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NHUG - Boston - 08/04/2010 1 Considerations for Operability of Chillers and Chilled Water Systems NHUG Summer Meeting August 4, 2010 Tim Mitchell Component Engineering Palo Verde Nuclear Generating Station

NHUG - Boston - 08/04/20101 Considerations for Operability of Chillers and Chilled Water Systems NHUG Summer Meeting August 4, 2010 Tim Mitchell Component

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NHUG - Boston - 08/04/2010 1

Considerations for Operability of Chillers

and Chilled Water Systems NHUG Summer Meeting

August 4, 2010

Considerations for Operability of Chillers

and Chilled Water Systems NHUG Summer Meeting

August 4, 2010

Tim MitchellComponent Engineering

Palo Verde Nuclear Generating Station

Tim MitchellComponent Engineering

Palo Verde Nuclear Generating Station

NHUG - Boston - 08/04/2010 2

What is OperabilityOPERABLE - OPERABILITY: A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety functions and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety functions are also capable of performing their related support functions.

To be operable the SSC must be capable of performing the safety functions specified by its design, within the required range of physical design conditions, initiation times, and mission times. In addition, the SSC must meet all Surveillance Requirements (SR) (as specified in SR 3.0.1). An SSC that does not meet an SR must be declared inoperable.(NUREGs 1430-1434 and RIS 2005-20, 3.8)

NHUG - Boston - 08/04/2010 3

Who Determines OperabilityWho Determines Operability

Operability Determination (OD):

The decision made by the SM or designated senior reactor operator (SRO) on the operating shift crew as to whether or not an identified or postulated condition has an impact on the operability of an SSC (i.e., operable or inoperable). For a determination that an SSC is operable, there must be a reasonable expectation that an SSC can perform its specified safety functions. (RIS 2005-20, 3.7)

Operability Determination (OD):

The decision made by the SM or designated senior reactor operator (SRO) on the operating shift crew as to whether or not an identified or postulated condition has an impact on the operability of an SSC (i.e., operable or inoperable). For a determination that an SSC is operable, there must be a reasonable expectation that an SSC can perform its specified safety functions. (RIS 2005-20, 3.7)

NHUG - Boston - 08/04/2010 4

Considerations for OperabilityConsiderations for Operability

• Design Control• Design Input• Design Process• Design Output

• Design Bases• Design Function• Design Values

• Supporting Design Information

• Licensing Bases

NHUG - Boston - 08/04/2010 5

Design ControlDesign Control

• Design Input

Design inputs identify what is intended to be accomplished

Definition (ANSI N45.2.11 and NEI 97-04, R1)

Those criteria, parameters, bases, or other design requirements upon which the detailed final design is based.

Design Bases are a subset of Design Inputs(ANSI N45.2.11 and NEI 97-04, R1)

• Design Input

Design inputs identify what is intended to be accomplished

Definition (ANSI N45.2.11 and NEI 97-04, R1)

Those criteria, parameters, bases, or other design requirements upon which the detailed final design is based.

Design Bases are a subset of Design Inputs(ANSI N45.2.11 and NEI 97-04, R1)

NHUG - Boston - 08/04/2010 6

Design ControlDesign Control

• Design Process

Confirms that the selected option meets goals. Numerous options may be considered

Definition (NEI 97-04, R1)

Documented design practices such as calculations, analysis, evaluations, technical review checklists, or other documented engineering activities that substantiates the final design.

• Design Process

Confirms that the selected option meets goals. Numerous options may be considered

Definition (NEI 97-04, R1)

Documented design practices such as calculations, analysis, evaluations, technical review checklists, or other documented engineering activities that substantiates the final design.

NHUG - Boston - 08/04/2010 7

Design ControlDesign Control

• Design Output

Describes the selected option such that it may be purchased and/or constructed. Basic technical communication

Definition (ANSI N45.2.11 and NEI 97-04, R1)

Documents such as drawings, specifications and other documents defining the technical requirements of structures, systems, and components

• Design Output

Describes the selected option such that it may be purchased and/or constructed. Basic technical communication

Definition (ANSI N45.2.11 and NEI 97-04, R1)

Documents such as drawings, specifications and other documents defining the technical requirements of structures, systems, and components

Design BasesDesign Bases The Design Bases is a subset of Design Inputs

Design bases means that information which identifies the specific function to be performed by the SSC of a facility and the specific value or range of values chosen for controlling parameters as references bounds of design.(ANSI N45.2.11 and NEI 97-04, R1)

The Design Bases is a subset of Design Inputs

Design bases means that information which identifies the specific function to be performed by the SSC of a facility and the specific value or range of values chosen for controlling parameters as references bounds of design.(ANSI N45.2.11 and NEI 97-04, R1)

NHUG - Boston - 08/04/2010 8

Design BasesDesign BasesDesign Bases Functions: Functions performed by SSCs that are (1) required by, or otherwise necessary to comply with, regulations, license condition, orders or technical specification, or (2) credited in the licensee safety analysis to meet NRC requirements.

