ML20154R495
| ML20154R495 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/24/1986 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Stoltz J, Stolz J Office of Nuclear Reactor Regulation |
| References | |
| 0533A, 5211-86-2051, 533A, NUDOCS 8603310024 | |
| Download: ML20154R495 (17) | |
Text
GPU Nuclear Corporation Ng gg{
Post Office Box 480.
Route 441 South Middletown, Pennsylvania '17057-0191 717 944 7621 TELEX 84-2386 Writer's Direct Dial Number:
March 24, 1986 5211-86-2051 l
Office of Nuclear Reactor Regulation Attn. John F. Stolz, Director PWR Project Directorate No. 6 U.S. Nuclear Regulatory Commission i
Washington, D. C. 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station Unit 1 TMI-1)
Operating License No. DPR-50 Docket No. 50-289 TMI-l FSAR Update-4 Date July,1985 Table of Contents Per your request, enclosed please find 135 copies of the Table of Contents which you were missing from the subject update.
Each copyholder should receive 9 sets to be inserted (1 each) in the front of each volume of the THI-l FSAR.
If you have any further questions, please call Mr. M. Iqbal at (201) 299-2257.
Si ncerely,
. D. Fukill Director, TMI-l HDH/MI/spb:0533A j
cc:
J. Thoma Enclosures gh 8603310024 860324 I
{DR ADOCK 05000289 PDR l
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
3
-s-l TABLE OF CONTENTS VOLUME 1 Section Pace i
1.0 INTRODUCTION
AND
SUMMARY
1.1-1
1.1 INTRODUCTION
1.1-1 1.2 DESIGN
SUMMARY
1.2-1 1.2.1 SITE CHARACTERISTICS 1.2-1 1.2.2 POWER LEVEL 1.2-1 1.2.3 LINEAR HEAT RATE 1.2-1 1.2.4 REACTOR BUILDING SYSTEM 1.2-1
{
1.2.5 ENGINEERED SAFEGUARDS 1.2-2 1.2.6 ELECTRICAL SYSTEM AND EMERGD;CY POWER 1.2-3 1.2.7 HYPOTHETICAL AIRCRAFT INCIDDIT
SUMMARY
1.2-3 1.2.8-SHARED CCMPONENTS WITH UNIT 2 1.2-S 1.3 DESIGN CHARACW.RISTICS 1.3-1 1.3.1 DESIGN CHARACTERISTICS 1.3-1 1.3.2 SIGNIFICANT DESIGN REVISIONS 1.3-1 1.4 PRINCIPAL ARCHITECTURAL AND DESIGN CRITERIA 1.4-1 1.4.1 CRITERION 1 - CUALITY STANDARDS (CATEGORY A) 1.4-1 1.4.2 CRITERIO!! 2 - PERFORMANCE STANDARDS (CATEGORY A) 1.4-2 9
1.4.3 CRITERION 3 - FIRE PROTECTION (CATEGORY A) 1.4-3 1.4.4 CRITFAION 4 - SHARING OF SYSTEMS (CATEGORY A) 1.4-4 1.4.S CRITERICN 5 - RECORDS REQUIREMENTS (CATEGORY A) 1.4-4 1.4.6 CRITERION 6 - REACTOR CORE DESIGN (CATEGORY A) 1.4-5 1.4.7 CRITERION 7 - SUPPRESSICN OF POWER OSCILLATIONS (CATEGORY B) 1.4-6 1.4.8 CRITERION 8 - OVERALL POWER COEFFICIENT (CATEGORY B) 1.4-7 1.4.9 CRITERION 9 - REACTOR COOLANT PRESSURE BOUNDARY (CATEGORY A) 1.4-7 4
i 1.4.10 CRITERION 10 - CONTAINMENT (CATEGORY A) 1.4-8 1.4.11 CRITERION 11 - CONTROL ROOM (CATEGORY B) 1.4-8
- 1.4.12 CRITERION 12 - INSTRUMENTATION AND 3
CCHTROL SYSTEMS (CATEGORY B) 1.4-9 1.4.13 CRITERICH 13 - FISSION PRCCESS MONITORS AND CONTROLS (CATEGORY B) 1.4-9 1.4.14 CRITERION 14 - CCRE PROTECTION SYSTO'.S (CATEGORY B) 1.4-10 TC-i
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TABLE OF CONTDITS (Continued)
Sectien Pcce 1.4.15 CRITERION 15 - ENGINEERED SAFETY FEATURES
~ PROTECTION SYSTEMS (CATEGORY B) 1.4-10 1.4.16 CRITERION 16 - MONITORING REACTOR COOLANT PRESSURE BOUNDARY (CATEGORY B) 1.4-10 1.4.17 CRITERION 17 - MONITORING RADI0 ACTIVITY RELEASE (CATEGORY B) 1.4-11 1.4.18 CRITERION 18 - MONITORING FUEL AND WASTE STORAGE (CATEGORY B) 1.4-11 1.4.19 CRITERION 19 - PROTECTION SYSTEMS RELIABILITY (CATEGORY B) 1.4-12 1.4.20 CRITERION 20 - PROTECTICN SYSTEMS REDUNDANCY AND INDEPENDDICE (CATEGORY B) 1.4-12 1.4.21 CRITERION 21 - SINGLE FAILURE DEFINITION (CATEGORY B) 1.4-13 1.4.22 CRITERION 22'- SEPARATION OF PROTECTION AND CONTROL INSTRUMENTATION SYSTDiS (CATEGORY B) 1.4-13 1
