ML20106G045
| ML20106G045 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1985 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0800, NUREG-0800-R05, NUREG-800, NUREG-800-R5, SRP-NUREG-0800, SRP-NUREG-800, NUDOCS 8502140198 | |
| Download: ML20106G045 (24) | |
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STANDARD REVIEW PLAN FOR THE REVIEW OF SAFETY-ANALYSIS REPORTS FOR NUCLEAR POWER PLANTS TABLE OF CONTE'NTS Applicable-Issued-SRP No.
Revision Year / Month INTRODUCTION.......................................
75/11 1
81/7 l-75/11 Table of Contents..................................
4 1
79/1 2
79/3 t
3 80/5 i
4 81/7 5
'84/12 l
Compilation of Branch Technical Positions..........
0' 81/7 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT
- 1. 8 Interfaces for Standard Design......
0 78/12 1
61/7 i
CHAPTER 2 SITE CHARACTERISTICS I
2.1.1 Site Location and Description.......
75/11 1
78/7 2
81/7 2.1.2 Exclusion Area Authority and 75/11 Control..........................
1 78/12 2
81/7 75/11 j
2.1. 3 Population Distribution.............
1 78/12 l
'2 81/7 2.2.1-2.2.2 Identification of Potential Hazards 75/11 in Site Vicinity.................,
1 78/7 2
81/7 75/11 2.2.3
' Evaluation of Potential Accidents...
1 78/12 2
81/7
-75/11 2.3.1 Regional Climatology................
1 78/4 2
81/7 75/11 2.3.2 Local Meteorology...................
1 78/4 2
81/7 1
2.3.3 Onsite Meteorological Measurements 75/11.
Programs..........................
i 1
78/5' 2
81/7 s.
i Rev. 5 - December 1 m
[
0800 R PDR
TABLE OF CONTENTS (Continued)
Applicable Issued SRP No.
Revision Year / Month Appendix A........
75/11 1
78/5 2
81/7 2.3.4 Snort-Term Diffusion Estimates For Accidental Atmospheric Releases.
75/11 1
81/7 2.3.5 Long-Term Dif fusion Estimates.....
75/11 1
78/5 2
81/7 75/11 2.4.1 Hydrologic Description 1
78/6 2
81/7 Appendix A............
75/11 1
78/6 2
81/7 75/11 2.4.2 Floods..............
1 78/6 2
81/7 2.4.3 Probable Maximum Flood (PMF) on Streams and Rivers 75/11 1
78/6 2
81/7 2.4.4 Potential Dam Failures....
75/11 1
78/6 2
81/7 2.4.5 Probable Maximum Surge and Seiche Flooding......
75/11 1
78/6 2
81/7 2.4.6 Probable Maximum Tsunami Flooding...
75/11 1
78/6 2
81/7 2.4.7 Ice Effects 75/11 1
78/5 2
81/7 2.4.8 Cooling Water Canals and Reservoirs............
75/11 1
78/6 2
81/7 75/11 2.4.9 Channel Diversions 1
78/6 2
81/7 75/11 2.4.10 Flood Protection Requirements.....
1 78/5 2
81/7 i
75/11 2.4.11 Cooling Water Supply................
1 78/5 2
81/7 2.4.12 Groundwater.......................
75/11 1
78/7 2
81/7 l
1 i
l 1
11 Rev. 5 - December 1984
~ ~.
-TABLE OF CONTENTS (Continued) l
' Applicable Issued-
}
SRP No.
Revision
. Year / Month:
2 BTP HMB/GSB 1..................
75/11 1
78/7 BTP HGEB 1.....................
2 81/7 2.4.13 iccidental Releases of Liquid.
Effluents in Cround and Surface Waters............................
75/11 1
-78/6
- t 2
81/7.
2.4.14 Technical. Specifications and Emergency Operation Requirements.....................
75/11 1.
78/6 2
81/7 2.5.1
. Basic Geologic and Seismic 75/11 i
Information.......................
1
'78/11.
2 81/7 75/11 2.5.2 Vibratory Ground Motion.............
1 81/7 2.5.3 Surface Faulting....................
75/11 1
78/11 2
81/7 1
2.5.4 Stability of Subsurface Materials and Foundations...................
75/11 1
78/11 2'
81/7 2.5.5 Stability of Slopes.................
75/11 1
78/11 2
81/7 CHAPTER 3 DESIGN OF STRUCTURES. COMPONENTS. EQUIPMENT. AND SYSTEMS 3.2.1 Seismic Classification..............
