ML20043F652

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Training Material for E-111 Emergency Diesel Generator Course, Chapter 1 (7-18), Diesel Generator as Emergency Power Sources
ML20043F652
Person / Time
Issue date: 02/12/2020
From:
Office of the Chief Human Capital Officer, Woodard Corp
To:
Gary Callaway
Shared Package
ML20043F634 List:
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Download: ML20043F652 (12)
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Emergency Diesel Generator Diesel Generators as Emergency Power Sources

1. DIESEL GENERATORS AS 3. Why diesel engines are used as the EMERGENCY POWER SOURCES prime movers for emergency power generators instead of alternative Learning Objectives engine designs.

The predominant means of supplying onsite 4. An overview of the regulations, codes, emergency (standby) electrical power for guides, and standards that establish nuclear power plants (NPPs) is emergency the design basis for these emergency diesel generators (EDGs). Therefore, diesel power systems.

generator sets are the specific focus of this NRC training course. Upon completing this 5. How the above documents are lesson students will understand the translated into the licensee's fundamental criteria used in selection of application and design for a nuclear emergency diesel generators for onsite power station.

electric power supplies at NPP's. That will include an overview of the primary federal 6. The major components of a diesel regulations, regulatory guides, codes, and generator system, as well as some industry standards applicable to these considerations involving site facilities essential safety systems. that support EDG operation.

In addition, this lesson will conclude with a NOTE: Many participants in this course will summary overview of the EDG and its already be very familiar with the regulatory associated systems and components, as criteria applicable to EDGs. However, the well as remarks on how they interface with NRC requires such documentation to be site facilities. For the EDG to be capable of part of the course because some attendees performing its design basis function, all of its may be relatively new on the job. Even on-skid and off-skid support systems and those with considerable experience may components must also meet their own benefit from a brief review of the underlying design basis functional requirements. documentation. This Chapter provides an overview of the fundamental requirements The primary objective of this lesson is to set relevant to EDGs in nuclear service. For the stage for later Chapters by giving both new and experienced staff it can serve students a fundamental understanding of: as a convenient reference.

1. The basic regulatory requirements 1.1 Regulatory Basis for Redundant, establishing the need for redundant Independent Power Systems power systems (onsite and offsite) for operating nuclear power plants. Federal regulations applicable to nuclear power plants and, hence, onsite emergency
2. Three fundamental performance power supplies, originate in Title 10, Part 50 requirements that emergency diesel of the Code of Federal Regulations (10 CFR generators (EDGs) must meet. 50). This document is the successor to the Rev 3/16 1-1 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources Atomic Energy Commission (AEC) General accident but is considered a precursor to Design Criteria of 10 July 1967, to which possible core damage and, therefore, is part many early Nuclear Power Plants, meaning of various postulated accident scenarios.

those starting construction prior to 1972, were licensed. Supporting regulatory Independence is the absence of shared guides, codes, and industry standards used components that could result in the to implement these federal regulations are simultaneous failure of both units. That briefly described in this Chapter. includes physical and electrical separation, such that a transformer or cable tray fire, for One of the most important nuclear power example, would not impact operation of the plant safety requirements is for redundant, other emergency diesel generator.

and independent, power systems. This is contained in 10 CFR 50 Appendix A, Redundancy is required to achieve the General Design Criterion (GDC) 17, which desired operational reliability, and also to specifically requires both off-site and onsite accommodate "down time" for testing and power systems "to permit functioning of maintenance. This means a dual EDG structures, systems, and components installation, where the required power is important to safety." available with either unit out of service.

GDC 17 further states that onsite electric Testability is somewhat self-explanatory.

power supplies, including the distribution EDG testing is discussed in Chapter 11.

system, shall have sufficient independence, redundancy, and testability to perform their 1.2 Regulatory Guide (RG) 1.9 and the safety functions assuming a single failure. Three Fundamental Performance This requires emergency power systems to Requirements for EDGs be designed such that failure of one will not adversely impact the other (more about that Regulatory Guide 1.9, Rev 4 (March 2007) later). Each electric power source must be is "Application and Testing of Safety-capable of providing the capacity and Related Diesel Generators in Nuclear Power capability to assure that: Plants" (new title for this edition) and evolved from AEC Safety Guide 9. A copy

1. "Fuel design limits and design conditions of RG 1.9, Rev 4 is included in this Manual of the reactor coolant pressure boundary as Appendix B. It covers three fundamental are not exceeded" for any anticipated performance requirements every EDG must occurrences, and meet to perform its design function per referenced Standards. They are as follows:
2. The "core is cooled and containment integrity and other vital functions are 1. The unit must be able to "...start and maintained in the event of postulated accelerate a number of large motor loads accidents." in rapid succession while maintaining voltage and frequency within acceptable Loss of Offsite Power (a LOOP) is not an limits...."