1.4.23 CRITERION 23 - PROTECTICH AGAINST MULTIPLE DISABILITY FOR PROTECTION
' SYSTEMS (CATEGORY B) 1.4-13 1.4.24 CRITERICH 24 - EMERGD!CY POWER FOR PROTECTION SYSTEMS (CATEGORY B)-
1.4-14 1.4.25 CRITERION 25 - DEMONSTRATION OF 5
FUNCTIONAL OPERABILITY OF PROTECTION SYSTEMS (CATEGORY B) 1.4-14 1.4.26 CRITERION 26 - PROTECTION SYSTEMS FAIL-SAFE DESIGN (CATEGORY B) 1.4-15 1.4.27 CRITERION 27 - REDUNDANCY OF REACTIVITY 1
C0!! TROL (CATEGORY A) 1.4-15 1.4.23 CRITERION 28 - REACTIVITY HOT SHUTCOWN CAPABILITY (CATEGORY A) 1.4-16 1.4.29 CRITERIO!{ 29 - REACTIVITY SHUTCOUN CAPABILITY (CATEGORY A) 1.4-16 1.4.30 CRITERION 30 - REACTIVITY HOLCCOUN CAPABILITY (CATEGORY B) 1.4-17 1.4.31 CRITERION 31 - REACTIVITY CONTROL SYSTEMS MALFUNCTION (CATEGORY B) 1.4-17 1.4.32 CRITERION 32 - MAXIMUM REACTIVITY UCRTH OF CONTROL RODS (CATEGORY A) 1.4-17 1.4.33 CRITERION 33 - REACTOR COOLANT PRESSURE BOU!iDARY CAPABILITY (CATEGORY A) 1.4-18 1.4.34 CRITERION 34 - REACTOR COOLANT PRESSURE BOUNDARY RAPID PROPAGATIO?i FAILURE PREVD; TION (CATEGORY B) 1.4-18 1.4.35 CRITERICN 35 - REACTOR COOLA:7 PRESSURE BOUNDARY BRITTLE FRACTURE PREVD:!ICN TC-ii i
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TABLE OF CONTDITS (Continued)
Section Pace (CATEGORY A) 1.4-19
~
1.4.36 CRITERION 36 - REACTOR COOLANT PRESSURE BOUNDARY SURVEILLANCE (CATEGORY A) 1.4-2C 1.4.37 CRITERIO!! 37 - ENGINEERED SAFETY FEATURES BASIS FOR DESIGN (CATEGORY A) 1.4-20 1.4.38 CRITERION 38 - RELIABILITY AND TESTABILITY.OF ENGINEERED SAFETY FEATURES (CATEGORY A) 1.4-20 1.4.39 CRITERION 39 - EMERGENCY PO'AER FOR DiGINEERED SAFETY FEATURES (CATEGORY A) 1.4-21 1.4.40 CRITERION 40 - MISSILE PROTECTION 1.4-22 (CATEGORY A) 1.4.41 CRITERION 41 - ENGINEERED SAFETY FEATURES PERFORMANCE CAPABILITY (CATEGORY A) 1.4-22 1.4.42 CRITERION 42 - DiGINEERED SAFETY FEATURES i
COMPONENTS CAPABILITY (CATEGORY A) 1.4-22 1.4.43 CRITERION 43 - ACCIDENT AGGRAVATION i
PREVENTION (CATEGORY A) 1.4-23 l
1.4.44 CRITERION 44 - EMERGENCY CCRE COOLING I
SYSTEMS CAPADILITY (CATEGORY A) 1.4-23 1.4.45 CRITERION 45 - INSPECTION OF EMERGENCY CORE COOLING SYSTEMS'(CATEGORY A) 1.4-24
'O 1.4.46 CRITERION 46 - TESTING OF EMERGENCY CORE COCLING SYSTEMS COMPONENTS (CATEGORY A) 1.4-24 1.4.47 CRITERION 47 - TESTING OF EMERGD;CY CORE COOLING SYSTEMS (CATEGORY A) 1.4-25 1.4.48 CRITERION 48 - TESTING OF OPERATIONAL SECUD:0Y OF EMERGD;CY CORE COOLING SYSTDiS (CATEGORY A) 1.4-25 1.4.49 CRITERION 49 - CONTAINMENT DESIGN BASIS (CATEGORY A) 1.4-26 1.4.50 CRITERION 50 - NDT REGUIREMDIT FCR i
CONTAINMENT MATERIAL (CATEGORY A) 1.4-26 1.4.51 CRITERICH 51 - REACTOR COOLANT PRESSURE BOUNDARY CUTSIDE CONTAINMENT (CATEGORY A) 1.4-25 1.4.52 CRITERION 52 - CONTAINMENT HEAT REMOVAL SYSTEMS (CATEGORY A) 1.4-27 1.4.53 CRITERION 53 - CONTAINMDIT ISOLATION VALVES (CATEGORY A) 1.4-27 1.4.54 CRITERION 54 - CONTAIMMDIT LEAKAGE RATE TESTING (CATEGORY A) 1.4-23 1.4.55 CRITERION 55 - C0!!TAINMD;T PERIODIC LEAKAGE RATE TESTING (CATEGORY A) 1.4-28 1.4.56 CRITERICH 56 - PROVISIONS FOR TESTING 0F PENETRATIONS (CATEGORY A) 1.4-29 1.4.57 CRITERION 57 - PROVISIONS FOR TESTING TC-lii
O TABLE OF CONTDITS (Continued)
Section Pcce CF ISOLATION VALVES (CATEGORY A) 1.4-29 1.4.58 CRITERION 58 - INSPECTIO!! 0F CONTAINMENT i,.
