ML11318A027

993754-1905(NP), Revision 1, Project Management Plan (Pmp).

ML11318A027
Person / Time
Site:	Diablo Canyon
Issue date:	10/13/2011
From:	Shaffer R Invensys Operations Management, Invensys/Triconex
To:	Office of New Reactors
References
3500897372 993754-1-905(NP), Rev 1
Download: ML11318A027 (82)

Text

in V e. ns->"._! S" i n V e. n s'. s" Operations Management Triconex Project: PG&E PROCESS PROTECTION SYSTEM REPLACEMENT Purchase Order No.: 3500897372 Project Sales Order: 993754 PACIFIC GAS & ELECTRIC COMPANY NUCLEAR SAFETY-RELATED PROCESS PROTECTION SYSTEM REPLACEMENT DIABLO CANYON POWER PLANT PROJECT MANAGEMENT PLAN (PMP)

Document No. 993754-1-905 (-NP)

Revision 1 October 13, 2011 Non -Proprietary copy per 10CFR2.390

- Areas of Invensys Operations Management proprietary information, marked as [P], have been redacted based on I OCFR2.390(a)(4).

Name S'j r) Title Author: Roman Shaffer P,iroject Manager Approvals: Harry Rice = *_ Project QA Manager Richard Lilfleston 64/ xr-"* Director, Nuclear Delivery

) i n v'e. n s',* s, i nvens'.w s" Operations Management Triconex Project: __PG&E PROCESS PROTECTION SYSTEM REPLACEMENT Purchase Order No.: 3500897372 Project Sales Order: 993754 PACIFIC GAS & ELECTRIC COMPANY NUCLEAR SAFETY-RELATED PROCESS PROTECTION SYSTEM REPLACEMENT DIABLO CANYON POWER PLANT

) PROJECT MANAGEMENT PLAN (PMP)

Document No. 993754-1-905 Revision I October 13, 2011 Name Signahwe-, r/-i Title Author: Rom an----e-ro Project Manager Approvals: Harry Rice ,*=*_ Project QA Manager SRich~ard Limesto. n / '/*f* 3 Director, NuclearDelivery

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I Project Management Plan Revision: 1 Page: 2 of 81 Date: 10/13/2011 Document Change History Revision Date Change Author 0 7/29/2011 Initial Issue for Use. R. Shaffer 1 10/13/2011 Revised to discuss control of Project Instructions, and R. Shaffer incorporate Invensys Operations Management organizational changes.

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I Project Management Plan Revision: I Page: 1 3 of 81 1 Date: 10/13/2011 Table of Contents L ist of T ables ............................................................................................................5 L ist of F igu res ........................................................................................................... 6

1. Introd uction .................................................................................................... 7 LI. Project Overview ............................................................................... 7 1.2. Project Deliverables ............................................................................. 11 1.3. Purpose of the Project Managem ent Plan ............................................................... 13 1.4. Evolution of the Project M anagement Plan .............................................................. 14 1.5. Reference M aterials .............................................................................. 14 1.5.1. PG&E Documents ........................................................................ 14 1.5.2. NRC Documents ......................................................................... 14 1.5.3. Industry Documents ....................................................................... 15 1.5.4. Invensys Operations M anagement Documents .... .................................................. 15 1.6. Definitions and Acronyms ......................................................................... 15 1.6,1. Definitions ............................................................................. 15 1.6.2. Acronyms .............................................................................. 16

2. Project O rganization .................................................................................... 19 2.1. Process M odel ................................................................................. 19 2.2. Organizational Structure .......................................................................... 19 2.3. Organizational Boundaries and Interfaces .............................................................. 23 2.4. Project Responsibilities ........................................................................... 24

3. M anagerial Process ....................................................................................... 29 3.1. M anagement Objectives .......................................................................... 29 3.2. Management Priorities ........................................................................... 29 3.3. Assumptions, Dependencies and Constraints ............................................................ 30 3.3.1. Assumptions ............................................................................ 30 3.3.2. Dependencies ........................................................................... 30 3.3.3. Constraints ............................................................................. 30 3.4. Risk M anagement ............................................................................... 31 3.5. M onitoring and Controlling M echanism s .............................................................. 33 3.5.1. W eekly Project Hours Tracking Sheets ......................................................... 33 3.5.2. Project Schedule W eekly Updates ............................................................. 33 3.5.3. Project Technical Reviews .................................................................. 33 3.5.4. Project Phase Summary Reports and Exit M eetings ................................................. 34 3.5.5. Project Review Comm ittee .................................................................. 35 3.5.6. NQA Audits and Surveillances ............................................................... 35 3.6. Staffi ng Plan ...........................................

............................................................... 35 3.6.1. Skill levels required ....................................................................... 35 3.6.2. Start times and duration of needs .............................................................. 36 3.6.3. Training requirements ..................................................................... 36

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4. Technical Process .......................................................................................... 39 4.1. Methods, Tools and Techniques .................................................................... 39 4.1.1. Computing systems to be used for software development ............................................ 39 4.1.2. D evelopm ent m ethods ..................................................................... 42 4.1.3. Programming languages ................................................................... 42 4.1.4. Computer-assisted software engineering (CASE) tools .............................................. 42 4.1.5. Technical standards to be followed ............................................................ 42 4.1.6. Company development procedures ............................................................ 44 4.1.7. Company programming style ................................................................ 45 4.2. Software Documentation ......................................................................... 46 4.3). Project Support Functions ........................................................................ 46 4.3.1. Software Quality Assurance ................................................................ 46 4.3.2. Software Configuration Management .......................................................... 46 4.3.3. Software Verification and Validation (including testing) ............................................. 46 4.3.4. Software Safety Management ............................................................... 46 4.3.5. Software reviews and audits ................................................................ 47 4.3.6. User Software Documentation ............................................................... 47

5. W ork Packages, Schedule, and Budget ...................................................... 48 5.1. W ork Packages ................................................................................ 48 5 .2 . D epen dencies ................................................................................. 63 5.3. R esource R equirem ents .......................................................................... 63 5.4. Budget and Resource Allocation .................................................................... 66 5 .5 . S chedu le .................................................................................... 66

6. A dditional C om ponents ............................................................................... 67 6.1. Project Security Requirements ..................................................................... 67 6.1.1. Physical A ccess C ontrols .................................................................. 67 6.1.2. Network Access Controls .................................................................. 67 6.1.3. Project Controls and Application Security ....................................................... 68

7. A ppendices .................................................................................................... 70 Appendix A- PPS Replacement Project Documents List ....................................................... 71 Appendix B- PPS Project Document Numbering Scheme ...................................................... 75 Appendix C- PPS Replacement Project Hours Tracking Sheets .................................................. 77 Appendix D- PPS Replacement Project Required Reading Lists .................................................. 79

n vee. n s".* s" i n \ e.n s'. s" Operations Management Triconex Document: 1993754-1-905 ,Title: I Project Management Plan Revision: 1 Page: 5 of 81 Date: 10/13/2011 List of Tables Table 1. V10 Tricon PPS Protection Set Channel Safety Functions ....................................... 10 Table 2. Lifecycle Mapping ..................................................................................................... 19 T able 3. R isk F actors .................................................................................................................... 31 Table 4. Work Package Dependencies ...................................................................................... 65

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Project Management Plan Revision: I Page: 6 of 81 1 Date: 10/13/2011 List of Figures Figure 1. Westinghouse PWR Reactor Protection Concept [Ref. 1.5.2] ................................... 7 Figure 2. Tricon Protection Set Architecture for the PPS Replacement System ....................... 9 Figure 3. PPS Replacement Project Organizational Structure ................................................ 22 Figure 4. PPS Replacement Project - Interface Boundaries ................................................... 24 Figure 5. Invensys Nuclear Integration Project Waterfall Lifecycle ....................................... 41

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1. Introduction 1.1. Project Overview The Pacific Gas & Electric (PG&E) Diablo Canyon Power Plant (DCPP) Process Protection System (PPS) Replacement Project upgrades the existing Westinghouse Eagle 21 safety system.

