ML20202G173
| ML20202G173 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/12/1998 |
| From: | Powers K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20202G179 | List: |
| References | |
| NUDOCS 9802200075 | |
| Download: ML20202G173 (26) | |
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- ip y j A CMS Energy Conpany bg hk hat klear Punt M !. Powers 10209 ls-31 nyttr Site General Manager 0
Ctwievoix, MI 49720 A
t February 12, 1998 Nuclear Regulatory Commission Document Control Desk 3
Washington, DC 20555-0001 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - REVISION 7 TO THE UPDATED FINAL HAZARDS
SUMMARY
REPORT I
l Pursuant to the requirements of 10 CFR 50,71, Consumers Energy I
Company hereby submits one original and ten copies of Revision 7 to I
the Updated Final Hazards Summary Report (FHSR) for Big Rock Point Plant.
Pursuant to the requirements of 10 CFR 50.4, one original
)
and ten copies are enclosed. Also attached is a list of Effective Pages and an Index of Chapters followed by the page replacement.
All Chapters except for 1.6 and 17 were replaced in their entirety, Chapter 16 is the Technical Specifications and Chapter 17 is the Quality Assurance Plan.
These were submitted under separate cover.
This revision to our Updated Final Hazards Summary Report is based upon the permanently defueled condition of Big Rock Point.
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Kenneth P. Powers j
i Site General Manager
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Administrator, Region III USNRC NRC Resident Inspector - Big Rock Point 4
NRR Project Manager - OWFN, USNRC
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ATTACHMENT I.l I.lll.l!Illi.I.Ill I.ll 9802200075 980212 4
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To'the best of'my knowledge,-cinformation and-belief, the contents Jof this submittal-are truthful and complete.
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' Kenneth P Powers Si te :. Gene ral '. Ma na ger Sworn and-subscribed to before me this.12th day of February 1998.
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-My commission, expires-AugustL 29. 1999.
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LIST OF EFFECilVE PAGES CHAPTER 1 INTRODUCTION AND GENEML PURPOSES 1.11 Revision 7 1.2 1 Rr 'sion 7 1.2 2 Re 'on 7 1,2 3 Re,a m 7 l.31 Revision 7 1.4-1.
Revision 7 -
4 1.5-1 Revision 7 1.6-1 Revision 7 1.7 1 Revision 7 CHAPTER 2 SITECHARACTERISTICS 2.1-1 Revision 7 2.1-2 Revision 7 2.1-3 Revision 7 4.-
2.1-4 Revision 7 2.15 Revision 7 2.1-6 Revision 7 2.1-7 Revision 7 -
2.1 8 Revision 7 2.1-9 Revision 7 2.1 10 Revision 7 2.1 11 Revision 7 2.1-12 Revision 7 2.21 Revision 7 2.2 2 Revision 7 2.2 3 Revision 7 -
2.2-4 Revision 7 2.2 5 Revision 7 2.2 6 Revision 7 -
2.31 Revision 7 2.3 2 Revision 7 2.3-3 Revision 7 2.3-4 Revision 7 2.3-5 Revision 7 2.3-6 Revision 7 2.3-7 Revision 7 2.3-8 Revision 7 2.39 Revision 7 2.4-1 Revision 7 2,4-2 Revision 7 2.4-3 Revision 7 2.4-4 Revision 7 2.4-5 Revision 7 2.4-6 Revision 7 2.5-1 Revision 7 2.52 Revision 7 2.53 Revision 7 2.5-4 Revision 7
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I,IST OF EFFECTIVE PAGES 2.55 Revision 7 2.5 6 Revision 7 2.5 7 Revision 7 f
2.58 Revision 7
-2.59 Revision 7 2,5 10 Revision 7 2.51I Revision 7 l
2.5-12 Revision 7 2.5 13 Revision 7 2.5 14 Revision 7 2.5 15 Revision 7 2.5 16 Revision 7 2.5 17 Revision 7 2.5 18 Revision 7 2.5 19 Revision 7 l