Rev 3/16 1-2 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources

2. The unit must also be able to "...provide requirement set for the onsite emergency power promptly to engineered safety power source to be ready to accept loads features if a loss of offsite power and an following loss of offsite power. So, two accident occur during the same time fundamental questions asked in the period...." selection of the emergency onsite power source are:
3. The unit must "...supply power continuously to the equipment needed to 1. Based on the plant-specific accident maintain the plant in a safe condition...." analysis, how fast must electrical power be restored to support Emergency Core A later chapter will cover the challenge of Cooling System (ECCS) operation to complying with the first of these three prevent core damage (i.e., to keep from performance requirements (EDG loading). exceeding peak fuel clad temperature)?

Item (2) immediately above introduces the Stated another way, how soon must the requirement to cope with two events emergency electrical source be running (failures / accidents) that occur either with breaker closed, ready to accept the simultaneously or with one following the required step loads? By analysis, many other. Finally, please note Item (3) has no of the reactor designs required power to endurance time. "Continuously" is open- be available within 15 to 30 seconds ended and effectively means "until normal after receiving a start signal. Although power is restored" (however long it takes). this time included the inherent delay for protective circuits to sense the loss of 1.3 Why DIESEL Generators? power and initiate a start signal to the emergency power source, the bulk of it There is no requirement that emergency represented the start-up time necessary diesel generators must be used for onsite to spin up the generator, energize its electric power supplies at nuclear power field, and get it switched on line.

plants. Hence, a natural question could be, why have diesel generators been selected To assure an acceptable margin of safety, as the predominant means of supplying this the accident analysis for many reactor power? Some other potential prime movers designs assumed emergency generator that could have been selected are: power would be available within 10 seconds.

NOTE: In some plants where nuclear fuel

  • Gasoline / Gaseous Fuel Engines upgrades have been implemented and new
  • Gas Turbine Engines core damage accident analysis calculations
  • Hydro-electric generation performed, they have frequently supported
  • Steam-driven turbine generator a corresponding increase in the delay time
  • Possible hybrid arrangement of stored for emergency generator availability.

energy and a slower-response system. However, it was not unusual to have the containment integrity support systems (e.g.

The answer to why diesel generators can Containment Spray System) become the usually be found by looking at the time new limiting consideration.

Rev 3/16 1-3 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources

2. Once the accident analysis has set the Criterion 38: Reliability and Testability of time limitations on restoration of power to Engineered Safety Features. All vital safety equipment, the only engineered safety features shall be remaining question is what power designed to provide high functional reliability supplies are readily available that could and ready testability. In determining the reliably supply the needed power within suitability of a facility for proposed site, the those time limitations? degree of reliance upon the acceptance of the inherent and engineered safety afforded With the exception of large gas engines, by the system, including the engineered which have other onsite energy availability safety features, will be influenced by the and safety concerns, none of the sources known and the demonstrated performance listed above could reliably match the capability and reliability of the systems, and required response time and output power as by the extent to which the operability of such well as diesel generators could. To use a systems can be tested and inspected where football analogy, they have the muscle to do appropriate during the life of the plant.

the job and the speed to get there in time.

Furthermore, diesel generators were readily Criterion 39: Emergency Power for available and their proven reliability had Engineered Safety Features. Alternate already gained them acceptance as power systems shall be provided and emergency power supplies under the Naval designed with adequate independency Reactors program. (independence), redundancy, capacity, and testability to permit the functioning required Therefore, although other factors such as of the engineered safety features. As a site location and engine type familiarity had minimum, the onsite power system and the some influence, the answers to the two offsite power system shall each, questions above ultimately decided the independently, provide this capacity question of what type of generators to use assuming a failure of a single active for NPP applications. Fundamentally, the component in each power system.

decision became what diesel generators will best fill our emergency power needs?" Criterion 48: Testing of Operational Sequence of Emergency Core Cooling 1.4 An Overview of EDG Regulations, Systems. A capability shall be provided to Guides, Codes, and Standards test under conditions as close to design as practical the full operational sequence that 1.4.1 Early Plants Licensed under AEC would bring the emergency core cooling General Design Criteria (i.e., those systems into action, including the transfer to starting construction before 1972) alternate power sources.