The scope of the equipment replacement is shown in the red box in Figure 1, below. The red box represents the Process Protection racks that contain the safety-related equipment.

The PPS monitors plant parameters, compares them against setpoints and provides signals to the Solid State Protection System (SSPS) if setpoints are exceeded. The SSPS evaluates the signals and performs Reactor Trip System (RTS) and Engineered Safety Feature Actuation System (ESFAS) functions to mitigate the event that is in progress. The SSPS, RTS, and ESFAS functions are not within the scope of the PPS Replacement Project.

O*PWR Protection Concept Rod Control Power Cabinet Figure 1. Westinghouse PWR Reactor Protection Concept [Ref. 1.5.2]

The PPS comprises four Protection Sets in sixteen racks. Separation of redundant process channels begins at the process sensors and is maintained in the field wiring, containment

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I Project Management Plan Revision: 1 Page: 8 of 81 1 Date: 10/13/2011 penetrations, and process Protection Sets to the two redundant trains in the SSPS logic racks.

Redundant process channels are separated by locating the electronics in different Protection Sets.

As shown in Figure 2, the replacement Protection Sets (I thru IV) each comprise the Vi10 Tricon, the Westinghouse Advanced Logic System (ALS) platform, the Maintenance Workstation, and various interface devices, such as the NetOptics Network Aggregator Tap and instrument loop isolators. The ALS is not within Invensys Operations Management scope of supply. However, the ALS converts sensor inputs to a signal type compatible with the VI 0 Tricon hardware.

Specifically, the ALS processes resistance temperature detector (RTD) inputs and converts them to 4-20 milliamp signals. This conversion is necessary to satisfy Diablo Canyon Power Plant loop accuracy requirements. See the Functional Requirements Specification [Ref. 1.5.1.3] for additional information.

The VI 0 Tricon portion of the PPS Replacement System comprises three V 10 Tricon chassis per Protection Set: one safety-related Main Chassis, one safety-related Remote Expansion Chassis (RXM), and one nonsafety-related RXM chassis - see Figure 2. The Network Aggregator Tap, which is intended as an isolation device between the Tricon and the nonsafety plant network, is provided by PG&E to Invensys Operations Management for factory acceptance testing. The media converter between the Tricon Main Chassis and the Network Aggregator Tap, to be provided by Invensys Operations Management, is necessary to convert the fiberoptic medium at the output of the Tricon Communication Module (TCM) to copper medium at the input of the Network Aggregator Tap.

The Maintenance Workstation is a nonsafety device developed separately from the PPS Replacement Project under a separate PG&E Purchase Order, budget, and staff. Development of the Maintenance Workstation is handled under a different project plan and by a separate project team. However, the Maintenance Workstation is part of the factory acceptance test of the V 10 Tricon Protection Sets, as discussed in the Validation Test Plan, 993754-1-813. The technical requirements for the Tricon-to-Maintenance Workstation interface are provided in PG&E Interface Requirements Specification [Ref. 1.5.1.4].

The functions required in each V 10 Tricon Protection Set are listed in Table I below. See the Functional Requirements Specification for additional details on the protection functions and their design bases. As can be seen in Table 1, the PPS Protection Sets do not have the same channel safety functions. This difference among Protection Sets influences the PPS Replacement Project approach to hardware and software development, and independent verification and validation.

The Conceptual Design Document [Ref 1.5.1.2] and Functional Requirements Specification have additional detail on the hardware configuration of the PPS.

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____4-2D mA Aralog Copper Figure 2. Tricon Protection Set Architecture for the PPS Replacement System The four Protection Sets have different hardware and software requirements. The Main Chassis in each Protection Set executes the TriStation 1131 application code (the PT2 file), therefore the PPS requires four application programs (four PT2 files). The application programs are developed as nuclear safety-related Software Integrity Level 4 (SIL4) software [Ref. 1.5.3.1].

Because of the differences between the Protection Sets, four sets of design documents are developed for the nuclear safety-related software. One of the following is developed for each Protection Set:

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Project Management Plan Revision: I Page: 10 of 81 1 Date: 10/13/2011 Table 1. VI0 Tricon PPS Protection Set Channel Safety Functions Function Purpose Protection Set Function Purpose1- I II1 IV Input to Low Temperature Overpressure Provides protection against over-pressurization at low Protection System (LTOPS) Jplant temperature X Xi.I .

Wide Range Reactor____Coolant___Pressure___Channels_

Input to LTOPS Provides protection against over-pressurization at low X plant temperature Input to Residual Heat Removal (RHR) valve Provides protection against improper operation of RHR X interlock circuit isolation valves Overtemperature Delta-T (OTDT) Reactor Trip Provides DNB protection X X X X Overpower Delta-T (OPDT) Reactor Trip Provides protection against excessive power (fuel rod X XX rating protection)

Pressurizer High Water Level Reactor Trip

• Provides backup protection to the Pressurizer High Pressure Reactor Trip, and X X

• Prevents the pressurizer from becoming water solid X during low-worth and -power rod withdrawal accidents Pressurizer Vapor Space Temperature Low RHR valve V-8701 interlock circuit input I I X Steam Flow Indication 1GProvide safety-related outputs for post-accident monitoring (S/G I thru 4) X111X Steamline Pressure Low SI and Steamline 9 Initiate the automatic starting of boron injection and Isolation decay heat removal systems and X X X X

• Provide protection against steamline break accidents Steamline Pressure High Negative Rate Provide protection in the case of a steamline break when Steamline Isolation Pressurizer Pressure is less than the P-I I setpoint and Low X X X X Steamline Pressure SI is blocked Steam Generator (S/G) High-High Level Provides protection against S/G overfill and damage to the Turbine Trip and Feedwater Isolation (P-14, S/G main steamlines or main turbine X X X X High Level Permissive)

S/G Low-Low Level Reactor Trip and Auxiliary Protects the reactor from loss of heat sink in the event of Feedwater (AFW) Pump Start loss of feedwater to one or more S/Gs or a major X X X X feedwater line rupture Turbine Impulse Chamber Pressure High to P-13

• Provide an input to P-7 indicative of low turbine power Interlock when less than the setpoint X X e P-7 permissive disables selected Reactor Trip signals at low power levels Turbine Impulse Chamber Pressure Low

• Blocks control rod withdrawal Interlock C-5

• The purpose of the C-5 interlock is to prevent automatic X outward rod motion when power is less than the design limit for the Rod Control System

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" Hardware Requirements Specification

• Software Requirements Specification

" Software Design Description

" Application Program (PT2 file)

The list of documents generated during the PPS Replacement Project is in Appendix A, with the project document numbering scheme provided in Appendix B. Additional discussion of project deliverables for PG&E is provided in Section 1.2.

