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{{#Wiki_filter:Revision 2 U.S. NUCLEAR REGULATORY COMMISSION                                                                                     February 1977 REGULATORY GUIDE
{{#Wiki_filter:Revision 2 February 1977 U.S. NUCLEAR REGULATORY COMMISSION
                                OFFICE OF STANDARDS DEVELOPMENT
REGULATORY GUIDE  
                                                                      REGULATORY GUIDE 1.32 CRITERIA FOR SAFETY-RELATED ELECTRIC POWER SYSTEMS
OFFICE OF STANDARDS DEVELOPMENT  
                                                                FOR NUCLEAR POWER PLANTS
REGULATORY GUIDE 1.32 CRITERIA FOR SAFETY-RELATED ELECTRIC POWER SYSTEMS  
FOR NUCLEAR POWER PLANTS


==A. INTRODUCTION==
==A. INTRODUCTION==
This revision to IEEE Std 308-1971 has made the standard consistent with the requirement in Criterion General Design Criterion 17, "Electric Power                                       17 for two circuits to the offsite network, each Systems," of Appendix A, "General Design Criteria                                       designed to be available in sufficient time following a for Nuclear Power Plants," to 10 CFR Part 50,                                           loss of onsite alternating current power supplies and
General Design Criterion 17, "Electric Power Systems," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50,  
  "Licensing of Production and Utilization Facilities,"                                   the other offsite electric power circuit. However, two requires that an onsite electric power system and an                                     potential conflicts with Criterion 17 remain un offsite electric power system be provided to permit                                     resolved: one in the area of availability of offsite functioning of structures, systems, and components                                       power (Item 1)and the other in battery charger supp important to safety. In addition, Criterion 17 con                                       ly requirements (Item 2). In addition, an incon tains requirements concerning system capacity, in                                       sistency exists between IEEE Std 308-1974 and IEEE
"Licensing of Production and Utilization Facilities,"  
  dependence, redundancy, availability, testability, and                                   Std 450-1975 (Item 3).
requires that an onsite electric power system and an offsite electric power system be provided to permit functioning of structures, systems, and components important to safety. In addition, Criterion 17 con tains requirements concerning system capacity, in dependence, redundancy, availability, testability, and reliability. General Design Criterion 18, "Inspection and Testing of Electric Power Systems," of Appendix A to 10 CFR Part 50, contains requirements concern ing periodic inspection, testing, and testability of electric power systems important to safety. This guide describes a method acceptable to the NRC staff of complying with Criteria 17 and 18 with respect to the design, operation, and testing of safety-related electric power systems in all types of nuclear power  
  reliability. General Design Criterion 18, "Inspection and Testing of Electric Power Systems," of Appendix                                           1. IEEE Standard 308-1974, Section 5.2.3(4), first A to 10 CFR Part 50, contains requirements concern                                       paragraph, requires that offsite power be available ing periodic inspection, testing, and testability of                                     within an acceptable time following a loss-of-coolant electric power systems important to safety. This guide                                   accident. In contrast, Criterion 17 requires that off describes a method acceptable to the NRC staff of                                       site power be available within a few seconds follow complying with Criteria 17 and 18 with respect to the                                   ing a loss-of-coolant accident. Thus a potential for design, operation, and testing of safety-related                                         misunderstanding exists with regard to the maximum electric power systems in all types of nuclear power                                     permissible time for access to the offsite network in
*  
* plants. The Advisory Committee on Reactor                                               the event of a loss-of-coolant accident, and further Safeguards has been consulted concerning this guide                                     guidance is needed.
plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.


and has concurred in the regulatory position.
==B. DISCUSSION==
IEEE Std 308-1974' is a revision of IEEE Std 308
1971 and was prepared by Working Group 4.1 of the Nuclear Power Engineering Committee (NPEC) of the Institute of Electrical and Electronics Engineers (IEEE). IEEE Std 308-1974 was approved by NPEC
at its meeting on May 17-18, 1973, and subsequently by the IEEE Standards Board on December 13, 1973.
 
* Lines indicate substantive changes from previous issue.
 
IEEE Std 308-1974, "IEEE Standard Criteria for Class IE Power Systems for Nuclear Power Generating Stations," may be obtained from the Institute of Electrical and Electronics Engineers, United Engineering Center, 345 East 47th Street, New York, New York
10017.
 
