ML20128L741
ML20128L741 | |
Person / Time | |
---|---|
Site: | Big Rock Point File:Consumers Energy icon.png |
Issue date: | 10/08/1996 |
From: | Fenech R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML20128L746 | List: |
References | |
NUDOCS 9610150178 | |
Download: ML20128L741 (37) | |
Text
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O Consumers M M N$ W Ftt Power MERM Robert A Fenech Mce President Nuclear Operations l Site Offices: 277SO Blue Star Memorial Highway, covert MI 49043 * (616) 764-8913. Ext 0210
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October 8, 1996 l Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - REVISION 6 TO THE 5 UPDATED FINAL HAZARDS SUNNARY REPORT (FHSR)
In accordance with 10 CFR 50.71 one original and ten copies of this submittal as specified in 10 CFR 50.4 are enclosed. This revision to our Updated Final Hazards Summary Report (FHSR) is submitted on a replacement page basis with a
" slash" typed in the right hand margin indicating the area changed and
" Revision 6" in the upper right-hand corner. Pages without " slashes" were affected by pagination only. Also attached is a List of Effective Pages and an Index of the Chapters, followed by the page replacement.
!./tA Robert A Fenech Vice President of Nuclear Operations CC: Administrator, Region III, USNRC NRC Project Manager - NRR, USNRC NRC Resident Inspector - Big Rock Point Plant ATTACHMENT 9610150170 961000 5 PDR ADOCK 0500 15u033 .
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~ ATTACHMENT 1 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 LIST OF EFFECTIVE PAGES Submitted October 8, 1996 l
22 Pages
FINAL HAZARDS
SUMMARY
REPORT Page 1 of 22 LIST OF EFFECTIVE PAGES CHAPTER 1 - INTRODUCTION AND GENERAL PURPOSES 1.2-1 Original 1.2-2 Revision 3 1.2-3 Original 1.2-4 Original 1.3-1 Original 1.4-1 Original 1.5-1 Original 1.5-2 Original 1.5-3 Original 1.5-4 Original 1.6-1 Revision 5 1.7-1 Original CHAPTER 2 - SITE CHARACTERISTICS 2.1-1 Revision 4 2.1-2 Revision 4 2.1-3 Revision 4 2.1-4 Revision 4 2.1-5 Revision 4 2.1-6 Revision 4 2.1-7 Revision 4 2.1-8 Revision 4 2.1-9 Original i 2.1-10 Revision 4 2.1-11 Revision 4 1 2.1-12 Revision 4 l 2.2-1 Revision 4 '
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FINAL HAZARDS
SUMMARY
REPORT Page 2 of 22 LIST OF EFFECTIVE PAGES CHAPTER 2 - SITE CHARACTERISTICS 2.4-7 Original 2.5-1 Original 2.5-2 Original 2.5-3 Original 2.5-4 Original 2.5-5 Original 2.5-6 Original 2.5-7 Revision 5 2.5-8 Original 2.5-9 Original 2.5-10 Original 2.5-11 Original 2.5-12 Original 2.5-13 Original 2.5-?4 Original 2.5-15 Original 2.5 15 Original 2 ;-17 Original 2.5-18 Original 2.5-19 Original 2.5-20 Original 2.5-21 Original 2.5-22 Original 2.5-23 Original ,
2.5-24 Revision 4 1 2.5-25 Original CHAPTER 3 - DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS 3.1-1 Original 3.1-2 Original 3.2-1 Original 3.2-2 Original 3.2-3 Original 3.2-4 Original 3.2-5 Original 3.2-6 Original 3.2-7 Original 3.2-8 Original 1.2-9 Original 3.2-10 Original 3.2-11 Original 3.2-12 Original 3.2-13 Original 3.2-14 Original 3.2-15 Original 3.2-16 Original 3.2-17 Original 3.2-18 Original 3.2-19 Original 3.2-20 Original 3.2-21 Original
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FINAL HAZARDS
SUMMARY
REPORT Page 3 of 22 LIST OF EFFECTIVE PAGES 3.2-22 Original 3.2-23 Original
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3.8-1 Original 3.8-2 Original 3.8-3 Original 3.8-4 Original 3.8-5 Original 3.8-6 Original 3.8-7 Original 3.8-8 Original 3.8-9 Original 3.8-10 Original 3.8-11 Original !
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FINAL HAZARDS
SUMMARY
REPORT Page 4 of 22 LIST OF EFFECTIVE PAGES 3.8-19 Original 3.8-20 Original 3.8-21 Revision 4 3.8-22 Original 3.9-1 Revision 5 3.9-2 Revision 5 3.9-3 Revision 1 3.9-4 Revision 3 3.9-5 Revision 3 3.9-6 Revision 5 3.9-7 Revision 5 3.9-8 Revision 5 3.9-9 Revision 5 3.9-10 Revision 5 3.9-11 Revision 5 3.10-1 Original ,
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3.11-4 Original 3.11-5 Original l 3.11-6 Original l 3.11-7 Original 1 3.11-8 Original CHAPTER 4 - REACTOR 4.1-1 Original 4.1-2 Original 4.2-1 Original 4.2-2 Original 4.2-3 Original 4.2-4 Original 4.2-5 Original 4.2-6 Original 4.3-1 Original 4.3-2 Original 4.3-3 Original 4.3-4 Original 4.3-5 Original 4.3-6 Original l 4.3-7 Original !
