Regulatory Guide 1.32: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 1: Line 1:
{{Adams
{{Adams
| number = ML13350A366
| number = ML003739990
| issue date = 03/31/1976
| issue date = 02/28/1977
| title = Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants
| title = Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.032, Rev. 1
| document report number = RG-1.032, Rev 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 3
| page count = 4
}}
}}
{{#Wiki_filter:Revision I
{{#Wiki_filter:Revision 2 February 1977 U.S. NUCLEAR REGULATORY COMMISSION
U.S. NUCLEAR REGULATORY COMMISSION                                                                                                                                     March 1976 REGULATORY GUIDE
REGULATORY GUIDE  
OFFICE OF STANDARDS DEVELOPMENT
OFFICE OF STANDARDS DEVELOPMENT  
                                                                              REGULATORY GUIDE 1.32 CRITERIA FOR SAFETY-RELATED ELECTRIC POWER SYSTEMS
REGULATORY GUIDE 1.32 CRITERIA FOR SAFETY-RELATED ELECTRIC POWER SYSTEMS  
                                                                  FOR NUCLEAR POWER PLANTS
FOR NUCLEAR POWER PLANTS


==A. INTRODUCTION==
==A. INTRODUCTION==
This revision to IEEE Std i08-_ ,)71 has made the standard consistent with the require ment ij- Criterion 17 General Design Criterion 17, "Electric Power Sys-                                              for two circuits to the uffsite network, each designed to tems," of Appendix A, "General Design Criteria for                                                   be available in sufficient time following a loss of onsite Nuclear Power Plants," to 10 CFR Part 50. "Licensing                                                 alternating current power supplies and the other ofl'sltt, of Production and Utilization Facilities," requires that                                             electric power circuit. However. two potential conflicts an onsite electric power system and an offsite electric                                             with Criterion 17 remain unresolved: one in the area of power system be provided to permit functioning of                                                   availability of offsitc power (Item I) and the other in structures, systems, and components important to                                                     battery charger supply requirements (Item 2). In addi- safety. In addition, Criterion 17 contains requirements                                             tion. an inconsistency. exists between IEEI Std concerning system capacity, capability, independence,                                               308-1974 and IIEEE.SId 450-1975 (Itiem 3).
General Design Criterion 17, "Electric Power Systems," of Appendix A, "General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50,
redundancy, availability, testability, and reliability. Gen- eral Design Criterion 18, "Inspection and Testing of                                                       1. IEEE Standard 308-1974. Section 5.2.3(4). first Electric Power Systems," of Appendix A to 10 CFR Part                                               paragraph. requires that off'site power be available within
"Licensing of Production and Utilization Facilities,"  
50, contains requirements concerning periodic in-                                                    an acceptable tine following a loss-of-coclarrt accident.
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.


spection, testing, and testability of electric power                                                 .ii, contrast, Criterion 17 requires that offsite power be systems important to safety. This guide describes a                                                  available within a few seconds following a loss-of-coolant method acccptable to the NRC staff of complying with..                                                        lccident.;
==B. DISCUSSION==
                                                                                                                      Thus a potential for misunderstanding exists Criteria 17 and 18 with respect to the design, operation'.                                            wi.vith regard to t[le maximum permissible time for access and testing of safety-related electric power systems' In all                                      ,tro the offsite network in the event of a loss-of-coolant types of nuclear power plants.                                                                      accident, and further guidance is needed.
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.


==B. DISCUSSION==
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:
2. Section 5.3.4 of IEEE Std 308-1974 requires. in part. that each battery charger supply (a) furnish electric IEEE Sid 3 08-1 9 7 4 ' is a revision of IEEE Std energy for 'he steady-state operation of connected loads
or postulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required.
308-1971 and was prepared byWorking Group 4.1 of the required duial          normal and postaccident oplration while Nuclear Power Engineermig Cobilnittee (NPEC) of the its battery is to turned to or maintained in a full!y charged Institute of Electrical and .Ele6tr6udlcs Engineers (IEEE).
 
                                                                                                      state and (b) have sufficient capacity to restore the IEEE Std 308-1974--was .approv'ed by NPEC at its meeting on MayfA.18.7':J973 itnd subsequently by the                                                  batter)y from the design mninimum charge to its f'ully IEEE Standards Bard on December 13, 1973.                                                           charged state while supplying normal and postaccident steady-state loads. In contrast, the equivalent position of Criterion 17 requires that the onsite electric power
===1. Power Reactors ===
  'IEEE Std"3(8-"974, "-lrF Standard Criteria for Class I-                                            supplies, including the batteries and the onsite electric Power Sysiemti'for Nuclear Power Generating Stations," may be obtained from '*itb Institute of Electrical and Electronics                                          distribution system. have sufficient independence, re- Engineers. United Eingineering Center. 345 East 47th Street.                                        dundancy. capacity. and testability to perform their New York, New York 10017.                                                                            safety functions assuming a single failure. Criterion 17.
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.