PRESSURE-REDUCI!;G SYSTEMS (CATEGORY A) 1.4-30 1.4.59 CRITERION 59 - TESTING OF CONTAINMENT PRESSURE-REDUCING SYSTEM COMPOND;TS (CATEGORY A) 1.4-30 1.4.60 CRITERION 60 - TESTING OF CONTAINHENT SPRAY SYSTEMS (CATEGORY A) 1.4-31 1.4.61 CRITERION 61 - TESTING OF OPERATIONAL SECUDICE OF CONTAINMENT PRESSURE-REDUCING SYSTCIS (CATEGORY A) 1.4-31 1.4.62 CRITERION 62 - INSPECTION OF AIR CLEANUP SYSTEMS (CATEGORY A) 1.4-32 1.4.63 CRITERION 63 - TESTING OF AIR CLEAtlUP SYSTEMS COMPONDITS (CATEGORY A) 1.4-32 1.4.64 CRITERION 64 - TESTING 0" AIR CLEANUP.
SYSTEMS (CATEGORY A) 1.4-32 1.4.65 CRITERION 65 - TESTING OF CPERATIONAL SEQUE!;CE OF AIR CLEANUP SYSTEMS
+
(CATEGORY A) 1.4-33 1.4.66 CRITERION 66 - PREVDITION OF FUEL STORAGE CRITICALITY (CATEGORY B) 1.4-33 1.4.67 CRITERION 67 - FUCL AND WASTE STORAGE DECAY HEAT (CATEGORY B) 1.4-33 1.4.68 CRITERION 68 - FUEL AND WASTE STORAGE SHIELDING (CATEGORY B) 1.4-34 1.4.69 CRITERION 69 - PROTECTION AGAINST RADIOACTIVITY RELEASE FRON SPENT FUCL' AND WASTE STORAGE (CATEGORY B) 1.4-34 1.4.70 CRITERION 70 - CONTROL OF RELEASES OF.
RADI0 ACTIVITY TO THE ENVIRONMCIT (CATEGORY B) 1.4-35 1.5 RESEARCH AND DEVELOPt!ENT 1.5-1 1.5.1 ONCE-THROUGH STEAM GENERATOR TEST 1.5-1 1.5.2 CONTROL RCD DRIVE LINE TEST 1.5-1 1.5.3 SELF-POWERED DETECTOR TESTS 1.5-1 1.5.4 THERMAL AND HYDRAULIC PROGRAMS 1.5-2 1.5.5 EMERGDICY ~ CORE COOLING AND INTERNALS VDIT VALVES
~1.5-2 1.5.6 FUEL RCD CLAD FAILURE 1.5-2 1.5.7 XENON OSCILLATIONS 1.5-3; 1.5.8 IGDINE RENOVAL SPRAY 1.5-4 1.6 OUALITY ASSURAf:0E 1.6-1 1.6.1 INTRCOUCTIO:i 1.6-1 1.6.2 DESIGN AtiD CONSTRUCTION 1.6-1 TC-iv
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1 i
TABLE OF CONTENTS (Continued)
Section Pece 1.6.3 OPERATIONAL GUALITY ASSURANCE PLAN 1.6-17 1.7 IDDITIFICATION OF AGENTS AND CONTRACTORS 1.7-1
1.8 CONCLUSION
S 1.8-1 1.9 ERM 1.9-1 VOLUME 1 2.0 SITE AND ENVIRONMENT 2.1-1 2.1.
GENERAL DESCRIPTION AND LCCATION 2.1-1 2.1.1 SITE LOCATION 2.1-1 2.1.2 SITE DESCRIPTION 2.1-1 2.2 POPULATION 2.2-1 2.2.1 POPULATION WITHIN 10 MILES 2.2-1 2.2.2 POPUEATIDF WITHIN 50 MILES 2.2-1 2.2.3 LOW POPULATION 2ONE 2.2-1 2.2.4 TRANSIENT POPULATION 2.2-1 2.2.5 POPULATION CENTER 2.2-2 2.2.6 PUBLIC FACILITIES AND INSTITUTIONS-2.2-2 2.2.7 BUSINESS FACILITIES WITHIN 5 MILES 2.2-3 2.3 LAND USE 2.3-1 2.4 AIRPORT TO SITE RELATIONSHTP 2.4-1 i
\\
2.4.1 RUNAWAY LOCATION AND USE 2,4-1 2.4.2