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4.4-1 Original I 4.4-2 Original 4.4-3 Revision 1 1 4.5-1 Revision 1 4.6-1 Original 4.6-2 Original 4.6-3 Original 4.6-4 Original 4.7-1 Original 4.7-2 Original
.l FINAL HAZARDS
SUMMARY
REPORT Page 5 of 22 LIST OF EFFECTIVE PAGES 4.7-3 Original 4.7-4 Original ,
4.7-5 Revision 5 l 4.7-6 Original l 4.7-7 Original 4.7-8 Original 4.7-9 Original 4.7-10 Original 4.7-11 Original 4.7-12 Original 4.7-13 Original 4.7-14 Original 4.7-15 Original 4.7-16 Original 4.7-17 Original 4.7-18 Revision 3 4.7-19 Revision 3 4.7-20 Revision 4 4.7-21 Revision 4 4.7-22 Original 4.7-23 Original 4.7-24 Revision 3 4.7-25 Revision 3 4.7-26 Revision 3 4.7-27 Revision 4 4.7-28 Revision 4 4.7-29 Original 4.7-30 Original 4.7-31 Original 4.7-32 Original 4.7-33 Original 4.7-34 Original 4.8-1 Original 4.8-2 Original 4.8-3 Original 4.8-4 Original 4.8-5 Revision 3 4.8-6 Original 4.8-7 Original 4.8-8 Original 4.8-9 Original CHAPTER 5 - REACTOR COOLANT AND CONNECTED SYSTEMS 5.1-1 Original 5.2-1 Original 5.2-2 Original 5.2-3 Original 5.2-4 Original 5.2-5 Original 5.2-6 Original 5.2-7 Original 5.2-8 Original 5.2-9 Original 5.2-10 Original
A FINAL HAZARDS
SUMMARY
REPORT Page 6 of 22 LIST OF EFFECTIVE PAGES i 5.2-11 Original 5.2-12 Revision 6 /
, 5.2-13 Original 5.2-14 Original 5.2-15 Revision 6 / i 5.2-16 Original I 5.2-17 Revision 4 I 5.2-18 Revision 3 '
5.2-19 Revision 3 l 5.2-20 Revision 3 l 5.3-1 Original 5.3-2 Original 5.3-3 Original 5.3-4 Original 5.3-5 Original 5.3-6 Original 5.3-7 Original 5.3-8 Original 5.3-9 Original 5.3-10 Original 5.3-11 Original 5.3-12 Original 5.3-13 Original 5.3-14 Original l 5.3-15 Original 5.3-16 Original 5.3-17 Original 5.3-18 Revision 1 5.3-19 Revision 1 5.3-20 Revision 4 5.3-21 Revision 6 / l 5.3-22 Revision 4 5.3-23 Revision 1 !
5.3-24 Revision 1 5.3-25 Revision 5 5.3-26 Revision 5 5.3-27 Revision 1 5.3-28 Revision 5 5.3-29 Revision 5 5.3-30 Revision 5 5.3-31 Revision 5 5.3-32 Revision 5 5.4-1 Original 5.4-2 Original 5.4-3 Original 5.4-4 Original 5.4-5 Original 5.4-6 Revision 3 5.4-7 Revision 1 5.4-8 Revision 2 5.4-9 Revision 1 5.4-10 Revision 1 5.4-11 Original 5.4-12 Original 5.4-13 Original
FINAL HAZARDS
SUMMARY
REPORT Page 7 of 22 LIST OF EFFECTIVE PAGES 5.4-14 Original 5.4-15 Original 5.4-16 Original 5.4-17 Revision 6 /
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CHAPTER 6 - ENGINEERED SAFETY FEATURES (ESF) 6.1-1 Original 6.1-2 Original 6.1-3 Original 6.1-4 Original 6.1-5 Original 6.2-1 Original 6.2-2 Original 6.2-3 Original 6.2-4 Original 6.2-5 Original 6.2-6 Original 6.2-7 Original 6.2-8 Original 6.2-9 Original 6.2-10 Original 6.2-11 Revision 6 /
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FINAL HAZARDS
SUMMARY
REPORT Page 8 of 22 LIST OF EFFECTIVE PAGES 6.2-17 Original 6.2-18 Original 6.2-19 ' Revision 4 6.2-20 Original 6.2-21 Original 6.2-22 Original 6.2-23 Original 6.2-24 Revision 3 6.2-25 Original 6.2-26 Original
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FINAL HAZARDS
SUMMARY
REPORT Page 9 of 22 LIST OF EFFECTIVE PAGES 6.8-7 Revision 1 6.8-8 Revision 1 6.8-9 Revision 1 6.8-10 Revision 1 6.8-11 Revision I l 6.8-12 Revision 1 6.8-13 Revision 1 6.8-14 Revision 1 6.8-15 Revision 1 6.8-16 Revision 1 6.9-1 Original 6.9-2 Original 6.9-3 Original 6.9-4 Original 6.9-5 Original 6.9-6 Original 6.9-7 Original 6.9-8 Original 6.9-9 Revision 6 /
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FINAL HAZARDS
SUMMARY
REPORT Page 10 of 22 i LIST OF EFFECTIVE PAGES l l
7.2-12 Revision 2 7.2-13 Revision 2 i 7.2-14 Revision 1 l
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, 7.7-3 Original 7.7-4 Original CHAPTER 8 - ELECTRIC POWER 8.1-1 Revision 6 /
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FINAL HAZARDS
SUMMARY
REPORT Page 11 of 22 LIST OF EFFECTIVE PAGES 8.2-14 Revision 6 /
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f FINAL HAZARDS
SUMMARY
REPORT Page 12 of 22 LIST OF EFFECTIVE PAGES i
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l FINAL HAZARDS
SUMMARY
REPORT Page 13 of 22 l l
LIST OF EFFECTIVE PAGES 9.4-1 Original l 9.4-2 Original 9.4-3 Original l 9.4-4 Revision 4 j 9.4-5 Original -
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9.6-1 Original 9.6-2 Original 9.6-3 Original 9.6-4 Original 1 9.6-5 Original i 9.6-6 Original l 9.6-7 Original 9.6-8 Original 9.6-9 Revision 4 CHAPTER 10 - STEAM POWER CONVERSION SYSTEMS 10.1-1 Original !