This revision to IEEE Std 308-1971 has made the standard consistent with the requirement in Criterion
17 for two circuits to the offsite network, each designed to be available in sufficient time following a loss of onsite alternating current power supplies and the other offsite electric power circuit. However, two potential conflicts with Criterion 17 remain un resolved: one in the area of availability of offsite power (Item 1) and the other in battery charger supp ly requirements (Item 2). In addition, an incon sistency exists between IEEE Std 308-1974 and IEEE
Std 450-1975 (Item 3). 
1. IEEE Standard 308-1974, Section 5.2.3(4), first paragraph, requires that offsite power be available within an acceptable time following a loss-of-coolant accident. In contrast, Criterion 17 requires that off site power be available within a few seconds follow ing a loss-of-coolant accident. Thus a potential for misunderstanding exists with regard to the maximum permissible time for access to the offsite network in the event of a loss-of-coolant accident, and further guidance is needed.
 
2. Section 5.3.4 of IEEE Std 308-1974 requires, in part, that each battery charger supply (a) furnish electric energy for the steady-state operation of con nected loads required during normal and postacci dent operation while its battery is returned to or maintained in a fully charged state and (b) have suf ficient capacity to restore the battery from the design minimum charge to its fully charged state while sup plying normal and postaccident steady-state loads. In contrast, the equivalent position of Criterion 17 re quires that -the onsite electric power supplies, in cluding the batteries and the onsite electric distribu tion system, have sufficient independence, redun dancy, capacity, and testability to perform their safety functions assuming a single failur
 
====e. Criterion ====
17, therefore, does not restrict the battery charger USNRC REGULATORY GUIDES
Comments should be sent to the Secretary of the Commission, US. Nuclear Regu latory Commission, Washington, D.C. 20555. Attention: Docketing and Service Regulatory Guides are issued to describe and make available to the public methods Branch.
 
acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions:
or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required.
 
===1. Power Reactors ===
6. Products Methods and solutions different from those set out in the guides will be accept-
2. Research and Test Reactors
 
===7. Transportation ===
3. Fuels and Materials Facilities
8. Occupational Health able if they provide a basis for the findings requisite to the issuance or continuance
4. Environmental andSiting
9. Antitrust Review of a permit or license by the Commission.
 
5. Materials and Plant Protection
10. General Comments and suggestions for improvements in these guides are encouraged at all Requests for single copies of issued guides (which may be reproduced) or for place times, and guides will be revised, as appropriate, to accommodate comments and ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience.
 
This guide was revised as a result of divisions should be made in writing to the US. Nuclear Regulatory Commission, substantive comments received from the public and additional staff review.


2. Section 5.3.4 of IEEE Std 308-1974 requires, in
Washington, D.C.


==B. DISCUSSION==
20555, Attention:
part, that each battery charger supply (a) furnish electric energy for the steady-state operation of con IEEE Std 308-1974' is a revision of IEEE Std 308                                  nected loads required during normal and postacci
Director, Division of Document Control.
  1971 and was prepared by Working Group 4.1 of the                                      dent operation while its battery is returned to or Nuclear Power Engineering Committee (NPEC) of                                            maintained in a fully charged state and (b) have suf the Institute of Electrical and Electronics Engineers                                    ficient capacity to restore the battery from the design (IEEE). IEEE Std 308-1974 was approved by NPEC                                          minimum charge to its fully charged state while sup at its meeting on May 17-18, 1973, and subsequently                                      plying normal and postaccident steady-state loads. In by the IEEE Standards Board on December 13, 1973.                                       contrast, the equivalent position of Criterion 17 re quires that -the onsite electric power supplies, in


* Lines indicate substantive changes from previous issue.                              cluding the batteries and the onsite electric distribu IEEE Std 308-1974, "IEEE Standard Criteria for Class IE Power                        tion system, have sufficient independence, redun Systems for Nuclear Power Generating Stations," may be obtained                          dancy, capacity, and testability to perform their from the Institute of Electrical and Electronics Engineers, United Engineering Center, 345 East 47th Street, New York, New York safety functions assuming a single failur
supply loads to normal and postaccident steady-state loads. A conflict may therefore exist for those plants in which other loads (e.g., loads required during hot or cold shutdown, large startup loads during an acci dent, or other design basis events) are greater than the normal and postaccident steady-state loads.


