ML18310A433

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NRR E-mail Capture - (External_Sender) NEI 96-07 Appendix D Rev 0g October 2018
ML18310A433
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Site: Nuclear Energy Institute
Issue date: 10/26/2018
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Nuclear Energy Institute
To: Tekia Govan, Bo Pham
Division of Inspection and Regional Support
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NEI-96-07
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NRR-DMPSPEm Resource From: AUSTGEN, Kati <kra@nei.org>

Sent: Friday, October 26, 2018 4:42 PM To: Pham, Bo; Govan, Tekia Cc: REMER, Jason; GEIER, Stephen; Beaulieu, David; Morton, Wendell; Carte, Norbert

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[External_Sender] NEI 96-07 Appendix D Rev 0g October 2018 Attachments: NEI 96-07 Appendix D Rev 0g October 2018.docx; NEI 96-07 Appendix D Rev 0g October 2018 REDLINE.docx Bo & Tekia, Please find the latest draft revision (0g) of NEI 96-07 Appendix D attached. A redline mark-up is also included for your convenience.

Thanks, Kati Austgen l Sr. Project Manager, New Plant, SMR & Advanced Reactors 1201 F Street, NW, Suite 1100 l Washington, DC 20004 P: 202.739.8068 M: 202.340.1224 nei.org This electronic message transmission contains information from the Nuclear Energy Institute, Inc. The information is intended solely for the use of the addressee and its use by any other person is not authorized. If you are not the intended recipient, you have received this communication in error, and any review, use, disclosure, copying or distribution of the contents of this communication is strictly prohibited. If you have received this electronic transmission in error, please notify the sender immediately by telephone or by electronic mail and permanently delete the original message. IRS Circular 230 disclosure: To ensure compliance with requirements imposed by the IRS and other taxing authorities, we inform you that any tax advice contained in this communication (including any attachments) is not intended or written to be used, and cannot be used, for the purpose of (i) avoiding penalties that may be imposed on any taxpayer or (ii) promoting, marketing or recommending to another party any transaction or matter addressed herein.

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[External_Sender] NEI 96-07 Appendix D Rev 0g October 2018 Sent Date: 10/26/2018 4:42:10 PM Received Date: 10/26/2018 4:42:22 PM From: AUSTGEN, Kati Created By: kra@nei.org Recipients:

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Tracking Status: None Post Office: MBX023-E2-VA-2.EXCH023.DOMAIN.LOCAL Files Size Date & Time MESSAGE 1508 10/26/2018 4:42:22 PM NEI 96-07 Appendix D Rev 0g October 2018.docx 180118 NEI 96-07 Appendix D Rev 0g October 2018 REDLINE.docx 268390 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

NEI 96-07, Appendix D Draft Revision 0g Nuclear Energy Institute SUPPLEMENTAL GUIDANCE FOR APPLICATION OF 10 CFR 50.59 TO DIGITAL MODIFICATIONS October 2018

ACKNOWLEDGMENTS NEI would like to thank the NEI 01-01 Focus Team for developing this document.

Although everyone contributed to the development of this document, NEI would like to give special recognition to David Ramendick, who was instrumental in preparing this document.

NOTICE Neither NEI, nor any of its employees, members, supporting organizations, contractors, or consultants make any warranty, expressed or implied, or assume any legal responsibility for the accuracy or completeness of, or assume any liability for damages resulting from any use of, any information apparatus, methods, or process disclosed in this report or that such may not infringe privately owned rights.

EXECUTIVE

SUMMARY

NEI 96-07, Appendix D, Supplemental Guidance for Application of 10 CFR 50.59 to Digital Modifications, provides focused application of the 10 CFR 50.59 guidance contained in NEI 96-07, Revision 1, to activities involving digital modifications.

The main objective of this guidance is to provide all stakeholders a common framework and understanding of how to apply the 10 CFR 50.59 process to activities involving digital modifications.

The guidance in this appendix supersedes the 10 CFR 50.59-related guidance contained in NEI 01-01/ EPRI TR-102348, Guideline on Licensing of Digital Upgrades and in Regulatory Issue Summary (RIS) 2002-22, Supplement 1, Clarification on Endorsement of Nuclear Energy Institute Guidance in Designing Digital Upgrades in Instrumentation and Control Systems.

i

TABLE OF CONTENTS EXECUTIVE

SUMMARY

...................................................................................................................................... i 1 INTRODUCTION ........................................................................................................................................ 2

1.1 BACKGROUND

................................................................................................... 2 1.2 PURPOSE ........................................................................................................... 3 1.3 10 CFR 50.59 PROCESS

SUMMARY

................................................................ 43 1.4 APPLICABILITY TO 10 CFR 72.48 ................................................................. 43 1.5 CONTENT OF THIS GUIDANCE DOCUMENT ................................................... 43 2 DEFENSE IN DEPTH DESIGN PHILOSOPHY AND 10 CFR 50.59 ............................................. 43 3 DEFINITIONS AND APPLICABILITY OF TERMS ............................................................................ 54 4 IMPLEMENTATION GUIDANCE........................................................................................................... 75 4.1 APPLICABILITY ............................................................................................... 75 4.2 SCREENING ..................................................................................................... 75 4.3 EVALUATION PROCESS ............................................................................... 2624 5.0 EXAMPLES ......................................................................................................................................... 6063 D-1

1 INTRODUCTION There are specific considerations that should be addressed as part of the 10 CFR 50.59 process when performing 10 CFR 50.59 reviews for digital modifications. These specific considerations include different potential failure modes of digital equipment as opposed to the equipment being replaced, the effect of combining functions of previously separate devices (at the component level, at the system level, or at the "multi-system" level) into fewer devices or one device, and the potential for software common cause failure (software CCF ).

The format of this Appendix was aligned with NEI 96-07, Rev. 1 text for ease of use. As such, there will be sections where no additional guidance is provided.

1.1 BACKGROUND

Licensees have a need to modify existing systems and components due to the growing problems of obsolescence, difficulty in obtaining replacement parts, and increased maintenance costs. Also, there is great incentive to take advantage of modern digital technologies that offer potential performance and reliability improvements.

In 2002, a joint effort between the Electric Power Research Institute (EPRI) and the Nuclear Energy Institute (NEI) produced NEI 01-01, Revision 0 (also known as EPRI TR-102348, Revision 1), Guideline on Licensing Digital Upgrades: A Revision of EPRI TR-102348 to Reflect Changes to the 10 CFR 50.59 Rule, which was endorsed (with qualifications) by the Nuclear Regulatory Commission (NRC) in Regulatory Issue Summary (RIS) 2002-22.

Since the issuance of NEI 01-01 in 2002, digital modifications have become more prevalent. Application of the 10 CFR 50.59 guidance contained in NEI 01-01 has not been consistent or thorough across the industry, leading to NRC concerns regarding uncertainty as to the effectiveness of NEI 01-01 and the need for clarity to ensure an appropriate level of rigor is being applied to a wide variety of activities involving digital modifications.

NEI 01-01 contained guidance for both the technical development and design of digital modifications, as well as the application of 10 CFR 50.59 to those digital modifications. The NRC also identified this "mixture of guidance" as an issue and stated that NEI should separate the technical guidance from the 10 CFR 50.59 guidance.

In 2018, Supplement 1 to RIS 2002-22 was issued to clarify the NRC staffs endorsement of the guidance pertaining to NEI 01-01, Sections 4 and 5 and Appendices A and B. Specifically, the RIS supplement clarified the guidance D-2

for preparing and documenting qualitative assessments that may be used to evaluate the likelihood of failure of a proposed digital modification, including the likelihood of failure due to a software common cause failure (software CCF).

Supplement 1 to RIS 2002-22 identified that a qualitative assessment may be used to support a conclusion that a proposed digital I&C modification will not result in more than a minimal increase in the frequency of occurrence of accidents or in the likelihood of occurrence of malfunctions (10 CFR 50.59(c)(2)(i) and (ii)). A qualitative assessment may also be used to support a conclusion that the proposed modification does not create the possibility of an accident of a different type or a malfunction with a different result than previously evaluated in the updated final safety analysis report (10 CFR 50.59(c)(2)(v) and (vi)).

1.2 PURPOSE Appendix D is intended to assist licensees in the performance of 10 CFR 50.59 reviews of activities involving digital modifications in a consistent and comprehensive manner. This assistance includes guidance for performing 10 CFR 50.59 Screens and 10 CFR 50.59 Evaluations. Appendix D does not alter and, unless explicitly noted, should not be interpreted differently than the guidance contained in NEI 96-07, Rev. 1. Rather, Appendix D provides focused guidance for the application of 10 CFR 50.59 to activities involving digital modifications.

The guidance in this appendix applies to 10 CFR 50.59 reviews for both small-scale and large-scale digital modifications; from the simple replacement of an individual analog meter with a microprocessor-based instrument, to a complete replacement of an analog reactor protection system with an integrated digital system. Examples of activities considered to involve a digital modification include computers, computer programs, data (and its presentation), embedded digital devices, software, firmware, hardware, the human-system interface, microprocessors and programmable digital devices (e.g., Programmable Logic Controllers and Field Programmable Gate Arrays).

This guidance is not limited to "stand-alone" instrumentation and control systems. This guidance can also be applied to the digital aspects of modifications or replacements of mechanical or electrical equipment if the new equipment makes use of digital technology (e.g., a new HVAC design that includes embedded microprocessors for control).

Finally, this guidance is applicable to digital modifications involving safety-related and non-safety-related systems and components and also covers D-3

digital-to-digital activities (i.e., modifications or replacements of digital-based systems).

1.3 10 CFR 50.59 PROCESS

SUMMARY

No additional guidance is provided.

1.4 APPLICABILITY TO 10 CFR 72.48 No additional guidance is provided.

1.5 CONTENT OF THIS GUIDANCE DOCUMENT Relationship of Appendix D to NEI 96-07, Revision 1 In sections 3 and 4 of this appendix, references to the main body of NEI 96-07, Revision 1 will be abbreviated as "NEI 96-07."

Guidance Focus In Sections 4.2 (Screening) and 4.3 (Evaluation), each section and sub-section addresses only a specific aspect, sometimes at the deliberate exclusion of other pertinent and/or related aspects.

This focused approach is intended to concentrate the guidance on the particular aspect of interest and does not imply that the other aspects do not apply or could not be related to the aspect being addressed. Initially, all aspects need to be considered, with the knowledge that some of them may be able to be excluded based on the actual scope of the digital modification being reviewed.

Example Focus Unless stated otherwise, a given example addresses ONLY the aspect within the section/sub-section in which it is included, sometimes at the deliberate exclusion of other pertinent and/or related aspects which, if considered, could potentially change the Screen and/or Evaluation conclusion(s).

2 DEFENSE IN DEPTH DESIGN PHILOSOPHY AND 10 CFR 50.59 No additional guidance is provided.

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3 DEFINITIONS AND APPLICABILITY OF TERMS Definitions 3.1 through 3.14 are the same as those provided in NEI 96-07.

Definitions specific to this appendix are defined below.

3.15 QUALITATIVE ASSESSMENT Definition:

A qualitative assessment is a specific type of technical-based engineering evaluation useful to 10 CFR 50.59 Evaluations when responding to Evaluation criteria 10 CFR 50.59(c)(2(i), (ii), (v) and (vi).

Discussion:

The purpose of a qualitative assessment is to determine the "magnitude" of the likelihood of a software CCF. The magnitude of the likelihood of a software CCF can be either sufficiently low (see the definition in Section 3.16) or not sufficiently low. Therefore, the only part of the qualitative assessment needed for responding to the four 10 CFR 50.59(c)(2) criteria listed above is the outcome (i.e., sufficiently low or not sufficiently low).

Although a qualitative assessment could be performed as part of developing the responses to the four 10 CFR 50.59(c)(2) criteria listed above, this technical-based engineering evaluation is typically performed "prior to" or "in parallel with" the completion of the 10 CFR 50.59 Evaluation.

Generally, reasonable assurance of the low likelihood of failure due to a software CCF is derived from the qualitative assessment of factors involving (1) the design attributes of the modified SSC, (2) the quality of the design processes, and (3) the operating experience of the software and hardware used (i.e., product maturity and in-service experience).

The qualitative assessment is used to record the factors and rationale for making a determination of the likelihood of failure (i.e., sufficiently low or not sufficiently low) due to a software CCF that a digital I&C modification will exhibit.

The determination of the likelihood of failure may consider the aggregate of all the factors described above. Namely, some of the factors may compensate for weaknesses in other areas or other factors. For example, thorough testing coupled with an analysis demonstrating untested states are accounted for in the proposed application may provide additional assurance of a sufficiently low likelihood of failure to compensate for a lack of operating experience.

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A qualitative assessment should not be used for digital I&C replacements of the reactor protection system (RPS), the engineered safety features actuation system (ESFAS), or modification/replacement of the internal logic portions of these systems (e.g., voting logic, bistable inputs, and signal conditioning/processing).

3.16 SUFFICIENTLY LOW Definition:

Sufficiently low means much lower than the likelihood of failures that are considered in the UFSAR (e.g., single failures) and comparable to other common cause failures that are not considered in the UFSAR (e.g., design flaws, maintenance errors and calibration errors).

Discussion:

This sufficiently low threshold is not interchangeable with that used for distinguishing between events that are credible or not credible. The threshold for determining if an event is credible uses the criterion of as likely as (i.e., not much lower than) the malfunctions already assumed in the UFSAR.

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4 IMPLEMENTATION GUIDANCE 4.1 APPLICABILITY No additional guidance is provided.

4.2 SCREENING CAUTION The guidance contained in this section of the appendix is intended to supplement the generic Screen guidance contained in the main body in NEI 96-07, Section 4.2.

Namely, the generic Screen guidance provided in the main body of NEI 96-07 and the more-focused Screen guidance in this appendix BOTH apply to digital modifications.

Introduction As stated in NEI 96-07, Section 4.2.1, the determination of the impact of a proposed activity (i.e., adverse or not adverse) is based on the impact of the proposed activity on UFSAR-described design functions. To assist in determining the impact of a digital modification on a UFSAR-described design function, the general guidance from NEI 96-07 will be supplemented with the digital-specific guidance in the topic areas identified below.

Digital-to-Digital Replacements and "Equivalency" In NEI 96-07, Section 4.2.1.1, equivalent replacements are discussed.

However, digital-to-digital changes may not necessarily be equivalent because the component/system behaviors, response times, failure modes, etc.

for the new component/system may be different from the old component/system. All non-equivalent digital-to-digital replacements should utilize the guidance provided in this Appendix.

Human-System Interface Considerations Similar to other technical evaluations (performed as part of the design modification package), a human factors engineering (HFE) evaluation determines the impacts and outcomes of the change (e.g., personnel acts or omissions, as well as their likelihoods and effects). The licensing-based reviews (Screens and Evaluations) performed in accordance with 10 CFR 50.59 compare the impacts and new outcomes (i.e., post-modification) to the initial conditions and current outcomes (i.e., pre-modification) in order to determine the effect on design functions (in the Screen phase) and the need for a license amendment request (in the Evaluation phase).

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4.2.1 Is the Activity a Change to the Facility or Procedures as Described in the UFSAR?

Introduction There is no regulatory requirement for a proposed activity involving a digital modification to default (i.e., be mandatorily "forced") to an adverse conclusion.

Although there may be adverse impacts on UFSAR-described design functions due to the following types of activities involving a digital modification, these typical activities do not default to an adverse conclusion simply because of the activities themselves.

  • The introduction of software or digital devices.
  • The replacement of software and/or digital devices with other software and/or digital devices.
  • The use of a digital processor to "calculate" a numerical value or "generate" a control signal using software in place of using analog components.
  • Replacement of hard controls (i.e., pushbuttons, knobs, switches, etc.) with a touch-screen to operate or control plant equipment.

Engineering/technical information should be documented (as part of the design process) to record the impacts from digital modifications. This engineering/technical information will be used as the basis/justification for the conclusion of adverse or not adverse.

Scope of Digital Modifications Generally, a digital modification may consist of three areas of activities: (1) software-related activities, (2) hardware-related activities and (3) Human-System Interface-related activities.

NEI 96-07, Section 4.2.1.1 provides guidance for activities that involve "...an SSC design function..." or a "...method of performing or controlling a design function..." and Section 4.2.1.2 provides guidance for activities that involve

"...how SSC design functions are performed or controlled (including changes to UFSAR-described procedures, assumed operator actions and response times)."

Based on this segmentation of activities, the software and hardware portions will be assessed within the "facility" Screen consideration since these aspects involve SSCs, SSC design functions, or the method of performing or controlling a design function and the Human-System Interface (HSI) portion will be assessed within the "procedures" Screen consideration since this portion involves how SSCs are operated and controlled.

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4.2.1.1 Screening of Changes to the Facility as Described in the UFSAR SCOPE In the determination of potential adverse impacts, the following aspects should be addressed in the response to this Screen consideration:

(a) Use of Software and Digital Devices (b) Combination of Components/Systems and/or Functions USE OF SOFTWARE AND DIGITAL DEVICES Discussion For applications involving SSCs with design functions, an adverse effect may be created due to the potential marginal increase in the likelihood of SSC failure due to the introduction of software. This does not mean that all digital modifications that introduce software will automatically screen-in.

For redundant safety systems, this marginal increase in likelihood creates a similar marginal increase in the likelihood of a common failure in the redundant safety systems. On this basis, most digital modifications to redundant safety systems are adverse.

However, for some digital modifications, the engineering/technical information supporting the change may show that the digital modification contains design attributes to eliminate consideration of a software common cause failure (i.e., software CCF likelihood = 0). In such cases, even when a digital modification involves redundant systems, the digital modification would not be adverse.

For relatively simple digital modifications, engineering/technical information supporting the change may be used to show that the digital modification would not adversely affect design functions; even for digital modifications that involve redundant components/systems because a software CCF is not introduced (i.e., software CCF likelihood = 0).

To reach a screen conclusion of not adverse for relatively simple digital modifications, the degree of assurance needed to make that conclusion is based on considerations such as the following:

  • Physical Characteristics of the Digital Modification The change has a limited scope (e.g., replace analog transmitter with a digital transmitter that drives an existing instrument loop)

Uses a relatively simple digital architecture internally (e.g., simple process of acquiring one input signal, setting one output, and performing some simple diagnostic checks)

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Has limited functionality (e.g., transmitters used to drive signals for parameters monitored)

Can be comprehensively tested (but not necessarily 100 percent of all combinations)

  • Engineering Evaluation Assessments The quality of the design processes employed Single failures of the digital device are encompassed by existing failures of the analog device (e.g., no new digital communications among devices that introduce possible new failure modes involving separate devices)

Has extensive applicable operating history The use of different software in two or more channels, trains or loops of SSCs is not adverse due to a software CCF because there is no mechanism to create a new malfunction due to the introduction of the software.

Some specific examples of activities that have the potential to cause an adverse effect include the following activities:

  • Addition or removal of a dead-band, or
  • Replacement of instantaneous readings with time-averaged readings (or vice-versa).

In each of these specific examples, the impact on a design function associated with the stated condition needs to be assessed to determine the Screen conclusion (i.e., adverse or not adverse).

EXAMPLES Example 4-1 illustrates the application of the guidance for a relatively simple digital modification.

Example 4-1. NO ADVERSE IMPACT on a Design Function for a Relatively Simple Digital Modification Proposed Activity Description Transmitters are used to drive signals for parameters monitored by redundant ESFAS channels. The original analog transmitters are to be replaced with microprocessor-based transmitters. The change is of limited scope since the existing 4-20 mA instrument loop is maintained for each channel without any changes other than replacing the transmitter itself.

The digital transmitters are used to drive signals of monitored parameters and thus have limited functionality with respect to the ESFAS design function.

Design Function Identification D-10

The ESFAS design function is the ability to respond to plant accidents.

Screen Response The digital transmitters use a relatively simple digital architecture internally.

Failures of the new digital device are encompassed by the failures of the existing analog device. The engineering/technical information supporting the change concluded that the digital system is at least as reliable as the previous system, the conclusion of which is based on the quality of the design processes employed, and the operating history of the software and hardware used. In addition, based on the simplicity of the device, it was comprehensively tested. Further, substantial operating history has demonstrated high reliability in applications similar to the ESFAS application.

Therefore, the proposed digital modification is not adverse (for the aspect being illustrated in this example) because the digital modification is relatively simple and the assessment of the considerations identified above has determined that the reliability of performing the design function is not reduced and a software CCF is not introduced.

Examples 4-2 and 4-3 illustrate the application of the Use of Software and Digital Devices aspect.

Example 4-2. NO ADVERSE IMPACT on a Design Function related to use of Software and Digital Devices Proposed Activity Description Two non-safety-related trains of main feedwater heaters exist, one for each train of main feedwater. Each main feedwater train consists of six feedwater heaters, for a total of 12 heaters. Each heater possesses an analog controller to control the water level in each of the heaters. Each analog controller is physically and functionally the same.

Each of the analog controllers will be replaced with its own digital controller.

The hardware platform for each digital controller is from the same supplier and the software in each digital controller is exactly the same.

Design Function Identification In this case, the review of the UFSAR determined that there are NO design functions associated with the feedwater heater water level controllers. The only UFSAR description related to the heaters states that the feedwater heater water level controllers are used to adjust the water levels in the heaters to optimize the thermal efficiency of the facility.

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Screen Response Since there are no design functions associated with the feedwater heater water level controllers, there are no adverse impacts (for the aspect being illustrated in this example).

Example 4-3. ADVERSE IMPACT on a Design Function related to use of Software and Digital Devices Proposed Activity Description Two non-safety-related main feedwater pumps (MFWPs) exist. There are two analog control systems (one per MFWP) that are physically and functionally the same.

The two analog control systems will be replaced with two digital control systems. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

No combination of components/systems and/or functions occurs as part of this digital modification.

Design Function Identification The design function of the feedwater control systems is to automatically control and regulate feedwater flow to the steam generators.

Screen Response The digital modification associated with this proposed activity is not relatively simple, so the process for assessing relatively simple digital modifications could not be used.

There is an adverse impact (for the aspect being illustrated in this example) on the design function of the main feedwater control system because the use of the exact same software in both digital control systems creates a potential software CCF that did not previously exist.

COMBINATION OF COMPONENTS/SYSTEMS AND/OR FUNCTIONS Discussion The UFSAR may identify the number of components/systems, how the components/systems are arranged and/or how functions are allocated to those components/systems.

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When replacing analog SSCs with digital SSCs, it is potentially advantageous to combine multiple components/systems and/or functions into a single device or control system. However, as a result of this combination, the failure of the single device or control system has the potential to adversely affect design functions.

The mere act of combining previously separate components/systems and/or functions does not make the Screen conclusion adverse. However, if combining the previously separate components/systems and/or functions causes an adverse impact on a design function (e.g., by causing the loss of multiple design functions when the digital device fails), then the combination aspect of the digital modification will have an adverse impact on a design function (i.e., screen in).

When comparing the existing and proposed configurations, consider how the proposed configuration affects the number and/or arrangement of components/systems and the potential impacts of the proposed arrangement on design functions.

Furthermore, digital modifications that involve networking; combining design functions from different systems; interconnectivity across channels, systems, and divisions; or shared resources, merit careful review to determine if such modifications cause reductions in the redundancy, diversity, separation, or independence of UFSAR-described design functions (if such design functions exist).

Combining different functions due to digital modifications can result in combining design functions of different systems; either directly in the same digital device, or indirectly through shared resources. Shared resources (e.g.,

bidirectional communications, power supplies, controllers, and multifunction display and control stations) introduced by digital modifications may reduce the redundancy, diversity, separation, or independence of UFSAR-described design functions.

Reductions in the redundancy, diversity, separation, or independence of a UFSAR-described design function (if such a design function exists) have an adverse impact on that design function.

EXAMPLES Examples 4-4 through 4-6 illustrate the application of the Combination of Components/Systems and/or Functions aspect.

Example 4-4. Combining Components and Functions with NO ADVERSE IMPACT on a Design Function Proposed Activity Description Two non-safety-related main feedwater pumps (MFWPs) exist. There are two D-13

analog control systems (one per MFWP) that are physically and functionally the same. Each analog control system has many subcomponents.

Option #1: Within each control system, all of the analog subcomponents will be replaced with a single digital device that consolidates all of the components, sub-components and the functions associated with each component and sub-component. The components and sub-components in each analog control system will be replaced with their own digital control system, retaining two discreet, unconnected control systems.

Option #2: Instead of two discreet, unconnected digital control systems being used for the feedwater control systems (as outlined in Option #1), only one digital device is proposed to be used that will combine ALL components, sub-components and functions of both control systems.

Design Function Identification Although the control systems and the major components are described in the UFSAR, only a design function for the feedwater control systems is identified.

The design function of the feedwater control systems is to automatically control and regulate feedwater flow to the steam generators.

The UFSAR identifies the following MFWP control system malfunctions:

(a) failures causing the loss of all feedwater to the steam generators, and (b) failures causing an increase in main feedwater flow to the maximum output from both MFWPs.

Screen Response Option #1: There is no adverse impact (for the aspect being illustrated in this example) on the design function of the main feedwater control systems to automatically control and regulate feedwater to the steam generators due to the combination of components in each of the two channels because only one design function would be affected by a failure of the new digital device (i.e.,

the current malfunctions already consider the effect on each MFWP).

Option #2: Although both main feedwater pumps would be affected by the failure of the one central digital processor, the proposed activity is not adverse (for the aspect being illustrated in this example) because only one design function would be affected by a failure of the new digital device and no new malfunctions are created (i.e., the current malfunctions already consider the effect on both MFWPs).

NOTE: For both options, if the malfunctions had considered the effect on only one MFWP, the Screen conclusions would have been adverse (for the aspect being illustrated in this example) because multiple design functions (i.e., one for each MFWP) would have been affected by a failure of the new D-14

digital device, creating a new malfunction.

Example 4-5. Combining Components and Functions with NO ADVERSE IMPACT on a Design Function Proposed Activity Description A temperature monitor/controller in a room containing an emergency room cooler provides an input to an air damper controller. If temperature gets too high, the temperature controller sends a signal to the air damper to open (if closed) to a predetermined initial position or, if already open, adjusts the position of the damper to allow increased air flow into the room.

Both analog controllers will be replaced with a single digital device that will perform in accordance with the original design requirements providing both temperature monitoring/control and air damper control.

Design Function Identification The temperature monitor/controller performs a design function to control the temperature in the room by continuously monitoring the temperature in the room to ensure the initial conditions are met should the emergency room cooler be needed.

The air damper controller performs a design function to control the temperature in the room by continuously providing the appropriate air flow to the room to ensure the initial conditions are met should the emergency room cooler be needed.

There is no lower limit on the acceptable temperature in the room.

Screen Response In the current design, a failure of the temperature monitor/controller or the air damper controller causes the loss of the ability to perform one design function (i.e., the ability to control the temperature in the room). In the proposed design, the failure of the digital device causes multiple failures, but still only the loss of the ability to perform one design function (i.e., the ability to control the temperature in the room). With only the loss of the ability to perform one design function in the current design and in the proposed design, there is no adverse impact (for the aspect being illustrated in this example) on the design functions.

The combining of components/systems and/or functions that were previously and completely physically and/or electrically discrete (i.e., not coupled) are of particular interest when determining the impact on design functions.

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Example 4-6 illustrates the combining of control systems from different, originally discrete systems.

Example 4-6. Combining Systems and Functions with an ADVERSE IMPACT on a Design Function Proposed Activity Description One non-safety-related analog Steam Bypass Control System (SBCS) and one non-safety-related main turbine steam inlet valves analog control system exist.

Both analog control systems will be replaced with one digital control system that will combine the SBCS and the main turbine steam-inlet valve control system into a single digital device.

