ML20151C389

Proposed Tech Specs Revising Titles Listed in Index Section of Tech Specs to Be Consistent W/Titles in Text Re Administrative Changes

ML20151C389
Person / Time
Site:	Brunswick
Issue date:	07/11/1988
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML20151C384	List: ML20151C380 ML20151C389
References
NUDOCS 8807210340
Download: ML20151C389 (34)

Text

.

c, ENCLOSURE 5-BRUNSW1CK STEAM ELECTRIC PLANT, UNITS.1 AND 2 NRC' DOCKETS 50-325 & 50-324 OPERATIFG LICENSES DPR-71 &

DPR-62 RF. QUEST FOR LICENSE AMENDMENT UNIT 1 TECHNICAL SPECIFICATION PAGES I

I a

4 6

I f

P PDC

(BSEP-1-133)

INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PACE 2.1 -SAFETY LIMITS Thermal Power'(Low Pressure or Low Flow)...................

2-1 Thermal Power (High Pressure and High Flow)................

2-1 Reac tor Coolant Sys tem Pre s sure............................

2-1 Reactor Vessel Water Levc1.................................

2-2 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Instrumentation Setpoints........

2-3 BASES 2.1 SAFE'Y LIMITS Thermal Power (Low Pressure or Low Flow)................;..

B 2-1 Thermal Power (High Pressure and High flow)................

B 2-2 Reactor Coolant System Pressure........................,...

B 2-8 Reactor Vessel Water Level.................................

B 2-8 2.2 Limiting Safety System Settings Reactor Protection System Instrumentation Setpoints........

B 2-9 BRUNSWICK - UNIT 1 III Amendment No.

(BSEP-1-133)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.0 APPLICABILITY.............................................

3/4 0-1 3/4.1 kEACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN HARCIN......................................

3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES.................................

3/4 1-2 3/4.1.3 CONTROL RODS Control Rod Operability..............................

3/4 1-3 Control Rod Maximum Scram Insertion Times............

3/4 1-5 Control Rod Average Scram Insertion Times............

3/4 1-6 Four Control Rod Group Scram Insertion Tires.i..i".~..#.'

'3/4'l-7 Control Rod Scram Accumulators.......................

3/4 1-8 Control Rod Drive Coup 11ng...........................

3/4 1-9 Control Rod Position Indication......................

3/4 1-11 Control Rod Drive Housing Support....................

3/4 1-13 3/4.1.4 CONTROL ROD PROGRAM CONTROLS Rod Worth Minimizer..................................

3/4 1-14 Rod Sequence Control System..........................

3/4 1-15 Rod Block Monitor.....................................

3/4 1-17 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM........................

3/4 1-18 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERACE PLANAR LINEAR HEAT GENERATION RATE...........

3/4 2-1 t

l 3/4.2.2 APRM ESTP0INTS.......................................

3/4 2-9 1

3/4.2.3 MINIMUM CRITICAL POWER RATI0.........................

3/4 2-10 j

3/4.2.4 LINEAR HEAT CENERATION RATE..........................

3/4 2-16 BRUNSWICK - UNIT 1 IV Amendment No.

(BSEP-1-A33)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

+

SECTION PACE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............

3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION..................

3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION...................................

3/4 3-30 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION.........

3/4 3-39 3/4.3.5 MONITORING INSTRUMENTATION Seismic Monitoring Instrumsntat'on...................

3/4 3-44 Remote Shutdown Monitoring Instrumentation...........

3/4 3-47 Accident Monitoring Instrumentation..................

3/4 3-50 Source Range Monitors..........,......................

3/4 3-53 Chlorine Detection System............................

3/4 3-54

, Chloride Intrusion Monitors..........................

3/4 3-55 Fire Detection Instrumentation.......................

3/4 3-59 Radioactive Liquid Effluent Monitoring Instrumentation...................................

3/4 3-62 Radioactive Caseous Effluent Mcnitoring Instrumentation...................................

3/4 3-68 3/4.3.6 ATWS RECIRCULATION PUMP TRIP SYSTEM INSTRUMENTATI0tf..

3/4 3-78 3/4.3.7 EEACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION...................................

3/4 3-82 l

3/4.4 REACTOR COOLANT SYSTEM j

3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops..................................

3/4 4-1 Jet Pumpe............................................

3/4 4-2 Idle Recirculation Loop Start-up.....................

3/4 4-3 3/4.4.2 SAFETY / RELIEF VALVES...............

3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............................

3/4 4-5 Operational Leakage..................................

3/4 4-6 1

BRUNSWICK - UNIT 1 V

Amendment No.

