - Electrical and Electronic systems and components
  • IEEE - Institute of Electrical and Electronics Engineers
  • NEI - Nuclear Energy Institute
  • NPEC - Nuclear Power Engineering Committee
  • NRC - Nuclear Regulatory Commission
  • PWROG - Pressurized Water Reactor Owners Group
  • RG - Regulatory Guide
  • SSC - system, structure, or component
  • Std. - Standard 16

References

  • NRC response to IEEE NPEC, dated 12/26/2019: ML19352E115
  • NRC presentation to PWROG, Risk Management Committee, dated 8/18/2021: ML21231A167

ML21300A176

  • IEEE NPEC letter to NRC, dated 3/6/2022: ML22066A768 17

Discussion 18

Public Comments 19

Closing Remarks 20