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| issue date = 08/31/1980
| issue date = 08/31/1980
| title = SEP Review of NRC Safety Topic III-1,Associated W/Electrical,Instrumentation & Control Portion of Classification of Structures Components & Sys for Ginna Nuclear Power Plant.
| title = SEP Review of NRC Safety Topic III-1,Associated W/Electrical,Instrumentation & Control Portion of Classification of Structures Components & Sys for Ginna Nuclear Power Plant.
| author name = GILMORE L W, LAUDENBACH D H, MAYN B G
| author name = Gilmore L, Laudenbach D, Mayn B
| author affiliation = EG&G, INC.
| author affiliation = EG&G, INC.
| addressee name =  
| addressee name =  
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:4%EnergyMeasurements Group1183-4164 AUGUST1980tef}~/cga''rSTEMATIC EVALUATION PIRQGRANREVIEWQFNRCSAFETYTOPICIII-1ASSQCIATEQ WITHTHEEILECTRICAL, IIMSTRUMKHTATIQIM, ANQCQIMmQLPORTIONOFTHECLASSIFICATION OFSTIRtjCTURES, COMPONENTS, ANDSYSTEMSFQRTHEGINNANUCLEARPQVZERPLANT,!P/0/IZOBg~
{{#Wiki_filter:1183-4164 AUGUST 1980 4%     Energy Measurements Group t
SANRAMONOPERATIONS 2801OLOCROWCANYONROAO8ANRAMON,CALIFORNIA 84583
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EVALUATIONPIRQGRAN REVIEW QF NRC SAFETY TOPIC III-1 ASSQCIATEQ WITH THE EILECTRICAL, IIMSTRUMKHTATIQIM, cga''rSTEMATIC ANQ CQIMmQL PORTION OF THE CLASSIFICATION OF STIRtjCTURES, COMPONENTS, AND SYSTEMS FQR THE  GINNA NUCLEAR PQVZER PLANT
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SAN RAMON OPERATIONS 2801 OLO CROW CANYON ROAO 8AN RAMON, CALIFORNIA 84583
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~EHzCrEnergyMeasurements.
~EHzCr Energy Measurements. Group                                                        1183-41'64 San Ramon Operations August 1980 SYSTEMATIC EVALUATIONPROGRAM REVIEW OF NRC SAFETY TOPIC              III-1 ASSOCIATED WITH THE ELECTRICAL, INSTRUMENTATION, AND CONTROL PORTION OF THE CLASSIFICATION OF STRUCTURES COMPONENTSr AND SYSTEMS FOR THE GINNA NUCLEAR POWER PLANT by
GroupSanRamonOperations 1183-41'64 August1980SYSTEMATIC EVALUATION PROGRAMREVIEWOFNRCSAFETYTOPICIII-1ASSOCIATED WITHTHEELECTRICAL, INSTRUMENTATION, ANDCONTROLPORTIONOFTHECLASSIFICATION OFSTRUCTURES COMPONENTSr ANDSYSTEMSFORTHEGINNANUCLEARPOWERPLANTby0.H.Laudenbach ApprovdforPublication B.G.MaynScientific Specialist II!Thisdocument.
: 0. H. Laudenbach Approv d  for Publication B. G. Mayn Scientific Specialist   II!
isUNCLASSIFIED
This document. is UNCLASSIFIED
\Derivative
                                                          \
~WFjClassifier:LeonarW.1moreAssistant ProgramManagerWorkPerformed forLawrenceLlvermore NationalLaboratory underU.S.Department ofEnergyContractNo.DE-ACQS-76 NVO1183.
Derivative Cl assi fi er:
4$a ABSTRACTThisreportdocuments thetechnical evaluation andreviewofNRCSafetyTopic111-1,associated withtheelectrical, instrumentation, andcontrolportionsoftheclassification ofstructures, components, andsystemsfortheGinnaNuclearPowerPlant,usingcurrentlicensing criteria.
                                    ~W      F        j Leonar  W. 1 more Assistant Program  Manager Work Performed for Lawrence Llvermore National Laboratory under U.S. Department of Energy Contract No. DE-ACQS-76 NVO 1183.
FOREWORDThisreportissuppliedaspartoftheSystematic Evaluation Pro-grambeingconducted fortheU.S.NuclearRegulatory Commission byLawrenceLivermore NationalLaboratory.
 