2.5 20 Revision 7 i
2.5 21 Revision 7 2.5 22 Revision 7 CHAPTER 3 - DESIGN OF STRUCTURES, COMPONENTS, i
EQUIPMENT AND SYSTEMS 3.1 1 Revision 7 3.2 1 Revision 7 3.2 2 Revision 7 3.2 3-Revision 7 3.2-4 Revision 7 3.2 5 Revision 7 3.2-6 Revisica 7 3.2-7 Revision 7 3.2 8 Revision 7 3.2 9-Revision 7 3.2 10 Revision 7 3.2 11 Revision 7 4
3.2 12 Revision 7 3.2 13 Revision 7 3.2-14 Revision 7 l
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' Revision 7 t-3.2 Revision 7 3.2-17 Revision 7 3.2 18 Revision 7 3.2-19 Revision 7 3.2 20 Revision 7 3.31 Revision 7 3.32 Revision 7 3.3 3 Revision 7 3.3-4 Revision 7 3.3-5 Revision 7 3.3-6 Revision 7 3.4-1 Revision 7 l
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3.5 3 Revision 7 3.5-4 Revision 7 3.5-5 Revision 7 3.56 Revision 7 3.5-7 Revision 7 3.6 1 Revision 7 3.7 1 Revision 7 3.8 1 Revision 7 3.8 2 Revision 7 3.8 3 Revision 7 3.8-4 Revision 7 3.8-5 Revision 7 3.8-6 Revision 7 3.8 7 Revision 7 3.8 8 Revision 7 3.8 9 Revision 7 3.8-10 Revision 7 3.8 11 Revision 7 3.8 12 Revision 7 3.8-13 Revision 7 3.8-14 Revision 7 3.8 15 Revision 7 3.8 16
. Revision 7 3.8-17 Revision 7 3.8-18 Revision 7 3.8-19 Revision 7 3.9 1 Revision 7 3.9-2 Revision 7 3.10-1 Revision 7 l
3.11-1 Revision 7 i
CIIAPTER 4 - REACTOR 1
l-4.0-1 Revision 7 CHAPTER 5 - REACTOR COOLANT AND CONNECTED SYSTEMS l
5.1-1 Revision 7 l
5.21 Revision 7 5.2-2 Revision 7 5.2-3 Revision 7 5.2-4 Revision 7 5.3-1 Revision 7 5.4-1 Revision 7 5.4-2 Revision 7 5.4-3 Revision 7 5.4-4 Revision 7 5.4 5 Revision 7
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7.13 Revision 7 7.2 1 Revision 7 7.31 Revision 7 7.4 1 Revision 7 7.5-1 Revision 7 7.6.I Revision 7 7.7 1 Revision 7 CIIAPTER 8 - ELECTRIC POWER 8.1-1 Revision 7 8.2 1 Revision 7 8.2-2 Revision 7 8.2-3 Revision 7 8.2-4 Revision 7 8.3-1 Revision 7 8.32 Revision 7 8.33 Revision 7 8.3-4 Revision 7 8.35 Revision 7 8.3-6 Revision 7 8.3-7 Revision 7 8.38 Revision 7 8.3-9 Revision 7 8.4-1 Revision 7 8.42 Revision 7 8.43 Revision 7 8.4-4 Revision 7 8.51 Revision 7 l
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CHAPTER 12 RANATION PROTECTION 12.1.I Revision 7 12.1 2
- Revision 7 12.1 3 Revision 7 12.2 1 Revision 7 12.3 1 Revision 7 12.3 2 Revision 7 12.3 3 Revision 7 12.3-4 Revision 7 12.3 5 Revision 7 12.3 6 Revision 7 12.4 1 Revision 7 -
12.4 2 Revision 7 12.4 3 Revision 7 12.5 1 Revision 7.
12.5-2 Revision 7 CHAPTER 13-CONDUCT OF OPERATIONS 13.1 Revision 7 '
13.1-2 Revision 7 13.1 Revision 7 13.1-4 Revision 7 j
13.1-5
- Revision 7 13.2-1 Revision 7 r
13.2 2 Revision 7 13.2-3 Revision 7 13.2-4 Revision 7-13.3-1 Revision 7 13.4-1 Revision 7 2
13.5-1 Revision 7 13.5 2 Revision 7 13.5-3 Revision 7 13.5-4 Revision 7 13.5 5 Revision 7 l
13.5 6 Revision 7 13.6-1 Revision 7 CHAPTER 14 -INITIAL RESEARCH AND DEVELOPMENT PROGRAM 14.0-1 Revision 7 CHAPTER 15-ACCIDENT ANALYSIS i.
15.0-1 Revision 7 15.1-1 Revision 7 15.2 1 Revision 7 15.3 1 Revision 7 15.4 1 Revision 7
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17.0 Original CHAPTER 18 - HUMAN FACTORS ENGINEERING 18.1-1 Revision 7 18.2-1 Revision 7 18.3-1 Revision 7 l
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Page 1 of 15 Revision 7 INDEX CHAR iER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
AND PURPOSE OF THIS REPORT
1.2 BACKGROUND
AND PLANT DESCRIPTION 1.2.1 3ACKGROUND 1.2.2 PLANT DESCRIPTION 1.3 SCOPE CHARACTER _ AND CONCLUSIONS OF THIS REPORT 1.3.1 SC7PE 1.3.2 CHARACTER 1.
