ML20244A974
| ML20244A974 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/02/1989 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20244A968 | List: |
| References | |
| TAC-69048, TAC-69049, NUDOCS 8906120215 | |
| Download: ML20244A974 (8) | |
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ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 6 50-324/ LICENSE NOS. DPR-71 & DPR-62 INDEX PAGE REVISIONS UPDATED TECHNICAL SPECIFICATION PAGES (NRC TAC NOS. 69048 AND 69049)
UNIT 1 TECHNICAL SPECIFICATION PAGES l
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8906120215 890602 PDR ADOCK 05000324 P PDC
, 4 -9 INDEX.
BASES SECTION PACE 3/4.0 APPLICABILITY............................................. B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SuUTDOWN MARGIN...................t.................... B 3/4 1-1
- 3/4.1.2 REACTIVITY ANOMALIES.................................. B 3/4 1-1 3/4.1.3 CONTROL R00S........................................... B 3/4 1-1 3/4.1.4 CONTROL ROD PROGRAM CONTR0LS.......................... B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM......................... B 3/4 1-4 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERACE PLANAR LINEAR HEAT CENERATING RATE............ B 3/4 2-1 3/4.2.2 APRM SETP0INTS........................................ B 3/4 2-2 3/4.2.3 MINIMUM CRITICAL POWER RATI0'..........'................ B 3/4 2-2 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............. B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION...................- B 3/4 3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.................................... B 3/4 3-2 3/4.3.4 CONTROL ROD WITHDRt.WAL BLOCK INSTRUMENTATION.......... B 3/4 3-2 3/4.3.5 MONImRING INSTRUMENTATION............................ B 3/4 3-2 3/4.3.6 AWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATION... B'3/4 3-6 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION.................................... B 3/4 3-6 l 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM................................... B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES................................... B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE......................... B 3/4 4-1 BRUNSWICK - UNIT 1 X Amendment No.
INDEX ADMINISTRATIVE CONTROLS 1,
_S_E_CTION PAGE 6.5. REVIEW'AND AUDIT (Continued) 6.5.4 CORPORATE NUCLEAR SAFETY SECTION Function............................................. 6-13 Organization......................................... 6-13 Review.....,................................~.........: 6-14 Records.............................................. 6-15 6.5.5 CORPORATE QUALITY ASSURANCE AUDIT PROGRAM Function............................................. 6-16 Audits............................................... 6-16 Records................................'.............. 6-17 )
Authority............,,............................... 6-17 Personne1............................................ 6-17 6.5.6 OUTSIDE AGENCY INSPECTION AND AUDIT PROGRAM.......... 6-18 6.6 REPORTABLE EVENT ACTION................................... 6-18 6.7 SAFETY LIMIT VIOLATION.................................... 6-18 6.8 PROCEDURES AND PR0 CRAMS................................... 6-19 6.9 REPORTING REQUIREMENTS Routine Reports...................................... 6-20 Startup Reports...................................... 6-20 )
Annual Reports....................................... 6-21 Personnel Exposure and Monitoring Report............. 6-21 j i
Annual Radiological Environmental Operating Report... 6-22 j Semiannual Radioactive Eifluent Release Report....... 6-23 I Monthly Operating Reports............................ 6-24 Special Reports......................................
6-25 Core Operating Limits Report......................... 6-25 1
BRUNSWICK - UNIT 1 XV Amendment No.
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INDEX' ADMINISTRATIVE CONTROLS SECTION PACE.
-6.10 RECORD RETENTION........................................'. 6-26 6.11 RADIATION PROTECTION PR0 CRAM.............=................' 6 6.12 HICH RADIATION AREA......................................- 6-28 6.1' OFFSITE DOSE CALCULATION MANUAL (ODCM)................... 6-29.
6.I4 PROCESS CONTROL PROGRAM (PCP)............................ 6-29 6.15 MAJOR CHANCES TO LIQUID, CASEOUS, AND SOLID WASTE TREATMEWT SYSTEMS......................... 6-30 i
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BRUNSWICK - UNIT 1 XVI Amendment No.