4 l

(BSEP-1-133)-

4 INDEX LIMITING CGMDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.6 CONTAINMENT SYSTEMS (Continued) 3/4.6.2 DEPRESSURIZATION AND COOLING 3YSTEMS Suppression Chamber...................................

3/4 6-9 l

Suppression Pool Cooling..............................

3/4 6-11 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES..................

3/4 6-12 3/4.6.4 VACUUM RELIEF 3rywell - Suppression Chamber Vacuum Breakers.........

3/4 6-18 Suppression Pool - Reactor Building Vacuum Breakers...

3/4 6-20 3/4.6.5 SECONDARY CONTAINMENT Secondary Containment Integrity.......................

3/4 6-21 Secondary Containment Automatic Isolation Dampers.....

3/4 6-22 3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL

'S tandby Cas Trea tmen t Sys t em..........................

3/4 6-25 Containment Atmosphere Dilution System................

?/4 6-28 0xygen Concentration..................................

3/4 6-29 Cas Analyzer Systems..................................

3/4 6-30 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System............

3/4 7-1 Service Water System..................................

3/4 7-2 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEP...............

3/4 7-3 3/4.7.3 FLOOD PROTECTION......................................

3/4 7-6 BRUNSWICK - UNIT 1 VII Amendment No.

(BSEP-1-133)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM.................

3/4 7-7 3/4.7.5 SNUBBERS..............................................

3/4 7-9 l

3/4.7.6 SEALED SOURCE CONTAMINATION...........................

3/4 7-15 3/4.7.7 FIRE SUPPRESSION SYSTEMS Fire Suppre>sion Water System.........................

3/4 7-17 Spray and/or Sprinkler Systems........................

3/4 7-20 High Prersure CO2 Systems.............................

3/4 7-22 Fire Hrse Stations....................................

3/4 7-23 F o am , y s t em s..........................................

3/4 7-26 3/4.7.8

. lad BARRIER PENETRATIONS.............................

3/4 7-28 3/4.8 ELECTRICAL POWEk SYSTEMS 3/4.8.1 A.C. SOURCES Operation of One or Both Units........................

3/4 8-1 Shutdown of Both Units................................

3/4 8-5 3/4.8.2 ONSITE POWEB DISTR 13UTION SYSTEMS A.C. Distriousfan - Operation of One or Both Units....

3/4 8-6 q

A.C Dis tribution - Shutdown of Both Unit s.............

3/4 8-7 D.C. Distribution -

Operating.........................

3/4 8-8 D.C. Distribution - Operation of One or Both Units....

3/4 8-12 D.C. Distribution -

Shutdown..........................

3/4 8-14 Reactor Protection System Electrical Power Monitoring.

3/4 8-15 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR H0DE SWITCH...................................

3/4 9-1 j

3/4.9.2 INSTRUMENTATION.......................................

3/4 9-3 BRUNSWICK - UNIT 1 VIII Amendment No.

1 (BSEP-1-133) i INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.9 REFUELING OPERATIONS (Continued) 3/4.9.3 CONTROL ROD POSITION......................,_..........

3/4 9-5 3/4.9.4 DECAY TIME...........................,.................

3/4 9-6 3/4.9.5 COMMUNICATIONS........................................

3/4 9-7 3/4.9.6 CRANE AND HOIST OPERABILITY...........................

3/4 9-8 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00L..................

3/4 9-9 3/4.9.8 WATER LEVEL-REACTOR VESSEL............................

3/4 9-10 3/4.9.9 WATER LEVEL-SPENT FUEL STORACE P00L...................

3/4 9-11 3/4.9.10 CONTROL ROD RCMOVAL Single Control Rod Remova1............................

3/4 9-12 Multiple Control Rod Remova1..........................

3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.........................

3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM...........................

3/4 10-2 3/4.10.3 SHUTDOWN HARCIN DEMONSTRATIONS........................

3/4 10-3 3/4.10.4 RECIRCULATION L00PS...................................

3/4 10-4 3/4.10.5 PLANT SERVICE WATER................

3/4 10-5 i

l 1

BRUNSWICK - UNIT 1 IX Amendmer.t No.

(BSEP-1-133) _

j INDEX LIMITING CONDtiIC::S FOR OPERATION AND SURVEILLANCE REQUIREMENTS l

3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration........................................

3/4 11-1 Dose - Liquid Effluents..............................

3/4 11-8 Liquid Radwaste Treatment System.....................

3/4 11-9 Liquid Holdup Tanks..................................

3/4 11-10 3/4.11.2 CASEGUS EFFLUENTS Dose Rate............................................

3/4 11-11 Dose - Noble Cases...................................