The primary design criteria applicable from Even the casual reader will note the close early AEC regulatory requirements...those similarity between Criterions 38, 39, 48 and still being the GDC of record at many older parts of 10 CFR 50 Appendix A, GDC 17.

nuclear power plantsare as follows:

Rev 3/16 1-4 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources The AEC had other GDC's which formed the periodically (1) the operability and functional basis for those currently appearing in 10 performance of the components of the CFR 50 Appendix A. Likewise, AEC Safety systems, such as onsite power sources, Guides that were used to interpret and relays, switches, and buses, and (2) the implement those early design criteria operability of the systems as a whole and, became the foundation for current NRC under conditions as close to design as Regulatory Guides. Some early NPP's have practical, the full operation sequence that voluntarily adopted portions of current brings the systems into operation, including requirements applicable to EDGs, such as operation of applicable portions of the IEEE 387 (discussed later). Therefore, no protection system, and the transfer of power further time will be spent on early criteria. among the nuclear power unit, the offsite power system, and the onsite power system.

1.4.2 Plants Licensed by NRC using the GDC of 10 CFR 50 Appendix A Criterion 33, 34, 35, 38, 41, and 44:

(construction began 1972 or later) Establish the criteria for specific safety systems to be able to perform their required As explained in Section 1.1, the 10 CFR 50 functions even assuming a Loss of Offsite Appendix A General Design Criteria are the Power (LOOP) and a single failure of a successor documents to AEC GDC's. source of onsite power (e.g. one EDG Train Those listed below provide primary design or Division).

criteria for EDGs. Some others that have relevant secondary criteria such as for the 1.4.3 "Top Level" NRC Regulations that physical plant design will not be described Pertain to NPP Licensing, Construction, (e.g., GDC 2, 4, 5, and 50). Commissioning, and Operation:

Criterion 17: "Electrical Power Systems"

To recap the previous discussions on page 1-2, GDC 17 states the fundamental safety

  • 10 CFR 50.23 Construction permits. A mission for on-site (and off-site) electrical permit for the construction of a systems, as well as the key attributes of production or utilization facility will be independence, redundancy, and testability. issued prior to the issuance of a license if the application is otherwise acceptable, Criterion 18: "Inspection and Testing of and will be converted upon due Electrical Power Systems" Electric power completion of the facility and systems important to safety shall be Commission action into a license as designed to permit appropriate periodic provided in 50.56 of this part.

inspection and testing of important areas and features, such as wiring, insulation,

  • 10 CFR 50.34 - Details the contents of connections, and switchboards, to assess applications; technical information. For the continuity of the systems and the purposes of this course, the following condition of their components. The systems excerpts from this document are of shall be designed with a capability to test particular significance to EDG selection:

Rev 3/16 1-5 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources

"(a) Preliminary safety analysis report.

  • 10 CFR 50.36 - This document covers Each application for a construction technical specifications intended to permit shall include a preliminary safety define safety system limiting conditions analysis report. (3) The preliminary for operation that may prevent design design of the facility including: and license safety function. More about this topic appears later in the Chapter, (i) The principal design criteria for the under Regulatory Guides 1.93, 1.156.

facility. Appendix A, General Design Criteria for Nuclear Power Plants,

establishes minimum requirements for the principal design criteria for water-

cooled nuclear power plants similar in "Each operating license for a boiling or design and location to plants for which pressurized water-cooled nuclear power construction permits have previously facility is subject to the conditions in been issued by the Commission and paragraphs (f)* and (g)* of this section provides guidance to applicants for and each construction permit for a construction permits in establishing utilization facility is subject to the principal design criteria for other types of following conditions in addition to those nuclear power units; specified in §50.55:

(ii) The design bases and the relation of "(a)(1) Structures, systems, and the design bases to the principal design components must be designed, criteria; fabricated, erected, constructed, tested, and inspected to quality standards (iii) Information relative to materials of commensurate with the importance of construction, general arrangement, and the safety function to be performed."

approximate dimensions, sufficient to provide reasonable assurance that the final design will conform to the design

  • NOTE: Items (f) and (g) above refer to bases with adequate margin for In-service inspection requirements.

safety..."