75/11 1
81/7 3.2.2 Systes Quality Group Classification...................
75/11 1
81/7 4
Appendix A (Formerly I
BTP RSB 3-1).................
75/11 1
81/7 Appendix B (Formerly BTP RSB 3-2).................
75/11 1
81/7 Appendix C..................
O None l
1 81/7
?
Apperdf" D...................
O None l
j.
1 81/7 75/11
. 3. 3.1 ~
Wind Loadings.......................
1 78/8 2
81/7 75/11
<\\
3.3.2 Tornado Loadings...................
1 78/8 2
81/7 111 Rev. 5 - December 1984
.--4
+
c
)
TABLE OF CONTENTS (Continued)
Applicable Issued SRP No.
Revision Year / Month 3.4.1 Flood Protection 75/11 1
78/3 2
81/7 3.4.2 Analysis Procedures.
75/11 1
None g
2 81/7 1
3.5.1.1 Internally Generated Missiles (Outside Containment) 75/11 1
78/4 2
81/7 3.5.1.2 Internally Generated Missiles (Inside Containment) 7/11 1
78/8 2
81/7 3.5.1.3 Turbine Missiles.......
75/11 1
78/7 2
81/7 3.5.1.4 Missiles Generated by Natural Phenomena 75/11 1
78/7 2
81/7 BTP AAB 3-2 75/11 1
None l
BTP ASB 3-2 2
81/7 3.5.1.5 Site Proximity Missiles (Except Aircraft)..
75/11 1
81/7 3.5.1.6 Aircraft Hazards 75/11 1
None l
2 81/7 3.5.2 Structures, Systems, and Components to be Protected from Externally Generated Missiles 75/11 1
78/3 2
81/7 3.5.3 Barrier Design Procedures 75/11 1
81/7 l
Appendix A.......
0 81/7 3.6.1 Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment...........
75/11 t
1 81/7 1
BTP ASB-3-1 75/11 l
1 81/7 l
l 3.6.2 Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping.....
75/11 1
81/7 BTP MEB-3-1.........
75/11 1
81/7 iv Rev. 5 - December 1984
4 TA8tE OF CONTENTS'(Continued) j-_[N Applicable Issued
'3 SRP No.
Revision Year / Month 75/11 3.7.1 Seismic Design Parameters...........
1 81/7 75/11 3.7.2
. Seismic System Analysis.............
1 81/7 9
75/11
'3.7.3
' Seismic Subsystem Analysis..........
1 81/7 75/11
- 3. 7. 4 '
Seismic Instrumentation.............
1 81/7 75/11 3.8.1 Concrete Containment................
1 81/7 Appendix..........................
0 81/7~
l
- 3. 8. 2 '
Steel Containment..................
75/11 1
81/7 3.8.3 Concrete and Steel Internal.
Structures of Steel or Concrete 75/11 Containments......................
1 81/7 3.8.4 Other Seismic Category I 75/11 Structures.......................
.1 -
81/7
{
Appendix A......................
0-81/7 Appendix B.......................
0 81/7 Appendix C........
0 81/7 Appendix D.......................
0 81/7 s
3.8.5 Foundations........................
75/11 1
81/7 3.9.1 Special Topics for Mechanical 75/11 Components 1
78/4 2
81/7-3.9.2 Dynamic Testing and Analysis of Systems, Components, and 75/11 j
Equipment.......
i 1
78/8~
-2 81/7 i
3.9.3
-ASME Code Class 1, 2, and 3 Components, Component Supports, 75/11 j
and Core Support Structures.......
1 81/7
. Appendix A........................
,0 81/7 1
84/4 l
I 3.9.4 Control Rod Drive Systems.........
75/11 1
81/7 2
84/4 l-3.9.5 Reactor Pressure Vessel Internals...
75/11' 1
.78/4 2
81/7 3.9.6 Inservico Testing of Pumps and 75/11 Valves............................
1 78/4 1
2 81/7 i.
v Rev. 5 - December 1984 :
TABLE OF CONTENTS (Continued)
Applicable Issued SRP No.
Revision Year / Month 3.10 Seismic Qualification of Category I Instrumentation and Electrical Equipment 75/11 1
78/4 2
81/7 3.11 Environmental Design of Mechanical and Electrical Equipment.....
75/11 1
78/7 2
81/7 CHAPTER 4 REACTOR 4.2 Fuel System Design........
75/11 1
78/9 2
81/7 0
81/7 l
Appendix A 75/11 4.3 Nuclear Design...