3/4 11-15 Dose - Iodine-131, Iodine-133, Tritium, end Radionuclides

.in Particulate Form................................

3/4 11-16 Caseous Radwaste Treatment System....................

3/4 11-17

- Ventilation Exhaust Treatment System.................

3/4 11-18 Explosive Cas Mixture................................

3/4 11-19 Main Condenser Air Ejector Radioactivity Release Rate..............................................

3/4 11-20 Drywell Venting or Purging...........................

3/4 11-21 3/4.11.3 SOLID RADIOACTIVE WASTE..............................

3/4 11-22 3/4.11.4 TOTAL DOSE (40 CFR PART 190).........................

3/4 11-23 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 CRAM...................................

3/4 12-1 3/4.12.2 LAND USE CENSUS......................................

3/4 12-13 3/4.12.3 INTERLABORATORY COMFARISON PROGRAM...................

3/4 12-15 BRUNSWICK - UNIT 1 IXa Amendment No.

(BSEP-1-133)

INDEX BASES SECTION PACE 3/4.0 APPLICABILITY.............................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 SHUTDOWN MARCIN.......................................

B 3/4 1-1 3/4.1.2 REACTIVITY AN0KALIES..................................

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 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 SETPOINTS........................................

B 3/4 2-3 3/4.2.3 MINIMUM CRITICAL POWER RATI0..........................

B 3/4 2-3 3/4.2.4 LINEAR HEAT CENERATION RATE...........................

E 3/4 2-5 3/4.3 INSTRUMENTATI_ON 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 ATWS 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 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTFe...................................

B 3/4 4-1 3/4.4.2 SAFETY / RELIEF VALVLS...................................

B 3/4 4-1 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE.........................

B 3/4 4-1 BRUNSWICK - UNIT 1 X

Amendment No.

l

=m P -

1

-(BSEP-1-133) 1 INDEX BASES SECTION PACE 3/4.4 REACTOR COOLANT SYSTEM (Continued) 3/4.4.4 CHEMISTRY.............................................

B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY.....................................

B 3/4 4-2 3/4.4.6 PRESSURE / TEMPERATURE LIMITS...........................

B 3/4 4-3 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES......................

B 3/4 4-7 3/4.4.8 STRUCTURAL INTEGRITY..................................

B 3/4 4-7 3/4.5 EMERGENCY CORE COOLING SYSTEM 3/4.5.1 HICH PRESSl'RE COOLANT INJECTION SYSTEM................

B 3/4 5-1 3/4.5.2 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS)...............

B 3/4 5-1 3/4.5.3 LOW PRESSURE. COOLING SYSTEMS..........................

B 3/4 5-2 3/4.5.4 SUPPRESSION P0UL......................................

B 3/4 5-4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT...................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS..................

B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES..................

B 3/4 6-4 3/4.6.4 VACUUM RELIEF......................................... - B 3/4 6-3 3/4.6.5 SECONDARY CONTAINMENT.................................

B 3/4 6-5 3/4.6.6 CONTAINMENT ATMOSPHEP.E CONTR0L........................

B 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS.................................

B 3/4 7-1 1

3/4.7.2 CONTROL ROOM EMERCENCY FILTRATION SYSTEM..............

8 3/4 7-1 l

l BRUNSWICK - UNIT 1 XI Amendment No.

(BSEP-1-133)

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION......................................

B 3/4 7-1 3/4.7.4 REl.CTOR CORE ISOLATION COOLING SYSTEM.................

B 3/4 7-1 B 3/4 7-2 l 3/4.7.5 SNUBBERS..............................................

3/4.7.6 SEALED SOURCE CONTAMINATION...........................

B 3/4 7-3 3/4.7.7 FIRE SUPPRESSION SYSTEMS..............................

B 3/4 7-3 3/4.7.8 FIRE BARRIER PENETRATIONS.............................

B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS..................................

B/3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1

, REACTOR MODE SWITCH...................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION.......................................

B 3/4 9-1 3/4.9.3 CON 110L ROD P0SITION..................................

B 3/4 9-1 3/4.9.4 DECAY TIME............................................

B 3/4 9-1 3/4.9.5 C0KMUNICATIONS........................................

B 3/4 9-1 3/4.9.6 CRANE AND HOIST OPERABILITY...........................

B 3/4 9-2

~

3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00L..................

B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and 3/4.9.9 WATER LEVEL-REACTOR FUEL STORACE P00L.................

B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL...................................

B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTECRITY.........................

B 3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM...........................

B 3/4 10-1 3/4.10.3 SHUTDOWN MARCIN DEMONSTRATIONS........................

B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS...................................

B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER...................................