Design Function Identification The design function of the SBCS is to maximize plant availability by making full utilization of the turbine bypass valve capacity to remove NSSS thermal energy to accommodate load rejections, unit trips, and other conditions that result in the generation of excessive energy by the NSSS. This objective is achieved by the selective use of turbine bypass valves to avoid unnecessary reactor trips and prevent the opening of secondary side safety valves whenever these occurrences can be averted by the controlled release of steam.

The design function of the main turbine inlet valve control system is to automatically control and regulate steam flow to the main turbine.

Screen Response Because the failure of the new, single digital device will cause the loss of multiple design functions, the digital modification has an adverse impact (for the aspect being illustrated in this example) on the design function of the SBCS and the design function of the main turbine steam inlet valves control system.

4.2.1.2 Screening of Changes to Procedures as Described in the UFSAR SCOPE If the digital modification does not include or affect an HSI element (e.g., the replacement of a stand-alone analog relay with a digital relay that has no features involving personnel interaction and does not feed signals into any other analog or digital device), then this section does not apply and may be excluded from the Screen assessment.

In NEI 96-07, Section 3.11 defines procedures as follows:

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"...Procedures include UFSAR descriptions of how actions related to system operation are to be performed and controls over the performance of design functions. This includes UFSAR descriptions of operator action sequencing or response times, certain descriptions...of SSC operation and operating modes, operational...controls, and similar information."

Although UFSARs do not typically describe the details of a specific HSI, UFSARs may describe any design functions associated with the HSI.

Because the HSI involves system/component operation, this portion of a digital modification is assessed in this Screen consideration. The focus of the Screen assessment is on potential adverse effects due to modifications of the interface between the human user and the technical device.

Note that the "human user" could involve Control Room Operators, other plant operators, maintenance personnel, engineering personnel, technicians, etc.

HUMAN FACTORS ENGINEERING (HFE) EVALUATION There are three "basic HSI elements" of an HSI (

Reference:

NUREG-0700):

  • Displays: the visual representation of the information personnel need to monitor and control the plant.
  • Controls: the devices through which personnel interact with the HSI and the plant.
  • User-interface interaction and management: the means by which personnel provide inputs to an interface, receive information from it, and manage the tasks associated with access and control of information.

Any user of the HSI must be able to accurately perceive, comprehend and respond to system information via the HSI to successfully complete their tasks. Specifically, nuclear power plant personnel perform "four generic primary tasks" (

Reference:

NUREG/CR-6947):

1. Monitoring and detection (extracting information from the environment and recognizing when something changes),
2. Situation assessment (evaluation of conditions),
3. Response planning (deciding upon actions to resolve the situation), and
4. Response implementation (performing an action).

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Table 1 contains examples of modifications to each of the three basic HSI elements applicable to this Screen consideration.

Table 1 - Example Human-System Interface Modifications Typical HSI Element Description/Example Modification Increase/decrease in the amount of information displayed by and/or available from the HSI (e.g., combining multiple parameters into a single integrated Number of Parameters parameter, adding additional information regarding component/system performance)

Change to the type of information displayed and/or available from the HSI Displays Type of Parameters (e.g., removing information that was previously available or adding information that was previously unavailable)

Change to visual representation of information (e.g. increment of presentation Information Presentation modified)

Change to structural arrangement of data/information (e.g., information now Information Organization organized by channel/train rather than by flow-path)

Change to the type/functionality of input device (e.g., replacement of a push Control Input button with a touch screen)

Controls Change to the information sent back to the individual in response to an action Control Feedback (e.g., changing feedback from tactile to auditory)

Change in number and/or type of decisions made and/or actions taken (e.g.,

replacing an analog controller that can be manipulated in one step with a Action Sequences digital controller that must be called-up on the interface and then User-Interface manipulated)

Interaction and Changes that affect how an individual retrieves information/data (e.g.,

Information/Data Management information that was continuously displayed via an analog meter now requires Acquisition interface interaction to retrieve data from a multi-purpose display panel)

Changes from manual to automatic initiation (or vice versa) of functions (e.g.,

Function Allocation manual pump actuation to automatic pump actuation)

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To determine potential adverse impacts of HSI modifications on design functions, a two-step HFE evaluation must be performed, as follows:

  • Step One - Identify the generic primary tasks that are involved with (i.e., potentially impacted by) the proposed activity.
  • Step Two - For all primary tasks involved, assess if the modification negatively impacts an individual's ability to perform the generic primary task.

Examples of impacts on an individual's performance that result in adverse effects on a design function include, but are not limited to:

increased possibility of mis-operation, increased difficulty in evaluating conditions, increased difficulty in performing an action, increased time to respond, and creation of new potential failure modes.

GUIDANCE After the two-step HFE evaluation, the next step is application of the standard Screen process.

Simple Human-System Interface Example Example 4-7 illustrates how a digital modification with HSI considerations would be addressed.

Example 4-7: Assessment of Modification with NO ADVERSE IMPACT on a UFSAR-Described Design Function Proposed Activity Description Currently, a knob is rotated clock-wise to open a flow control valve in 1%

increments and counter clock-wise to close a flow control valve in 1%

increments. This knob will be replaced with a touch screen that has two separate arrows, each in its own function block. Using the touch screen, touching the "up" arrow will open the flow control valve in 1% increments and touching the "down" arrow will close the flow control valve in 1%

increments.

HFE Evaluation STEP 1. Identification of the Generic Primary Tasks Involved:

(1) Monitoring and detection (extracting information from the environment and recognizing when something changes) - NOT D-19

INVOLVED (2) Situation assessment (evaluation of conditions) - NOT INVOLVED (3) Response planning (deciding upon actions to resolve the situation) -

NOT INVOLVED (4) Response implementation (performing an action) - INVOLVED STEP 2. Assessment of Modification Impacts on the Involved Generic Primary Tasks:

Tasks 1, 2 and 3 were not involved, so these tasks are not impacted by the modification.

Task 4 is involved. The HFE evaluation determined that the change from knob to touch screen would not impact the operators ability to perform the response implementation task.

Identification and Assessment of Design Functions Design Function Identification The UFSAR states the operator can "open and close the flow control valve using manual controls located in the Main Control Room." Thus, the design function is the ability of the operator to manually adjust the position of the flow control valve and the UFSAR description implicitly identifies the SSC (i.e., the knob).

Screen Response Using the results from the engineering/technical information supporting the change, including the HFE evaluation, and examining the replacement of the "knob" with a "touch screen," the modification is not adverse (for the aspect being illustrated in this example) because it does not impact the ability of the operator to "open and close the flow control valve using manual controls located in the Main Control Room," maintaining satisfaction of how the UFSAR-described design function is performed or controlled.

Comprehensive Human-System Interface Examples Examples 4-8a and 4-8b illustrate how a digital modification with HSI considerations would be addressed.

Although both examples use the same basic digital modification, Example 4-8a illustrates a no adverse impact case and Example 4-8b illustrates an adverse impact case by complicating the HSI portion of the modification and modifying the applicable licensing basis.

Example 4-8a. Digital Modification Involving HSI Considerations D-20

with NO ADVERSE IMPACT on a Design Function Proposed Activity Description Analog components and controls for a redundant safety-related system are to be replaced with digital components and controls, including new digital-based HSI.

Currently, two redundant channels/trains of information and controls are provided to the operators in the Main Control Room for the redundant systems. For each channel/train, several different analog instruments present information regarding the performance of the system. The analog displays are arranged by system "flow path" to facilitate the operator's ability to monitor the system as a whole.

The existing HSI for these components is made up of redundant hard-wired switches, indicator lights and analog meters. The new HSI consolidates the information and controls onto two flat panel displays (one per train) with touch screen soft controls. The information available on the flat panels is equivalent to that provided on the current analog HSI. Each flat panel display contains only one screen that displays the information and the controls for only that train, replicating the information and controls arrangement as they are in the existing HSI.

The existing HSI requires operators to manipulate analog switches to implement a control action. To take a control action using the new HSI, the operator must (via the touch screen) select the appropriate activity (e.g.,

starting/initiating the system or changing the system line-up), select the component to be controlled (e.g., pump or valve), select the control action (e.g., start/stop or open/close) and execute the action.

HFE Evaluation Step 1. Identification of Which Four Generic Primary Tasks are Involved:

(1) Monitoring and detection (extracting information from the environment and recognizing when something changes) - INVOLVED (2) Situation assessment (evaluation of conditions) - NOT INVOLVED (3) Response planning (deciding upon actions to resolve the situation) -

NOT INVOLVED (4) Response implementation (performing an action) - INVOLVED Step 2. Assessment of the Modification Impacts on the Involved Generic Primary Tasks:

Task 1 is involved. Any change to information presentation has the potential D-21

to impact the operators ability to monitor and detect changes in plant parameters. Even though the modification will result in information being presented on flat panels, the information available and the organization of that information (i.e., by train) will be equivalent to the existing HSI. Due to this equivalence and additional favorable factors (e.g., appropriate sized flat panels, appropriate display brightness, clearly identified function buttons, etc.), as documented in the HFE evaluation, there is no impact on the operators ability to monitor and detect changes in plant parameters.

Tasks 2 and 3 were not involved, so these tasks are not impacted by the modification.

Task 4 is involved. The modification will require the operator to perform four actions in order to manipulate a control (i.e., 1. select the appropriate activity, 2. select the specific component to be controlled, 3. select the control action to be initiated, and 4. execute the action). Currently, the operator is able to manipulate a control in one action (e.g., turn a switch to on/off). The HFE evaluation determined that the modification impacts the operators ability to respond by requiring four actions instead of one action and the additional actions result in an increase in the operators time to respond.

Identification and Assessment of Design Functions Design Function Identification (a) Status indications are continuously available to the operator.

(b) The operator controls the system components manually.

In this case, the review of the UFSAR, including the assumptions described in the safety analyses, determined that there were no additional design functions related to how design function (b) was performed or controlled.

Namely, there were no design functions related to the number of steps necessary to perform the design function (i.e., complexity) or the duration in which the steps were to be performed (i.e., time response).

Screen Response Since the information available and the organization of that information using the new HSI is equivalent to the existing HSI, the design function for continuous availability of status indications is met and there is no adverse impact (for the aspect being illustrated in this example) on design function (a).

Using the touch screen, the operator is still able to perform design function (b) to manipulate the control for the systems components. Therefore, there is no adverse impact (for the aspect being illustrated in this example) on how design function (b) is performed or controlled.

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Example 4-8b. Digital Modification Involving HSI Considerations with an ADVERSE IMPACT on a Design Function Proposed Activity Description Analog components and controls for a redundant safety-related system are to be replaced with digital components and controls, including new digital-based HSI.

Currently, two redundant channels/trains of information and controls are provided to the operators in the Main Control Room for the redundant systems. For each channel/train, several different analog instruments present information regarding the performance of the system. The analog displays are arranged by system "flow path" to facilitate the operator's ability to monitor the system as a whole.

The existing HSI for these components is made up of redundant hard-wired switches, indicator lights and analog meters. The new HSI consolidates the information and controls onto two flat panel displays (one per train) with touch screen soft controls. The information available on the flat panels is equivalent to that provided on the current analog HSI. Each flat panel display contains only one screen, which can display the information for only one train and the controls for only that train, replicating the information and controls arrangement as they are in the existing HSI. Each flat panel display can be customized to display the parameters and/or the configuration (e.g. by train, by flow path or only portions of a train or flow path) preferred by the operators. In addition, the flat panel displays provide many other display options to the user (e.g., individual component status and component/system alarms).

The existing HSI requires operators to manipulate analog switches to implement a control action. To take a control action using the new HSI, the operator must (via the touch screen) select the appropriate activity (e.g.,

starting/initiating the system or changing the system line-up), select the component to be controlled (e.g., pump or valve), select the control action (e.g., start/stop or open/close), and execute the action.

HFE Evaluation Step 1. Identification of Which Four Generic Primary Tasks are Involved:

(1) Monitoring and detection (extracting information from the environment and recognizing when something changes) - INVOLVED (2) Situation assessment (evaluation of conditions) - INVOLVED (3) Response planning (deciding upon actions to resolve the situation) -

INVOLVED D-23

(4) Response implementation (performing an action) - INVOLVED Step 2. Assessment of the Modification Impacts on the Involved Generic Primary Tasks:

Tasks 1, 2 and 3 are involved (emphasizing that the modification includes a change to information presentation and organization, such that the indications/instruments are now consolidated and presented on customizable flat panel displays, rather than static analog control boards). With the new displays and display options available to the operators, the operators can choose which parameters to display and the organization of that information (e.g., by train/path). The HFE evaluation concluded that this modification could result in the operator choosing not to have certain parameters displayed; thus impacting their ability to monitor the plant and detect changes. In addition, altering the information displayed and the organization of the information will impact the operators understanding of how the information relates to system performance. This impact on understanding will also impact the operators ability to assess the situation and plan an appropriate response.

Task 4 is involved. The modification will require the operator to perform four actions in order to manipulate a control (i.e., 1. select the appropriate activity, 2. select the specific component to be controlled, 3. select the control action to be initiated, and 4. execute the action). Currently, the operator is able to manipulate a control in one action (e.g., turn a switch to on/off). The HFE evaluation determined that the modification impacts the operators ability to respond by requiring four actions instead of one action and the additional actions result in an increase in the operators time to respond.

Identification and Assessment of Design Functions Design Function Identification (a) Status indications are continuously available to the operator.

(b) The operator controls the system components manually.

The review of the UFSAR, including the assumptions described in the safety analysis, determined that an additional design function related to how design function (b) was performedexists . Namely, in the pertinent safety analysis, a response time requirement of the operator had been credited.

Screen Response The information available and the organization of that information in the new displays are customizable based on operator preference. Critical status indications may not be continuously available to the operator, thus there is D-24

an adverse impact (for the aspect being illustrated in this example) on design function (a).

Using the touch screen, the operator is still able to perform design function (b) to manipulate the control for the systems components. However, there is an adverse impact (for the aspect being illustrated in this example) on how design function (b) is performed due to the increased response time.

4.2.1.3 Screening Changes to UFSAR Methods of Evaluation By definition, a proposed activity involving a digital modification involves SSCs and how SSCs are operated and controlled, not a method of evaluation described in the UFSAR (see NEI 96-07, Section 3.10).

Methods of evaluation are analytical or numerical computer models used to determine and/or justify conclusions in the UFSAR (e.g., accident analyses that demonstrate the ability to safely shut down the reactor or prevent/limit radiological releases). These models also use "software." However, the software used in these models is separate and distinct from the software installed in the facility. The response to this Screen consideration should reflect this distinction.

A necessary revision or replacement of a method of evaluation (see NEI 96-07, Section 3.10) resulting from a digital modification is separate from the digital modification itself and the guidance in NEI 96-07, Section 4.2.1.3 applies.

4.2.2 Is the Activity a Test or Experiment Not Described in the UFSAR?

By definition, a proposed activity involving a digital modification involves SSCs and how SSCs are operated and controlled, not a test or experiment (see NEI 96-07, Section 4.2.2). The response to this Screen consideration should reflect this characterization.

A necessary test or experiment (see NEI 96-07, Section 3.14) involving a digital modification is separate from the digital modification itself and the guidance in NEI 96-07, Section 4.2.2 applies.

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4.3 EVALUATION CAUTION The guidance contained in this section of the appendix is intended to supplement the generic Evaluation guidance contained in the main body in NEI 96-07, Section 4.3. Namely, the generic Evaluation guidance provided in the main body of NEI 96-07 and the more-focused Evaluation guidance in this appendix BOTH apply to digital modifications.

4.3.1 Does the Activity Result in More Than a Minimal Increase in the Frequency of Occurrence of an Accident?

INTRODUCTION From NEI 96-07, Section 3.2:

"The term 'accidents' refers to the anticipated (or abnormal) operational transients and postulated design basis accidents..."

Therefore, for purposes of 10 CFR 50.59, both Anticipated Operational Occurrences (AOOs) and Postulated Accidents (PAs) fall within the definition of "accident."

After applying the generic guidance in NEI 96-07, Section 4.3.1 to identify any accidents affected by the systems/components involved with the digital modification, the change is examined to determine if the frequency of these accidents could increase due to the change. When addressing this Evaluation criterion for digital upgrades, the key issue is determining if the digital equipment can increase the frequency of initiating events that lead to the identified accidents.

All initiating events fall into one of two categories: equipment-related or personnel-related. Therefore, the assessment of the impact of a digital modification also needs to consider both equipment-related and personnel-related sources.

For a digital modification, the range of possible equipment-related sources of initiating events includes items unique to digital and items not unique to digital. An example of an item unique to digital is consideration of the impact on accident frequency due to a software CCF, which will be addressed in this guidance. An example of a potential source of common cause failure D-26

that is not unique to digital is consideration of the impact on accident frequency due to the digital system's compatibility with the environment in which the system is being installed, which would be addressed by applying the general guidance in NEI 96-07, Section 4.3.1.

Typically, numerical values quantifying an accident frequency are not available, so the qualitative approach using the guidance from NEI 96-07, Section 4.3.1 will be applied in this guidance.

The frequency of occurrence of an accident is directly related to the likelihood of failure of equipment that initiates the accident (e.g., an increase in the likelihood of a steam generator tube failure has a corresponding increase in the frequency of a steam generator tube rupture accident). Thus, an increase in the likelihood of failure of the modified equipment causes an increase in the frequency of the accident.

GUIDANCE Qualitative Assessment Outcome If the qualitative assessment outcome is sufficiently low, then there is NOT more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR.

If the qualitative assessment outcome is not sufficiently low, then there may be more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR.

Negligible To achieve a negligible conclusion, the change in the accident frequency "...is so small or the uncertainties in determining whether a change in frequency has occurred are such that it cannot be reasonably concluded that the frequency has actually changed (i.e., there is no clear trend toward increasing the frequency)"1 [emphasis added]

Discernable If a clear trend towards increasing the accident frequency exists, then a discernable increase in the accident frequency would exist. In this case, the software CCF likelihood would be not sufficiently low.

A qualitative assessment may also be used to determine if the discernible increase in the accident frequency is "more than minimal" or "NOT more than minimal." To achieve a conclusion of "NOT more than minimal" based on an 1 Refer to NEI 96-07, Section 4.3.1, Example 1.

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examination of the factors considered in a qualitative assessment, the proposed activity must also continue to meet and/or satisfy all applicable NRC requirements, as well as design, material, and construction standards, to which the licensee is committed. Applicable requirements and standards include those selected by the licensee for use in the development of the proposed digital modification and documented within the design modification package.

EXAMPLES Example 4-9 illustrates a case with not more than a minimal increase in the accident frequency.

Example 4-9. NOT MORE THAN A MINIMAL Increase in the Frequency of Occurrence of an Accident Proposed Activity Description Two non-safety-related main feedwater pumps (MFWPs) exist, each with its own flow control valve. There are two analog control systems (one per MFWP and flow control valve combination) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Qualitative Assessment Outcome A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSC is sufficiently low. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

Conclusion With the failure likelihood introduced by the modified SSC being sufficiently low, there is not more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR (for the aspect being illustrated in this example)

Example 4-10 illustrates a case with more than a minimal increase in the accident frequency.

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Example 4-10. MORE THAN A MINIMAL Increase in the Frequency of Occurrence of an Accident Proposed Activity Description Same as Example 4-9.

Qualitative Assessment Outcome A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSC is not sufficiently low.

For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

Conclusion As documented in the qualitative assessment, the features of the design process and operating experience were insufficient to offset weaknesses in the design attributes that were available to prevent certain failures. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

With the failure likelihood introduced by the modified SSC being not sufficiently low and the inability to offset weaknesses in the design attributes, there is more than a minimal increase in the frequency of occurrence of the accident previously evaluated in the UFSAR (for the aspect being illustrated in this example) .

4.3.2 Does the Activity Result in More Than a Minimal Increase in the Likelihood of Occurrence of a Malfunction of an SSC Important to Safety?

INTRODUCTION After applying the generic guidance in NEI 96-07, Section 4.3.2 to identify any malfunctions affected by the systems/components involved with the digital modification, the change is examined to determine if the likelihood of these malfunctions could increase due to the change. When addressing this Evaluation criterion for digital upgrades, the key issue is determining if the digital equipment can increase the likelihood of initiating events that lead to the identified malfunctions.

All initiating events fall into one of two categories: equipment-related or personnel-related. Therefore, the assessment of the impact of a digital D-29

modification also needs to consider both equipment-related and personnel-related sources.

For a digital modification, the range of possible equipment-related sources of initiating events includes items unique to digital and items not unique to digital. An example of an item unique to digital is consideration of the impact on malfunction likelihood due to a software CCF, which will be addressed in this guidance. An example of a potential source of common cause failure that is not unique to digital is consideration of the impact on malfunction likelihood due to the digital system's compatibility with the environment in which the system is being installed, which would be addressed by applying the general guidance in NEI 96-07, Section 4.3.2.

Typically, numerical values quantifying a malfunction likelihood are not available, so the qualitative approach using the guidancefrom NEI 96-07, Section 4.3.2 will be applied in this guidance.

The likelihood of occurrence of a malfunction of an SSC important to safety is directly related to the likelihood of failure of equipment that causes a failure of SSCs to perform their intended design functions [e.g., an increase in the likelihood of failure of an auxiliary feedwater (AFW) pump has a corresponding increase in the likelihood of occurrence of a malfunction of SSCs (i.e., the AFW pump and the AFW system)]. Thus, an increase in the likelihood of failure of the modified equipment that causes the failure of an SSC to perform its intended design functions is directly related to the likelihood of the occurrence of a malfunction of an SSC important to safety.

GUIDANCE As discussed in NEI 96-07, Section 4.3.2, Example 6, a proposed activity that reduces redundancy, diversity, separation or independence of the design function(s) is considered more than a minimal increase in the likelihood of a malfunction and requires prior NRC approval. However, licensees may reduce excess redundancy, diversity, separation or independence of design function(s) (if any) to the level credited in the safety analyses without prior NRC approval.

The possibility exists that a proposed activity can cause a previously incredible event to become credible.

Example 4-11 illustrates a case in which a previously incredible event has become credible due to a digital modification.Example 4-11. Impact on the Likelihood of Occurrence of a Malfunction Proposed Activity Description D-30

Two safety-related containment chillers exist. There are two analog control systems (one per chiller) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Affected Malfunctions and Malfunction Initiators The affected malfunction is the failure of a safety-related containment chiller to provide its cooling design function. The UFSAR identifies three specific equipment-related initiators of a containment chiller malfunction: (1) failure of the Emergency Diesel Generator (EDG) to start (preventing the EDG from supplying electrical power to the containment chiller it powers), (2) an electrical failure associated with the chiller system (e.g., feeder breaker failure), and (3) a mechanical failure within the chiller itself (e.g., flow blockage). The UFSAR also states that the single failure criteria were satisfied because two chillers were provided and there were no common malfunction sources.

Impact on Malfunction Likelihood Although the safety-related chiller control system is not one of the three malfunction initiators identified in the UFSAR, a new common malfunction source has been introduced due to the potential for a software common cause failure from the exact same software being used in both digital control systems. A common malfunction initiator was previously considered, but was concluded to be non-existent. However, this conclusion is no longer valid.

Therefore, an impact on the likelihood of occurrence of the malfunction due to the digital modification has occurred. (NOTE: The magnitude of the impact would then need to be assessed.)

Qualitative Assessment Outcome If the qualitative assessment outcome is sufficiently low, then there is NOT more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR.

If the qualitative assessment outcome is not sufficiently low, then there may be more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR.

Negligible To achieve a negligible conclusion, the change in the malfunction likelihood

"...is so small or the uncertainties in determining whether a change in D-31

likelihood has occurred are such that it cannot be reasonably concluded that the likelihood has actually changed (i.e., there is no clear trend toward increasing the likelihood)"2 [emphasis added] and the qualitative assessment outcome for a software CCF will be sufficiently low.

Discernable If a clear trend towards increasing the malfunction likelihood exists, then a discernable increase in the malfunction likelihood would exist. In this case, the software CCF likelihood would be not sufficiently low.

A qualitative assessment) may also be used to determine if the discernible increase in the malfunction likelihood is "more than minimal" or "NOT more than minimal." To achieve a conclusion of "NOT more than minimal" based on an examination of the factors considered in a qualitative assessment, the proposed activity must also continue to meet and/or satisfy all applicable NRC requirements, as well as design, material, and construction standards, to which the licensee is committed. Applicable requirements and standards include those selected by the licensee for use in the development of the proposed digital I&C design modification and documented within the design modification package.

EXAMPLES Example 4-12 illustrates a case with not more than a minimal increase in the malfunction likelihood.

Example 4-12. NOT MORE THAN A MINIMAL Increase in the Likelihood of Occurrence of a Malfunction Proposed Activity Description Two non-safety-related main feedwater pumps (MFWPs) exist, each with its own flow control valve. There are two analog control systems (one per MFWP and flow control valve combination) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Qualitative Assessment Outcome A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered 2 Refer to NEI 96-07, Section 4.3.2, 4th paragraph.

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system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSC is sufficiently low. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

All applicable requirements and other acceptance criteria to which the licensee is committed, as well as applicable design, material and construction standards, continue to be met.

Conclusion With the failure likelihood introduced by the modified SSC being sufficiently low, there is not more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR (for the aspect being illustrated in this example).

Example 4-13 illustrates a case with more than a minimal increase in the malfunction likelihood.

Example 4-13. MORE THAN A MINIMAL Increase in the Likelihood of Occurrence of a Malfunction Proposed Activity Description Two safety-related main control room chillers exist. There are two analog control systems (one per chiller) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

The logic components/system and controls for the starting and operation of the safety injection pumps are located within the main control room boundary. The environmental requirements associated with the logic components/system and controls are maintained within their allowable limits by the main control room cooling system, which includes the chillers involved with this digital modification.

Affected Malfunction The review of the UFSAR accident analyses identified several events for which the safety injection pumps are assumed to start and operate (as reflected in the inputs and assumptions for the accident analyses).

In each of these events, the UFSAR states the following: "To satisfy single D-33

failure requirements, the loss of only one chiller control system and its worst-case effect on the event due to the loss of one chiller has been considered in the accident analysis."

Qualitative Assessment Outcome A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSC is not sufficiently low.

For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

An increase in the likelihood of occurrence of the malfunction of both safety injection pumps occurs since the single failure criteria are no longer met.

Conclusion Withthe failure to satisfy single failure criteria, there is more than a minimal increase in the likelihood of occurrence of the malfunction of the safety injection pumps due to the digital modification. As documented in the qualitative assessment, the features of the design process and operating experience were insufficient to offset weaknesses in the design attributes that were available to prevent certain failures. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

With the failure likelihood introduced by the modified SSC being not sufficiently low and the inability to offset weaknesses in the design attributes, there is more than a minimal increase in the likelihood of occurrence of a malfunction previously evaluated in the UFSAR (for the aspect being illustrated in this example).

4.3.3 Does the Activity Result in More Than a Minimal Increase in the Consequences of an Accident?

There is no unique guidance applicable to digital modifications for responding to this Evaluation criterion because the identification of affected accidents and dose analysis inputs and/or assumptions are not unique for a digital modification. The guidance in NEI 96-07, Section 4.3.3 applies.

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4.3.4 Does the Activity Result in More Than a Minimal Increase in the Consequences of a Malfunction?

There is no unique guidance applicable to digital modifications for responding to this Evaluation criterion because the identification of the affected malfunctions and dose analysis inputs and/or assumptions are not unique for a digital modification. The guidance in NEI 96-07, Section 4.3.4 applies.

4.3.5 Does the Activity Create a Possibility for an Accident of a Different Type?

INTRODUCTION From NEI 96-07, Section 3.2:

"The term 'accidents' refers to the anticipated (or abnormal) operational transients and postulated design basis accidents..."

Therefore, for purposes of 10 CFR 50.59, both Anticipated Operational Occurrences (AOOs) and Postulated Accidents (PAs) fall within the definition of "accident."

