Regulatory Guide 1.9: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A381
| number = ML13038A105
| issue date = 11/30/1978
| issue date = 12/31/1979
| title = Selection, Design, and Qualification of Diesel-Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants
| title = Selection, Design, and Qualification of Diesel-Generator Units Used as Standby (Onsite) Electric Systems at Nuclear Power Plants
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.009, Rev. 1
| document report number = RG-1.009, Rev. 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 3
| page count = 4
}}
}}
{{#Wiki_filter:Revision 1 U.S. NUCLEAR REGULATORY COMMISSION                                                                                   November 1978 k REGULATORY GUIDE
{{#Wiki_filter:.,UE                                                                                                                    Revision 2
                            OFFICE OF STANDARDS DEVELOPMENT
                              4-1,      U.S.REGUL
                                                                  REGULATORY GUIDE 1.9 SELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR
                                                NUCLEAR REGULATORY COMMISSION                                                       December 1979 REGULATORY GUIDE
                          UNITS USED AS ONSITE ELECTRIC POWER SYSTEMS
                                1ý *OFFICE OF STANDARDS DEVELOPMENT
                                                  AT NUCLEAR POWER PLANTS
                                                                    REGULATORY GUIDE 1.9
?SECD C,,AI...ELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR UNITS USED AS
        *I                STANDBY (ONSITE) ELECTRIC POWER SYSTEMS AT NUCLEAR POWER PLANTS
    i JA* ";  J,*    *-'         


==A. INTRODUCTION==
==A. INTRODUCTION==
equipment needed to maintain the plant in a safe condition if an extended loss of offsite power occurs.
General Design Criterion 17, "Electric Power Systems,"
          of Appendix A, "General Design Criteria for Nuclear Power                IEEE Std 387-1977, "IEEE Standard Criteria for Diesel- Plants," to 10 CFR Part 50, "Domestic Licensing of Produc-            Generator Units Applied as Standby Power Supplies for Nu- tion and Utilization Facilities," includes a requirement that        clear Power Generating Stations,"'I delineates principal the onsite electric power system have sufficient capacity            design criteria and qualification testing requirements that, if and capability to ensure that (I) specified acceptable fuel          followed, will help ensure that selected diesel-generator design limits and design conditions of the reactor coolant          units meet their performance and reliability requirements.
pressure boundary are not exceeded as a result of anticipated        IEEE Std 387-1977 was developed by Working-Group 4.2C
          operational occurrences and (2) the core is cooled and con-          of the Nuclear Power Engineering Committee (NPEC) of tainment integrity and other vital functions are maintained          the Institute of Electrical and Electronics Engineers, Inc.
in the event of postulated accidents.                                (IEEE), approved by NPEC, and subsequently approved by the IEEE Standards Board on September 9, 1976. IEEE Std Criterion III, "Design Control," of Appendix B, "Quality        387-1977 is supplementary to IEEE Std 308-1974, "IEEE
          Assurance Criteria for Nuclear Power Plants and Fuel                  Standard Criteria for Class IE Power Systems and Nuclear Reprocessing Plants," to 10 CFR Part 50 includes a require-          Power Generating Stations," I and specifically amplifies ment that measures be provided for verifying or checking              paragraph 5.2.4, "Standby Power Supplies," of that docu- the adequacy of design by design reviews, by the use of              ment with respect to the application of diesel-generator alternative or simplified calculational methods, or by the          units. IEEE Std 308-1974 is endorsed, with certain excep- performance of a suitable testing program.                            tions, by Regulatory Guide 1.32, "Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants."
              Diesel-generator units have been widely used as the power source for the onsite electric power systems. This                  A knowledge of the characteristics of each load is regulatory guide describes a method acceptable to the NRC            essential in establishing the bases for the selection of a staff for complying with the Commission's requirements              diesel-generator unit that is able to accept large loads in that diesel-generator units intended for use as onsite power        rapid succession. The majority of the emergency loads are sources in nuclear power plants be selected with sufficient          large induction motors. This type of motor draws, at full capacity and be qualified for this service. The Advisory              voltage, a starting current five to eight times its rated load Committee on Reactor Safeguards has been consulted                    current. The sudden large increases in current drawn from concerning this guide and has concurred in the regulatory            the diesel generator resulting from the startup of induction position.                                                            motors can result in substantial voltage reductions. The lower voltage could prevent a motor from starting, i.e.,