1 78/4 2
81/7 BTP CPB 4.3-1 75/11 1
78/4 2
81/7 4.4 Thermal and Hydraulic Design 75/11 1
81/7 Appendix 75/11 1
81/7 4.5.1 Control Rod Drive Structural Materials........
75/11 1
78/1 2
81/7 4.5.2 Reactor Internal and Core Support Materials.........
75/11 1
78/1 2
81/7 4.6 Functional Design of Control Rod Drive System 75/11 1
81/7 CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5.2.1.1 Compliance with the Codes and Standard Rule, 10 CFR S 50.55a...........
75/11 1
78/1 2
81/7 5.2.1.2 Applicable Code Cases........
75/11 1
78/1 2
81/7 5.2.2 Overpressure Protection......
75/11 1
81/7 0
81/7 BTP RSB 5-2 i
5.2.3 Reactor Coolant Pressure Bouncary Materials......................
75/11 l
1 78/4 l
2 81/7 1
vi Rev. 5 - December 1984 1
i TABLE OF CONTENTS (Continued) i Applicable Issued
\\
SRP No.
Revision Year / Month:
BTP MTEB 5-7....................
75/11 I
1 78/4 2
81/7 4
I 5.2.4 Reactor Coolant Pressure Boundary Inservice Inspection and Testing...
75/11 1
81/7 5.2.5 Reactor Coolant Pressure' Boundary Leakage Detection..................
75/11 1
81/7 75/11 5.3.1 Reactor Vessel Materials'............
l-1 81/7 i
~
~
75/11 5.3.2 Pressure-Temperature Limits..........
I 1-81/7 1
BTP MTEB 5-2...................
75/11 1
81/7 4
5.3.3 Reactor Vessel Integrity............
~----
75/11
{'
1 81/7 j
5.4 Preface...........................
75/11 1
81/7 4
5.4.1.1 Pump Flywheel Integrity (PWR).......
.75/11 1
81/7 1
5.4.2.1 Steam Generator Materials............
75/11 1
78/11 j -
2 81/7-1 BTP MTEB 5-3..................
75/11 1
78/11 2
81/7 s
I l
5.4.2.2 Steam Generator Tube Inservice Inspection.......................
75/11-j 1
81/7 5.4.6 Reactor Core Isolation Cooling System (BWR).....................
75/11 j
l 1
78/3 4
2 81/7 i
3 84/4 l
75/11-5.4.7 Residual Heat Removal (RHR) System...
1 78/8 2
81/7 1
3 84/4 l
75/11-BTP RSB 5-1..........
1 78/8
+
2 81/7 l
5.4.8 Reactor Water Cleanup System i
75/11 (BWR)...........................
1 78/7-2 81/7 i
75/11-l 5.4.11 Pressurizer Relief Tank.............
l
-1 78/8 2
81/7 j
5.4.12 ~
Reactor Coolant System High Point Vents.................
0 81/7 i
vi l -.
Rev. 5 - December 1984 4
.e-,--,.r----
.,.,1, e-,-
.c
-s,
+r
TABLE OF CONTENTS (Continued)
Applicable Issued SRP No.
_ Revision Year / Month CHAPTER 6 ENGINEERED SAFETY FEATURES 6.1.1 Engineered Safety Features Materials.
75/11 1
78/12 2
81/7 BTP MTEB 6-1....
75/11 1
78/12 2
81/7 6.1.2 Protective Coating Systems (Paints) - Organic Materials 75/11 1
78/12 2
81/7 6.2.1 Containment Functional Design 75/11 1
78/4 2
81/7 6.2.1.1.A PWR Dry Containments, Including Subatmospheric Containments.....
75/11 1
78/8 2
81/7 6.2.1.1.8 Ice Condenser Containments...
75/11 1
78/8 2
81/7 6.2.1.1.C Pressure-Suppression Type BWR Containments.....
75/11 1
78/5 2
78/8 3
79/2 4
81/7 5
83/1 6
84/8 Appendix I 0
79/2 1
81/7 Appendix A 2
83/1 l
0 83/1 1
Appendix B 6.2.1.2 Subcompartment Analysis....
75/11 1
78/8 2
81/7 6.2.1.3 Mass and Energy Release Analysis for Postulated Loss-of-Coolant 75/11 Accidents 1
81/7 6.2.1.4 Mass and Energy Release Analysis for Postulated Secondary System Pipe 75/11 Ruptures.....