"(b) Final safety analysis report. Each construction permit to license; or application for a license to operate a amendment of license. Upon completion facility shall include a final safety of the construction or alteration of a analysis report. The final safety analysis facility, in compliance with the terms and report shall include information that conditions of the construction permit and describes the facility, presents the subject to any necessary testing of the design bases and the limits on its facility for health or safety purposes, the operation, and presents a safety analysis Commission will, in the absence of good of the structures, systems, and cause shown to the contrary issue a components and of the facility as a license of the class for which the whole" construction permit was issued or an Rev 3/16 1-6 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources appropriate amendment of the license,

Power Sources and Between Their

  • 10 CFR 50.57 Issuance of operating Distribution Systems," (Formerly Safety license. Guide 6). Each power supply (e.g. EDG) shall have the "...capability of performing
  • 10 CFR 50.63 Loss of All Alternating as a redundant unit of a standby power Current Power (Station Blackout). This supply." Therefore, mechanically and is an additional source of functional electrically, the Emergency Diesel regulatory requirements involving Generator must be able to operate Emergency Diesel Generators. Target during and after any design basis event EDG reliability is used to determine without support from a preferred power station blackout coping capability. source.
  • Regulatory Guide 1.9 - "Selection, Design Criteria. - This was previously Design, Qualification, and Testing of discussed in this Chapter. See Sections Emergency Diesel Generator Units Used 1.1, 1.4.2, etc. as Class 1E Onsite Electric Power Systems at Nuclear Power Plants,"

1.5 Implementation of These Criteria (formerly AEC Safety Guide 9). RG 1.9, into Site-Specific System Design Rev 4 (March, 2007) was introduced in 1.2 of this Chapter and discusses three 1.5.1 Overview of Primary Regulatory fundamental performance requirements Guides and Referenced Standards for EDGs. It incorporates portions of Used to Implement Design Criteria GDC 17 Electric Power Systems, and GDC 18 Inspection and Testing of For early nuclear plants licensed under AEC Electrical Power Systems. RG 1.9 also General Design Criteria the applicable references these IEEE documents:

design requirements were implemented via the AEC's Safety Guides. With transition of

  • IEEE 308 - "Standard Criteria for Class the criteria to 10 CFR 50, Appendix A, the 1E Power Systems for Nuclear Power NRC's Regulatory Guides (RG's) became Generating Stations." In practice, the means to implement requirements into Section 6.2.4, "Standby Power NPP design. Supplies," of the IEEE 308 standard is implemented through IEEE 387.

Under both of these regimes, codes and standards developed by industry groups or

national organizations (e.g., ANSI, IEEE, "IEEE Standard Criteria for Diesel-NFPA, etc.) were incorporated into the Generator Units Applied as Standby regulations. This training course provides Power Supplies for Nuclear Power just an overview of the more important Generating Stations." The parent documents relevant to EDGs. standard to IEEE 387-1995 (and 1984) is Rev 3/16 1-7 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources IEEE Standard 308-1980. IEEE 387

  • Regulatory Guide 1.32 - "Criteria for expands on IEEE 308, Section 6.2.4, Safety-Related Electric Power Systems "Standby Power Supplies" with respect for Nuclear Power Plants." RG 1.32 to application of diesel generator units. seeks to implement compliance with portions of the following document:

This standard provides many amplifying and supplemental details, in conjunction

  • GDC 17 - Electric Power Systems.

with Regulatory Guide 1.9, regarding the design, testing, and qualification of

  • IEEE 308 - "Standard Criteria for Class Emergency Diesel Generators used in 1E Power Systems for Nuclear Power nuclear applications. Not all plants are Generating Stations." Invoked by RG committed to use IEEE 387, especially 1.32, this Standard specifies capabilities those licensed prior to 1972. IEEE 387 of a Standby Power Supply (e.g. EDG) to also endorses several other codes and serve as an independent / redundant unit standards including the Diesel Engine (or Train or Division) of power.