==B. DISCUSSION==
==B. DISCUSSION==
General Design Criterion 17, "Electric Power                                          A diesel-generator unit selected for use in an Systems," of Appendix A,                          "General Design                    onsite electric power system should have the Criteria for Nuclear Power Plants," to 10 CFR                                          capability to (1) start and acceate a number Part 50, "Domestic Licensing of Production and                                        of large motor loads in rapid ar                                sion and be Utilization Facilities," includes a requirement                                        able to sustain the loss ok an o%1._y part of such loads        and    maintain         v0I*ge        an, Irequency that the onsite electric power system have sufficient capacity and capability to ensure                                          within acceptable limit                            "        supply power that (1) specified acceptable fuel design limits                                      continuously to the                            i      V~eded bq*"4 to main- and design conditions of the reactor coolant                                          tain the plant in a .*2e c 4itioA if an extended pressure boundary are not exceeded as a                                                loss of offsite po A~r o urý b'
accelerating its load to rated speed in the required time, or cause a running motor to coast down or stall. Other loads A diesel-generator unit selected for use in an onsite           might be lost if their contactors drop out. Recovery from electric power system should have the capability to (1) start         the transient caused by starting large motors or from the and accelerate a number of large motor loads in rapid               loss of a large load could cause diesel engine overspeed succession and be able to sustain the loss of all or any part        which, if excessive, might result in a trip of the engine.
result of anticipated operational occurrences                                                                                      A
*and (2) the core is cooled and containment in-                                            IEEE Std              -197 ;,,;              E Standard Criteria tegrity and other vital functions are maintained                                      for Diesel-G *              k*tor      mits Applied as Standby in the event of postulated accidents.                                                  Power                      " K Nuclear Power Generating Stations            4ceea'kes principal design criteria Criterion III, "Design Control," of Appen-                                        an ,}*ua            a         testing requirements that, if dix B, "Quality Assurance Criteria for Nuclear                                        foI          ,        help ensure that selected diesel- Power Plants and Fuel Reprocessing Plants," to                                      .genrhrat"            Units meet their performance and
10 CFR Part 50 includes a requirement that                                      '          a h*t'requirements. IEEE Std 387-1977 was measures be provided for verifying or checking                                            'f;      ed by Working Group 4.2C of the the adequacy of design by design reviews, J%$.                                            cl r Power Engineering Committee (NPEC)
the use of alternative or simplified calculati al                                    ot0      .he Institute of Electrical and Electronics methods, or by the performance of a suit".e                                            Engineers, Inc. (IEEE), approved by NPEC,
testing program.                                                ,                    and subsequently approved by the -IEEE Stan-
                                                                              - "      dards Board on September 9, 1976. IEEE Std Diesel-generator units have been wiely ud                                        387-1977 is supplementary to IEEE Std 308- as the power source for the onsiV                                    le      ic        1974, "IEEE Standard. Criteria for Class IE
power systems. This regulatory gfiae                                          -        Power Systems and Nuclear Power Generating scribes a method acceptable to the NRC staff                                          Stations,"' and specifically amplifies paragraph for complying with the                      a mission's require-                      5.2.4, "Standby Power Supplies," of that doc- ments that diesel-gene                          units intended for                    ument with respect to'the application of diesel- use as onsite power                      r j          nuclear power                  generator units. IEEE Std 308-1974 is en- plants be selected with                        ic        capacity and                dorsed, with certain exceptions, by Regulatory be qualified for                      v                                              Guide 1.32,              "Criteria              for      Safety-Related Electric Power Systems for Nuclear Power wThe substantial          her of        ges in this revision has made              Plants. "
it impractical to              the c    ges wit*      es in the margin.


'Copies         e                    the Institute of Electrical and                 A knowledge of the characteristics of each Electronics                 In ..n  ited Engineering Center, 345 East
of such loads and maintain voltage and frequency within acceptable limits and (2) supply power continuously to the                1 Copies may be obtained from the Institute of Electrical and Electronics Engineers, Inc., United Engineering Center, 345 East Lines indicate substantive changes from Revision 1.          47th Street, New York, New York 10017.
47th Street,           ork, New York 10017.                                          load is essential in establishing the bases for USNRC REGULATORY GUIDES                                            Comments should be sMnt to the Secrety of the Conmi;slon, U.S. Nudcer Regulatory Commurorn , Wastington, D.C. 26.              Attention: Dockasth and Regulatney Guides re Issued to descrbe and rnake available to the public              Sevice Branch.


methods acceptable to the NRC staff of                   specific parts of the commlssiora's regultionts, to delinestedvt            sdb the staff In avalu-         The guides are Issued Inthe following ten broad divisioin:
USNRC    REGULATORY GUIDES                      Comments should be sent to the Secretary of the Commission, U.S. Nuclear    Regulatory  Commission, Regulatory Guides are issued to describe and make available to the  Attention:  Doclketing and Service Branch. Washington, D.C. 20555, public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech-   The guides are issued in the following ten broad divisions:
atg spec        probles or postulated accidents. or to provide guidance to applicants. Regulatory Guides ae not sutbstitutes for regulations, and corn-          1. Power React"                              B. Products plence with them Is not requked. Methods end solutions different from those           2. Reseerch end Teat Reactors                  7. Transportation set out Inthe guides wil b acceptable If they provide a b"si for the findings        3. Fuels and Materiab Factites                & Occupational Health re=ui      to the issgirce or continuance of a pewrh or Bse e by the                  4. Environmental and Sitng                    9. Antitrust and Financial Review Cornwitiuo*                                                                            rLMatmerilsand Plant protection              10. General Comments and suggestions for Imroernemeis In tees gudes are encouraged                Requests for single copies of Isued guides Iwit-h may be reproducedl or for at Imes, end guides wil bee rwl sd,      aspramopas, to accommodate corn-            placerment on en autonlatic: distribution list for single copies of fuaum guldes mene= and to reflect new        rmt    or aperen*e. Howeve. corment t,                In s ief*cdivslons should be ,de In wrtltng to the US. NudIsr Reguatory this gtuld. If eeed wlfhn about two mond afte Its Issuance, wil be                    Cornenssion, Washingion, D.C.              I, Attentio: Okector, D,4lon of wfttleft useful In awluating the need for an eauly r      .evilon.                  Technical Informaiwon and Document Control.
          niques used by the staff in evaluating specific problems or postu- lated accidents, or to provide guidance to applicants. Regulatory   1.  Power Reactors                  6. Products Guides are not substitutes for regulations, and compliance with      2. Research and Test Reactors      7. Transportation them is not required. Methods and solutions different from those set 3. Fuels and Materials Facilities  8. Occupational Health out in the guides will be acceptable if they provide a basis for the 4.  Environmental and Siting        9. Antitrust and Financial Review findings requisite to the issuance or continuance of a permit or     5. Materials and Plant Protection 10. General license by the Commission.