Accidents of a different type are caused by failures of equipment that initiate an accident of a different type.

GUIDANCE From NEI 96-07, Section 4.3.5, the two considerations that need to be assessed when answering this Evaluation question are as likely to happen as and the the manner in which the safety analysis will account for the effects of the failure (which is discussed in more detail below). For brevity, the second consideration will hereafter be referred to as the "safety analysis manner of accounting."

Determination of "As Likely To Happen As" From NEI 96-07, Section 4.3.5:

"The possible accidents of a different type are limited to those that are as likely to happen as those previously evaluated in the UFSAR. The accident must be credible in the sense of having been created within the range of assumptions previously considered in the licensing basis (e.g.,

random single failure, loss of off-site power, etc.)."

If the outcome of the qualitative assessment is sufficiently low, then the activity does not introduce any failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different type. Therefore, the D-35

activity does not create a possibility for an accident of a different type than any previously evaluated in the UFSAR.

If the outcome of the qualitative assessment is not sufficiently low, then the activity may introduce failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different type. For these cases, this Evaluation criterion also needs to consider the safety analysis manner of accocunting.

Determination of Safety Analysis Manner of Accounting For cases in which the outcome of the qualitative assessment is not sufficiently low), the safety analysis manner of accounting needs to be assessed to determine if the accident is a different type.

There are two possible manners of accounting in a safety analysis:

(1) a revision to an existing safety analysis is possible, or (2) a new safety analysis will be required because the effect on the plant is different than any previously evaluated in the UFSAR.

Accidents of a different type are accidents for which a new safety analysis would be needed, not just a revision of a current safety analysis.

EXAMPLES Example 4-14 illustrates the NO CREATION of the possibility of an accident of a different type case.

Example 4-14. NO CREATION of the Possibility of an Accident of a Different Type Proposed Activity Two non-safety-related main feedwater pumps (MFWPs) exist, each with its own flow control valve. There are two analog control systems (one per MFWP and flow control valve combination) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Qualitative Assessment Outcome A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the D-36

failure likelihood introduced by the modified SSC is sufficiently low. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

Conclusion With the failure likelihood introduced by the modified SSC being sufficiently low, the activity does not introduce any failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different type. Therefore, the activity does not create a possibility for an accident of a different type than any previously evaluated in the UFSAR (for the aspect being illustrated in this example).

Example 4-15 illustrates the CREATION of the possibility of an accident of a different type case.

Example 4-15. CREATION of the Possibility of an Accident of a Different Type Proposed Activity Two non-safety-related analog feedwater control systems and one non-safety-related main turbine steam-inlet valves analog control system exist.

The two feedwater control systems and the one main turbine steam-inlet valves control system will be combined into a single digital control system.

Qualitative Assessment Outcome A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSC is not sufficiently low.

For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

Malfunction / Accident Identification The UFSAR describes the following feedwater control system malfunctions:

(a) failures causing the loss of all feedwater to the steam generators, which is evaluated in the Loss of Feedwater event, and (b) failures causing an increase in main feedwater flow to the maximum output from both MFWPs, which is evaluated in the Excess Feedwater event.

The UFSAR describes the following main turbine steam-inlet valve control system malfunctions: (a) all valves going fully closed causing no steam to be admitted into the turbine, which is evaluated in the Loss of Load event, and (b) all valves going fully open causing excess steam to be admitted into the D-37

turbine, which is evaluated in the Excess Steam Demand event.

Therefore, the impact of the failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different type will be assessed for the following accident analyses:

(1) Loss of Feedwater (2) Excess Feedwater (3) Loss of Load (4) Excess Steam Demand Safety Analysis Manner of Accounting Assessment The following events and combination of events will be assessed:

(A) Loss of both feedwater pumps in the Loss of Feedwater accident analysis (B) Increase in main feedwater flow to the maximum output from both MFWPs in the Excess Feedwater accident analysis (C) All main turbine steam-inlet valves going fully closed in the Loss of Load accident analysis (D) All main turbine steam-inlet valves going fully open in the Excess Steam Demand accident analysis (E) Combination of a Loss of Feedwater event and a Loss of Load event (F) Combination of a Loss of Feedwater event and an Excess Steam Demand event (G) Combination of an Excess Feedwater event and a Loss of Load event (H) Combination of an Excess Feedwater event and an Excess Steam Demand event Events (A) though (D) are already considered in the accident analyses, so revisions to existing accident analyses are possible. Thus, events (A) through (D) do NOT create the possibility of an accident of a different type (for the aspect being illustrated in this example).

The current set of accidents identified in the accident analyses do not consider the simultaneous events represented by events (E) through (H).

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Therefore, events (E) though (H) will require new accident analyses to be performed and create the possibility of accidents of a different type (for the aspect being illustrated in this example).

4.3.6 Does the Activity Create a Possibility for a Malfunction of an SSC Important to Safety with a Different Result?

INTRODUCTION NOTE: Due to the unique nature of digital modifications and the inherent complexities therein, the application of this criterion is especially important. Specifically, the unique aspect of concern is the potential for a software CCF to create the possibility for a malfunction with a different result. Therefore, rather than providing simplistic supplemental guidance to that already included in NEI 96-07, Section 4.3.6, more detailed guidance will be provided in this section.

Review To ensure the unique aspects of digital modifications are addressed correctly and adequately, a review of selected discussions and excerpts from NEI 96-07, including malfunctions, design functions, and safety analyses, is presented first.

CAUTION: The following review summaries are intended for general understanding only. For complete discussions of each term, see the references identified for each term.

From NEI 96-07, Section 3.9:

Malfunction of SSCs important to safety means the failure of SSCs to perform their intended design functions described in the UFSAR (whether or not classified as safety-related in accordance with 10 CFR 50, Appendix B). [emphasis added]

From NEI 96-07, Section 3.3:

Design functions are UFSAR-described design bases functions and other SSC functions described in the UFSAR that support or impact design bases functions... [emphasis added]

Also, Design bases functions are functions performed by systems, structures and components (SSCs) that are (1) required by, or otherwise necessary to comply with, regulations, license conditions, orders or technical D-39

specifications, or (2) credited in licensee safety analyses to meet NRC requirements. [emphasis added]

Furthermore, Design functions...include functions that, if not performed, would initiate a transient or accident that the plant is required to withstand. [emphasis added]

Finally, As used above, credited in the safety analyses means that, if the SSC were not to perform its design bases function in the manner described, the assumed initial conditions, mitigative actions or other information in the analyses would no longer be within the range evaluated (i.e., the analysis results would be called into question). The phrase support or impact design bases functions refers both to those SSCs needed to support design bases functions (cooling, power, environmental control, etc.) and to SSCs whose operation or malfunction could adversely affect the performance of design bases functions (for instance, control systems and physical arrangements).

Thus, both safety-related and nonsafety-related SSCs may perform design functions. [emphasis added]

This definition is oriented around the definition of design bases function, which itself is defined in NEI 97-04, Appendix B, Guidelines and Examples for Identifying 10 CFR 50.2 Design Bases, endorsed by Regulatory Guide 1.186, and highlighted in bold above.

A more complete understanding of the meaning of a design basis function can be obtained by examination of NEI 97-04, Appendix B. From NEI 97-04, the three characteristics of design bases functions are summarized as follows:

1. Design bases functions are credited in the safety analyses.
2. The functions of any individual SSC are functionally below that of a design basis function.
3. Design bases functions are derived primarily from the General Design Criteria.

Repeating a portion from above to highlight the importance of identifying the design basis function and its connection to a safety analysis result, we have the following:

As used above, credited in the safety analyses means that, if the SSC were not to perform its design bases function in the manner described, the assumed initial conditions, mitigative actions or other information in the analyses would no longer be D-40

within the range evaluated (i.e., the analysis results would be called into question). [emphasis added]

Then, from NEI 96-07, Section 3.12:

Safety analyses are analyses performed pursuant to NRC requirements to demonstrate the integrity of the reactor coolant pressure boundary, the capability to shut down the reactor and maintain it in a safe shutdown condition, or the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guidelines in 10 CFR 50.34(a)(1) or 10 CFR 100.11...and include, but are not limited to, the accident analyses typically presented in Chapter 15 of the UFSAR. [emphasis added]

And from the first sentence of the associated discussion:

Safety analyses are those analyses or evaluations that demonstrate that acceptance criteria for the facilitys capability to withstand or respond to postulated events are met.

[emphasis added]

Also included in the definition of safety analyses are supporting UFSAR analyses that demonstrate that SSC design functions will be accomplished as credited in the accident analyses.

Failure Modes and Effects Analysis (FMEA)

NEI 96-07, Section 4.3.6 recognizes that the effect of a proposed modification must be assessed. This assessment may require the use of a failure modes and effects analysis (FMEA), including the possible creation of a new FMEA.

From NEI 96-07, Section 4.3.6:

In evaluating a proposed activity against this criterion, the types and results of failure modes of SSCs that have previously been evaluated in the UFSAR and that are affected by the proposed activity should be identified. This evaluation should be performed consistent with any failure modes and effects analysis (FMEA) described in the UFSAR, recognizing that certain proposed activities may require a new FMEA to be performed. [emphasis added]

Overall Perspective NEI 96-07, Section 4.3.6 provides the overall perspective on this Evaluation criterion with its first sentence, which states:

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Malfunctions of SSCs are generally postulated as potential single failures to evaluate plant performance with the focus being on the result of the malfunction rather than the cause or type of malfunction.

Expanding upon this foundation, the following conclusion is reached, which is based upon discussion from 63 FR 56106:

Unless the equipment would fail in a way not already evaluated in the safety analysis, there can be no malfunction of an SSC important to safety with a different result. [emphasis added]

GUIDANCE From NEI 96-07, Section 4.3.6, the two considerations that need to be assessed when answering this Evaluation question are as likely to happen as and the impact on the safety analysis result.

Determination of "As Likely to Happen As" From NEI 96-07, Section 4.3.6:

The possible malfunctions with a different result are limited to those that are as likely to happen as those described in the UFSARa proposed change or activity that increases the likelihood of a malfunction previously thought to be incredible to the point where it becomes as likely as the malfunctions assumed in the UFSAR could create a possible malfunction with a different result. [emphasis added]

If the outcome of the qualitative assessment is sufficiently low, then the activity does not introduce any failures that are as likely to happen as those in the UFSAR. Therefore, the activity does not create a possibility for a malfunction of an SSC important to safety with a different result from any previously evaluated in the UFSAR.

If the outcome of the qualitative assessment is not sufficiently low, then the activity may introduce failures that are as likely to happen as those in the UFSAR that can create a possibility for a malfunction of an SSC important to safety with a different result from any previously evaluated in the UFSAR.

For these cases, this Evaluation criterion also needs to consider the impact of this potential failure on the safety analysis result using assumptions consistent with the plants UFSAR.

EXAMPLE Example 4-16 illustrates the NO CREATION of the possibility for a malfunction with a different result case.

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Example 4-16. NO CREATION of the Possibility for a Malfunction with a Different Result Proposed Activity A large number of analog transmitters in several different systems and uses are being replaced with digital transmitters. These transmitters perform a variety of functions, including controlling the automatic actuation of devices (e.g., valve stroking) that are credited in a safety analysis.

Qualitative Assessment Outcome A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSCs is sufficiently low. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

Conclusion With the failure likelihood introduced by the modified SSCs being sufficiently low, the activity does not introduce any failures that are as likely to happen as those in the UFSAR that can initiate a malfunction of an SSC important to safety. Therefore, the activity does not create a possibility for a malfunction of an SSC important to safety with a different result from any previously evaluated in the UFSAR (for the aspect being illustrated in this example).

Determination of Safety Analysis Result Impact For cases in which the qualitative assessment outcome is a failure likelihood of not sufficiently low, the safety analysis result impact needs to be assessed to determine if the result is different.

The generic process to determine the impact of a malfunction of an SSC important to safety on the safety analyses (i.e., a comparison of the safety analyses results to identify any different results), consists of multiple steps, as summarized next.

Step 1: Identify the functions directly or indirectly related to the proposed modification.

Considering the scope of the proposed digital modification, identify the functions that are directly or indirectly related to the proposed activity.

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The functions identified as part of this step will be further classified in Step 2.

As a reminder of the guidance provided in NEI 96-07, the following additional guidance is provided to assist in the identification and consideration of the proper scope of SSCs and their functions:

(1) Identification and consideration of the proper scope of SSCs is concerned with the functional involvement of an SSC, not necessarily only its level of direct description in the UFSAR.

(2) In cases in which a proposed activity involves a sub-component/component that is not directly described in the UFSAR, the effect of the proposed activity involving the sub-component/component needs to consider the impact on the system in which the sub-component/component is a part.

(3) In cases in which a proposed activity involves a sub-component/component that is not described in the UFSAR, the effect of the proposed activity involving the sub-component/component needs to consider the impact on the system that the subcomponent/component supports.

Regardless of the level of description, the assessment of the impact also needs to consider the elements of a design function as described in NEI 96-07, Section 3.3, which are repeated below:

  • Implicitly included within the meaning of design function are the conditions under which intended functions are required to be performed, such as equipment response times, process conditions, equipment qualification and single failure.
  • Design functions may be performed by safety-related SSCs or nonsafety-related SSCs and include functions that, if not performed, would initiate a transient or accident that the plant is required to withstand.

Step 2: Identify which of the functions from Step 1 are Design Functions and/or Design Bases Functions.

Utilizing NEI 96-07, Section 3.3, classify each of the functions from Step 1 as either NOT a design function or as a design function.

If no design functions are identified, then the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result because malfunctions (and the results thereof) refers ONLY to the failure of an SSC to perform its intended design functions.

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For each design function identified above, utilize NEI 96-07, Section 3.3 (along with Appendix B to NEI 97-04, as needed) to identify which design functions are design bases functions, which design functions support or impact design bases functions, and which design functions are not involved with design bases functions, but are functions that if not performed would initiate a transient or accident that the plant is required to withstand. If multiple design functions are identified, each design function is to be considered in this multi-step process.If no design basis functions are involved, proceed to Step 5 since neither the performance of design basis functions nor the support or impactof design basis functions are involved. (NOTE: The potential for more severe accident initiation is addressed in Step 5.)

The process for determining if a design function is a design basis function may be aided by identifying the associated General Design Criteria (GDC) to which a design bases function applies or, more specifically, the associated principal design criteria (PDC) for an individual facility, the minimum standards for which are set by 10 CFR Part 50 Appendix A (or perhaps their 1967 precursors). Each design function may then be related to the requirements discussed within the GDC to determine if that design function is directly involved with the design basis function itself or if the design function supports or impacts the related design basis function. If the design function is found to directly involve the GDC requirement, then that design function is a design basis function. If the design function supports or impacts the GDC requirement, then it is not a design basis function, but is still credited in the safety analysis.

As described in NEI 96-07, Section 4.3.2 (but equally applicable here),

safety analyses typically assume certain SSCs perform certain design functions as part of demonstrating the adequacy of the design. The process of determining if a design function is a design abses function should include both direct and indirect affects on the design functions.

However, safety analyses do not typically identify all of the SSCs that are relied upon to perform their design functions. Therefore, the review should not be limited to only the SSCs discussed in the safety analyses. For example, performing a design change on a valve controller in a high pressure safety injection system would be considered to involve an SSC credited in the safety analyses even though the valve itself may not be mentioned in the safety analyses.

Step 3: Determine if a new FMEA needs to be generated.

If the impact on the design basis function involved is readily apparent, no new FMEA needs to be generated. Go to Step 4.

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For example, there is no reason to contemplate the generation of a new FMEA if the impact of the failure on the design bases functions is recognized as being immediate. Otherwise, generate the new FMEA to describe the connection of the proposed activity, or failures due to the proposed activity, to an impact on the design bases functions.

As part of the process for generating the new FMEA, presume compliance with pre-existing/interdependent, modification-related procedures and utilization of existing equipment to determine if adequate SSC design and/or operational (i.e., procedural) options exist to mitigate potential detrimental impacts on design functions.

Interdependence is discussed in NEI 96-07, Sections 4.2 and 4.3 (which is distinct from compensatory actions discussed in NEI 96-07, Section 4.4). An example of an interdependent procedure change would be the modifications to an existing procedure to reflect operation of the new digital equipment and controls, including any new features such as a control system restart option. (NOTE: NEI 96-07, Section 4.3.2, Example 4 provides guidance on assessing new operator actions.)

Step 4: Determine if each design basis function continues to be performed/satisfied.

If all design basis functions continue to be performed/satisfied, and there are no other design functions involved, then the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result because no malfunction occurs. With no malfunction occurring, there cannot be a different result.

For any design basis function that does not continue to be performed/satisfied, or other design functions that are involved, continue to Step 5.

Step 5: Identify all safety analyses involved.

Identify all safety analyses that rely directly or indirectly on the design basis functions performance/satisfaction. Also, identify all safety analyses related to any other design function that could impact either the accidents initiation or the events initial conditions (i.e., design functions that, if not performed, would initiate a transient or accident that the plant is required to withstand).

If there are no safety analyses involved, then there cannot be a change in the result of a safety analysis. Therefore, in this case, the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result.

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Step 6: For each safety analysis involved, compare the projected/postulated results with the previously evaluated results.

NEI 96-07, Section 4.3.6 provides the following guidance regarding the identification of failure modes and effects:

Once the malfunctions previously evaluated in the UFSAR and the results of these malfunctions have been determined, then the types and results of failure modes that the proposed activity could create are identified.

If any of the identified safety analyses have become invalid due to their basic assumptions no longer being valid, e.g., single failure assumption is not maintained, or if the numerical result(s) of any safety analysis would no longer satisfy the acceptance criteria, i.e., the safety analysis is no longer bounded, then the proposed activity DOES create the possibility for a malfunction of an SSC important to safety with a different result.

As part of the response and determining if the safety analyses continue to be bounded, include the impact on the severity of the initiating conditions and the impact on the initial conditions assumed in the safety analysis. Specifically, consider any design functions that, if not performed, would initiate a transient or accident that the plant is required to withstand.

EXAMPLES Examples 4-17 through 4-21 illustrate some cases of NO CREATION of a malfunction with a different result by applying the multi-step process outlined above.

Example 4-17. NO CREATION of a Malfunction with a Different Result Proposed Activity A feedwater control system is being upgraded from an analog system to a digital system.

Safety Analysis Result Impact Step 1:

The pertinent function of the feedwater control system is to establish and maintain steam generator water level within predetermined physical limits during normal operating conditions.

Step 2:

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The function of the feedwater control system is classified as a design function due to its ability to initiate a transient or accident that the plant is required to withstand. However, the design function is not a design basis function.

With no design basis functions involved, proceed to Step 5.

Step 3:

Not applicable Step 4:

Not applicable Step 5:

The pertinent safety analysis is the accident analysis for Loss of Feedwater. The feedwater control system has a direct impact on the accident analysis assumptions and modeling.

Step 6:

Previously, only one feedwater flow control valve (out of four) could fail closed due to a failure of the analog control system. In the proposed design, all four feedwater flow control valves could simultaneously fail closed due to a software CCF in the digital control system.

Although only one feedwater flow control valve could fail due to a failure of the analog control system, the Loss of Feedwater accident analysis assumed the closure of all four flow control valves. The severity of the initiating failure assumed in the Loss of Feedwater accident analysis (four valves affected) is unchanged since the analysis currently assumes a total loss of feedwater flow. The failure mode (valve closure) is determined to have no effect on this assumption. The mechanism by which feedwater flow is lost (loss of control signal) has no impact on the initial conditions of the event.

Conclusion Although the software CCF likelihood was determined to be not sufficiently low, the initiation severity assumed in the Loss of Feedwater accident analysis (four valves affected), the failure mode (valve closure) and the mechanism by which feedwater flow was lost (loss of control signal) remain bounded. Furthermore, the results of the safety analysis, including the type of event (increasing pressure) and all criteria that must be satisfied (maximum allowed peak RCS pressure and maximum allowed secondary pressure) remain bounded.

Thus, the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result (for the aspect being D-48

illustrated in this example).

NOTE: See Example 4-23 for a similar example that illustrates the case in which the current Loss of Feedwater accident analysis assumed the closure of only one flow control valve, causing the CREATION of a malfunction with a different result.

Example 4-18. NO CREATION of a Malfunction with a Different Result Proposed Activity A feedwater control system is being upgraded from an analog system to a digital system. Previously, only one of four feedwater flow control valves was assumed to fail open as part of the initiation of the Excess Feedwater event. Now, as a result of this change, all four feedwater flow control valves could simultaneously fail open following a software CCF.

Safety Analysis Result Impact Consideration Step 1:

The identified function is to establish and maintain steam generator water level within predetermined physical limits during normal operating conditions.

Step 2:

The function is classified as a design function due to its ability to initiate a transient or accident that the plant is required to withstand. However, the design function is not a design basis function. With no design basis functions involved, proceed to Step 5.

Step 3:

Not applicable Step 4:

Not applicable Step 5:

The pertinent safety analysis is the accident analysis for Excess Feedwater. The feedwater control system has a direct impact on the accident analysis assumptions and modeling.

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Step 6:

The severity of the initiating failure has increased due to four valves supplying flow as compared to one valve prior to the change.

The minimum acceptable departure from nucleate boiling ratio (DNBR), i.e., the safety analysis result, is 1.30. The current safety analysis result is a minimum DNBR value equal to 1.42. After using the increased value for the new feedwater flow (to represent the increase in feedwater flow caused by the opening of the four feedwater flow control valves) in a revision to the Excess Feedwater accident analysis, the new safety analysis result is a minimum DNBR value equal to 1.33.

Conclusion Although the software CCF likelihood was determined to be not sufficiently low and the severity of the initiating failure has increased, a comparison of the safety analysis results of the minimum DNBR values shows that the new minimum DNBR value remains bounded. Therefore, the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result.

Example 4-19. NO CREATION of a Malfunction with a Different Result Proposed Activity A complete upgrade of the area radiation monitors that monitor a variety of containment compartments subject to a radioactive release during a LOCA is proposed. The outdated analog-based radiation monitors are being replaced by digital-based monitors. The hardware platform for each area radiation monitor is from the same supplier and the software in each area radiation monitor is exactly the same.

Safety Analysis Result Impact Step 1:

The pertinent function of each radiation monitor is to monitor the various compartments, rooms and areas that may be subject to an increase in radiation during the recirculation phase of a LOCA.

Step 2:

In this case, whether the function is a design bases function is not readily apparent, so the associated GDC will be identified and examined.

Criterion 64 -- Monitoring radioactivity releases. Means shall be provided for monitoring the reactor containment atmosphere, spaces D-50

containing components for recirculation of loss-of-coolant accident fluids, effluent discharge paths, and the plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrences, and from postulated accidents.

[emphasis added]

The area radiation monitors perform a function that is necessary to comply with a requirement specified in GDC 64. Therefore, the function of the radiation monitoris a design function directly involved with a design basis function.

Step 3:

No new FMEA needs to be generated. The effect of a postulated software CCF on the design basis function is readily apparent.

Step 4:

If a software CCF occurs, the area radiation monitors will not perform their design function that supports or impacts a design basis function.

Thus, the design basis function will not be performed/satisfied.

Step 5:

There are no safety analyses that directly or indirectly credit this design basis function. Namely, there are no considerations of malfunctions of single or multiple radiation monitors, or expected responses of the radiation monitors, in any safety analysis.

Step 6:

Not applicable Conclusion Although the software CCF likelihood was determined to be not sufficiently low, there are no safety analyses that directly or indirectly credit the design basis function or contain expected responses of the radiation monitors. Thus, there cannot be a different result when comparing to a pre-existing safety analysis since none exists.

Therefore, the proposed activity does NOT create the possibility of a malfunction of an SSC important to safety with a different result.

NOTE: The acceptability of these new area radiation monitors will be dictated by their reliability, which is assessed as part of Criterion (ii),

not Criterion (vi).

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Example 4-20. NO CREATION of a Malfunction with a Different Result Proposed Activity Two chillers that cool the Main Control Room Ventilation System (MCRVS) are being upgraded. The MCRVS provides cooling to the Main Control Room and the adjacent Relay Room. The Relay Room contains multiple instrument racks that control both the Reactor Protection System (RPS) and Engineering Safety Features Actuation System (ESFAS) signals.

As part of the upgrade, each of the chiller's analog control systems will be replaced with a digital control system. Each digital control system maintains all of the operational features (e.g., auto/manual start/stop, setpoints and alarms) as the analog control systems. The hardware platform for each chiller control system is from the same supplier and the software in each chiller control system is exactly the same.

Safety Analysis Result Impact Step 1:

The pertinent functions of the MCRVS involve the air flow path from the Main Control Room to the Relay Room (which is described in the UFSAR) and a function to maintain the Relay Rooms temperature less than or equal to 120 ºF.

Step 2:

The function involving the "air flow path" is not affected and can be eliminated from consideration since the Screen phase determined that there was no adverse impact.

In this case, whether the "maintain temperature" function is a design bases function is not readily apparent, so the associated GDC will be identified and examined.

Criterion 20 -- Protection system functions. The protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety. [emphasis added]

The chiller control system performs a function that supports or impacts the design basis function specified in GDC 20. Therefore, the function of the D-52

chiller control system is a design basis function credited in the safety analysis.

Step 3:

The impact of a software CCF on the design bases function credited in the safety analysis is not readily apparent, so a new FMEA was generated.

Step 4:

The new FMEA concluded that compliance with pre-existing procedures will result in the restoration of at least one chiller well before the Relay Room cooling becomes inadequate and temperature exceeds 120 ºF . Specifically, compliance with existing procedures will lead to recognition of the problem and, using currently proceduralized alternate methods for operating the system (i.e., NOT compensatory actions for addressing degraded or nonconforming conditions), restore the chiller control system function prior to the impairment of the associated design basis functions. In addition, an interdependent procedure change (satisfying the four bullets in NEI 96-07, Section 4.3.2, Example 4) will lead to the use of a new digital control system restart feature to reinitialize the control system and clear any software faults, allowing the chiller control system functions to be restored well before the Relay Room cooling becomes inadequate and temperature exceeds 120 ºF.

Step 5:

Although none of the safety analyses specifically identify assumptions or inputs related to the MCRVS, the Relay Room or the components therein, several accident analyses assume correct and timely actuation of the RPS and/or the ESFAS signals. As determined in Step 2 above, operation of the chiller control system is considered to be credited in the safety analysis since they support or impact the design bases functions associated with GDC 20. As demonstrated as part of Step 4, all design basis functions are preserved.

Step 6:

As determined in Step 4, all design basis functions are preserved.

Therefore, all of the safety analyses identified in Step 5 remain valid and there is no change in any safety analysis result.

Conclusion Although the software CCF likelihood was determined to be not sufficiently low, the design bases functions will continue to be performed/satisfied and the safety analyses (and all of the results from D-53

these analyses) are unaffected. Therefore, the proposed activity does NOT create the possibility of a malfunction of an SSC important to safety with a different result (for the aspect being illustrated in this example).

Example 4-21. NO CREATION of a Malfunction with a Different Result Proposed Activity Currently, the non-safety-related Steam Bypass Control System (SBCS) and the non-safety-related pressurizer pressure/level control system are separate analog control systems.

The SBCS is being upgraded from an analog to a digital system.

The pressurizer pressure/level control system is being upgraded from an analog control system to a digital control system.

As part of this modification, the two previously separate control systems (steam bypass and pressurizer) will be combined within the same digital controller in a distributed control system (DCS) with the same software controlling all steam bypass and pressurizer functions.

Safety Analysis Result Impact Consideration Step 1:

Steam Bypass - The pertinent function of the SBCS is to maximize plant availability by making full utilization of the turbine bypass valve capacity to remove NSSS thermal energy to accommodate load rejections, unit trips, and other conditions that result in the generation of excessive energy by the NSSS. This objective is achieved by the selective use of turbine bypass valves to avoid unnecessary reactor trips and prevent the opening of secondary side safety valves whenever these occurrences can be averted by the controlled release of steam.