B 3/4 10-1 BRUNSWICK - UNIT 1 XII Amendment No.

(BSEP-1-133)

INDEX BASES SECTION PACE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS r

concentration........................................

B 3/4 11-1 Dose - Liquid Effluents..............................

B 3/4 11-1 Liquid Radwaste Treatment System.....................

B 3/4 11-2 l

Liquid Holdup Tanks..................................

B 3/4 11-3 3/4.11.2 CASEOUS EFFLUENTb Dose Rate............................................

B 3/4 11-3 Dose-Noble Cases.....................................

B 3/4 11-4 Dose-Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form..................

B 3/4 11-5 l

, Caseous Radwaste Treatment System....................

B 3/4 11-5 Ventilation Exhaust Treatment System.................

B 3/4 11-6 Explosive Gas Mixture................................

B 3/4 11-6 Main Condenser Air Ejector Radioactivity Release Rate..............................................

B 3/4 11-6 Drywell Vcnting or Purging...........................

B 3/4 11-7 3/4.11.3 SOLID RADIOACTIVE WASTE..............................

B 3/4 11-7 3/4.11.4 TOTAL DOSE (40 CFR PART 190).........................

B 3/4 11-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 CRAM...................................

B 3/4 12-1 3/4.12.2 LAND USE CENSUS......................................

B 3/4 12-1 3/4.12.3 INTERLA BORATORY COMPARI SON PROGRAM...................

B 3/4 12-2 l

BRUNSWICK - UNIT 1 XIIA Amendment No.

(BSEP-1-133)

INDEX ADMINISTRATIVE CONTROLS SECTION PACE 6.1 RESPONSIBILITY............................................

6-1 6.2 ORCANIZATION 6.2.1 0FFSITE..............................................

6-1 6.2.2 FACILITY STAFF.......................................

6-1 6.2.3 ONSITE NUCLEAR SAFETY (ONS) l Function.............................................

6-8 Responsibilities.....................................

6-8 Authority............................................

6-8 6.2.4 SHIFT TECHNICAL ADVIS0R..............................

6-8 l

6.3 FACILITY STAFF QUALIFICATION..............................

6-8 6.4 TRAININC..................................................

6-8 6.5 REVIEW AND AUDIT 6.5.1 NUCLEAR SAFETY REVIEWERS.............................

6-9 6.5.2 SAFETY EVALUATIONS AND INDEPENDENT REVIEW CONTROL l

1 Safety Evaluations...................................

6-9 l

Procedures, Tests, and Experiments...................

6-10 Modifications........................................

6-10 Operating License / Technical Specifications...........

6-10 6.5.3 PLANT NUCLEAR SAFETY C0KMITTEE (PNSC)

Function.............................................

6-11 Composition..........................................

6-11 Alternates...........................................

6-11 Meeting Frequency....................................

6-11 Quorum...............................................

6-11 Activities...........................................

6-12 Authority............................................

6-13 Records..............................................

6-13 BRUNSWICK - UNIT 1 XIV Amendment No.

1

(BSEP-1-133)

INDEX ADMINISTRATIVE CONTROLS SECTION PACE 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 CORPORATS QUALITY ASSURANCE AUDIT PROGRAM Function.............................................

6-16 Audits...............................................

6-16 Records..............................................

6-17 Authority............................................

6-17 Personne1............................................

6-17 6.5.6

'OUTSIDE ACENCY INSPECTION AND AUDIT PROGRAM..........

6-18 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 i

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 BRUNSWICX - UNIT 1 XV Amendment No.

.l

. (BSEP-1-133)

INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.10 RECORD RETENTION.........................................

.6-25 6.11 RADIATION PROTECTION PR0 GRAM.............'................

6-27 6.12 HICH RADIATION AREA......................................

6-21 6.13 0FFSITE DOSE CALCULATION MANUAL (0DCM)...................

6-28 6.14 PROCESS CONTROL PROGRAM (PCP)............................

6-28 6.15 MAJOR CHANCES TO LIQUID, CASEOUS, AND SOLID WASTE TREATMENT SYSTEMS.........................

6-29 t

1 I

l BRUNSWICK - UNIT 1 XVI Amendment No.

(BSEP-1-133)

RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste' treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent from the site to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed 0.12 mrem to the total body or 0.4 mrem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

a.

With radioactive liquid waste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or sub-system, and reason for the inoperability.

2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary of description of action (s) taken to prevent a recur-rence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQt!I??MENTS 4.11.1.3 Doses due to liquid releases from the site to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the ODCM.

t k

NOTE:

See Bases 3/4.11.1.3 BRUNSWICK - UNIT 1 3/4 11-9 Amendment No.