Manufacturers Association (DEMA) guide Standard Practices for Low and Medium

Engines, last revised in 1972. DEMA is Deals more with the physical than no longer an active association but its functional independence or separation guidelines are still relevant to the design between classes and Trains or Divisions.

criteria applied to EDGs installed at most The criteria are intended to ensure US nuclear power plants. Post-1977 adequate independence through versions of the IEEE 387 standard also physical separation and barriers to outline criteria for initial EDG first unit assure continued function under all qualification tests for NPP service. postulated plant events. RG 1.75 also These will be discussed in Chapter 11. invokes the following Standards:

NOTE: IEEE 387-1995 gives the design

  • IEEE 384 - "Standard Criteria for basis for nuclear service EDGs as 4000 Independence of Class 1E Equipment starts and 6000 operating hours, over a and Circuits.

specified service life of 40 years. Such intermittent duty is very different from Regulatory Guide 1.93 - "Availability of typical commercial service! This course Electric Power Sources." RG 1.93 will point out the profound impact that provides guidance for the application of has on EDG maintenance and testing, as 10 CFR 50.36 (above), particularly well as some design implications. A section 50.36(c)(2), "Limiting Conditions copy of IEEE 387-1995 is Appendix 3. for Operation," (LCO) when less than the number of power supplies required by

Class 1E Equipment for Nuclear Power Generating Stations." Regulatory Guide 1.108 - "Periodic Rev 3/16 1-8 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources Testing of Diesel Generator Units Used 1.5.2 Licensee's Implementation of EDG as Onsite Electric Power Systems at System Design Criteria Nuclear Power Plants." (Withdrawn.

See 58 FR 41813, 5 August 1993. It should be evident the criteria for design Superseded by Regulatory Guide 1.9, have evolved and what is applicable to a Revision 3). specific plant depends to a large extent on the time frame in which it was constructed NOTE: Some of the early design plants and licensed. Licensees take whatever previously committed to Regulatory documents are applicable at the time their Guide 1.108 only adopted portions of project moves forward, including the proper Regulatory Guide 1.9. revision dates, and implement them into their plant-specific design and operations.

Regulatory Guide 1.137 - "Fuel-Oil The resulting EDG documents include:

Systems for Standby Diesel System drawings and isometrics Generators." RG 1.137 also seeks to implement compliance with portions of System specifications GDC 17, Electric Power Systems Equipment specification (above), and it endorses the following Purchase specifications standard for regulatory compliance. Installation and Test Criteria ANSI N195 / ANS 59.51 - "Fuel Oil The design criteria which were applied to the Systems for Emergency Diesel plant are typically listed or referenced in the Generators." licensee design and equipment specifications and the Final safety Analysis Regulatory Guide 1.155 - "Station Report / Updated Final Safety Analysis Blackout." This Guide seeks to Report (FSAR / UFSAR).

implement compliance with all of:

Highlights of Licensee FSAR / UFSAR:

10 CFR 50.63, "Loss of all Alternating Current Power."The specified station FSAR / UFSAR Chapter 1, Plant blackout duration shall be based on the (Design)

Description:

Typically following factors: outlines the design criteria applicable to the plant design, construction, and

"(i) The redundancy of the onsite operation. NOTE: Subsequent updates emergency ac power sources; of regulatory criteria may be difficult, or (ii) The reliability of the onsite emergency impractical, for a licensee to back-fit.

ac power sources;"

The licensees Final Safety Analysis RG 1.155 also invokes NUMARC 8700: Report or Updated Final Safety Analysis Guidlines and Technical Bases for Report (FSAR/ UFSAR) will document NUMARC Initiatives Addressing Station the regulatory requirements followed in Blackout at Light Water Reactors. their licensing process.

Rev 3/16 1-9 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources FSAR / UFSAR Chapter 8, Section Additional limiting requirements for the 8.3(4), Onsite Emergency (AC) Power availability of Emergency Power supplies Systems: The bulk of the plant-specific are contained within the Technical design criteria applied by the licensee to Specifications for the supported safety the EDGs is typically included here. systems. These Technical Specs typically identify the plant mode and required number FSAR / UFSAR Chapter 9, Plant of available Trains or Divisions of that safety Auxiliary Systems: Typically includes system. Reg Guide 1.93 (see previous) design criteria for many of the major should be referenced to assist with EDG support systems such as Fuel Oil, determining NPP implementation and Jacket Water, Lube oil, and Starting Air. compliance with Electric Power Technical Specification LCOs, including Emergency All licensees were required to develop plant Diesel Generators.

