Digital Instrumentation and Control December 17, 2015 Speakers - - PowerPoint PPT Presentation

digital instrumentation and control
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Digital Instrumentation and Control December 17, 2015 Speakers - - PowerPoint PPT Presentation

Digital Instrumentation and Control December 17, 2015 Speakers Speakers Victor McCree, Executive Director for Operations, NRC John Lubinski, Acting Deputy Office Director for Engineering, NRR Richard Stattel, Senior Electronics


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Digital Instrumentation and Control

December 17, 2015

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SLIDE 2

Speakers Speakers

  • Victor McCree, Executive Director for

Operations, NRC

  • John Lubinski, Acting Deputy Office Director

for Engineering, NRR

  • Richard Stattel, Senior Electronics Engineer,

NRR

  • John Tappert, Director of Division of

Engineering, NRO

  • Deanna Zhang, Senior Electronics Engineer,

NRO

2

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Agenda Agenda

  • Background of Digital I&C and

Lessons Learned

  • Incorporation by Reference of

IEEE 603-2009

  • Other Key Regulatory Initiatives

3

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Background Background—Why is Digital Why is Digital Technology Unique? Technology Unique?

  • Different principles of operation
  • Different hazards for digital vs.

analog

  • Communications independence

challenges

  • Increased potential for latent

errors

4

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Early Actions Taken Early Actions Taken to Address Digital to Address Digital

  • Development of guidance to

address unique aspects of digital

– Regulatory guides on digital I&C system development – Standard review plan revision

5

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Formation of the Digital I&C Formation of the Digital I&C Steering Committee Steering Committee

  • Task working groups initiated to

address digital I&C licensing process

  • Issuance of digital I&C interim

staff guidance

6

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SLIDE 7

What We Learned What We Learned— Operating Reactors Operating Reactors

  • Digital I&C licensing processes

can be improved

– Early communications and identification of required documentation works well – Graded review approach needs to be improved

7

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What We Learned What We Learned— New New Reactors Reactors

  • Utilize highly integrated digital

I&C systems

  • Challenged in providing sufficient

design information and analysis to demonstrate safety with initial designs

  • Addressing requirements at

architectural level was effective

8

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What We Learned What We Learned— Other Key Issues Other Key Issues

  • Current I&C requirements should

be updated to address digital

  • Ambiguities in 10 CFR 50.59

guidance need to be revised

  • Diversity and defense-in-depth

criteria need to be re-evaluated

9

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The Role of IEEE 603 The Role of IEEE 603

  • Criteria for I&C safety systems

– Tech Technolog nology y neu neutral tral – Perfor Performa manc nce base based

  • Incorporated into regulation

– Inco Incorp rpor

  • rate

ted by by refe referen ence ce – Gene General ral Design Design Crite Criteria ria

10

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What Changed in the What Changed in the Standard Standard

  • New version of the standard adds:

– Guidance for digital technology – Annex on electromagnetic compatibility – Guidance for connected equipment – Communication independence criteria

11

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Applicability of Applicability of New New Standard Standard

  • Cond

Conditions for itions for a applicability o pplicability of th f the e new new and and prev previously iously incorp incorporat

  • rated

ed version versions

– New plant designs required to comply with IEEE 603-2009 – Impacts operating plants and existing design certifications if changes meet threshold

12

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System Integrit System Integrity

  • Amplify “System Integrity”

requ requirement irements

  • Cond

Condition ition adde added: d:

– In order to assure the integrity and reliable operation of safety systems, safety functions shall be designed to

  • perate in a predictable and

repeatable manner.

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Examp Example le Reac Reactor tor Prote Protectio ction n Syste System

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Safety Division (A) Safety Division (B) Safety Division (C) Safety Division (D) Actuation Components (Reactor Trip Breakers / ESF)

Coincidence Voting Processor (Two of Four) Coincidence Voting Processor (Two of Four)

Plant Process Inputs Non Safety Related Systems

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Independe Independence nce

  • Amplify “Independence”

requ requirement irements

– Between redundant portions of safety systems – Between safety systems and other systems

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Independe Independence (cont.) nce (cont.)

  • Amplify “Independence”

requ requirement irements

  • A. Manne
  • A. Manner

r of

  • f processi

processing ng data data

  • B. Detec
  • B. Detection

tion an and d mitigation mitigation ca capa pabilities bilities

16

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Independe Independence (cont.) nce (cont.)

  • Amplify “Independence”

requ requirement irements

  • C. For
  • C. For curr

current nt reac reacto tors, rs, Sign Signals als mus must s t sup uppo port rt safe safety ty or

  • r pro

provide vide a safety a safety ben benefit. efit.

17

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Independe Independence (cont.) nce (cont.)

  • Amplify “Independence”

requ requirement irements

  • D. For
  • D. For new

new reac reacto tors rs, (1) (1) One One-way way—ha hardwa ware re en enforc forced (2) On (2) Only ly signals to signals to pe perfor rform m safety safety funct function ions s are are allowed allowed

18

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Independe Independence (cont.) nce (cont.)