====e. Criterion====
3. Table 2, "Illustrative Periodic Tests," of IEEE
  10017.                                                                                  17, therefore, does not restrict the battery charger USNRC REGULATORY GUIDES                                          Comments should be sent to the Secretary of the Commission, US. Nuclear Regu latory Commission, Washington, D.C. 20555. Attention: Docketing and Service Regulatory Guides are issued to describe and make available to the public methods      Branch.
Std 308-1974 lists a test interval of 3 years for the bat tery performance discharge test and refers to IEEE
Std 450-1972,
"Recommended Practice for Maintenance, Testing, and Replacement of Large Stationary Type Power Plant and Substation Lead Storage Batteries," for details regarding performance of such tests. Subsequent to the publication of IEEE
Std 308-1974, IEEE Std 450-1972 was revised and published as IEEE Std 450-1975, "IEEE Recom mended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations." IEEE Std 450
1975 specifies a battery performance discharge test within the first two years of service and thereafter at intervals of 5 years until the battery shows signs of degradation or until 85% of expected service life is reached, at which time annual tests are require


acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions:
====d. The ====
    or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required.          1. Power Reactors                            6. Products Methods and solutions different from those set out in the guides will be accept-        2. Research and Test Reactors               
3-year interval specified in IEEE Std 308-1974 con flicts with these requirements. IEEE Std 450-1975 also describes a battery service test, but no test fre quency is specified. IEEE Std 308-1974 does not specifically mention the battery service test.


===7. Transportation===
It should be noted that the scope of IEEE Std 308
                                                                                            3.  Fuels and Materials Facilities            8. Occupational Health able if they provide a basis for the findings requisite to the issuance or continuance  4.  Environmental andSiting                  9. Antitrust Review of a permit or license by the Commission.                                              5.  Materials and Plant Protection          10. General Comments and suggestions for improvements in these guides are encouraged at all          Requests for single copies of issued guides (which may be reproduced) or for place times, and guides will be revised, as appropriate, to accommodate comments and          ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience. This guide was revised as a result of         divisions should be made in writing to the US. Nuclear Regulatory Commission, substantive comments received from the public and additional staff review.              Washington, D.C. 20555, Attention: Director, Division of Document Control.
1974 is more limited than that of Criteria 17 and 18.


supply loads to normal and postaccident steady-state            nuclear power plants have been the subject of such loads. A conflict may therefore exist for those plants          regulatory guides as Regulatory Guide 1.9 (Safety in which other loads (e.g., loads required during hot          Guide 9), "Selection of Diesel Generator Set or cold shutdown, large startup loads during an acci            Capacity for Standby Power Supplies," and dent, or other design basis events) are greater than            Regulatory Guide 1.93, "Availability of Electric the normal and postaccident steady-state loads.                Power Sources."
For example, the scope of IEEE Std 308-1974 ex cludes the unit generator(s) and their buses; step-up, auxiliary, and startup transfomers; connections to the station switchyard; switchyard; transmission lines;
  3. Table 2, "Illustrative Periodic Tests," of IEEE              The criteria and requirements in IEEE Std 308 Std 308-1974 lists a test interval of 3 years for the bat        1974 are indicated by the verbs "shall" and "must,"
and the transmission network. Except for the unit generator(s), these are all included within the scope of Criteria 17 and 18.
tery performance discharge test and refers to IEEE              and recommendations are indicated by the verb Std 450-1972, "Recommended                Practice for         "should." The terms "may," "suggested," and "il Maintenance, Testing, and Replacement of Large                  lustrative" indicate optional practices.


Stationary Type Power Plant and Substation Lead Storage Batteries," for details regarding performance                     
In the forward to IEEE Std 308-1974 it is noted that certain areas of this standard need more exten sive treatment. These include shared systems in multi unit stations, independence between redundant standby sources, connection of non-Class 1E equip ment to Class I E systems, and the definition of design basis events. Some of these topics have been the sub ject of other regulatory guides, e.g., Regulatory Guide 1.6 (Safety Guide 6), "Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems," which is con cerned with electrical independence;
Regulatory Guide
1:75,
"Physical Independence of Electric Systems,"  
which is concerned with physical in dependence of Class lE systems and the connection of non-Class IE equipment to Class 1E systems; and Regulatory Guide 1.81, "Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants." Other matters of importance to the regulatory process for electric power systems in nuclear power plants have been the subject of such regulatory guides as Regulatory Guide 1.9 (Safety Guide 9), "Selection of Diesel Generator Set Capacity for Standby Power Supplies,"
and Regulatory Guide 1.93, "Availability of Electric Power Sources."
The criteria and requirements in IEEE Std 308
1974 are indicated by the verbs "shall" and "must,"
and recommendations are indicated by the verb
"should." The terms "may," "suggested," and "il lustrative" indicate optional practices.


