Regulatory Guide 1.9: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A381
| number = ML12305A253
| 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 Power Systems at Nuclear Power Plants
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/OSD, 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 November 1978 U.S. NUCLEAR REGULATORY COMMISSION
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION
k REGULATORY GUIDE
Revision 2 December 1979 REGULATORY G IDE
* '
OFFICE OF STANDARDS DEVELOPMENT
OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE 1.9 SELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR
REGULATORY GUIDE 1.9 SELECTION, DESIGN, AND QUALIFICATION OF DIESEL-GENERATOR UNITS USED AS
UNITS USED AS ONSITE ELECTRIC POWER SYSTEMS
STANDBY (ONSITE) ELECTRIC POWER SYSTEMS AT NUCLEAR POWER PLANTS
AT NUCLEAR POWER PLANTS
A.


INTRODUCTION
==A. INTRODUCTION==
General Design Criterion 17, "Electric Power Systems,"
of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Produc- tion and Utilization Facilities," includes a requirement that the onsite electric power system have sufficient capacity and capability to ensure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences and (2) the core is cooled and con- tainment integrity and other vital functions are maintained in the event of postulated accidents.
 
Criterion III, "Design Control," of Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 includes a require- ment that measures be provided for verifying or checking the adequacy of design by design reviews, by the use of alternative or simplified calculational methods, or by the performance of a suitable testing program.
 
Diesel-generator units have been widely used as the power source for the onsite electric power systems. This regulatory guide describes a method acceptable to the NRC
staff for complying with the Commission's requirements that diesel-generator units intended for use as onsite power sources in nuclear power plants be selected with sufficient capacity and be qualified for this service. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.


==B. DISCUSSION==
==B. DISCUSSION==
General Design Criterion 17, "Electric Power A diesel-generator unit selected for use in an Systems,"
A diesel-generator unit selected for use in an onsite electric power system should have the capability to (1) start and accelerate a number of large motor loads in rapid succession and be able to sustain the loss of all or any part of such loads and maintain voltage and frequency within acceptable limits and (2) supply power continuously to the Lines indicate substantive changes from Revision 1.
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
equipment needed to maintain the plant in a safe condition if an extended loss of offsite power occurs.
" 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
IEEE Std 387-1977, "IEEE Standard Criteria for Diesel- Generator Units Applied as Standby Power Supplies for Nu- clear Power Generating Stations," 1 delineates principal design criteria and qualification testing requirements that, if followed, will help ensure that selected diesel-generator units meet their performance and reliability requirements.
'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),
IEEE Std 387-1977 was developed by Working Group 4.2C
approved by NPEC,
of the Nuclear Power Engineering Committee (NPEC) of the Institute of Electrical and Electronics Engineers, Inc.
testing program.


,  
(IEEE), approved by NPEC, and subsequently approved by the IEEE Standards Board on September 9, 197
and subsequently approved by the -IEEE Stan-
-
"
dards Board on September 9,  
1976.


IEEE Std Diesel-generator units have been wiely ud
===6. IEEE Std===
387-1977 is supplementary to IEEE Std 308- as the power source for the onsi V
387-1977 is supplementary to IEEE Std 308-1974, "IEEE
le ic
Standard Criteria for Class 1E Power Systems and Nuclear Power Generating Stations,"l and specifically amplifies paragraph 5.2.4, "Standby Power Supplies," of that docu- ment with respect to the application of diesel-generator units. IEEE Std 308-1974 is endorsed, with certain excep- tions, by Regulatory Guide 1.32, "Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants."
1974,  
A knowledge of the characteristics of each load is essential in establishing the bases for 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 eight times its rated load I
"IEEE Standard. Criteria for Class IE
current. The sudden large increases in current drawn from the diesel generator resulting from the startup of induction- motors can result in substantial voltage reductions. The lower voltage could prevent a motor from starting, i.e.,
power systems.
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.


This regulatory gfiae
tCopies may be obtained from the Institute of Electrical and Electronics Engineers, Inc., United Engineering Center, 345 East
-
47th Street, New York, New York 10017.
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
USNRC REGULATORY GUIDES
Guide 1.32,
Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech- niques used by the staff in evaluating specific problems or postu- lated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required. Methods and solutions different from those set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.
"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
Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new information or experience. This guide was revised as a result of substantive com- ments received from the public and additional staff review.
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
Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Service Branch.
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
The guides are issued in the following ten broad divisions:
.evilon.


