ML20209C672
| ML20209C672 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/29/1987 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20209B455 | List: |
| References | |
| NUDOCS 8702040317 | |
| Download: ML20209C672 (4) | |
Text
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TABLE OF CONTENTS Section Page 3.16 SHOCK SUPPRESSORS (SNUBBERS) 3-63
-3.17 URE 3-80 3.18 FIRE PROTECTION 3-86 3.18.1 FIRE DtitCTION INSTRUMENTATION 3-86 3.18.2 FIRE SUPPRESSION WATER SYSTEM 3-88 3.18.3 DELUGE / SPRINKLER SYSTEMS 3-89
-3.18.4 CO2 SYSTEM 3-90 3.18.5 HALON SYSTEMS 3-91 3.18.6 FIRE HOSE STATIONS 3-92 3.18.7
~ FIRE BARRIER PENETRATION' SEALS 3-94 3.18.8 RD10TE SHUTDOWN INSTRUMENTATION AND CONTROLS 3-94a l
3.19 CONTAINMENT SYSTEMS 3-95 3.20 SPECI AL TEST EXCEPTIONS 3-95a 3.20.1 LOW POWER NATURAL CIRCULATION TEST 3-95a 3.21 RADIOACTIVE EFFLUENT INSTRUMENTATION 3-96 3.21.1-RADIOACTIVE LIQUID tttLUENT IN5tRUMENTATION 3-96 3.21.2 RADIOACTIVE GASEOUS PROCESS AND EFFLUENT 3-100 MONITORING INSTRUMENTATION
'3.22 RADIOACTIVE EFFLUENTS 3-106 3.22.1 LIQUID tttLUENTS 3-106 3.22.2 GASEOUS EFFLUENTS 3-111 3.22.3 SOLID RADI0 ACTIVE 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 COMPARIS0N PROGRAM 3-127 4
SURVEILLANCE STANDARDS 4-1 4.1 OPERATIONAL SAFETY REVIEW 4-1 4.2 REACTOR COOLANT SYSTEM INSERVICE INSPECTION 4-11
- 4.3 TESTING FOLLOWING OPENING OF SYSTEM 4-28 l
4.4 REACTOR BUILDING 4-29 j
4.4.1 CONTAINMENT LEAKAGE TESTS 4 -29 4.4.2 STRUCTURAL INTEGRITY 4-35 4.4.3 DELETED 4-37 4.5 EMERGENCY LOADING SEQUENCE AND POWER TRANSFER, 4 -39 EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 4.5.1 EMERGENCY LOADING SEQUENCE 4-39 4.5.2 EMERGENCY CORE COOLING SYSTEM 4-41 14.5.3 REACTOR BUILDING COOLING AND ISOLATION SYSTEM 4-43 4.5.4 DECAY HEAT REMOVAL SYSTEM LEAKAGE 4-45 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTS 4-46 4.7 REACTOR CONTROL ROD SYSTEM TESTS 4-48 4.7.1 CONTROL ROD DRIVE SYSTEM FUNCTIONAL TESTS 4-48 4.7.2 CONTROL R0D PROGRAM VERIFICATION 4-50 8702040317 B70129 DR ADOCK 050 9
- _999, Amendment 72, 81, 108
TABLE OF CONTENTS Section Page 4.8 MAIN STEAM ISOLATION VALVES 4-51 4.9 EMERGENCY FEEDWATER SYSTEM PERIODIC TESTING 4-52 4.9.1 TEST 4-52 4.9.2 ACCEPTANCE CRITERIA 4-52a 4.10 REACTIVITY ANOMALIES 4-53 4.11 REACTOR COOLANT SYSTEM VENTS 4-54 4.12 AIR TREATMENT SYSTEMS 4-55 4.12.1 EMERGENCY CONTROL ROOM AIR TREATMENT SYSTEM 4-55 4.12.2 REACTOR BUILDING PURGE AIR TREATMENT SYSTEM 4-55b 4.12.3 AUXILIARY & FUEL HANDLING EXHAUST AIR TREATMENT SYSTEM 4-55d 4.13 RADIOACTIVE MATERIALS SOURCES SURVEILLANCE 4-56 4.14 DELETED 4-57 4.15 MAIN STEAM SYSTEM INSERVICE INSPECTION 4-58 4.16 REACTOR INTERNALS VENT VALVES SURVEILLANCE 4-59 4.17 SHDCK SUPPRESSORS (SNUBBERS) 4-60 4.18 FIRE PROTECTION SYSTEMS 4-72 4.18.1 FIRE PROTECTION INSTRUMENTS 4-72 4.18.2 FIRE SUPPRESSION WATER SYSTEM 4-73 4.18.3 DELUGE / SPRINKLER SYSTEM 4-74 4.18.4 CO2 SYSTEM 4-74 4.18.5 HALON SYSTEMS 4-75 4.18.6 HOSE STATIONS 4-76 4.18.7 FIRE BARRIER PENETRATION SEALS 4-76a 4.18.8 RDiOTE SHUTDOWN INSTRUMENTATION AND CONTROLS 4-76b 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 FREQUENCIES 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 LFFLUENT INSTRUMENTATION 4-87 4.21.1 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 4-87 l