the selection of a diesel-generator unit that is      generator unit so that it exceeds the sum of able to accept large loads in rapid succession.        the loads needed at any one time. A more accu- The majority of the emergency loads are large          rate estimate of safety loads is possihle duringl induction motors. This type of motor draws, at         the operating license stage of review because full voltage, a starting current five to ten          detailed designs have been completed and times its rated load current. The sudden large        preoperational test data are available. This increases in current drawn from the diesel            permits the consideration of a somewhat less generator resulting from the startup of induc-        conservative approach, such as operation with tion motors can result in substantial voltage          safety loads within the short-time rating of the reductions. The lower voltage could prevent a          diesel-generator unit.
Copies of issued guides may be purchased at the current Government Comments and suggestions for improvements in these guides are        Printing Office price. A subscription service for future guides in spe- encouraged at all times, and guides will be revised, as appropriate, cific divisions is available through the Government Printing Office.


motor from starting, i.e. , accelerating its load to rated speed in the required time, or cause a                   
to accommodate comments and to reflect new information or            Information on the subscription service and current GPO prices may experience. This guide was revised as a result of substantive com-  be obtained by writing the U.S. Nuclear Regulatory Commission, ments received from the public and additional staff review.          Washington, D.C. 20555, Attention: Publications Sales Manager.


==C. REGULATORY POSITION==
These same consequences can also result from the cumu-                  system should be selected to have a continuous load rating lative effect of a sequence of more moderate transients if              (as defined in Section 3.7.1 of IEEE Std 387-1977) equal the system is not permitted to recover sufficiently between            to or greater than the sum of the conservatively estimated successive steps in a loading sequence.                                 loads needed to be powered by that unit at any one time.
running motor to coast down or stall. Other loads might be lost if their contactors drop                Conformance with the requirements of IEEE
 
out. Recovery from the transient caused by              Std 387-1977, "IEEE Standard Criteria for starting large motors or from the loss of a            Diesel-Generator Units Applied as Standby large load could cause diesel engine overspeed          Power Supplies for Nuclear Power Generating which, if excessive, might result in a trip of         Stations," dated June 17, 1977, is acceptable the engine. These same consequences can also            for meeting the requirements of the principal result from the cumulative effect of a sequence        design criteria and qualification testing of of more moderate transients if the system is not        diesel-generator units used as onsite electric.
In the absence of fully substantiated performance character- Generally it has been industry practice to specify a                istics for mechanical equipment such as pumps, the electric maximum voltage reduction of 10 to 15 percent when                      motor drive ratings should be calculated using conservative starting large motors from large-capacity power systems and            estimates of these characteristics, e.g., pump runout condi- a voltage reduction of 20 to 30 percent when starting these             tions and motor efficiencies of 90 percent or less and motors from limited-capacity power sources such as diesel-              power factors of 85 percent or less.
 
generator units. Large induction motors can achieve rated speed in less than 5 seconds when powered from adequately                    2. At the operating license stage of review, the predicted sized diesel-generator units that are capable of restoring the         loads should not exceed the short-time rating (as defined in voltage to 90 percent of nominal in about I second.                    Section 3.7.2 of IEEE Std 387-1977) of the diesel-generator unit.


permitted to recover sufficiently between suc-          power systems for nuclear power plants subject cessive steps in a loading sequence.                    to the following:
Protection of the diesel-generator unit from excessive overspeed, which can result from a loss of load, is afforded                3. In Section 5.1.1, "GeneraL" of IEEE Std 387-1977, the by the immediate operation of a diesel-generator unit trip,            requirements of IEEE Std 308-1974 should be used subject usually set at 115 percent of nominal speed. In addition,               to the regulatory position of Regulatory Guide 1.32.
    Generally it has been industry practice to              1. When the characteristics of loads are not specify a maximum voltage reduction of 10 to 15        accurately known, such as during the con- percent when starting large motors from large-          struction permit stage of design, each diesel- capacity power systems and a voltage reduction          generator unit of an onsite power supply of 20 to 30 percent when starting these motors          system should be selected to have a continuous from limited-capacity power sources such as            load rating (as defined in Section 3.7.1 of IEEE
diesel-generator units. Large induction motors          Std 387-1977) equal to or greater than the sum can achieve rated speed in less than 5 seconds          of the conservatively estimated loads needed to when powered from adequately sized diesel-             be powered by that unit at any one time. In generator units that are capable of restoring          the absence of fully substantiated performance the voltage to 90 percent of nominal in about 1        characteristics for mechanical equipment such second.                                                 as pumps, the electric motor drive ratings should be calculated using conservative esti- Protection of the diesel-generator unit from        mates of these characteristics, e.g., pump excessive overspeed, which can result from a            runout conditions and motor efficiencies of 90%
loss of load, is afforded by the immediate oper-        or less.