Design Bases Values:

Values or range of values of controlling parameters established as reference bounds for design to meet design bases functional requirements. These values may be (1) established by NRC requirements, (2) derived from or confirmed from safety analysis, or(3) Chosen by the licensee from applicable code, standard or guidance document

Design Bases Functions: Functions performed by SSCs that are (1) required by, or otherwise necessary to comply with, regulations, license condition, orders or technical specification, or (2) credited in the licensee safety analysis to meet NRC requirements.

Design Bases Values:

Values or range of values of controlling parameters established as reference bounds for design to meet design bases functional requirements. These values may be (1) established by NRC requirements, (2) derived from or confirmed from safety analysis, or(3) Chosen by the licensee from applicable code, standard or guidance document

NHUG - Boston - 08/04/2010 9

NHUG - Boston - 08/04/2010 10

Design Input Design Process Design Output

Requirements•Design•Regulations•Other

Design Bases

•Calculations•Analysis•Evaluations•Others

•Specifications•Drawings•Lists•Other

Design Bases Function

Design Bases Value

Design control produces design documents

When the design bases are design inputs, the resulting documents are termed “ supporting design information”

Definition (NEI 97-04, R1)

The substantial set of detailed design information underlying 10 CFR 50.2 design bases, including other design inputs, design analyses and design output documents. Supporting design information may be contained in the UFSAR (as designed description) or other documents either docketed with the NRC or retained by the Licensee

Design control produces design documents

When the design bases are design inputs, the resulting documents are termed “ supporting design information”

Definition (NEI 97-04, R1)

The substantial set of detailed design information underlying 10 CFR 50.2 design bases, including other design inputs, design analyses and design output documents. Supporting design information may be contained in the UFSAR (as designed description) or other documents either docketed with the NRC or retained by the Licensee

NHUG - Boston - 08/04/2010 11

Supporting Design InformationSupporting Design Information

Current Licensing BasesCurrent Licensing BasesThe CLB is a set of NRC requirements applicable to a specific plant, plus a Licensee’s docketed and currently effective written commitments for ensuring compliance with, and operation within, applicable NRC requirements and the plant specific design bases, including all modifications and additions to such commitments over the life of the facility operating license.(RIS 2005-20, 3.1)

The CLB is a set of NRC requirements applicable to a specific plant, plus a Licensee’s docketed and currently effective written commitments for ensuring compliance with, and operation within, applicable NRC requirements and the plant specific design bases, including all modifications and additions to such commitments over the life of the facility operating license.(RIS 2005-20, 3.1)

NHUG - Boston - 08/04/2010 12

NHUG - Boston - 08/04/2010 13

Design Input Design Input Design Input

Requirements•Design•Regulations•Other

•Calculations•Analysis•Evaluations•Others

•Specifications•Drawings•Lists•Other

Licensing Bases

UFSAR

Design Bases• Design Bases Function• Design Bases Values

Supporting Design Information

NHUG - Boston - 08/04/2010 14

FSAR Information

Part of the Original Application

Contained:Descriptive InformationDesign Basis and Limits on OperationsFacility Safety Analysis

10 CFR 50.71(e) Updates FSAR to create USFAR

NHUG - Boston - 08/04/2010 15

10 CFR 50, Appendix AGeneral Design Criteria

10 CFR 50, Appendix A, Criterion 19:

A control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss-of-coolant accidents. Adequate radiation protection shall be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem whole body, or its equivalent to any part of the body, for the duration of the accident. Equipment at appropriate locations outside the control room shall be provided (1) with a design capability for prompt hot shutdown of the reactor, including necessary instrumentation and controls to maintain the unit in a safe condition during hot shutdown, and (2) with a potential capability for subsequent cold shutdown of the reactor through the use of suitable procedures.

NHUG - Boston - 08/04/2010 16

Basis Design and Licensing Practices(RIS 2005-20, Section 3.4 and 6.3)

Required SSC Function

Licensing Level / Full Qualification

Design Requirement

Actual SSC Capacity

NHUG - Boston - 08/04/2010 17

10 CFR 50, Appendix BQuality Assurance Requirements10 CFR 50, Appendix B

Quality Assurance Requirements

10 CFR 50, Appendix B, Criterion III – Design Control- Measures shall be established to assure that applicable regulatory

requirements and design bases, … are correctly translated into specification, drawings, procedures, and instructions

- Measures shall be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the SSC

- Where a test program is used to verify the adequacy of a specific design feature

- Design control measures shall be applied to items such as the following: Compatibility of materials; accessibility for in-service inspection, maintenance and repair; and delineation of acceptance criteria for inspections and tests.