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FINAL HAZARDS
SUMMARY
REPORT Page 14 of 22 i
I LIST OF EFFECTIVE PAGES 10.2-2 Original 10.2-3 Original 10.2-4 Original 10.2-5 Revision 1 10.2-6 Revision 4 10.2-7 Revision I i 10.2-8 Revision 3 '
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10.4-22 Original l CHAPTER 11 - RADI0 ACTIVE WASTE MANAGEMENT 11.1-1 Revision 4 11.1-2 Original 11.1-3 Revision 5 11.1-4 Original 11.1-5 Original 11.1-6 Original 11.1 ^ Original q 11.1-8 Original i 11.2-1 Original 11.2-2 Original 11.2-3 Original 11.2-4 Original 11.3-1 Original 11.3-2 Original ;
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FINAL HAZARDS SUMARY REPORT Page 15 of 22 LIST OF EFFECTIVE PAGES 11.5-3 Revision 4 l 11.5-4 Original l 11.5-5 Revision 4 l 11.5-6 Original l 11.5-7 Original 11.5-8 Revision 4 11.5-9 Original 11.5-10 Revision 4 11.5-11 Original 11.6-1 Revision 1 CHAPTER 12 - RADIATION PROTECTION 12.1-1 Revision 4 l 12.1-2 Original l 12.1-3 Original 12.1-4 Revision 4 12.2-1 Original 12.2-2 Revision 4 12.2-3 Revision 4 12.3-1 Revision 5 /
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CHAPTER'13 - CONDUCT OF OPERATIONS 13.1-1 Revision 6 / ,
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FINAL HAZARDS
SUMMARY
REPORT Page 16 of 22 LIST OF EFFECTIVE PAGES 13.5-9 Original 13.5-10 Original 13.5-11 Revision 1 13.5-12 Revision 3 13.5-13 Revision 3 13.6-1 Original CHAPTER 14 - INITIAL RESEARCH AND DEVELOPMENT PROGRAM 14.1-1 Original 14.1-2 Original 14.1-3 Original 14.2-1 Original 14.2-2 Original CHAPTER 15 - ACCIDENT ANALYSIS -
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FINAL HAZARDS
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REPORT Page 17 of 22 LIST OF EFFECTIVE PAGES 15.1-9 Original 15.1-10 Original 15.1-11 Original 15.1-12 Original 15.1-13 Original 15.1-14 Original 15.1-15 1riginal 15.1-16 Original 15.1-17 Original 15.1-18 Original 15.1-19 Original 15.1-20 Original 15.1-21 Original 15.1-22 Original 15.1-23 Original 15.1-24 Original 15.1-25 Original 15.1-26 Original 15.1-27 Original 15.1-28 Original 15.1-29 Original 15.1-30 Original 15.1-31 Original 15.1-32 Original 15.1-33 Original 15.1-34 Original 15.1-35 Original 15.1-36 Original 15.1-37 Original 15.1-38 Original 15.1-39 Original 15.1-40 Original 15.1-41 Original 15.1-42 Original 15.1-43 Original 15.1-44 Original 15.1-45 Original 15.1-46 Original 15.1-47 Original 15.1-48 Original 15.2-1 Original 15.2-2 Original 15.2-3 Original 15.2-4 Original 15.2-5 Original 15.2-6 Original 15.2-7 Original 15.2-8 Original 15.2-9 Original 15.2-10 Original 15.2-11 Original 15.2-12 Original 15.2-13 Original 15.2-14 Original 15.2-15 Original
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REPORT Page 18 of 22 LIST OF EFFECTIVE PAGES 15.2-16 Original '
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FINAL HAZARDS
SUMMARY