Theworkwasperformed byEGSG,Inc.,EnergyMeasurements Group,SanRamonOpertions forLawrenceLivermoreNationalLaboratory underU.S.DepartmentofEnergycontractnumberDE-AC08-76NV01183.
4$
0 TABLEOFCONTENTSPage1.INTRODUCTION.................
a
12.REVIEWGUIDELINES................
 
33.COMPILATION OFIDENTIFIED SYSTEMS3.1Engineered SafetyFeatureSystems3.2ReactorProtection System.3.3Additional Systems5566REFERENCES.
ABSTRACT This report documents the technical evaluation and review of NRC Safety Topic 111-1, associated with the electrical, instrumentation, and control portions of the classification of structures, components, and systems for the Ginna Nuclear Power Plant, using current licensing cri teri a.
...................7APPENDIXANRCSAFETYTOPICSRELATEDTOTHISREPORT.....
 
A-1 SYSTEMATIC EVALUATION'ROGRAM REVIEWOFNRCSAFETYTOPICIII-1ASSOCIATED WITHTHEELECTRICAL, INSTRUMENTATION, ANDCONTROLPORTIONOFTHECLASSIFICATION OFSTRUCTURES, COMPONENTS, ANDSYSTEMSFORTHEGINNANUCLEARPOWERPLANT,D.H.Laudenbach EG8G,Inc.,EnergyMeasurements GroupSanRamonOperations 1.INTRODUCTION SomeoftheSEPplantstructures, systems,andcomponents maynotbedesignedtowithstand theeffectsofasafeshutdownearthquake andremainfunctional.In-somecases,systemsandcomponents important tosafetymaynotbedesigned, fabricated, erected,andtestedtoqualitystandards commensurate withtheirsafetyfunction.
FOREWORD This report is supplied as part of the Systematic Evaluation Pro-gram being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore National Laboratory. The work was performed by EGSG, Inc.,
Thecompilation ofthemajorsystemsrequiredfordesignbasisevents(DBE)andforsafeshutdownoftheplantissubmitted insupportofNRCSafetyTopic111-12.Thissafetytopicaddresses whetherthemajorsystemsidentified meetcurrentqualitystandards.
Energy Measurements  Group, San Ramon Opertions for Lawrence Livermor e National Laboratory under U.S. Depar tment of Energy contract number DE-AC08-76NV01183.
2.REVIEWGUIDELINES Theobjective ofthisreviewistoidentifyonlythemajorelec-trical,instrumentation andcontrolsystems(EICS)requiredforDBEandforsafeshutdownoftheplant.Thisidentification istobeperformed whenreviewing eachNRCsafetytopic.AdetailedsearchisnottobemadetoidentifyallrequiredsystemsforDBEandforsafeshutdown.
 