==C. REGULATORY POSITION==
==C. REGULATORY POSITION==
of such tests. Subsequent to the publication of IEEE
1. For the portion of safety-related electric power systems within its scope, the criteria, requirements, and recommendations in IEEE Std 308-1974 are generally acceptable to the NRC staff and provide an adequate basis for complying with the Commission's General Design Criteria 17 and 18 of Appendix A to  
Std 308-1974, IEEE Std 450-1972 was revised and                    1. For the portion of safety-related electric power published as IEEE Std 450-1975, "IEEE Recom                    systems within its scope, the criteria, requirements, mended Practice for Maintenance, Testing, and                  and recommendations in IEEE Std 308-1974 are Replacement of Large Lead Storage Batteries for                generally acceptable to the NRC staff and provide an Generating Stations and Substations." IEEE Std 450              adequate basis for complying with the Commission's
10 CFR Part 50 with respect to the design, operation, and testing of electric power systems, subject to the following:  
1975 specifies a battery performance discharge test            General Design Criteria 17 and 18 of Appendix A to within the first two years of service and thereafter at          10 CFR Part 50 with respect to the design, operation, intervals of 5 years until the battery shows signs of          and testing of electric power systems, subject to the degradation or until 85% of expected service life is            following:
a. Availability of Offsite Power. Consistent with the requirements of Criterion 17, the phrase "within an acceptable time" in Section 5.2.3(4), first paragraph, of IEEE Std 308-1974 should be con strued to mean "within a few seconds". A preferred design would include two immediate access circuits from the transmission network. Detailed guidance for operating procedures and restrictions acceptable to the staff, applicable where two immediate access circuits are available, is contained in Regulatory Guide 1.93, "Availability of Electric Power Sources."
reached, at which time annual tests are required. The
An acceptable design would substitute a delayed ac cess circuit for one of the immediate access circuits provided the availability of the delayed access circuit conforms to Criterion 17.
3-year interval specified in IEEE Std 308-1974 con                    a. Availability of Offsite Power. Consistent with flicts with these requirements. IEEE Std 450-1975              the requirements of Criterion 17, the phrase "within also describes a battery service test, but no test fre          an acceptable time" in Section 5.2.3(4), first quency is specified. IEEE Std 308-1974 does not                paragraph, of IEEE Std 308-1974 should be con specifically mention the battery service test.                  strued to mean "within a few seconds". A preferred design would include two immediate access circuits It should be noted that the scope of IEEE Std 308           from the transmission networ
 
b. Battery Charger Supply. The provisions of Section 5.3.4 of IEEE Std 308-1974 should be con strued to mean that the capacity of the battery charger supply should be based on the largest com bined demands of the various steady-state loads and the charging capacity to restore the battery from the design minimum charge state to the fully charged state, irrespective of the status of the plant during which these demands occur.
 
c. Battery Performance Discharge Tests. The test interval for the battery performance discharge test should be as specified in IEEE Std 450-1975 instead of the 3 years specified in Table 2, "Illustrative Periodic Tests," of IEEE Std 308-1974. The battery service test described in IEEE Std 450-1975 should be performed in addition to the battery performance dis charge test. The battery service test should be per formed during refueling operations or at some other outage, with intervals between tests not to exceed 18
1.32-2
 
months. The note following Table 2 of IEEE Std 308
1974 should reference IEEE Std 450-1975 rather than IEEE Std 450-1972.
 
d. Independence of Redundant Standby Sources.