Comments should be sMnt to the Secrety of the Conmi;slon, U.S. Nudcer Regulatory Commurorn
====i. Power Reactors ====
, Wastington, D.C. 26.


Attention: Dockasth and Sevice Branch.
===6. Products===
2. Research and Test Reactors


The guides are Issued In the following ten broad divisioin:
===7. Transportation===
1. Power React"
3. Fuels and Materials Facilities
2. Reseerch end Teat Reactors
3. Fuels and Materiab Factites
4. Environmental and Sitng rL Matmerilsand Plant protection B. Products


===7. Transportation===
===8. Occupational Health===
& Occupational Health
4. Environmental and Siting
9. Antitrust and Financial Review
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.
5. Materials and Plant Protection 1
 
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.
===0. General===
.Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe- cific divisions is available through the Government Printing Office.


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.
Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Publications Sales Manager.


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.
These same consequences can also result from the cumu- lative.effect of a sequence of more moderate transients if, the system is not permitted to recover sufficiently between successive steps in a loading sequence.


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


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.
Protection of the diesel-generator unit from excessive overspeed, which can result from a loss of load, is afforded by the immediate operation of a diesel-generator unit trip, usually set at 115 percent of nominal speed. In addition, the generator differential trip must operate immediately in order to prevent substantial damage to the generator. There are other protective trips provided to protect the diesel- generator units from possible damage or degradation.


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.
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 actuation 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.
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 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.
This margin can be provided by estimating the loads conser- vatively 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 accurate estimate of safety loads is possible during 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==
Conformance with the requirements of IEEE
Conformance with the requirements of IEEE Std 387-1977,
Std  
"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 qualifica- tion testing of diesel-generator units used as onsite electric power systems for nuclear power plants subject to the following:
387-1977,  
1. When the characteristics of loads are not accurately known, such as during the construction 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.
"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:
In the absence of fully substantiated performance character- istics for mechanical equipment such as pumps, the electric motor drive ratings should be calculated using conservative estimates of these characteristics, e.g., pump runout condi- tions and motor efficiencies of 90 percent or less and power factors of 85 percent or less.
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.
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.
3. In Section 5.1.1, "General," of IEEE Std 387-1977, the I
requirements of IEEE Std 308-1974 should be used subject to the regulatory position of Regulatory Guide 1.32.


4. In Section 5.1.1, "General," of IEEE Std
4. Section 5.1.2, "Mechanical and Electrical Capabilities,"
387-1977, the requirements of IEEE Std 308-
of IEEE Std 387-1977 pertains, in part, to the starting and load-accepting capabilities of the diesel-generator unit. In conjunction with Section 5.1.2, each diesel-generator unit should be capable of starting and accelerating to rated speed, in the required sequence, all the needed engineered safety feature and emergency shutdown loads. The diesel- generator unit design should be such that 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, respectively. (A larger decrease in voltage and frequency may be justified for a diesel-generator unit that carries only one large connected load.) Frequency should be restored to within 2 percent of nominal, and voltage should be restored to within 10 percent of nominal within
1974 should be used subject to the regulatory position of Regulatory Guide 1.32.
60 percent of each load-sequence time interval. (A greater percentage of the time interval may be used if it can be justified by analysis. However, the load-sequence time interval should include sufficient 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 lower. Further, the transient following the complete loss of load should not cause the speed of the unit to attain the overspeed trip setpoint.


5. Section 5.1.2, "Mechanical and Electrical Capabilities," of IEEE Std 387-1977 should be supplemented with the following:
5. In Section 5.4, "Qualification," of IEEE Std 387-1977, the qualification testing requirements of IEEE Std 323-1974,
"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
"IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations,"'
should be used subject to the regulatory position of Regulatory Guide 1.89,
"Qualification of Class IE Equipment for Nuclear Power Plants."
6. Section 5.5, "Design and Application Considerations,"
of IEEE Std 387-1977 pertains to design features for con- I
sideration in diesel-generator unit design. In conjunction with Section 5.5, diesel-generator units should be designed
1.9-2
1.9-2