I 3.COMPILATION OFIDENTIFIED SYSTEMS3.1ENGINEERED SAFETYFEATURESYSTEMSThefollowing engineered safetyfeaturesystemsarerequiredforDBEandsafeshutdown:
0 TABLE OF CONTENTS Page
1.Safetyinjection system(Emergency CoreCoolingSystem)a.High-pressure safetyinjection pumpsb.Low-pressure safetyinjection (RHR)pumpsc.Passiveaccumulators d.Refueling waterstoragetanke.Boricacidtanks2.Containment airrecirculation andfiltration system.a.Fan-cooler unitsb.Charcoalfilterunitsc.Iodineremovalunitsd.Hydrogenrecombiner 3.Containment spraysystema.Containment spraypumpsb.Refueling waterstoragetankc.Sprayadditivetank4.Containment isolation system5.Containment ventilatingsystema.Recirculation ventilation b.Purgesystem lO 3.2REACTORPROTECTION SYSTEMSThefollowing reactorprotection systems(reactortripchannels) arerequiredforDBEandsafeshutdown:
: 1. INTRODUCTION.................                                   1
1.Highnuclearflux(powerrange)2.Highnuclearflux(intermediate range)3.Highnuclearflux(sourcerange)4.Overtemperature hT5.Overpower hT6.LowRCSpressure7.Highpressurizer pressure8.Highpressurizer waterlevel9.Lowreactorcoolantflow10.Turbinetrip11.Highcontainment pressure12.Lowsteamgenerator pressure13.Lowsteamgenerator level14.Manualtrip3.3ADDITIONAL SYSTEMSInadditiontotheESFandRPS,thefollowing systemsarerequir-edforDBEandsafeshutdown:
: 2. REVIEW  GUIDELINES................                             3
1.Auxiliary feedwater system2.Servicewatersystem3.Component coolingwatersystem4..Residualheatremovalsystem5.Chemicalandvolumecontrolsystem6.Offsitepowersystem7.Controlroomsystems8.Emergency power(a-candd-c)andcontrolpowerfortheabovesystemsandcomponents REFERENCES 1.Rochester GasandElectricCorporation, GinnaFinalSafetyAnalysisReport,datedApril23,1975.2.EQG,SanRamonDivision, technical evaluation reportsonNRCsafetytopics:a)b)c)e)f)g)h)SafetyTopicVI-7.A.3, "ECCSActuation."
: 3. COMPILATION OF IDENTIFIED SYSTEMS                              5 3.1    Engineered Safety Feature Systems                        5 3.2    Reactor Protection System .                             6 3.3    Additional Systems                                      6 REFERENCES.   .   . . .   . .   . . . . .   . . . . . . . . 7 APPENDIX A    NRC SAFETY TOPICS RELATED TO THIS    REPORT..... A-1
November1979.SafetyTopicVI-lO.A,"TestingofRTSandESF,Including ResponseTime,"November1979.SafetyTopicVII=1.A,"Isolation ofRPSfromNon-safety Systems,Including gualification ofIsolation Devices,"
 
July1980.SafetyTopicYI-7.B,"ESFSwitchover fromInjection toRecircula-tionNode,"November1979.SafetyTopicVII-2,"ESFSystemControlLogicandDesign,"July1980.SafetyTopicY-11.B,"RHRInterlock Requirements,"
SYSTEMATIC EVALUATION'ROGRAM REVIEW OF NRC SAFETY TOPIC      III-1 ASSOCIATED WITH THE ELECTRICAL, INSTRUMENTATION, AND CONTROL PORTION OF THE CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS FOR THE GINNA NUCLEAR POWER PLANT
June1980.SafetyTopicV-10.B,"RHRSystemReliability,"May1980.SafetyTopicVII-3,"SystemsRequiredforSafeShutdown,"
                                    ,D. H. Laudenbach EG8G,     Inc.,   Energy Measurements Group San Ramon  Operations
August1980.
: 1. INTRODUCTION Some  of the  SEP  plant structures, systems, and components may not be designed to withstand the effects of a safe shutdown earthquake and remain functi onal . In some cases, systems and components important to safety may not be designed, fabricated, erected, and tested to quality standards commensurate with their safety function.
APPENDIXANRCSAFETYTOPICSRELATEDTOTHISREPORT1.SafetyTopicVI-7.A.32.SafetyTopicVI-10.A"ECCSActuation."
The  compilation of the major systems required for design basis events (DBE) and for safe shutdown of the plant is submitted in support of NRC Safety Topic 111-12.         This safety topic addresses whether the major systems identified meet current quality standards.
"TestingofRTSandESF,Including ResponseTime."3.SafetyTopicVII-1.A"Isolation ofRPSfromNon-safety Systems,Including
: 2. REVIEW GUIDELINES The  objective of this review is to identify only the major elec-trical, instrumentation and control systems (EICS) required for DBE and for safe shutdown of the plant. This identification is to be performed when reviewing each NRC safety topic. A detailed search is not to be made to identify all required systems for DBE and for safe shutdown.
()ualificationofIsolationDevices."
 
