Regulatory Guide 1.9: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
Line 14: Line 14:
| page count = 3
| page count = 3
}}
}}
{{#Wiki_filter:Revision 1 U.S. NUCLEAR REGULATORY COMMISSION                                                                                   November 1978 k REGULATORY GUIDE
{{#Wiki_filter:Revision 1 November 1978 U.S. NUCLEAR REGULATORY COMMISSION
                            OFFICE OF STANDARDS DEVELOPMENT
k REGULATORY GUIDE
                                                                  REGULATORY GUIDE 1.9 SELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR
OFFICE OF STANDARDS DEVELOPMENT
                          UNITS USED AS ONSITE ELECTRIC POWER SYSTEMS
REGULATORY GUIDE 1.9 SELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR
                                                  AT NUCLEAR POWER PLANTS
UNITS USED AS ONSITE ELECTRIC POWER SYSTEMS
AT NUCLEAR POWER PLANTS
A.


==A. INTRODUCTION==
INTRODUCTION


==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'
General Design Criterion 17, "Electric Power A diesel-generator unit selected for use in an Systems,"  
result of anticipated operational occurrences                                                                                     A
of Appendix 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
"General Design onsite electric power system should have the Criteria for Nuclear Power Plants," to 10 CFR  
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)
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 that the onsite electric power system have such loads and maintain v0I*ge an, Irequency sufficient capacity and capability to ensure within acceptable limit  
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-
supply power that (1)  
                                                                              - "      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
specified acceptable fuel design limits continuously to the bq*"4 i  
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. "
V~eded 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  
it impractical to              the c    ges wit*      es in the margin.
loss of offsite po A~r o  
urý b'
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.


'Copies          e                    the Institute of Electrical and                  A knowledge of the characteristics of each Electronics                In ..n  ited Engineering Center, 345 East
Power
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.
" 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.


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:
IEEE Std 387-1977 was measures be provided for verifying or checking
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.
'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
0
ot
.he Institute of Electrical and Electronics methods, or by the performance of a suit".e Engineers, Inc.


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.
(IEEE),  
approved by NPEC,
testing program.


motor from starting, i.e. , accelerating its load to rated speed in the required time, or cause a                  
,
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 onsi V
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 Electronics In .. n ited Engineering Center, 345 East
47th Street, ork, New York 10017.
 
A knowledge of the characteristics of each load is essential in establishing the bases for USNRC REGULATORY GUIDES
Regulatney Guides re Issued to descrbe and rnake available to the public methods acceptable to the NRC staff of specific parts of the commlssiora's regultionts, to delinestedvt sdb the staff In avalu- atg spec probles or postulated accidents. or to provide guidance to applicants. Regulatory Guides ae not sutbstitutes for regulations, and corn- plence with them Is not requked. Methods end solutions different from those set out In the guides wil b acceptable If they provide a b"si for the findings re=ui to the issgirce or continuance of a pewrh or Bse e by the Cornwitiuo*
Comments and suggestions for Imroernemeis In tees gudes are encouraged at Imes, end guides wil e rwl sd, be aspramopas, to accommodate corn- mene= and to reflect new rmt or aperen*e. Howeve. corment t, this gtuld.
 
If eeed wlfhn about two mond afte Its Issuance, wil be wfttleft useful In awluating the need for an eauly r
.evilon.
 
Comments should be sMnt to the Secrety of the Conmi;slon, U.S. Nudcer Regulatory Commurorn
, Wastington, D.C. 26.
 
Attention: Dockasth and Sevice Branch.
 
The guides are Issued In the following ten broad divisioin:
1. Power React"
2. Reseerch end Teat Reactors
3. Fuels and Materiab Factites
4. Environmental and Sitng rL Matmerilsand Plant protection B. Products
 
===7. Transportation===
& Occupational Health
9. Antitrust and Financial Review
10. General Requests for single copies of Isued guides Iwit-h may be reproducedl or for placerment on en autonlatic: distribution list for single copies of fuaum guldes In s ief*c divslons should be ,de In wrtltng to the US. NudIsr Reguatory Cornenssion, Washingion, D.C.
 