REPORT Page 20 of 22 LIST OF EFFECTIVE PAGES 15.6-7 Original 15.6-8 Original 15.6-9 Original 15.6-10 Original 15.6-11 Original 15.6-12 Original 15.6-13 Original 15.6-14 Original 15.6-15 Original 15.6-16 Original 15.6-17 Original 15.6-18 Original 15.6-19 Original 15.6-20 Original 15.6-21 Original 15.6-22 Original 15.6-23 Original 15.6-24 Original 15.6-25 Original 15.6-26 Original 15.6-27 Original 15.6-28 Original 15.6-29 Original 15.6-30 Original 15.6-31 Original 15.6-32 Original 15.6-33 Original 15.6-34 Original 15.6-35 Original 15.6-36 Original 15.6-37 Original 15.6-38 Original 15.6-39 Original 15.6-40 Original 15.6-41 Original 15.6-42 Original 15.6-43 Original 15.6-44 Original 15.6-45 Original 15.6-46 Original 15.6-47 Original 15.6-48 Original 15.6-49 Original 15.7-1 Original 15.7-2 Revision 4 15.7-3 Original 15.7-4 Original 15.7-5 Original 15.7-6 Original 15.7-7 Original 15.7-8 Original 15.7-9 Original 15.7-10 Original 15.7-11 Original 15.7-12 Original
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l l FINAL HAZARDS
SUMMARY
REPORT Page 21 of 22 LIST OF EFFECTIVE PAGES 15.8-1 Revision 2 15.8-2 Revision 1 l 15.8-3 Revision 3 15.8-4 Revision 1 l 15.8-5 Revision 1 15.8-6 Revision 4 15.8-7 Revision 1 15.8-8 Revision 1 15.8-9 Revision 1 15.8-10 Revision 1 15.8-11 Revision 1 15.8-12 Revision 1 15.8-13 Revision 1 15.8-14 Revision 1 15.8-15 Revision 1 15.8-16 Revision 1 15.8-17 Revision 1 15.8-18 Revision 1 15.8-19 Revision 1 15.8-20 Revision 1 15.8-21 Revision 1 15.8-22 Revision 1 15.8-23 Revision 1 15.8-24 Revision 1 15.8-25 Revision 1 15.8-26 Revision 1 15.8-27 Revision 1 15.8-28 Revision 1 15.8-29 Revision 1 I 15.8-30 Revision 1 1 15.8-31 Revision 1 15.8-32 Revision 1 15.8-33 Revision 1 15.8-34 Revision 1 15.8-35 Revision 1 15.8-36 Revision 1 15.8-37 Revision 1 15.8-38 Revision 1 15.9-1 Original 15.9-2 Original 15.9-3 Original 15.9-4 Original 15.9-5 Original 15.9-6 Original 15.9-7 Original 15.9-8 Original 15.9-9 Original 15.9-10 Original 15.9-11 Original 15.9-12 Original 15.9-13 Original 15.9-14 Original 15.9-15 Original
FINAL HAZARDS SUNNARY REPORT Page 22 of 22 LIST OF EFFECTIVE PAGES CHAPTER 16 - TECHNICAL SPECIFICATIONS 16.1-0 Original ;
CHAPTER 17 - QUALITY ASSURANCE 17.1-0 Original CHAPTER 18 - HUMAN FACTORS ENGINEERING 18.1-1 Original 18.1-2 Original 18.1-3 Revision 1 18.2-1 Original 18.2-2 Original 18.2-3 Revision 1 18.3-1 Original '
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l ATTACHMENT 2 CONSUMERS POWER COMPANY BIG ROCK P0 INT PLANT DOCKET 50-155 INDEX OF CHAPTERS Submitted October 8, 1996 13 Pages
Page 1 of 13 Revision 6 1E911 CHAPTER 1: INTRODUCTION AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
AND PURPOSE OF THIS REPORT
1.2 BACKGROUND
AND PLANT DESCRIPTION 1.
2.1 BACKGROUND
1.2.2 PLANT DESCRIPTION 1.3 SCOPE. CHARACTER. AND CONCLUSIONS OF THIS REPORT 1.3.1 SCOPE 1.3.2 CHARACTER 1.
3.3 CONCLUSION
S 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 1.5 RE0VIREMENTS FOR FURTHER TECHNIC /.L INFORMATION 1.5.1 INTEGRATED ASSESSMENT OF ISSUES 1.5.2 PROBABILISTIC RISK ASSESSMENT (PRA) 1.5.3 SYSTEMATIC EVALUATION PROGRAM (SEP) 1.6 MATERIAL INCORPORATED BY REFERENCE 1.7 DRAWINGS AND OTHER DETAILED INFORMATION CHAPTER 2: SITE CHARACTERISTICS 2.1 GE0 GRAPHY 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 INDUSTRIAL. 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 2.3.2 METEOROLOGICAL MONITORING 2.3.3 ATMOSPHERIC TRANSPORT AND DIFFUSION ESTIMATES
Page 2 of 13 Revision 6 2.4 HYDROLOGY 2.4.1 HYDROLOGIC DESCRIPTION 1 2.4.2 FLOODS !