4.SafetyTopicVI-7.B"ESFSwitchover fromInjection toRecir-culationMode.5.SafetyTopicVII-26.SafetyTopicIII-27.SafetyTopicIII-3"ESFSystemControlLogicandDesign.""MindandTornadoLoadings."
I
"Hydrodynamic Loads."a)Effectsofhighwaterlevelonstructures b)Structural andotherconsequences (e.g.,floodingofsafety-related
: 3. COMPILATION OF IDENTIFIED SYSTEMS 3.1      ENGINEERED SAFETY FEATURE SYSTEMS The  following engineered safety feature systems are required for DBE and safe shutdown:
.equipment inbasements) offailureofunderdrain systemsc)Inservice inspection ofwatercontrolstructures.
: 1. Safety injection system           (Emergency   Core  Cooling System)
8.SafetyTopicIII-49.SafetyTopicIII-510.SafetyTopicIII-6"MissileGeneration andProtection."
: a. High-pressure safety injection pumps
a)Tornadomissilesb)Turbinemissilesc)Internally-generated missilesd)Siteproximitymissiles(including aircraft)."EvaluationofPipeBreaks."a)Effectsofpipebreakonstructures, systemsandcomponents insidecon-tainmentb)Pipebreakoutsidecontainment.
: b. Low-pressure safety injection (RHR) pumps
"SeismicDesignConsiderations."}}
: c. Passive accumulators
: d. Refueling water storage tank
: e. Boric acid tanks
: 2. Containment   air recirculation    and filtration  system.
: a. Fan-cooler units
: b. Charcoal  filter  units
: c. Iodine removal units
: d. Hydrogen recombiner
: 3. Containment spray system
: a. Containment spray pumps
: b. Refueling water storage tank
: c. Spray additive tank
: 4. Containment   isolation   system
: 5. Containment   ventil ating system
: a. Recirculation ventilation
: b. Purge system
 
lO 3.2        REACTOR PROTECTION SYSTEMS The  following reactor protection systems (reactor      trip channels) are required for DBE and safe shutdown:
: 1. High nuclear flux (power range)
: 2. High nuclear flux (intermediate range)
: 3. High nuclear flux (source range)
: 4. Overtemperature hT
: 5. Overpower hT
: 6. Low RCS pressure
: 7. High pressurizer  pressure
: 8. High pressurizer water level
: 9. Low  reactor coolant flow
: 10. Turbine trip
: 11. High containment pressure
: 12. Low steam generator pressure
: 13. Low steam generator level
: 14. Manual  trip 3.3        ADDITIONAL SYSTEMS In addition to the  ESF and RPS,   the following systems are requir-ed  for DBE  and safe shutdown:
: 1. Auxiliary feedwater   system
: 2. Service water system
: 3. Component cooling water system
: 4. . Residual heat removal system
: 5. Chemical and volume  control system
: 6. Offsite  power system
: 7. Control room systems
: 8. Emergency power (a-c and d-c) and control power for the above systems and components
 
REFERENCES
: 1. Rochester Gas and Electric Corporation,     Ginna Final Safety Analysis Report, dated April 23, 1975.
: 2. EQG, San  Ramon Division, technical evaluation reports  on  NRC safety topics:
a)   Safety Topic VI-7.A.3, "ECCS Actuation." November 1979.
b)  Safety Topic VI-lO.A, "Testing of RTS and ESF, Including Response Time," November 1979.
c)  Safety Topic VII=1.A, "Isolation of RPS from Non-safety Systems, Including gualification of Isolation Devices," July 1980.
Safety Topic YI-7.B, "ESF Switchover from Injection to Recircula-tion Node," November 1979.
e)  Safety Topic VII-2,   "ESF System Control Logic and Design," July 1980.
f)  Safety Topic Y-11.B, "RHR Interlock Requirements," June 1980.
g)  Safety Topic V-10.B, "RHR System Reliabi lity," May 1980.
h)  Safety Topic VII-3, "Systems Required for Safe Shutdown," August 1980.
 
APPENDIX A NRC SAFETY TOPICS RELATED TO THIS REPORT
: 1. Safety Topic VI-7.A.3      "ECCS  Actuation."
: 2. Safety Topic VI-10.A       "Testing of  RTS  and ESF, Including Response Time."
: 3. Safety Topic VII-1.A       "Isolation of RPS from Non-safety Systems, Including ()ual i f i cation of I sol ation Devices."
: 4. Safety Topic VI-7.B       "ESF  Switchover from Injection to Recir-culation  Mode.
: 5. Safety Topic VII-2        "ESF System  Control Logic and Design."
: 6. Safety Topic  III-2        "Mind and Tornado Loadings."
: 7. Safety Topic  III-3        "Hydrodynamic Loads."
a)   Effects      of high    water  level    on structures b)   Structural and other consequences (e.g., flooding of safety-related
                                  .equipment in basements) of failure of underdrain systems c) Inservice inspection of water control structures.
: 8. Safety Topic  III-4        "Missile Generation and Protection."
a)   Tornado missiles b) Turbine missiles c) Internally-generated missiles d) Site pr oximi ty missiles (including aircraf t) .
: 9. Safety Topic  III-5        "Eval uati on of Pi pe Breaks."
a)   Effects of pipe break on structures, systems and components insi de con-tainment b)   Pipe break outside containment.
: 10. Safety Topic  III-6        "Seismic Design Considerations."}}