3.3 CONCLUSION
S 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 1.5 REOUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.5,1 INTEGRATED ASSESSMENT OFISSUES 1.5.2 PROBABILISTIC RISK ASSESSMENT (PRA) 1.5.3 SYSTEMATIC EVALUATION PROGRAM (SEP) 1.6 MATERIALINCORPORATED BY REFERENCE 1.7 DRAWINGS AND OTHhR DETAILED INFORMATION CHAPTER 2 SIT E CHARACTERISTICS 2.1 GEOGRAPHY AND DEMOGRAPHY 2.1.1 SITE LOCATION AND DESCRIPTION 2.1.2 EXCLUSION AREA AUTHORITY AND CONTROL 2.1.3 POPULATION DISTRIBUTION 2.2 NEARBY INDU' TRIAL. TRANSPORTATION. AND MILITARY FACILITIES 2.2.1 LOCATIONS AND ROUTES 2.2.2 EVALUATION
SUMMARY
2.2.3 SAFETY EVALUATION CONCLUSIONS 2.3 METEOROLOGY 2.3.1 NORMAL AND SEVERE WEATHER
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Page 4 of 15 Revision 7 3.6.2 EFFECTS OF PIPE BREAKS ON STRUCTURES, SYSTEMS, AND COMPONENTS INSIDE CONTAINMENT 3,7 SEISMIC DESIGN 3.7.1 SEISMIC INPUT 3.7.2 SEISMIC SYSTEM ANALYSIS -
3.7.3 SEISMIC SUBSYSTEM ANALYSIS 37.4 SE15MIC INSTRUMENTATION 3.8 DESIGN OF CATEGOR 7 I STP.UCTURES 3.8.1 CONTAINMENT -
3.8.2 CONCRETE AND STEEL STRUCTURES 3.8.3 DESIGN CODES, DESIGN CRITERIA, LOAD COMBINATIONS, AND REACTOR CAVITY DESIGN CRITERIA
. 3.9 MECHANICAL SYLTEMS AND COMPONENTS 3.9.1 ASME CODE CLASS 1,2, and 3 COMPONENTS 3.9.2 INSERVICE INSPECTION AND INSERVICE TESTING PROGRAM 3.9.3 INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) INSPECTION PROGRAM 3.9.4 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM 3.9.5 REACTOR PRESSURE VESSELINTERNALS 3.10 SEISMIC OUALIFICATION OF SEISMIC CATF60RY I INSTRUMENTATION AND ELEC i KICAL EOUIPMENT 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EOUIPMENT 3.11.1 ELECTRICAL EQUIPMENT QUALIFICATION (EEQ) 3.11.2 ELECTRICAL QUALIFICATION (EQ) PROGRAM CERTIFICATION 3.11.3 EEQ PROGRAM SUMiv!ARY 3.11.4 NRC SAFETY EVALUATION (S) 3.11.5 RESOLUTION OF EEQ PROGRAM 3.11.6 EEQ PROGRAM ADDITIONS CHAPTER 4 REACTOR 4.1
SUMMARY
DESCRIPTION 4.2 FUEL SYSTEM DESIGN
- 4.3 NUCLEAR DESIGN 4.4 THERMAL AND HYDRAULIC DESIGN
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OPERATION WITH LESS THAN ALL LOOPS 4.6
' REACTIVITY CONTROL SYSTEMS 4.7 CONTROL ROD DRIVE SYSTEMS 4.8 LIOUID POISON SYSTEM (LPS) l CHAPTER 5: REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5.1
SUMMARY
DESCRIPTION 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY 5.2.1 COMPLIANCE WITH CODES AND CODE CASES 5.2.2
- OVERPRESSURE PROTECTION 5.2.3 REACTOR COOLANT PRESSURE BOUNDARY MATERIALS 5.2.4 INSERVICE INSPECTION AND TESTING OF REACTOR COOLANT PRESSURE BOUNSARY 5.2.5 DETECTION OF LEAKAGE THROUGH REACTOls COOLANT PRESSURE BOUNDARY (RCPB) 5.2.6 THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS 5.3 REACTOR VESSEL 5.3.1 GENERAL DESCRIPTION 5.3.2 -
REACTOR VESSEL PRESSURE / TEMPERATURE LIMITS 5.3.3 REACTOR VESSEL INTEURITY 5.4 COMPONENT AND SUBSYSTEM DESIGN.