Technical Specifications that prescribe plant Limiting Conditions of Operation (LCOs) for FSAR/USFAR Chapter 14, Accident required safety systems. As outlined in 10 (Safety) Analysis: The following CFR 50.36, "The technical specifications constitute a few of the generic plant will be derived from the analyses and design basis events or accidents where evaluation included in the safety analysis Emergency Diesel generators are report, and amendments thereto, submitted required to mitigate the resulting effects:

pursuant to 50.34. (c) Technical specifications will include items in the Loss of Coolant Accident (LOCA) with following categories: LOOP: Safety Injection Actuation (SIAS) due to large or small break Loss of (1) Safety limits, limiting safety system Coolant Accident, with a concurrent or settings, and limiting control settings. subsequent Loss of Offsite (preferred)

(i)(A) Safety limits for nuclear reactors are Power (LOCA / LOOP or SI / LOOP).

limits upon important process variables that are found to be necessary to reasonably NOTE: Many plants were originally protect the integrity of certain of the physical designed for a LOCA with a concurrent barriers that guard against the uncontrolled LOOP in such a manner that other release of radioactivity. If any safety limit scenarios may not have been is exceeded, the reactor must be shut adequately addressed. Be aware of down." associated issues contained within IN 93-17 and TI 2515 / 176 regarding LOCA The following are key typical Technical with a subsequent LOOP, and LOOP Specifications which apply to EDGs: with subsequent LOCA.

Loss of Offsite Power (LOOP): Loss of 3 / 4.8: Electrical Power Systems normal and preferred electric power to 3 / 4.8.1: AC Sources - Operating station auxiliaries.

3 / 4 .8.2: AC Sources - Shutdown NOTE: Cases have been identified Rev 3/16 1-10 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources where actual monitoring for loss of offsite Generator: Serving as the interconnected power was not being performed at the emergency electrical source, the generator 4KV class 1E buses. Then it would be follows (responds to) the electrical load possible for the 1E bus to lose power or demands placed on the ESF bus. Major become disconnected from the offsite components of generators are:

(preferred) source with no automatic initiation of the EDG to restore power.

  • Generator rotor and exciter High Energy Line Break (HELB): Steam
  • Voltage Regulator or feedwater system piping failure with
  • EDG emergency trip controls and relays Loss of Offsite Power (LOOP).

NOTE: Issues have been identified Diesel Engine: Most of the diesel engines where at least one of the Emergency installed at current nuclear power plants Diesel Generators could be adversely were selected using guidance of the Diesel impacted by the postulated HELB and Engine Manufacturers Association (DEMA).

was not previously protected against it. Their "Standard Practices for Low and Medium Speed Diesel and Gas Engines, The preferred plant power source is always DEMA-1972, was the 6th edition of this the normal offsite power supply, as defined standard, which has not been actively in Regulatory Guide 1.9 and associated updated since.

standards, including IEEE 308-1980, "Criteria for Class 1E Power Systems for As the prime mover, the diesel engine Nuclear Power Generating Stations." follows (responds to) both the steady state and transient load demands applied to the 1.5.3 EDG Component Selection generator. Its major components and systems are:

Each emergency diesel generator is one of

  • Governor the most unique and complex "support
  • Starting System (air or electric) systems" found within a nuclear power plant.

The EDG is itself an independent miniature

  • Fuel Oil Delivery System power plant serving critical safety equipment
  • Combustion Air Intake within the much larger facility.
  • Exhaust System
  • Lubrication System Figure 1-1 "Diesel Generator Systems" (next page) is from RG 1.9 and illustrates an
  • Cooling (Jacket Water) System EDG system, including most of its support
  • Crankcase Ventilation systems. The selection of EDGs to serve as
  • EDG start logic controls and relays independent, redundant, power sources for
  • Emergency run controls and Relays nuclear power plant emergency systems involves evaluation of the following major components, support systems, and circuits:

Rev 3/16 1-11 of 12 USNRC HRTD

Emergency Diesel Generator Diesel Generators as Emergency Power Sources Figure 1-1 Diesel Generator Systems Rev 3/16 1-12 of 12 USNRC HRTD

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