Pressurizer - The pertinent function is control of the pressurizer sprays and heaters to maintain RCS pressure and pressurizer level within the established limits.

Step 2:

Steam Bypass - The function of the SBCS is classified as a design function due to its ability to initiate a transient or accident that the plant is required to withstand. However, the design function is not a design bases function.

(This design function goes directly to Step 5.)

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Pressurizer - In this case, determining if the function is a design bases function is not readily apparent, so the associated GDC will be identified and examined.

Criterion 10 -- Reactor design. The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. [emphasis added]

The pressurizer control system performs a function that supports or impacts a design basis function specified in GDC 10. Therefore, the pressurizer control system function is a design basis function credited in the safety analysis.

Step 3:

The effect on the steam bypass and pressurizer control systems is clear and understood, having a direct impact on the accident analysis assumptions and modeling. There is no reason to generate a new FMEA since the impact of the software CCF on the accident analysis is readily apparent (i.e., clear and understood).

Step 4:

If a software CCF occurs, the pressurizer pressure/level control function, which supports or impacts the GDC 10 design basis function, will not be performed.

Step 5:

The pertinent safety analysis is the accident analysis for Increased Main Steam Flow. Typically, in Chapter 15 accident analyses, control system action is considered only if that action results in more severe accident results. The steam bypass and pressurizer control systems have a direct impact on the accident analysis assumptions and modeling.

Step 6:

Previously, all four SBCS turbine bypass valves were assumed to fail open as part of the initiation of the Increased Main Steam Flow event.

In the proposed design, all four SBCS turbine bypass valves could also fail open due to a software CCF in the digital control system.

In the Increased Main Steam Flow accident analysis, the pressurizer pressure/level control system is assumed to be in automatic and would attempt to mitigate the results of the accident. However, the sequence D-55

of events for the accident identifies that the pressurizer empties during the event. Therefore, regardless of the operation (or mis-operation) of the pressurizer pressure/level control system during the event, the malfunction of the pressurizer pressure/level control system would have no effect on this event and no effect on the safety analysis result.

The severity of the initiating failure assumed in the Increased Main Steam Flow accident analysis (four valves affected) is unchanged since the current analysis assumes the maximum possible increased steam flow. Furthermore, the failure mode (valve closure) is determined to have no effect and the mechanism (control signal error) that allows the valves to open, allowing the steam flow to increase, has no impact on the initial conditions of the event.

The assumption regarding the "status" of the pressurizer pressure/level control system (i.e., automatic vs. failed) both lead to emptying of the pressurizer, having no impact on the outcome of the event.

Therefore, there are no impacts due to the combination of the two control systems.

Conclusion Although the software CCF likelihood was determined to be not sufficiently low, the initiation severity assumed in the Increased Main Steam Flow accident analysis (four valves affected), the failure modes (valve closure) and the mechanism by which steam flow increases (control signal error) remain bounded. Furthermore, the results of the safety analysis, including the type of event (decreasing pressure) and all criteria that must be satisfied (maximum allowed peak RCS pressure, maximum allowed secondary pressure, minimum allowed DNBR, maximum allowed peak linear heat rate and the dose consequences) remain bounded.

Therefore, the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result (for the aspect being illustrated in this example).

Examples 4-22 and 4-23 illustrate cases in which there is the CREATION of a malfunction with a different result.

Example 4-22. CREATION of a Malfunction with a Different Result Proposed Activity An upgrade to the analog-based reactor protection system with a digital-based reactor protection system is proposed. This proposed modification involves replacement of all the solid state cards that D-56

control the detection of anticipated operational occurrences and the actuation of the required reactor trip signals. Redundant channels contain these cards in satisfaction of single failure criteria.

Safety Analysis Result Impact Consideration Step 1:

The number of involved functions is large, all of which involve the detection of anticipated operational occurrences, the processing of those signals, and the generation of the appropriate reactor trip signals.

Step 2:

In this case, whether the functions are design bases function is not readily apparent, so the associated GDCs will be identified and examined.

Criterion 20 -- Protection system functions. The protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety. [emphasis added]

Criterion 21 -- Protection system reliability and testability. The protection system shall be designed for high functional reliability and inservice testability commensurate with the safety functions to be performed. Redundancy and independence designed into the protection system shall be sufficient to assure that (1) no single failure results in loss of the protection function and (2) removal from service of any component or channel does not result in loss of the required minimum redundancy unless the acceptable reliability of operation of the protection system can be otherwise demonstrated. The protection system shall be designed to permit periodic testing of its functioning when the reactor is in operation, including a capability to test channels independently to determine failures and losses of redundancy that may have occurred. [emphasis added]

Criterion 22 -- Protection system independence. The protection system shall be designed to assure that the effects of natural phenomena, and of normal operating, maintenance, testing, and postulated accident conditions on redundant channels do not result in loss of the protection function, or shall be demonstrated to be acceptable on some other defined basis. Design techniques, such as functional diversity or diversity in component design and principles of operation, D-57

shall be used to the extent practical to prevent loss of the protection function. [emphasis added]

The components perform functions that support or impact design bases functions specified in GDCs 20, 21, and 22. Thus, these functions are design basis functions credited in the safety analysis.

Step 3:

The effect on the detection, processing and generation of signals is clear and understood, having a direct impact on the safety analysis assumptions. There is no reason to generate a new FMEA since the impact of the software CCF on the design bases functions is readily apparent (i.e., clear and understood).

Step 4:

The design bases functions related to the GDC 21 and 22 requirements regarding single failure criteria and redundant channels will not be performed.

Step 5:

Numerous safety analyses contain implicit assumptions regarding the performance and/or expectation of the minimum number of system/components and/or trains/channels that are expected to perform their function, which satisfy the applicable redundancy requirements and/or single failure criteria.

Step 6:

In all cases, for each safety analysis, the inability to satisfy the performance and/or expectation of the minimum number of systems/components and/or trains/channels violates an assumption upon which the safety analysis results are based.

In these instances, a review of the safety analyses and their structure will quickly conclude that the results will no longer be bounded.

Conclusion With the software CCF likelihood determined to be not sufficiently low, the assumptions regarding satisfaction of single failure criteria are invalidated and the results are no longer bounded. Therefore, the proposed activity CREATES the possibility of a malfunction of an SSC important to safety with a different result (for the aspect being illustrated in this example)..

Example 4-23. CREATION of a Malfunction with a Different Result D-58

Proposed Activity A feedwater control system is being upgraded from an analog system to a digital system.

Safety Analysis Result Impact Step 1:

The pertinent function of the feedwater control system is to establish and maintain steam generator water level within predetermined physical limits during normal operating conditions.

Step 2:

The function of the feedwater control system is classified as a design function due to its ability to initiate a transient or accident that the plant is required to withstand. However, the design function is not a design basis function.

With no design basis functions involved, proceed to Step 5.

Step 3:

Not applicable Step 4:

Not applicable Step 5:

The pertinent safety analysis is the accident analysis for Loss of Feedwater. The feedwater control system has a direct impact on the accident analysis assumptions and modeling.

Step 6:

Previously, only one feedwater flow control valve (out of four) could fail closed due to a failure of the analog control system. In the proposed design, all four feedwater flow control valves could simultaneously fail closed due to a software CCF in the digital control system.

In the current Loss of Feedwater accident analysis, the closure of only one flow control valve is assumed. With the proposed design, the severity of the initiating failure that needs to be assumed in the Loss of Feedwater accident analysis (four valves affected) is changed since the current analysis did not assume a total loss of feedwater flow. The failure mode (valve closure) is determined to have no effect on this assumption. The mechanism by which feedwater flow is lost (loss of control signal) has no impact on the initial conditions of the event.

Conclusion D-59

With the software CCF likelihood determined to be not sufficiently low and the initiation severity assumed in the current Loss of Feedwater accident analysis (only one valve affected), the accident analysis result does not remain bounded.

Thus, the proposed activity CREATES the possibility for a malfunction of an SSC important to safety with a different result (for the aspect being illustrated in this example).

NOTE: See Example 4-17 for a similar example that illustrates the case in which the current Loss of Feedwater accident analysis assumed the closure of all four flow control valves, causing NO CREATION of a malfunction with a different result.

4.3.7 Does the Activity Result in a Design Basis Limit for a Fission Product Barrier Being Exceeded or Altered?

There is no unique guidance applicable to digital modifications for responding to this Evaluation question because the identification of possible design basis limits for fission product barriers and the process for determination of "exceeded" or "altered" are not unique for a digital modification. The guidance in NEI 96-07, Section 4.3.7 applies.

4.3.8 Does the Activity Result in a Departure from a Method of Evaluation Described in the UFSAR Used in Establishing the Design Bases or in the Safety Analyses?

There is no unique guidance applicable to digital modifications for responding to this Evaluation criterion because activities involving methods of evaluation do not involve SSCs. The guidance in NEI 96-07, Section 4.3.8 applies.

5.0 EXAMPLES

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NEI 96-07, Appendix D Draft Revision 0fg Nuclear Energy Institute SUPPLEMENTAL GUIDANCE FOR APPLICATION OF 10 CFR 50.59 TO DIGITAL MODIFICATIONS JulyOctober 2018

ACKNOWLEDGMENTS NEI would like to thank the NEI 01-01 Focus Team for developing this document.

Although everyone contributed to the development of this document, NEI would like to give special recognition to David Ramendick, who was instrumental in preparing this document.

NOTICE Neither NEI, nor any of its employees, members, supporting organizations, contractors, or consultants make any warranty, expressed or implied, or assume any legal responsibility for the accuracy or completeness of, or assume any liability for damages resulting from any use of, any information apparatus, methods, or process disclosed in this report or that such may not infringe privately owned rights.

EXECUTIVE

SUMMARY

NEI 96-07, Appendix D, Supplemental Guidance for Application of 10 CFR 50.59 to Digital Modifications, provides focused application of the 10 CFR 50.59 guidance contained in NEI 96-07, Revision 1, to activities involving digital modifications.

The main objective of this guidance is to provide all stakeholders a common framework and understanding of how to apply the 10 CFR 50.59 process to activities involving digital modifications.

The guidance in this appendix supersedes the 10 CFR 50.59-related guidance contained in NEI 01-01/ EPRI TR-102348, Guideline on Licensing of Digital Upgrades and in Regulatory Issue Summary (RIS) 2002-22, Supplement 1, Clarification on Endorsement of Nuclear Energy Institute Guidance in Designing Digital Upgrades in Instrumentation and Control Systems. Commented [NEI1]: Addresses NRC comment A1.

i

TABLE OF CONTENTS EXECUTIVE

SUMMARY

...................................................................................................................................... i 1 INTRODUCTION ........................................................................................................................................ 2

1.1 BACKGROUND

................................................................................................... 2 1.2 PURPOSE ........................................................................................................... 3 1.3 10 CFR 50.59 PROCESS

SUMMARY

................................................................ 43 1.4 APPLICABILITY TO 10 CFR 72.48 ................................................................. 43 1.5 CONTENT OF THIS GUIDANCE DOCUMENT ................................................... 43 2 DEFENSE IN DEPTH DESIGN PHILOSOPHY AND 10 CFR 50.59 ............................................. 43 3 DEFINITIONS AND APPLICABILITY OF TERMS ............................................................................ 54 4 IMPLEMENTATION GUIDANCE........................................................................................................... 75 4.1 APPLICABILITY ............................................................................................... 75 4.2 SCREENING ..................................................................................................... 75 4.3 EVALUATION PROCESS ............................................................................... 2924 5.0 EXAMPLES .......................................................................................................................................... 7563 D-1

1 INTRODUCTION There are specific considerations that should be addressed as part of the 10 CFR 50.59 process when performing 10 CFR 50.59 reviews for digital modifications. These specific considerations include different potential failure modes of digital equipment as opposed to the equipment being replaced, the effect of combining functions of previously separate devices (at the component level, at the system level, or at the "multi-system" level) into fewer devices or one device, and the potential for software common cause failure (software CCF ).

The format of this Appendix was aligned with NEI 96-07, Rev. 1 text for ease of use. As such, there will be sections where no additional guidance is provided.

1.1 BACKGROUND

Licensees have a need to modify existing systems and components due to the growing problems of obsolescence, difficulty in obtaining replacement parts, and increased maintenance costs. Also, Tthere also is great incentive to take advantage of modern digital technologies whichthat offer potential performance and reliability improvements.

In 2002, a joint effort between the Electric Power Research Institute (EPRI) and the Nuclear Energy Institute (NEI) produced NEI 01-01, Revision 0 (also known as EPRI TR-102348, Revision 1), Guideline on Licensing Digital Upgrades: A Revision of EPRI TR-102348 to Reflect Changes to the 10 CFR 50.59 Rule, which was endorsed (with qualifications) by the Nuclear Regulatory Commission (NRC) in Regulatory Issue Summary (RIS) 2002-22.

Since the issuance of NEI 01-01 in 2002, digital modifications have become more prevalent. Application of the 10 CFR 50.59 guidance contained in NEI 01-01 has not been consistent or thorough across the industry, leading to NRC concerns regarding uncertainty as to the effectiveness of NEI 01-01 and the need for clarity to ensure an appropriate level of rigor is being applied to a wide variety of activities involving digital modifications.

NEI 01-01 contained guidance for both the technical development and design of digital modifications, as well as the application of 10 CFR 50.59 to those digital modifications. The NRC also identified this "mixture of guidance" as an issue and stated that NEI cshould separate the technical guidance from the 10 CFR 50.59 related guidance.

In 2018, Supplement 1 to RIS 2002-22 was issued to clarify the NRC staffs endorsement of the guidance pertaining to NEI 01-01, Sections 4 and 5 and Appendices A and B. Specifically, the RIS supplement clarified the guidance D-2

for preparing and documenting qualitative assessments that may be used to evaluate the likelihood of failure of a proposed digital modification, including the likelihood of failure due to a software common cause failure (software CCF).

Supplement 1 to RIS 2002-22 identified that a qualitative assessment may be used to support a conclusion that a proposed digital I&C modification will not result in more than a minimal increase in the frequency of occurrence of accidents or in the likelihood of occurrence of malfunctions (10 CFR 50.59(c)(2)(i) and (ii)). A qualitative assessment may also be used to support a conclusion that the proposed modification does not create the possibility of an accident of a different type or a malfunction with a different result than previously evaluated in the updated final safety analysis report (10 CFR 50.59(c)(2)(v) and (vi)). Commented [NEI2]: Addresses NRC comment A2.

1.2 PURPOSE Appendix D is intended to assist licensees in the performance of 10 CFR 50.59 reviews of activities involving digital modifications in a consistent and comprehensive manner. This assistance includes guidance for performing 10 CFR 50.59 Screens and 10 CFR 50.59 Evaluations. Appendix D does not alter and, unless explicitly noted, should not be interpreted differently than the guidance contained in NEI 96-07, Rev. 1. Rather, Appendix D provides focused guidance for the application of 10 CFR 50.59 to activities involving digital modifications. This appendix does not include guidance regarding Commented [NEI3]: Addresses NRC comment A3.

design requirements for digital activities. Commented [NEI4]: [Enhancement] Considers NRC comment A4.

The guidance in this appendix applies to 10 CFR 50.59 reviews for both small-scale and large-scale digital modifications; from the simple replacement of an individual analog meter with a microprocessor-based instrument, to a complete replacement of an analog reactor protection system with an integrated digital system. Examples of activities considered to beinvolve a digital modification include computers, computer programs, data (and its presentation), embedded digital devices, software, firmware, hardware, the human-system interface, microprocessors and programmable digital devices (e.g., Programmable Logic Controllers and Field Programmable Gate Arrays).

This guidance is not limited to "stand-alone" instrumentation and control systems. This guidance can also be applied to the digital aspects of modifications or replacements of mechanical or electrical equipment if the new equipment makes use of digital technology (e.g., a new HVAC design that includes embedded microprocessors for control).

Finally, this guidance is applicable to digital modifications involving safety-related and non-safety-related systems and components and also covers D-3

digital-to-digital activities (i.e., modifications or replacements of digital-based systems).

1.3 10 CFR 50.59 PROCESS

SUMMARY

No additional guidance is provided.

1.4 APPLICABILITY TO 10 CFR 72.48 No additional guidance is provided.

1.5 CONTENT OF THIS GUIDANCE DOCUMENT Relationship of Appendix D to NEI 96-07, Revision 1 No additional guidance is provided.In sections 3 and 4 of this appendix, references to the main body of NEI 96-07, Revision 1 will be abbreviated as "NEI 96-07."

Guidance Focus In Sections 4.2 (Screening) and 4.3 (Evaluation), each section and sub-section addresses only a specific aspect, sometimes at the deliberate exclusion of other pertinent and/or related aspects.

This focused approach is intended to concentrate the guidance on the particular aspect of interest and does not imply that the other aspects do not apply or could not be related to the aspect being addressed. Initially, all aspects need to be considered, with the knowledge that some of them may be able to be excluded based on the actual scope of the digital modification being reviewed.

Example Focus Commented [NEI5]: Addresses NRC comment A6 by adding bold emphasis. (Refer to the changes in each Unless stated otherwise, a given example addresses ONLY the aspect within example for specific incorporation of this NRC comment and other, more specific NRC comments.)

the section/sub-section in which it is included, sometimes at the deliberate exclusion of other pertinent and/or related aspects which, if considered, could potentially change the Screen and/or Evaluation conclusion(s). Commented [NEI6]: Addresses NRC comment A7.

Although this type of guidance is not contained in NEI 96-07, Rev. 1, in an attempt to limit the amount of information 2 DEFENSE IN DEPTH DESIGN PHILOSOPHY AND 10 CFR 50.59 that needs to be included in Appendix D, only the conclusion related to the specific aspect will be addressed.

To minimize the potential for user or regulatory No additional guidance is provided. uncertainty, the conclusions in the examples will be modified by adding the parenthetical phrase "(for the aspect being illustrated in this example)" after all Screen and Evaluation example conclusions.

Commented [NEI7]: Text moved here from duplicate locations in the Screen and Evaluation sections.

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3 DEFINITIONS AND APPLICABILITY OF TERMS Definitions 3.1 through 3.14 are the same as those provided in NEI 96-07, Rev. 1.

Definitions specific to this appendix are defined below.

3.15 Sufficiently LowQUALITATIVE ASSESSMENT Sufficiently low means much lower than the likelihood of failures that are considered in the UFSAR (e.g., single failures) and comparable to other common cause failures that are not considered in the UFSAR (e.g., design flaws, maintenance errors, and calibration errors).Definition:

A qualitative assessment is a specific type of technical-based engineering evaluation useful to 10 CFR 50.59 Evaluations when responding to Evaluation criteria 10 CFR 50.59(c)(2(i), (ii), (v) and (vi).

Discussion:

The purpose of a qualitative assessment is to determine the "magnitude" of the likelihood of a software CCF. The magnitude of the likelihood of a software CCF can be either sufficiently low (see the definition in Section 3.16) or not sufficiently low. Therefore, the only part of the qualitative assessment needed for responding to the four 10 CFR 50.59(c)(2) criteria listed above is the outcome (i.e., sufficiently low or not sufficiently low).

Although a qualitative assessment could be performed as part of developing the responses to the four 10 CFR 50.59(c)(2) criteria listed above, this technical-based engineering evaluation is typically performed "prior to" or "in parallel with" the completion of the 10 CFR 50.59 Evaluation.

Generally, reasonable assurance of the low likelihood of failure due to a software CCF is derived from the qualitative assessment of factors involving (1) the design attributes of the modified SSC, (2) the quality of the design processes, and (3) the operating experience of the software and hardware used (i.e., product maturity and in-service experience).

The qualitative assessment is used to record the factors and rationale for making a determination of the likelihood of failure (i.e., sufficiently low or not sufficiently low) due to a software CCF that a digital I&C modification will exhibit.

The determination of the likelihood of failure may consider the aggregate of all the factors described above. Namely, some of the factors may compensate D-5

for weaknesses in other areas or other factors. For example, thorough testing coupled with an analysis demonstrating untested states are accounted for in the proposed application may provide additional assurance of a sufficiently low likelihood of failure to compensate for a lack of operating experience. Commented [NEI8]: Addresses NRC comments A41 and A42.

A qualitative assessment should not be used for digital I&C replacements of the reactor protection system (RPS), the engineered safety features actuation system (ESFAS), or modification/replacement of the internal logic portions of these systems (e.g., voting logic, bistable inputs, and signal conditioning/processing). Commented [NEI9]: Addresses NRC comment A41.

3.16 SUFFICIENTLY LOW Definition:

Sufficiently low means much lower than the likelihood of failures that are considered in the UFSAR (e.g., single failures) and comparable to other common cause failures that are not considered in the UFSAR (e.g., design flaws, maintenance errors and calibration errors).

Discussion:

This sufficiently low threshold is not interchangeable with that used for distinguishing between events that are credible or not credible. The threshold for determining if an event is credible uses the criterion of as likely as (i.e., not much lower than) the malfunctions already assumed in the UFSAR. Commented [NEI10]: Addresses NRC comment A43.

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4 IMPLEMENTATION GUIDANCE 4.1 APPLICABILITY No additional guidance is provided.

4.2 SCREENING CAUTION The guidance contained in this section of the appendix is intended to supplement the generic Screen guidance contained in the main body in NEI 96-07, Section 4.2.

Namely, the generic Screen guidance provided in the main body of NEI 96-07 and the more-focused Screen guidance in this appendix BOTH apply to digital modifications.

Introduction Throughout this section, references to the main body of NEI 96-07, Rev. 1 will be identified as "NEI 96-07." Commented [NEI11]: Text moved to Section 1.5.

As stated in NEI 96-07, Section 4.2.1, the determination of the impact of a proposed activity (i.e., adverse or not adverse) is based on the impact of the proposed activity on UFSAR-described design functions. To assist in determining the impact of a digital modification on a UFSAR-described design function, the general guidance from NEI 96-07 will be supplemented with the digital-specific guidance in the topic areas identified below.

Digital-to-Digital Replacements and "Equivalency" In NEI 96-07, Section 4.2.1.1, equivalent replacements are discussed.

However, digital-to-digital changes may not necessarily be equivalent because the component/system behaviors, response times, failure modes, etc.

for the new component/system may be different from the old component/system. All non-equivalent digital-to-digital replacements should utilize the guidance provided in this Appendix.

Guidance Focus In the following sections and sub-sections that provide the Screen guidance unique to the application of 10 CFR 50.59 to digital modifications, each section and sub-section addresses only a specific aspect, sometimes at the deliberate exclusion of other related aspects.

This focused approach is intended to concentrate on the particular aspect of interest and does not imply that the other aspects do not apply or could not D-7

be related to the aspect being addressed. Initially, all aspects need to be considered, with the knowledge that some of them may be able to be excluded based on the actual scope of the digital modification being reviewed. Commented [NEI12]: Text moved to Section 1.5.

Example Focus Within this appendix, examples are provided to illustrate the guidance.

Unless stated otherwise, a given example only addresses the aspect or topic within the section/sub-section in which it is included, sometimes at the deliberate exclusion of other aspects or topics which, if considered, could potentially change the Screen conclusion. Commented [NEI13]: Text moved to Section 1.5.

Human-System Interface EvaluationsConsiderations Commented [NEI14]: NRC comment A8 to remove the HSI guidance is NOT incorporated. HSI guidance here and in the Screen section will be retained. NEI 96-07, Rev. 1, Similar to other technical evaluations (performed as part of the design Section 4.2.1.2 contains generic guidance that needs to be modification package), a human factors engineering (HFE) evaluation specifically applied to digital modifications. Furthermore, NEI 01-01, Section 4.3.4 currently contains endorsed HSI-determines the impacts and outcomes of the change (e.g., personnel acts or related guidance that needs to be brought forward into omissions, as well as their likelihoods and effects). The licensing-based Appendix D. Finally, this guidance satisfies the NRC expectation in General Comment #1 that all pertinent reviews (Screens and Evaluations) performed in accordance with 10 CFR guidance from NEI 01-01 is to be included in the 50.59 compare the impacts and new outcomes (i.e., post-modification) to the appropriate new guidance.

initial conditions and current outcomes (i.e., pre-modification) in order to determine the effect on design functions (in the Screen phase) and the need for a license amendment request (in the Evaluation phase).

4.2.1 Is the Activity a Change to the Facility or Procedures as Described in the UFSAR?

Introduction A 10 CFR 50.59 Evaluation is required for digital modifications that adversely affect design functions, or the methods used to perform or control design functions. There is no regulatory requirement for a proposed activity involving a digital modification to default (i.e., be mandatorily "forced") to an adverse conclusion.

Although there may be adverse impacts on UFSAR-described design functions due to the following types of activities involving a digital modification, these typical activities do not default to an adverse conclusion simply because of the activities themselves.

  • The introduction of software or digital devices.
  • The replacement of software and/or digital devices with other software and/or digital devices.
  • The use of a digital processor to "calculate" a numerical value or "generate" a control signal using software in place of using analog components.

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  • Replacement of hard controls (i.e., pushbuttons, knobs, switches, etc.) with a touch-screen to operate or control plant equipment.

Engineering/technical information should be documented (as part of the design process) to record the impacts from digital modifications. This engineering/technical information will be used as the basis/justification for the conclusion of adverse or not adverse.

Scope of Digital Modifications Generally, a digital modification may consist of three areas of activities: (1) software-related activities, (2) hardware-related activities and (3) Human-System Interface-related activities.

NEI 96-07, Section 4.2.1.1 provides guidance for activities that involve "...an SSC design function..." or a "...method of performing or controlling a design function..." and Section 4.2.1.2 provides guidance for activities that involve

"...how SSC design functions are performed or controlled (including changes to UFSAR-described procedures, assumed operator actions and response times)."

Based on this segmentation of activities, the software and hardware portions will be assessed within the "facility" Screen consideration since these aspects involve SSCs, SSC design functions, or the method of performing or controlling a design function and the Human-System Interface (HSI) portion will be assessed within the "procedures" Screen consideration since this portion involves how SSCs are operated and controlled.

4.2.1.1 Screening of Changes to the Facility as Described in the UFSAR SCOPE In the determination of potential adverse impacts, the following aspects should be addressed in the response to this Screen consideration:

(a) Use of Software and Digital Devices (b) Combination of Components/Systems and/or Functions USE OF SOFTWARE AND DIGITAL DEVICES Discussion In NEI 96-07, Section 4.2.1, sub-section titled "Screening for Adverse Effects,"

the second paragraph contains the following guidance:

"...changes that would introduce a new type of accident or malfunction would screen in." [emphasis added]

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Note that this Screen guidance does NOT address the "result(s)" of a new malfunction, which is the subject of Evaluation criterion (c)(2)(vi).For Commented [NEI15]: Addresses NRC comments A9 and A10.

applications involving SSCs with design functions, digital modifications that introduce the exact same software into redundant trains or channels to perform a design function have the potential to create a new malfunction.

The potential to create a new malfunction comes from the possibility of a software CCF that did not previously exist. an adverse effect may be created due to the potential marginal increase in the likelihood of SSC failure due to the introduction of software. This does not mean that all digital modifications that introduce software will automatically screen-in.

For redundant safety systems, this marginal increase in likelihood creates a similar marginal increase in the likelihood of a common failure in the redundant safety systems. On this basis, most digital modifications to redundant safety systems are adverse.

However, for some digital modifications, the engineering/technical information supporting the change may show that the digital modification contains design attributes to eliminate consideration of a software common cause failure (i.e., software CCF likelihood = 0). In such cases, even when a digital modification involves redundant systems, the digital modification would not be adverse. Commented [NEI16]: Addresses NRC comments A11 and A12.