A single Project Traceability Matrix, 993754-1-804, is maintained, but is formatted to facilitate requirements traceability for each Protection Set. Invensys document 993754-1-906, Software Development Plan, provides details on the application program development process. Invensys document 993754-1-910, Software Integration Plan, discusses the strategy for integrating the software and hardware for each Protection Set. Invensys document 993754-1-802, Software Verification and Validation Plan, discusses the strategy for performing independent verification and validation of the PPS application software. See Section 3.6 of this plan for details on staffing requirements for the PPS Replacement Project.

The SIL4 application code (i.e., PT2 file) that is executed on the safety-related Tricon Main Chassis is developed as safety-related software using approved processes and procedures that adhere to current regulatory requirements. Specifically, the Invensys Nuclear System Integration Program Manual (NSIPM) [Ref. 1.5.4.1 ] describes the overarching approach used during the PPS Replacement Project, as explained in the remaining sections of this Plan, and the Project Procedures Manual (PPM) [Ref. 1.5.4.4] are the implementing procedures. The independent verification and validation activities meet the intent of Institute of Electrical and Electronics Engineers (IEEE) Standard 1012 [Ref. 1.5.3.11 for SIL 4 software.

Software and firmware related to the VI 0 Tricon platform and TriStation 1131 Developer Workbench are included in the U.S. NRC safety evaluation of the V10 Tricon Topical Report

[Ref. 1.5.4.3]. The PPS Replacement Project activities do not develop or modify software or firmware related to either the V 10 Tricon platform or TriStation 1131.

1.2. Project Deliverables PG&E will submit a License Amendment Request (LAR) in accordance with Interim Staff Guidance-6 (DI&C-ISG-06) [Ref. 1.5.2.7]. The guidance contained in DI&C-ISG-06 specifies certain design documents that should be provided to the NRC to support the staff's review of a LAR application. Based on DI&C-ISG-06, the PPS LAR review is a Tier 2 review. The list of documents required by the staff for a Tier 2 review includes normal digital system design documentation, e.g., SRS, SDD, test plans, and so on, but also several other documents particular to the NRC regulatory review process.

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I Project Management Plan Revision: I Page: 12 of 81 1 Date: 10/13/2011 The DI&C-ISG-06 Tier 2 review is divided into three phases:

Phase I - Initial Application Phase 2- Continued Review and Audit Phase 3 - System Implementation and Inspection Enclosure B of DI&C-ISG-06 lists which documents should be submitted and/or available for audit during each of the above phases. To summarize, Phase I requires system software design documentation through the Software Requirements Specification as well as System Test Plan(s).

Phase 2 requires software code listings as well as test documentation (e.g., test specifications and test reports). Phase 3, the system site-installation phase, requires Licensee project plans, user manuals, and test reports to be available for audit.

PG&E prefers that the PPS Replacement Project be funded in phases that are synchronized to the DI&C-ISG-06 Tier 2 review phases. Therefore, PG&E Purchase Order 3500897372 [Ref.

1.5.1.1 ] identifies project document deliverables' for Project Phase I only. Project Phase 2 is covered under a new Purchase Order (or a Changer Order to the existing Purchase Order). In anticipation of receiving a Purchase Order for Project Phase 2, Invensys Operations Management PPS Replacement Project activities are managed with this Plan for the entire project scope (Phases 1 and 2). Section 2.1 describes the lifecycle applied during this project, including the mapping to DI&C-ISG-06 phased deliverables.

Appendix A lists the set of documents that Invensys Operations Management intends to deliver to PG&E for the PPS Replacement Project, separated into Phase I and Phase 2 deliverables.

Section 2.1 describes the lifecycle applied during this project, including the mapping to DI&C-ISG-06 phased deliverables. The sequence follows the lifecycle applied by Invensys Operations Management - see Section 2.1 for further discussion. Project Phase I ends at the end of the Requirements Phase and the Requirements Phase Summary Report will be issued. Appendix B shows the Invensys Operations Management document numbering scheme for the PPS Replacement Project.

PPS Replacement Project Phase 1 does not involve delivery of safety-related hardware.

However, in anticipation of PG&E needs related to Project Phase 2, the PPS Vi 0 Tricon hardware may be ordered during Project Phase I after receiving written permission from PG&E.

Ordering hardware prior to approved and released drawings requires a Conditional Release, in accordance with the NSIPM and PPMs. The risk is acceptable because the Hardware Requirements Specification for each Protection Set will have been released to PG&E for review and comment. Final assembly and release of the VIO Tricon Protection Set equipment for test does not proceed until system drawings are approved for use.

1At the time the Purchase Order was issued that DI&C-ISG-06 was still in draft form. Since then, Revision 1 of DI&C-ISG-06 has been released, and Appendix A reflects the changes since the Purchase Order was issued.

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I Project Management Plan Revision: I Page: 13 of 81 1 Date: 10/13/2011 Invensys Operations Management will begin Project Phase 2 upon receiving written authorization by Purchase Order (or Change Order to the existing Purchase Order) from PG&E.

Project Phase 2 deliverables are listed in Appendix A are only a proposed set of deliverables, and are for information only. This plan will be updated accordingly with the final set of deliverables negotiated with PG&E in accordance with the PPS Replacement Project Software Configuration Management Plan, 993754-1-909. The long-lead item in Project Phase 2 is the Final V&V Report.

PG&E is responsible for negotiating the DCPP LAR review schedule with the NRC. The detailed schedule, 993754-1-059, developed by Invensys Operations Management is synchronized with the LAR submittal dates provided by PG&E. As the LAR schedule changes, PG&E provides the updates to Invensys Operations Management and the detailed project schedule is updated accordingly.

All DI&C-ISG-06 LAR Phase 1 deliverables in Appendix A are scheduled for delivery to PG&E as shown in the PPS Replacement Project Schedule, 993754-1-059. The document deliverables are released to PG&E at various times for review and comment as shown in the detailed project schedule - see Section 5.5 for discussion of the PPS Replacement Project schedule.

1.3. Purpose of the Project Management Plan This Project Management Plan (PMP) has been written to ensure that the management of the PPS Replacement Project conforms to NRC guidance for development of software intended for use in nuclear safety-related applications. This Plan was written to conform to Branch Technical Position 7-14, Guidance on Software Reviews for Digital Computer-Based Instrumentation and Control Systems [Ref. 1.5.2.2], and NUREG/CR-61 01 [Ref. 1.5.2.4].

This Plan describes the management process for the PPS Replacement Project to ensure adherence to the Invensys Operations Management quality and process requirements for the development of nuclear safety-related software and hardware. This Plan addresses the following areas:

" Project Organization - The Plan describes the organizational structure of the Invensys Operations Management project team, including organizational boundaries and interfaces to PG&E, PG&E subcontractors, and the NRC.

" Management Oversight - The Plan describes the management methods and tools used to oversee the work performed by the Invensys Operations Management project team.

" Organizational and Personnel Responsibilities - The Plan describes the duties of the Invensys Operations Management organizations involved in developing the PPS Protection Sets based on the VI 0 Tricon hardware and software, and of the individuals within each organization.

• Project Risks - The Plan describes the methods and tools used to identify, assess, and manage project risks that may interfere with achieving project objectives.

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I Project Management Plan Revision: 1 Page: 14 of81 1 Date: 10/13/2011 Development Environment and Product Security - The Plan describes the methods used to protect project data and equipment from inadvertent or malicious alteration.