-PROBABILITY OF AIRPLANE STRIKES 2.4-2 2.5 METEOROLOGY 2.5-1 2.5.1 GDiERAL 2.5-1 2.5.2 SEVERE WEATHER 2.5-1 2.5.3 AVERAGE ATMCSPHERIC D J* FUSION CONDITIONS 2.5-2 2.5.4 ACCIDENT METEORCLCGY 2.5-5 2.5.5 APPLICATION OF SFs TRACER GAS TESTS AT THREE MILE ISLAND TO SITE i
METEOROLOGICAL RECORDS 2.5-7 2.5.6 ADDITIONAL INFORMATI0H RELATED TO TMI SITE METEOROLOGY AND DIFFUCION TESTS 2.5-11 2.6 HYDROLOGY 2.G-1 2.6.1 CHARACTERISTICS OF STREAMS IN VICINIT't 2.6-1 2.6.2 STREAM USERS 2.6-2 2.6.3 LOW FLOM STUDIES 2.6-9 2.6.4 FLCOD STUDIES 2.6-12 2.6.5 DESIGN OF HYDRAULIC FACILITIES I 2.6-17 TC-v O
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ll TABLE OF CONTENTS (Continued)
Section Pace i
2.7 ENGINEERI!!G GEOLC0Y AND FOUNDATION CONSIDERATIONS 2.7-1 2.7.1 GENERAL 2.7-1 2.7.2 FIELD INVESTIGATION 2.7-2 2.7.3 GEOLOGY 2.7-3 2.7.4 GROUNDWATER HYDROLOGY 2.7-7 2.7.5 FOUNDATION CONSIDERATIONS 2.7-10 2.8 SEISMOLOGY-2.8-1 l
2.8.1 SEISMICITY 2.8-1 i
2.8.2 ACCELERATION RESPONSE SPECTRA 2.8-1 j
2.9 GEOLCGIC GLOSSARY 2.9-1 2.9.1 GENERAL 2.9-1 2.9.2 HARDNESS CRITERIA 2.9-2 2.10 REFERENCES 2.10-1 l
i VOLUME 2 4
3.0 REACTOR 3.1 3.1 DESIG!! BASES 3.1-1 O
3.1.1 PERFORMANCE OBJECTIVES 3.1-1 4
v 3.1.2 LIMITS 3.1-2 3.2 REACTOR DESIGN 3.2-1 3.2.1 GENERAL
SUMMARY
3.2-1 3.2.2 NUCLEAR DESIGN AND EVALUATION 3.2-1 3.2.3 THERMAL AND HYDRAULIC DESIGN AND EVALUATION 3.2-16 3.2.4 MECHANI3AL DESIGN 3.2-65 3.3 TESTS AND INSPECTIONS 3. 3 -1 ~
3.3.1 NUCLEAR TESTS AND INSPECTICN 3.3-1 TESTING 3.3-1 i
3.3.2 THERMAL AND HYDRAULIC TESTS AND INSPECTION 3.3-2 3.3.3 FUEL ASSEMBLY, C0tiTROL RCD ASSEMBLY, AND 4
CONTROL ROD DRIVE MECHANICAL TESTS 3.3-2 3.3.4 INTERNALS TESTS AND INSPECTIONS 3.3-6 3.4 REFEREMCES 3.4-1 VOLUME 2 l
4.0 REACTOR CCCLANT SYSTEM 4.1-1 TC-vi
~
6 TABLE CT CONTDITS (Contint.ed) i Section Pece 4.1 DESIGN BASES 4.1-1 j
4.1.1 PERFORMA! ICE OBJECTIVES 4.1-1 j
4.1.2 DESIGN CONDITIONS 4'1-2 1
4.1.3 CODES AND CLASSIFICATIONS 4.1-6 4.2 SYSTD1 DESCRIPTION AND OPERATION 4.2-1
.4.2.1 GENERAL 4.2.1 4.2.2 MAJOR. COMPONENTS 4.2-2 4.2.3 SYSTEM PARAMETERS 4.2-12 4.2.4 PRESSURE CONTROL AND PROTECTION 4.2-18 4.2.5 INTERCONNECTED SYSTEMS 4.2-21 4.2.6 COMPONENT FOUNDATIONS AND SUPPORT 4.2-22 4.2.7 MISSILE PROTECTION 4.2-25 4.3 SYSTEM DESIGN EVALUATION 4.3-1 4.3.1 DESIGN MARGIN 4.3-1 4.3.2 MATERIAL SELECTION 4.3-1 4.3.3 REACTOR VESSEL 4.3-2 i
4.3.4 STEAM GENERATORS 4.3-7 4.3.5 RELIANCE ON INTERCONNECTED SYSTEMS 4.3-10 4.3.6 SYSTD! INTEGRITY 4.3-10 4.3.7 OVERPRESSURE PROTECTION 4.3-10
.)