I, Attentio:
Okector, D,4lon of Technical Informaiwon and Document Control.
 
the selection of a diesel-generator unit that is able to accept large loads in rapid succession.
 
The majority of the emergency loads are large induction motors. This type of motor draws, at full voltage, a starting current five to ten times its rated load current. The sudden large increases in current drawn from the diesel generator resulting from the startup of induc- tion motors can result in substantial voltage reductions. The lower voltage could prevent a motor from starting, i.e. , accelerating its load to rated speed in the required time, or cause a running motor to coast down or stall. Other loads might be lost if their contactors drop out.
 
Recovery from the transient caused by starting large motors or from the loss of a large load could cause diesel engine overspeed which, if excessive, might result in a trip of the engine. These same consequences can also result from the cumulative effect of a sequence of more moderate transients if the system is not permitted to recover sufficiently between suc- cessive steps in a loading sequence.
 
Generally it has been industry practice to specify a maximum voltage reduction of 10 to 15 percent when starting large motors from large- capacity power systems and a voltage reduction of 20 to 30 percent when starting these motors from limited-capacity power sources such as diesel-generator units. Large induction motors can achieve rated speed in less than 5 seconds when powered from adequately sized diesel- generator units that are capable of restoring the voltage to 90 percent of nominal in about 1 second.
 
Protection of the diesel-generator unit from excessive overspeed, which can result from a loss of load, is afforded by the immediate oper- ation of a diesel-generator unit trip, usually set at 115 percent of nominal speed. In addi- tion, the generator differential trip must oper- ate immediately in order to prevent substantial damage to the generator. There are other pro- tective trips provided to protect the diesel- generator units from possible damage or degra- dation.
 
However, these trips could interfere with the successful functioning of the unit when it is most needed, i.e. , during accident conditions.
 
Experience has shown that there have been numerous occasions when these trips have needlessly shut down diesel-generator units because of spurious operation of a trip circuit.
 
Consequently, it is important that measures be taken to ensure that spurious ac- tuation of these other protective trips does not prevent the diesel-generator unit from performing its function.
 
The uncertainties inherent in estimates of safety loads at the construction permit stage of design are sometimes of such magnitude that it is prudent to provide a substantial margin in selecting the load capabilities of the diesel- generator unit. This margin can be provided by estimating the loads conservatively and selecting the continuous rating of the diesel- generator unit so that it exceeds the sum of the loads needed at any one time. A more accu- rate estimate of safety loads is possihle duringl the operating license stage of review because detailed designs have been completed and preoperational test data are available.
 
This permits the consideration of a somewhat less conservative approach, such as operation with safety loads within the short-time rating of the diesel-generator unit.


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
running motor to coast down or stall. Other loads might be lost if their contactors drop                Conformance with the requirements of IEEE
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.
Std  
387-1977,  
"IEEE  
Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations," dated June 17,  
1977, is acceptable for meeting the requirements of the principal design criteria and qualification testing of diesel-generator units used as onsite electric.
 
power systems for nuclear power plants subject to the following:
1. When the characteristics of loads are not accurately known, such as during the con- struction permit stage of design, each diesel- generator unit of an onsite power supply system should be selected to have a continuous load rating (as defined in Section 3.7.1 of IEEE
Std 387-1977) equal to or greater than the sum of the conservatively estimated loads needed to be powered by that unit at any one time. In the absence of fully substantiated performance characteristics for mechanical equipment such as pumps, the electric motor drive ratings should be calculated using conservative esti- mates of these characteristics, e.g.,
pump runout conditions and motor efficiencies of 90%
or less.
 
2. At the operating license stage of review, the predicted loads should not exceed the short-time rating (as defined in Section 3.7.2 of IEEE Std 387-1977) of the diesel-generator unit.
 
3. During preoperational testing, the pre- dicted loads should be verified by tests.
 
4. In Section 5.1.1, "General," of IEEE Std
387-1977, the requirements of IEEE Std 308-
1974 should be used subject to the regulatory position of Regulatory Guide 1.32.
 