1 81/7 6.2.1.5 Minimum Containment Pressure Analysis for Emergency Core Cooling System Performance 75/11 Capability Studies...
1 78/8 2
81/7 75/11 BTP CSB 6-1 1
78/8 2
81/7 viii Rev. 5 - December 1984 l
l
TABLE OF CONTENTS-(Continued)
- ("
Applicable Issued SRP No.
Revision Year / Month 6.2.2 Containment Heat Removal Systems....
- 75/11 1
78/4 2
78/8 3
81/7 6.2.3 Secondary Containment Functional Design............................
75/11 1
78/8 2
81/7 75/11 BTP CSB 6-3....................
1 78/8 2
81/7 6.2.4 Containment Isolation System........
75/11 I -
1 78/5 2
81/7 BTP CSB 6-4....................
~
75/11 1
1 78/5 l
2 81/7 J
6.2.5 Combustible Gas Control in Containment.......................
75/11 1
78/5 2
81/7 Appendix A.....................
75/11 1
78/5 2
81/7 BTP CSB 6-2..................
75/11 1
78/5 2
81/7 6.2.6 Containment Leakage Testing.........
75/11 1
78/9 2
81/7 6.2.7 Fracture Prevention of Containment Pressure Boundary.................
0 81/7 1
6.3 Emergency Core Cooling System.......
75/11 1
81/7 2
84/4 l
BTP RSB 6-1...................
-75/11 1
81/7 6.4 Control Room Habitability Systems...
75/11.
i 1
78/12.
1 2
81/7 Appendix A.....................
75/11 1
78/12-2 81/7 6.5.1 ESF Atmosphere Cleanup Systems......
75/11 1
78/7 2
81/7 6.5.2 Containment Spray as a Fission Product cleanup System............
75/11^
1 81/7 1x Rev. 5 - December 1984
TABLE OF CONTENTS (Continueo) j Applicable Issued SRP No.
Revision Year / Month 6.5.3 Fission Product Control Systems 75/11 and Structures 1
78/7 2
81/7 6.5.4 Ice Condenser as a Fission Product Cleanup System.....
75/11 1
78/4 2
81/7 6.6 Inservice Inspection of Class 2 and 3 Components...
75/11 1
81/7 6.7 Main Steam Isolation Valve Leakage Control System (BWR)........
75/11 1
78/3 2
81/7 CHAPTER 7 INSTRUMENTATION AND CONTROLS 7.1 Instrumentation and Controls -
Introduction...........
75/11 1
78/7 2
81/7 3
84/2 l
Table 7-1 Acceptance Criteria and Guidelines for Instrumen-tation and Controls Systems Important to Safety 75/11 1
78/7 2
81/7 3
84/2 Table 7-2 TMI Action Plan Requirements for Instrumenta-tion and Controls Systems Important to Safety 0
81/7 Appendix A 0
81/7 1
84/2 Appendix B.
0 81/7 7.2 Reactor Trip System....
75/11 1
78/7 2
81/7 Appendix A 75/11 1
78/7 2
81/7
- 7. 3 Engineered Safety Features Systems 75/11
[
1 78/7 l
2 81/7 Appendix A 75/11 1
78/7 2
81/7 7.4 Safe Shutdown Systems........
75/11 1
78/7 2
81/7 x
Rev. 5 - December 1984
TABLE OF' CONTENTS (Continued)
Applicable Issued SRP No.
Revision Year / Month Jnformation Sys' ems Important to
~ 7.5 t
Safety..........'...............
75/11 1-78/7
~2 81/7 r.
3 84/2 1l:
, 7. 6 _-
- Interlock' Systems Important to
- Safety............................
75/11 i
1
-78/7 2-81/7 l
' 7. 7 Control Systems.....................
75/11..
l' 78/7-2 81/7 j.
3 84/2 l.
{
Appendix 7-A - Branch Technical Positions-(ICSB)...
75/11-1 78/7 2
.81/7
' BTP ICSB 1 (DOR)..............
75/11 i
1 78/7
- 2 81/7 BTP ICSB' 3....................
.75/11 1
78/7 2
81/7 BTP ICSB 4 (PSB)..............
'75/11 1
78/7 2-81/7 75/11 BTP ICSB 5...................
1 78/7-j
- 2
- 81/7 i'
BTP ICSB 9....................
75/11 1
1 78/7:
~
i 2
81/7 BTP ICSB 12 75/11 1
78/7 2
81/7 i
BTP ICSB 13'....................
75/11 1
78/7 i
2-81/7 i
j BTP ICSB 14....................