For relatively simple digital modifications, engineering evaluationsengineering/technical information supporting the change may be Commented [NEI17]: Addresses NRC comment A13.

used to show that the digital modification would not adversely affect design functions; even for digital modifications that involve redundant components/systems because the reliability of performing design functions is not decreased and no new malfunctions are created a software CCF is not introduced (i.e., software CCF likelihood = 0). Commented [NEI18]: Addresses NRC comment A14.

To reach a screen conclusion of not adverse for relatively simple digital modifications, the degree of assurance needed to make that conclusion is based on considerations such as the following:

  • Physical Characteristics of the Digital Modification The change has a limited scope (e.g., replace analog transmitter with a digital transmitter that drives an existing instrument loop)

Uses a relatively simple digital architecture internally (e.g., simple Commented [NEI19]: Addresses NRC comment A15.

process of acquiring one input signal, setting one output, and performing some simple diagnostic checks)

Has limited functionality (e.g., transmitters used to drive signals for parameters monitored)

Can be comprehensively tested (but not necessarily 100 percent of all combinations)

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  • Engineering Evaluation Assessments The quality of the design processes employed Single failures of the digital device are encompassed by existing failures of the analog device (e.g., no new digital communications among devices that introduce possible new failure modes involving separate devices)

Has extensive applicable operating history The use of different software in two or more channels, trains or loops of SSCs is not adverse due to a software CCF because there is no mechanism to create a new malfunction due to the introduction of the software.

Some specific examples of activities that have the potential to cause an adverse effect include the following activities:

  • Addition or removal of a dead-band, or
  • Replacement of instantaneous readings with time-averaged readings (or vice-versa).

In each of these specific examples, the impact on a design function associated with the stated condition needs to be assessed to determine the Screen conclusion (i.e., adverse or not adverse).

EXAMPLES Example 4-1 illustrates the application of the guidance for a relatively simple digital modification.

Example 4-1. NO ADVERSE IMPACT on a Design Function for a Relatively Simple Digital Modification Proposed Activity Description Transmitters are used to drive signals for parameters monitored by redundant ESFAS channels. The original analog transmitters are to be replaced with microprocessor-based transmitters. The change is of limited scope since the existing 4-20 mA instrument loop is maintained for each channel without any changes other than replacing the transmitter itself.

The digital transmitters are used to drive signals of monitored parameters and thus have limited functionality with respect to the Engineered Safety Features Actuation System (ESFAS) design function.

Design Function Identification The ESFAS design function is the ability to respond to plant accidents.

Screen Response The digital transmitters use a relatively simple digital architecture internally D-11

in that the firmware in the new transmitters implements a simple process of acquiring one input signal, setting one output, and performing some simple diagnostic checks. Commented [NEI20]: Addresses NRC comment A16.

Failures of the new digital device are encompassed by the failures of the existing analog device in that there are no new digital communications among devices that introduce possible new failure modes involving multiple devices. The engineering evaluation of the digital Commented [NEI21]: Addresses NRC comment A17.

deviceengineering/technical information supporting the change concluded Commented [NEI22]: Addresses NRC comment A13.

that the digital system is at least as reliable as the previous system, the conclusion of which is based on the quality of the design processes employed, and the operating history of the software and hardware used. In addition, based on the simplicity of the device (one input and one output), it was Commented [NEI23]: Addresses NRC comment A18.

comprehensively tested. Further, substantial operating history has demonstrated high reliability in applications similar to the ESFAS application.

Therefore, the proposed digital modification is not adverse (for the aspect being illustrated in this example) because the digital modification is Commented [NEI24]: Addresses NRC comment A7.

relatively simple and the assessment of the considerations identified above has determined that the reliability of performing the design function is not reduced and no new malfunctions are createda software CCF is not introduced.

Examples 4-2 and 4-3 illustrate the application of the Use of Software and Digital Devices aspect.

Example 4-2. NO ADVERSE IMPACT on a Design Function related to use of Software and Digital Devices Proposed Activity Description Two non-safety-related trains of main feedwater heaters exist, one for each train of main feedwater. Each main feedwater train consists of six feedwater heaters, for a total of 12 heaters. Each heater possesses an analog controller to control the water level in each of the heaters. Each analog controller is physically and functionally the same.

Each of the analog controllers will be replaced with its own digital controller.

The hardware platform for each digital controller is from the same supplier and the software in each digital controller is exactly the same.

Design Function Identification In this case, the review of the UFSAR determined that Tthere are NO design Commented [NEI25]: Addresses NRC comments A19 and A20.

functions associated with the feedwater heater water level controllers. The only UFSAR description related to the heaters states that the feedwater heater water level controllers are used to adjust the water levels in the D-12

heaters to optimize the thermal efficiency of the facility.

Screen Response Since there are no design functions associated with the feedwater heater water level controllers, there are no adverse impacts (for the aspect being illustrated in this example). Commented [NEI26]: Addresses NRC comment A7.

Example 4-3. ADVERSE IMPACT on a Design Function related to use of Software and Digital Devices Proposed Activity Description Two non-safety-related main feedwater pumps (MFWPs) exist. There are two analog control systems (one per MFWP) that are physically and functionally the same.

The two analog control systems will be replaced with two digital control systems. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

No combination of components/systems and/or functions occurs as part of this digital modification. Commented [NEI27]: Addresses NRC comment A21.

Design Function Identification The design function of the feedwater control systems is to automatically control and regulate feedwater flow to the steam generators.

The UFSAR identifies the following MFWP control system malfunctions:

(a) failures causing the loss of one MFWP and its associated flow to the steam generators, and (b) failures causing an increase in main feedwater flow to the maximum output from one MFWP. Commented [NEI28]: Addresses NRC comment A21.

Screen Response The digital modification associated with this proposed activity is not relatively simple, so the process for assessing relatively simple digital modifications could not be used.

There is an adverse impact (for the aspect being illustrated in this example) Commented [NEI29]: Addresses NRC comment A7.

on the design function of the main feedwater control system because the use of the exact same software in both digital control systems creates a new D-13

malfunction that could impact both MFWPs due to a potential software CCF that did not previously exist.

COMBINATION OF COMPONENTS/SYSTEMS AND/OR FUNCTIONS Discussion The UFSAR may identify the number of components/systems, how the components/systems wereare arranged, and/or how functions, i.e., design requirements, wereare allocated to those components/systems.

When replacing analog SSCs with digital SSCs, it is potentially advantageous to combine multiple components/systems and/or functions into a single device or control system. However, as a result of this combination, the failure of the single device or control system has the potential to adversely affect the performance of design functions.

The combination of mere act of combining previously separate components/systems and/or functions, in and of itself, does not make the Screen conclusion adverse. OnlyHowever, if combining the previously separate components/systems and/or functions causes an adverse impact on a design function does (e.g., by causing the loss of multiple design functions when the digital device fails), then the combination aspect of the digital Commented [NEI30]: Addresses NRC comment A23.

Note that the parenthetical phrase is a paraphrasing of the modification will have an adverse impact on a design function (i.e., screen in). guidance from NEI 01-01, Section 4.3.3, 1st bullet at the end of the first paragraph.

When comparing the existing and proposed configurations, consider how the proposed configuration affects the number and/or arrangement of components/systems and the potential impacts of the proposed arrangement on design functions.

Furthermore, digital modifications that involve networking; combining design functions from different systems; interconnectivity across channels, systems, and divisions; or shared resources, merit careful review to determine if such modifications cause reductions in the redundancy, diversity, separation, or independence of UFSAR-described design functions (if such design functions exist).

Combining different functions due to digital modifications can result in combining design functions of different systems; either directly in the same digital device, or indirectly through shared resources. Shared resources (e.g.,

bidirectional communications, power supplies, controllers, and multifunction display and control stations) introduced by digital modifications may reduce the redundancy, diversity, separation, or independence of UFSAR-described design functions.

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Reductions in the redundancy, diversity, separation, or independence of a UFSAR-described design function (if such a design function exists) have an adverse impact on that design function. Commented [NEI31]: Addresses NRC comment A40 (incorporation of RIS Supplement 1).

EXAMPLES Examples 4-4 through 4-6 illustrate the application of the Combination of Components/Systems and/or Functions aspect.

Example 4-4. Combining Components and Functions with NO ADVERSE IMPACT on a Design Function Proposed Activity Description Two non-safety-related main feedwater pumps (MFWPs) exist. There are two analog control systems (one per MFWP) that are physically and functionally the same. Each analog control system has many subcomponents.

Option #1: Within each control system, all of the analog subcomponents will be replaced with a single digital device that consolidates all of the components, sub-components and the functions associated with each component and sub-component. The components and sub-components in each analog control system will be replaced with a separatetheir own digital control system, retaining two discreet, unconnected control systems.

Option #2: Instead of two separate, discreet, unconnected digital control systems being used for the feedwater control systems (as outlined in Option

  1. 1), only one central digital device is proposed to be used that will combine the previously separate ALL components, sub-components and functions of both control systems and control both main feedwater pumps. Commented [NEI32]: Clarifications. Also, the word "separate" contains a unique connotation not applicable in Design Function Identification this example Although the control systems and the major components are described in the UFSAR, only a design function for the feedwater control systems is identified.

The design function of the feedwater control systems is to automatically control and regulate feedwater flow to the steam generators.

The UFSAR identifies the following MFWP control system malfunctions:

(a) failures causing the loss of all feedwater to the steam generators, and (b) failures causing an increase in main feedwater flow to the maximum output from both MFWPs.

Screen Response NOTE: Since the intent of this example is to illustrate the combination aspect ONLY, the software and hardware aspects will not be addressed in this example. Commented [NEI33]: This NOTE is no longer needed due to the incorporation of NRC comment A7 throughout the Screen section.

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Option #1: There is no adverse impact (for the aspect being illustrated in this example) on the design function of the main feedwater control systems to Commented [NEI34]: Addresses NRC comment A7.

automatically control and regulate feedwater to the steam generators due to the combination of components in each of the two channels because only one design function would be affected by a failure of the new digital device no new malfunctions are created (i.e., the current malfunctions already consider the effect on botheach MFWPs). Commented [NEI35]: Addresses NRC comment A24.

Option #2: Although both main feedwater pumps would be affected by the failure of the one central digital processor, the proposed activity is not adverse (for the aspect being illustrated in this example) because only one Commented [NEI36]: Addresses NRC comment A7.

design function would be affected by a failure of the new digital device and no new malfunctions are created (i.e., the current malfunctions already consider the effect on both MFWPs).

NOTE: For both options, if the malfunctions had considered the effect on only one MFWP, the Screen conclusions would have been adverse (for the aspect being illustrated in this example) because multiple design functions Commented [NEI37]: Addresses NRC comment A7.

(i.e., one for each MFWP) would have been affected by a failure of the new digital device, creating a new malfunction would have been created. Commented [NEI38]: Addresses NRC comment A25.

Example 4-5. Combining Components and Functions with NO ADVERSE IMPACT on a Design Function Proposed Activity Description A temperature monitor/controller in a room containing an emergency room cooler provides an input to an air damper controller. If temperature gets too Commented [NEI39]: Clarification.

high, the temperature controller sends a signal to the air damper to open (if closed) to a predetermined initial position or, if already open, adjusts the position of the damper to allow increased air flow into the room.

Both analog controllers will be replaced with a single digital device that will perform in accordance with the original design requirements providing both temperature monitoring/control and air damper control.

Design Function Identification The temperature monitor/controller performs a design function to control the temperature in the room by continuously monitoring the temperature in the room to ensure the initial conditions are met should the emergency room coolers be needed.

The air damper controller performs a design function to control the temperature in the room by continuously provideing the appropriate air flow to the room to ensure the initial conditions are met should the emergency D-16

room coolers be needed. Commented [NEI40]: Clarification.

There is no lower limit on the acceptable temperature in the room.

Screen Response An engineering evaluation has documented the following malfunctions of the analog devices:

(1) failure of the temperature monitor/controller, causing the loss of input to the air damper controller and the ability of the air damper controller to control the temperature in the room, and (2) failure of the air damper controller, causing the loss of the ability to control the temperature in the room.

Also documented in the engineering evaluation is the malfunction of the digital device, causing the loss of input to the air damper controller and the ability of the air damper controller to control the temperature in the room.

A comparison of the analog component and digital device malfunctions shows them to be the same.In the current design, a failure of the temperature monitor/controller or the air damper controller causes the loss of the ability to perform one design function (i.e., the ability to control the temperature in the room). Therefore, although usingIn the proposed design, the failure of the digital device might causes multiple design functions to not be performedfailures, no new malfunctions are createdbut still only the loss of the ability to perform one design function (i.e., the ability to control the temperature in the room). With no new malfunctions being createdonly the loss of the ability to perform one design function in the current design and in the proposed design, there is no adverse impact (for the aspect being illustrated in this example) on the design functions due to the combination Commented [NEI41]: Addresses NRC comment A7.

aspect. Also, there are no indirect impacts that could affect the performance of the design functions due to the combination aspect. Commented [NEI42]: Addresses NRC comment A26.

The combining of components/systems and/or functions that were previously and completely physically and/or electrically separatediscrete (i.e., not Commented [NEI43]: Clarification. The word "separate" contains a unique connotation not applicable in this coupled) are of particular interest when determining the impact on design example.

functions.

Example 4-6 illustrates the combining of control systems from different, originally separatediscrete systems. Commented [NEI44]: Clarification. The word "separate" contains a unique connotation not applicable in this example Example 4-6. Combining Systems and Functions with an ADVERSE IMPACT on a Design Function Commented [NEI45]: Addresses NRC comment A22. The example now uses SBCS in place of feedwater.

Proposed Activity Description TwoOne non-safety-related analog feedwaterSteam Bypass cControl D-17

sSystems (SBCS) and one separate non-safety-related main turbine steam Commented [NEI46]: Clarification. The word "separate" contains a unique connotation not applicable in this inlet valves analog control system exist. example All threeBoth analog control systems will be replaced with one digital control system that will combine the two feedwater control systemsSBCS and the main turbine steam-inlet valve control system into a single digital device.

Design Function Identification The design function of the feedwater control systemsSBCS is to automatically control and regulate feedwater flow to the steam generatorsmaximize plant availability by making full utilization of the turbine bypass valve capacity to remove NSSS thermal energy to accommodate load rejections, unit trips, and other conditions that result in the generation of excessive energy by the NSSS. This objective is achieved by the selective use of turbine bypass valves to avoid unnecessary reactor trips and prevent the opening of secondary side safety valves whenever these occurrences can be averted by the controlled release of steam.

The design function of the main turbine inlet valve control system is to automatically control and regulate steam flow to the main turbine.

A review of the accident analyses identifies that none of the analyses consider the simultaneous failure of the feedwater control system and the failure of the main turbine control system. Commented [NEI47]: Information not needed for this example.

Screen Response Because new malfunctions have been introducedthe failure of the new, single digital device will cause the loss of multiple design functions, there are digital modification has an adverse impacts (for the aspect being illustrated in this example) on the design function of the main feedwater control systemsSBCS Commented [NEI48]: Addresses NRC comment A7.

and the design function of the main turbine steam inlet valves control system due to the combination of components and functions from the three control systems. Commented [NEI49]: Although "independence" does not apply to these non-safety-related control systems, the changes address NRC comment A27.

4.2.1.2 Screening of Changes to Procedures as Described in the UFSAR SCOPE If the digital modification does not include or affect an Human-System InterfaceHSI element (e.g., the replacement of a stand-alone analog relay with a digital relay that has no features involving personnel interaction and does not feed signals into any other analog or digital device), then this section does not apply and may be excluded from the Screen assessment.

In NEI 96-07, Section 3.11 defines procedures as follows:

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"...Procedures include UFSAR descriptions of how actions related to system operation are to be performed and controls over the performance of design functions. This includes UFSAR descriptions of operator action sequencing or response times, certain descriptions...of SSC operation and operating modes, operational...controls, and similar information."

Although UFSARs do not typically describe the details of a specific Human-System Interface (HSI), UFSARs willmay describe any design functions Commented [NEI50]: Clarification.

associated with the HSI.

Because the HSI involves system/component operation, this portion of a digital modification is assessed in this Screen consideration. The focus of the Screen assessment is on potential adverse effects due to modifications of the interface between the human user and the technical device.

Note that the "human user" could involve Control Room Operators, other plant operators, maintenance personnel, engineering personnel, technicians, etc.

HUMAN FACTORS ENGINEERING (HFE) EVALUATION Commented [NEI51]: Clarification. Added heading for information/guidance that follows.

There are three "basic HSI elements" of an HSI (

Reference:

NUREG-0700):

  • Displays: the visual representation of the information personnel need to monitor and control the plant.
  • Controls: the devices through which personnel interact with the HSI and the plant.
  • User-interface interaction and management: the means by which personnel provide inputs to an interface, receive information from it, and manage the tasks associated with access and control of information.

Any user of the HSI must be able to accurately perceive, comprehend and respond to system information via the HSI to successfully complete their tasks. Specifically, nuclear power plant personnel perform "four generic primary tasks" (

Reference:

NUREG/CR-6947):

1. Monitoring and detection (extracting information from the environment and recognizing when something changes),
2. Situation assessment (evaluation of conditions),
3. Response planning (deciding upon actions to resolve the situation), and
4. Response implementation (performing an action).

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Table 1 contains examples of modifications to each of the three basic HSI elements applicable to this Screen consideration.

Table 1 - Example Human-System Interface Modifications Typical HSI Element Description/Example Modification Increase/decrease in the amount of information displayed by and/or available from the HSI (e.g., combining multiple parameters into a single integrated Number of Parameters parameter, adding additional information regarding component/system performance)

Change to the type of information displayed and/or available from the HSI Displays Type of Parameters (e.g., removing information that was previously available or adding information that was previously unavailable)

Change to visual representation of information (e.g. increment of presentation Information Presentation modified)

Change to structural arrangement of data/information (e.g., information now Information Organization organized by channel/train rather than by flow-path)

Change to the type/functionality of input device (e.g., replacement of a push Control Input button with a touch screen)

Controls Change to the information sent back to the individual in response to an action Control Feedback (e.g., changing feedback from tactile to auditory)

Change in number and/or type of decisions made and/or actions taken (e.g.,

replacing an analog controller that can be manipulated in one step with a Action Sequences digital controller that must be called-up on the interface and then User-Interface manipulated)

Interaction and Changes that affect how an individual retrieves information/data (e.g.,

Information/Data Management information that was continuously displayed via an analog meter now requires Acquisition interface interaction to retrieve data from a multi-purpose display panel)

Changes from manual to automatic initiation (or vice versa) of functions (e.g.,

Function Allocation manual pump actuation to automatic pump actuation)

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To determine potential adverse impacts of HSI modifications on design functions, a two-step HSI assessmentHFE evaluation must be performed, as Commented [NEI52]: Addresses NRC comment A28.

follows:

  • Step One - Identify the generic primary tasks that are involved with (i.e., potentially impacted by) the proposed activity.
  • Step Two - For all primary tasks involved, assess if the modification negatively impacts an individual's ability to perform the generic primary task.

Examples of negative impacts on an individual's performance that may Commented [NEI53]: Addresses NRC comment A31.

result in adverse effects on a design function include, but are not limited to:

increased possibility of mis-operation, increased difficulty in evaluating conditions, increased difficulty in performing an action, increased time to respond, and creation of new potential failure modes.

GUIDANCE Commented [NEI54]: Clarification.

After the two-step HSI assessmentHFE evaluation, the finalnext step is Commented [NEI55]: Addresses NRC comment A28.

application of the standard Screen assessment process (i.e., identification of Commented [NEI56]: Addresses NRC comment A32.

design functions and determination of adverse or not adverse, including the justification for the conclusion). Commented [NEI57]: Addresses NRC comment A33.

Simple Human-System Interface Example Example 4-7 illustrates how a digital modification with HSI considerations would be addressed.

Example 4-7: Assessment of Modification with NO ADVERSE IMPACT on a UFSAR-Described Design Function Proposed Activity Description Currently, a knob is rotated clock-wise to open a flow control valve in 1%

increments and counter clock-wise to close a flow control valve in 1%

increments. This knob will be replaced with a touch screen that has two separate arrows, each in its own function block. Using the touch screen, touching the "up" arrow will open the flow control valve in 1% increments and touching the "down" arrow will close the flow control valve in 1%

increments.

HSI Assessment ProcessHFE Evaluation Commented [NEI58]: Addresses NRC comment A28.

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STEP 1. Identification of the Generic Primary Tasks Involved:

(1) Monitoring and detection (extracting information from the environment and recognizing when something changes) - NOT INVOLVED (2) Situation assessment (evaluation of conditions) - NOT INVOLVED (3) Response planning (deciding upon actions to resolve the situation) -

NOT INVOLVED (4) Response implementation (performing an action) - INVOLVED STEP 2. Assessment of Modification Impacts on the Involved Generic Primary Tasks:

As part of the technical evaluation supporting the proposed modification, a HFE evaluation was performed. Commented [NEI59]: Not needed since it is clearly part of the HFE evaluation.

Tasks 1, 2 and 3 were not involved, so these tasks are not impacted by the modification.

Task 4 was identified asis involved.; tThe HFE evaluation determined that Commented [NEI60]: Grammatical corrections.

the change from knob to touch screen would not have a negative impact Commented [NEI61]: Addresses NRC comments A31 and A34.

because it does not affect the operators ability to perform the response Commented [NEI62]: Grammatical correction.

implementation task.

Identification and Assessment of the Relevant Design Function(s)

Design Function Identification The UFSAR states the operator can "open and close the flow control valve using manual controls located in the Main Control Room." Thus, the design function is the ability to allowof the operator to manually adjust the position of the flow control valve and the UFSAR description implicitly identifies the SSC (i.e., the knob).

Screen Response Using the results from the engineering/technical information supporting the change, including the HFE evaluation, and examining the replacement of Commented [NEI63]: Addresses NRC comment A13.

the "knob" with a "touch screen," the modification is not adverse (for the aspect being illustrated in this example) because it does not impact the Commented [NEI64]: Addresses NRC comment A7.

ability of the operator to "open and close the flow control valve using manual controls located in the Main Control Room," maintaining satisfaction of how the UFSAR-described design function is performed or controlled. Commented [NEI65]: Clarification Comprehensive Human-System Interface Examples Examples 4-8a and 4-8b illustrate how a digital modification with HSI considerations would be addressed.

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Although both examples use the same basic digital modification, Example 4-8a illustrates a no adverse impact case and Example 4-8b illustrates an adverse impact case by "complicating" the HSI portion of the modification and modifying the applicable licensing basis.

Example 4-8a. Digital Modification Involving HSI Considerations with NO ADVERSE IMPACT on a Design Function Proposed Activity Description Analog components and controls for a redundant safety-related system are to be replaced with digital components and controls, including new digital-based HSI.

Currently, two redundant channels/trains of information and controls are provided to the operators in the Main Control Room for the redundant systems. For each channel/train, several different analog instruments present information regarding the performance of the system. The analog displays are arranged by system "flow path" to facilitate the operator's ability to monitor the system as a whole.

The existing HSI for these components is made up of redundant hard-wired switches, indicator lights and analog meters. The new HSI consolidates the information and controls onto two flat panel displays (one per train) with touch screen soft controls. The information available on the flat panels is equivalent to that provided on the current analog HSI. Each flat panel display contains only one screen that displays the information and the controls for only that train, replicating the information and controls arrangement as they are in the existing HSI.

The existing HSI requires operators to manipulate analog switches to implement a control action. To take a control action using the new HSI, the operator must (via the touch screen) select the appropriate activity (e.g.,

starting/initiating the system or changing the system line-up), select the component to be controlled (e.g., pump or valve), select the control action (e.g., start/stop or open/close), and execute the action.

HSI Assessment ProcessHFE Evaluation Commented [NEI66]: Addresses NRC comment A28.

Step 1. Identification of Which Four Generic Primary Tasks are Involved:

(1) Monitoring and detection (extracting information from the environment and recognizing when something changes) - INVOLVED (2) Situation assessment (evaluation of conditions) - NOT INVOLVED (3) Response planning (deciding upon actions to resolve the situation) -

NOT INVOLVED D-23

(4) Response implementation (performing an action) - INVOLVED Step 2. Assessment of the Modification Impacts on the Involved Generic Primary Tasks:

As part of the technical evaluation supporting the proposed modification, a HFE evaluation was performed. Commented [NEI67]: Not needed as it is clearly part of the HFE evaluation.

Task 1 is involved. Any change to information presentation has the potential to impact the operators ability to monitor and detect changes in plant parameters. Even though the modification will result in information being presented on flat panels, the information available and the organization of that information (i.e., by train) will be equivalent to the existing HSI. Due to this equivalence and additional favorable factors (e.g., appropriate sized flat panels, appropriate display brightness, clearly identified function buttons, etc.), as documented in the HFE evaluation, there is no impact toon the operators ability to monitor and detect changes in plant parameters.

Tasks 2 and 3 were not involved, so these tasks are not impacted by the modification.

Task 4 is involved. The modification will require the operator to perform four actions in order to manipulate a control (i.e., 1. select the appropriate activity, 2. select the specific component to be controlled, 3. select the control action to be initiated, and 4. execute the action). Currently, the operator is able to manipulate a control in one action (e.g., turn a switch to on/off). The HFE evaluation determined that the modification negatively impacts the operators ability to respond because the modification increases the difficulty of implementing a response by requiring four actions instead of one action Commented [NEI68]: Addresses NRC comment A34.

and the additional actions result in an increase in the operators time to respond.

Identification and Assessment of Design Functions Design Function Identification (a) Status indications are continuously available to the operator.

(b) The operator controls the system components manually.

In this case, the review of the UFSAR, including the assumptions described in the safety analyses, determined that there were no additional design functions related to how design function (b) was performed or controlled.

Namely, there were no design functions related to the number of steps necessary to perform the design function (i.e., complexity) or the duration in which the steps were to be performed (i.e., time response). Commented [NEI69]: Addresses NRC comment A39.

Screen Response D-24

Since the information available and the organization of that information using the new HSI is equivalent to the existing HSI, the design function for continuous availability of status indications is met and there is no adverse impact (for the aspect being illustrated in this example) on design function Commented [NEI70]: Addresses NRC comment A7.

(a).

Using the touch screen, the operator is still able to perform design function (b) to manipulate the control for the systems components. Therefore, there is no adverse impact (for the aspect being illustrated in this example) on Commented [NEI71]: Addresses NRC comment A7.

satisfaction of how design function (b) is performed or controlled. Commented [NEI72]: Addresses NRC comment A35.

Example 4-8b. Digital Modification Involving HSI Considerations with an ADVERSE IMPACT on a Design Function Proposed Activity Description Analog components and controls for a redundant safety-related system are to be replaced with digital components and controls, including new digital-based HSI.

Currently, two redundant channels/trains of information and controls are provided to the operators in the Main Control Room for the redundant systems. For each channel/train, several different analog instruments present information regarding the performance of the system. The analog displays are arranged by system "flow path" to facilitate the operator's ability to monitor the system as a whole.

The existing HSI for these components is made up of redundant hard-wired switches, indicator lights and analog meters. The new HSI consolidates the information and controls onto two flat panel displays (one per train) with touch screen soft controls. The information available on the flat panels is equivalent to that provided on the current analog HSI. Each flat panel display contains only one screen, which can display the information for only one train and the controls for only that train, replicating the information and controls arrangement as they are in the existing HSI. Each flat panel display can be customized to display the parameters and/or the configuration (e.g. by train, by flow path or only portions of a train or flow path) preferred by the operators. In addition, the flat panel displays provide many other display options to the user (e.g., individual component status and component/system alarms).

The existing HSI requires operators to manipulate analog switches to implement a control action. To take a control action using the new HSI, the operator must (via the touch screen) select the appropriate activity (e.g.,

starting/initiating the system or changing the system line-up), select the component to be controlled (e.g., pump or valve), select the control action D-25

(e.g., start/stop or open/close), and execute the action.