* within
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 Regula- tory 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.
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
Testability should be considered in the selection and location of instrumentation sensors and critical components (e.g.,
Std
governor, starting system components), and the overall design should include status indication and alarm features. Instrumentation sensors should be readily accessible and, where practicable, designed so that their inspection and calibration can be verified in place.
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.)"
7. Section 5.6.2.2, "Automatic Control," of IEEE Std
9. Section 5.6.3. 1, "Surveillance Systems," or IEEE Std 387-1977 should be supplemented with the following:
387-1977 pertains to automatic startup requirements and their relationship to other operating modes. In conjunction with Section5.6.2.2, engine-overspeed and generator-differ- ential trips may be implemented by a single-channel trip. All other diesel-generator protective trips should be handled in one of two ways: Either, (1) a trip should be implemented with two or more independent measurements for each trip parameter with coincident logic provisions for trip actuation, or (2) a trip may be bypassed under accident conditions, provided the operator has sufficient time to react appro- priately to an abnormal diesel-generator unit condition. 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 (1) testing the status and operability of the bypass circuits, (2) alarming in the control room abnormal values of all bypass parameters, and
"In order to facilitate trouble diagnosis, the surveillance system should indicate which of the diesel-generator protective trips is acti- vated first."
(3) manually resetting of the trip bypass function. (Capability for automatic reset is not acceptable.)
10. In Section 6.3, "Type Qualification Test- ing Procedures and Methods," of IEEE Std 387-
8. Section 5.6.3.1, "Surveillance Systems," of IEEE Std
1977, the requirements of IEEE Std 344-1975,
387-1977 pertains to status indication of diesel-generator unit conditions. In conjunction with Section 5.6.3.1, in order to facilitate trouble diagnosis, the surveillance system should indicate which of the diesel-generator protective trips is activated first.
"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.
9. In Section 6.3, "Type Qualification Testing Procedures and Methods," of IEEE Std 387-1977, the requirements of IEEE Std 344-1975, "Recommended Practices for Seismic Qualification 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 position of Regulatory Guide 1.100, "Seismic Qualification of Electric Equipment for Nuclear Power Plants."
10. The option indicated by "may" in Section 6.3.2(5)(c)
of IEEE Std 387-1977 should be treated as a requirement.


12.
11. Section 6.5, "Site Acceptance Testing," and Section 6.6,
"Periodic Testing," of IEEE Std 387-1977 should be supple- mented by Regulatory Guide 1.108.


Section 6.5, "Site Acceptance Testing,"
12. Section 4, "Reference Standards," of IEEE Std 387-1977 lists additional applicable IEEE standards. The specific appli- cability or acceptability of these referenced standards has been or will be covered separately in other regulatory guides, where appropriate.
and Section 6.6, "Periodic Testing," of IEEE
Std 387-1977 should be supplemented by Regu- latory Guide 1.108.


13.
13. Section 6.3.2,
"Start and Load Acceptance Qualifi- cation," pertains to test requirements for diesel-generator unit qualification.


Section 4,  
In conjunction with Section 6.3.2, fewer successful start-and-load tests and allowed failures than that specified-300 valid tests with no more than 3 failures-may be justified for a diesel-generator unit that carries only one large connected load tested under actual conditions, provided an equivalent reliability/confidence level is demonstrated.
"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.
14. In Section 6.3.1, "Load Capability Qualification," of IEEE Std 387-1977, the order of sequence of load tests described in parts (1) and (2) should be as follows: Load equal to the continuous rating should be applied for the time required to reach engine temperature equilibrium, at which time, the rated short-time load should be applied for a period of 2 hours. Immediately following the 2-hour short-time load test, load equal to the continuous rating should be applied for 22 hours. ,


D.
==D. IMPLEMENTATION==
Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method de- scribed herein will be used in the evaluation of applications for construction permits docketed after December 1979.