ation of a diesel-generator unit trip, usually set at 115 percent of nominal speed. In addi-              2. At the operating  license stage of review, tion, the generator differential trip must oper-        the predicted loads    should   not exceed the ate immediately in order to prevent substantial         short-time rating (as  defined  in Section 3.7.2 damage to the generator. There are other pro-           of IEEE Std 387-1977)   of the diesel-generator tective trips provided to protect the diesel-           unit.
the generator differential trip must operate immediately in order to prevent substantial damage to the generator. There                4. Section 5.1.2, "Mechanical and Electrical Capabilities,"
are other protective trips provided to protect the diesel-              of IEEE Std 387-1977 pertains, in part, to the starting and generator units from possible damage or degradation.                    load-accepting capabilities of the diesel-generator unit. In However, these trips could interfere with the successful                conjunction with Section 5.1.2, each diesel-generator unit functioning of the unit when it is most needed, i.e., during            should be capable of starting and accelerating to rated accident conditions. Experience has shown that there have              speed, in the required sequence, all the needed engineered been numerous occasions when these trips have needlessly                safety feature and emergency shutdown loads. The diesel- shut down diesel-generator units because of spurious                  generator unit design should be such that at no time during operation of a trip circuit. Consequently, it is important              the loading sequence should the frequency and voltage that measures be taken to ensure that spurious actuation of            decrease to less than 95 percent of nominal and 75 percent these other protective trips does not prevent the diesel-              of nominal, respectively. (A larger decrease in voltage and generator unit from performing its function.                            frequency may be justified for a diesel-generator unit that carries only one large connected load.) Frequency should The uncertainties inherent in estimates of safety loads at          be restored to within 2 percent of nominal, and voltage the construction permit stage of design are sometimes of such          should be restored to within 10 percent of nominal within magnitude that it is prudent to provide a substantial margin            60 percent of each load-sequence time interval. (A greater in selecting the load capabilities of the diesel-generator unit.       percentage of the time interval may be used if it can be This margin can be provided by estimating the loads conser-            justified by analysis. However, the load-sequence time vatively and selecting the continuous rating of the diesel-            interval should include sufficient margin to account for the generator unit so that it exceeds the sum of the loads needed           accuracy and repeatability of the load-sequence timer.)
at any one time. A more accurate estimate of safety loads is            During recovery from transients caused by step load increases possible during the operating license stage of review because          or resulting from the disconnection of the largest single detailed .designs have been completed and preoperational              load, the speed of the diesel-generator unit should not test data are available. This permits the consideration of a          exceed the nominal speed plus 75 percent of the difference somewhat less conservative approach, such as operation                  between nominal speed and the overspeed trip setpoint with safety loads within the short-time rating of the diesel-         or 115 percent of nominal, whichever is lower. Further, the generator unit.                                                         transient following the complete loss of load should not cause the speed of the unit to attain the overspeed trip


generator units from possible damage or degra- dation. However, these trips could interfere              3. During preoperational testing, the pre- with the successful functioning of the unit            dicted loads should be verified by tests.
==C. REGULATORY POSITION==
setpoint.


when it is most needed, i.e. , during accident conditions. Experience has shown that there                4. In Section 5.1.1, "General," of IEEE Std have been numerous occasions when these trips          387-1977, the requirements of IEEE Std 308- have needlessly shut down diesel-generator             1974 should be used subject to the regulatory units because of spurious operation of a trip          position of Regulatory Guide 1.32.
Conformance with the requirements of IEEE Std 387-1977,                 5. In Section 5.4, "Qualification," of IEEE Std 387-1 977,
"IEEE Standard Criteria for Diesel-Generator Units Applied            the qualification testing requirements of IEEE Std 323-1974, as Standby Power Supplies for Nuclear Power Generating                "IEEE Standard for Qualifying Class IE Equipment for Stations," dated June 17, 1977, is acceptable for meeting             Nuclear Power Generating Stations,"' should be used the requirements of the principal design criteria and qualifica-      subject to the regulatory position of Regulatory Guide 1.89, tion testing of diesel-generator units used as onsite electric        "Qualification of Class IE Equipment for Nuclear Power power systems for nuclear power plants subject to the                  Plants."
following:
                                                                            6. Section  5.5, "Design and Application Considerations,"
    I. When the characteristics of loads are not accurately            of IEEE Std      387-1977 pertains to design features for con- known, such as during the construction permit stage of                sideration in    diesel-generator unit design. In conjunction design, each diesel-generator unit of an onsite power supply          with Section    5.5, diesel-generator units should be designed  I
                                                                1.9-2


circuit. Consequently, it is important that measures be taken to ensure that spurious ac-               5. Section 5.1.2, "Mechanical and Electrical tuation of these other protective trips does not        Capabilities," of IEEE Std 387-1977 should be prevent      the  diesel-generator  unit  from        supplemented with the following:
to be testable during operation of the nuclear power plant          Qualification of Class I E Equipment for Nuclear Power as well as while the plant is shut down. The design should          Generating Stations," for seismic analysis or seismic testing
performing its function.
  -, include provisions so that the testing of the units will            by equipment manufacturers should be used subject to the simulate the parameters of operation (outlined in Regula-           regulatory position of Regulatory Guide 1.100, "Seismic tory Guide 1.108, "Periodic Testing of Diesel-Generator              Qualification of Electric Equipment for Nuclear Power Units Used as Onsite Electric Power Systems at Nuclear              Plants."
    Power Plants") that would be expected if actual demand were to be placed on the system.                                        10. The option indicated by "may" in Section 6.3.2(5)(c)
                                                                          of IEEE Std 387-1977 should be treated as a requirement.