75/11 l
1 78/7-2 81/7 i
-75/11 BTP ICSB 16.!..................
1 1
78/7 2
81/7 BTP ICSB 19....................
75/11.
1 78/7 j-2 81/7 75/11.
BTP ICSB 20....................
f
. 1 78/7 2
81/7 I
75/11 BTP ICSB 21....................
j 1
78/7 2
81/7
- i l
I l
' xi l Rev. 5 December 1984-2
~
4
-.--,,-,w.
-w=
s.
---w-w+4 ir e-,
,-,reer
...m.
,,,m
,..,-..w my w.
VABLE OF CONTENTS (Continued)
Applicable Issued j
SRP No.
._Rawlsion Year / Month 75/11 BTP ICSB 22................
1 78/7 2
81/7 75/11 BTP ICSB 25.......
1 78/7 2
81/7 BTP ICSB 26.................
75/11 1
78/7 2
81/7 Appendix 7-B General Agenda, Station Site Visits.
75/11 1
81/7 CHAPTER 8 ELECTRIC POWER 8.1 Electric Power-Introduction 75/11 1
78/4 2
81/7 Table 8-1 Acceptance Criteria and Guidlelines for Electric Power Systems 75/11 1
78/4 2
81/7 8.2 Offsite Power System............
75/11 1
78/4 2
81/7 3
83/7 Appendix A 0
83/7 l
8.3.1 A-C Power Systems (Onsite).
75/11 1
78/5 2
81/7 Appendix.....
2 81/7 8.3.2 D-C Power Systems (Onsite)..
75/11 1
78/4 2
81/7 Appendix 8A Branch Technical Positions (PSB)....
75/11 1
78/6 2
81/7 BTP ICSB 2 (PSB).
75/11 l
1 78/6 l
2 81/7 BTP ICSB 4 (PSB).............
75/11 1
78/6 2
81/7 BTP ICSB 8 (PSB).............
75/11 1
78/6 2
81/7 BTP ICSB 11 (PSB) 75/11 1
78/6 2
81/7 BTP ICSB 15 (PSB)...
75/11 1
78/6 2
81/7 xii Rev. 5 - December 1984
a.
~.
T.
,9 4
TABLE OF CONTENTS (Continued)
Applicable Issued-SRP No.
Revision Year / Month A/
BTP ICSB 17 (PSB)..............
---~
75/11~
1 78/6 r
2
'81/7 75/11 BTP ICSB 18 (PSB)..............
1
.78/6 2
81/7-s-
~
BTP ICSB 21 (PSB)..............
-75/11' t
+
1 78/6 2
81/7 s
BTP PSB 1'......................
0:
81/7 BTP PSB 2......................
0 81/7
- Appendix 88 General Agenda, Station Site Visits 0
81/7 CHAPTER 9 AUXILIARY SYSTEMS.
75/11 j!
- 9.1.1 New Fuel Storage...................
1 78/2 j!.
2:
81/7 f
9.1.2 Spent Fuel Storage...............
75/11 1
78/3.
.)
2 79/3 l
3 '
81/7
(
t 9.1.3 Spent Fuel Pool Cooling and Cleanup
- [m System..........................
75/11 t
1 81/7 4
i 9.1. 4 Light-Load Handling System (Related to Refueling).....
75/11 4 --
1 78/4 l
2 81/7-75/11 l
BTP ASB 9-1....................
1 78/4 4
2 81/7 l
9.1.5 Overhead Heavy Load Handling Systems..........................
0 81/7 75/11 9.2.1 Station Service Water System........
)
a 1
78/3
[
2 81/7-t 3
84/4 l.
1 9.2.2 Reactor Auxiliary Cooling Water 75/11 Systems...........................
1 81/7 2
84/4 l
75/11 9.2.3 Domineralized Water Makeup System...
1 78/3
-2 81/7 75/11
- 9. 2.4 -
Potable and Sanitary Water Systems..
1 78/3' t -
1 2
81/7 75/11 9.2.5 Ultimate Heat Sink..................
1 78/3
~2 81/7 f'
xiii Rev. 5 - December 1984
}
1.
TABLE OF CONTENTS (Continued)
Applicable Issued SRP No.