  • Amplify “Independence”

requ requirement irements

(3) (3) Signals to suppor Signals to support t diversity diversity and and au autom tomat atic ic an anticipa ticipatory ry rea reacto ctor r trip trip funct function ions (4) (4) Proposed Proposed alterna alternatives tives requ requireme irements ts

19

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Potential Impact Potential Impact on

  • n

Operating Operating Plants Plants

  • Supp

Supports

  • rts use of n

use of newer ewer version version of

  • f

IEEE IEEE 603 603

  • Applican

Applicants a ts already lready perform perform hazard hazard ana analysis lysis

20

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Potential Impact Potential Impact on

  • n

New Reactors New Reactors

  • Commun

Communication ication indepe independen ndence ce demon demonstrat strated ed at h at higher igher level level

  • Limit failure

Limit failure modes modes and and unexpected unexpected behaviors behaviors associated associated with communications with communications

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Stakeholder Stakeholder Engagement Engagement

  • NRC staff

NRC staff part participated icipated in in IEEE IEEE 603 603-2009 2009 d develop evelopment ment

  • ACRS recomme

ACRS recommended nded adding adding cond conditions itions

  • Indust

Industry g ry gener enerally did n ally did not s

  • t suppo

upport rt added conditi added conditions

  • ns
  • NEI d

NEI does not

  • es not supp

support

  • rt issuan

issuance of ce of proposed rule proposed rule

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Benefits of Proposed Rule Benefits of Proposed Rule

  • Facilitates use of IEEE 603-2009

– Updates for new technology – More effective EMC

  • Conditions provide improved

consistency and predictability for licensing

  • Issuing the proposed rule will

facilitate external stakeholder feedback

23

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Key Regulatory Initiatives Key Regulatory Initiatives— Develop a DI&C Action Plan Develop a DI&C Action Plan

  • Address lessons learned and

stakeholder feedback

  • Prioritize activities
  • Coordinate with industry

initiatives

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Interface with industry stakeholders Interface with industry stakeholders

10 CFR 50.59

DI&C Action DI&C Action Plan Plan

Review/Comment

  • n NEI draft 50.59

guidance Identify impact on NRC policy/guidance documents

Licensing Process

Evaluate guidance based

  • n lessons

learned Revise regulatory guidance Interface with industry stakeholders Revise regulatory guidance

Software CCF

Evaluate assumptions in SECY-93-087 Evaluate options for updating NRC policy Prepare technical basis Prepare SECY paper

Cyber Review in Design

Develop options for reviewing cyber- related design information Draft SECY paper to propose options to Commission Revise appropriate documentation in accordance with Commission direction

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Enhance 10 CFR Enhance 10 CFR 50.59 Guidance 50.59 Guidance

  • Non-compliances identified when

upgrades performed

  • Ensure updated guidance is

adequate

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How Software Common Cause How Software Common Cause Failure is Currently Failure is Currently Addressed Addressed

  • SRM-SECY-93-087 defines criteria

for addressing software common cause failure

– BTP 7-19: guidance for implementation – NUREG/CR-6303: guidance for performing diversity and defense-in- depth analysis

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Improve Softwar Improve Software e Common Common Cause Failure Criteria Cause Failure Criteria

  • Evaluate existing policy on

software common cause failure

– Incorporate advances in digital technology – Prepare a technical basis paper and a SECY paper – Maintain interfaces with industry stakeholders throughout effort

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Improve Licensing Proc Improve Licensing Process ess for for Digital I&C Systems Digital I&C Systems

  • Enhance licensing process in

ISG-06 to include lessons from the pilot

  • Improve guidance for new reactor

licensing processes

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Review Cyber Security Design Review Cyber Security Design Features During Licensing Features During Licensing

  • Cyber security design not

currently reviewed as part of licensing

  • Early consideration of cyber

security in the design process is beneficial

  • SECY paper under development

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Digital I&C Action Plan Digital I&C Action Plan

  • Additional activities:

– Highly integrated systems – Regulatory infrastructure – Guidance for alternative evaluation – Consistency: licensing and inspections – Topical report process

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Summary Summary

  • Publish proposed rule to obtain

stakeholder feedback

  • Ensure Digital I&C Action Plan

includes key regulatory initiatives

  • Coordinate with industry digital

I&C working group

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Acronyms Acronyms

ACRS – Advisory Committee on Reactor Safeguards BTP – Branch Technical Position CFR – Code of Federal Regulations DI&C – Digital Instrumentation and Control EMC – Electromagnetic Compatibility ESF – Engineered Safety Feature I&C – Instrumentation and Control IEEE – Institute of Electrical and Electronics Engineers ISG – Interim Staff Guidance NEI – Nuclear Energy Institute NRC – Nuclear Regulatory Commission NRO – Office of New Reactors NRR – Office of Nuclear Reactor Regulation NUREG – NRC technical report SECY paper – Commission Paper SRM – Staff Requirements Memorandum 33