5.4.1 REACTOR COOLANT RECIRCULATING PUMPS 5.4.2 STEAM DRUM AND STEAM DRUM RELIEF VALVES 5.4.3 REACTOR COOLANT PIPING AND VALVES 5.4.4 NUCLEAR STEAM SUPPLY SYSTEM 5.4.5 RESILUAL HEAT REMOVAL SHUTDOWN COOLING SYSTEM 5.4.6 REACTOR CLEANUP SYSTEM 5.4.7 REACTOR COOLANT SYSTEM HIGH POINT VENTS 5.4.8 PRIMARY COOLANT PURITY AND LIMITS 5.4.9 '
REACTOR COOLING WATER SYSTEM CHAPTER & ENGINEERED SAFETY FEATURES (ESF) 6.1 ENGINEERED S AFETY FEATURE.S (ESF) SYSTEMS DEFINED
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Page 6 of 15 Revision 7 6.1.1 ENGINEERED SAFETY FEATURES (ESF) MATERIALS 6.2 CONTAINMENT SYSTEMS 6.2.1 CONTAINMENT FUNCTIONAL DESIGN DESCRIPTION 6.2.2 CONTAINMENT ISOLATION SYSTEM (CIS) 6.2.3 CONTAINMENT CONFORMANCE TO 10 CFR 50 APPENDIX J -
LEAKAGE TESTING 6.2.4 CIS VENTILATION VALVES ISOLATION AND VACUUM RELIEF 6.2.5 CONTAINMENT SPHERE INTEGRITY REQUIREMENTS 6.2.6 CONTAINMENT VISUAL EXAMINATION REQUIREMENTS 6.2.7 CONTAINMENT LEAKAGE TESTING 6.2.8 CONTAINMENT ISOLATION SYSTEM DEPENDABILITY 6.2.9 SAFETY CIRCUIT OVERRIDES ANNUNCIATION 6.2.10 ENGINEERED SAFETY FEATURES (ESP) RESET CONTROLS 6.2.11 COMBUSTIBLE GAS CONTROL IN CONTAINMENT 6.2.12 CONTAINMENT VENTILATION 6.2.13 CONTAINMENT HEAT UP 6.3 EMERGENCY CORE COOLING / POST INCIDENT SYSTEM CCS/PIS) 6.3.1 ECCS/PIS CORE SPRAY, CORE SPRAY RECIRCULATION, AND ENCLOSURE SPRAYS DESIGN BASES 6.3.2 ECCS/PIS SYSTEM DESIGN 6.3.3 ECCS/PIS TESTS ANDINSPECTIONS 6.3.4 ECCS/PIS PERFORMANCE EVALUATION 6.3.5 10 CFR PART 50,50,46 AND APPENDIX K EXEMPTION 6.4 HABITABILITY SYSTEMS 6.4.1 PLANT SHIELDING FOR SERIOUS CORE DAMAGE ACCIDENTS 6.4.2 CONTROL ROOM HABITABILITY 6.4.3 CONTROL ROOM AIR CONDITIONING 6.4.4 CONTROL ROOM HEAT-UP TEST 6.5 EISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.6 IN3ERVICE INSPECTION OF CLASS 2 AND 3 COMPONENTS 67 MAIN STEAM ISOLATION VALVE SEAL LEAKAGE CONTROL SYSTEM 6.8 EMERGEhCY CONDENSER SYSTEM mCS) 6.8.1 EMERGENCY CONDENSER GENERAL CHARACTERISTICS AND CONTROL 6.8.2 EMERGENCY CONDENSER SYSTEM DESCRIPTION 6.8.3 EMERGENCY CONDENSER VENT MONITORS 6.8.4 EMERGENCY CONDENSER ANALYSES / EVALUATIONS
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5 Page 7 of 15 Re.ision 7 6.8.5 EMERGENCY CONDENSER OPERABIL!TY AND TESTING REQUIREMENTS 6.8.6 EMERGENCY CONDENSER HIGH POINT VENTS 6.9 REACTOR DEPRESSURIZATION SYSTEM (RDS) 6.9.1 REACTOR DEPRESSURIZATION SYSTEM DESIGN BASEC 6.9.2 REACTOR DEPRESSURIZATION SYSTEM DESCRIPTION 6.9.3 REACTOR DEPRESSURIZATION SYSTEM SURVE!LLANCE, TESTING AND INSPECTION 6.9.4 REACTOR DEPRESSURIZATION SYSTEM COMPLIANCE EVALUATION QMPTEP 7 INSTRUMENTATION AND CONTROLS 7.1 INSTRUMENT AND CONTROL (I&C) INTRODUCTION 7.1.1 PLANT SAFETY AND MONITORING SYSTEMS 7.1.2 OTHERINSTRUMENTATION AND CONTROLS 7.2 REACTOR PROTEC'iiON SYSTEM (RPS}