Latest revision as of 11:12, 4 February 2020

SEP Review of NRC Safety Topic III-1,Associated W/Electrical,Instrumentation & Control Portion of Classification of Structures Components & Sys for Ginna Nuclear Power Plant.
ML17258A700
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Issue date: 08/31/1980
From: Gilmore L, Laudenbach D, Mayn B
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Text

1183-4164 AUGUST 1980 4% Energy Measurements Group t

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EVALUATIONPIRQGRAN REVIEW QF NRC SAFETY TOPIC III-1 ASSQCIATEQ WITH THE EILECTRICAL, IIMSTRUMKHTATIQIM, cgarSTEMATIC ANQ CQIMmQL PORTION OF THE CLASSIFICATION OF STIRtjCTURES, COMPONENTS, AND SYSTEMS FQR THE GINNA NUCLEAR PQVZER PLANT

~

/

SAN RAMON OPERATIONS 2801 OLO CROW CANYON ROAO 8AN RAMON, CALIFORNIA 84583

,! P/0/IZOBg~

~EHzCr Energy Measurements. Group 1183-41'64 San Ramon Operations August 1980 SYSTEMATIC EVALUATIONPROGRAM REVIEW OF NRC SAFETY TOPIC III-1 ASSOCIATED WITH THE ELECTRICAL, INSTRUMENTATION, AND CONTROL PORTION OF THE CLASSIFICATION OF STRUCTURES COMPONENTSr AND SYSTEMS FOR THE GINNA NUCLEAR POWER PLANT by

0. H. Laudenbach Approv d for Publication B. G. Mayn Scientific Specialist II!

This document. is UNCLASSIFIED

\

Derivative Cl assi fi er:

~W F j Leonar W. 1 more Assistant Program Manager Work Performed for Lawrence Llvermore National Laboratory under U.S. Department of Energy Contract No. DE-ACQS-76 NVO 1183.

4$

a

ABSTRACT This report documents the technical evaluation and review of NRC Safety Topic 111-1, associated with the electrical, instrumentation, and control portions of the classification of structures, components, and systems for the Ginna Nuclear Power Plant, using current licensing cri teri a.

FOREWORD This report is supplied as part of the Systematic Evaluation Pro-gram being conducted for the U.S. Nuclear Regulatory Commission by Lawrence Livermore National Laboratory. The work was performed by EGSG, Inc.,

Energy Measurements Group, San Ramon Opertions for Lawrence Livermor e National Laboratory under U.S. Depar tment of Energy contract number DE-AC08-76NV01183.

0 TABLE OF CONTENTS Page

1. INTRODUCTION................. 1
2. REVIEW GUIDELINES................ 3
3. COMPILATION OF IDENTIFIED SYSTEMS 5 3.1 Engineered Safety Feature Systems 5 3.2 Reactor Protection System . 6 3.3 Additional Systems 6 REFERENCES. . . . . . . . . . . . . . . . . . . . 7 APPENDIX A NRC SAFETY TOPICS RELATED TO THIS REPORT..... A-1

SYSTEMATIC EVALUATION'ROGRAM REVIEW OF NRC SAFETY TOPIC III-1 ASSOCIATED WITH THE ELECTRICAL, INSTRUMENTATION, AND CONTROL PORTION OF THE CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS FOR THE GINNA NUCLEAR POWER PLANT

,D. H. Laudenbach EG8G, Inc., Energy Measurements Group San Ramon Operations

1. INTRODUCTION Some of the SEP plant structures, systems, and components may not be designed to withstand the effects of a safe shutdown earthquake and remain functi onal . In some cases, systems and components important to safety may not be designed, fabricated, erected, and tested to quality standards commensurate with their safety function.

The compilation of the major systems required for design basis events (DBE) and for safe shutdown of the plant is submitted in support of NRC Safety Topic 111-12. This safety topic addresses whether the major systems identified meet current quality standards.