HSI Assessment ProcessHFE Evaluation Commented [NEI73]: Addresses NRC comment A28.

Step 1. Identification of Which Four Generic Primary Tasks are Involved:

(1) Monitoring and detection (extracting information from the environment and recognizing when something changes) - INVOLVED (2) Situation assessment (evaluation of conditions) - INVOLVED (3) Response planning (deciding upon actions to resolve the situation) -

INVOLVED (4) Response implementation (performing an action) - INVOLVED Step 2. Assessment of the Modification Impacts on the Involved Generic Primary Tasks:

As part of the technical evaluation supporting the proposed modification, a HFE evaluation was performed. Commented [NEI74]: Not needed as it is clearly part of the HFE evaluation.

Tasks 1, 2 and 3 are involved (emphasizing that the modification includes a change to information presentation and organization, such that the indications/instruments are now consolidated and presented on customizable flat panel displays, rather than static analog control boards). With the new displays and display options available to the operators, the operators can choose which parameters to display and the organization of that information (e.g., by train/path). The HFE evaluation concluded that this modification could result in the operator choosing not to have certain parameters displayed; thus negatively impacting their ability to monitor the plant and detect changes. In addition, altering the information displayed and the organization of the information will negatively impact the operators understanding of how the information relates to system performance. This negative impact on understanding will also negatively impact the operators Commented [NEI75]: Addresses NRC comment A36.

ability to assess the situation and plan an appropriate response.

Task 4 is involved. The modification will require the operator to perform four actions in order to manipulate a control (i.e., 1. select the appropriate activity, 2. select the specific component to be controlled, 3. select the control action to be initiated, and 4. execute the action). Currently, the operator is able to manipulate a control in one action (e.g., turn a switch to on/off). The HFE evaluation determined that the modification negatively impacts the operators ability to respond because the modification increases the difficulty of implementing a response by requiring four actions instead of one action Commented [NEI76]: Addresses NRC comment A37.

and the additional actions result in an increase in the operators time to respond.

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Identification and Assessment of Design Functions Design Function Identification (a) Status indications are continuously available to the operator.

(b) The operator controls the system components manually.

The review of the UFSAR, including the assumptions described in the safety analysis, determined that an additional design function related to how design function (b) was performed exists . Namely, in the pertinent safety analysis, a response time requirement of the operator had been credited. Commented [NEI77]: Addresses NRC comment A39.

Screen Response The information available and the organization of that information in the new displays are customizable based on operator preference. Critical status indications may not be continuously available to the operator, thus there is an adverse impact (for the aspect being illustrated in this example) on design Commented [NEI78]: Addresses NRC comment A7.

function (a).

Using the touch screen, the operator is still able to perform design function (b) to manipulate the control for the systems components.

ThereforeHowever, there is an no adverse impact (for the aspect being illustrated in this example) on satisfaction of how design function (b) is Commented [NEI79]: Addresses NRC comment A7.

performed due to the increased response time.Since there is an adverse Commented [NEI80]: Addresses NRC comment A39.

impact on design function (a), the overall conclusion of the Screen for this consideration would be adverse. Commented [NEI81]: Not needed since the example only illustrates the aspect being discussed.

4.2.1.3 Screening Changes to UFSAR Methods of Evaluation By definition, a proposed activity involving a digital modification involves SSCs and how SSCs are operated and controlled, not a method of evaluation described in the UFSAR (see NEI 96-07, Section 3.10).

Methods of evaluation are analytical or numerical computer models used to determine and/or justify conclusions in the UFSAR (e.g., accident analyses that demonstrate the ability to safely shut down the reactor or prevent/limit radiological releases). These models also use "software." However, the software used in these models is separate and distinct from the software installed in the facility. The response to this Screen consideration should reflect this distinction.

A necessary revision or replacement of a method of evaluation (see NEI 96-07, Section 3.10) resulting from a digital modification is separate from the digital modification itself and the guidance in NEI 96-07, Section 4.2.1.3 applies.

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4.2.2 Is the Activity a Test or Experiment Not Described in the UFSAR?

By definition, a proposed activity involving a digital modification involves SSCs and how SSCs are operated and controlled, not a test or experiment (see NEI 96-07, Section 4.2.2). The response to this Screen consideration should reflect this characterization.

A necessary test or experiment (see NEI 96-07, Section 3.14) involving a digital modification is separate from the digital modification itself and the guidance in NEI 96-07, Section 4.2.2 applies.

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4.3 EVALUATION PROCESS CAUTION The guidance contained in this section of the appendix is intended to supplement the generic Evaluation guidance contained in the main body in NEI 96-07, Section 4.3. Namely, the generic Evaluation guidance provided in the main body of NEI 96-07 and the more-focused Evaluation guidance in this appendix BOTH apply to digital modifications.

Introduction Throughout this section, references to the main body of NEI 96-07, Rev. 1 will be identified as "NEI 96-07." Commented [NEI82]: Text moved to Section 1.5.

Guidance Focus In the following sections and sub-sections that describe the Evaluation guidance particularly useful for the application of 10 CFR 50.59 to digital modifications, each section and sub-section describes only a specific aspect, sometimes at the deliberate exclusion of other related aspects. This focused approach is intended to concentrate on the particular aspect of interest and does not imply that the other aspects do not apply or could not be related to the aspect being addressed. Commented [NEI83]: Text moved to Section 1.5.

Example Focus Examples are provided to illustrate the guidance provided herein. Unless stated otherwise, a given example only addresses the specific aspect or topic within the section/sub-section in which it is included, sometimes at the deliberate exclusion of other aspects or topics that, if considered, could potentially change the Evaluation conclusion. Commented [NEI84]: Text moved to Section 1.5.

Qualitative Assessment For digital I&C systems, reasonable assurance of low likelihood of failure is derived from a qualitative assessment of factors involving the design attributes of the modified SSC, the quality of the design processes, and the operating experience of the software and hardware used (i.e., product maturity and in-service experience). The qualitative assessment is used to record the factors and rationale and reasoning for making a determination that there is reasonable assurance that the digital I&C modification will exhibit a low likelihood of failure by considering the aggregate of these factors. Commented [NEI85]: Discussion moved to Definition 3.15. Addresses NRC comments A40 (incorporation of RIS SSC Failure Likelihood Determination Outcomes Supplement 1), A41 and A42.

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The possible outcomes of an engineering evaluation (e.g., qualitative assessment), performed in accordance with applicable Industry and/or NRC guidance documents, are as follows:

SSC failure likelihood is sufficiently low (as defined in Definition 3.15), or SSC failure likelihood is not sufficiently low.

If the SSC failure likelihood is determined to be sufficiently low, then by extension, the likelihood of software CCF is also considered to be sufficiently low.

If the failure likelihood of the modified SSC is not examined as part of an engineering evaluation, then the failure likelihood of the modified SSC will be assumed to be not sufficiently low for purposes of responding to the following 10 CFR 50.59 Evaluation criteria.

These possible outcomes (i.e., sufficiently low or not sufficiently low) will be used in developing the responses to Evaluation criteria 1, 2, 5 and 6. Commented [NEI86]: Discussion moved to Section 3.15.

Addresses NRC comments A41 and A43. Definition of 4.3.1 Does the Activity Result in More Than a Minimal Increase in the qualitative assessment added to Section 3.15 and expanded Frequency of Occurrence of an Accident? to include more guidance from Supplement 1.

INTRODUCTION From NEI 96-07, Section 3.2:

"The term 'accidents' refers to the anticipated (or abnormal) operational transients and postulated design basis accidents..."

Therefore, for purposes of 10 CFR 50.59, both Anticipated Operational Occurrences (AOOs) and Postulated Accidents (PAs) fall within the definition of "accident."

After applying the generic guidance in NEI 96-07, Section 4.3.1 to identify any accidents affected by the systems/components involved with the digital modification, and examining the initiators of those accidents,the impact on the frequency of the initiator (and, hence, the accident itself) due to the digital modification can be assessedthe change is examined to determine if the frequency of these accidents could increase due to the change. When addressing this Evaluation criterion for digital upgrades, the key issue is determining if the digital equipment can increase the frequency of initiating events that lead to the identified accidents. Commented [NEI87]: Addresses NRC comments A44 and A46.

All accident initiatorsinitiating events fall into one of two categories: Commented [NEI88]: Addresses NRC comments A44 and equipment-related or personnel-related. Therefore, the assessment of the A46.

impact of a digital modification also needs to consider both equipment-related and personnel-related sources.

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For a digital modification, the range of possible equipment-related sources of accident initiatorsinitiating events includes items unique to digital and items Commented [NEI89]: Addresses NRC comments A44 and A46.

not unique to digital. An example of an item unique to digital is consideration of the impact on accident frequency due to a software CCF, which will be addressed in this guidance. An example of a potential source of common cause failure that is not unique to digital is consideration of the impact on accident frequency due to the digital system's compatibility with the environment in which the system is being installed, which would be addressed by applying the general guidance related to meeting applicable regulatory requirements and other acceptance criteria to which the licensee is committed, and departures from standards as outlined in the general design criteria, as discussed in NEI 96-07, Section 4.3.1 and Section 4.3.1, Example 2. Commented [NEI90]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

For a digital modification, the assessment for personnel-related sources will consider the impact due to the Human-System Interface (HSI). Commented [NEI91]: Addresses NRC comment A54.

Typically, numerical values quantifying an accident frequency are not available, so the qualitative approach using the attributable (i.e., causal relationship) and the negligible/discernable (i.e., magnitude) criteriaguidance from NEI 96-07, Section 4.3.1 will be examinedapplied in this guidance.

The frequency of occurrence of an accident is directly related to the likelihood of failure of equipment that initiates the accident (e.g., an increase in the likelihood of a steam generator tube failure has a corresponding increase in the frequency of a steam generator tube rupture accident). Thus, an increase in the likelihood of failure of the modified equipment causes an increase in the frequency of the accident. Commented [NEI92]: Addresses NRC comment A43.

GUIDANCE Determination of Attributable (i.e., Causality)

NOTE: This guidance is not unique to digital and is the same as that provided in NEI 96-07, Section 4.3.1. This guidance is included here for completeness.

If none of the components/systems involved with the digital modification are identified as affecting an accident initiator previously identified in the UFSAR, then there is no attributable impact on the frequency of occurrence of an accident.

Alternately, if any component/system involved with the digital modification is identified as affecting an accident initiator previously identified in the UFSAR, then an impact on the frequency of occurrence of an accident can be attributed to the digital modification. If an attributable impact is identified, then further assessment to determine the magnitude of the impact will be performed.

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Examples 4-9 and 4-10 will illustrate the application of the attributable criterion.

Example 4-9 illustrates a case of NO attributable impact on the frequency of occurrence of an accident. Commented [NEI93]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

Example 4-9. NO ATTRIBUTABLE Impact on the Frequency of Occurrence of an Accident Proposed Activity Description Two safety-related containment chillers exist. There are two analog control systems (one per chiller) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Affected Accidents and Accident Initiators The review of the UFSAR accident analyses identified the Loss of Coolant Accident (LOCA) and Main Steam Line Break (MSLB) events as containing requirements related to the safety-related containment chillers. Specifically, the UFSAR states the following: "To satisfy single failure requirements, the loss of only one control system and its worst-case effect on the containment post-accident [emphasis added] environment due to the loss of one chiller has been considered in the LOCA and MSLB analyses."

Therefore, the affected accidents are LOCA and MSLB.

The UFSAR identified an equipment-related initiator for both accidents as being a pipe break. For LOCA, the pipe break occurs in a hot leg or a cold leg. For MSLB, the pipe break occurs in the main steam line exiting the steam generator.

Impact on Accident Frequency In these accidents, the safety-related containment chillers are not accident initiators (i.e., they are not pipe breaks). Furthermore, the chillers are only considered as part of accident mitigation; after the accidents have already occurred. Therefore, there is NO impact on the frequency of occurrence of the accidents that can be attributed to the digital modification. Commented [NEI94]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

Example 4-10 illustrates a case of an attributable impact on the frequency of occurrence of an accident. Commented [NEI95]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

Example 4-10. ATTRIBUTABLE Impact on the Frequency of Occurrence of an Accident D-32

Proposed Activity Description Two non-safety-related main feedwater pumps (MFWPs) exist, each with its own flow control valve. There are two analog control systems (one per MFWP and flow control valve combination) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Affected Accident and Accident Initiators The affected accident is the Loss of Feedwater event. The UFSAR identifies the equipment-related initiators as being the loss of one MFWP or the closure of one MFWP flow control valve.

Impact on Accident Frequency In this accident, the non-safety-related feedwater system is related to the accident initiators (i.e., loss of a MFWP and/or closure of a flow control valve).

Therefore, an impact on the frequency of occurrence of the accident can be attributed to the digital modification. (NOTE: The magnitude of the impact would be assessed next.) Commented [NEI96]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

Determination of Negligible/Discernable (i.e., Magnitude)Qualitative Assessment Outcome If the qualitative assessment outcome is sufficiently low, then there is NOT more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR.

If the qualitative assessment outcome is not sufficiently low, then there may be more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR. Commented [NEI97]: Addresses NRC comment A43.

NOTE: The guidance in this sub-section applies ONLY when an attributable impact on the frequency of occurrence of an accident has been established.

For proposed activities in which there is an attributable impact on the frequency of occurrence of an accident, the negligible/discernable portion of the criteria (i.e., magnitude) also needs to be assessed.

To determine the overall effect of the digital modification on the frequency of an accident, an engineering evaluation is performed. An engineering evaluation that uses a qualitative assessment to judge the failure likelihood of the modified SSC should consider each factor identified below:

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  • Design attributes employed
  • Quality of the design processes, and
  • Operating experience of the software and hardware used (i.e., product maturity and in-service experience). Commented [NEI98]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

Negligible:

To achieve a negligible conclusion, the engineering evaluation of each factor (e.g., as documented in a qualitative assessment) would conclude that the affected SSC will exhibit a sufficiently low likelihood of failure, and by extension, that the change in the accident frequency "...is so small or the uncertainties in determining whether a change in frequency has occurred are such that it cannot be reasonably concluded that the frequency has actually changed (i.e., there is no clear trend toward increasing the frequency)"1

[emphasis added]Therefore, if the qualitative assessment outcome is sufficiently low, there is not more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the UFSAR.

Discernable:

If the examination of each factor concludes that the change in the accident frequency exhibits a clear trend towards increasing the accident frequency exists, then a discernable increase in the accident frequency would exist. In this case, the software CCF likelihood cwould be sufficiently low or not sufficiently low. Commented [NEI99]: Addresses NRC comment A51.

AThe engineering evaluation (e.g., the qualitative assessment) is may also be used to determine if the discernible increase in the accident frequency is "more than minimal" or "NOT more than minimal." To achieve a conclusion of "NOT more than minimal," based on an examination of the factors considered in a qualitative assessment, the proposed activity must also continue to meet and/or satisfy all applicable NRC requirements, as well as design, material, and construction standards, to which the licensee is committed. Applicable requirements and standards include those selected by the licensee for use in the development of the proposed digital modification and documented within the design modification package.

Examples 4-11 and 4-12 illustrate the negligible/discernable portion (i.e.,

magnitude) of the criteria and assume the attributable portion of the criteria has been satisfied. Commented [NEI100]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

EXAMPLES 1 Refer to NEI 96-07, Section 4.3.1, Example 1.

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Example 4-119 illustrates a case with a negligible not more than a minimal change toincrease in the accident frequency.

Example 4-119. NEGLIGIBLENOT MORE THAN A MINIMAL Impact onIncrease in the Frequency of Occurrence of an Accident Proposed Activity Description Two non-safety-related main feedwater pumps (MFWPs) exist, each with its own flow control valve. There are two analog control systems (one per MFWP and flow control valve combination) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Magnitude ConclusionQualitative Assessment Outcome A qualitative assessment performed as part of the design processwas included in the engineering/technical information supporting the change,. The Commented [NEI101]: Addresses NRC comment A13.

qualitative assessment consideringed system design attributes, quality of the design processes employed, and operating experience of the proposed equipment, and concluded that the failure likelihood ofintroduced by the modified SSC is sufficiently low. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

All applicable requirements and other acceptance criteria to which the licensee is committed, as well as applicable design, material and construction standards, continue to be met.

Therefore, the change in the frequency of occurrence of the Loss of Feedwater event is negligible due to the effect of the factors considered in the qualitative assessment.

Overall Conclusion Although an attributable impact on the frequency of occurrence of the Loss of Feedwater event was determined to exist, there was no clear trend toward increasing the frequency. With no clear trend toward increasing the frequency, there is not more than a minimal increase in the frequency of occurrence of the accident due to the digital modification.With the failure likelihood introduced by the modified SSC being sufficiently low, there is not more than a minimal increase in the frequency of occurrence of an Commented [NEI102]: Addresses NRC comment A40 accident previously evaluated in the UFSAR (for the aspect being illustrated (expansion/paraphrasing of generic guidance) and incorporates the suggested language from NRC comment in this example) A69.

Commented [NEI103]: Addresses NRC comment A7.

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Example 4-120 illustrates a case with a discernablemore than a minimal increase toin the accident frequency.

Example 4-120. DISCERNABLEMORE THAN A MINIMAL Increase in the Frequency of Occurrence of an Accident Proposed Activity Description Same as Example 4-119.

Magnitude ConclusionQualitative Assessment Outcome Based on the qualitative assessment performed as part of the technical assessment supporting this digital modification, the likelihood of failure causing the loss of both feedwater control systems (resulting in the loss of both MFWPs) has been determined to be not sufficiently low.

All applicable requirements and other acceptance criteria to which the licensee is committed, as well as applicable design, material and construction standards, continue to be met.

The change in the frequency of occurrence of the Loss of Feedwater event is discernable due to the effect of the factors considered in the qualitative evaluation. A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative Commented [NEI104]: Addresses NRC comment A13.

assessment considered system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSC is not sufficiently low. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

Overall Conclusion An attributable impact on the frequency of occurrence of the Loss of Feedwater event was determined to exist and there is a clear trend towards increasing the frequency. The clear trend toward increasing the frequency (i.e., the discernable increase) is due to the software CCF likelihood being not sufficiently low.

However, even with a clear trend towards increasing the frequency, the assessments and conclusions documented in the qualitative assessment of the considered factors and the satisfaction of applicable requirements and other acceptance criteria to which the licensee is committed, as well as applicable design, material and construction standards, there is NOT more than a minimal increase in the frequency of occurrence of the accident due to the digital modification.As documented in the qualitative assessment, the features of the design process and operating experience were insufficient to offset weaknesses in the design attributes that were available to prevent D-36

certain failures. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

With the failure likelihood introduced by the modified SSC being not sufficiently low and the inability to offset weaknesses in the design attributes, there is more than a minimal increase in the frequency of occurrence of the accident previously evaluated in the UFSAR (for the aspect Commented [NEI105]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance) and being illustrated in this example) . incorporates the suggested language from NRC comment A69.

Commented [NEI106]: Addresses NRC comment A7.

HUMAN-SYSTEM INTERFACE ASSESSMENT If no personnel-based initiators involving degraded operator performance (e.g., operator error) are identified among the accident initiators, then an increase in the frequency of the accident cannot occur due to the Human-System Interface portion of the digital modification. Otherwise, the application of the attributable criterion (i.e., causality) and the negligible/discernable criterion (i.e., magnitude) are assessed utilizing the guidance described in NEI 96-07, Section 4.3.1. Commented [NEI107]: Addresses NRC comment A54.

4.3.2 Does the Activity Result in More Than a Minimal Increase in the Likelihood of Occurrence of a Malfunction of an SSC Important to Safety?

INTRODUCTION After applying the generic guidance in NEI 96-07, Section 4.3.2 to identify any malfunctions affected by the systems/components involved with the digital modification, and examining the initiators of those malfunctions, the impact on the likelihood of the initiator (and, hence, the malfunction itself) due to the digital modification can be assessedthe change is examined to determine if the likelihood of these malfunctions could increase due to the change. When addressing this Evaluation criterion for digital upgrades, the key issue is determining if the digital equipment can increase the likelihood of initiating events that lead to the identified malfunctions. Commented [NEI108]: Addresses NRC comments A44 and A46.

All malfunction initiatorsinitiating events fall into one of two categories: Commented [NEI109]: Addresses NRC comments A44 equipment-related or personnel-related. Therefore, the assessment of the and A46.

impact of a digital modification also needs to consider both equipment-related and personnel-related sources.

For a digital modification, the range of possible equipment-related sources of malfunction initiatorsinitiating events includes items unique to digital and Commented [NEI110]: Addresses NRC comments A44 and A46.

items not unique to digital. An example of an item unique to digital is consideration of the impact on malfunction likelihood due to a software CCF, which will be addressed in this guidance. An example of a potential source of D-37

common cause failure that is not unique to digital is consideration of the impact on malfunction likelihood due to the digital system's compatibility with the environment in which the system is being installed, which would be addressed by applying the general guidance related to meeting applicable regulatory requirements and other acceptance criteria to which the licensee is committed, and departures from standards as outlined in the general design criteria, as discussed in NEI 96-07, Section 4.3.2. Commented [NEI111]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

For a digital modification, the assessment for personnel-related sources will consider the impact due to the Human-System Interface (HSI). Commented [NEI112]: Addresses NRC comment A54.

Typically, numerical values quantifying a malfunction likelihood are not available, so the qualitative approach using the attributable (i.e., causal relationship) and the negligible/discernable (i.e., magnitude) criteriaguidance from NEI 96-07, Section 4.3.2 will be examinedapplied in this guidance.

The likelihood of occurrence of a malfunction of an SSC important to safety is directly related to the likelihood of failure of equipment that causes a failure of SSCs to perform their intended design functions [e.g., an increase in the likelihood of failure of an auxiliary feedwater (AFW) pump has a corresponding increase in the likelihood of occurrence of a malfunction of SSCs (i.e., the AFW pump and the AFW system)]. Thus, an increase in the likelihood of failure of the modified equipment that causes the failure of an SSC to perform its intended design functions is directly related to the likelihood of the occurrence of a malfunction of an SSC important to safety. Commented [NEI113]: Addresses concerns identified in NRC comments A43 and A51.

GUIDANCE Impact on Redundancy, Diversity, Separation or Independence As discussed in NEI 96-07, Section 4.3.2, Example 6, a proposed activity that reduces redundancy, diversity, separation or independence of the design function(s) is considered more than a minimal increase in the likelihood of a malfunction and requires prior NRC approval. However, licensees may reduce excess redundancy, diversity, separation or independence of design function(s) (if any) to the level credited in the safety analyses without prior NRC approval.

To ensure consistent application of this guidance, each of these characteristics is reviewed below.

Redundancy:

"Redundancy" means two or more SSCs performing the same design function.

The introduction of the exact same software into redundant channels and the potential creation of a software CCF has no impact on an SSCs' redundancy because the SSCs perform the same design function(s) before the introduction of software as they will after the introduction of software.

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Diversity:

"Diversity" is not defined within the regulations as a stand-alone term. The term is defined within the context of GDC 22, as follows:

"Criterion 22 -- Protection system independence. The protection system shall be designed to assure that the effects of natural phenomena, and of normal operating, maintenance, testing, and postulated accident conditions on redundant channels do not result in loss of the protection function, or shall be demonstrated to be acceptable on some other defined basis. Design techniques, such as functional diversity or diversity in component design and principles of operation, shall be used to the extent practical to prevent loss of the protection function."

[emphasis added]

Therefore, "diversity" is addressed in terms of functional or component design and principles of operation.

The introduction of the exact same software and the potential creation of a software CCF into single-failure proof channels, or merely redundant channels, has no impact on diversity because the channels were not initially diverse. Namely, each of the channels used the same principles of operation and they all contained identical components. Thus, the channels were identical before the introduction of software and will remain identical after the introduction of software.

Separation:

"Separation" refers to physical arrangement to provide missile protection, or to eliminate or minimize the detrimental impacts due to fires, floods, etc.

The introduction of the exact same software and the potential creation of a software CCF does not impact the physical arrangement of SSCs.

Independence:

"Independence" means non-interaction of SSCs.

Assuming that no interactions (e.g., communication between multiple applications of the software) exist, the introduction of the exact same software and the potential creation of a software CCF does not impact the independence of SSCs. However, the failure of such software due to a software CCF is possible and is addressed in Evaluation criterion #5 and/or

  1. 6. Commented [NEI114]: Addresses NRC comments A56 through A64.

Determination of Attributable (i.e., Causality)

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NOTE: This guidance is not unique to digital and is the same as that provided in NEI 96-07, Section 4.3.2. This guidance is included here for completeness.

If none of the components/systems involved with the digital modification are identified as affecting a malfunction initiator previously identified in the UFSAR, then there is no attributable impact on the likelihood of occurrence of a malfunction.

Alternately, if any components/systems involved with the digital modification are identified as affecting a malfunction initiator previously identified in the UFSAR, then an impact on the likelihood of occurrence of a malfunction can be attributed to the digital modification. If an attributable impact is identified, then further assessment to determine the magnitude of the impact will be performed.The possibility exists that a proposed activity can cause a previously incredible event to become credible.

Example 4-131 illustrates a case of an attributable impact on the likelihood of occurrence of a malfunctionin which a previously incredible event has become credible due to a digital modification. Commented [NEI115]: Addresses NRC comments A40 (expansion/paraphrasing of generic guidance) and A65.

Example 4-131. ATTRIBUTABLE Impact on the Likelihood of Occurrence of a Malfunction Proposed Activity Description Two safety-related containment chillers exist. There are two analog control systems (one per chiller) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Affected Malfunctions and Malfunction Initiators The affected malfunction is the failure of a safety-related containment chiller to provide its cooling design function. The UFSAR identifies three specific equipment-related initiators of a containment chiller malfunction: (1) failure of the Emergency Diesel Generator (EDG) to start (preventing the EDG from supplying electrical power to the containment chiller it powers), (2) an electrical failure associated with the chiller system (e.g., feeder breaker failure), and (3) a mechanical failure within the chiller itself (e.g., flow blockage). The UFSAR also states that the single failure criteria were satisfied because two chillers were provided and there were no common malfunction sources.

Impact on Malfunction Likelihood D-40

Although the safety-related chiller control system is not one of the three malfunction initiators identified in the UFSAR, a new common malfunction source has been introduced due to the potential for a software common cause failure from the exact same software being used in both digital control systems. A common malfunction initiator was previously considered, but was concluded to be non-existent. However, this conclusion is no longer valid.

Therefore, an impact on the likelihood of occurrence of the malfunction due to the digital modification has occurred. (NOTE: The magnitude of the impact would then need to be assessed.) Commented [NEI116]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

Determination of Negligible/Discernable (i.e., Magnitude)

Qualitative Assessment Outcome If the qualitative assessment outcome is sufficiently low, then there is NOT more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. Commented [NEI117]: Addresses generic concerns identified in NRC comments A43 and A51.

If the qualitative assessment outcome is not sufficiently low, then there may be more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. Commented [NEI118]: Addresses generic concerns identified in NRC comments A43, A51 and A66 and A67.

NOTE: The guidance in this sub-section applies ONLY when an attributable impact on the likelihood of occurrence of a malfunction has been established.

For proposed activities in which there is an attributable impact on the likelihood of occurrence of a malfunction, the negligible/discernable portion of the criteria (i.e., magnitude) also needs to be assessed.

To determine the overall effect of the digital modification on the likelihood of a malfunction, an engineering evaluation is performed. An engineering evaluation that uses a qualitative assessment to judge the failure likelihood of the modified SSC should consider each factor identified below:

Design attributes employed Quality of the design processes, and Operating experience of the software and hardware used (i.e., product maturity and in-service experience). Commented [NEI119]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

Negligible:

To achieve a negligible conclusion, the engineering evaluation of each factor (e.g., as documented in a qualitative assessment) would conclude that the affected SSC will exhibit a sufficiently low likelihood of failure, and by extension, that the change in the malfunction likelihood "...is so small or the uncertainties in determining whether a change in likelihood has occurred are D-41

such that it cannot be reasonably concluded that the likelihood has actually changed (i.e., there is no clear trend toward increasing the likelihood)"2

[emphasis added] and the qualitative assessment outcome for a software CCF will be sufficiently low.