7.2.1 REACTOR PROTECTION SYSTEM DESCRIPTION 7.2.2 REACTOR PROTECTION SYSTEM RESPONSE TIME 7.2.3 REACTOR PROTECTION SYSTEM SENSORS 7.2.4 REACTOR MODE SELECTOR SWITCH 7.2.5 REACTOR PROTECTION SYSTEM POWER SOURCES AND ASSO'CIATED CONTROLS 7.2.6 REACTOR PROTECTION SYSTEM LOGIC UNIT AND POWER SWITCHES 7.2.7 REACTOR PROTECTION SYSTEM ANNUNCIATOR CONTROL UNITS AND OPEPATIONS RECORDER 7.2.8 REACTOR PROTECTION SYSTEM POST-TRIP REVIEW 7.2.9 REACTOR PROTECTION SYSTEM ISOLATION FROM NON-SAFETY SYSTEMS 7.3 NEUTRON MONITORING SYSTEM (NMS) s 7.3.1 NEUTRON MONITORING SYSTEM DESCRIPTION 7.3.2 SOURCE RANGE MONITORING (CHANNEL 6 AND 7) 7.3.3 POWER (WIDE) RANGE MONITORING (CHANNELS 1,2, AND 3) 7.3.4 FISSION COUNTERS (CHANNELS E AND 9) 7.3.5 IN-CORE FLUX MONITORING (CHANNELS 11 THROUGH 18) 7.4 ERQINEERED S AFETY FEATURES (ESF) INSTRUMENTATION AND CONTROL EVALUATIONS 7.4.1 ENGINEERED SAFETY FEATURES (ESF) SYSTEM CONTROL LOGIC AND DESIGN 7.4.2 EMERGENCY L )RE COOLING SYSTEM (ECCS) ACTUATION SYSTEM TESTING
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Revision 7 7.5 REACTOR PROTECTION SYSTEM AND ENGINEERED SAFETY FEATURES TESTING INCLUDING RESPONSE TIME TESTING 7.5.1 RPS & ESF TESTING, SEP TOPIC VI 10.A RESOLUTION 7.6 SYSTEM REOUIRED FOR S AFE SHUTDOWN 7,6.1 SAFE SHUTDOWN ST STEMS 7.6.2 ELECTRICAL, INSTRUMENTATION, AND CONTROLS FEATURES OF SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7,7 OTHER INSTRUMENTATION AND CONTROLS 7,7,1 -
REACTOR WATER LEVEL MONITORS IN THE REACTOR DEPRESSURIZATION SYSTEM 7.7.2 CONTAINMENT PRESSURE AND WATER LEVEL MONITORING SYSTEMS 7,7.3 INSTRUMENTATION TO DETECT INADEQUATE CORE COOLING 7.7.4 POSTACCIDENT SAMPLING 7.7.5 CONTAINMENT HIGH RANGE MONITOR CALIBRATION CONTROLS 7,7.6 -
STEAM DRUM AND REACTOR LEVEL INSTRUMENTS CHAPTER 8 ELECTRIC POWER 8,1 INTRODUCTION 8.1.1 OFFSITE POWER SYSTEMS 8.1.2 ONSITE AC POWER SYSTEMS 8.1.3 ONSITE DC POWER SYSTEMS 8.2 OFFSITh POWER SYSTEMS 8.2.1 FUNCTIONAL DESIGN DESCRIPTION 8.2.2 OFFSITE POWER FREQUENCY DECAY 8.2.3 DISTRIBUTION SYSTEM VOLTAGES AND DEGRADED GRID PROTECTION 8.3 ONSITE U POWER SYSTEM 8.3.1 FUNCTIONAL DESIGN DESCRIPTION 8.3.2 2400 VAC BUS i
8.3.3 480 VAC EUSES 8.3.4 EMERGENCY DIESEL GENERATOR 8.3.5 STANDBY DIESEL GENERATOR 8.4 ONSITE DC POWER SYSTEM 8.4.1 STATION BATTERY SYSTEM
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Page 9 of 15 Revision 7 8.4.2 ALTERNATE SHUTDOWN BATTERY SYSTEM 8.4.3 RDS UNINTERRUPTIBLE POWER SUPPLIES 8.4.4 DIESEL STARTING SYSTEMS 8.5 ELECTRICAL PENETRATIONS ASSEMBLIES CHAPTER 9: AUXILIARY SYSTEMS 9.1 FUEL STO_RA SE AND HANDLING 9.1,1 NEW FUEL STORAGE 9.1.2 SPENT FUEL POOL SYSTEM (SFP) 9.1.3 SPENT FUEL POOL COOLING, CLEANUP, AND MAKEUP SYSTEMS 9.1.4 FUEL HANDLING SYSTEMS (FHS) 9.1.$