(BSEP-1-133)

ADMINISTRATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 NUCLEAR SAFETY REVIEWERS 6.5.1.1 Individuals shall be designated / approved by the General Manager -

Brunswick Plant for performing nuclear safety reviews.

6.5.1.2 Individuals designated under Specifi ation 6.5.1.1 above shall have an academic degree in an engineering or related field or equivalent and two years related experience.

6.5.1.3 A list shall be maintained of individuals qualified to perform nuclear safety reviews, including additional individuals whose expertise may be necessary during the reviews to assure that the reviewers collectively possess the background and qualifications in the disciplines necessary and important to the specific review.

6.5.1.4 The list specified in Specification 6.5.1.3 above shall include the disciplines for which each individual is qualified.

6.5.1.5 For those cases where interdisciplinary reviews are required, as many individuals as necessary shall be used to perform the nuclear review function.

6.5.1.6 One of the two nuclear safety reviewers shall be an individual other than the original preparer of the individual approving the action.

6.5.2 SAFETY EVALUATIONS AND INDEPENDENT REVIEW CONTRCL SAFETY EVALUATIONS 6.5.2.1 A safety evaluation shall be prepared for each of the following:

a.

Changes to procedures required by Specification 6.8, or changes to other procedures that affect' nuclear safety.

b.

Proposed tests or experiments that affect nuclear safety.

c.

Proposed modifications to plant systems or equipment that affect nuclear safety.

d.

Proposed changes to the Technical Specifications.

e.

Proposed changes to the Operating License.

6.5.2.2 Two nuclear safety reviews of the item and safety evaluation (s) prepared in accordance with Specification 6.5.2.1 above shall be performed prior to approval and implementation.

6.5.2.3 The item and associated safety evaluation (s) shall be examined in order to determine whether an interdisciplinary review is required in accordance with Specification 6.5.1.5 above.

BRUNSWICK - UNIT 1 6-9 Amendment No.

ENCIDSURE 6 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50 325 & 50-324

PERATING LICENSES DPR 71 & DPR 62 REQUEST FOR LICENSE AMENDMENT UNIT 2 TECHNICAL SPECIFICATION PAGES 1

l 4

u -

(BSEP-2-137)

INDEX SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS SECTION PACE 2.1 SAFETY LIMITS Thermal Power (Low Pressure or Low Flow).......,

2-1 Thermal Power (High Pressure and High Flow)................

2-1 Reactor Coolant System Pressure...........'.................

2-1 Reactor Vessel Water Level.................................

2-2

+

P 2.2 LIMITING SAFETY SYSTEM SETTINGS Reactor Protection System Instrumentation Setpoints........

2-3 BASES 2.1 SAFETY LIMITS Thermal Power (Low Pressure or Low Flow)...................

B 2-1 Thermal Power (High Pressure and High Flow)................

B 2-2 Reactor Coolant System Pressure............................

B 2-3 Reactor Vessel Water Leve1.................................

B 2-3 I

I 2.2 Limiting Safety System Settings Reactor Protection System Instrumentation Setpoints........

B 2-4 i

i BRUNSWICK - UNIT 2 III Amendment No, i

4 (BSEP-2-137)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.0 APPLICA8ILITY.............................................

3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS s

3/4.1.1 SHUTDOWN MARCIN......................................

3/4 1-1 3/4.1.2 REACTIVITY AN0MALIES.................................

3/4 1-2 3/4.1.3 CONTROL RODS Control Rod Operability..............................

3/4 1-3 Control Rod Maximum Scram Insertion Times............

3/4 1-5 Control Rod Average Scram Insertion Times............

3/4 1-6 Four Control Rod Group Scram Insertion Times.........

3/4 1-7 l

Control Rod Scram Accumulators.......................

3/4 1-8 Control Rod Drive Coupling...........................

3/4 1-9

' Control Rod Position Indication......................

3/4 1-11 Control Rod Drive Housing Support....................

3/4 1-13 3/4.1.4 CONTROL ROD PROCRAM CONTROLS l

Rod Worth Minimiser..................................

3/4 1-14 Rod Sequence Control System..........................

3/4 1-15 Rod Block Monitor....................................

3/4 1-17 3/4.1.5 STANDBY LIQUID CONTROL SYSTEM........................

3/4 1-18 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AVERACE PLANAR LINEAR HEAT CENERATION RATE...........

3/4 2-1 3/4.2.2 APRM SETP0INTS.......................................

3/4 2-8 3/4.2.3 MINIMUM CRITICAL POWER RATIO.........................

3/4 2-9 3/4.2.4 LINEAR HEAT CENERATION RATE.....................