Therefore, if the qualitative assessment outcome is sufficiently low, there is not more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR. Commented [NEI120]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

Discernable:

If the examination of each factor concludes that the change in the malfunction likelihood exhibits a clear trend towards increasing the malfunction likelihood exists, then a discernable increase in the malfunction likelihood would exist. In this case, the software CCF likelihood cwould be sufficiently low or not sufficiently low. Commented [NEI121]: Addresses NRC comments A66 and A67.

AThe engineering evaluation (e.g., the qualitative assessment) ismay also be used to determine if the discernible increase in the malfunction likelihood is "more than minimal" or "NOT more than minimal." To achieve a conclusion of "NOT more than minimal," based on an examination of the factors considered in a qualitative assessment, the proposed activity must also continue to meet and/or satisfy all applicable NRC requirements, as well as design, material, and construction standards, to which the licensee is committed. Applicable requirements and standards include those selected by the licensee for use in the development of the proposed digital I&C design modification and documented within the design modification package.

Examples 4-14 and 4-15 illustrate the negligible/discernable portion (i.e.,

magnitude) of the criteria and assume the attributable portion of the criteria has been satisfied. Commented [NEI122]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

EXAMPLES Example 4-142 illustrates a case with a negligible changenot more than a minimal increase to in the malfunction likelihood.

Example 4-142. NEGLIGIBLE ImpactNOT MORE THAN A MINIMAL Increase in the Likelihood of Occurrence of a Malfunction Proposed Activity Description Two non-safety-related main feedwater pumps (MFWPs) exist, each with its own flow control valve. There are two analog control systems (one per MFWP 2 Refer to NEI 96-07, Section 4.3.2, 4th paragraph.

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and flow control valve combination) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Magnitude ConclusionQualitative Assessment Outcome A qualitative assessment performed as part of the design processwas included in the engineering/technical information supporting the change,. The Commented [NEI123]: Addresses NRC comment A13.

qualitative assessment consideringed system design attributes, quality of the design processes employed, and operating experience of the proposed equipment, and concluded that the failure likelihood ofintroduced by the modified SSC is sufficiently low. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

All applicable requirements and other acceptance criteria to which the licensee is committed, as well as applicable design, material and construction standards, continue to be met.

Therefore, the change in the likelihood of occurrence of the loss of a MFWP or the closure of a MFWP flow control valve initiated by the failure of a feedwater control system is negligible due to the effect of the factors considered in the qualitative assessment.

Overall Conclusion Although an attributable impact on the likelihood of occurrence of the loss of a MFWP or the closure of a MFWP flow control valve was determined to exist, there was no clear trend toward increasing the likelihood. With no clear trend toward increasing the likelihood, there is not more than a minimal increase in the likelihood of occurrence of the malfunctions due to the digital modification.With the failure likelihood introduced by the modified SSC being sufficiently low, there is not more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety previously evaluated in the UFSAR (for the aspect being illustrated in this Commented [NEI124]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance) and example). incorporates the suggested language from NRC comment A69.

Example 4-153 illustrates a case with a discernablemore than a minimal Commented [NEI125]: Addresses NRC comment A7.

increase toin the malfunction likelihood.

Example 4-153. DISCERNABLE MORE THAN A MINIMAL Increase in the Likelihood of Occurrence of a Malfunction D-43

Proposed Activity Description Two safety-related main control room chillers exist. There are two analog control systems (one per chiller) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

The logic components/system and controls for the starting and operation of the safety injection pumps are located within the main control room boundary. The environmental requirements associated with the logic components/system and controls are maintained within their allowable limits by the main control room cooling system, which includes the chillers involved with this digital modification.

Affected Malfunction and Malfunction Initiator The review of the UFSAR accident analyses identified several events for which the safety injection pumps are assumed to start and operate (as reflected in the inputs and assumptions tofor the accident analyses).

In each of these events, the UFSAR states the following: "To satisfy single failure requirements, the loss of only one chiller control system and its worst-case effect on the event due to the loss of one chiller has been considered in the accident analyseis."

Magnitude ConclusionQualitative Assessment Outcome Based on the qualitative assessment performed as part of the technical assessment supporting this digital modification, the likelihood of a failure impacting both chiller control systems has been determined to be not sufficiently low.

A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered Commented [NEI126]: Addresses NRC comment A13.

system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSC is not sufficiently low.

For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

The changeAn increase in the likelihood of occurrence of the malfunction of both safety injection pumps is discernable due to the outcome of the qualitative assessment. Specifically, occurs since the single failure criteria are no longer met.

D-44

Overall Conclusion An attributable impact on the likelihood of occurrence of the malfunction of both safety injection pumps was determined to exist and there is a clear trend toward increasing the likelihood. The clear trend toward increasing the likelihood (i.e., the discernable increase) is due to the failure being not sufficiently low which, in this case, causes single failure criteria to not be satisfied.

With a clear trend toward increasing the likelihood and failure to satisfy single failure criteria, there is more than a minimal increase in the likelihood of occurrence of the malfunction of both logic components/system and controls for the starting and operation of the safety injection pumps due to the digital modification. As documented in the qualitative assessment, the features of the design process and operating experience were insufficient to offset weaknesses in the design attributes that were available to prevent certain failures. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

With the failure likelihood introduced by the modified SSC being not sufficiently low and the inability to offset weaknesses in the design attributes, there is more than a minimal increase in the likelihood of occurrence of a malfunction previously evaluated in the UFSAR (for the Commented [NEI127]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance) and aspect being illustrated in this example). incorporates the suggested language from NRC comment A69.

Commented [NEI128]: Addresses NRC comment A7.

HUMAN-SYSTEM INTERFACE ASSESSMENT If no personnel-based initiators involving degraded operator performance (e.g., operator error) are identified among the malfunction initiators, then an increase in the likelihood of the malfunction cannot occur due to the Human-System Interface portion of the digital modification. Otherwise, the application of the attributable criterion (i.e., causality) and the negligible/discernable criterion (i.e., magnitude) are assessed utilizing the guidance described in NEI 96-07, Section 4.3.2. Commented [NEI129]: Addresses NRC comment A54.

4.3.3 Does the Activity Result in More Than a Minimal Increase in the Consequences of an Accident?

There is no unique guidance applicable to digital modifications for responding to this Evaluation criterion because the identification of affected accidents and dose analysis inputs and/or assumptions are not unique for a digital modification. The guidance in NEI 96-07, Section 4.3.3 applies.

D-45

4.3.4 Does the Activity Result in More Than a Minimal Increase in the Consequences of a Malfunction?

There is no unique guidance applicable to digital modifications for responding to this Evaluation criterion because the identification of the affected malfunctions and dose analysis inputs and/or assumptions are not unique for a digital modification. The guidance in NEI 96-07, Section 4.3.4 applies.

4.3.5 Does the Activity Create a Possibility for an Accident of a Different Type?

INTRODUCTION From NEI 96-07, Section 3.2:

"The term 'accidents' refers to the anticipated (or abnormal) operational transients and postulated design basis accidents..."

Therefore, for purposes of 10 CFR 50.59, both Anticipated Operational Occurrences (AOOs) and Postulated Accidents (PAs) fall within the definition of "accident."

Accidents of a different type are caused by failures of equipment that initiate an accident of a different type. Commented [NEI130]: Addresses NRC comment A68.

GUIDANCE From NEI 96-07, Section 4.3.5, the two considerations that need to be assessed when answering this Evaluation question are as likely to happen as and the impact on the accident analysesthe manner in which the safety analysis will account for the effects of the failure (i.e., a new analysis will be required or a revision to a current analysis is possiblewhich is discussed in more detail below). For brevity, the second consideration will hereafter be referred to as the "safety analysis manner of accounting."

GUIDANCE Determination of "As Likely To Happen As" From NEI 96-07, Section 4.3.5:

"The possible accidents of a different type are limited to those that are as likely to happen as those previously evaluated in the UFSAR. The accident must be credible in the sense of having been created within the range of assumptions previously considered in the licensing basis (e.g.,

random single failure, loss of off-site power, etc.)." Commented [NEI131]: Addresses NRC comment A40 (expansion/paraphrasing of generic guidance).

If the failure likelihood of the modified SSC is determined to be sufficiently low, then the activity does not introduce any failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different D-46

type. Therefore, the activity does not create a possibility for an accident of a different type than any previously evaluated in the UFSAR.

Alternately, if the failure likelihood of the modified SSC is determined to be not sufficiently low, then the activity does introduce failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different type. In this case, further assessment to determine the impact on the accident analysis is to be performed.If the outcome of the qualitative assessment is sufficiently low, then the activity does not introduce any failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different type. Therefore, the activity does not create a possibility for an accident of a different type than any previously evaluated in the UFSAR.

If the outcome of the qualitative assessment is not sufficiently low, then the activity may introduce failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different type. For these cases, this Evaluation criterion also needs to consider the safety analysis manner of accocunting. Commented [NEI132]: Addresses NRC comments A43 and A68 through A71.

Determination of AccidentSafety Analysis ImpactManner of Accounting NOTE: This guidance is not unique to digital and is the same as that provided in NEI 96-07, Section 4.3.5, as clarified in RG 1.187. Commented [NEI133]: Addresses NRC comment A72.

For the cases in which the creation of a possibility for an accident of a different type is as likely to happen as those in the UFSAR the outcome of the qualitative assessment is not sufficiently low), the accidentsafety analysis Commented [NEI134]: Addresses NRC comment A69.

impactmanner of accounting also needs to be assessed to determine whetherif the accident is, in fact, a different type.

There are two possible impactsmanners of accounting on thein a accidentsafety analysis:

(1) a revision to an existing safety analysis is possible, or (2) a new safety analysis will be required because the effect on the plant is different than any previously evaluated in the UFSAR.

Accidents of a different type are accidents that are as likely to happen as those in the UFSAR for which a new accidentsafety analysis would be needed, not just a revision of a current accidentsafety analysis.

EXAMPLES Example 4-164 illustrates the NO CREATION of the possibility of an accident of a different type case.

Example 4-164. NO CREATION of the Possibility of an Accident of a D-47

Different Type Proposed Activity Two non-safety-related main feedwater pumps (MFWPs) exist, each with its own flow control valve. There are two analog control systems (one per MFWP and flow control valve combination) that are physically and functionally the same.

Each analog control system will be replaced with a separate digital control system. The hardware platform for each digital control system is from the same supplier and the software in each digital control system is exactly the same.

Malfunction / Accident Initiator The malfunction/accident initiator identified in the UFSAR for the analog main feedwater control system is the loss of one main feedwater pump (out of two pumps) due to the loss of one feedwater control system.

Accident Frequency and Type The pertinent accident is the Loss of Feedwater event. The characteristics of the Loss of Feedwater event are as follows:

Type of Accident - Decrease in Heat Removal by the Secondary System Accident Category - Infrequent Incident Commented [NEI135]: Addresses NRC comment A73.

As Likely to Happen As ConclusionQualitative Assessment Outcome Based on the qualitative assessment performed as part of the technical assessment supporting this digital modification, the failure likelihood of the modified SSC, causing the loss of both feedwater control systems (resulting in the loss of both MFWPs) has been determined to be sufficiently low.

A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered Commented [NEI136]: Addresses NRC comment A13.

system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSC is sufficiently low. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X. Commented [NEI137]: Addresses NRC comments A73 and A74.

Conclusion Therefore, in this case, the creation of a possibility for an accident of a different type is NOT as likely to happen as those in the UFSAR and there is no need to determine the accident analysis impact.With the failure likelihood introduced by the modified SSC being sufficiently low, the activity does not D-48

introduce any failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different type. Therefore, the activity does not create a possibility for an accident of a different type than any previously evaluated in the UFSAR (for the aspect being illustrated in this example). Commented [NEI138]: Addresses NRC comments A73 and A74.

Commented [NEI139]: Addresses NRC comment A7.

Example 4-175 illustrates the CREATION of the possibility of an accident of a different type case.

Example 4-175. CREATION of the Possibility of an Accident of a Different Type Proposed Activity Two non-safety-related analog feedwater control systems and one non-safety-related main turbine steam-inlet valves analog control system exist.

The two feedwater control systems and the one main turbine steam-inlet valves control system will be combined into a single digital control system.

Qualitative Assessment Outcome A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered Commented [NEI140]: Addresses NRC comment A13.

system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSC is not sufficiently low.

For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

Malfunction / Accident InitiatorIdentification The identifiedUFSAR describes the following feedwater control system malfunctions include: (a) failures causing the loss of all feedwater to the steam generators, which is [evaluated in the Loss of Feedwater event], and (b) failures causing an increase in main feedwater flow to the maximum output from both MFWPs, which is [evaluated in the Excess Feedwater event].

The identifiedUFSAR describes the following main turbine steam-inlet valve control system malfunctions include: (a) all valves going fully closed causing no steam to be admitted into the turbine, which is [evaluated in the Loss of Load event], and (b) all valves going fully open causing excess steam to be admitted into the turbine, which is [evaluated in the Excess Steam Demand event].

Therefore, the impact of the failures that are as likely to happen as those in the UFSAR that can initiate an accident of a different type will be assessed for the following accident analyses:

D-49

(1) Loss of Feedwater (2) Excess Feedwater (3) Loss of Load (4) Excess Steam Demand Accident Frequency and Type The characteristics of the pertinent accidents are as follows:

Loss of Feedwater:

Type of Accident - Decrease in Heat Removal by the Secondary System Accident Category - Infrequent Incident Excess Feedwater:

Type of Accident - Increase in Heat Removal by the Secondary System Accident Category - Moderate Frequency Incident Loss of Load:

Type of Accident - Decrease in Heat Removal by the Secondary System Accident Category - Moderate Frequency Incident Excess Steam Demand:

Type of Accident - Increase in Heat Removal by the Secondary System Accident Category - Moderate Frequency Incident As Likely to Happen As Conclusion Based on the qualitative assessment performed as part of the technical assessment supporting this digital modification, the failure likelihood of the modified SSC impacting both the feedwater control systems and the main turbine steam-inlet valves control system has been determined to be not sufficiently low.

Safety Analysis Manner of Accounting Assessment Therefore, in this case, tThe following conditionsevents and combination of events are as likely to happen as those in the UFSAR, creating a possibility for several accidentswill be assessed:

(1A) Loss of both feedwater pumps in the Loss of Feedwater accident analysis (2B) Increase in main feedwater flow to the maximum output from both D-50

MFWPs. in the Excess Feedwater accident analysis (3C) All main turbine steam-inlet valves going fully closed in the Loss of Load accident analysis (4D) All main turbine steam-inlet valves going fully open in the Excess Steam Demand accident analysis (5E) Combination of (1)a Loss of Feedwater event and (3)a Loss of Load event (6F) Combination of (1)a Loss of Feedwater event and (4)an Excess Steam Demand event (7G) Combination of (2)an Excess Feedwater event and (3)a Loss of Load event (8H) Combination of (2)an Excess Feedwater event and (4)an Excess Steam Demand event Accident Analysis Impact Conclusion ConditionsEvents (1A) though (4D) are already considered in the safetyaccident analyses, so a revisions to an existing accident analysies isare possible. Thus, conditionsevents (1A) through (4D) aredo NOT create the possibility of an accidents of a different type (for the aspect being illustrated Commented [NEI141]: Addresses NRC comment A75.

in this example). Commented [NEI142]: Addresses NRC comment A7.

The current set of accidents identified in the safetyaccident analyses does not consider athe simultaneous Feedwater events (i.e., Loss of Feedwater or Excess Feedwater) with a Main Steam event (i.e., Excess Steam Demand or Loss of Load). represented by events (E) through (H).

Condition (5) still causes a decrease in heat removal by the secondary system.

Condition (6) involves both a decrease and an increase in heat removal by the secondary system.

Condition (7) involves both a decrease and an increase in heat removal by the secondary system.

Condition (8) still causes an increase in heat removal by the secondary system.Therefore, Conditionsevents (5E) though (8H) will require new accident analyses to be performed. As such, conditions (5) though (8) are and create the possibility of accidents of a different type (for the Commented [NEI143]: Addresses NRC comment A75 aspect being illustrated in this example). Therefore, the proposed Commented [NEI144]: Addresses NRC comment A7.

activity does create the possibility of accidents of a different type.

HUMAN-SYSTEM INTERFACE ASSESSMENT D-51

If no personnel-based initiators involving degraded operator performance (e.g., operator error) are identified as accident initiators, then the creation of a possibility for an accident of a different type cannot occur due to the Human-System Interface portion of the digital modification. Otherwise, the creation of a possibility for an accident of a different type is assessed utilizing the guidance described in NEI 96-07, Section 4.3.5. Commented [NEI145]: Addresses NRC comment A54.

4.3.6 Does the Activity Create a Possibility for a Malfunction of an SSC Important to Safety with a Different Result?

INTRODUCTION NOTE: Due to the unique nature of digital modifications, and the inherent complexities therein, the application of this criterion is especially important. Specifically, the unique aspect of concern is the potential for a software CCF to create the possibility for a malfunction with a different result. Therefore, rather than simply providing simplistic supplemental guidance to that already included in NEI 96-07, Section 4.3.6, more detailed guidance will be provided in this section.

However, none of the more detailed guidance provided in this section conflicts with that provided in NEI 96-07, Section 4.3.6, or should be construed as being new, or modified from that in NEI 96-07, Section 4.3.6.

Review To ensure the unique aspects of digital modifications are addressed correctly and adequately, a review of selected discussions and excerpts from NEI 96-07, including malfunctions, design functions, and safety analyses, is presented first.

CAUTION: The following review summaries are intended for general understanding only. For complete discussions of each term, see the references identified for each term.

From NEI 96-07, Section 3.9:

Malfunction of SSCs important to safety means the failure of SSCs to perform their intended design functions described in the UFSAR (whether or not classified as safety-related in accordance with 10 CFR 50, Appendix B). [emphasis added]

From NEI 96-07, Section 3.3:

Design functions are UFSAR-described design bases functions and other SSC functions described in the UFSAR that support or impact design bases functions... [emphasis added]

Also, D-52

Design bases functions are functions performed by systems, structures and components (SSCs) that are (1) required by, or otherwise necessary to comply with, regulations, license conditions, orders or technical specifications, or (2) credited in licensee safety analyses to meet NRC requirements. [emphasis added]

Furthermore, Design functions...include functions that, if not performed, would initiate a transient or accident that the plant is required to withstand. [emphasis added]

Finally, As used above, credited in the safety analyses means that, if the SSC were not to perform its design bases function in the manner described, the assumed initial conditions, mitigative actions or other information in the analyses would no longer be within the range evaluated (i.e., the analysis results would be called into question). The phrase support or impact design bases functions refers both to those SSCs needed to support design bases functions (cooling, power, environmental control, etc.) and to SSCs whose operation or malfunction could adversely affect the performance of design bases functions (for instance, control systems and physical arrangements).

Thus, both safety-related and nonsafety-related SSCs may perform design functions. [emphasis added]

This definition is oriented around the definition of design bases function, which itself is defined in NEI 97-04, Appendix B, Guidelines and Examples for Identifying 10 CFR 50.2 Design Bases, endorsed by Regulatory Guide 1.186, and highlighted in bold above.

A more complete understanding of the meaning of a design basis function can be obtained by examination of NEI 97-04, Appendix B. From NEI 97-04, the three characteristics of design bases functions are summarized as follows:

1. Design bases functions are credited in the safety analyses.
2. The functions of any individual SSC are functionally below that of a design basis function.
3. Design bases functions are derived primarily from the General Design Criteria.

Repeating a portion from above to highlight the importance of identifying the design basis function and its connection to a safety analysis result, we have the following:

As used above, credited in the safety analyses means that, if the SSC were not to perform its design bases function in the D-53

manner described, the assumed initial conditions, mitigative actions or other information in the analyses would no longer be within the range evaluated (i.e., the analysis results would be called into question). [emphasis added]

Then, from NEI 96-07, Section 3.12:

Safety analyses are analyses performed pursuant to NRC requirements to demonstrate the integrity of the reactor coolant pressure boundary, the capability to shut down the reactor and maintain it in a safe shutdown condition, or the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guidelines in 10 CFR 50.34(a)(1) or 10 CFR 100.11...and include, but are not limited to, the accident analyses typically presented in Chapter 15 of the UFSAR. [emphasis added]

And from the first sentence of the associated discussion:

Safety analyses are those analyses or evaluations that demonstrate that acceptance criteria for the facilitys capability to withstand or respond to postulated events are met.

[emphasis added]

Also included in the definition of safety analyses are supporting UFSAR analyses that demonstrate that SSC design functions will be accomplished as credited in the accident analyses. Commented [NEI146]: Addresses NRC comment A78.

Failure Modes and Effects Analysis (FMEA)

NEI 96-07, Section 4.3.6 recognizes that the effect of a proposed modification must be assessed. This assessment may require the use of a failure modes and effects analysis (FMEA), including the possible creation of a new FMEA.

From NEI 96-07, Section 4.3.6:

In evaluating a proposed activity against this criterion, the types and results of failure modes of SSCs that have previously been evaluated in the UFSAR and that are affected by the proposed activity should be identified. This evaluation should be performed consistent with any failure modes and effects analysis (FMEA) described in the UFSAR, recognizing that certain proposed activities may require a new FMEA to be performed. [emphasis added]

Overall Perspective NEI 96-07, Section 4.3.6 provides the overall perspective on this Evaluation criterion with its first sentence, which states:

D-54

Malfunctions of SSCs are generally postulated as potential single failures to evaluate plant performance with the focus being on the result of the malfunction rather than the cause or type of malfunction.

Expanding upon this foundation, the following conclusion is reached, which is based upon discussion from 63 FR 56106:

Unless the equipment would fail in a way not already evaluated in the safety analysis, there can be no malfunction of an SSC important to safety with a different result. [emphasis added]

GUIDANCE From NEI 96-07, Section 4.3.6, there are two considerations that need to be assessed when answering this criterion:Evaluation question are as likely to happen as and the impact on the safety analysis result.

GUIDANCE Determination of "As Likely to Happen As" From NEI 96-07, Section 4.3.6:

The possible malfunctions with a different result are limited to those that are as likely to happen as those described in the UFSARa proposed change or activity that increases the likelihood of a malfunction previously thought to be incredible to the point where it becomes as likely as the malfunctions assumed in the UFSAR could create a possible malfunction with a different result. [emphasis added]

If the outcome of the qualitative assessment is sufficiently low, then the activity does not introduce any failures that are as likely to happen as those in the UFSAR. Therefore, the activity does not create a possibility for a malfunction of an SSC important to safety with a different result from any previously evaluated in the UFSAR.

If the outcome of the qualitative assessment is not sufficiently low, then the activity may introduce failures that are as likely to happen as those in the UFSAR that can create a possibility for a malfunction of an SSC important to safety with a different result from any previously evaluated in the UFSAR.

For these cases, this Evaluation criterion also needs to consider the impact of this potential failure on the safety analysis result using assumptions consistent with the plants UFSAR. Commented [NEI147]: Addresses NRC comment A43.

From NEI 96-07, Section 4.3.6:

The possible malfunctions with a different result are limited to those that are as likely to happen as those described in the UFSARa D-55

proposed change or activity that increases the likelihood of a malfunction previously thought to be incredible to the point where it becomes as likely as the malfunctions assumed in the UFSAR could create a possible malfunction with a different result. [emphasis added]

If the failure likelihood of the modified SSC is determined to be sufficiently low, then the activity does not introduce any failures that are as likely to happen as those in the UFSAR. Therefore, the activity does not create a possibility for a malfunction of an SSC important to safety with a different result from any other previously evaluated in the UFSAR.

Alternately, if the failure likelihood of the modified SSC is determined to be not sufficiently low, then the activity does introduce failures that are as likely to happen as those in the UFSAR. In this case, further assessment to determine the impact of the malfunction on the safety analysis result is to be performed.

EXAMPLE Example 4-186 illustrates the NO CREATION of the possibility for a malfunction with a different result due to applying the as likely to happen as consideration case.

Example 4-186. NO CREATION of the Possibility for a Malfunction with a Different Result Proposed Activity A large number of analog transmitters in several different systems and uses are being replaced with digital transmitters. These transmitters perform a variety of functions, including controlling the automatic actuation of devices (e.g., valve stroking) that are credited in a safety analysis.

Qualitative Assessment Outcome A qualitative assessment was included in the engineering/technical information supporting the change. The qualitative assessment considered Commented [NEI148]: Addresses NRC comment A13.

system design attributes, quality of the design processes employed, and operating experience of the proposed equipment and concluded that the failure likelihood introduced by the modified SSCs is sufficiently low. For the specific items that were considered within each factor, refer to the qualitative assessment documented in design change package X.

Conclusion Based on the qualitative assessment, the failure likelihood of the modified SSC has been determined to be sufficiently low.

Therefore, a malfunction with a different result is NOT as likely to happen as D-56

those described in the UFSAR and there is no need to determine the impact of the malfunction on the safety analysis result. Thus, the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result.With the failure likelihood introduced by the modified SSCs being sufficiently low, the activity does not introduce any failures that are as likely to happen as those in the UFSAR that can initiate a malfunction of an SSC important to safety. Therefore, the activity does not create a possibility for a malfunction of an SSC important to safety with a different result from any previously evaluated in the UFSAR (for the aspect Commented [NEI149]: Addresses NRC comment A43.

being illustrated in this example). Commented [NEI150]: Addresses NRC comment A7.

Determination of Safety Analysis Result Impact For cases in which the qualitative assessment outcome is a failure likelihood of not sufficiently low, the safety analysis result impact needs to be Commented [NEI151]: Addresses NRC comment A43.

assessed to determine if the result is different.

The generic process to determine the impact of a malfunction of an SSC important to safety on the safety analyses, (i.e., a comparison of the safety analyses results to identify any different results), consists of multiple steps, as summarized next.

Step 1: Identify the functions directly or indirectly related to the proposed modification.

Considering the scope of the proposed digital modification, identify the functions that are directly or indirectly related to the proposed activity.

The functions identified as part of this step will be further classified in Step 2.

As a reminder of the guidance provided in NEI 96-07, the following additional guidance is provided to assist in the identification and consideration of the proper scope of SSCs and their functions:

(1) Identification and consideration of the proper scope of SSCs is concerned with the functional involvement of an SSC, not necessarily only its level of direct description in the UFSAR.

(2) In cases in which a proposed activity involves a sub-component/component that is not directly described in the UFSAR, the effect of the proposed activity involving the sub-component/component needs to consider the impact on the system in which the sub-component/component is a part.

(3) In cases in which a proposed activity involves a sub-component/component that is not described in the UFSAR, the effect of the proposed activity involving the sub-D-57

component/component needs to consider the impact on the system that the subcomponent/component supports.

Regardless of the level of description, the assessment of the impact also needs to consider the elements of a design function as described in NEI 96-07, Section 3.3, which are repeated below:

  • Implicitly included within the meaning of design function are the conditions under which intended functions are required to be performed, such as equipment response times, process conditions, equipment qualification and single failure.
  • Design functions may be performed by safety-related SSCs or nonsafety-related SSCs and include functions that, if not performed, would initiate a transient or accident that the plant is required to withstand.

Step 2: Identify which of the functions from Step 1 are Design Functions and/or Design Bases Functions.

Utilizing NEI 96-07, Section 3.3, classify each of the functions from Step 1 as either NOT a design function or as a design function.

If no design functions are identified, then the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result because malfunctions (and the results thereof) refers ONLY to the failure of an SSC to perform its intended design functions.