5. Section 5.1.2, "Mechanical and Electrical Capabilities," of IEEE Std 387-1977 should be supplemented with the following:
"Each diesel-generator unit should be capa- ble of starting and 'accelerating to rated speed, in the required sequence, all the needed engineered safety feature and emer- gency shutdown loads. At no time during the loading sequence should the frequency and voltage decrease to less than 95 percent of nominal and 75 percent of nominal, respec- tively"b Frequency should be restored to
1.9-2
 
* within
2 percent of nominal, and voltage should be restored to within 10 percent of nominal within
60 percent of each load- sequence time interval. (A greater percent- age of the time interval may be used if it can be justified by analysis. However, the load- sequence time interval should include suffi- cient margin to account for the accuracy and repeatability of the load-sequence timer.)
During recovery from transients caused by step load increases or resulting from the disconnection of the largest single load, the speed of the diesel-generator unit should not exceed the nominal speed plus 75 percent of the difference between nominal speed and the overspeed trip setpoint or 115 *percent of nominal, whichever is lowei.
 
Further, the transient following the complete loss of load should not cause the speed of the unit to attain the overspeed trip setpoint."
6.
 
In Section 5.4, "Qualification,"
of IEEE
Std 387-1977, the qualification testing require- ments of IEEE Std 323-1974, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations,"' should be used subject to the regulatory p*osition of Regulatory Guide 1.89,
"Qualification of C!ass IE Equip- ment for Nuclear Power Plants."
7. Section 5.5, "Design and Application Con- siderations," of IEEE Std 387-1977 should be supplemented with the following:
"Diesel-generator units should be designed to be testable during operation of the nuclear power plant as well as while the plant is shut down. The design should include provisions so that the testing of the units will simulate the parameters of operation (outlined in Regulatory Guide 1.108, "Periodic Testing of Diesel-Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants")
that would be expected if actual demand were to be placed on the system.
 
"Testability should be considered in the selection and location of instrumentation sen- sors and critical components (e.g.,
gover- nor, starting system components),
and the overall design should include status indica- tion and alarm features.
 
Instrumentation sensors should be readily accessible and designed so that their inspection and calibra- tion can be verified in place."
8.


permitted to recover sufficiently between suc-          power systems for nuclear power plants subject cessive steps in a loading sequence.                   to the following:
Section 5.6.2.2, "Automatic Control," of IEEE Std 387-1977 should be supplemented with
    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
,the following:
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%
(3) "With the exception of the engine over- speed trip and the generator differential trip, all diesel-generator protective trips should be either (1)
loss of load, is afforded by the immediate oper-        or less.
implemented with two or more independent measurements for each trip parameter with coincident logic provisions for trip actuation or (2)
automatically bypassed during accident conditions.


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 design of the bypass circuitry should satisfy the requirements of IEEE
Std
279-1971 at the diesel- generator system level and should include the capability for (I) testing the status and operability of the bypass circuits,  
(2) alarming in the control room abnormal values of all bypass param- eters, and (3)  
manually resetting of the trip bypass function.


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.
(Capability for automatic reset is not acceptable.)"
9. Section 5.6.3. 1, "Surveillance Systems," or IEEE Std 387-1977 should be supplemented with the following:
"In order to facilitate trouble diagnosis, the surveillance system should indicate which of the diesel-generator protective trips is acti- vated first."
10. In Section 6.3, "Type Qualification Test- ing Procedures and Methods," of IEEE Std 387-
1977, the requirements of IEEE Std 344-1975,
"Recommended Practices for Seismic Qualifica- tion of Class 1E Equipment for Nuclear Power Generating Stations," for seismic analysis or seismic testing by equipment manufacturers should be used subject to the regulatory posi- tion of Regulatory Guide 1.100, "Seismic Quali- fication of Electric Equipment for Nuclear Power Plants."
11.


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.
The option indicated by "may" in Sec- tion 6.3.2(5)(c) of IEEE Std 387-1977 should be treated as a requirement.


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:
12.
performing its function.


"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
Section 6.5, "Site Acceptance Testing,"
                                                  1.9-2
and Section 6.6, "Periodic Testing," of IEEE
Std 387-1977 should be supplemented by Regu- latory Guide 1.108.