1.4. Evolution of the Project Management Plan This Plan is controlled as a Configuration Item in accordance with the Invensys Operations Management Nuclear System Integration Program Manual (NSIPM), Section 10.0, Project Document and Data Control. In accordance with the NSIPM, the PMP is listed on a master configuration list that identifies the current revision level of the PMP to ensure project personnel are using the approved version. The initial and subsequent releases of the PMP is reviewed and approved by the Project Manager and the Quality Assurance Manager prior to use by project personnel. Upon each release of the PMP for project use, the project Master Configuration List, 993754-1-803, is updated.

Release of any version of the PMP to PG&E is done in accordance with the NSIPM, Section 10.

See Invensys document 993754-1-909, Software Configuration Management Plan, for additional details on the Configuration Management activities during the PPS Replacement Project.

1.5. Reference Materials 1.5.1. PG&E Documents 1.5.1.1 PG&E Purchase Order 3500897372.

1.5.1.2 PG&E Process Protection System Replacement Conceptual Design Document.

1.5.1.3 PG&E Functional Requirements Specification, 08-0015-SP-001.

1.5.1.4 PG&E Process Protection System Replacement Interface Requirements Specification.

1.5.2. NRC Documents 1.5.2.1 NUREG-0800, Standard Review Plan, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition, Chapter 7 - Instrumentation and Controls, U.S. Nuclear Regulatory Commission.

1.5.2.2 Branch Technical Position 7-14, Guidance on Software Reviews for Digital Computer-Based Instrumentation and Control Systems, U.S. Nuclear Regulatory Commission.

1.5.2.3 Regulatory Guide 1.168, Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants, U.S. Nuclear Regulatory Commission.

1.5.2.4 NUREG/CR-6101, Software Reliability and Safety in Nuclear Reactor Protection Systems, U.S. Nuclear Regulatory Commission.

1.5.2.5 DI&C-ISG-01, Digital Instrumentation and Controls Task Working Group #1: Cyber Security Interim Staff Guidance, U.S. Nuclear Regulatory Commission.

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ýProject Management Plan Revision: I Page: 15 of 81 1 Date: 10/13/2011 1.5.2.6 DI&C-ISG-04, Digital Instrumentation and Controls Task Working Group #4: Highly-Integrated Control Rooms - Communications Issues Interim Staff Guidance, U.S.

Nuclear Regulatory Commission.

1.5.2.7 DI&C-ISG-06, Digital Instrumentation and Controls Task Working Group #6: Licensing Process Interim Staff Guidance, U.S. Nuclear Regulatory Commission.

1.5.2.8 Title 10 of the Code of Federal Regulations, Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.

1.5.2.9 Regulatory Guide 1.209, Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants, U.S.

Nuclear Regulatory Commission.

1.5.3. Industry Documents 1.5.3.1 IEEE Standard 1012-1998, IEEE Standard for Software Verification and Validation.

1.5.3.2 NQA-1-1994, Quality Assurance Requirements for Nuclear Facility Applications.

1.5.3.3-IEEE Standard 1074-1995, IEEE Standard for Developing Software Life Cycle Processes.

1.5.4. Invensys Operations Management Documents 1.5.4.1 NSIPM, Nuclear Systems Integration Program Manual, NTX-SER-09-21.

1.5.4.2 IOM-Q2, Invensys Operations Management Nuclear Quality Assurance Manual.

1.5.4.3 VI 0 Tricon Topical Report, 7286-1-545, Invensys Operations Management (ADAMS Accession Number ML110140443).

1.5.4.4 Project Procedures Manual, Invensys Operations Management.

1.5.4.5 Manufacturing Department Manual, Invensys Operations Management.

1.5.4.6 NTX-SER-10-14, V10 Tricon Conformance to Regulatory Guide 1.152.

1.5.4.7 Project Instruction 1.0, Application Project Administrative Controls for the PPS Replacement Project.

1.5.4.8 Project Instruction 7.0, Application Program Development for the PPS Replacement Project.

1.6. Definitions and Acronyms 1.6.1. Definitions activity: A defined body of work to be performed, including its required Input and Output Information.

Configuration Item: A specification or product that is to be incorporated into the configuration management process.

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I Project Management Plan Revision: I Page: 16 of 81 1 Date: I 10/13/2011 constraint: A restriction on software life cycle process (SLCP) development.

integrity level: A denotation of a range of values of a property of an item necessary to maintain system risks within acceptable limits. For items that perform mitigating functions, the property is the reliability with which the item must perform the mitigating function. For items whose failure can lead to a threat, the property is the limit on the frequency of that failure.

product: Any output of the software development Activities (e.g., document, code, or model).

Software Integrity Level (SIL): The integrity level of a software item.

software life cycle (SLC): The project-specific sequence of Activities.

work package: A work package is a subset of a project that can be assigned to a responsible individual or organization to complete a collection of work actions necessary to create a specific result; the lowest level of the work breakdown structure where both the cost and the duration can be reliably estimated.

1.6.2. Acronyms AFW Auxiliary Feedwater ALS Advanced Logic System ANSI American National Standards Institute ASME American Society of Mechanical Engineers CASE Computer-Assisted Software Engineering CDD Conceptual Design Document CFR Code of Federal Regulations DCPP Diablo Canyon Power Plant DI&C Digital Instrumentation and Controls EMI Electromagnetic Interference ESFAS Engineered Safety Feature Actuation System FAT Factory Acceptance Test FMEA Failure Modes and Effects Analysis FRS Functional Requirements Specification HRS Hardware Requirements Specification HSI Human-System Interface HVT Hardware Validation Test I/O Input/Output IEC International Electrotechnical Commission IEEE Institute of Electrical and Electronics Engineers IOM Invensys Operations Management IRS Interface Requirements Specification ISG Interim Staff Guidance IV&V Independent Verification and Validation LAR License Amendment Request LLR Lessons Learned Report

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Project 1 Management Plan Revision: I Page: 17 of 81 1 Date: 10/13/2011 LOE Level of Effort LTOPS Low Temperature Overpressure Protection System MCB Main Control Board MCL Master Configuration List MDM Manufacturing Department Manual ND Nuclear Project Delivery NQA Nuclear Quality Assurance NRC U.S. Nuclear Regulatory Commission NSIPM Nuclear System Integration Program Manual OPDT Over-Power Delta-T OTDT Over-Temperature Delta-T PE Project Engineer PG&E Pacific Gas & Electric Company PMP Project Management Plan PO Purchase Order POCM Purchase Order Compliance Matrix PPM Project Procedures Manual PQAE Project Quality Assurance Engineer PQAM Project Quality Assurance Manager PQP Project Quality Plan PPS Process Protection System PRC Project Review Committee PT2 File extension for the TriStation 1131 application code, i.e., *.PT2 PTM Project Traceability Matrix PWR Pressurized Water Reactor QA Quality Assurance QC Quality Controls QPM Quality Procedures Manual RFI Radio-Frequency Interference RG Regulatory Guide RHR Residual Heat Removal RTS Reactor Trip System RXM Remote Extender Module, Remote Expansion Chassis S/G Steam Generator SAT Site Acceptance Test SCMP Software Configuration Management Plan SDD Software Design Description SDP Software Development Plan SER Safety Evaluation Report SI Safety Injection SIL Software Integrity Level SlntP Software Integration Plan

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Project Management Plan Revision: I Page: 1 18 of 81I Date: 10/13/2011 SLC Software Life Cycle SLCP Software Life Cycle Process SQAP Software Quality Assurance Plan SRS Software Requirements Specification SSP Software Safety Plan SSPS Solid State Protection System SVVP Software V&V Plan SWR Software Walkthrough Report TCM Tricon Communications Module TRL Technical Requirements List TS 1131 TriStation 1131 TSAP TriStation Application Program V&V Verification and Validation

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2. Project Organization 2.1. Process Model Invensys Operations Management project scope is limited to design of the V 10 Tricon portion of the PPS hardware and software and Factory Acceptance Testing. As an approved 10 CFR Part 50 Appendix B supplier, Invensys Operations Management adheres to the Invensys Nuclear Systems Integration Program Manual (NSIPM) to ensure compliance with NRC requirements regarding safety-related software development. The Invensys Operations Management Quality Procedures Manual (QPM), Project Procedures Manual (PPM), and Manufacturing Department Manual (MDM) are the implementing procedures under the NSIPM.

