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) | |
Text
- .
(
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
t i
l l
i i
l l
8906120215 890602 PDR ADOCK 05000324 P
, 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.
i
.{
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
1 l
BRUNSWICK - UNIT 1 XVI Amendment No.
9 ENCIDSURE 4
~
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
j i
1 I
i
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.
3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION.....
B 3/4 3-6 I
i 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION 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.
1 l
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
'l l
6.14 PROCESS CONTROL PROGRAM (PCP)........'.................... 29 6.15 MAJOR CHANCES TO LIQUID, CASEOUS, AND SOLID WASTE TREATMENT. SYSTEMS.........................
6-30
)
l i
-l I
j
-i
~!
~!
i i
l
' BRUNSWICK - UNIT 2 XVI Amendment No.
L
_-_ ___ _ i