"Each diesel-generator unit should be capa- The uncertainties inherent in estimates of             ble of starting and 'accelerating to rated safety loads at the construction permit stage of            speed, in the required sequence, all the design are sometimes of such magnitude that it              needed engineered safety feature and emer- is prudent to provide a substantial margin in              gency shutdown loads. At no time during the selecting the load capabilities of the diesel-             loading sequence should the frequency and generator unit. This margin can be provided                voltage decrease to less than 95 percent of by estimating the loads conservatively and                  nominal and 75 percent of nominal, respec- selecting the continuous rating of the diesel-              tively"b Frequency should be restored to
Testability should be considered in the selection and location of instrumentation sensors and critical components            11. Section 6.5, "Site Acceptance Testing," and Section 6.6, (e.g., governor, starting system components), and the               "Periodic Testing," of IEEE Std 387-1977 should be supple- overall design should include status indication and alarm            mented by Regulatory Guide 1.108.
                                                  1.9-2


* within 2 percent of nominal, and voltage                      conditions. The design of the bypass should be restored to within 10 percent of                    circuitry should satisfy the requirements nominal within 60 percent of each load-                      of IEEE Std 279-1971 at the diesel- sequence time interval. (A greater percent-                  generator    system  level  and  should age of the time interval may be used if it can                include the capability for (I) testing the be justified by analysis. However, the load-                  status and operability of the bypass sequence time interval should include suffi-                  circuits, (2) alarming in the control room cient margin to account for the accuracy and                  abnormal values of all bypass param- repeatability of the load-sequence timer.)                    eters, and (3) manually resetting of the During recovery from transients caused by                    trip bypass function. (Capability for step load increases or resulting from the                    automatic reset is not acceptable.)"
features. Instrumentation sensors should be readily accessible and, where practicable, designed so that their inspection              12. Section 4, "Reference Standards," of IEEE Std 387-1977 and calibration can be verified in place.                            lists additional applicable IEEE standards. The specific appli- cability or acceptability of these referenced standards has
  disconnection of the largest single load, the speed of the diesel-generator unit should not            9. Section 5.6.3. 1, "Surveillance Systems," or exceed the nominal speed plus 75 percent of           IEEE Std 387-1977 should be supplemented with the difference between nominal speed and the          the following:
        7. Section 5.6.2.2, "Automatic Control," of IEEE Std             been or will be covered separately in other regulatory guides,
  overspeed trip setpoint or 115 *percent of                "In order to facilitate trouble diagnosis, the nominal, whichever is lowei. Further, the                surveillance system should indicate which of transient following the complete loss of load            the diesel-generator protective trips is acti- should not cause the speed of the unit to                vated first."
      387-1977 pertains to automatic startup requirements and            where appropriate.
  attain the overspeed trip setpoint."
                                                            10. In Section 6.3, "Type Qualification Test-
  6. In Section 5.4, "Qualification," of IEEE            ing Procedures and Methods," of IEEE Std 387- Std 387-1977, the qualification testing require-          1977, the requirements of IEEE Std 344-1975, ments of IEEE Std 323-1974, "IEEE Standard for            "Recommended Practices for Seismic Qualifica- Qualifying Class IE Equipment for Nuclear                tion of Class 1E Equipment for Nuclear Power Power Generating Stations,"' should be used              Generating Stations," for seismic analysis or subject to the regulatory p*osition of Regulatory        seismic testing by equipment manufacturers Guide 1.89, "Qualification of C!ass IE Equip-            should be used subject to the regulatory posi- ment for Nuclear Power Plants."                          tion of Regulatory Guide 1.100, "Seismic Quali- fication of Electric Equipment for Nuclear
  7. Section 5.5, "Design and Application Con-          Power Plants."
siderations," of IEEE Std 387-1977 should be supplemented with the following:                            11. The option indicated by "may" in Sec- tion 6.3.2(5)(c) of IEEE Std 387-1977 should
  "Diesel-generator units should be designed to         be treated as a requirement.


be testable during operation of the nuclear power plant as well as while the plant is shut           12. Section 6.5, "Site Acceptance Testing,"
their relationship to other operating modes. In conjunction with Section 5.6.2.2, engine-overspeed and generator-differ-           13. Section 6.3.2, "Start and Load Acceptance Qualifi- ential trips may be implemented by a single-channel trip. All        cation," pertains to test requirements for diesel-generator other diesel-generator protective trips should be handled in        unit qualification. In conjunction with Section 6.3.2, one of two ways: Either, (1) a trip should be implemented            fewer successful start-and-load tests and allowed failures with two or more independent measurements for each trip              than that specified-300 valid tests with no more than 3 parameter with coincident logic provisions for trip actuation,      failures-may be justified for a diesel-generator unit that or (2) a trip may be bypassed under accident conditions,            carries only one large connected load tested under actual provided the operator has sufficient time to react appro-            conditions, provided an equivalent reliability/confidence priately to an abnormal diesel-generator unit condition. The        level is demonstrated.
  down. The design should include provisions            and Section 6.6, "Periodic Testing," of IEEE
  so that the testing of the units will simulate        Std 387-1977 should be supplemented by Regu- the parameters of operation (outlined in              latory Guide 1.108.


Regulatory Guide 1.108, "Periodic Testing of Diesel-Generator      Units  Used    as  Onsite          13.   Section 4, "Reference Standards," of Electric Power Systems at Nuclear Power                IEEE Std 387-1977 lists additional applicable Plants") that would be expected if actual              IEEE standards. The specific applicability or demand were to be placed on the system.               acceptability of these referenced standards has been or will be covered separately in other
design of the bypass circuitry should satisfy the requirements of IEEE Std 279-1971 at the diesel-generator system level              14. In Section 6.3.1, "Load Capability Qualification," of
  "Testability should be considered in the              regulatory guides, where appropriate.
-    and should include the capability for (1) testing the status        IEEE Std 387-1977, the order of sequence of load tests and operability of the bypass circuits, (2) alarming in the          described in parts (1) and (2) should be as follows: Load control room abnormal values of all bypass parameters, and          equal to the continuous rating should be applied for the
    (3) manually resetting of the trip bypass function. (Capability      time required to reach engine temperature equilibrium, at for automatic reset is not acceptable.)                            which time, the rated short-time load should be applied for a period of 2 hours. Immediately following the 2-hour
        8. Section 5.6.3.1, "Surveillance Systems," of IEEE Std          short-time load test, load equal to the continuous rating
      387-1977 pertains to status indication of diesel-generator          should be applied for 22 hours.