====k. Detailed guidance====
Electrical independence between redundant standby
1974 is more limited than that of Criteria 17 and 18.          for operating procedures and restrictions acceptable For example, the scope of IEEE Std 308-1974 ex                  to the staff, applicable where two immediate access cludes the unit generator(s) and their buses; step-up,          circuits are available, is contained in Regulatory auxiliary, and startup transfomers; connections to the          Guide 1.93, "Availability of Electric Power Sources."
-
station switchyard; switchyard; transmission lines;            An acceptable design would substitute a delayed ac and the transmission network. Except for the unit              cess circuit for one of the immediate access circuits generator(s), these are all included within the scope of        provided the availability of the delayed access circuit Criteria 17 and 18.                                             conforms to Criterion 17.
(onsite) power sources should be in accordance with Regulatory Guide 1.6. Physical independence should be in accordance with Regulatory Guide 1.75.


In the forward to IEEE Std 308-1974 it is noted                  b. Battery Charger Supply. The provisions of that certain areas of this standard need more exten            Section 5.3.4 of IEEE Std 308-1974 should be con sive treatment. These include shared systems in multi          strued to mean that the capacity of the battery unit stations, independence between redundant                  charger supply should be based on the largest com standby sources, connection of non-Class 1E equip              bined demands of the various steady-state loads and ment to Class IE systems, and the definition of design          the charging capacity to restore the battery from the basis events. Some of these topics have been the sub          design minimum charge state to the fully charged ject of other regulatory guides, e.g., Regulatory               state, irrespective of the status of the plant during Guide 1.6 (Safety Guide 6), "Independence Between              which these demands occur.
e. Connection of Non-Class IE Equipment to Class 1E Systems. The guidance presented in Regulatory Guide 1.75 should be followed.


Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems," which is con                    c. Battery Performance Discharge Tests. The test cerned with electrical independence; Regulatory                interval for the battery performance discharge test Guide 1:75, "Physical Independence of Electric                  should be as specified in IEEE Std 450-1975 instead Systems," which is concerned with physical in                  of the 3 years specified in Table 2, "Illustrative dependence of Class lE systems and the connection                Periodic Tests," of IEEE Std 308-1974. The battery of non-Class IE equipment to Class 1E systems; and              service test described in IEEE Std 450-1975 should be Regulatory Guide 1.81, "Shared Emergency and                  performed in addition to the battery performance dis Shutdown Electric Systems for Multi-Unit Nuclear                charge test. The battery service test should be per Power Plants." Other matters of importance to the                formed during refueling operations or at some other regulatory process for electric power systems in                outage, with intervals between tests not to exceed 18
f. Selection of Diesel Generator Set Capacity for Standby Power Supplies. The guidance presented in Regulatory Guide 1.9 should be followed.
                                                          1.32-2


months. The note following Table 2 of IEEE Std 308               b. Availability of Electric Power Source
2. The following optional practices are considered to be unacceptable as given below:
a. Shared Electric Systems for Multi-Unit Nuclear Power Plants. The provisions of Section 8.2 of IEEE Std 308-1974, which permit sharing of stand by power supplies among units of a multi-unit sta tion, are unacceptable except as specified in Regulatory Guide 1.81. The provisions of Section
8.3.1 of IEEE Std 308-1974 that permit sharing of battery supplies among units at a multi-unit plant are considered unacceptable and should be supplanted by the recommendations of Regulatory Guide 1.81.


====s. Table====
b. Availability of Electric Power Source
  1974 should reference IEEE Std 450-1975 rather than        3, "Suggested Operating Alternatives with Degraded IEEE Std 450-1972.                                          Class IE Power System Conditions," of IEEE Std
                                                              308-1974 is considered unacceptable and should be d. Independence of Redundant Standby Sources.          supplanted by the recommendations of Regulatory Electrical independence between redundant standby          Guide 1.93.


- (onsite) power sources should be in accordance with Regulatory Guide 1.6. Physical independence should                       
====s. Table ====
3, "Suggested Operating Alternatives with Degraded Class IE Power System Conditions," of IEEE Std
308-1974 is considered unacceptable and should be supplanted by the recommendations of Regulatory Guide 1.93.


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
be in accordance with Regulatory Guide 1.75.
The purpose of this section is to provide informa tion to applicants regarding the NRC staff's plans for using this regulatory guide.


The purpose of this section is to provide informa tion to applicants regarding the NRC staff's plans for e. Connection of Non-Class IE Equipment to            using this regulatory guide.
Except in those cases in which the applicant proposes an acceptable alternative method for com plying with specified portions of the Commission'*s regulations, (1) the methods described in portions of this guide that reference other regulatory guides are being and will continue to be used in the evaluation of submittals for construction permit applications and (2) the methods described in other portions of this guide will be used in the evaluation of submittals for construction permit applications docketed after April 15, 1977, unless this guide is revised as a result of suggestions from the public or additional staff review.