2.4.3 PROBABLE MAXIMUM FLOODING (PMF) 2.4.4 PROBABLE MAXJMUM PRECIPITATION (PMP) 2.4.5 LOSS OF ULTIMATE HEAT SINK (VHS) 2.4.6 FLOOD EMERGENCY OPERATIONAL REQUIREMENTS 2.5 GE0 LOGY. SEISM 0 LOGY AND GE0 TECHNICAL ENGINEERING 2.5.1 BASIC GE0 LOGIC AND SEISMIC INFORMATION 2.5.2 VIBRATORY GROUND MOTION 2.5.3 SURFACE FAULTING 2.5.4 STABILITY OF SUBSURFACE MATERIALS AND FOUNDATIONS 2.5.5 STABILITY OF SLOPES 2.5.6 EMBANKMENTS AND DAMS CHAPTER 3: DESIGN OF STRUCTURES. COMPONENTS. E0VIPMENT AND SYSTEMS 3.1 CONFORMANCE WITH NRC GENERAL DESIGN CRITERIA 1
3.2 CLASSIFICATION OF STRUCTURES. COMPONENTS. AND SYSTEMS 3.2.1 SEISMIC CLASSIFICATION 3.2.2 QUALITY GROUP CLASSIFICATION 3.3 WIND AND TORNADO LOADING 1 3.3.1 WIND LOADINGS 3.3.2 TORNADO LOADINGS 3.4 WATER LEVEL (FLOOD) DESIGN 3.4.1 FLOOD PROTECTION 3.4.2 ANALYTICAL AND TEST PROCEDURES 3.4.3 INSERVICE INSPECTION OF WATER CONTROL STRUCTURES .
1 3.5 MISSILE PROTECTION 3.5.1 MISSILE EFFECTS 3.6 PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING 3.6.1 POSTULATED PIPING FAILURES IN FLUID SYSTEMS OUTSIDE OF CONTAINMENT 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 3.7.4 SEISMIC INSTRUMENTATION
Page 3 of 13 Revision 6 3.8 DESIGN OF CATEGORY I STRUCTURES 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 SYSTEMS AND COMP 0NENTS 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 SsRVEILLANCE PROGRAM 3.9.5 REACTOR PRESSURE VESSEL INTERNALS 3.10 SEISMIC OVALIFICATION OF SEISMIC CATEGORY I INSTRUMENTATION AND ELECTRICAL E0VIPMENT 3.11 ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL E0VIPMENT 3.11.1 ELECTRICAL EQUIPMENT QUALIFICATION (EEQ) 3.11.2 ELECTRICAL QUALIFICATION (EQ) PROGRAM CERTIFICATION 3.11.3 EEQ PROGRAM
SUMMARY
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 4.2.1 DESIGN BASIS 4.
2.2 DESCRIPTION
AND DESIGN DRAWINGS 4.2.3 DESIGN EVALUATION 4.2.4 TESTING AND INSPECTION PLAN 4.3 NUCLEAR DESIGN 4.3.1 DESIGN BASIS 4.3.2 NUCLEAR DESIGN DESCRIPTION 4.3.3 ANALYTICAL METHODS 4.4 THERMAL AND HYDRAULIC DESIGN 4.4.1 CORE FLOW AND PRESSURE DROP 4.4.2 HYDRAULIC STABILITY 4.4.3 NRC BULLETIN 88-07, POWER OSCILLATIONS IN BWR'S
Page 4 of 13 Revision 6 4.5 OPERATION WITH LESS THAN ALL LOOPS 4.6 REACTIVITY CONTROL SYSTEMS 4.6.1 REACTIVITY CONTROL SYSTEMS OPERABILITY REQUIREMENTS 4.7 CONTROL R0D DRIVE SYSTEMS 4.7.1 CONTROL R00 BLADE ASSEMBLIES 4.7.2 CONTROL R00 DRIVES 4.7.3 CONTROL R0D DRIVE MATERIALS OF CONSTRUCTION 4.7.4 CONTROL R0D DRIVE HYDRAULIC CONTROL SYSTEM 4.7.5 CONTROL R0D SYSTEM INSTRUMENTATION AND CONTROL 4.7.6 CONTROL R0D SYSTEM PERFORMANCE REQUIREMENTS 4.7.7 BWR SCRAM SYSTEM PIPE BREAKS 4.7.8 CONTROL R0D DRIVE SUPPORT STRUCTURE 4.7.9 ACTIVITY OF COBALT-60 PRODUCED IN THE CONTROL RODS AND ACTIVATED CONTROL R0D TRANSFER ANALYSIS 4.7.10 CONTROL R00 DRIVE FAILURE MODES AND EFFECTS ANALYSIS 4.7.11 CONTROL R0D DRIVE ANALYSIS 0F OPERATOR ERRORS 4.8 LIOUID POIS0N SYSTEM (LPS) 4.8.1 LPS PURPOSE AND
SUMMARY
DESCRIPTION 4.8.2 LPS DESIGN CHARACTERISTICS 4.8.3 LPS INSTRUMENTS AND CONTROLS 4.8.4 LPS EFFECTIVENESS 4.8.5 LPS FQUIVALENT CONTROL CAPACITY 4.8.6 INTE;TY OF LPS PRESSURE ISOLATION VALVES 4.8.7 LP: INJECTION GAS PRESSURE 4.8.8 LPS PERFORMANCE REQUIREMENTS CHAPTER 5: REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5.1
SUMMARY
DESCRIPTION 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE B0UNDARY 5.2.1 COMPLIANCE WITH CODES AND CODE CASES 5.2.2 OVERPRESSURE PROTECTION 5.2.3 REACTOR COOLANT PRESSURE B0UNDARY MATERIALS 5.2.4 INSERVICE INSPECTION AND TESTING 0F REACTOR COOLANT PRESSURE B0UNDARY 5.2.5 DETECTION OF LEAKAGE THROUGH REACTOR COOLANT PRESSURE B0UNDARY (RCPB) 5.2.6 THERPa.L STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTtMS 5.3 REACTOR VESSEL 5.3.1 GENERAL DESCRIPTION 5.3.2 REACTOR VESSEL PRESSURE / TEMPERATURE LIMITS l 5.3.3 REACTOR VESSEL INTEGRITY i I
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l Page 5 of 13 Revision 6 5.4 COMPONENT AND SUBSYSTEM DESIGN !
