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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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Presentation on theme: "NHUG - Boston - 08/04/20101 Considerations for Operability of Chillers and Chilled Water Systems NHUG Summer Meeting August 4, 2010 Tim Mitchell Component."— Presentation transcript:

1 NHUG - Boston - 08/04/20101 Considerations for Operability of Chillers and Chilled Water Systems NHUG Summer Meeting August 4, 2010 Tim Mitchell Component Engineering Palo Verde Nuclear Generating Station Tim Mitchell Component Engineering Palo Verde Nuclear Generating Station

2 NHUG - Boston - 08/04/20102 What is Operability OPERABLE - 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)

3 NHUG - Boston - 08/04/20103 Who 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)

4 NHUG - Boston - 08/04/20104 Considerations for Operability Design Control Design Input Design Process Design Output Design Bases Design Function Design Values Supporting Design Information Licensing Bases

5 NHUG - Boston - 08/04/20105 Design 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)

6 NHUG - Boston - 08/04/20106 Design 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.

7 NHUG - Boston - 08/04/20107 Design 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

8 Design 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 - 08/04/20108

9 Design Bases 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 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 - 08/04/20109

10 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

11 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 - 08/04/201011 Supporting Design Information

12 Current Licensing Bases 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) 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 - 08/04/201012

13 NHUG - Boston - 08/04/201013 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

14 NHUG - Boston - 08/04/201014 FSAR Information Part of the Original Application Contained: Descriptive Information Design Basis and Limits on Operations Facility Safety Analysis 10 CFR 50.71(e) Updates FSAR to create USFAR

15 NHUG - Boston - 08/04/201015 10 CFR 50, Appendix A General 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.

16 NHUG - Boston - 08/04/201016 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

17 NHUG - Boston - 08/04/201017 10 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.

18 NHUG - Boston - 08/04/201018 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

19 NHUG - Boston - 08/04/201019 Fundamental Questions to Equipment Degradation Equipment Degradation Can it be relied upon? If conditions worsen, are we prepared? What are we going to do about it?

20 NHUG - Boston - 08/04/201020 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

21 NHUG - Boston - 08/04/201021 SAFELY and efficiently generate electricity for the long term SAFELY and efficiently generate electricity for the long term

22 NHUG - Boston - 08/04/2010 22 Questions & Discussion

23 NHUG - Boston - 08/04/201023 10 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 Components IX. 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 Components IX. 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 Build & Maintain Quality Assurance Requirements

24 NHUG - Boston - 08/04/201024 10 CFR 50 Appendix A I. Quality Standards and Records 2. Design Bases – Natural Phenomena 3. Fire Protection 4. Environmental & Dynamic Effect 5. Sharing of SSCs 10. Reactor Design 11. Reactor Inherent Protection 12. Suppression of Reactor Power Osc. 13. Instrument and Control 14. Reactor Coolant Press. Boundary 15. Reactor Coolant System Design 16. Containment Design 17. Electrical Power Systems 18. Inspection and Test of Power Syst. I. Quality Standards and Records 2. Design Bases – Natural Phenomena 3. Fire Protection 4. Environmental & Dynamic Effect 5. Sharing of SSCs 10. Reactor Design 11. Reactor Inherent Protection 12. Suppression of Reactor Power Osc. 13. Instrument and Control 14. Reactor Coolant Press. Boundary 15. Reactor Coolant System Design 16. Containment Design 17. Electrical Power Systems 18. Inspection and Test of Power Syst. 19. Control Room 20. Protection System Functions 21. Protection System Reliability & Test 22. Protection System Independence 23. Protection System Failure Modes 24. Separation and Protection & Control Systems 25. Reactivity Control Malfunctions 26. Reactivity Control Redundancy 27. Reactivity Control Syst. Capability 28. Reactivity Limits 29. Protection against Anticipated Operational Occurrences Design Inputs General Design Criteria


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