4.3.8 SYSTDI INCIDDIT POTENTIAL 4.3-12 4.3.9 REDUNDANCY 4.3-12 4.3.10 SAFETY LIMITS AND CONDITIONS 4.3-13 4.3.11 QUALITY ASSURANCE 4.3-15 4.4 TESTS AND INSPECTIONS 4.4-1 4.4.1 IN-SERVICE INSPECTION OF THE REACTOR j
COOLANT SYSTEM 4.4-1 4.4.2 CONSTRUCTION INSPECTION 4.4-5 4.4.3 INSTALLATION TESTING 4.4-5 4.4.4 FUNCTIONAL TESTING 4.4-6 4.4.5 MATERIAL IRRADIATION SURVEILLANCE 4.4-6 4.4.6 REACTOR COOLANT SYSTEM LOOCE PARTS AND VIBRATION MONITORING SYSTDI 4.4-7 i
4.5 REFERENCES
4.5-1~
VOLUME 3 5.0 CONTAINMENT SYSTEM AND OTHER SPECIAL STRUCTURES 5.0-1 5.1 STRUCTURAL DESIGN CLASSIFICATION 5.0-1 5.1.1 CLASSES CF SIRUCTURES-AND SYSTEMS FOR SEISMIC DESIGN 5.0-1 5.1.2 SEISMIC DESIGN BASES 5.1-8
~
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TABLE OF CCHTENTS (Centinued)~
Seetion P t c,.e.,e 5.1.3 AIRCRAFT PROTECTED STRUCTURES 5.1-11 5.2 REACTOR BUILDING 5.2-1 5.2.1 STRUCTURAL DESIGN PARAMETERS 5.2-2 5.2.2 MATERIALS AND SPECIFICATIONS 5.2-13 5.2.3
-STRUCTURAL DESIGN CRITERIA 5.2-35 5.2.4 HETHOD OF ANALYSIS 5.2-50 5.2.5 INTERIOR STRUCTURE 5.2-54 5.3 ISOLATION SYSTEM 5.3-1 5.3.1 DESIGN BASES 5.3-1 5.3.2 SYSTEM DESIGN 5.3-1 5.3.3 REACTOR BUILDING PURGE SYSTEM ISCLATION 5.3-7 5.3.4 LEAK RATE TEST SYSTEM 5.3-10 5.3.5-LEAKAGE BLOCKING SYSTEMS 5.3-11 5.4 OTHER SPECIAL STRUCTURES 5.4-1 5.4.1 STRUCTURAL DESIGN PARAMETERS 5.4-1 5.4.2 MATERIALS AND SPECIFICATIONS 5.4-2 5.4.3 STRUCTURAL DESIGN CRITERIA 5.4-2 5.4.4 PIPING DESIGN CRITERIA 5.4-9 5.4.5 METHOD OF ANALYSIS-5.4-15 5.5 QUALITY CONTROL 5.5-1 5.5.1 GENERAL 5.5-1 5.5.2 CONCRETE 5.5-1
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5.5.3 REINFORCING STEEL 5.5-2 5.5.4 CADWELD SPLICES 5.5-3 5.5.5 LINER PLATE 5.5-5 5.5.6 PRESTRESSING TENDONS 5.5-8 5.6 VEMTILATION AND PURGE SYSTEMS 5.6-1 5.6.1 DESIGN BASES 5.6-1 5.6.2 SYSTEM FUNCTICH 5.6-1 5.
6.3 DESCRIPTION
5.6-2 5.6.4 METHODS OF OPERATION 5.6-3 5.6.5 SYSTEM EVALUATION 5.6-4 5.7 TESTING 5.7-1 5.7.1 STRUCTURAL PROOF TEST AND INSTRUMENTATION 5.7-1 5.7.2 PREOPERATIONAL LEAK H0!!ITORING 5.7-1 1
5.7.3 INITIAL INTEGRATED LEAK RATE TEST 5.7-2~
5.7.4 POSTOPERATIONAL LEAKAGE RATE TESTS 5.7-3 5.7.5 TENCON STRESS SURVEILLANCE 5.7-5
5.8 REFERENCES
5.8-1 VOLUMC 4 TC-viii
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' TABLE CF CC;! TENTS (Centinued) k,_)
Section Pace 5
j.
APPENDICES 5A
SUMMARY
OF AIRCRAFT DfPACT DESIGN 58 REPORT ON BBRV POST-TENSIONING SYSIDfS SC REPORT ON LARGE OPENING REINFORCDfDITS FOR REACTOR BUILDING SD REPORT ON STRESS ANALYSIS OF BUTTRESS SE REPORT CN' STRUCTURAL INTEGRITY TESTING OF REACTOR CONTADI!!ENT STRUCTURE 9
l EM5 j
6.0 ENGINEEREbSAFEGUARDS 6.0-1 6.1 EMERGENCY CORE COOLING SYSTDI 6.1-1 6.1.1 DESIGN BASES
' S.1-1 6.1.2 SYSTEM DESIGN 6.1-2 6.1.3 DESIGN EVALUATION 6.1-12 6.l.4 TESTS AND INSPECTIONS 6.1-13 O
6.2 REACTOR BUILDING SPRAY SYSTDt 6.2-1 6.2.1 DESIGN BASES 6.2-1 6.2.2 SYSTDt DESIGN 6.2 6.2.3 DESIGN EVALUATION 6.2-5 6.2.4,.
TESTS AND INSPECTION 6.2-6 6.3 REACTOR BUILDING EMERGENCY CCCLING SYST.rM 6.3-1 6.3.1 DESIGN BASES 6.3-1 E.
3.2 DESCRIPTION
6.3-1 6.3.3 ACTUATION 6.3-3 i
6.4 ENGDIEERED SAFEGUARDS LEAKAGE AND RADIATION CONSIDERATIONS 6.4-1 6.
4.1 INTRODUCTION
6.4-1 6.4.2
SUMMARY
OF POSTACCIDENT RECIRCULATIO!!
6.4-1 6.4.3 BASES OF LEAKAGE ESTIMATE 6.4-2 6.4.4 DESIGN BASIS LEA % AGE 6.4-3 6.4.5 SAFEGUARDS CUBICLE LEAK DETECTIO!I 6.4-3 6.5 REACTOR EUILDING COMBUSTIDLE GAS CCNTROL 6.5-1 6.5.1 HYDP.CGEN RECOMBINER SYSTCM 6.5-1 s
-6.5.2 HYDROGDI M0!!ITORING 6.5-5 6.5.3 HYDROGDI GDIERATION'
'i.