selection and location of instrumentation sen- sors and critical components (e.g., gover-                           
unit conditions. In conjunction with Section 5.6.3.1, in order to facilitate trouble diagnosis, the surveillance system                         


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
nor, starting system components), and the overall design should include status indica-             This proposed guide has been released to tion and alarm features.        Instrumentation        encourage public participation in its develop- sensors should be readily accessible and              ment. Except in those cases in which an appli- designed so that their inspection and calibra-        cant proposes an acceptable alternative method tion can be verified in place."                        for complying with specified portions of the Commission's regulations, the method to be
should indicate which of the diesel-generator protective trips is activated first.                                               Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified
  8. Section 5.6.2.2, "Automatic Control," of           described in the active guide reflecting public IEEE Std 387-1977 should be supplemented with            comments will be used in the evaluation of
        9. In Section 6.3, "Type Qualification Testing Procedures        portions of the Commission's regulations, the method de- and Methods," of IEEE Std 387-1977, the requirements of              scribed herein will be used in the evaluation of applications IEEE Std 344-1975, "Recommended Practices for Seismic                for construction permits docketed after December 1979.
,the following:                                          applications for construction permits docketed after the implementation date to be specified in
    (3) "With the exception of the engine over-          the active guide. This implementation date will speed trip and the generator differential        in no case be earlier than July 1979.


trip, all diesel-generator protective trips should be either (1) implemented with                If an .applicant wishes to use this draft guide two or more independent measurements              in an application docketed prior to the imple- for each trip parameter with coincident          mentation date, the pertinent portions of the logic provisions for trip actuation or (2)        application will be evaluated on the basis of automatically bypassed during accident            this draft guide.
1.9-3


1.9-3}}
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NUCLEAR REGULATORY COMMISSION
    WASHINGTON, D. C. 20555 POSTAGE AND FEES PAID
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                            OFFICE OF THE COMMISSIONERS
                            DR JOSEPH  HENDRIE
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Revision as of 13:49, 10 March 2020

Selection, Design, and Qualification of Diesel-Generator Units Used as Standby (Onsite) Electric Systems at Nuclear Power Plants
ML13038A105
Person / Time
Issue date: 12/31/1979
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.009, Rev. 2
Download: ML13038A105 (4)


.,UE Revision 2

4-1, U.S.REGUL

NUCLEAR REGULATORY COMMISSION December 1979 REGULATORY GUIDE

1ý *OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.9

?SECD C,,AI...ELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR UNITS USED AS

  • I STANDBY (ONSITE) ELECTRIC POWER SYSTEMS AT NUCLEAR POWER PLANTS

i JA* "; J,* *-'

A. INTRODUCTION

equipment needed to maintain the plant in a safe condition if an extended loss of offsite power occurs.

General Design Criterion 17, "Electric Power Systems,"

of Appendix A, "General Design Criteria for Nuclear Power IEEE Std 387-1977, "IEEE Standard Criteria for Diesel- Plants," to 10 CFR Part 50, "Domestic Licensing of Produc- Generator Units Applied as Standby Power Supplies for Nu- tion and Utilization Facilities," includes a requirement that clear Power Generating Stations,"'I delineates principal the onsite electric power system have sufficient capacity design criteria and qualification testing requirements that, if and capability to ensure that (I) specified acceptable fuel followed, will help ensure that selected diesel-generator design limits and design conditions of the reactor coolant units meet their performance and reliability requirements.

pressure boundary are not exceeded as a result of anticipated IEEE Std 387-1977 was developed by Working-Group 4.2C

operational occurrences and (2) the core is cooled and con- of the Nuclear Power Engineering Committee (NPEC) of tainment integrity and other vital functions are maintained the Institute of Electrical and Electronics Engineers, Inc.

in the event of postulated accidents. (IEEE), approved by NPEC, and subsequently approved by the IEEE Standards Board on September 9, 1976. IEEE Std Criterion III, "Design Control," of Appendix B, "Quality 387-1977 is supplementary to IEEE Std 308-1974, "IEEE

Assurance Criteria for Nuclear Power Plants and Fuel Standard Criteria for Class IE Power Systems and Nuclear Reprocessing Plants," to 10 CFR Part 50 includes a require- Power Generating Stations," I and specifically amplifies ment that measures be provided for verifying or checking paragraph 5.2.4, "Standby Power Supplies," of that docu- the adequacy of design by design reviews, by the use of ment with respect to the application of diesel-generator alternative or simplified calculational methods, or by the units. IEEE Std 308-1974 is endorsed, with certain excep- performance of a suitable testing program. tions, by Regulatory Guide 1.32, "Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants."