IMPLEMENTATION
1.9-3
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.
UNITED STATES
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Revision as of 21:27, 11 January 2025

Selection, Design, and Qualification of Diesel-Generator Units Used as Standby (Onsite) Electric Power Systems at Nuclear Power Plants
ML12305A253
Person / Time
Issue date: 12/31/1979
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NRC/OSD, Office of Nuclear Regulatory Research
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References
RG-1.009, Rev 2
Download: ML12305A253 (4)


U.S. NUCLEAR REGULATORY COMMISSION

Revision 2 December 1979 REGULATORY G IDE

  • '

OFFICE OF STANDARDS DEVELOPMENT

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

STANDBY (ONSITE) ELECTRIC POWER SYSTEMS AT NUCLEAR POWER PLANTS

A. INTRODUCTION

General Design Criterion 17, "Electric Power Systems,"

of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50, "Domestic Licensing of Produc- tion and Utilization Facilities," includes a requirement that the onsite electric power system have sufficient capacity and capability to ensure that (1) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences and (2) the core is cooled and con- tainment integrity and other vital functions are maintained in the event of postulated accidents.

Criterion III, "Design Control," of Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50 includes a require- ment that measures be provided for verifying or checking the adequacy of design by design reviews, by the use of alternative or simplified calculational methods, or by the performance of a suitable testing program.

Diesel-generator units have been widely used as the power source for the onsite electric power systems. This regulatory guide describes a method acceptable to the NRC

staff for complying with the Commission's requirements that diesel-generator units intended for use as onsite power sources in nuclear power plants be selected with sufficient capacity and be qualified for this service. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.

B. DISCUSSION

A diesel-generator unit selected for use in an onsite electric power system should have the capability to (1) start and accelerate a number of large motor loads in rapid succession and be able to sustain the loss of all or any part of such loads and maintain voltage and frequency within acceptable limits and (2) supply power continuously to the Lines indicate substantive changes from Revision 1.

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

IEEE Std 387-1977, "IEEE Standard Criteria for Diesel- Generator Units Applied as Standby Power Supplies for Nu- clear Power Generating Stations," 1 delineates principal design criteria and qualification testing requirements that, if followed, will help ensure that selected diesel-generator units meet their performance and reliability requirements.

IEEE Std 387-1977 was developed by Working Group 4.2C

of the Nuclear Power Engineering Committee (NPEC) of the Institute of Electrical and Electronics Engineers, Inc.

(IEEE), approved by NPEC, and subsequently approved by the IEEE Standards Board on September 9, 197

6. IEEE Std

387-1977 is supplementary to IEEE Std 308-1974, "IEEE

Standard Criteria for Class 1E Power Systems and Nuclear Power Generating Stations,"l and specifically amplifies paragraph 5.2.4, "Standby Power Supplies," of that docu- ment with respect to the application of diesel-generator units. IEEE Std 308-1974 is endorsed, with certain excep- tions, by Regulatory Guide 1.32, "Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants."

A knowledge of the characteristics of each load is essential in establishing the bases for 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 eight times its rated load I

current. The sudden large increases in current drawn from the diesel generator resulting from the startup of induction- 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.

tCopies may be obtained from the Institute of Electrical and Electronics Engineers, Inc., United Engineering Center, 345 East

47th Street, New York, New York 10017.

USNRC REGULATORY GUIDES

Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech- niques used by the staff in evaluating specific problems or postu- lated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required. Methods and solutions different from those set out in the guides will be acceptable if they provide a basis for the findings requisite to the issuance or continuance of a permit or license by the Commission.

Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new information or experience. This guide was revised as a result of substantive com- ments received from the public and additional staff review.

Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Service Branch.

The guides are issued in the following ten broad divisions:

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0. General

.Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe- cific divisions is available through the Government Printing Office.

Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Publications Sales Manager.

These same consequences can also result from the cumu- lative.effect of a sequence of more moderate transients if, the system is not permitted to recover sufficiently between successive 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 operation of a diesel-generator unit trip, usually set at 115 percent of nominal speed. In addition, the generator differential trip must operate immediately in order to prevent substantial damage to the generator. There are other protective trips provided to protect the diesel- generator units from possible damage or degradation.

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 actuation 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 conser- vatively 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 accurate estimate of safety loads is possible during 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 qualifica- tion 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 construction 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 character- istics for mechanical equipment such as pumps, the electric motor drive ratings should be calculated using conservative estimates of these characteristics, e.g., pump runout condi- tions and motor efficiencies of 90 percent or less and power factors of 85 percent 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. In Section 5.1.1, "General," of IEEE Std 387-1977, the I

requirements of IEEE Std 308-1974 should be used subject to the regulatory position of Regulatory Guide 1.32.