* 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.)"
13.
  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:
  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."
  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,"
Section 4,  
  down. The design should include provisions            and Section 6.6, "Periodic Testing," of IEEE
"Reference Standards,"  
  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.
of IEEE Std 387-1977 lists additional applicable IEEE standards.


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
The specific applicability or acceptability of these referenced standards has been or will be covered separately in other regulatory guides, where appropriate.
  "Testability should be considered in the              regulatory guides, where appropriate.


selection and location of instrumentation sen- sors and critical components (e.g., gover-                           
D.


==D. IMPLEMENTATION==
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
This proposed guide has been released to encourage public participation in its develop- ment. Except in those cases in which an appli- cant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method to be described in the active guide reflecting public comments will be used in the evaluation of applications for construction permits docketed after the implementation date to be specified in the active guide. This implementation date will in no case be earlier than July 1979.
  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
,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.
If an .applicant wishes to use this draft guide in an application docketed prior to the imple- mentation date, the pertinent portions of the application will be evaluated on the basis of this draft guide.


1.9-3}}
1.9-3}}


{{RG-Nav}}
{{RG-Nav}}

Revision as of 00:16, 11 January 2025

Selection, Design, and Qualification of Diesel-Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants
ML13350A381
Person / Time
Issue date: 11/30/1978
From:
NRC/OSD
To:
References
RG-1.009, Rev. 1
Download: ML13350A381 (3)


Revision 1 November 1978 U.S. NUCLEAR REGULATORY COMMISSION

k REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.9 SELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR

UNITS USED AS ONSITE ELECTRIC POWER SYSTEMS

AT NUCLEAR POWER PLANTS

A.

INTRODUCTION

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 that the onsite electric power system have such loads and maintain v0I*ge an, Irequency sufficient capacity and capability to ensure within acceptable limit

"

supply power that (1)

specified acceptable fuel design limits continuously to the bq*"4 i

V~eded 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'

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

0

ot

.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 onsi V

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 Electronics In .. n ited Engineering Center, 345 East

47th Street, ork, New York 10017.

A knowledge of the characteristics of each load is essential in establishing the bases for USNRC REGULATORY GUIDES

Regulatney Guides re Issued to descrbe and rnake available to the public methods acceptable to the NRC staff of specific parts of the commlssiora's regultionts, to delinestedvt sdb the staff In avalu- atg spec probles or postulated accidents. or to provide guidance to applicants. Regulatory Guides ae not sutbstitutes for regulations, and corn- plence with them Is not requked. Methods end solutions different from those set out In the guides wil b acceptable If they provide a b"si for the findings re=ui to the issgirce or continuance of a pewrh or Bse e by the Cornwitiuo*

Comments and suggestions for Imroernemeis In tees gudes are encouraged at Imes, end guides wil e rwl sd, be aspramopas, to accommodate corn- mene= and to reflect new rmt or aperen*e. Howeve. corment t, this gtuld.

If eeed wlfhn about two mond afte Its Issuance, wil be wfttleft useful In awluating the need for an eauly r

.evilon.

Comments should be sMnt to the Secrety of the Conmi;slon, U.S. Nudcer Regulatory Commurorn

, Wastington, D.C. 26.

Attention: Dockasth and Sevice Branch.

The guides are Issued In the following ten broad divisioin:

1. Power React"

2. Reseerch end Teat Reactors

3. Fuels and Materiab Factites

4. Environmental and Sitng rL Matmerilsand Plant protection B. Products

7. Transportation

& Occupational Health

9. Antitrust and Financial Review

10. General Requests for single copies of Isued guides Iwit-h may be reproducedl or for placerment on en autonlatic: distribution list for single copies of fuaum guldes In s ief*c divslons should be ,de In wrtltng to the US. NudIsr Reguatory Cornenssion, Washingion, D.C.

I, Attentio:

Okector, D,4lon of Technical Informaiwon and Document Control.

the selection of a diesel-generator unit that is able to accept large loads in rapid succession.