Class 1E Systems. The guidance presented in Regulatory Guide 1.75 should be followed.                    Except in those cases in which the applicant proposes an acceptable alternative method for com f. Selection of Diesel Generator Set Capacity for      plying with specified portions of the Commission'*s Standby Power Supplies. The guidance presented in          regulations, (1) the methods described in portions of Regulatory Guide 1.9 should be followed.                  this guide that reference other regulatory guides are being and will continue to be used in the evaluation
If an applicant wishes to use this regulatory guide in developing submittals for applications docketed on or before April 15, 1977, the pertinent portions of the application will be evaluated on the basis of this guide.
    2. The following optional practices are considered      of submittals for construction permit applications to be unacceptable as given below:                          and (2) the methods described in other portions of this guide will be used in the evaluation of submittals a. Shared Electric Systems for Multi-Unit              for construction permit applications docketed after Nuclear Power Plants. The provisions of Section 8.2        April 15, 1977, unless this guide is revised as a result of IEEE Std 308-1974, which permit sharing of stand        of suggestions from the public or additional staff by power supplies among units of a multi-unit sta          review.


tion, are unacceptable except as specified in Regulatory Guide 1.81. The provisions of Section              If an applicant wishes to use this regulatory guide
1.32-3
  8.3.1 of IEEE Std 308-1974 that permit sharing of          in developing submittals for applications docketed on battery supplies among units at a multi-unit plant are      or before April 15, 1977, the pertinent portions of the considered unacceptable and should be supplanted            application will be evaluated on the basis of this by the recommendations of Regulatory Guide 1.81.            guide.                                                  0
0
                                                        1.32-3


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Latest revision as of 02:08, 17 January 2025

Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants
ML003739990
Person / Time
Issue date: 02/28/1977
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.032, Rev 2
Download: ML003739990 (4)


Revision 2 February 1977 U.S. NUCLEAR REGULATORY COMMISSION

REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.32 CRITERIA FOR SAFETY-RELATED ELECTRIC POWER SYSTEMS

FOR 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,

"Licensing of Production and Utilization Facilities,"

requires that an onsite electric power system and an offsite electric power system be provided to permit functioning of structures, systems, and components important to safety. In addition, Criterion 17 con tains requirements concerning system capacity, in dependence, redundancy, availability, testability, and reliability. General Design Criterion 18, "Inspection and Testing of Electric Power Systems," of Appendix A to 10 CFR Part 50, contains requirements concern ing periodic inspection, testing, and testability of electric power systems important to safety. This guide describes a method acceptable to the NRC staff of complying with Criteria 17 and 18 with respect to the design, operation, and testing of safety-related electric power systems in all types of nuclear power

plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.

B. DISCUSSION

IEEE Std 308-1974' is a revision of IEEE Std 308

1971 and was prepared by Working Group 4.1 of the Nuclear Power Engineering Committee (NPEC) of the Institute of Electrical and Electronics Engineers (IEEE). IEEE Std 308-1974 was approved by NPEC

at its meeting on May 17-18, 1973, and subsequently by the IEEE Standards Board on December 13, 1973.

  • Lines indicate substantive changes from previous issue.

IEEE Std 308-1974, "IEEE Standard Criteria for Class IE Power Systems for Nuclear Power Generating Stations," may be obtained from the Institute of Electrical and Electronics Engineers, United Engineering Center, 345 East 47th Street, New York, New York

10017.

This revision to IEEE Std 308-1971 has made the standard consistent with the requirement in Criterion

17 for two circuits to the offsite network, each designed to be available in sufficient time following a loss of onsite alternating current power supplies and the other offsite electric power circuit. However, two potential conflicts with Criterion 17 remain un resolved: one in the area of availability of offsite power (Item 1) and the other in battery charger supp ly requirements (Item 2). In addition, an incon sistency exists between IEEE Std 308-1974 and IEEE Std 450-1975 (Item 3).