For each design function identified above, Uutilizinge NEI 96-07, Section 3.3 (along with Appendix B to NEI 97-04, as needed) to identify which design functions are design bases functions, which design functions support or impact design bases functions, and which design functions are not involved with design bases functions, but are functions that if not performed would initiate a transient or accident that the plant is required to withstand. If multiple design functions are identified, each design function is to be considered in this multi-step process.

If no design basis functions are involved, proceed to Step 5 since neither the performance of design basis functions nor the support or impactof design basis functions are involved. (NOTE: The potential for more severe accident initiation is addressed in Step 5.)

The process for determining if a design function is a design basis function ismay be aided by identifying the associated General Design Criteria (GDC) to which a design bases function applies or, more specifically, the associated principal design criteria (PDC) for an individual facility, the minimum standards for which are set by 10 D-58

CFR Part 50 Appendix A (or perhaps their 1967 precursors). Each Commented [NEI152]: Addresses NRC comment A81.

design function may then be related to the requirements discussed within the GDC to determine if that design function is directly involved with the design basis function itself or if the design function supports or impacts the related design basis function. If the design function is found to directly involve the GDC requirement, then that design function is a design basis function. If the design function supports or impacts the GDC requirement, then it is not a design basis function, but is still credited in the safety analysis.

As described in NEI 96-07, Section 4.3.2 (but equally applicable here),

safety analyses typically assume certain SSCs perform certain design functions as part of demonstrating the adequacy of the design. The process of determining if a design function is a design abses function should include both direct and indirect affects on the design functions.

However, safety analyses do not typically identify all of the SSCs that are relied upon to perform their design functions. Therefore, the review should not be limited to only the SSCs discussed in the safety analyses. For example, performing a design change on a valve controller in a high pressure safety injection system would be considered to involve an SSC credited in the safety analyses even though the valve itself may not be mentioned in the safety analyses.

Step 3: Determine if a new FMEA needs to be generated.

If the impact on the design basis function involved is readily apparent, no new FMEA needs to be generated, skip this step and. gGo to Step 4.

For example, there is no reason to contemplate the generation of a new FMEA if the impact of the failure on the design bases functions is recognized as being immediate. Otherwise, generate the new FMEA to describe the connection of the proposed activity, or failures due to the proposed activity, to an impact on the design bases functions.

As part of the process for generating the new FMEA, presume compliance with pre-existing/interdependent, modification-related procedures and utilization of existing equipment to determine if adequate SSC design and/or operational (i.e., procedural) options exist Commented [NEI153]: Addresses NRC comment A83.

to mitigate potential detrimental impacts on design functions.

Interdependence is discussed in NEI 96-07, Sections 4.2 and 4.3 (which is distinct from compensatory actions discussed in NEI 96-07, Section 4.4). An example of an interdependent procedure change would be the modifications to an existing procedure to reflect operation of the new digital equipment and controls, including any new features such as a control system restart option. (NOTE: NEI 96-07, Section Commented [NEI154]: Addresses NRC comments A82 4.3.2, Example 4 provides guidance on assessing new operator actions.) and A83.

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Step 4: Determine if each design basis function continues to be performed/satisfied.

If all design basis functions continue to be performed/satisfied, and there are no other design functions involved, then the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result because no malfunction occurs. With no malfunction occurring, there cannot be a different result.

For any design basis function that does not continue to be performed/satisfied, or other design functions that are involved, continue to Step 5.

Step 5: Identify all safety analyses involved.

Identify all safety analyses that rely directly or indirectly on the design basis functions performance/satisfaction. Also, identify all safety analyses related to any other design function that could impact either the accidents initiation or the events initial conditions, (i.e., design functions that, if not performed, would initiate a transient or accident that the plant is required to withstand).

If there are no safety analyses involved, then there cannot be a change in the result of a safety analysis. Therefore, in this case, the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result.

Step 6: For each safety analysis involved, compare the projected/postulated results with the previously evaluated results.

NEI 96-07, Section 4.3.6 provides the following guidance regarding the identification of failure modes and effects:

Once the malfunctions previously evaluated in the UFSAR and the results of these malfunctions have been determined, then the types and results of failure modes that the proposed activity could create are identified.

If any of the identified safety analyses have become invalid due to their basic assumptions no longer being valid, e.g., single failure assumption is not maintained, or if the numerical result(s) of any safety analysis would no longer satisfy the acceptance criteria, i.e., the safety analysis is no longer bounded, then the proposed activity DOES create the possibility for a malfunction of an SSC important to safety with a different result.

As part of the response and determining if the safety analyses acceptance criteria continue to be satisfiedbounded, include the impact D-60

on the severity of the initiating conditions and the impact on the initial conditions assumed in the safety analysis. Specifically, consider any design functions that, if not performed, would initiate a transient or accident that the plant is required to withstand.

Examples 4-19 through 4-24 illustrate cases in which the failure likelihood of the modified SSC is determined to be not sufficiently low and, by extension, the likelihood of a software CCF is also determined to be not sufficiently low, i.e., a malfunction is as likely to happen as those described in the UFSAR. In these cases, the multi-step process applying the safety analysis result impact consideration is performed to determine the impact of the malfunction on the safety analysis result. Commented [NEI155]: Addresses NRC comment A43.

EXAMPLES Examples 4-197 through 4-2321 illustrate some cases of NO CREATION of a malfunction with a different result by applying the multi-step process outlined above.

Example 4-197. NO CREATION of a Malfunction with a Different Result Proposed Activity A feedwater control system is being upgraded from an analog system to a digital system. New components are being added that could fail in ways other than the components in the original design. Now, as a result of this change, all four feedwater flow control valves could simultaneously fail closed following a software CCF.

Safety Analysis Result Impact Consideration Step 1:

The identifiedpertinent function of the feedwater control system is to establish and maintain steam generator water level within predetermined physical limits during normal operating conditions.

Step 2:

The function of the feedwater control system is classified as a design function due to its ability to initiate a transient or accident that the plant is required to withstand. However, the design function is not a design basis function. With no design basis functions involved, proceed to Step 5.

Step 3:

Not applicable Step 4:

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Not applicable Step 5:

The pertinent safety analysis is the accident analysis for Loss of Feedwater. The feedwater control system has a direct impact on the accident analysis assumptions and modeling.

Step 6:

Previously, only one feedwater flow control valve (out of four) could fail closed due to a failure of the analog control system. In the proposed design, all four feedwater flow control valves could simultaneously fail closed due to a software CCF in the digital control system.

Although only one feedwater flow control valve could fail due to a failure of the analog control system, the Loss of Feedwater accident analysis assumed the closure of all four flow control valves. The severity of the initiating failure forassumed in the Loss of Feedwater accident analysis (four valves affected) is unchanged. The event already since the analysis currently assumes a total loss of feedwater flow. The newly created failure modes are (valve closure) is determined to have no effect on this assumption. The manner inmechanism by which feedwater flow is lost (loss of control signal) has no impact on the initial conditions of the event.

Conclusion Although the software CCF likelihood was determined to be not sufficiently low (i.e., a malfunction is as likely to happen as those described in the UFSAR), the initiation severity ofassumed in the Loss of Feedwater eventaccident analysis (four valves affected), the newly created failure modes (valve closure) and the manner in mechanism by which feedwater flow was lost (loss of control signal) remain bounded. do not change Furthermore, the results of the safety analysis, including the type of event (increasing pressure) and all criteria that must be satisfied (maximum allowed peak RCS pressure and maximum allowed secondary pressure) remain bounded.

Thus, the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result (for the aspect being illustrated in this example). Commented [NEI156]: Addresses NRC comment A7.

NOTE: See Example 4-23 for a similar example that illustrates the case in which the current Loss of Feedwater accident analysis assumed the closure of only one flow control valve, causing the CREATION of a malfunction with a different result.

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Example 4-2018. NO CREATION of a Malfunction with a Different Result Proposed Activity A feedwater control system is being upgraded from an analog system to a digital system. Previously, only one of four feedwater flow control valves was assumed to fail open as part of the initiation of the Excess Feedwater event. Now, as a result of this change, all four feedwater flow control valves could simultaneously fail open following a software CCF.

Safety Analysis Result Impact Consideration Step 1:

The identified function is to establish and maintain steam generator water level within predetermined physical limits during normal operating conditions.

Step 2:

The function is classified as a design function due to its ability to initiate a transient or accident that the plant is required to withstand. However, the design function is not a design basis function. With no design basis functions involved, proceed to Step 5.

Step 3:

Not applicable Step 4:

Not applicable Step 5:

The pertinent safety analysis is the accident analysis for Excess Feedwater. The feedwater control system has a direct impact on the accident analysis assumptions and modeling.

Step 6:

The severity of the initiating failure has increased due to four valves supplying flow as compared to one valve prior to the change.

The minimum acceptable departure from nucleate boiling ratio (DNBR), i.e., the safety analysis result, is 1.30. The current safety analysis result is a minimum DNBR value equal to 1.42. After using the increased value for the new feedwater flow (to represent the D-63

increase in feedwater flow caused by the opening of the four feedwater flow control valves) in a revision to the Excess Feedwater accident analysis, the new safety analysis result is a minimum DNBR value equal to 1.33.

Conclusion Although the software CCF likelihood was determined to be not sufficiently low and the severity of the initiating failure has increased, a comparison of the safety analysis results of the minimum DNBR values shows that the new minimum DNBR value remains bounded. Therefore, the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result.

Example 4-219. NO CREATION of a Malfunction with a Different Result Proposed Activity A complete system upgrade toof the area radiation monitors that monitor a variety of containment compartments that could be subject to a radioactive releases during a LOCA is proposed. The outdated analog-based radiation monitors are being replaced by digitally-based monitors. The hardware platform for each area radiation monitor is from the same supplier and the software in each area radiation monitor is exactly the same.

Safety Analysis Result Impact Consideration Step 1:

The pertinent functions of each radiation monitor include the monitoring ofis to monitor the various compartments, rooms and areas that may be subject to an increase in radiation during the recirculation phase of a LOCA.

Step 2:

In this case, whether the function is a design bases function is not readily determinedapparent, so the associated GDC will be identified and examined.

Criterion 64 -- Monitoring radioactivity releases. Means shall be provided for monitoring the reactor containment atmosphere, spaces containing components for recirculation of loss-of-coolant accident fluids, effluent discharge paths, and the plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrences, and from postulated accidents.

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[emphasis added]

The area radiation monitors perform a function that is necessary to comply with a requirement specified in GDC 64. Therefore, the function of the radiation monitor's function is a design function directly involved with a design basis function.

Step 3:

No new FMEA needs to be generated. The effect of a postulated software CCF on the design basis function involved is readily apparent.

Step 4:

If a software CCF occurs, the area radiation monitors will not perform their design function that supports or impacts a design basis function.

Thus, the design basis function will not be performed/satisfied.

Step 5:

There are no safety analyses that directly or indirectly credit this design basis function. That isNamely, there are no considerations of malfunctions of single or multiple radiation monitors, or expected responses of the radiation monitors, in any safety analysis.

Step 6:

Not applicable Conclusion The cited GDC does not contain any reference to single failure protection, so there is no distinction between a failure of a single radiation monitor or multiple radiation monitors.

Although the software CCF likelihood was determined to be not sufficiently low (i.e., a malfunction is as likely to happen as those described in the UFSAR), there are no safety analyses that directly or indirectly credit the design basis function or contain expected responses of the radiation monitors. Thus, there cannot be a different result when comparing to a pre-existing safety analysis since none exists.

Therefore, the proposed activity does NOT create the possibility of a malfunction of an SSC important to safety with a different result.

NOTE: The acceptability of these new area radiation monitors will be dictated by their reliability, which is assessed as part of Criterion

  1. 2(ii), not Criterion #6(vi).

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Example 4-2220. NO CREATION of a Malfunction with a Different Result Proposed Activity Two chillers that cool the Main Control Room Ventilation System (MCRVS) are being upgraded. The MCRVS provides cooling to the Main Control Room and the adjacent Relay Room. The Relay Room contains multiple instrument racks that control both the Reactor Protection System (RPS) and Engineering Safety Features Actuation System (ESFAS) signals.

As part of the upgrade, each of the chiller's analog control systems will be replaced with a digital control system. Each digital control system maintains all of the operational features (e.g., auto/manual start/stop, setpoints and alarms) as the analog control systems. The hardware platform for each chiller control system is from the same supplier and the software in each chiller control system is exactly the same.

Safety Analysis Result Impact Consideration Step 1:

The MCRVS also cools the Relay Room that is adjacent to the main control room. The Relay Room contains multiple instrument racks that control both Reactor Protection and Safeguards actuation signals.

The pertinent functions of the MCRVS involve the air flow path from the Main Control Room to the Relay Room (which is described in the UFSAR), along with and a function to maintain the Relay Rooms temperature less than or equal to 120 ºF.

Step 2:

The function involving the "air flow path" is not affected and can be eliminated from consideration since the Screen phase determined that there was no adverse impact.

In this case, whether the "maintain temperature" function is a design bases function is not readily determinedapparent, so the associated GDC will be identified and examined.

Criterion 20 -- Protection system functions. The protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident D-66

conditions and to initiate the operation of systems and components important to safety. [emphasis added]

The chillers and the chiller control systems performs a function that supports or impacts the design basis function specified in GDC 20. Therefore, the chillers and function of the chillers control systems functions are is a design basis functions credited in the safety analysis.

Step 3:

The impact of a software CCF on the design bases functions credited in the safety analysis is not readily apparent, so a new FMEA was generated.

Step 4:

The new FMEA concluded that compliance with pre-existing procedures will result in the restoration of at least one chiller well before the Relay Room cooling becomes inadequate and temperature exceeds 120 ºF . Specifically, compliance with existing procedures will direct the lead to recognition of the problem and, using currently proceduralized alternate methods for operating the system (i.e., NOT compensatory actions for addressing degraded or nonconforming conditions), the restoration ofrestore the chillers control system Commented [NEI157]: Addresses NRC comment A88.

function prior to the impairment of the associated design basis functions. In addition, an interdependent procedure change (satisfying the four bullets in NEI 96-07, Section 4.3.2, Example 4) will lead to Commented [NEI158]: Addreses NRC coment A88.

the use of thea new digital control system restart feature to reinitialize the control system, which would and clear any software faults, allowing the chiller control system functions to be restored well before the Relay Room cooling becomes inadequate and temperature exceeds 120 ºF.

Step 5:

Although none of the safety analyses specifically identify assumptions or inputs related to the MCRVS, the Relay Room or the components therein, several accident analyses assume correct and timely actuation of the Reactor ProtectionRPS and/or the Safeguards featuresESFAS signals. As determined in Step 2 above, the chillers operation of the chiller control system is considered to be credited in the safety analysis since they support or impact the design bases functions associated with GDC 20. As demonstrated as part of Step 4, all design basis functions are preserved.

Step 6:

As determined in Step 4, all design basis functions are preserved.

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Therefore, all of the safety analyses identified in Step 5 remain valid and there is no change in any safety analysis result.

Conclusion Although the software CCF likelihood was determined to be not sufficiently low (i.e., a malfunction is as likely to happen as those described in the UFSAR), the design bases functions will continue to be performed/satisfied and the safety analyses (and all of the results from these analyses) are unaffected. Therefore, the proposed activity does NOT create the possibility of a malfunction of an SSC important to safety with a different result (for the aspect being illustrated in this example). Commented [NEI159]: Addresses NRC comment A7.

Example 4-2321. NO CREATION of a Malfunction with a Different Result Proposed Activity Currently, the non-safety-related feedwaterSteam Bypass cControl sSystem (SBCS) and the non-safety-related pressurizer pressure/level control system are separate analog control systems.

The feedwater control systemSBCS is being upgraded from an analog to a digital system. Previously, only one of four feedwater flow control valves was assumed to fail open as part of the initiation of the Excess Feedwater event. Now, as a result of this change, all four feedwater flow control valves could simultaneously fail open following a software CCF.

The pressurizer pressure/level control system is being upgraded from an analog control system to a digital control system.

As part of this modification, the two previously separate control systems (steam bypass and pressurizer) will be combined within the same digital controller in a distributed control system (DCS) with the same software controlling all feedwatersteam bypass and pressurizer functions.

Safety Analysis Result Impact Consideration Step 1:

FeedwaterSteam Bypass - The identifiedpertinent function of the SBCS is to establish and maintain steam generator water level within predetermined physical limits during normal operating conditionsmaximize plant availability by making full utilization of the turbine bypass valve capacity to D-68

remove NSSS thermal energy to accommodate load rejections, unit trips, and other conditions that result in the generation of excessive energy by the NSSS. This objective is achieved by the selective use of turbine bypass valves to avoid unnecessary reactor trips and prevent the opening of secondary side safety valves whenever these occurrences can be averted by the controlled release of steam.

Pressurizer - The identifiedpertinent function is control of the pressurizer sprays and heaters to maintain RCS pressure and pressurizer level within the established limits.

Step 2:

FeedwaterSteam Bypass - The function of the SBCS is classified as a design function due to its ability to initiate a transient or accident that the plant is required to withstand. However, the design function is not a design bases function. (This design function goes directly to Step 5.) Commented [NEI160]: Addresses NRC comment A89.

Pressurizer - In this case, whetherdetermining if the function is a design bases function is not readily determinedapparent, so the associated GDC will be identified and examined.

Criterion 10 -- Reactor design. The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. [emphasis added]

The pressurizer control system performs a function that supports or impacts a design basis function specified in GDC 10. Therefore, the pressurizer control systems function is a design basis function and is credited in the safety analysis.

Step 3:

The effect on the feedwatersteam bypass and pressurizer control systems is clear and understood, having a direct impact on the accident analysis assumptions and modeling. There is no reason to contemplate the generation ofgenerate a new FMEA since the impact of the software CCF on the accident analysis is readily apparent (i.e., clear and understood).

Step 4:

If a software CCF occurs, the pressurizer pressure/level control function, which supports or impacts the GDC 10 design basis function, will not continue to be performed/satisfied.

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Step 5:

The pertinent safety analysis is the accident analysis for Excess FeedwaterIncreased Main Steam Flow. Typically, in Chapter 15 accident analyses, control system action is considered only if that action results in more severe accident results. The feedwatersteam bypass and pressurizer control systems have a direct impact on the accident analysis assumptions and modeling.

Step 6:

Previously, all four SBCS turbine bypass valves were assumed to fail open as part of the initiation of the Increased Main Steam Flow event.

In the proposed design, all four SBCS turbine bypass valves could also fail open due to a software CCF in the digital control system.

In the Excess FeedwaterIncreased Main Steam Flow accident analysis, the initial conditions already assume abnormally low pressure and/or DNBR. Since the pressurizer pressure/level control system is assumed to be in automatic and would attempt to mitigate the results of the accident, . However, the sequence of events for the accident identifies that the pressurizer empties during the event. Therefore, no credit is taken forregardless of the operation (or mis-operation) of the pressurizer pressure/level control system during the event,. Therefore, a the malfunction of the pressurizer pressure/level control system would have no effect on this event and no effect on the safety analysis result.

The severity of the initiating failure assumed in the Increased Main Steam Flow accident analysis (four valves affected) is not affectedunchanged since the current analysis assumes the maximum possible increased steam flow. Furthermore, the failure mode (valve closure) is determined to have no effect and the mechanism (control signal error) that allows the valves to open, allowing the steam flow to increase, has no impact on the initial conditions of the event.

The assumption regarding the "status" of the pressurizer pressure/level control system (i.e., automatic vs. failed) both lead to emptying of the pressurizer, having no impact on the outcome of the event.

Therefore, there are no impacts due to the combination of the two control systems. The minimum allowed DNBR to satisfy the accident analysis acceptance limit is 1.30. The current minimum DNBR result is 1.42. After using an increased value for the new feedwater flow (to represent the increase in feedwater flow caused by the opening of the four feedwater flow control valves) and adjusting the appropriate D-70

inputs to reflect the new detrimental pressurizer heater and spray conditions in a revision to the Excess Feedwater accident analysis, the new minimum DNBR result is 1.33.

Conclusion WithAlthough the software CCF likelihood was determined to be not sufficiently low (i.e., a malfunction is as likely to happen as those described in the UFSAR), the severity of the initiating failure has increased. The impairment of the pressurizer pressure control function is already incorporated in the safety analysis modeling. The new minimum DNBR result continues to satisfy the accident analysis acceptance limit, which does Commented [NEI161]: Addresses NRC comment A91.

not change the result of the safety analysis. Therefore, the proposed activity does NOT create the possibility of a malfunction of an SSC important to safety with a different result., the initiation severity assumed in the Increased Main Steam Flow accident analysis (four valves affected), the failure modes (valve closure) and the mechanism by which steam flow increases (control signal error) remain bounded. Furthermore, the results of the safety analysis, including the type of event (decreasing pressure) and all criteria that must be satisfied (maximum allowed peak RCS pressure, maximum allowed secondary pressure, minimum allowed DNBR, maximum allowed peak linear heat rate and the dose consequences) remain bounded. Commented [NEI162]: Addresses NRC comment A90.

Therefore, the proposed activity does NOT create the possibility for a malfunction of an SSC important to safety with a different result (for the aspect being illustrated in this example). Commented [NEI163]: Addresses NRC comment A7.

Examples 4-242 and 4-23 illustrates a cases in which there is the CREATION of a malfunction with a different result.

Example 4-242. CREATION of a Malfunction with a Different Result Proposed Activity An upgrade to the analog-based reactor protection system with a digital-based reactor protection system is proposed. This proposed modification involves replacement of all the solid state cards that control the detection of anticipated operational occurrences and the actuation of the required reactor trip signals. Redundant channels contain these cards in satisfaction of single failure criteria.

Safety Analysis Result Impact Consideration Step 1:

The number of involved functions is large, all of which involve the detection of the occurrence of anticipated operational occurrences, the processing of those signals, and the generation of the appropriate D-71

reactor trip signals.

Step 2:

In this case, whether the functions are design bases function is not readily determinedapparent, so the associated GDCs will be identified and examined.

Criterion 20 -- Protection system functions. The protection system shall be designed (1) to initiate automatically the operation of appropriate systems including the reactivity control systems, to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences and (2) to sense accident conditions and to initiate the operation of systems and components important to safety. [emphasis added]

Criterion 21 -- Protection system reliability and testability. The protection system shall be designed for high functional reliability and inservice testability commensurate with the safety functions to be performed. Redundancy and independence designed into the protection system shall be sufficient to assure that (1) no single failure results in loss of the protection function and (2) removal from service of any component or channel does not result in loss of the required minimum redundancy unless the acceptable reliability of operation of the protection system can be otherwise demonstrated. The protection system shall be designed to permit periodic testing of its functioning when the reactor is in operation, including a capability to test channels independently to determine failures and losses of redundancy that may have occurred. [emphasis added]

Criterion 22 -- Protection system independence. The protection system shall be designed to assure that the effects of natural phenomena, and of normal operating, maintenance, testing, and postulated accident conditions on redundant channels do not result in loss of the protection function, or shall be demonstrated to be acceptable on some other defined basis. Design techniques, such as functional diversity or diversity in component design and principles of operation, shall be used to the extent practical to prevent loss of the protection function. [emphasis added]

The components perform functions that support or impact design bases functions specified in GDCs 20, 21, and 22. Thus, these functions are design basis functions and are credited in the safety analysis.

Step 3:

The effect on the detection, processing and generation of signals is clear and understood, having a direct impact on the safety analysis D-72

assumptions. There is no reason to contemplate the generation ofgenerate a new FMEA since the impact of the software CCF on the design bases functions is readily apparent (i.e., clear and understood).

Step 4:

Performance/satisfaction of tThe design bases functions related to the GDC 21 and 22 requirements regarding single failure criteria and redundant channels will not continue to be performed/satisfied.

Step 5:

Numerous safety analyses contain implicit assumptions regarding the performance and/or expectation of the minimum number of system/components and/or trains/channels that are expected to perform their function, which satisfy the applicable redundancy requirements and/or single failure criteria.

Step 6:

In all cases, for each safety analysis, the inability to satisfy the performance and/or expectation of the minimum number of systems/components and/or trains/channels violates an assumption upon which the safety analysis results are based.

In these instances, a simple review of the safety analyses and their structure will quickly identifyconclude that the results will exceed the associated acceptance criteriawill no longer be bounded.

Conclusion With the software CCF likelihood determined to be not sufficiently low(i.e.,

a malfunction is as likely to happen as those described in the UFSAR), the assumptions regarding satisfaction of single failure criteria are invalidated and the results are no longer bounded. Therefore, the proposed activity DOES createCREATES the possibility of a malfunction of an SSC important to safety with a different result (for the aspect being illustrated in this example).. Commented [NEI164]: Addresses NRC comment A7.

Example 4-23. CREATION of a Malfunction with a Different Result Proposed Activity A feedwater control system is being upgraded from an analog system to a digital system.

Safety Analysis Result Impact D-73

Step 1:

The pertinent function of the feedwater control system is to establish and maintain steam generator water level within predetermined physical limits during normal operating conditions.

Step 2:

The function of the feedwater control system is classified as a design function due to its ability to initiate a transient or accident that the plant is required to withstand. However, the design function is not a design basis function.

With no design basis functions involved, proceed to Step 5.

Step 3:

Not applicable Step 4:

Not applicable Step 5:

The pertinent safety analysis is the accident analysis for Loss of Feedwater. The feedwater control system has a direct impact on the accident analysis assumptions and modeling.

Step 6:

Previously, only one feedwater flow control valve (out of four) could fail closed due to a failure of the analog control system. In the proposed design, all four feedwater flow control valves could simultaneously fail closed due to a software CCF in the digital control system.

In the current Loss of Feedwater accident analysis, the closure of only one flow control valve is assumed. With the proposed design, the severity of the initiating failure that needs to be assumed in the Loss of Feedwater accident analysis (four valves affected) is changed since the current analysis did not assume a total loss of feedwater flow. The failure mode (valve closure) is determined to have no effect on this assumption. The mechanism by which feedwater flow is lost (loss of control signal) has no impact on the initial conditions of the event.

Conclusion With the software CCF likelihood determined to be not sufficiently low and the initiation severity assumed in the current Loss of Feedwater accident analysis (only one valve affected), the accident analysis result does not remain bounded.

Thus, the proposed activity CREATES the possibility for a malfunction of an D-74

SSC important to safety with a different result (for the aspect being illustrated in this example). Commented [NEI165]: Addresses NRC comment A7.

NOTE: See Example 4-17 for a similar example that illustrates the case in which the current Loss of Feedwater accident analysis assumed the closure of all four flow control valves, causing NO CREATION of a malfunction with a different result.

HUMAN-SYSTEM INTERFACE ASSESSMENT If no personnel-based initiators involving degraded operator performance (e.g., operator error) are identified as malfunction initiators, then the creation of a possibility for a malfunction of an SCC important to safety with a different result cannot occur due to the Human-System Interface portion of the digital modification. Otherwise, the creation of a possibility for a malfunction of an SSC important to safety with a different result is assessed utilizing the guidance described in NEI 96-07, Section 4.3.6. Commented [NEI166]: Addresses NRC comment A54.

4.3.7 Does the Activity Result in a Design Basis Limit for a Fission Product Barrier Being Exceeded or Altered?

There is no unique guidance applicable to digital modifications for responding to this Evaluation question because the identification of possible design basis limits for fission product barriers and the process for determination of "exceeded" or "altered" are not unique for a digital modification. The guidance in NEI 96-07, Section 4.3.7 applies.

4.3.8 Does the Activity Result in a Departure from a Method of Evaluation Described in the UFSAR Used in Establishing the Design Bases or in the Safety Analyses?

There is no unique guidance applicable to digital modifications for responding to this Evaluation criterion because activities involving methods of evaluation do not involve SSCs. The guidance in NEI 96-07, Section 4.3.8 applies.

5.0 EXAMPLES

[LATER]

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