3/4 2-15 i

BRUNSWICK - UNIT 2 IV Amendment No.

o (BSEP-2-137)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION............

3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION..................

3/4 3-9 l

3/4.3.3 EMERCENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION...................,................

3/4 3-30 3/4.3.4 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION.........

3/4 3-39 3/4.3.5 MONITORING INSTRUMENTATION Seismic Monitoring Instrumentation...................

3/4 3-44 Remote Shutdown Monitoring Instrumentation...........

3/4 3-47 Accident Monitoring Instrumentation..................

3/4 3-50 Source Range Monitors................................

3/4 3-53 Chlorine Detection System............................

3/4 3-54 Chloride Intrusion Monitors..........................

3/4 3-55 Fire Detection Instrumentation.......................

3/4 3-59

' Radioactive Liquid Effluent Monitoring Instrumentation...................................

3/4 3-62 Radioactive Caseous Effluent Monitoring Instrumentation...................................

3/4 3-68 3/4.3.6 RECIRCULATION PUMP TRIP ACTUATION INSTRUMENTATION ATWS Recirculation Pump Trip (RPT) System Instrumentation...................................

3/4 3-78 End-of-Cycle Recirculation Pump Trip System Instrumentation...................................

3/4 3-82 3/4.3.7 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION l

INSTRUMENTATION...................................

3/4 3-88 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops..................................

3/4 4-1 Jet Pumps............................................

3/4 4-2 Idle Recirculation Loop Start-up.....................

3/4 4-3 l

3/4.4.2 SAFETY / RELIEF VALVES.................................

3/4 4-4 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE Leakage Detection Systems............................

3/4 4-5 l

Operational Leakage..................................

3/4 4-6 l

BRUNSWICK - UNIT 2 V

Amendment No.

1

s (BSEP-2-137)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.4 REACTOR COOLANT SYSTEM (Continued) 3/4.4.4 C H EM I S TR Y............................................

3/4 4-7 3/4.4.5 SPECIFIC ACTIVITY....................................

3/4 4-10 3/4.4.6 PRESSURE / TEMPERATURE LIMITS Reactor Coolant System.............

2................

3/4 4 Reactor Steam Dome...................................

3/4 4-18 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES.....................

3/4 4-19 3/4.4.8 STRUCTURAL INTECRITY.................................

3/4 4-20 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 HICH PRESSURE COOLANT INJECTION SYSTEM...............

3/4 5-1 3/4.5.2 AUTOHATIC DEPRESSURIZATION SYSTEM....................

3/4 5-3 3/4.5.3 LOW PRESSURE COOLING SYSTEMS

, Core Spray System....................................

3/4 5-4 Low Pressure Coolant Injection System................

3/4 5-7 3/4.5.4 SUPPRESSION P00L.....................................

3/4 5-9 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Primary Containment Integrity........................

3/4 6-1 Primary Containment Leakage..........................

3/4 6-2 Primary Containment Air Lock.........................

3/4 6-4 Primary Containment Structural Integrity.............

3/4 6-6 j

Primary Containment Internal Pressure................

3/4 6-7 Primary Containment Average Air Temperature..........

3/4 6-8 l

j BRUNSWICK - UNIT 2 VI Amendment No.

s (BSEP-2-137)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PACE 3/4.6 CONTAINMENT SYSTEMS (Continued) 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Suppression Chamber...................................

3/4 6-9 l

Suppression Pool Cooling..............................

3/4 6-11 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES.'.................

3/4 6-12 3/4.6.4 VACUUM RELIEF Drywell - Suppression Chamber Vacuum Breakers.........

3/4 6-18 l

Suppression Pool - Reactor Building Vacuum Breakers...

3/4 6-20 3/4.6.5 SECONDARY CONTAINMENT Secondary Containment Integrity.......................

3/4 6-21 Secondary Containment Automatic Isolation Dampers.....

3/4 6-22 3/4.6.6 CONTAINMENT ATMOSPHERE CONTROL Standby Cas Treatment System..........................

3/4 6-25

. Containment Atmosphere Dilution System................

3/4 6-28 0xygen Concentration..................................

3/4 6-29 l

Cas Analyzer Systems..................................

3/4 6-30 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System............

3/4 7-1 Service Water System..................................

3/4 7-2 3/4.7.2 CONTROL ROOM EMERGENCY FILTRATION SYSTEM..............

3/4 7-3 3/4.7.3 FLOOD PROTECTION......................................

3/4 7-6 l

1 BRUNSWICK UNIT 2 VII Amendment No.

i a

,_.--s-,-

,---w--

5 (BSEP-2-137)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM.................

3/4 7-7 3/4.7.5 SNUBBERS..............................................