Diesel-generator units have been widely used as the power source for the onsite electric power systems. This A knowledge of the characteristics of each load is regulatory guide describes a method acceptable to the NRC essential in establishing the bases for the selection of a staff for complying with the Commission's requirements diesel-generator unit that is able to accept large loads in that diesel-generator units intended for use as onsite power rapid succession. The majority of the emergency loads are sources in nuclear power plants be selected with sufficient large induction motors. This type of motor draws, at full capacity and be qualified for this service. The Advisory voltage, a starting current five to eight times its rated load Committee on Reactor Safeguards has been consulted current. The sudden large increases in current drawn from concerning this guide and has concurred in the regulatory the diesel generator resulting from the startup of induction position. motors can result in substantial voltage reductions. The lower voltage could prevent a motor from starting, i.e.,

B. DISCUSSION

accelerating its load to rated speed in the required time, or cause a running motor to coast down or stall. Other loads A diesel-generator unit selected for use in an onsite might be lost if their contactors drop out. Recovery from electric power system should have the capability to (1) start the transient caused by starting large motors or from the and accelerate a number of large motor loads in rapid loss of a large load could cause diesel engine overspeed succession and be able to sustain the loss of all or any part which, if excessive, might result in a trip of the engine.

of such loads and maintain voltage and frequency within acceptable limits and (2) supply power continuously to the 1 Copies may be obtained from the Institute of Electrical and Electronics Engineers, Inc., United Engineering Center, 345 East Lines indicate substantive changes from Revision 1. 47th Street, New York, New York 10017.

USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Regulatory Guides are issued to describe and make available to the Attention: Doclketing and Service Branch. Washington, D.C. 20555, public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech- The guides are issued in the following ten broad divisions:

niques used by the staff in evaluating specific problems or postu- lated accidents, or to provide guidance to applicants. Regulatory 1. Power Reactors 6. Products Guides are not substitutes for regulations, and compliance with 2. Research and Test Reactors 7. Transportation them is not required. Methods and solutions different from those set 3. Fuels and Materials Facilities 8. Occupational Health out in the guides will be acceptable if they provide a basis for the 4. Environmental and Siting 9. Antitrust and Financial Review findings requisite to the issuance or continuance of a permit or 5. Materials and Plant Protection 10. General license by the Commission.

Copies of issued guides may be purchased at the current Government Comments and suggestions for improvements in these guides are Printing Office price. A subscription service for future guides in spe- encouraged at all times, and guides will be revised, as appropriate, cific divisions is available through the Government Printing Office.

to accommodate comments and to reflect new information or Information on the subscription service and current GPO prices may experience. This guide was revised as a result of substantive com- be obtained by writing the U.S. Nuclear Regulatory Commission, ments received from the public and additional staff review. Washington, D.C. 20555, Attention: Publications Sales Manager.

These same consequences can also result from the cumu- system should be selected to have a continuous load rating lative effect of a sequence of more moderate transients if (as defined in Section 3.7.1 of IEEE Std 387-1977) equal the system is not permitted to recover sufficiently between to or greater than the sum of the conservatively estimated successive steps in a loading sequence. loads needed to be powered by that unit at any one time.

In the absence of fully substantiated performance character- Generally it has been industry practice to specify a istics for mechanical equipment such as pumps, the electric maximum voltage reduction of 10 to 15 percent when motor drive ratings should be calculated using conservative starting large motors from large-capacity power systems and estimates of these characteristics, e.g., pump runout condi- a voltage reduction of 20 to 30 percent when starting these tions and motor efficiencies of 90 percent or less and motors from limited-capacity power sources such as diesel- power factors of 85 percent or less.

generator units. Large induction motors can achieve rated speed in less than 5 seconds when powered from adequately 2. At the operating license stage of review, the predicted sized diesel-generator units that are capable of restoring the loads should not exceed the short-time rating (as defined in voltage to 90 percent of nominal in about I second. Section 3.7.2 of IEEE Std 387-1977) of the diesel-generator unit.

Protection of the diesel-generator unit from excessive overspeed, which can result from a loss of load, is afforded 3. In Section 5.1.1, "GeneraL" of IEEE Std 387-1977, the by the immediate operation of a diesel-generator unit trip, requirements of IEEE Std 308-1974 should be used subject usually set at 115 percent of nominal speed. In addition, to the regulatory position of Regulatory Guide 1.32.

the generator differential trip must operate immediately in order to prevent substantial damage to the generator. There 4. Section 5.1.2, "Mechanical and Electrical Capabilities,"

are other protective trips provided to protect the diesel- of IEEE Std 387-1977 pertains, in part, to the starting and generator units from possible damage or degradation. load-accepting capabilities of the diesel-generator unit. In However, these trips could interfere with the successful conjunction with Section 5.1.2, each diesel-generator unit functioning of the unit when it is most needed, i.e., during should be capable of starting and accelerating to rated accident conditions. Experience has shown that there have speed, in the required sequence, all the needed engineered been numerous occasions when these trips have needlessly safety feature and emergency shutdown loads. The diesel- shut down diesel-generator units because of spurious generator unit design should be such that at no time during operation of a trip circuit. Consequently, it is important the loading sequence should the frequency and voltage that measures be taken to ensure that spurious actuation of decrease to less than 95 percent of nominal and 75 percent these other protective trips does not prevent the diesel- of nominal, respectively. (A larger decrease in voltage and generator unit from performing its function. frequency may be justified for a diesel-generator unit that carries only one large connected load.) Frequency should The uncertainties inherent in estimates of safety loads at be restored to within 2 percent of nominal, and voltage the construction permit stage of design are sometimes of such should be restored to within 10 percent of nominal within magnitude that it is prudent to provide a substantial margin 60 percent of each load-sequence time interval. (A greater in selecting the load capabilities of the diesel-generator unit. percentage of the time interval may be used if it can be This margin can be provided by estimating the loads conser- justified by analysis. However, the load-sequence time vatively and selecting the continuous rating of the diesel- interval should include sufficient margin to account for the generator unit so that it exceeds the sum of the loads needed accuracy and repeatability of the load-sequence timer.)

at any one time. A more accurate estimate of safety loads is During recovery from transients caused by step load increases possible during the operating license stage of review because or resulting from the disconnection of the largest single detailed .designs have been completed and preoperational load, the speed of the diesel-generator unit should not test data are available. This permits the consideration of a exceed the nominal speed plus 75 percent of the difference somewhat less conservative approach, such as operation between nominal speed and the overspeed trip setpoint with safety loads within the short-time rating of the diesel- or 115 percent of nominal, whichever is lower. Further, the generator unit. transient following the complete loss of load should not cause the speed of the unit to attain the overspeed trip

C. REGULATORY POSITION

setpoint.