The Invensys Operations Management PPM requires a project lifecycle comprising several phases. The overlap between the DI&C-ISG-06 LAR review phases and the NSIPM project lifecycle phases is shown in Table 4, below. Section 1.2 of this plan provides more detail on the DI&C-ISG-06 Enclosure B documents that are produced during PPS Replacement Project Phases 1 and 2.

Table 2. Lifecycle Mapping PPS Project DI&C-ISG-06 NSIPM Project Lifecycle Phase Enclosure B Phase I Phase I Acquisition Planning Requirements Design (until completion of software design description and test plans)

Phase 2 Phase 2 Design (remainder of Enclosure B documents)

Implementation Test Delivery Phase 3 Scope of Supply To Be Determined Discussion of the detailed project schedule is provided in Section 5.5.

2.2. Organizational Structure The organizational structure for the Invensys Operations Management project team is shown in Figure 3. The figure shows the organizations involved in the PPS Replacement Project, which includes Nuclear Delivery (ND), Nuclear Quality Assurance (NQA), and Nuclear Independent Verification and Validation (IV&V). The following is a description of the role of each organization, assigned project responsibilities, and document deliverables. A summary of the responsibilities of each position shown in Figure 3 are provided in Section 2.4. Additional details are provided in the NSIPM.

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Project Management Plan 7 Revision: I Page: 20 of 81 1 Date: 10/13/2011 ND is responsible for project execution, system hardware and software design, software implementation, system construction, and system delivery (during project Delivery Phase). PPS Replacement Project Team members from ND include the PM, PE, Hardware Design team, Software Design team, and support staff as needed (a project Administrative Assistant, test engineers, etc.). Ultimately, ND is responsible for the quality and safety of the delivered PPS, and for delivering the VI 0 Tricon Protection Sets within budget and schedule constraints. ND is responsible for producing the following documents:

Nuclear IV&V is responsible for ensuring that ND has adequately met the safety system requirements as defined in contract documents, Design Input documents, regulatory requirements, and Invensys Operations Management procedures. As shown in Figure 3, Nuclear IV&V is independent of ND to ensure Nuclear IV&V is not be adversely impacted by schedule pressure and financial/budget constraints. PPS Replacement Project Team members from Nuclear IV&V include the IV&V Team Lead and three IV&V Engineers. Nuclear IV&V is responsible for the following:

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NQA is responsible for ensuring that ND and Nuclear IV&V are adhering to applicable procedures and processes for nuclear safety-related system development, such as the Invensys Operations Management IOM-Q2 corporate Nuclear Quality Assurance Manual [Ref. 1.5.4.2],

the QPM and PPM. As shown in Figure 3, NQA is also sufficiently independent of ND to ensure the reporting chain is not unduly influenced by ND. NQA is responsible for the following:

1) Project Quality Plan, 993754-1-900

2) Software Quality Assurance Plan, 993754-1-801

3) Audits and surveillances during the project ND interfaces with Nuclear IV&V staff and NQA as needed. When anomalies have been identified during the project lifecycle, cases may arise that require escalating the resolution to

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Project Management Plan I Revision: I Page: 22 of 81 1 Date: T 10/13/2011 higher levels of Management within Invensys Operations Management. In Figure 3, the lines of communication between the organizations at the Management and Director levels are shown by the dashed lines. As shown, issues requiring escalation can be escalated up separate and independent reporting chains up to the Director level. In those rare cases that the Director level is not sufficient, IOM-Q2 allows escalation to the Regional and Global Director levels and still maintain the necessary managerial, technical, and financial independence necessary for compliance to NRC requirements contained in, for example, Regulatory Guide 1.168 [Ref.

1.5.2.3].

This Project Plan is revised appropriately if the PPS Replacement Project organizational structure depicted in Figure 3 changes. This may entail changes to Figure 3, addition of project personnel, changes to project responsibilities, or changes in the reporting structure.

10MgDirector. Nuclear 10M Nuclear Quality DeliveY- Director ProjectManager -- -- -- - - -- -- - -- ----

Admiin (PM)

AMs istant Irelepedent Prect Veriication &

Eroer (POAM) Valkdation (IV&V)

ý1 Manager S OiierAs ~Engineer Project GA verification &

Engine (PQAE) Validiation Hardwere (IV&V) Staff Software Figure 3. PPS Replacement Project Organizational Structure It is important to note that if any change in the organizational structure depicted in Figure 3 impact the organizational independence between Nuclear IV&V and Nuclear Delivery, project activity must stop and an assessment made as to the impact on regulatory commitments related to the VIO Tricon Safety Evaluation. The assessment determines if project mitigation measures are necessary to ensure compliance with NRC requirements regarding independence of the Nuclear IV&V staff. Any mitigation measure(s) could require that this Project Plan be revised appropriately (and in accordance with the NSIPM, Section 10.0). The assessment, conclusions, and any necessary mitigation measures are documented and handled in accordance with the NSIPM, Sections 4.0 through 11.0, as appropriate.

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I Project Management Plan Revision: I Page: 23 of 81 Date: 10/13/2011 2.3. Organizational Boundaries and Interfaces PG&E is the customer and nuclear licensee pursuing the License Amendment Request (LAR) for Diablo Canyon Power Plant (DCPP). As such, PG&E is the project/system integrator responsible for overall project execution, and creation and submittal of the LAR package.

PG&E has contracted with both Westinghouse and Invensys Operations Management for the PPS Replacement Project. All interactions between Westinghouse and Invensys Operations Management pertinent to the PPS Replacement Project are at the direction of and coordinated by PG&E.

PG&E also utilizes the engineering services of Altran Solutions (Altran). Both PG&E and Altran could provide technical input and direction to Invensys Operations Management. Any technical direction provided by Altran must first be approved by the PG&E Project Manager.

The single point of contact within Invensys Operations Management for external interactions is the Project Manager or designee. Certain technical questions and coordination of project meetings may be handled by the Project Engineer after first discussing it with the Project Manager. For issues related to Nuclear IV&V and NQA, the Project Manager or his designee coordinates the interactions with PG&E and/or Altran.

All interactions with the NRC are coordinated by and through PG&E. Figure 4 shows the organizational boundaries among the various entities.

Invensys Operations Management will subcontract engineering services for supplemental EMI/RFI testing during Project Phase 2. When PG&E has authorized work for Project Phase 2, this Project Plan will be revised in accordance with the NSIPM, Section 10.0, and re-issued with the appropriate information (e.g., subcontractor name, project responsibilities including deliverables, and associated schedule changes). The Project Manager is responsible for the technical interface with the subcontractor(s) to ensure day-to-day tasks are on track with schedule and technical expectations. The subcontractor services are procured in accordance with the NSIPM, Section 11.0, and any design outputs from the subcontractor reviewed, managed, and controlled in accordance with NSIPM Sections 4.0, 7.0, 8.0, 9.0, and 10.0.