4. Section 5.1.2, "Mechanical and Electrical Capabilities,"

of IEEE Std 387-1977 pertains, in part, to the starting and load-accepting capabilities of the diesel-generator unit. In conjunction with Section 5.1.2, each diesel-generator unit should be capable of starting and accelerating to rated speed, in the required sequence, all the needed engineered safety feature and emergency shutdown loads. The diesel- generator unit design should be such that 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, respectively. (A larger decrease in voltage and frequency may be justified for a diesel-generator unit that carries only one large connected load.) Frequency should be restored to 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 percentage of the time interval may be used if it can be justified by analysis. However, the load-sequence time interval should include sufficient 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 lower. Further, the transient following the complete loss of load should not cause the speed of the unit to attain the overspeed trip setpoint.

5. In Section 5.4, "Qualification," of IEEE Std 387-1977, the qualification testing requirements of IEEE Std 323-1974,

"IEEE Standard for Qualifying Class IE Equipment for Nuclear Power Generating Stations,"'

should be used subject to the regulatory position of Regulatory Guide 1.89,

"Qualification of Class IE Equipment for Nuclear Power Plants."

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

of IEEE Std 387-1977 pertains to design features for con- I

sideration in diesel-generator unit design. In conjunction with Section 5.5, diesel-generator units should be designed

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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 Regula- tory 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 sensors and critical components (e.g.,

governor, starting system components), and the overall design should include status indication and alarm features. Instrumentation sensors should be readily accessible and, where practicable, designed so that their inspection and calibration can be verified in place.

7. Section 5.6.2.2, "Automatic Control," of IEEE Std 387-1977 pertains to automatic startup requirements and their relationship to other operating modes. In conjunction with Section5.6.2.2, engine-overspeed and generator-differ- ential trips may be implemented by a single-channel trip. All other diesel-generator protective trips should be handled in one of two ways: Either, (1) a trip should be implemented with two or more independent measurements for each trip parameter with coincident logic provisions for trip actuation, or (2) a trip may be bypassed under accident conditions, provided the operator has sufficient time to react appro- priately to an abnormal diesel-generator unit condition. 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 (1) testing the status and operability of the bypass circuits, (2) alarming in the control room abnormal values of all bypass parameters, and

(3) manually resetting of the trip bypass function. (Capability for automatic reset is not acceptable.)

8. Section 5.6.3.1, "Surveillance Systems," of IEEE Std 387-1977 pertains to status indication of diesel-generator unit conditions. In conjunction with Section 5.6.3.1, in order to facilitate trouble diagnosis, the surveillance system should indicate which of the diesel-generator protective trips is activated first.

9. In Section 6.3, "Type Qualification Testing Procedures and Methods," of IEEE Std 387-1977, the requirements of IEEE Std 344-1975, "Recommended Practices for Seismic Qualification 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 position of Regulatory Guide 1.100, "Seismic Qualification of Electric Equipment for Nuclear Power Plants."

10. The option indicated by "may" in Section 6.3.2(5)(c)

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

11. Section 6.5, "Site Acceptance Testing," and Section 6.6,

"Periodic Testing," of IEEE Std 387-1977 should be supple- mented by Regulatory Guide 1.108.

12. Section 4, "Reference Standards," of IEEE Std 387-1977 lists additional applicable IEEE standards. The specific appli- cability or acceptability of these referenced standards has been or will be covered separately in other regulatory guides, where appropriate.

13. Section 6.3.2,

"Start and Load Acceptance Qualifi- cation," pertains to test requirements for diesel-generator unit qualification.

In conjunction with Section 6.3.2, fewer successful start-and-load tests and allowed failures than that specified-300 valid tests with no more than 3 failures-may be justified for a diesel-generator unit that carries only one large connected load tested under actual conditions, provided an equivalent reliability/confidence level is demonstrated.

14. In Section 6.3.1, "Load Capability Qualification," of IEEE Std 387-1977, the order of sequence of load tests described in parts (1) and (2) should be as follows: Load equal to the continuous rating should be applied for the time required to reach engine temperature equilibrium, at 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 short-time load test, load equal to the continuous rating should be applied for 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />. ,

D. IMPLEMENTATION

Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method de- scribed herein will be used in the evaluation of applications for construction permits docketed after December 1979.

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