6.5-7 6.6 REACTCR BUILDING PRESSURE TD!E RESP 7tSE 6.6-1 6.7 REFEROlCES I
6.7-1
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O TABLE CF CONTDITS (Centinued)-
Section Pcce APPENDICES 6A
SUMMARY
DESCRIPTION - REACTOR BUILDDIG FAN CCOLER ASSEMBLY 6B ENVIE h M TAL QUALIFICATION VOLUME 5 7.0 INSTRUMENTATION AND CONTROL 7.0-1 7.1 PROTECTION SYSTEMS 7.1-1 7.1.1 DESIGN BASIS 7.1-1 7.1.2 CORE PROTECTION SAFETY LIMITS 7.1-4 7.1.3 ENGINEERED SAFEGUARDS ACTUATION SYSTD1 7.1-16 7.1. 4 '
DtERGENCY FEEDWATER SYSTEM 7.1-26 7.2 REGULATION SYSTEMS 7.2-1 7.2.1 DESIGN BASES 7.2-1 7.2.2 RCD DRIVE CCNTROL SYSTDi 7.2-1 7.2.3 INTEORATED CONTRCL SYSTDi 7.2-15 7.3 INSTRUMENTATION 7.3-1 7.3.1 NUCLEAR INSTRUMENTATION 7.3-1 7.3.2 NON-NUCLEAR INSTRUMDITATICH 7.3-4 7.3.3 INCCRE MONITORING SYSTDI 7.3-21 7.4 CPERATINO CONTROL STATIONS 7.4-1 7.4.1 GaiERAL LAYOUT 7.4-1 7.4.2 INFORMATION DISPLAY AND CCNTP.CL FU!;CTICN 7.4-1 7.4.3
SUMMARY
OF ALARMS 7.4-4 7.4.4 CCMNUNICATICN 7.4-4 7.4.5 HABITABILITY 7.4-4 7.4.6 RDiOTE SHUTDOWN PANEL 7.4-5 7.4.7 EMERGENCY FACILITIES AND ECUIPMCIT 7.4-10 7.5 REFERD'CES 7.5-1 VCLUME 6 8.0 ELECTRICAL SYSTEMS 8.1-1 8.1 DESIGN BASES 8.1-1 TC-x O
~
s TABLE OF CONTENTS (Contint:ed)
Section Pace 8.2 ELECTRICAL SYSTEM DESIGN 8.2-1 8.2.1 NETWORK INTERCONNECTIONS 8.2-1 8.2.2 UNIT DISTRIBUTION SYSTEM 8.2-3 8.2.3 SOURCES OF AUXILIARY POWER 8.2-17 8.3 TESTS AND INSPECTIONS 8.3-1 8.4 QUALITY CONTROL 8.4-1 8.4.1 DESIGN REVIEW 8.4-1 8.4.2 PROCUREMENT DOCUMENTS 8.4-2
8.5 REFERENCES
8.5-1 VOLUME 6 9.0 AUXILIARY AND EMERGENCY SYSTD!S 9.0-1 9.1 MAKEUP AND PURIFICATION SYSTEM 9.1-1 9.1.1 DESIGN BASES 9.1-1 9.1.2 SYSTEM DESCRIPTION AND EVALUATION 9.1-2
~
9.2 CHEMICAL ADDITION AND SAMPLING SYSTEMS 9.2-1 9.2.1 CHEMICAL ADDITION SYSTEM 9.2 9.2.2 SAMPLING SYSTEM 9.2-5 9.3 INTERMEDIATE COOLING SYSTEM 9.3-1 9.3.1 DESIGN BASES 9.3-1 9.3.2 SYSTEM DESCRIPTION AND EVALUATION 9.3-1 9.4 SPENT FUEL COOLING SYSTEM 9.4-1 9.4.1 DESIGN BASES 9.4-1 9.4.2 SYSTEM FUNCTIONS 9.4-1 9.4.3 SYSTEM DESCRIPTION 9.4-2 9.4.4 PERFORMANCE REGUIREMENTS 9.4-3 9.4.5 METHODS OF OPERATION 9.4 9.4.6 LEAXAGE CONSIDERATIONS 9.4-4 9.4.7 SYSTEM EVALUATION-9.4-4 9.5 DECAY HEAT REMOVAL SYSTEM 9.5-1 9.5.1 DESIGN BASES 9.5-1 9.5.2 SYSTEM DESCRIPTION AND EVALUATION 9.5-1 9.6 COOLING MATER SYSTEMS 9.6-1 9.6.1 DESICH BASES 9.6-1 9.6.2 SYSTEM DESCRIPTION AND EVALUATION 9.6-5 9.7 FUEL HANDLING SYSTEM 9.7-1 9.7.1 DESIGli DASES 9.7-1 9.7.2 SYSTDI DESCRIPTION AND EVALUATICN 9.7-G 9.8 VENTILATIO'I SYSTEMS 9.8-1 9.8.1 CO!! TROL BUILDING VE!;TILATICN SYSTE!!
9.8-1 9.8.2 FUEL HA! DLING BUILDING VCNTILATICII SYSTC!