5.4.1 REACTOR COOLANT RECIRCULATING PUMPS '
5.4.2 STEAM DRUM AND STEAM DRUM RELIEF VALVES i 5.4.3 REACTOR COOLANT PIPING AND VALVES 5.4.4 NUCLEAR STEAM SUPPLY SYSTEM 5.4.5 RESIDUAL 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 6: ENGINEERED SAFETY FEATURES (ESF) 6.1 ENGINEERED SAFETY FEATURES (ESF) SYSTEMS DEFINED l l
6.1.1 ENGINEERED SAFETY FEATURES (ESF) MATERIALS 6.2 CONTAINMENT SYSTEMS 6.2.1 CONTAINMENT FUNCTIONAL DESIGN DESCRIPTION 6.2.2 CON 1AINMENT ISOLATION SYSTEM (CIS) 6.2.3 CONTAINMENT CONFORMANCE TO 10 CFR 50 APPENDIX J - ,
LEAKAGE TESTING i 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 (ESF) RESET CONTROLS 6.2.11 COMBUSTIBLE GAS CONTROL IN CONTAINMENT 6.2.12 CONTAINMENT VENTILATION i 6.2.13 CONTAINMENI HEAT-UP i 1
6.3 EMERGENCY CORE COOLING / POST INCIDENT SYSTEM (ECCS/ Pill 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 AND INSPECTIONS 6.3.4 ECCS/PIS PERFORMANCE EVALUATION 6.3.5 10 CFR PART 50, 50.46 AND APPENDIX K EXEMPTION 6.4 HABJJABILITY 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 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS 6.6 INSERVICE INSPECTION OF CLASS 2 AND 3 COMP 0NENTS 6.7 MAIN STEAM ISOLATION VALVE SEAL LEAKAGE CONTROL SYSTEM
I Page 6 of 13 Revision 6 i
6.8 _ EMERGENCY CONDENSER SYSTEM (ECS) 6.6.1 EMERGENCY CONDENSER GENERAL CHARACTERISTICS AND CONTROL l 6.8.2 EMERGENCY CONDENSER SYSTEM DESCRIPTION 6.8.3 EMERGENCY CONDENSER VENT MONITORS j 6.8.4 EMERGENCY CONDENSER ANALYSES / EVALUATIONS i 6.8.5 EMERGENCY CONDENSER OPERABILITY AND TESTING REQUIREMENTS 6.8.6 EMERGENCY CONDENSER HIGH POINT VENTS )
i 6.9 REACTOR DEPRESSURIZATION SYSTEM (RDS) 6.9.1 REACTOR DEPRESSURIZATION SYSTEM DESIGN BASES 6.9.2' REACTOR DEPRESSURIZATION SYSTEM DESCRIPTION 6.9.3 REACTOR DEPRESSURIZATION SYSTEM SURVEILLANCE, TESTING AND INSPECTION
, 6.9.4 REACTOR DEPRESSURIZATION SYSTEM COMPLIANCE EVALUATION CHAPTER 7: INSTRUMENTATION AND CONTROLS 7.1 INSTRUMENT AND CONTROL (I&C) INTRODUCTION 7.1.1 PLANT SAFETY AND MONITORING SYSTEMS I
- 7.1.2 OTHER INSTRUMENTATION AND CONTROLS l 7.2 REACTOR PROTECTION SYSTEM (RPS) 7.2.1 REACTOR PROTECTION SYSTEM DESCRIPTION l 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 ASSOCIATED CONTROLS 7.2.6 REACTOR PROTECTION SYSTEM LOGIC UNIT AND POWER SWITCHES i
7.2.7 REACTOR PROTECTION SYSTEM ANNUNCIATOR CONTROL UNITS AND OPERATIONS RECORDER 7.2.8 REACTOR PROTECTION SYSTEM POST-TRIP REVIEW 7.2.9 REACTOR PROTECTION SYSTEM ISCLATION FROM NON-SAFETY SYSTEMS 7.3 NEUTRON MONITORING SYSTEM (NMS) a 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 8 AND 9)
- 7.3.5 IN-CORE FLUX MONITORING (CHANNELS 11 THROUGH 18) 7.4 ENGINEERED SAFETY FEATURES (ESF) INSTRUMENTATION AND CONTROL
- EVALUATIONS 4 7.4.1 ENGINEERED SAFETY FEATURES (ESF) SYSTEM CONTROL LOGIC AND DESIGN 7.4.2 EMERGENCY CORE COOLING SYSTEM (ECCS) ACTUATION SYSTEM TESTING
l Page 7 of 13 Revision 6 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 REQUIRED FOR SAFE SHUTDOWN 7.6.1 SAFE SHUTDOWN SYSTEMS 7.6.2 ELECTRICAL, INSTRUMENTATION, AND CONTROLS FEATURES OF l SYSTEMS REQUIRED FOR SAFE SHUTDOWN i 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 l l
