ML20151C290
| ML20151C290 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/04/1988 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20151C253 | List: |
| References | |
| GL-86-10, NUDOCS 8804120302 | |
| Download: ML20151C290 (4) | |
Text
I TABLE OF CONTENTS Section Page 3.16 SHOCK SUPPRESSORS (SNUBBERS) 3-63 3.17 REACTOR BUILDING AIR TEMPERATURE 3-80 3.18 FIRE PROTECTION (DdLETED) 3-86 l
3.19 CONTAINMENT SYSTEMS 3-95 3.20 SPECIAL TEST EXCEPTIONS 3-95a 3.20.1 LOW POWER NATURAL CIRCULATION TEST 3-95a 3.21 RADIOACTIVE EFFLUENT IMSTRUMENTATION 3-36 3.21.1 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-96 3.21. 2 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT 3-100 MONITORING INSTRUMENTATIOS 3.22 RADI0 ACTIVE EFFLUENTS 3-106 3.22.1 LIQUID EFFLUENTS 3-106 3.22.2 GASE0US EFFLUENTS 3-111 3.22.3 SOLID RADIOACTIVE WASTE 3-118 3.22.4 TOTAL DOSE 3-119 3.23 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-120 3.23.1 MONITORING PROGRAM 3-120 3.23.2 LAND USE CENSUS 3-125 3.23.3 INTERLABORATORY COMPARISON PROGRAM 3-127 4
SURVEILLANCE STANDARDS 4-1 4.1 OPERATIONAL SAFELY REVIEW 4-1 4.2 REACTOR CODLANT SiSTEM INSERVICE INSPECTION-4-11 4.3 TESTING FOLLOWIMU LPENING OF SYSTEM 4-28 4.4 REACTOR BUILDING 4-29 4.4.1 CONTAINMENT LEAKAGE TESTS 4-29 4.4.2 STRUCTURAL INTEGRITY 4.35 4.4.3 DELETED 4-37 4.5 EMERGFNCY LOADING SEQUENCE AND POWER TRANSFER, 4-39 TR UGEECY CORE COOLING SYSTEM AND REXCTUR BUILDING C00 lid 5 SYSTEM PERIODIC TESTINO~
4.5.1 EMERGENCY LOADING SEQUENCE 4-39 4.5.2 EMERGENCY CORE COOLING SYSTEM 4-41 4.5.3 REACTOR BUILDING COOLING AND ISOLATION SYSTEM 4-43 4.5.4 DECAY HEAT REMOYAL SYSTEM LEAKAGE 4-45 j
4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-46 4.7 REACTOR CONTROL ROD SYSTih TESTS 4-48 i
4.7.1 CONTROL ROD ORIVE SYSTEM FUNCTIONAL TESTS 4-48 j
4.7.2 CONTROL ROD PROGRAM VERIFICATION 4-50 i
l t
i eso412oso2 eso4o4 DR p
ADOCK 0500o2g9
-lii-DCD l
Amendmen t 72, 81, 100, 129, 137 l
l
9 TABLE OF CONTENTS Section Page 4.8 MAIN STEAM ISOLATION VALVES 4-51 4.9 DECAY HEAT REMOVAL CAPABILITY - PERIODIC TESTING 4-52 4.9.1 EMERGENCY FEEDWATER SYSTEM - PERIODIC TESTING 4-52 (REACTOR COOLANT TEMPERATURE GREATER THAN 250*F) 4.9.2 DECAY HEAT REMOVAL CAPABILITY - PERIODIC TESTING 4-52a (REACTOR COOLANT TEMPERATURE 250*F OR LESS) 4.10 REACTIVITY ANOMALIES 4-53 4.11 REACTOR COOLANT SYSTEM VENTS 4-54 4.12 AIR TREATMENT SY3 TEM 3 4-55 4.12.1 EMERGENCY CONTROL ROOM AIR TREATMENT SYSTEM 4-55 4.12.2 REACTOR BUILDING PURGE AIR TREATMENT SYSTEM 4-E5b 4.12.3 AUXILIARY & FUEL HANDLING EXHAUST AIR TREATMENT SYSTEM 4-55d 4.13 RADIOACTIVE MATERI ALS SOURCES SURVEILLANCE 4-56 4.14 DELETED 4-56 4.15 MAIN STEAM SYSTEM INSERVICE INSPECTION 4-58 4.16 REACTOR INTERNALS VENT VALVES SBPVElECANCE 4-59 4.17 SHDCK SUPPRE5 SORS (SNUBBER 5) 4-60 4.18 FIRE PROTECTION SYSTEMS (DELETED) 4-72 l
4.19 OTSG TUBE INSERVICE INSPECTION 4-77 4.19.1 STEAM GENERATOR SAMPLE SELECTION & INSPECTION METHODS 4-77 4.19.2 STEAM GENERATOR TUBE SAMPLE SELECTION & INSPECTION 4-77 4.19.3 INSPECTION FREQllENCIES 4-79 4.19.4 ACCEPTANCE CRITERIA 4-80 4.19.5 REPORTS 4-81 4.20 REACTOR BUILDING AIR TEMPERATURE 4-86 4.21 RADIOACTIVE EFFLUENT Ih5TRLMENTATION 4-87 4.21.1 RADI0 ACTIVE LIQUID EFFLUENT TR5TEUMENTAT!0N 4-87 4.21.2 RADI0 ACTIVE GASE0US PROCESS & EFFLUENT MONITORINC 4-90 INSTRUMENTATION 4.22 RADIOACTIVE EFFLUENTS 4-95 4
4.22.1 LIQUID EFFLUENTS 4-95 4.22.2 GASEOUS EFFLUENTS 4-1 01 4.22.3 SOLID RADI0 ACTIVE WASTE 4-107 4.22.4 TOTAL DOSE 4-108 4.23.1 MONITORING PROGRAM 4-117 4.23.2 LAND USE CENSUS 4-121 4.23.3 INTERL/BORATORY COMPARISON PROGRAM 4-122 i
l l
l
-iv-i Amendment No. 11, 28, 30, 41, 47, 55, 72, 78, 95, 97, 119, 122, 129 1
137
(_-_
THIS PAGE LEFT BLANK INTENTIONALLY 3-86 (Pages 3-87 through 3-94 deleted)
Anendcent No. 32,101
F J
THIS PAGE LEFT BLANK INTENTIONALLY 4-72 (Pages 4-73 through 4-76A deleted)
Anendnent No. 32,101