OVERHEAD LOAD HANDLING / HEAVY LOAD
SUMMARY
9.1.6 HEAVY OBJECT MOVEMENT 9.1,7 CASK MOVEMENT / DROP ANALYSES 9.2 WATER SYSTEMS 9.2.1 SERVICE WATER SYSTEM 9.2.2 COOLING WATER FOR REACTOR AUXILIARIES 9.2.3 DEMINERALIZED WATER SYSTEM 9.2.4 WELL WATER SYSTEM (WWS) AND DOMESTIC WATER SYSTEM (DWS) 9.2.5 SANITARY WATER SERVICES 9.2.6 ULTIMATE HEAT SINK 9.2.7 CONDENSATE STORAGE FACILITIES 9.2.8 BIOLOGICAL CONTROL SYSTEM 9.3 PROCESS AUXILIARIES 9.3.1 COMPRESSED AIR SYSTEM 9.3.2 PROCESS SAMPLING SYSTEM 9.3.3 EQUIPMENT AND FLOORDRAINAGE SYSTEM 9.3.4 STANDBY LIQUID CONTROL SYSTEM 9.4 IIEATING AND VENTILATION SYSTEM (VAS) 9.4.1 CONTROL ROOM VENTILATION SYSTEM 9.4.2 SPENT FUEL POOL VENTILATION SYSTEM 9.4.3 RADWASTE AREA VENTILATION SYSTEM 9.4.4 TURBINE AND SERVICE BUILDING VENTILATION SYSTEM 9.4.5 ENGINEERING SAFETY FEATURES VENTILATIOM SYSTEM 9.4.6 CONTAINMENT SPHERE VENTILATION SYSTEM
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Page 10 of 15 Revision 7 9.5 OTHER AUX 1LIARY SYSTEMS 9.5.1 FIRE PROTECTION SYS TEM (FPS) GENERAL 9.5.2 COMMUNICATIONS (COM) AND WARNING SYSTEMS 9.5.3 EMERGENCY LIGHTING SYSTEMS 9.5.4 DIESEL FUEL OIL STORAGE 9.5.5 EMERGEtJCY DIESEL GENERATOR AND DIESEL FIRE PUMP PROTECTIVE TRIPS 9.5.6 EMERGENCY DIESEL GENERATOR ALARM AND CONTROL CIRCUITRY 9.5.7 EMERGENCY DIESEL GENERATOR COOLING WATER 9.6 ALTERNATE SHUTDOWN (ASD) SYSTEM i
9.6.1 ALTERNATE SHUTDOWN SYSTEh. GENERAL t
9.C.2 ALTERNATE SHUTDOWN SYSTEM DESCRIPTION 9.6.3 POST. FIRE SHUTDOWN CAPABILITY 9.6.4 ALTERNATE SHUTDOWN CAPABILITY CHAPTER 10: STEAM AND POWER CONVERSION SYSTEM 10.1 STEAM AND POWER CONVERSION SYSTEMS
SUMMARY
DESCRIPTIQH 10.1,1 TURBINE AND MAIN STEAM CONTROL 10.1.2 TURBINE PROTECTION DEVICES 10.1.3 HEAT BALANCE 10.2 TURBINE GENERATOR SYSTEM EQS) 10.2.1 TURBINE GENERATOR DESIGN BASES AND DESCRIPTION 10.2.2 TURBINE GENERATOR CONTROL 10.2.3 TURBINE BYPASS VALVE AND CONTROL SYSTEM 10.2.4 SECONDARY SYSTEM INSTABILITIES 10.2.5 TURBINE ROTOR DISC INTEGRITY AND OVERSPEED PROTECTION 10.2.6 TURBII,'E STOP VALVE 10.3 MAIN STEAM SYSTEM (MSS) 10.3.1 MAIN STEAM SYSTEM DESIGN BASES 10.3.2 MAIN STEAM SYSTEM DESCRIPTION 10.3.3 MSIV CLOSURE AT POWER 10.3.4 RUPTURE OF MAIN STEAM LINE I
10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEMS 10.4.1 MAIN CONDENSER 10.4.2 MAIN CONDENSER EVACUATION SYSTEM / AIR EJECTOR SYSTEM (AES) 10.4.3 MINE SEAL AND LUBE OIL SYSTEM (SLO)
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^"2 Page 11 of 15 Revision 7 10.4.4 CIRCULATING WATER SYSTEM (CWS) 10.4.5 CONDENSATE AND MAKE UP DEMINERALIZERS 10.4.6 CONDENSATE DEMINERALIZER RESIN REPLACEMENT 10.4.7_
CONDENSATE SYSTEM (CDS) AND FEEDWATER SYSTEM (FWS)