8.1 INTRODUCTION
8.1.1 0FFSITE POWER SYSTEMS 8.1.2 ONSITE AC POWER SYSTEMS 8.1.3 ONSITE DC POWER SYSTEMS 8.2 0FFSITE POWER SYSTEMS 8.2.1 FUNCTIONAL DESIGN DESCRIPTION 8.2.2 0FFSITE POWER FREQUENCY DECAY 8.2.3 DISTRIBUTION SYSTEM VOLTAGES AND DEGRADED GRID PROTECTION 8.3 ONSITE AC POWER SYSTEM 8.3.1 FUNCTIONAL DESIGN DESCRIPTION 8.3.2 2400 VAC BUS 8.3.3 480 VAC BUSES 8.3.4 EMERGENCY DIESEL GENERATOR 8.3.5 STANDBY DIESEL GENERATOR 8.4 ONSITE DC POWER SYSTEM 8.4.1 STATION BATTERY SYSTEM 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
Page 8 of 13 Revision 6 CHAPTER 9: AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING >
9.1.1 NEW FUEL STORAGE 9.1.2 SPENT FUEL P00L SYSTEM (SFP) 9.1.3 SPENT FUEL P0OL COOLING, CLEANUP, AND MAKEUP SYSTEMS 9.1.4 FUEL HANDLING SYSTEMS (FHS) 9.1.5 OVERHEAD LOAD HANDLING / HEAVY LOAD
SUMMARY
9.1.6 HEAVY OBJECT MOVEMENT i 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 I 2
9.2.3 DEMINERALIZED WATER SYSTEM i 9.2.4 WELL WATER SYSTr 'WWS) AND DOMESTIC WATER SYSTEM (DWS) 9.2.5 SANITARY WATER L. VICES 9.2.6 ULTIMATE HEAT SINK 9.2.7 CONDENSATE STORAGE FACILITIES 9.3 PROCESS AUXILIARIES
- 9.3.1 COMPRESSED AIR SYSTEM J
9.3.2 PROCESS SAMPLING SYSTEM 9.3.3 EQUIPMENT AND FLOOR DRAINAGE SYSTEM
. 9.3.4 STANDBY LIQUID CONTROL SYSTEM 9.4 HEATING AND VENTILATION SYSTEM (VAS) 9.4.1 CONTROL ROOM VENTILATION SYSTEM 9.4.2 SPENT FUEL P0OL VENTILATION SYSTEM
!' 9.4.3 RADWASTE AREA VENTILATION SYSTEM 9.4.4 TURBINE AND SERVICE BUILDING VENTILATION SYSTEM 9.4.5 ENGINEERING SAFETY FEATURES VENTILATION SYSTEM 9.4.6 CONTAINMENT SPHERE VENTILATION SYSTEM i 9.5 OTHER AUXILIARY SYSTEMS I i
9.5.1 FIRE PROTECTION SYSTEM (FPS) GENERAL 9.5.2 COMMUNICATIONS (COM) AND WARNING SYSTEMS i 9.5.3 EMERGENCY LIGHTING SYSTEMS 9.5.4 DIESEL FUEL OIL STORAGE 9.5.5 EMERGENCY DIESEL GENERATOR AND DIESEL FIRE PUMP PROTECTIVE TRIPS 9.5.6 EMERGENCY DIESEL GENERATOR ALARM AND CONTROL CIRCU',TRY 9.5.7 EMERGENCY DIESEL GENERATOR COOLING WATER 9.6 ALTERNATE SHUTDOWN (ASD) SYSTEM 9.6.1 ALTERNATE SHUTDOWN SYSTEM GENERAL 9.6.2 ALTERNATE SHUTDOWN SYSTEM DESCRIPTION 9.6.3 POST-FIRE SHUTDOWN CAPABILITY 9.6.4 ALTERNATE SHilTDOWN CAPABILITY
l Page 9 of 13 Revision 6 CHAPTER 10: STEAM AND POWER CONVERSION SYSTEM 10.1 STEAM AND POWER CONVERSION SYSTEMS
SUMMARY
DESCRIPTION 10.1.1 TURBINE AND MAIN STEAM CONTROL 10.1.2 TURBINE PROTECTION DEVICES 10.1.3 HEAT BALANCE 10.2 TURBINE GENERATOR SYSTEM (TGS) 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 TURBINE 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 TURBINE SEAL AND LUBE OIL SYSTEM (SLO) 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: RADI0 ACTIVE WASTE MANAGEMENT 11.1 SOURCE TERMS 11.1.1 ACTIVATION PRODUCTS 11.1.2 FISSION PRODUCTS 11.2 LIOUID WASTE MANAGEMENT SYSTEM 11.2.1 DESIGN BASES 11.2.2 SYSTEM DESCRIPTION 11.2.3 RADI0 ACTIVE RELEASES 11.3 GASE0US WASTE MANAGEMENT SYSTEM 11.3.1 DESIGN BASES 11.3.2 SYSTEM DESCRIPTION 11.3.3 RADI0 ACTIVE RELEASES