USNRC REGULATORY GUIDES                                                        Comments should be sent to the Sectetaty of the Comrnison U S Nuclea, Regulatory Ctoniison        Washiglon    DC  2M56  Attention Oocketing &tid Rfqulatoty Guides ,..e...ued to describe and niafke dvuilable to th, pulibtc nt-thods acceptlble to ftle NRC Stall of implemtenting                iSpecific prl,.    tit tieo Conim-issin s teguldtions. to detineale lechniques used by the staff in avalo                          Ihe guides ate issued in the following ten broad divisions hlunq specitic ptiiblents or poItulated accident,. orto provide guidance lu apph cants Reguldtoiv Guides at. not substitutes tot regulations. and comph.ance                            I Power React.is                      6P'odutcts with them is nut tequtoedl MeIthods and solutions different fion, those %elout                        22t%Research aid Test Reactots          7 Ttansporalaton the guides will be accept.iblr it they provide a basis tot the fitdings requisite to                     J Fuels and Matetiats facilities      8 Occupational Heallh the isslance tit ciinlinuttsce il d p-totit os license by the Comntmission                                m*nvtonmental and Siting            9 Antitrust Review Comntits asd                ll s i    -iilqestii          ntitttieh e guides aie encouraged l III
3. Table 2, "Illustrative Periodic Tests," of IEEE
                                                            oinigtist                                    5 MuterldJs and Plant Protection    t0 Generta at alt ltii.    inld qiljes will li      i-d.
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


tev      is iltptopriale to 4tccuntndalole con.
====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.


noe,,fs a,, sitIle.*ter    new tttliltli ittnot      esgtellrent rit                However. cotmme*ts Ill          Copies ot published guides may be obtained by written tequest indicating the thi. ,utitfe. if rii,  f** wiitthi .httiiI
It should be noted that the scope of IEEE Std 308
                                        utw      toilithtl      otter its issuartce. w*ll he pat        divisions desired to the U S Nucleat Regulatory Commission, Washingtoin 0 C
1974 is more limited than that of Criteria 17 and 18.
ticulltai useful ...etlittiiqltil the iln-d fill .ill eily oI vitool l                                  20556, Attention Ditector. OfiIce of Standards Development


therefore, does not restrict the battery charger supply          process for electric power systems in nuclear power loads to normal and postaccident steady.state loads. A          plants have been the subject of such regulatory guides as conflict may therefore exist for those plants in which          Regulatory Guide 1.9 (Safety Guide 9), "Selection of other loads (e.g., loads required during hot or cold            Diesel Generator Set Capacity for Standby Power shutdown, large startup loads during an accident, or            Supplies," and Regulatory Guide 1.93, "Availability of other design basis events) are greater than the normal          Electric 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;
and postaccident steady-state loads.                                The criteria and requirements in IEEE Std 308-1974 are indicated by the verbs "shall" and "must", and
and the transmission network. Except for the unit generator(s), these are all included within the scope of Criteria 17 and 18.
    3. Table 2, "illustrative Periodic Tests," of IEEE Std        recommendations are indicated by the verb "fhould".
308-1974 lists a test interval of 3 years for the battery The terms "may", "suggested", and "illustrative" indi- performance discharge test and refers to IEEE Std
450-1972, "Recommended Practice for Maintenance,                cate optional practices.


Testing, and Replacement of Urge Stationary Type Power Plant and Substation Lead Storage Batteries," for                        
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==
details regarding performance of such tests. Subsequent to the publication of IEEE Std 308-1974, IEEE Std                    1. For the portion of safety-related electric power
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  
450-1972 was revised and published as IEEE Std                  system within its scope, the criteria, requirements, and
10 CFR Part 50 with respect to the design, operation, and testing of electric power systems, subject to the following:  
450.1975, "IEEE Recommended Practice for Mainten-                recommendations in IEEE Std 308-1974 are generally ance, Testing, and Replacement of Large Lead Storage acceptable to the NRC staff and provide an adequate Batteries for Generating Stations and Substations."              basis for complying with the Commission's General IEEE Std 450.1975 specifies a battery performance                Design Criteria 17 and 18 of Appendix A to 10 CFR
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."
discharge test within the first two years of service and        Part 50 %k  ith respect to the design, operation, and testing thereafter at intervals of 5 years until the battery shows of e!ectric power systems, subject to the following:
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.
signs of degradation or until 85% of expected service life is reached, at which time annual tests are required. The                a. Availability of Offsite Powe


====r. Consistent with====
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.
3-year interval specified in IEEE Std 308-1974 conflicts        the requirements of Criterion 17, the phrase "within an with these requirements. IEEE Std 450-1975 also                  acceptable time" in Section 5.2.3(4), first paragraph, of describes a battery service test, but no test frequency is      IEEE Std 308.1974 should be construed to mean specified. IEEE Std 308-1974 does not specifically              "within a few seconds". A preferred design would mention the battery service test.                                include two immediate access circuits from the trans- mission network. Detailed guidance for operating pro- It should be noted that the scope of IEEE Std                cedures and restrictions acceptable to the staff, appli.


