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| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| document type = TECHNICAL SPECIFICATIONS, TECHNICAL SPECIFICATIONS & TEST REPORTS
| page count = 8
| page count = 8
| project = TAC:69048, TAC:69049
| stage = Other
}}
}}


=Text=
=Text=
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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)
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)
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8906120215 890602 PDR ADOCK 05000324 P             PDC
8906120215 890602 PDR ADOCK 05000324 P
PDC


  , 4 -9 INDEX.
, 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
BASES SECTION PACE 3/4.0 APPLICABILITY.............................................
    - 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.
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,
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     )
_S_E_CTION PAGE 6.5.
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     )
REVIEW'AND AUDIT (Continued) 6.5.4 CORPORATE NUCLEAR SAFETY SECTION Function.............................................
Annual Reports.......................................     6-21 Personnel Exposure and Monitoring   Report............. 6-21   j i
6-13 Organization.........................................
Annual Radiological Environmental Operating Report...     6-22       j Semiannual Radioactive Eifluent Release Report.......     6-23     I Monthly Operating Reports............................     6-24 Special Reports......................................
6-13 Review.....,................................~.........:
6-25 Core Operating Limits Report......................... 6-25 1
6-14 Records..............................................
BRUNSWICK - UNIT 1                       XV                       Amendment No.
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.
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.
-6.10 RECORD RETENTION........................................'.
6.I4                     PROCESS CONTROL PROGRAM (PCP)............................     6-29 6.15                     MAJOR CHANCES TO LIQUID, CASEOUS, AND SOLID WASTE TREATMEWT SYSTEMS.........................     6-30 i
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.
BRUNSWICK - UNIT 1 XVI Amendment No.


9 ENCIDSURE 4
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)
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
UNIT 2 TECHNICAL SPECIFICATION PAGES 2
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INDEX BASES                                                                               .]
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   [
.]
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
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
3/4.2.1 AVERACE PLANAR LINEAR HEAT GENERATING RATE............
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.
B 3/4 2-1 l
I 3/4.3.6     RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION..... B 3/4 3-6     ,
3/4.2.2 APRM SETPOINTS........................................
3/4.3.7     REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION i
B 3/4 2-2 l
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
l i
i BRUNSWICK - UNIT 2                       X                     Amendment No.
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.
INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.5 REVIEW AND AUDIT (Continued) 6.5.4 CORPORATE NUCLEAR SAFETY SECTION Function.............................................
                                                  . 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.
6-13.
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.
. Organization.........................................
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.
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
INDEX
        , ADMINISTRATIVE CONTROLS SECTION                                                                 PAGE 6.10   RECORD RETENTION.........................................       6-26' A
, ADMINISTRATIVE CONTROLS SECTION PAGE 6.10 RECORD RETENTION.........................................
6.11   RADIATION PROTECTION PROGRAM. 4..........................       6-28 6.12   HICH RADIATION AREA......................................       6-28 6.13   0FFSITE DOSE CALCULATION MANUAL (0DCM)...................       6-29
6-26' A
                                                                                                      'l l
6.11 RADIATION PROTECTION PROGRAM.
6.14   PROCESS CONTROL PROGRAM (PCP)........'.................... 29 6.15   MAJOR CHANCES TO LIQUID, CASEOUS, AND SOLID WASTE TREATMENT. SYSTEMS.........................     6-30                 )
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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~!
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~!
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      ' BRUNSWICK - UNIT 2                     XVI                     Amendment No.
' BRUNSWICK - UNIT 2 XVI Amendment No.
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Latest revision as of 04:25, 2 December 2024

Proposed Tech Specs Revised Index
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)
v • d • e


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

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.

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

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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

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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

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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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