CHAPTER 11: RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE TERMS 11.1.1 ACTIVAT!ON PRODUCTS 11.1.2 FISSION PRODUCTS 11.1.3 HIGH INTEGRITY CONTAINER (HIC) RESIN FIRE Il.2 LIOUID WASTE MANAGEMENT SYSTEM 11.2.1 DESIGN BASES 11.2.2 SYSTEM DESCRIPTION 11.2.3 RADIOACTIVE RELEASES 11.3 GASEOUS WASTE MANAGEMENT SYSTEM i1.3.1 DESIGN BASES 11.3.2 SYSTEM DESCRIPTION 11.3.3 RADIOACTIVE RELEASES 11.4 SOLID WASTE MANAGEMENT SYSTEM 11.4.1 DESIGN BASES 11.4.2 SYSTEM DESCRIPTION 11.4.3 RADIOACTIVE SHIPMENTS 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5.1 DESIGN BASES L
11 5.2 SYSTEM DESCRIPTION I
11.6 DISCHARGE CANAL DREDGING MANAGEMENT l
CHAPTER 12: RADIATION PROTECIIDE j
12.1 ENSURING OCCUPATIONAL ALARA 12.1.1 POLICY CONSIDERATIONS 12.1.2 DESIGN CONSIDERATIONS 12.1.3 OPERATIONAL CONSIDERATIONS l
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l Page 12 of15 Revision 7 12.2 ItADIATION SOURCES 12.2.1 CONTAINED SOURCES 12.2.2 AIRBORNE SOURCES 12.3 RADIATION PROTECTION DESIGN FEATURES 12.3.1 FACILITY DESIGN FEATURES 12.3.2 SHIELDING 11.3.3 VENTILATION 12.3.4 AREA AND AIRBORNE RADIATION MONITORING INSTRUMENTATION 12.4 DOSE ASSESSMENT 12.5 HEAL 7" PHYSICS PROGRAM 12.5.1 ORGANIZATION 12.5.2 EQUIPMENT, INSTRUMENTATION AND FACILITIES 12.5.3 PROCEDURES CHAPTER 13 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE 13.1.1 MANAGEMENT AND TECHNICAL SUPPORT ORGANIZATION 13.1.2 OPERATING ORGAN 17ATION RESPONSIBILITIES 13.1.3 QUALIFICATIONS Of.4UCLEAR PLANT PERSONNEL 13.1.4 PLANT ADDITIONAL SUPPORT 13.1.5 SHIFT COMPOSITION 13.1.6 OVERTIME ulMITS AND GUIDELINES 13.2 TRAINING 13.2.1 Pt ANT AND SUPPORT STAFF TRAINING PROGRAMS q
13.3 EMERGENCY PLANNING r
13.3.1 SITE EMERGENCY PLAN 13.3.2 SITE EMERGENCY PLAN IMPLEMENTING PROCEDURES 13.4 REVIEW AND AUDIT 13.5 PLANT PROCEDURES 13.5.1 ADMINISTRATIVE PROCEDURES 13.5.2 PLANT OPERATING PROCEDURES 13.5.3 OPERATING PROCEDURAL SAFEGUARDS 13.5.4 MEASURES TO PREVENT OPERATING ERROR I
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- Revision 7 13.5.5i OTHERPROCEDURES 13.61 INDUSTRIAL SECURITY.
- 13.6.1 SECURITY PLAN :
13.6.2-SAFEGUARDS CONTINGENCY PLAN -
13.6.3 ^ SUITABILITY TRAINING AND QUALIFICATION PLAN: -
CHAPTER 14 INITIAL RESEARCH AND DEVELOPMENT PROGRAM 14.1 = INITIAL RESEARCH AND DEVELOPMENT PROGRAM -
~ 14.1.1 - DEVELOPMENT PROGRAM OBJECTIVES -
- 14.1.2 > DEVELOPMENT PROGRAM SCOPE
- 14.2 SUBSEOUENT RESEARCH AND DEVELOPMENT PROGRAMS '
- 14.2.1 - FUEL RELATED RESEARCH
- 14.2.2 - COBALT PRODUCTION :
CHAPTER 15 ACCIDENT ANALYSES 15.0 CALCULATIONAL METHODS AND INPUT PARAMETERS
!15,0,1 INTRODUCTION =
15.0.2 PLANT THERMAL-HYDRAULIC ANALYSIS -
-15.0.3 CORE THERMAL-HYDRAULIC ANALYSIS '
15.0.4 MINIMUM CRITICAL POWER RATIO (MCPR) :
15.0.5 EVALUATION OF INCREASED SCRAM TIME REQUIREMENTS.
15.