1. IEEE Standard 308-1974, Section 5.2.3(4), first paragraph, requires that offsite power be available within an acceptable time following a loss-of-coolant accident. In contrast, Criterion 17 requires that off site power be available within a few seconds follow ing a loss-of-coolant accident. Thus a potential for misunderstanding exists with regard to the maximum permissible time for access to the offsite network in the event of a loss-of-coolant accident, and further guidance is needed.

2. Section 5.3.4 of IEEE Std 308-1974 requires, in part, that each battery charger supply (a) furnish electric energy for the steady-state operation of con nected loads required during normal and postacci dent operation while its battery is returned to or maintained in a fully charged state and (b) have suf ficient capacity to restore the battery from the design minimum charge to its fully charged state while sup plying normal and postaccident steady-state loads. In contrast, the equivalent position of Criterion 17 re quires that -the onsite electric power supplies, in cluding the batteries and the onsite electric distribu tion system, have sufficient independence, redun dancy, capacity, and testability to perform their safety functions assuming a single failur

e. Criterion

17, therefore, does not restrict the battery charger USNRC REGULATORY GUIDES

Comments should be sent to the Secretary of the Commission, US. Nuclear Regu latory Commission, Washington, D.C. 20555. Attention: Docketing and Service Regulatory Guides are issued to describe and make available to the public methods Branch.

acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions:

or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required.

1. Power Reactors

6. Products Methods and solutions different from those set out in the guides will be accept-

2. Research and Test Reactors

7. Transportation

3. Fuels and Materials Facilities

8. Occupational Health able if they provide a basis for the findings requisite to the issuance or continuance

4. Environmental andSiting

9. Antitrust Review of a permit or license by the Commission.

5. Materials and Plant Protection

10. General Comments and suggestions for improvements in these guides are encouraged at all Requests for single copies of issued guides (which may be reproduced) or for place times, and guides will be revised, as appropriate, to accommodate comments and ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience.

This guide was revised as a result of divisions should be made in writing to the US. Nuclear Regulatory Commission, substantive comments received from the public and additional staff review.

Washington, D.C.

20555, Attention:

Director, Division of Document Control.

supply loads to normal and postaccident steady-state loads. A conflict may therefore exist for those plants in which other loads (e.g., loads required during hot or cold shutdown, large startup loads during an acci dent, or other design basis events) are greater than the normal and postaccident steady-state loads.

3. Table 2, "Illustrative Periodic Tests," of IEEE Std 308-1974 lists a test interval of 3 years for the bat tery performance discharge test and refers to IEEE Std 450-1972,

"Recommended Practice for Maintenance, Testing, and Replacement of Large Stationary Type Power Plant and Substation Lead Storage Batteries," for details regarding performance of such tests. Subsequent to the publication of IEEE Std 308-1974, IEEE Std 450-1972 was revised and published as IEEE Std 450-1975, "IEEE Recom mended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations." IEEE Std 450

1975 specifies a battery performance discharge test within the first two years of service and thereafter at intervals of 5 years until the battery shows signs of degradation or until 85% of expected service life is reached, at which time annual tests are require

d. The

3-year interval specified in IEEE Std 308-1974 con flicts with these requirements. IEEE Std 450-1975 also describes a battery service test, but no test fre quency is specified. IEEE Std 308-1974 does not specifically mention the battery service test.

It should be noted that the scope of IEEE Std 308

1974 is more limited than that of Criteria 17 and 18.

For example, the scope of IEEE Std 308-1974 ex cludes the unit generator(s) and their buses; step-up, auxiliary, and startup transfomers; connections to the station switchyard; switchyard; transmission lines;

and the transmission network. Except for the unit generator(s), these are all included within the scope of Criteria 17 and 18.

In the forward to IEEE Std 308-1974 it is noted that certain areas of this standard need more exten sive treatment. These include shared systems in multi unit stations, independence between redundant standby sources, connection of non-Class 1E equip ment to Class I E systems, and the definition of design basis events. Some of these topics have been the sub ject of other regulatory guides, e.g., Regulatory Guide 1.6 (Safety Guide 6), "Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems," which is con cerned with electrical independence;

Regulatory Guide

1:75,

"Physical Independence of Electric Systems,"

which is concerned with physical in dependence of Class lE systems and the connection of non-Class IE equipment to Class 1E systems; and Regulatory Guide 1.81, "Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants." Other matters of importance to the regulatory process for electric power systems in nuclear power plants have been the subject of such regulatory guides as Regulatory Guide 1.9 (Safety Guide 9), "Selection of Diesel Generator Set Capacity for Standby Power Supplies,"

and Regulatory Guide 1.93, "Availability of Electric Power Sources."