308-1974 is more limited than that of Criteria 17 and            cable where two immediate access circuits are available,
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
18. For example. the scope of IEEE Std 308-1974                  is contained in Regulatory Guide 1.93, "Availability of excludes the unit generator(s) and th"ir buses; step-up,        Electric Power Sources." An acceptable design would auxiliary, and startup transformers; connections to the         substitute a delayed access circuit for one of the station switchyard. switchyard; transmission lines; and          immediate access circuits provided the availability of the the transmission network. Except for the unit genera-           delayed access circuit conforms to Criterion 17.
1.32-2


tor(s), these are all included within the scope of Criteria
months. The note following Table 2 of IEEE Std 308
17 and 18.                                                              b. Battery Charger Supply. The capacity of the battery charger supply should be based on the largest combined demands of the various steady-state and In the foreword to IEEE Std 308-1974 it is noted            transient loads and the charging capacity to restore the that certain areas of this standard neee more extensive          battery from the design minimum charge state to the treatment. These include shared systems in multi-unit            fully charged state, irrespective of the status of the plant stations, independence between redundant standby                during which these demands occur.
1974 should reference IEEE Std 450-1975 rather than IEEE Std 450-1972.


sourcem, connection of non-Class I E equipment to Class I E systems, and the definition of design basis events.                 c. Battery Performance Discharge Tests. The test Some of these topics have been the subject of other              interval for the battery performance discharge test regulatory guides, e.g., Regulatory Guide 1.6 (Safety            should be as specified in IEEE Std 450-1975 instead of Guide 6), "Independence Between Redundant Standby               the 3 years specified in Table 2 of IEEE Std 308-1974, (Onsite) Power Sources and Between Their Distribution            "Illustrative Periodic Tests." The battery service test Systems," which is concerned with electrical independ-          described In IEEE Std 450-1975 should be performed in ence. Regulatory Guide 1.75, "Physical Independence of          addition to the battery performance discharge test. The Electric Systems," which is concerned with physical              battery service test should be performed during refueling independence of Class IE systems and the connection of          operations or at some other outage, with intervals non-Class I E equipment to Class IE systems; and                between tests not to exceed 18 months. The note Regulatory Guide 1.81, "Shared Emergency and Shut.              following Table 2 of IEEE Std 308-1974 should refer- down Electric Systems for Multi-Unit Nuclear Power              ence IEEE Std 450-1975 rather than IEEE Std Plants." Other matters of importance to the regulatory          450-1972.
d. Independence of Redundant Standby Sources.


1.32-2
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.


d. Independence of Redundant Standby Sources.         IE Power System Conditions," of IEEEStd 308.1974 is Electrical independence between redundant standby            considered unacceptable and should be supplanted by (onsite) power sources should be in accordance with          the recommendations of Regulatory Guide 1.93.
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.


Regulatory Guide 1.6. Physical independence should be in accordance with Regulatory Guide 1.75.
b. Availability of Electric Power Source


e. Connection of Non-Class IE Equipments to Class IE Systems. The guidance presented in Regulatory                         
====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==
Guide 1.75 should be followed.
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 information f. Selection of Diesel Generator Set Capacity for      to applicants reg-irding the NRC staff's plans for using Standby Power Supplies. The guidance presented in              this regulatory guide.


Regulatory Guide 1.9 should be followed.
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.


Except in those cases in which the applicant proposes
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 to       an acceptable alternative method for complying with be unacceptable as given below:                                specified portions of the Commission's regulations. ( I )
                                                                the methods described in portions of this guide that a. Shared Electric Systems for Multi-Unit Nuclear        reference other regulatory guides are being and will Power Plants. The provisions of Section 8.2 of IEEE Sid        continue to be used in the evaluation of submittals for
308.1974, which permit sharing of standby power                construction permit applications and (2) the methods supplies among units of a multi.unit station, are un-        described in other portions of this guide will be used in acceptable except as specified in Regulatory Guide 1.81.        the evaluation of submittals for construction permit The provisions of Section 8.3.1 of IEEE Std 308-1974            applications docketed after November 1. 1976, unless that permit sharing of battery supplies among units at a      this guide is revised as a result of suggestions from the multi.unit plant are considered unacceptable and should        public or additional staff review.


be supplanted by tne recommendations of Regulatory Guide 1.81.                                                        If an applicant wishes to use this regulatory guide in developing submittals for applications docketcd on or b. Availability of Electric Power Sources. Table 3,      before November 1, 1976, the pertinent portions of the
1.32-3
"Suggested Operating Alternatives with Degraded Class          application will be evaluated on the basis of this guide.
0


1.32-3}}
UNITED STATES
NUCLEAR REGULATORY COMMISSION
WASHINGTON, 0. C. 20555 OFFICIAL BUSINESS
PENALTY FOR PRIVATE USE, $300
POSTAGE AND FEES PAID
U.S. NUCLEAR REGULATORY
COMMISSION
1.32-4}}


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

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

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.

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.

1.32-3

0

UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, 0. C. 20555 OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

POSTAGE AND FEES PAID

U.S. NUCLEAR REGULATORY

COMMISSION

1.32-4