0.6 REFERENCES
15.1 INCREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM 15.1.1 DECREASEIN FEEDWATERTEMPERATURE
-15.1.2 INCREASEIN FEEDWATER FLOW 4/
'15.1.3 INCREASEIN STEAM FLOW 15.2 i DECREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM 15.2.1 -LOSS OF EXTERNAL ELECTRIC LOAD -
15.2.2 TURBINE TRIP WITHOUT BYPASS 15.2.3 LOSS OF CONDENSERVACUUM 15.2.4 INADVERTENT CLOSURE OF MAIN STEAM ISOLATION VALVE 15.2.5 STEAM PRESSURE REGULATOR MALFUNCTION OR FAILURE 15.2.6 LOSS OF AC POWER 15.2.7 LOSS OF NORMAL FEEDWATER
Page 14 of 15 Revision 7 l
l 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW 15.3.1 LOSS OF FORCED RECIRCULATION FLOW 15.3.2 PUMP TRIP OR FLOW CONTROLLER MALFUNCTION 15.3.3 RECIRCULATION PUMP SElZURE 4
15.3.4 RECIRCULATION PUMP SHAFT BREAK 15.
3.5 REFERENCES
a 15.4 REACTIVITY AND POWER DISTRIBUTION ANOMAllES 15.4.1 CONTROL ROD MISOPERATION CONTROL ROD WITHDRAWAL 15.4.2 START UP OF AN IDLE RECIRCULATION PUMP 15.4.3 INADVERTENT LOADING AND OPERATION OF A FUEL ASSEMBLYIN AN IMPROPER POSITION 15.4.4 SPECTRUM OF ROD DROP ACCIDENTS 15.4.5 FLOW CONTROLLER MALFUNCTION CAUSING AN INCREASE IN CORE FLOW RATE 15.5 INCREASE IN REACTOR COOLANT INVENTORY 15.5.1 INADVERTENT OPERATION OF ECCS THAT INCREASES REACTOR COOLANTINVENTORY 15,6 DECREASE IN REACTOR COOLANT INVENTORY 4
15.6.1 INADVERTENT OPENING OF A SAFETY / RELIEF VALVE 15.6.2 RADIOLOGICAL CONSEQUENCES OF FAILURE OF SMALL LINES CARRYING PRIMARY COOLANT OUTSIDE CONTAINMENT 15.6.3 RADIOLOGICAL CONSEQUENCES OF A MAIN STEAM LINE FAILURE OUTSIDE CONTAINMENT 15.6.4 LOSS OF COOLANT ACCIDENT 15.7 RADIO / CTIVE RELEASE FROM A SUBSYSTEM OR COMPONENT 15.7.1 RADIOLOGICAL CONSEQUENCE OF FUEL DAMAGING A CIDENTS 15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM 15.
8.1 INTRODUCTION
15.8.2 ANALYSIS 15.8.3 LOW LEVEL TRANSIENTS 15.8.4 HIGH. PRESSURE TRANSIENT WITH LIMITED FEEDWATER 15.8.5 HIGH PRESSURE TRANSIENTS WITHOUT FEEDWATER 15,8.6 LIQUID POISON SYSTEM 15.8.7 CONTAINMENT RESPONSE TO ATWS EVENTS 15.
8.8 REFERENCES
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V I Page 15 of 15 1 Revision 71 15.9 SINGLE LOOP OPERATION 1 15.9.11 LOSS OF COOLANT ACCIDENT "
- 15.9.2 ANTICIPATED TRANSIENTS 15.
9.3 REFERENCES
15.10 DECOMMISSIONING ACCILENT CONSIDERATIONS s
- 15.10.1 L INTRODUCTION 15.10.2 ACCIDENTS INVOLVING FUEL :
.15.10.3 EXTERNALEVENTS
- 15,10.4 NON FUEL RELATED DECOMMISSIONING ACCIDENTS 15.
10.5 REFERENCES
CHAPTER 16 TECHNICAL SPECIFICATIONS CHAPTER 17 OUALITY ASSURANCE CHAPTER 18 HUMAN F, ACTORS ENGINFFRING 18.1 CONTROL ROOM DESIGN REVIEW (CRQEl 18.1.1 CRDR BACKGROUND 18.1.2 FINAL CONTROL ROOM DESIGN REVIEW
SUMMARY
REPORT 18.1.3 CRDR RESOLUTION-18.2 ' S AFETY PARAMETER DISPLA" SYSTEM (SPDS).
1 18.2.1 SPDS BACKGROUND 18.2.2 CRITICAL SAFETY FUNCTIONS (CSF) 18.2.3 SPDS/CSF RESOLUTION 18.3 EMERGENCY RESPONSE CAPABILITY l8.3.1 EMERGENCY RESPONSE CAPABILITY BACKGROUND '
18.3.2 EMERGENCY RESPONSE FACILITIEF (ERF) 18.3.3 EP,F RESOLUTION 4
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