Conformance with the requirements of IEEE Std 387-1977, 5. In Section 5.4, "Qualification," of IEEE Std 387-1 977,

"IEEE Standard Criteria for Diesel-Generator Units Applied the qualification testing requirements of IEEE Std 323-1974, as Standby Power Supplies for Nuclear Power Generating "IEEE Standard for Qualifying Class IE Equipment for Stations," dated June 17, 1977, is acceptable for meeting Nuclear Power Generating Stations,"' should be used the requirements of the principal design criteria and qualifica- subject to the regulatory position of Regulatory Guide 1.89, tion testing of diesel-generator units used as onsite electric "Qualification of Class IE Equipment for Nuclear Power power systems for nuclear power plants subject to the Plants."

following:

6. Section 5.5, "Design and Application Considerations,"

I. When the characteristics of loads are not accurately of IEEE Std 387-1977 pertains to design features for con- known, such as during the construction permit stage of sideration in diesel-generator unit design. In conjunction design, each diesel-generator unit of an onsite power supply with Section 5.5, diesel-generator units should be designed I

1.9-2

to be testable during operation of the nuclear power plant Qualification of Class I E Equipment for Nuclear Power as well as while the plant is shut down. The design should Generating Stations," for seismic analysis or seismic testing

-, include provisions so that the testing of the units will by equipment manufacturers should be used subject to the simulate the parameters of operation (outlined in Regula- regulatory position of Regulatory Guide 1.100, "Seismic tory Guide 1.108, "Periodic Testing of Diesel-Generator Qualification of Electric Equipment for Nuclear Power Units Used as Onsite Electric Power Systems at Nuclear Plants."

Power Plants") that would be expected if actual demand were to be placed on the system. 10. The option indicated by "may" in Section 6.3.2(5)(c)

of IEEE Std 387-1977 should be treated as a requirement.

Testability should be considered in the selection and location of instrumentation sensors and critical components 11. Section 6.5, "Site Acceptance Testing," and Section 6.6, (e.g., governor, starting system components), and the "Periodic Testing," of IEEE Std 387-1977 should be supple- overall design should include status indication and alarm mented by Regulatory Guide 1.108.

features. Instrumentation sensors should be readily accessible and, where practicable, designed so that their inspection 12. Section 4, "Reference Standards," of IEEE Std 387-1977 and calibration can be verified in place. lists additional applicable IEEE standards. The specific appli- cability or acceptability of these referenced standards has

7. Section 5.6.2.2, "Automatic Control," of IEEE Std been or will be covered separately in other regulatory guides,

387-1977 pertains to automatic startup requirements and where appropriate.

their relationship to other operating modes. In conjunction with Section 5.6.2.2, engine-overspeed and generator-differ- 13. Section 6.3.2, "Start and Load Acceptance Qualifi- ential trips may be implemented by a single-channel trip. All cation," pertains to test requirements for diesel-generator other diesel-generator protective trips should be handled in unit qualification. In conjunction with Section 6.3.2, one of two ways: Either, (1) a trip should be implemented fewer successful start-and-load tests and allowed failures with two or more independent measurements for each trip than that specified-300 valid tests with no more than 3 parameter with coincident logic provisions for trip actuation, failures-may be justified for a diesel-generator unit that or (2) a trip may be bypassed under accident conditions, carries only one large connected load tested under actual provided the operator has sufficient time to react appro- conditions, provided an equivalent reliability/confidence priately to an abnormal diesel-generator unit condition. The level is demonstrated.

design of the bypass circuitry should satisfy the requirements of IEEE Std 279-1971 at the diesel-generator system level 14. In Section 6.3.1, "Load Capability Qualification," of

- and should include the capability for (1) testing the status IEEE Std 387-1977, the order of sequence of load tests and operability of the bypass circuits, (2) alarming in the described in parts (1) and (2) should be as follows: Load control room abnormal values of all bypass parameters, and equal to the continuous rating should be applied for the

(3) manually resetting of the trip bypass function. (Capability time required to reach engine temperature equilibrium, at for automatic reset is not acceptable.) which time, the rated short-time load should be applied for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Immediately following the 2-hour

8. Section 5.6.3.1, "Surveillance Systems," of IEEE Std short-time load test, load equal to the continuous rating

387-1977 pertains to status indication of diesel-generator should be applied for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.

unit conditions. In conjunction with Section 5.6.3.1, in order to facilitate trouble diagnosis, the surveillance system

D. IMPLEMENTATION

should indicate which of the diesel-generator protective trips is activated first. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified

9. In Section 6.3, "Type Qualification Testing Procedures portions of the Commission's regulations, the method de- and Methods," of IEEE Std 387-1977, the requirements of scribed herein will be used in the evaluation of applications IEEE Std 344-1975, "Recommended Practices for Seismic for construction permits docketed after December 1979.

1.9-3

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555 POSTAGE AND FEES PAID

U.S. NUCLEAR REGULATORY

OFFICIAL BUSINESS COMMISSION

PENALTY FOR PRIVATE USE, $300

120555011962 1 SN

US NRC

OFFICE OF THE COMMISSIONERS

DR JOSEPH HENDRIE

COMMISSIONER

Hi 149 WASHINGTUN DC 20555