9.8-7 TC-xi
.~ -
.c Ob TABLE OF CONTE!!TS (Continued)
Secticn Pace 9.8.3 AUXILIARY BUILDING VENTILATICN SYSTEM 9.8-10 9.8.4 TURBINE BUILDING VDITILATION SYSTEM 9.8-13 9.8.5 RECIRCULATION COOLING UNITS 9.6-14 9.8.6 INTERMEDIATE BUILDING VENTILATION SYSTDi 9.8-15 9.8.7 DIESEL GENERATOR BUILDING 9.8-16 9.8.8 SERVICE BUILDING VENTILATION SYSTEM 9.8-17 9.9 PLANT FIRE PROTECTION SYSTEM 9.9-1 9.9.1 SYSTEM FUNCTIONS 9.9-1 9.9.2 SYSTDi DESCRIPTION 9.9-1 9.9.3 SYSTDI DESIGN RECUIRDIDITS 9.9-2 9.9.4 DETAILED DESCRIPTION OF SYSTEM 9.9-3 9.9.5 INSTRUMDITS, CONTROLS, ALARMS, AND PROTECTIVE DEVICES 9.9-10 9.9.6 TESTING OF FIPI PROTECTION SYSTD!S 9.9-15 9.9.7 FIRE DETECTION AND SUPPRESSI0ft FOLLOWING A 9.10 AUXILIARY SYSTEMS 9.10-1 9.10.1 INSTRUMENT AND CONTROL AIR SYSTD1 9.10-1 9.10.2 NUCLEAR PLANT HYDROGEN AND HITROGDI SUPPLY SYSTDi 9.10-2 9.10.3 TWO-HOUR BACKUP AIR SUPPLY 9.10-4 9.11 REFERD CES 9.11-11 O
VOLUME 7 10.0 STEAff AND POWER CONVERSIOM SYSTEi 10.1-1 10.1
SUMMARY
DESCRIPTION 10.1-1 10.2 TURBINE GENERATOR 10.2-1 10.2.1 DESICN BASIS
~10.2-1 10.2.2 SYSTDi DESCRIPTION AND OPERATION 10.2-1 10.3 STEAM SUPPLY SYSTEMS 10.3-1 10.3.1 MAIN STEAM SYSTDi 10.3-1 10.3.2 TURBINE BYPASS SYSTEM 10.3-3 10.3.3 EXTRACTION STEAM AND DRADIS SYSTDi 10.3-4 10.3.4 AUXILIARY STEAM SYSTDi 10.3-5 10.4 CONDENSATE SYSTDt 10.4-1 10.4.1 MAI!! CONDDISATE SYSTEM 10.4-1 10.4.2 CONDENSATE POLISHING.'
10.4-3 10.4.3 CONDENSATE CHD1ICAL TREATMDIT SYSTDi 10.4-4 10.4.4 CONDENSER AIR REMOVAL'SYSTDI 10.4-5 10.5 MAIN FE DMATER SYSTE!!
-10.5-1 10.5.1 DCSIGli BASIS 10.5-1 10.5.2 SYSTDI DESCRIPTION AND OPERATION 10.5-1 OV TC-xil
TABLE OF CONTENTS (Continued)
Section Pace 10.6 EMERGDICY FW SYSTEM 10.6-1 10.6.1 DESIGN BASIS 10.6-1 10.6.2 SYSTEM DESCRIPTION AND OPERATION 10.6-1 10.7 SYSTEM ANALYSIS' 10.7-1 10.7.1 TRIPS AUTOMATIC CONTROL ACTIONS, AND ALARMS 10.7-1 10.7.2 TRANSIENT CONDITIONS 10.7-2 10.7.3 MALFUCTIONS 10.7-3 10.7.4 OVERPRESSURE PROTECTION 10.7-3 10.7.S INTERACTIONS 10.7-3 10.8' TESTS AND IMSPECTIONS 10.8-1 10.8.1 GENERAL 10.8-1 10.8.2 EMERGENCY FEEDWATER SYSTDI TESTS AND SURVEILLANCE 10.8-1
10.9 REFERENCES
10.9-1 VOLUME 7 11.0 RADI0 ACTIVE WASTE AND RADIATION PROTECTION 11.1-1 11.1 DESIGN PERrORMANCE DEJECTIVES 11.1-1 11.1.1 DESIGN BASIS 11.1-1 11.2 RADIOACTIVE WASTE DISPOSAL SYSTEMC 11.2-1 11.2.1 RADIOACTIVE LICUID' HASTE DISPOSAL SYSTEM 11.2-2 11.2.2 RADIOACTIVE WASTE GAS DISPCSAL SYSTDI 11.2-8 11.2.3 RADI0 ACTIVE SOLID WASTC DISPOSAL SYSTDi 11.2-13 11.2.4 OPERATING POLICY ON RADIOACTIVE DISCHARGES TO THE ENVIRONMD:T 11.2-17 11.2.S DILUTION FACTORS IN SUSCUEHANNA RIVER 11.2-19 11.3 RADIATION SHIELDING 11.3-1 l
11.3.1 DESIGN CRITERIA 11.3-1 11.3.2 GDIERAL DESCRIPTION 11.3-2 11.3.3 MATERIALS 11.3-4' 11.4 RADIATION MONITORING SYSTDI 11.4-1
- 11.4.1 DESIGN BASIS 11.4-1 11.4.2 AREA MONITORING SUBSYSTD1 DESCRIPTION 11~.4-1 11.4.3 ATMOSPHERIC MONITORING SUBSYSTEM DESCRIPTION 11.4-2 11.4.4 LICUID MONITORING SUBSYSTE!! DESCRIPTION 11.4-S 11.4.S POSTACCIDENT MONITORING 11.4-G 11.4.6 RADIOLCGICAL SAMPLING 11.4-10 TC-xiii
.C4
TABLE CF CONTENTS (Continued) 11.5 RADICLOGICAL CONTROLS 11.5-1 11.5.1 RADIATICH WORK PERMITS 11.5-1 11.5.2 PERSONNEL MCNITORING SYSTEM 11.5-2 11.5.3 PERSONNEL PROTECTIVE ECUIPMENT 11.5-2 11.5.4 ACCESS CONTROL 11.5-3 11.5.5 RADIOLOGICAL CONTROLS LABORATORY FACILITIES 11.5-4 11.5.6 RADIOLOGICAL CONTROLS DISTRUMENTATION 11.5-4 11.5.7 MEDICAL PROGRAM 11.5-4 11.5.8 RADIATION PROTECTICH PLAN 11.5-5 11.6 RADI0 ACTIVE MATERIALS SAFETY 11.6-1 11.6.1 MATERIALS SAFETY PROGRAM 11.6-1 11.6.2 FACILITIES AND EQUIPMENT 11.6-3 11.6.3 PERSONNEL AND PROCEDURES 11.6-4 11.6.4 REQUIRED RADIOACTIVE SOURCES 11.6-4
11.7 REFERENCES
11.7-1 APPENDICES 11A POST ACCIDENT SHIELDING EVALUATION O
VOLUME 7 l
12.0 CC?iCUCT CF OPERATIONS 12.1-1 12.1 ORGANIZATICN AND OUALIFICATIONS 12.1-1 12.1.1 STATIOI ORGANIZATION 12.1-3 12.1.2 STATION SUPPORT CRGANIZATIO!I 12.1-42 12.1.3 SAFETY REVIEWS 12.1-54 12.2 TRAINING 12.2-1 12.