9 ENCIDSURE 4
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BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 6 50-324/ LICENSE NOS. DPR-71 & DPR-62 INDEX PAGE REVISIONS UPDATED TECHNICAL SPECIFICATION PAGES (NRC TAC NOS. 69048 AND 69049)
UNIT 2 TECHNICAL SPECIFICATION PAGES 2
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INDEX BASES .]
SECTION PACE 3/4.0 APPLICABILITY............................................. B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARGIN....................................... B 3/4 1-1 3/4.1.2 REACTIVITY' ANOMALIES.................................. B 3/4 1-1 3/4.1.3 CONTROL R0DS.......................................... B 3/4 1-1 3/4.1.4 CONTROL ROD PROGRAM CONTR0LS..........................- -B 3/4 1-3 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM......................... B 3/4 1-4 [
l 3/4.2 POWER' DISTRIBUTION LIMITS i
3/4.2.1 AVERACE PLANAR LINEAR HEAT GENERATING RATE............ B 3/4 2-1 l 3/4.2.2 APRM SETPOINTS........................................ B 3/4 2-2 l l
i 3/4.2.3 MINIMUM CRITICAL POWER RATI0.......................... B 3/4 2-2' j 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............. B 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION................... B 3/4~3-2 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION.................................... B 3/4 3-2 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION.......... B 3/4 3-2 3/4.3.5 MONITORING INSTRUMENTATION............................ B 3/4 3-2.
I 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION..... B 3/4 3-6 ,
3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION i
l INSTRUMENTATION.....................'............... B 3/4 3-7 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM................................... B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVES................................... B 3/4 4-1 l 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE......................... B 3/4 4-1 1
i BRUNSWICK - UNIT 2 X Amendment No.
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5 REVIEW AND AUDIT (Continued) 6.5.4 CORPORATE NUCLEAR SAFETY SECTION Function............................................. 6-13.
. Organization......................................... 6 Review.................'.............................. 6-14 Records............................................... 6-15 6.5.5 CORPORATE QUALITY ASSURANCE AUDIT PROGRAM Function............................................. 6-16 Audits.........................................'...... 6-16 Records............................................... 6-17 Authority............................................ 6-17 Personnel............................................ 6-17 6.5.6 0UTSIDE AGENCY INSPECTION AND AUDIT PROGRAM.......... ~6 6.6 REPORTABLE EVENT ACTI0N................................... 6-18.
6.7 SAFETY LIMIT VIOLATION.................................... 6-18 6.8 PROCEDURES AND PR0 CRAMS................................... 6-19 6.9 REPORTING REQUIREMENTS Routine Reports...................................'... 6-20 Startup Reports.......................'............... 6-20 Annual-Reports....................................... 6-21.
Personnel Exposure and Monitoring Report............. 6-21 Annual Radiological Environmental Operating Report... 6-22 Semiannual Radioactive' Effluent Release Report....... 6-23 Monthly Operating Reports............................ 6-24 Special Reports....................................... 6-25 I Core Operating Limits Report......................... 6-25 BRUNSWICK - UNIT 2 XV Amendment No.
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INDEX
, ADMINISTRATIVE CONTROLS SECTION PAGE 6.10 RECORD RETENTION......................................... 6-26' A
6.11 RADIATION PROTECTION PROGRAM. 4.......................... 6-28 6.12 HICH RADIATION AREA...................................... 6-28 6.13 0FFSITE DOSE CALCULATION MANUAL (0DCM)................... 6-29
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6.14 PROCESS CONTROL PROGRAM (PCP)........'.................... 29 6.15 MAJOR CHANCES TO LIQUID, CASEOUS, AND SOLID WASTE TREATMENT. SYSTEMS......................... 6-30 )
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' BRUNSWICK - UNIT 2 XVI Amendment No.
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