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4Project Management Plan Revision: I Page: 24 of 81 1 Date: 10/13/2011 INVENSYS OPERATIONS MANAGEMENT NUCLEAR DELIVERY SUBCONTRACTOR Figure 4. PPS Replacement Project - Interface Boundaries 2.4. Project Responsibilities Invensys Operations Management has assigned a core group of engineers and support staff to the PPS Replacement Project. As project needs change, assigned personnel are added or removed.

The following individuals are involved in the PPS Replacement Project:

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Project Management Plan Revision: I Page: 28 of 81 1 Date: 10/13/2011 Eli Changes to the organization chart or position responsibilities could require a revision to this Project Plan. If necessary, the Project Plan is revised in accordance with the NSIPM, Section 10.0.

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3. Managerial Process 3.1. Management Objectives The primary management objective is to produce the safety-related V 10 Tricon Protection Sets within the authorized budget limitations negotiated with PG&E by the scheduled submittal date for the Diablo Canyon Power Plant License Amendment Request. Progress against schedule and hours expended per work package (see Section 5) is tracked and measured against the risk factors identified in Section 3.4. Negative trends with regard to schedule and hours expended is assessed for appropriate compensatory measures, including:

1) Identifying work-process efficiencies,

2) Adding project personnel, and

3) Increasing the "Not to Exceed" value of Project Phase 1 (requires PG&E approval).

Section 3.4 discusses project risk management.

Adherence to the NSIPM and the implementing procedures in the PPM, QPM, and MDM is essential to achieving project quality objectives in accordance with the Invensys Operations Management Appendix B program. The project schedule and negotiated budget (schedule and cost) were developed based on the life cycle defined in the NSIPM as implemented by the PPM.

Adhering to the procedures also assures the required project deliverables satisfy PG&E technical and NRC regulatory requirements, and that the necessary supporting collateral is generated to support the safety conclusions of both ND and Nuclear IV&V. Quality metrics are identified in the Software Quality Assurance Plan, 993754-1-801.

3.2. Management Priorities w-

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Issues related to anomalies, non-conformances, and process deficiencies will be addressed with the utmost care in accordance with the NSIPM, Sections 7.0 and 8.0.

3.3. Assumptions, Dependencies and Constraints EZJ

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ED

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3.5. Monitoring and Controlling Mechanisms

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3.5.4. Project Phase Summary Reports and Exit Meetings Project Phase 1 fully encompasses Acquisition, Planning, and Requirements Phases, and partially encompasses the Design Phase of the Invensys Operations Management system design lifecycle as described in the NSIPM and implemented by the PPM. In accordance with the Invensys Operations Management process, the Requirements Phase Exit Meeting occurs at the end of the Requirements Phase and is a prerequisite to entering the Design Phase.

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Project Management Plan Revision: I Page: 35 of 81 Date: 10/13/2011 3.5.5. Project Review Committee The Project Review Committee is composed of the Project Manager, Project Engineer, Project Quality Assurance Engineer, and Nuclear IV&V/Test Director. The Project Review Committee will meet for PPS Project Phase I related activities as follows:

• Requirements Phase Exit Meeting - The Project Review Committee reviews project activities associated with the Requirements Phase and evaluates the risks and provide recommendations associated with lessons learned prior to transitioning to the Design Phase.

• Other - The Project Review Committee reviews and evaluates additional project activities as deemed appropriate by the Project Manager.

3.5.6. NQA Audits and Surveillances Invensys document 993754-1-900, Project Quality Plan, describes the overarching project quality requirements contained in the PG&E Purchase Order [Ref. 1.5.1.1 ] and purchase specification documents [References 1.5.1.2, 1.5.1.3, and 1.5.1.4]. The project Software Quality Assurance Plan, 993754-1-801, describes the NQA activities to ensure the project quality requirements and Invensys methods and procedures are being followed. This includes the various audits and surveillances conducted during the PPS Replacement Project Phase 1.

3.6. Staffing Plan Technical expertise for the PPS Replacement Project Team is found from a combination of available Invensys Operations Management staff and external staff augmentation resources.

During Project Phase 2 EMI/RFI testing will be performed by a subcontractor on the nuclear approved suppliers list.

3.6.1. Skill levels required The PPS Replacement Project requires a ND project team with combined knowledge and experience with the U.S. NRC regulations and processes, software engineering lifecycle management, and technical design and implementation of nuclear safety-related hardware and software. Specific skills and knowledge are required in the following areas:

1) Design and procedural compliance with 10 CFR Part 50, including Appendices A and B

2) Application of U.S. NRC Regulatory Guides relevant to safety-system software development

3) Application of relevant U.S. NRC staff guidance related to design of nuclear safety systems, such as Branch Technical Position 7-14 [Ref. 1.5.2.2] and DI&C-ISG-01 [Ref.

1.5. 2.5], DI&C-ISG -04 [Ref. 1.5.2.6], and DI&C-ISG -06 [Ref. 1.5.2.7]

4) Understanding of staff guidance contained in Chapter 7 of U.S. NRC NUREG-0800, Standard Review Plan [Ref. 1.5.2.1]

5) Application of relevant Institute of Electrical and Electronics Engineers standards (e.g.,

those endorsed by U.S. NRC Regulatory Guides) to nuclear safety-related system design and implementation

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6) Implementation of the Invensys Operations Management NSIPM and PPM to nuclear safety-related projects

7) Nuclear safety and protection systems

8) Tricon system hardware design and construction

9) Tricon application code (PT2 file) development using TriStation 1131 In addition to the above skill sets for the ND project team, the Nuclear IV&V team requires specific skills and knowledge in the following areas:

1) Application of U.S. NRC Regulatory Guides relevant to independent verification and validation safety-system software

2) Application of Institute of Electrical and Electronics Engineers standards (e.g., those endorsed by U.S. NRC Regulatory Guides) relevant to independent verification and validation of software for nuclear safety-related applications In addition to the above skill sets for the Nuclear IV&V team, the NQA Project Quality Assurance Engineer requires specific skills and knowledge in the following areas:

1) Invensys Operations Management PPMs

2) Invensys Operations Management corporate Nuclear Quality Policy, IOM-Q2 [Ref.

1.5.4.2]

3) U.S. NRC Appendix B criteria [Ref. 1.5.2.8] and application of such criteria to nuclear safety-related projects involving hardware and software design

4) NQA-I criteria [Ref. 1.5.3.2] and application of such criteria to nuclear safety-related projects involving hardware and software design See Section 2.0 for a detailed discussion of the PPS Replacement Project Organizational Structure (Section 2.2) and project team members' responsibilities (Section 2.4). Training files, including experience summaries, for the PPS Replacement Project team members are maintained by the Project Administrator. Changes to the project team could require an update to this plan, which will be done in accordance with NSIPM Section 10.0.

3.6.2. Start times and duration of needs A constant staffing level is used during PPS Replacement Project Phase I. Project activities remain at a constant level up to the scheduled delivery dates for project deliverables. Section 5.3 discusses resource requirements in more detail.

3.6.3. Training requirements Project personnel shall be appropriately qualified and trained in accordance with the NSIPM Section 9.0 and PPM 9.0, Personnel Training and Qualification. A copy of project personnel qualification and training records is included in the PPS Replacement Project document file.