10 CFR 50, Appendix B, Criterion III – Design Control- Measures shall be established to assure that applicable regulatory

requirements and design bases, … are correctly translated into specification, drawings, procedures, and instructions

- Measures shall be established for the selection and review for suitability of application of materials, parts, equipment, and processes that are essential to the safety-related functions of the SSC

- Where a test program is used to verify the adequacy of a specific design feature

- Design control measures shall be applied to items such as the following: Compatibility of materials; accessibility for in-service inspection, maintenance and repair; and delineation of acceptance criteria for inspections and tests.

NHUG - Boston - 08/04/2010 18

Basis Design and Licensing Practices(RIS 2005-20, Section 3.4 and 6.3)

Actual SSC Capacity

Design Requirement

Licensing Level / Full Qualification

Required SSC Function

Degraded

Non-Conforming

INOP

NHUG - Boston - 08/04/2010 19

Fundamental Questions to Equipment Degradation

EquipmentDegradation

Can it be relied upon?

If conditions worsen, are we prepared?

What are we goingto do about it?

NHUG - Boston - 08/04/2010 20

Design Requirements

What is required to be

there

What we say is There

What is There

Facility Configuration Information

Physical Configuration

Configuration Management – 3 Ball Model(ANSI/NIRMA CM 1.0-2000)

Work Processes must assure that:-Elements conform all the time- All Changes are Authorized- Conformance is Auditable

Must Conform

NHUG - Boston - 08/04/2010 21

SAFELY and efficientlygenerate electricity for

the long term

SAFELY and efficientlygenerate electricity for

the long term

NHUG - Boston - 08/04/2010

22

Questions &

Discussion

Questions &

Discussion

NHUG - Boston - 08/04/2010 23

10 CFR 50 Appendix B10 CFR 50 Appendix B

I. Organization II. Quality Assurance Program III. Design Control IV. Procurement Document Control V. Instructions, Procedures, and

Drawings VI. Document Control VII. Control of Purchased Material,

Equipment, and Services VIII. Identification and Control of

Materials, Parts, and ComponentsIX. Control of Special Processes

I. Organization II. Quality Assurance Program III. Design Control IV. Procurement Document Control V. Instructions, Procedures, and

Drawings VI. Document Control VII. Control of Purchased Material,

Equipment, and Services VIII. Identification and Control of

Materials, Parts, and ComponentsIX. Control of Special Processes

X. Inspection XI. Test Control XII. Control of Measuring and Test

Equipment XIII. Handling, Storage and Shipping XIV. Inspection, Test, and Operating

Status XV. Nonconforming Materials, Parts,

or Components XVI. Corrective Action XVII. Quality Assurance Records XVIII. Audits

X. Inspection XI. Test Control XII. Control of Measuring and Test

Equipment XIII. Handling, Storage and Shipping XIV. Inspection, Test, and Operating

Status XV. Nonconforming Materials, Parts,

or Components XVI. Corrective Action XVII. Quality Assurance Records XVIII. Audits

Build &Maintain

Quality Assurance Requirements

NHUG - Boston - 08/04/2010 24

10 CFR 50 Appendix A10 CFR 50 Appendix A

I. Quality Standards and Records2. Design Bases – Natural Phenomena3. Fire Protection4. Environmental & Dynamic Effect5. Sharing of SSCs10. Reactor Design11. Reactor Inherent Protection12. Suppression of Reactor Power Osc.13. Instrument and Control14. Reactor Coolant Press. Boundary15. Reactor Coolant System Design16. Containment Design17. Electrical Power Systems18. Inspection and Test of Power Syst.

I. Quality Standards and Records2. Design Bases – Natural Phenomena3. Fire Protection4. Environmental & Dynamic Effect5. Sharing of SSCs10. Reactor Design11. Reactor Inherent Protection12. Suppression of Reactor Power Osc.13. Instrument and Control14. Reactor Coolant Press. Boundary15. Reactor Coolant System Design16. Containment Design17. Electrical Power Systems18. Inspection and Test of Power Syst.

19. Control Room20. Protection System Functions21. Protection System Reliability &

Test22. Protection System Independence23. Protection System Failure Modes24. Separation and Protection &

Control Systems25. Reactivity Control Malfunctions26. Reactivity Control Redundancy27. Reactivity Control Syst. Capability28. Reactivity Limits29. Protection against Anticipated

Operational Occurrences

19. Control Room20. Protection System Functions21. Protection System Reliability &

Test22. Protection System Independence23. Protection System Failure Modes24. Separation and Protection &

Control Systems25. Reactivity Control Malfunctions26. Reactivity Control Redundancy27. Reactivity Control Syst. Capability28. Reactivity Limits29. Protection against Anticipated

Operational Occurrences

Design Inputs

General Design Criteria