The majority of the emergency loads are large induction motors. This type of motor draws, at full voltage, a starting current five to ten times its rated load current. The sudden large increases in current drawn from the diesel generator resulting from the startup of induc- tion motors can result in substantial voltage reductions. The lower voltage could prevent a motor from starting, i.e. , accelerating its load to rated speed in the required time, or cause a running motor to coast down or stall. Other loads might be lost if their contactors drop out.

Recovery from the transient caused by starting large motors or from the loss of a large load could cause diesel engine overspeed which, if excessive, might result in a trip of the engine. These same consequences can also result from the cumulative effect of a sequence of more moderate transients if the system is not permitted to recover sufficiently between suc- cessive steps in a loading sequence.

Generally it has been industry practice to specify a maximum voltage reduction of 10 to 15 percent when starting large motors from large- capacity power systems and a voltage reduction of 20 to 30 percent when starting these motors from limited-capacity power sources such as diesel-generator units. Large induction motors can achieve rated speed in less than 5 seconds when powered from adequately sized diesel- generator units that are capable of restoring the voltage to 90 percent of nominal in about 1 second.

Protection of the diesel-generator unit from excessive overspeed, which can result from a loss of load, is afforded by the immediate oper- ation of a diesel-generator unit trip, usually set at 115 percent of nominal speed. In addi- tion, the generator differential trip must oper- ate immediately in order to prevent substantial damage to the generator. There are other pro- tective trips provided to protect the diesel- generator units from possible damage or degra- dation.

However, these trips could interfere with the successful functioning of the unit when it is most needed, i.e. , during accident conditions.

Experience has shown that there have been numerous occasions when these trips have needlessly shut down diesel-generator units because of spurious operation of a trip circuit.

Consequently, it is important that measures be taken to ensure that spurious ac- tuation of these other protective trips does not prevent the diesel-generator unit from performing its function.

The uncertainties inherent in estimates of safety loads at the construction permit stage of design are sometimes of such magnitude that it is prudent to provide a substantial margin in selecting the load capabilities of the diesel- generator unit. This margin can be provided by estimating the loads conservatively and selecting the continuous rating of the diesel- generator unit so that it exceeds the sum of the loads needed at any one time. A more accu- rate estimate of safety loads is possihle duringl the operating license stage of review because detailed designs have been completed and preoperational test data are available.

This permits the consideration of a somewhat less conservative approach, such as operation with safety loads within the short-time rating of the diesel-generator unit.

C. REGULATORY POSITION

Conformance with the requirements of IEEE Std 387-1977,

"IEEE

Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations," dated June 17,

1977, is acceptable for meeting the requirements of the principal design criteria and qualification testing of diesel-generator units used as onsite electric.

power systems for nuclear power plants subject to the following:

1. When the characteristics of loads are not accurately known, such as during the con- struction permit stage of design, each diesel- generator unit of an onsite power supply system should be selected to have a continuous load rating (as defined in Section 3.7.1 of IEEE Std 387-1977) equal to or greater than the sum of the conservatively estimated loads needed to be powered by that unit at any one time. In the absence of fully substantiated performance characteristics for mechanical equipment such as pumps, the electric motor drive ratings should be calculated using conservative esti- mates of these characteristics, e.g.,

pump runout conditions and motor efficiencies of 90%

or less.

2. At the operating license stage of review, the predicted loads should not exceed the short-time rating (as defined in Section 3.7.2 of IEEE Std 387-1977) of the diesel-generator unit.

3. During preoperational testing, the pre- dicted loads should be verified by tests.

4. In Section 5.1.1, "General," of IEEE Std 387-1977, the requirements of IEEE Std 308-

1974 should be used subject to the regulatory position of Regulatory Guide 1.32.

5. Section 5.1.2, "Mechanical and Electrical Capabilities," of IEEE Std 387-1977 should be supplemented with the following:

"Each diesel-generator unit should be capa- ble of starting and 'accelerating to rated speed, in the required sequence, all the needed engineered safety feature and emer- gency shutdown loads. At no time during the loading sequence should the frequency and voltage decrease to less than 95 percent of nominal and 75 percent of nominal, respec- tively"b Frequency should be restored to

1.9-2

  • within

2 percent of nominal, and voltage should be restored to within 10 percent of nominal within

60 percent of each load- sequence time interval. (A greater percent- age of the time interval may be used if it can be justified by analysis. However, the load- sequence time interval should include suffi- cient margin to account for the accuracy and repeatability of the load-sequence timer.)