Revision Year / Month BTP ASB 9-2 75/11 1
78/3 2
81/7 9.2.6 Condensate Storage Facilities 75/11 1
78/3 2
81/7 9.3.1 Compressed Air System 75/11 1
81/7 9.3.2 Process and Post-Accident Sampling 75/11 Systems 1
78/7 2
81/7 9.3.3 Equipment and Floor Drainage System 75/11 1
78/3 2
81/7 9.3.4 Chemical and Volume Control System (PWR) (Including Boron Recovery System) 75/11 1
78/3 2
81/7 9.3.5 Standby Liquid Control System (BWR)..
75/11 1
78/3 2
81/7 9.4.1 Control Room Area Ventilation System 75/11 1
78/3 2
81/7 9.4.2 Spent Fuel Pool Area Ventilation System 75/11 1
78/3 2
81/7 l
9.4.3 Auxiliary and Radwaste Area l
Ventilation System 75/11 t
1 78/3 2
81/7 9.4.4 Turbine Area Ventilation System 75/11 1
78/3 2
81/7 9.4.5 Engineered Safety Feature Ventilation System 75/11 1
78/3 2
81/7 9.5.1 Fire Protection Program...
75/11 1
76/5 2
78/3 3
81/7 BTP CMEB 9.5.1 76/5 1
78/3 2
81/7 Appendix A 76/11 l
1 81/7 l
xiv Rev. 5 - December 1984
.= -,
i
- TABLE OF' CONTENTS (Continued) -
-.s Applicable Issued s
'SRP No.
Revision Year / Month
\\'-
9.5.2
'75/11 Communications Systems.............
1 78/4 2
81/7 9.5.3 Lighting Systems....................
75/11 4
1 78/4 2
81/7-9.5.4 Emergency Diesel Engine Fuel Oil 75/11 Storage and Transfer System.......
4 1
78/4 2
81/7 t
9.5.5 Emergency Diesel Engine-Cooling.
75/11 Water System......................
1 78/4 2
81/7 9.5.6 Emergency Diesel Engine Starting-System.'..........................
75/11 1
78/4 2
81/7 9.5.7 Emergency Diesel Engine Lubrication System..........................
75/11' 1
78/4 2'
81/7 i
- 9. 5. 8 -
Emergency Diesel Engine Combustion 75/11 Air Intake and Exhaust System.....
1 78/4 2
81/7 i
CHAPTER 10 STEAM AND POWER CONVERSION SYSTEM l
10.2 Turbine Generator..................
75/11 1
78/4 2
81/7 10.2.3 Turbine Disk Integrity............
75/11 i
1 81/7 4
10.3 Main Steam Supply System............
75/11 1
78/4 2
81/7 3
84/4 l
10.3.6 Steam and Feedwater System 75/11 Materials.....................
1 78/4
-2 81/7 10.4.1 Main Condensers.....................
75/11 1
78/4 2
81/7 75/11 10.4.2 Main Condenser Evacuation System....
l' 78/7 2
81/7 10.4.3 Turbine Gland Sealing System 75/11 1
78/I 2
81/7 75/11 10.4.4 Turbine Bypass System..............
1 78/4 2
81/7 xv Rev. 5 - December 1984
,,1 m,, -
..n.
1,___.~-_,.
TABLE OF CONTENTS (Continued)
Applicable Issued SRP No.
Revision Year / Month 10.4.5 Circulating Water System.
75/11 1
78/3 2
81/7 10.4.6 Condensate Cleanup System 75/11 1
78/3 2
81/7 10.4.7 Condensate and Feedwater System.
75/11 1
78/3 2
81/7 3
84/4 l
75/11 BTP ASB 10-2...
1 78/3 2
81/7 3
84/4 l
10.4.8 Steam Generator Blowdown System 75/11 (PWR) 1 78/7 2
81/7 10.4.9 Auxiliary Feedwater System (PWR) 75/11 1
78/4 2
81/7 BTP ASB 10-1 75/11 1
78/4 2
81/7 CHAPTER 11 RADI0 ACTIVE WASTE MANAGEMENT 11.1 Source Terms...
75/11 1
78/7 2
81/7 11.2 Liquid Waste Management Systems 75/11 1
78/7 2
81/7 11.3 Gaseous Waste Management Systems 75/11 1
78/7 2
81/7 0
81/7 BTP ETSB 11-5...
11.4 Solid Waste Management Systems 75/11 1
78/7 2
81/7 BTP ETSB 11-3 75/11 1
78/7 2
81/7 0
81/7 Appendix 11.4-A.
11.5 Process and Effluent Radiological Monitoring Instrumentation and 75/11 Sampling Systems....
1 78/7 l
2 70/4 l
3 81/7 l
l Appendix 11.5-A..