2. REVIEW GUIDELINES The objective of this review is to identify only the major elec-trical, instrumentation and control systems (EICS) required for DBE and for safe shutdown of the plant. This identification is to be performed when reviewing each NRC safety topic. A detailed search is not to be made to identify all required systems for DBE and for safe shutdown.

I

3. COMPILATION OF IDENTIFIED SYSTEMS 3.1 ENGINEERED SAFETY FEATURE SYSTEMS The following engineered safety feature systems are required for DBE and safe shutdown:
1. Safety injection system (Emergency Core Cooling System)
a. High-pressure safety injection pumps
b. Low-pressure safety injection (RHR) pumps
c. Passive accumulators
d. Refueling water storage tank
e. Boric acid tanks
2. Containment air recirculation and filtration system.
a. Fan-cooler units
b. Charcoal filter units
c. Iodine removal units
d. Hydrogen recombiner
3. Containment spray system
a. Containment spray pumps
b. Refueling water storage tank
c. Spray additive tank
4. Containment isolation system
5. Containment ventil ating system
a. Recirculation ventilation
b. Purge system

lO 3.2 REACTOR PROTECTION SYSTEMS The following reactor protection systems (reactor trip channels) are required for DBE and safe shutdown:

1. High nuclear flux (power range)
2. High nuclear flux (intermediate range)
3. High nuclear flux (source range)
4. Overtemperature hT
5. Overpower hT
6. Low RCS pressure
7. High pressurizer pressure
8. High pressurizer water level
9. Low reactor coolant flow
10. Turbine trip
11. High containment pressure
12. Low steam generator pressure
13. Low steam generator level
14. Manual trip 3.3 ADDITIONAL SYSTEMS In addition to the ESF and RPS, the following systems are requir-ed for DBE and safe shutdown:
1. Auxiliary feedwater system
2. Service water system
3. Component cooling water system
4. . Residual heat removal system
5. Chemical and volume control system
6. Offsite power system
7. Control room systems
8. Emergency power (a-c and d-c) and control power for the above systems and components

REFERENCES

1. Rochester Gas and Electric Corporation, Ginna Final Safety Analysis Report, dated April 23, 1975.
2. EQG, San Ramon Division, technical evaluation reports on NRC safety topics:

a) Safety Topic VI-7.A.3, "ECCS Actuation." November 1979.

b) Safety Topic VI-lO.A, "Testing of RTS and ESF, Including Response Time," November 1979.

c) Safety Topic VII=1.A, "Isolation of RPS from Non-safety Systems, Including gualification of Isolation Devices," July 1980.

Safety Topic YI-7.B, "ESF Switchover from Injection to Recircula-tion Node," November 1979.

e) Safety Topic VII-2, "ESF System Control Logic and Design," July 1980.

f) Safety Topic Y-11.B, "RHR Interlock Requirements," June 1980.

g) Safety Topic V-10.B, "RHR System Reliabi lity," May 1980.

h) Safety Topic VII-3, "Systems Required for Safe Shutdown," August 1980.

APPENDIX A NRC SAFETY TOPICS RELATED TO THIS REPORT

1. Safety Topic VI-7.A.3 "ECCS Actuation."
2. Safety Topic VI-10.A "Testing of RTS and ESF, Including Response Time."
3. Safety Topic VII-1.A "Isolation of RPS from Non-safety Systems, Including ()ual i f i cation of I sol ation Devices."
4. Safety Topic VI-7.B "ESF Switchover from Injection to Recir-culation Mode.
5. Safety Topic VII-2 "ESF System Control Logic and Design."
6. Safety Topic III-2 "Mind and Tornado Loadings."
7. Safety Topic III-3 "Hydrodynamic Loads."

a) Effects of high water level on structures b) Structural and other consequences (e.g., flooding of safety-related

.equipment in basements) of failure of underdrain systems c) Inservice inspection of water control structures.

8. Safety Topic III-4 "Missile Generation and Protection."

a) Tornado missiles b) Turbine missiles c) Internally-generated missiles d) Site pr oximi ty missiles (including aircraf t) .

9. Safety Topic III-5 "Eval uati on of Pi pe Breaks."

a) Effects of pipe break on structures, systems and components insi de con-tainment b) Pipe break outside containment.

10. Safety Topic III-6 "Seismic Design Considerations."
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