2.1 INTRODUCTION
12.2-1 j
12.2.2 TRADiING PRCGRAM 12.2-1 12.2.3 LICENSED GPERATOR TRAINING 12.2-3 (CRO/SRO)-
12.2-3 12.2.4 FIRE PROTECTICN TRAINING, PROGRAM 12'.2-Q12 2.1 12.2.5 SUPPORT TRAINIriG PROGRh b 12.2.6 TRAINING RECORDS 12.2-14 12.3 PROCEDURES 12.3-1 i
l 12.3.1 ADMINISTRATIVE CO!iTROLS 12.3-2 12.3.2 CPERATIMG PRCCEDUT.ES 12.3 TC-xiv O
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m,
i l
O' '
TABLE CF CCNTC{TS (Continued)
Section Pace 12.4 PLANT l'CDIFICATICf:S 12.4-1' 12.4.1 MODIFICATIONS 12.4-1 12.4.2 TESTING OF MODIFICATIONS 12.4-2 12.5 RECORDS 12.5-1 12.5.1 PLANT HISTORY 12.5-1 12.5.2 OPERATING RECORDS 12.5-1 12.5.3 EVENT RECORDS 12.5-1 12.6 OPERATIONAL QUALITY ASSURAf;CE PLAN 12.6-1 12.7 EMERGDICY PLAN 12.7-1 12.8 INDUSTRIAL SECURITY 12.8-1
12.9 REFERENCES
12.9-1 VOLUME 7 i
13.0, INITIAL TESTS AND OPERATIO!!
13.1-1 13.1 TEST PROGRAll DCSCRIPTION 13.1-1 13.1.1 ADMI!!ISTRATIVE PRCCCDUnES (TESTING) 13.1-1 13.1.2 ADMINISTRATIVE PROCEDURES (MODIFICATIONS) 13.1-4 13.1.3 TEST CBJECTIVES AND PRCCCCURES 13.1-4 13.1.4 FUEL LGADING AND INITIAL OPERATION 13.1-6 O
12.1.s aonznIsraarzvc raccEoUacs (SYSTEM OPERATION)-
13.1-9 13.2 AUGMDITATION OF APPLICAf!T'S STAF FOR INITIAL TESTS AND OPERATIO?!S 13.2-1 13.2.1 ORGANIZATICHAL FUI;CTICNS, RESPCNSIBILITIES, A!!D AUTHC'lIIIES 13.2-1 13.2.2 INTERRELATICNSHIPS A!iD INTERTAC.S 13.2-3 13.2.3 PERSONNCL FUNCTICIIS, RESPO!!SICILITIES, AND AUTHORITIES 13.2-5 VOLUME 8 14.0 SAFTTY ANALYSIS 14.1-1 14.1 CORE At-:D CCCLANT COUr:DARY PROTCCTION A??ALYSIS 14.1-1 14.1.1 ABNCRMALITIES 14.1-1 14.1.2 ANALYSIS OF EFFECTS A!ID C0!!SEOUENCIS 14.1-1 TC-xv O
1 O
TABLE OF CCNTENTS (Continued)
Section Pace I
14.2 STANDBY SAFEGUARDS ANALYSIS 14.2-1 14.2.1 SITUATICNS ANALYZED AND CAUSES 14.2-1 14.2.2 ACCIDENT ANALYSES 14.2-1
14.3 REFERENCES
14.3-1 VOLINE - 9 APPENDICES 14 A DESIGNREhIEWFORCONSIDERATIONOFEFFECTSCF PIPING SYSTEM BREAKS CUTSIDE CONTAINMENTS 14 B ICDINE REMOVAL CAPABILITIES OF THE TMI-1 REACTOR BUILDING SPRAY SYSTEM 14 C EVALUATION OF ACCIDENT DOSE 14 D EVALUATION OF PURGING AS A MEANS OF CONTROLLING POSTACCIDENT NYDROGEN CONCENTRATION IN THE THREE MILE ISLAND UNIT 1 REACTOR BUILDING 14 E AN EVALUATION OF ACCIDENT DOSE PROBABILITIES USING THREE MILE ISLAND SITE MEASURED METEORCLOGY DATA r!O 4
TC-xvi O
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