3/4 7-9 l

3/4.7.6 SEALED SOURCE CONTAMINATION...........................

3/4 7-15 3/4.7.7 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System.........................

3/4 7-17 Spray and/or Sprinkler Systems........................

3/4 7-20 High Pressure CO2 Systems.............................

3/4 7-22 Fire Hose Stations....................................

3/4 7-23 Foam Systems..........................................

3/4 7-26 3/4.7.8 FIRE BARRIER PENETRATIONS.............................

3/4 7-28 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1

.A.C.

SOURCES Operation of One or Both Units........................

3/4 8-1 Shutdown of Both Units................................

3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operation of One or Both Unite....

3/4 8-6 A.C Distribution - Shutdown of Both Units..............

3/4 8-7 D.C. Distribution - Operating.........................

3/4 8-8 D.C. Distribution - Operation of One or Both Units....

3/4 8-12 D.C. Distribution - Shutdown..........................

3/4 8-14 Reactor Protection System Electrical Power Monitoring.

3/4 8-15 l

3/4.9 REFUELINC OPERATIONS 3/4.9.1 REACTOR MODE SWITCH...................................

3/4 9-1 3/4.9.2 INSTRUMENTATION.......................................

3/4 9-3 1

1 r

i BRUNSWICK - UNIT 2 VIII Amendment No.

5 (BSEP-2-137)

INDEX LIMITINC CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION

_ PAC.E.

3/4.9 REFUELINC OPERATIONS (Continued) 3/4.9.3 CONTROL ROD P0SITION..................................

3/4 9-5 3/4.9.4 DECAY TIME............................................

3/4 9-6 3/4.9.5 COMMUNICATIONS........................................

3/4 9-7 3/4.9.6 CRANE AND HOI ST OPERABILITY..........'.................

3/4 9-8 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00L..................

3/4 9-9 3/4.9.8 WATER LEVEL-REACTOR VESSEL............................

3/4 9-10 3/4.9.9 WATER LEVEL-SPENT FUEL STORACE POOL...................

3/4 9-11 3/4.9.10 CONTROL ROD REMOVAL Single Control Rod Removal............................

3/4 9-12 Multiple Control Rod Remova1..........................

3/4 9-14 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1

. PRIMARY CONTAINMENT INTEGRITY.........................

3/4 10-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM...........................

3/4 10-2 l

3/4.10.3 SHUTDOWN MARCIN DEMONSTRATIONS........................

3/4 10-3 3/4.10.4 RECIRCULATION L00PS...................................

3/4 10-4 3/4.10.5 PLANT SERVICE WATER...................................

3/4 10-5 l

i BRUNSWICK - UNIT 2 IX Amendment No.

l J

(BSEP-2-137)

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.i.

LIQUID EFFLUENTS C o n c e n t r a t i o n.. '..'...................................

3/4 11-1 Dose - Liquid Effluents..............................

3/4 11-8 Liquid Radwaste Treatment System.....................

3/4 11-9 Liquid Holdup Tanks..................................

3/4 11-10 3/4.11.2 CASEOUS EFFLUENTS Dose Rate............................................

3/4 11-11 Dose - Noble Cases...................................

3/4 11-15 Dose - Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form..................

3/4 11-16 Caseous Radwaste Treatment System....................

3/4 11-17 Ventilation Exhaust Treatment System.................

3/4 11-18 Explosive Gas Mixture................................

3/4 11-19 Main Condenser Air Ejector Radioactivity Release Rate..............................................

3/4 11-20 Drywell Venting or Purging...........................

3/4 11-21 3/4.11.3 SOLID RADIOACTIVE WASTE..............................

3/4 11-22 3/4.11.4 TOTAL DOSE (40 CFR PART 190).........................

3/4 11-23 I

3/4.12 RADIOLOGICAL ENVIRONMENTAL HONITORINC 3/4.12.1 h0NITORING PROGRAM...................................

3/4 12-1 3

3/4.12.2 LAND USE CENSUS......................................

3/4 12-13 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM...................

3/4 12-15 1

J l

BRUNSWICK - UNIT 2 IXa Amendment No.

$ o I

(BSEP-2-137)

.i

_fNDEX BASES SECTION PACE 3/4.4 REACTOR COOLANT SYSTEM (Continued) 3/4.4.4 CHEMISTRY.............................~................

B 3/4 4-2 3/4.4.5 SPECIFIC ACTIVITY.....................................

B 3/4 4-2 3/4.4.6 PRESSURE / TEMPERATURE LIMITS.........,.................

B 3/4 4-3 3/4.4.7 MAIN STEAM LINE ISOLATION VALVES....................'..