The criteria and requirements in IEEE Std 308

1974 are indicated by the verbs "shall" and "must,"

and recommendations are indicated by the verb

"should." The terms "may," "suggested," and "il lustrative" indicate optional practices.

C. REGULATORY POSITION

1. For the portion of safety-related electric power systems within its scope, the criteria, requirements, and recommendations in IEEE Std 308-1974 are generally acceptable to the NRC staff and provide an adequate basis for complying with the Commission's General Design Criteria 17 and 18 of Appendix A to

10 CFR Part 50 with respect to the design, operation, and testing of electric power systems, subject to the following:

a. Availability of Offsite Power. Consistent with the requirements of Criterion 17, the phrase "within an acceptable time" in Section 5.2.3(4), first paragraph, of IEEE Std 308-1974 should be con strued to mean "within a few seconds". A preferred design would include two immediate access circuits from the transmission network. Detailed guidance for operating procedures and restrictions acceptable to the staff, applicable where two immediate access circuits are available, is contained in Regulatory Guide 1.93, "Availability of Electric Power Sources."

An acceptable design would substitute a delayed ac cess circuit for one of the immediate access circuits provided the availability of the delayed access circuit conforms to Criterion 17.

b. Battery Charger Supply. The provisions of Section 5.3.4 of IEEE Std 308-1974 should be con strued to mean that the capacity of the battery charger supply should be based on the largest com bined demands of the various steady-state loads and the charging capacity to restore the battery from the design minimum charge state to the fully charged state, irrespective of the status of the plant during which these demands occur.

c. Battery Performance Discharge Tests. The test interval for the battery performance discharge test should be as specified in IEEE Std 450-1975 instead of the 3 years specified in Table 2, "Illustrative Periodic Tests," of IEEE Std 308-1974. The battery service test described in IEEE Std 450-1975 should be performed in addition to the battery performance dis charge test. The battery service test should be per formed during refueling operations or at some other outage, with intervals between tests not to exceed 18

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months. The note following Table 2 of IEEE Std 308

1974 should reference IEEE Std 450-1975 rather than IEEE Std 450-1972.

d. Independence of Redundant Standby Sources.

Electrical independence between redundant standby

-

(onsite) power sources should be in accordance with Regulatory Guide 1.6. Physical independence should be in accordance with Regulatory Guide 1.75.

e. Connection of Non-Class IE Equipment to Class 1E Systems. The guidance presented in Regulatory Guide 1.75 should be followed.

f. Selection of Diesel Generator Set Capacity for Standby Power Supplies. The guidance presented in Regulatory Guide 1.9 should be followed.

2. The following optional practices are considered to be unacceptable as given below:

a. Shared Electric Systems for Multi-Unit Nuclear Power Plants. The provisions of Section 8.2 of IEEE Std 308-1974, which permit sharing of stand by power supplies among units of a multi-unit sta tion, are unacceptable except as specified in Regulatory Guide 1.81. The provisions of Section

8.3.1 of IEEE Std 308-1974 that permit sharing of battery supplies among units at a multi-unit plant are considered unacceptable and should be supplanted by the recommendations of Regulatory Guide 1.81.

b. Availability of Electric Power Source

s. Table

3, "Suggested Operating Alternatives with Degraded Class IE Power System Conditions," of IEEE Std 308-1974 is considered unacceptable and should be supplanted by the recommendations of Regulatory Guide 1.93.

D. IMPLEMENTATION

The purpose of this section is to provide informa tion to applicants regarding the NRC staff's plans for using this regulatory guide.

Except in those cases in which the applicant proposes an acceptable alternative method for com plying with specified portions of the Commission'*s regulations, (1) the methods described in portions of this guide that reference other regulatory guides are being and will continue to be used in the evaluation of submittals for construction permit applications and (2) the methods described in other portions of this guide will be used in the evaluation of submittals for construction permit applications docketed after April 15, 1977, unless this guide is revised as a result of suggestions from the public or additional staff review.

If an applicant wishes to use this regulatory guide in developing submittals for applications docketed on or before April 15, 1977, the pertinent portions of the application will be evaluated on the basis of this guide.

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