0 79/4 1
81/7 l
xvi Rev. 5 - December 1984
1 l
TA8LE OF CONTENTS (Continued)
-fN-Applicable.
Issued' f
i~
SRP No.
Revision Year / Month
\\
1 Q:
CHAPTER 12 ~ RADIATION PROTECTION 12.1
' Assuring That Occupational Radiation Exposures are As Low As Is' 75/11 Reasonably Achievable...........
1 78/5 2
81/7 12.2 Radiation Sources..................
75/11 1
78/5 2
~81/7-12.3-12.4 Radiation Protection Design Features.......................
75/11 1
la?
2 81/7 II) '
75/11 12.4 Dose Assessment....................
1 78/5 12.5 Operational Radiation Protection 75/11 Program.............
1 78/5 2
81/7 CHAPTER 13 CONDUCT OF OPERATIONS 13.1.1 Management and Technical Support Organization....................
75/11 1
79/4 2
81/7 13.1.2-13.1.3 Operating Organization..............
75/11 1
79/4 2
81/7 13.1.3(2)
Qualifications of Nuclear Plant Personnel.......................
75/11 1
79/4 13.2(3)
Training............................
-75/11 1
78/3 2
81/7 l
13.2.1 Reactor Operator Trai ning...........
0 81/7 13.2.2 Training For Non-Licensed Plant Staff.............................
0 81/7 75/11 13.3 Emergency Planning..................
1 78/3 2
81/7 13.4 Operational Review................
75/11 1
79/2
'2 81/7 13.5(4)
Plant Procedures....................
75/11-1 78/3 2
81/7 l
(1)SRP Section has been combined with SRP Section 12.3.
\\
(2)SRP Section has been combined with SRP Section 13.1.2.
(3)SRP Section has been replaced by SRP Sections 13.2.1 and 13.2.2.'
(4)SRP Section has been replaced by SRP Sections 13.5.1 and 13.5.2.
xvii Rev. 5 - December 1984
~
TABLE OF CONTENTS (Continued)
Applicable Issuea SRP No.
Revision Year / Month 13.5.1 Administration Procedures.....
0 81/7 13.5.2 Operating and Maintenance 0
81/7 Procedures.....
13.6 Physical Security....
75/11 2
81/7 CHAPTER 14 INITIAL TEST PROGRAM 14.1 Initial Plant Test Programs - PSAR 75/11 1
79/2 2
81/7 14.2 Initial Plant Test Programs - FSAR..
75/11 1
79/2 2
81/7 14.3 Standard Plant Designs, Initial Test Program - Final Design Approval 0
79/2 (FDA) 1 81/7 CHAPTER 15 ACCIDENT ANALYSIS 15.0 Introduction 75/11 1
78/8 2
81/7 l
15.1 INCREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM 15.1.1-15.1.4 Decrease in Feedwater Temperature, Increase in Feedwater Flow, I
Increase in Steam Flow, and Inadvertent Opening of a Steam Generator Relief or Safety Valve.
75/11 1
81/7 l
15.1.5 Steam System Piping Failures Inside and Outside of Containment 75/11 (PWR) l 1
78/8 2
81/7 l
Appendix A..
75/11 1
78/8 2
81/7 15.2 DECREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM 15.2.1-15.2.5 Loss of External Load Turbine Trip, Loss of Condenser Vacuum, Closure of Main Steam Isolation Valve (BWR), and Steam Pressure Regulatory Failure (Closed) 75/11 1
81/7 15.2.6 Loss of Nonemergency AC Power to the Station Auxiliaries 75/11 1
81/7 15.2.7 Loss of Normal Feedwater Flow 75/11 1
81/7 xviii Rev. 5 - December 1984
TABLE OF CONTENTS (Continued)'
- 7.c Applicable Issued i
SRP No,'
' Revision Year / Month 15.2.8 Feedwater System Pipe Breaks Inside and Outside Containment 75/11 (PWR)...........................
1 81/7 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE 15.3.1-15.3.2 Loss of Forced Reactor Coolant Flow Including Trip of Pump and Flow Controller Mal functions...........
75/11' 1
81/7 2
15.3.3-15.3.4 Reactor Coolant Pump Rotor Seizure and Reactor Coolant Pump Shaft Break............................
75/11 1
78/8 2
81/7 15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES 15.4.1 Uncontrolled Control Rod Assembly Withdrawal from a Subcritical d
75/11 or Low Power Startup Condition....
1 78/4 2
81/7 15.4.2 Uncontrolled Control Rod Assembly Withdrawal at Power............