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I Project Management Plan Revision: I Page: 38 of 81 1 Date: 10/13/2011 Specialized Training. The Project Quality Assurance Engineer requires specialized training, because of the project responsibilities performed by the Nuclear Quality Assurance organization.

Specifically, personnel performing inspection activities shall be qualified and certified in accordance with Invensys Operations Management QPM 18.2. Other specialized training will be assigned as needed on a case-by-case basis.

Training records for the PPS Replacement Project Team are handled in accordance with the NSIPM as implemented by the PPM and QPM with regard to Quality Records and retention.

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4. Technical Process 4.1. Methods, Tools and Techniques The PPS Replacement Project team adheres to the NSIPM and utilizes the PPM as the implementing set of procedures. The PPM defines a modified Waterfall model, as shown in Figure 5, based upon NQA-l [Ref. 1.5.3.2]. The guidance contained in NQA-I-1994 was utilized in preparing the PPM to ensure compliance with all nuclear quality requirements. The PPM is a combination of different procedures, including forms specified for use in the various PPM procedures. The PPM is a controlled document, and each procedure within the PPM is revision-controlled with its own revision level. Forms, which are to be used during project implementation, are also revision-controlled documents. The PPM contains a compliance matrix showing compliance with 10 CFR Part 50 Appendix B [Ref. 1.5.3.1] and NQA-l-1994.

4.1.1. Computing systems to be used for software development Equipment and tools used by the Invensys Operations Management project team during the project lifecycle are listed below. Control of material (e.g., test equipment, safety-related V 10 Tricon hardware, and so on) and equipment calibration (e.g., for hardware validation and factory acceptance testing) is handled in accordance with the NSIPM as implemented by the PPM.

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I Project Management Plan Revision: 1 Page: 42 of 81 Date: 10/13/2011 4.1.2. Development methods The NSIPM as implemented by-the PPM follows a modified Waterfall software development methodology in conformance to IEEE Std 1074 [Ref. 1.5.3.3]. Project management controls are utilized in each lifecycle phase to ensure phase activities are performed in accordance with the NSIPM as implemented by the PPM. Additional details of the technical process are found in the PPS Replacement Project Software Development Plan, 993754-1-906.

4.1.3. Programming languages TriStation 1131 provides three programming languages that comply with the IEC 61131-3 standard: Function Block Diagram, Ladder Diagram, and Structured Text. An optional language, CEMPLE (Cause and Effect Matrix), has not been qualified by Invensys Operations Management for use in developing software intended for nuclear safety-related applications.

For the PPS Replacement Project, the following programming languages are utilized when developing the V 10 Tricon Protection Set application code:

" Function blocks

" Structured Text Section 4.1.7 discusses the programming guidelines described in 993754-1-907, PPS Replacement Project Coding Guidelines.

4.1.4. Computer-assisted software engineering (CASE) tools None.

4.1.5. Technical standards to be followed Replacement of the Diablo Canyon Power Plant Process Protection System requires NRC approval prior to installation of the Vi0 Tricon Protection Sets. PG&E intends to submit the License Amendment Request package to the NRC for review. There are a number of regulatory requirements that must be satisfied, such as 10 CFR 50.55a(h), which incorporates IEEE Standard 603-1991 by reference, the General Design Criteria contained in Appendix A, and Appendix B quality and design criteria,as well as a number of regulatory guidance documents.

The regulatory guidance documents endorse consensus standards from the Institute of Electronics and Electrical Engineers (IEEE). The following standards and guidance are used as developmental references for all PPS Replacement Project documents.

It should be noted that the V10 Tricon platform safety evaluation assessed Invensys Operations Management against these same requirements and guidance. Therefore, the below list is focused on the PPS application development aspects, rather than on the entire set of documents expected for a Tier 2 review as defined in NRC DI&C-ISG-06.

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• NUREG-0800, Standard Review Plan, Chapter 7

" Branch Technical Position 7-14, Guidance on Software Reviews for Digital Computer-Based Instrumentation and Control Systems Regulatory Guides:

• 1.152, Criteria for Use of Computers in Safety Systems of Nuclear Power Plants

• 1.168, Verification, Validation, Reviews and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

• 1.169, Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

• 1.170, Software Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

• 1.172, Software Requirements Specifications for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

• 1.173, Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants

• 1.180, Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-related Instrumentation and Control Systems

& 1.209, Guidelines for Environmental Qualification of Safety-Related Computer-Based Instrumentation and Control Systems in Nuclear Power Plants Nuclear Regulatory Reports:

• NUREG/CR-6101, Software Reliability and Safety in Nuclear Reactor Protection Systems IEEE standards:

• 603, IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations 0 7-4.3.2, IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations

• 730, IEEE Standard for Quality Assurance Plans

• 828, IEEE Standard for Configuration Management Plans 0 829, IEEE Standard for Software Test Documentation o 830, IEEE Recommended Practice for Software Requirements Specifications 0 1012, IEEE Standard for Software Verification and Validation 0 1016, IEEE Recommended Practice for Software Design Descriptions 0 1028, IEEE Standard for Software Reviews and Audits

• 1058, IEEE Standard for Software Project Management Plans 0 1059, IEEE Guide for Software Verification and Validation Plans 0 1074, IEEE Standard for Developing Software Life Cycle Processes 0 1228, IEEE Standard for Software Safety Plans

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Project Management Plan Revision: I Page: 44 of 81 Date: 10/13/2011 Other standards:

• ANSI/ASME NQA-I -1983, Quality Assurance Program Requirements for Nuclear Facilities

• ANSI/ASME NQA-la-1983 (Addenda), Addenda to ANSI/ASME NQA-l-1983, Quality Assurance Program Requirements for Nuclear Facilities

• ANSI/ASME NQA-l-1994, the basis for the PPM 4.1.6. Company development procedures As an approved 10 CFR Part 50 Appendix B supplier, Invensys Operations Management adheres to the Invensys Nuclear Systems Integration Program Manual (NSIPM) to ensure compliance with NRC requirements regarding safety-related software development. The Invensys Operations Management Quality Procedures Manual (QPM), Project Procedures Manual (PPM),

and Manufacturing Department Manual (MDM) [Ref. 1.5.4.5] are the implementing procedures under the NSIPM. These procedures have been audited numerous times by third parties, including the NRC, and found compliant with a 10 CFR Part 50 Appendix B program as well as the NRC requirements for development of safety-related software.

IOM-Q2: This is the corporate policy manual applicable to nuclear safety-related activities at Invensys Operations Management facilities. The corporate Nuclear Quality Assurance Manual, IOM-Q2, governs the quality affecting activities performed by ND personnel at Invensys Operations Management facilities. Nuclear quality affecting activities are conducted in accordance with the IOM-Q2 and the Project Quality Plan, 993754-1-900.

NTX-SER-09-21: This is the Nuclear System Integration Program Manual. This program manual is the overarching lifecycle document for nuclear system integration projects, and it is currently being reviewed by the NRC as part of the V 10 Tricon safety evaluation.

Project Procedures Manual: This manual contains the ND implementing procedures under the NSIPM. The PPM describes the process lifecycle for nuclear safety system integration projects.

Quality Procedures Manual: Defines the quality (implementing) procedures for nuclear safety-related activities. This program manual is not specific to integration projects, but rather for any issue pertinent to nuclear safety-related activities, materials, and systems. NQA is predominantly responsible for the implementation of the QPM procedures.