4.21.2 RADI0 ACTIVE GASE0US PROCESS & EFFLUENT MONITORING 4-90 INSTRUMENTATION 4.22 RADI0 ACTIVE EFFLUENTS 4-97 4.22.1 LIQUID EFFLUENTS 4-97 4.22.2 GASE0US EFFLUENTS 4-105 4.22.3 SOLID RADI0 ACTIVE WASTE 4-115 4.22.4 TOTAL DOSE 4-116 4.23 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-117 l
4.23.1 MONITORING PROGRAM 4-117 4.23.2 LAND USE CENSUS 4-1 21 4.23.3 INTERLABORATORY CuiPARISON PROGRAM 4-122
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t Amendment No. 11, 28, 30, 41, 47, 55, 72, 78, 95, 97
3.18.8 REMOTE SHilTDOWN INSTRUMENTATION AND CONTROLS Applicability Applies to the operability of remote shutdown instrumentation and controls when the reactor is CRITICAL.
Objective To assure operability of monitoring instrumentation and controls needed to perform a safe shutdown of the plant from outside the Control Room.
Specification 3.18.8.1 The monitoring instrumentation and controls shall be OPERABLE. When inoperable, restore to OPERABLE status within 14 days.
If not, compensatory measures will be in place by the fourteenth day and a Special Report will be submitted to the NRC Region I Administrator within the next 30 days outlining the compensatory measures and plans to repair the inoperable instrumentation.
I Bases The remote shutdown system exists to meet the requirement of 10 CFR 50 Appendix R.
Instrumentation and controls may be inoperable for up to 14 days. This is based on the low probability of an undetected fire severe enough to require the use of any portion of the remote shutdown system that may be inoperable.
If an alternate means of achieving the function of the inoperable feature is available, the feature may remain inoperable for more than 14 days.
3-9 4a
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m-o 4.18.8 RD40TE SHUTDOWN INSTRUMENTATION AND CONTROLS Applicability Applies to remote shutdown instrumentation and controls.
Objective To maintain operability of remote shutdown instrumentation and controls.
Specification 4.18.8.1 Remote shutdown instrumentation that continuously displays shall be verified OPERABLE by the performance of a weekly check.
4.18.8.2 Circuit isolation transfer switches and status indicators shall be demonstrated OPERABLE by verifying the capability to perform intended functions once each refueling.
4.18.8.3 Control functions will be tested once each refueling.
Bases Instrumentation that continuously displays will be checked weekly. This will assure prompt detection and repair of inoperable instrumentation.
Circuit isolation transfer switches and status indicators will be verified to be operable and control functions tested once each refueling.
This will assure operability with minimal risk in the event of a malfunction.
4 4-76b
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