During recovery from transients caused by step load increases or resulting from the disconnection of the largest single load, the speed of the diesel-generator unit should not exceed the nominal speed plus 75 percent of the difference between nominal speed and the overspeed trip setpoint or 115 *percent of nominal, whichever is lowei.

Further, the transient following the complete loss of load should not cause the speed of the unit to attain the overspeed trip setpoint."

6.

In Section 5.4, "Qualification,"

of IEEE Std 387-1977, the qualification testing require- ments of IEEE Std 323-1974, "IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations,"' should be used subject to the regulatory p*osition of Regulatory Guide 1.89,

"Qualification of C!ass IE Equip- ment for Nuclear Power Plants."

7. Section 5.5, "Design and Application Con- siderations," of IEEE Std 387-1977 should be supplemented with the following:

"Diesel-generator units should be designed to be testable during operation of the nuclear power plant as well as while the plant is shut down. The design should include provisions so that the testing of the units will simulate the parameters of operation (outlined in Regulatory Guide 1.108, "Periodic Testing of Diesel-Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants")

that would be expected if actual demand were to be placed on the system.

"Testability should be considered in the selection and location of instrumentation sen- sors and critical components (e.g.,

gover- nor, starting system components),

and the overall design should include status indica- tion and alarm features.

Instrumentation sensors should be readily accessible and designed so that their inspection and calibra- tion can be verified in place."

8.

Section 5.6.2.2, "Automatic Control," of IEEE Std 387-1977 should be supplemented with

,the following:

(3) "With the exception of the engine over- speed trip and the generator differential trip, all diesel-generator protective trips should be either (1)

implemented with two or more independent measurements for each trip parameter with coincident logic provisions for trip actuation or (2)

automatically bypassed during accident conditions.

The design of the bypass circuitry should satisfy the requirements of IEEE Std 279-1971 at the diesel- generator system level and should include the capability for (I) testing the status and operability of the bypass circuits,

(2) alarming in the control room abnormal values of all bypass param- eters, and (3)

manually resetting of the trip bypass function.

(Capability for automatic reset is not acceptable.)"

9. Section 5.6.3. 1, "Surveillance Systems," or IEEE Std 387-1977 should be supplemented with the following:

"In order to facilitate trouble diagnosis, the surveillance system should indicate which of the diesel-generator protective trips is acti- vated first."

10. In Section 6.3, "Type Qualification Test- ing Procedures and Methods," of IEEE Std 387-

1977, the requirements of IEEE Std 344-1975,

"Recommended Practices for Seismic Qualifica- tion of Class 1E Equipment for Nuclear Power Generating Stations," for seismic analysis or seismic testing by equipment manufacturers should be used subject to the regulatory posi- tion of Regulatory Guide 1.100, "Seismic Quali- fication of Electric Equipment for Nuclear Power Plants."

11.

The option indicated by "may" in Sec- tion 6.3.2(5)(c) of IEEE Std 387-1977 should be treated as a requirement.

12.

Section 6.5, "Site Acceptance Testing,"

and Section 6.6, "Periodic Testing," of IEEE Std 387-1977 should be supplemented by Regu- latory Guide 1.108.

13.

Section 4,

"Reference Standards,"

of IEEE Std 387-1977 lists additional applicable IEEE standards.

The specific applicability or acceptability of these referenced standards has been or will be covered separately in other regulatory guides, where appropriate.

D.

IMPLEMENTATION

This proposed guide has been released to encourage public participation in its develop- ment. Except in those cases in which an appli- cant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method to be described in the active guide reflecting public comments will be used in the evaluation of applications for construction permits docketed after the implementation date to be specified in the active guide. This implementation date will in no case be earlier than July 1979.

If an .applicant wishes to use this draft guide in an application docketed prior to the imple- mentation date, the pertinent portions of the application will be evaluated on the basis of this draft guide.

1.9-3