Manufacturing Department Manual: This manual defines the manufacture, assembly, and test activities for Tricon components. It describes assembly and test of nuclear safety-related Tricon systems, including the tools for and controls over the manufacturing of printed circuit boards, modules, power supplies, and chassis, among other things. It also addresses receiving and shipment of materials.

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I Project Management Plan Revision: I Page: 45 of 81 Date:. 10/13/2011 4.1.7. Company programming style Coding Guidelines, 993754-1-907, contains guidance for the ND staff regarding TriStation 1131 project configuration, application code layout, tagname convention, and general guidance on programming style. The guidance also discusses proper usage of the PPS-specific function blocks in the VI 0 Tricon Protection Set application code. Product and technical advisories and bulletins (i.e., PANs, TAN, and TAB) relevant to the V 10 Tricon are listed along with necessary compensating actions.

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o ect Management Plan Revision: I Page: 46 of 81 Date: 10/13/2011 4.2. Software Documentation Appendix A contains a sequential list of documents that Invensys Operations Management produces for PG&E during the PPS Replacement. The sequence follows the lifecycle applied by Invensys Operations Management as discussed in Section 2.1.

The Software Development Plan, 993754-1-906, provides a detailed discussion of the technical documents required for the development of the V 10 Tricon Protection Set application code The PPS Replacement Project Software Verification and Validation Plan, 993754-1-802, provides additional details on the verification and validation activities performed by Nuclear IV&V and the documents generated during verification and validation activities. The Software Quality Assurance Plan, 993754-1-801, defines the quality affecting activities to be followed in the design, development, review, and testing for the PPS Replacement Project to ensure the specified quality requirements are met.

4.3. Project Support Functions Project support functions are those functions that are not performed by ND, but are essential to ensure the quality of the V 10 Tricon Protection Sets meet PG&E requirements. The below functions are inherent in the Invensys Operations Management Nuclear System Integration process and procedures.

4.3.1. Software Quality Assurance Software Quality Assurance is performed by the Nuclear Quality Assurance organization.

Project responsibilities are defined in the Software Quality Assurance Plan, 993754-1-801.

4.3.2. Software Configuration Management Software configuration management is the responsibility of ND. Nuclear IV&V verifies adequate configuration control and document the analysis in the project phase reports. Project responsibilities are defined in the Software Configuration Management Plan, 993754-1-909.

4.3.3. Software Verification and Validation (including testing)

Software Verification and Validation is the responsibility of Nuclear IV&V. Project responsibilities are defined in the Software Verification and Validation Plan, 993754-1-802.

4.3.4. Software Safety Management Software Safety Management is the responsibility of Nuclear IV&V. Project responsibilities are defined in the Software Safety Plan, 993754-1-911.

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Project Management Plan Revision: I Page: 47of81 Date: 10/13/2011 4.3.5. Software reviews and audits Software reviews are the responsibility of.ND and NQA. The Software Development Plan, 993754-1-906, describes the software reviews performed by ND. Reviews and audits performed by NQA are defined in the Software Quality Assurance Plan, 993754-1-801, and the Invensys Operations Management QPM.

4.3.6. User Software Documentation User software documentation for the VI 0 Tricon Protection Sets is not within the scope of the PPS Replacement Project Phase 1.

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5. Work Packages, Schedule, and Budget 5.1. Work Packages A work package is a subset of the PPS Replacement Project that can be assigned to a responsible individual/organization to complete a collection of work actions necessary for a specific result, such as: 1) develop a design output (e.g., document, application code); 2) review a design output (including documentation); or 3) complete a test (e.g., verification, validation). The work packages for the PPS Replacement Project are the lowest level of the work breakdown structure where both the cost and the duration can be reliably estimated.

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I Project Management Plan Revision: 1 Page: 63 of 81 I Date:. 10/13/2011 E-L 5.2. Dependencies As stated in Section 4.1, The PPS Replacement Project team adheres to the NSIPM and utilize the PPM as the implementing set of procedures. The PPM defines a modified Waterfall model.

At the macroscopic level, Figure 5 depicts the Waterfall lifecycle dependencies among the phases. These dependencies mean that Design Outputs from a subsequent project phase cannot be issued to Nuclear IV&V for independent review without first exiting the current phase. At the project implementation level, the various work packages related to planning and technical documents (Design Outputs) have dependencies within project phases. The significant dependencies are shown in Table 6.

EL The PPS Replacement Project Software Development Plan, 993754-1-906, contains more details on the dependencies and procedures for working with conditionally released Design Outputs.

5.3. Resource Requirements The PPS comprises four Protection Sets (I thru IV), with each set composed of three V10 Tricon chassis. Because of the differences between the Protection Sets, four sets of documents are developed - one of the following for each Protection Set:

" Hardware Requirements Specification

" Software Requirement Specification

" Software Design Description

" Application Program (PT2 file)

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6. Additional Components 6.1. Project Security Requirements Invensys Operations Management utilizes several layers of defense to ensure protection of sensitive customer information and equipment. Invensys document NTX-SER-1 0-14 [Ref.

1.5.4.6] describes the Invensys Operations Management security controls over personnel, physical, and network access to nuclear safety-related equipment and data. NTX-SER-1 0-14 describes the controls to ensure a secure development environment for the VI 0 Tricon platform to meet regulatory commitments to maintain conformance with Regulatory Guide 1.152. These same controls are utilized on the PPS Replacement Project supplemented with the following project specific requirements. Invensys document 993754-1-913, PPS Replacement Project:

Conformance to RG 1.152, provides the Regulatory Guide 1.152 compliance matrix for the PPS replacement project.

6.1.1. Physical Access Controls Physical Security of the Development Environment. Access into the Invensys Operations Management facility requires a picture badge and keycard. Guests, including PG&E visitors, must check in at the front desk to obtain a guest badge and meet their sponsor from Invensys Operations Management.

Entry to the ND test floor where the V10 Tricon Protection Sets is staged is limited to ND and Nuclear IV&V personnel only. Guests, including PG&E, are escorted at all times while on the ND test floor.

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V10 Tricon Protection Set Application Code. Role-Based access to the TriStation 1131 project file (PT2) for the Vi10 Tricon Protection Sets will be configured in accordance with the followin2:

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7. Appendices Appendix A - PPS Replacement Project Documents List Appendix B - PPS Replacement Project Document Numbering Scheme Appendix B - PPS Replacement Project Hours Tracking Sheets Appendix C - PPS Replacement Project Required Reading Lists

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I Project Management Plan - Appendix A Revision: 1 Page: 71 of 81 1 Date: 1 10/13/2011 Appendix A - PPS Replacement Project Documents List The table below lists the project documents generated for the PPS Replacement Project according to Project Phase. Not all documents are project deliverables to PG&E, indicated in the table below in the "Deliverable" column. The "PMP" and "SDP" columns indicate where the document is described, either the Project Management Plan, or the Software Development Plan, 993754-1-906. The w:

descriptions of project documents generated by Nuclear IV&V are in the relevant planning document (e.g., SVVP, SSP).

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I Project Management Plan - Appendix B Revision: I Page: 75 of 81 1 Date: 1 10/13/2011 Appendix B - PPS Project Document Numbering Scheme The document numbering scheme in the below table is taken from PPMs 3.0 and 4.0, with most of the listed documents from the latter. Table 4.2, Project Document Number Scheme, has been modified for the PPS Replacement Project. The table below includes documents from NRC Branch Technical Position 7-14 and Interim Staff Guidance 6.

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