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Page 10 of 13 Revision 6 11.4 SOLID WASTE MANAGEMENT SYSTEM 11.4.1 DESIGN BASES 11.4.2 SYSTEM DESCRIPTION 11.4.3 RADI0 ACTIVE SHIPMENTS 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5.1 DESIGN BASES ,
11.5.2 SYSTEM DESCRIPTION 1 11.6 DISCHARGE CANAL DREDGING MANAGEMENT CHAPTER 12: RADIATION PROTECTION 12.1 ENSURING OCCUPATIONAL ALARA 12.1.1 POLICY CONSIDERATIONS 12.1.2 DESIGN CONSIDERATIONS 12.1.3 OPERATIONAL CONSIDERATIONS 12.2 RADIATION SOURCES a
12.2.1 CONTAINED SOURCES ,
- 12.2.2 AIRBORNE SOURCES l 12.3 RADIATION PROTECTION DESIGN FEATURES l 12.3.1 FACILITY DESIGN FEATURES 12.3.2 SHIELDING 12.3.3 VENTILATION 12.3.4 AREA AND AIRBORNE RADIATION MONITORING INSTRUMENTATION 12.4 DOSE ASSESSMENT l 12.5 HEALTH 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 ORGANIZATION RESPONSIBILITIES 1
13.1.3 QUALIFICATIONS OF NUCLEAR PLANT PERSONNEL
- 13.1.4 PLANT ADDITIONAL SUPPORT
- 13.1.5 SHIFT COMPOSITION
. 13.1.6 OVERTIME LIMITS AND GUIDELINES 4
13.2 TRAINING 13.2.1 PLANT AND SUPPORT STAFF TRAINING PROGRAMS
Page 11 of 13 Revision 6 l
13.3 EMERGENCY PLANNING i 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 13.5.5 OTHER PROCEDURES 13.6 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 SUBSE0 VENT 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 PARAMEIERS 15.
0.1 INTRODUCTION
15.0.2 PLANT THERMAL - HYDRAULIC ANALYSIS !
15.0.3 CORE THERHAL - HYDRAULIC ANALYSIS 1 I
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 DECREASE IN FEEDWATER TEMPERATURE 15.1.2 INCREASE IN FEEDWATER FLOW 15.1.3 INCREASE IN STEAM FLOW l
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Page 12 of 13 Revision 6 15.2 QEfBIASE.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 CONDENSER VACUUM 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 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW 15.3.1 LOSS OF FORCED RECIRCULATION FLOW 15.3.2 PUMP iRIP OR FLOW CONTROLLER MALFUNCTION 15.3.3 RECIRCULATION PUMP SEIZURE 15.3.4 RECIRCULATION PUMP SHAFT BREAK 15.
3.5 REFERENCES
15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES 15.4.1 CONTROL ROD MIS 0PERATION - CONTROL R00 WITHDRAWAL
, 15.4.2 START-UP OF AN IDLE RECIRCULATION PUMP !
15.4.3 INADVERTENT LOADING AND OPERATION OF A FUEL ASSEMBLY IN AN IMPROPER POSITION l 15.4.4 SPECTRUM 0F R0D DROP ACCIDENTS
, 15.4.5 FLOW CONTROLLER MALFUNCTION CAUSING AN INCREASE IN CORE FLOW RATE
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15.5 INCREASE IN REACTOR COOLANT INVENTORY 1
15.5.1 INADVERTENT OPERATION OF ECCS THAT INCREASES 1 REACTOR COOLANT INVENTORY 15.6 DECREASE IN REACTOR COOLANT INVENTORY 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 i 15.6.3 RADIOLOGICAL CONSEQUENCES OF A MAIN STEAM LINE FAILURE OUTSIDE CONTAINMENT
, 15.6.4 LOSS OF COOLANT ACCIDENT 2
15.7 RADI0 ACTIVE RELEASE FROM A SUBSYSTEM OR COMP 0NENT 15.7.1 RADIOLOGICAL CONSEQUENCE OF FUEL DAMAGING ACCIDENTS 15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM ;
15.
8.1 INTRODUCTION
l 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.