75/11 s
1 78/4 2
81/7 15.4.3 Control Rod Misoperation (System 75/11 Malfunction or Operator Error) 1 78/4 2-81/7 15.4.4-15.4.5 Startup of an Inactive Loop or Recirculation Loop at an Incorrect Temperature, and Flow Controller Malfunction Causing an Increase 75/11 in BWR Core Flow Rate.............
1 81/7 15.4.6 Chemical and Volume Control System Malfunction That Results in a Decrease in the Boron Concentra-tion in the Reactor Coolant 75/11 (PWR).
1 81/7 15.4.7 Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position............
75/11 1
81/7 15.4.8-Spectrum of Rod Ejection Accidents (PWR).................
75/11 1
78/4 2
81/7 75/11 Appendix A....................
1 81/7 N.
i xix Rev 5 - December 1984 b
-~
TABLE OF CONTENTS (Continued)
Applicable Issued SRP No.
Revision Year / Month 15.4.9 Spectrum of Rod Drop Accidents 75/11 (BWR)...................
1 78/4 2
81/7 Appendix A 75/11 1
78/4 2
81/7 15.5 INCREASE IN REACTOR COOLANT INVENTORY 15.5.1-15.5.2 Inadvertent Operation of ECCS and Chemical and Volume Control System Malfunction That Increases Reactor Coolant Inventory.............
75/11 1
81/7 15.6 DECREASE IN REACTOR COOLANT INVENTORY 15.6.1 Inadvertent Opening of a PWR Pressurizer Relief Valve 75/11 or a BWR Relief Valve 1
81/7 15.6.2 Radiological Consequences of the Failure of Small Lines Carrying Primary Coolant Outside Containment...
75/11 1
78/7 2
81/7 15.6.3 Radiological Consequences of Steam Generator Tube Failure (PWR)..
75/11 1
78/12 2
81/7 15.6.4 Radiological Consequences of Main Steam Line Failure Outside 75/11 Containment (BWR)...
1 78/7 2
81/7 15.6.5 Loss-of-Coolant Accidents Resulting from Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary.......
75/11 1
78/8 2
81/7 Appendix A 75/11 1
81/7 Appendix B......
75/11 1
81/7 l
Appendix C.
75/11 1
1 78/7 2
81/7 i
l 75/11 Appendix D..
1 81/7 O
xx Rev. 5 - December 1984
.,.~.
~
. l
, e
-s 1
I
. TABLE OF CONTENTS-(Continued),
E i
h/N
'Appiicable Issued-
'(
> \\ :'
SRP No.
Revision Year / Month i -
- 15.7-RADIOACTIVE RELEASE FROM A' SUBSYSTEM OR COMPONENT -
75/11 i.
15.'7.1 Waste Gas System Failure............
i 1
81/7.
6 i.
15.7.2c Radioactive Liquid Waste System j
Leak or Failure (Release.to
---~
75/11:
Atmosphere).......................
1-
-81/7 i
15.7.3 Postulated Radioactive Release Due'-
to Liquid-Containing Tank
'75/11 Failures'..........................
j
~
1 78/7-2 81/7
.. Radiological Consequences of Fuel-15.7.4 75/11 Handling Accidents'................
1
.81/7 s
I~
- 75/11 i
1 15.7.5
. Spent Fuel Cask Drop Accidents......
.1-78/12' j
'2 81/7 I
I-e
(
15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM i-f
-15.8-Anticipated Transients Without 75/11' Scram.............................
I z
1 81/7' Appendix.......................
75/11 1
81/7 i
i CHAPTER 16 TECHNICAL SPECIFICATIONS 75/11 16.0 Technical Specifications............
1 81/7 i
CHAPTER 17 QUALITY ASSURANCE
. l
}
17.1 Quality Assurance During the Design 75/11 l
l and Construction Phases...........
i
- 1 79/2 j
t-2 81/7 -
T l
i i
~
17.2 Quality Assurance During the 75/11 t
Operations Phase.................
1 79/2-2 81/7
-CHAPTER 18 HUMAN FACTORS ENGINEERING f
18.0 Human Factors Engineering / Standard
[
- Review Plan Development...........
0 81/7' i
1 84/9 s-
~ -18.1 Control Room........................
0 84/9 1j' Appendix A........................
-0 84/9 i
i 18.2 Safety Parameter Display System.....
0 84/12 i
l Appendix A........................
0' 84/12 l
?
i xx i Rev. b - December 1984
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