B . (-7 3/4.4.8 STRUCTURAL INTEGRITY..................................

B 3/4 4-7 3/4.5 EMERGENCY CORE COOLING SYSTEM l

3/4.5.1 HICH PRESSURE COOLANT INJECTION SYSTEM................

B 3/4 5-1 3/4.5.2

\\UTOMATIC DEPRESSURIZATION 3YSTEM (ADS)...............

B 3/4 5-1 1

3/4.5.3 LOW PRESSURE COOLING SYSTEMS..........................

B 3/4 _5-2 3/4.5.4 SUPPRESSION P00L..............

4..

B 3/4 5-4 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT...................................

B 3/4 6-1 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS....'..............

B 3/4 6-3 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES..................

B 3/4 6-4 3/4.6.4 VACUUM RELIEF.........................................

B 3/4 6-5 3/4.6.5 SECONDARY CONTAINMENT.................................

B 3/4 6-5 3/4.6.6 CONTAINMENT ATMOSPHERE CONTR0L........................

B 3/4 6-5 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS.................................

B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERCENCY FILTRATION SYSTEM..............

B 3/4 7-1 1

l BRUNSWICK - UNIT 2 XI Amendment No.

I

o o

(BSEP-2-137)

INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS (Continued) 3/4.7.3 FLOOD PROTECTION......................................

B 3/4 7-1 3/4.7.4 REACTOR CORE ISOLATION COOLING SYSTEM.................

B 3/4 7-1 3/4.7.5 SNUBBERS..............................................

B 3/4 7-2 3/4.7.6 SEALED SOURCE CONTAMINATION...........................

B 3/4 7-4 3/4.7.7 FIRE SUPPRESSION SYSTEMS..............................

B 3/4 7-4 3/4.7.8 FIRE BARRIER PENETRATIONS.............................

B 3/4 7-5 3/4.8 ELECTRICAL POWER SYSTEMS.................................

B/3/4 8-1 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH...................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION..................'.....................

B 3/4 9-1 3/4.9.3 CONTROL ROD P0SITION..................................

B 3/4 9-1 3/4.9.4 DECAY TIME............................................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS........................................

B 3/4 9-1 3/4.9.6 CRANE AND HOIST OPERABILITY...........................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL-SPENT FUEL STORACE P00L..................

B 3/4 9-2 3/4.9.8 WATER LEVEL-REACTOR VESSEL, and i

3/4.9.9 WATER LEVEL-REACTOR FUEL STORAGE P00L.................

B 3/4 9-2 3/4.9.10 CONTROL ROD REM 0 VAL...................................

B 3/4 9-2 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.........................

B 3/6 '0-1 3/4.10.2 ROD SEQUENCE CONTROL SYSTEM...........................

B 3/4 10-1 3/4.10.3 SHUTDOWN MARGIN DEMONSTRATIONS........................

B 3/4 10-1 3/4.10.4 RECIRCULATION L00PS...................................

B 3/4 10-1 3/4.10.5 PLANT SERVICE WATER...................................

B 3/4 10-1 BRUNSWICK - UNIT 2 XII Amendment No.

s (BSEP-2-137)

INDEX l

BASES SECTION PACE 3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration........................................

B 3/4 11-1 Dose - Liquid Effluents..............'................

B 3/4 11-1 Liquid Radwaste Treatment System.....................

B 3/4 11-2 Liquid Holdup Tanks..................................

B 3/4 11-3 3/4.11.2 CASEQUS EFFLUENTS Dose Rate.............................................

B 3/4 11-3 Dose-Noble Cases.....................................

B 3/4 11-4 Dose-Iodine-131, Iodine-133, Tritium, and Radionuclides in Particulate Form..................

B 3/4 11-5 Caseous Radwaste Treatment System....................

B 3/4 11-5 Ventilation Exhaust Treatment System.................

B 3/4 11-6

' Explosive Gas Mixture................................

B 3/4 11-6 t:ain Condenser Air Ejector Radioactivity Release Rate..............................................

B 3/4 11-6 Drywell Venting or Purging...........................

B 3/4 11-7 3/4.11.3 SOLID RADIOACTIVE WASTE..............................

B 3/4 11-7 3/4.11.4 TOTAL DOSE (40 CFR PART 190).........................

B 3/4 11-7 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PR0 CRAM...................................

B 3/4 12-1 3/4.12.2 LAND USE CENSUS......................................

B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM...................

B 3/4 12-2 BRUNSWICK - UNIT 2 XIIA Amendment No.

(BSEP-2-137)

INDEX ADMINISTRATIVE' CONTROLS SECTION PACE 6.1

-RESPONSIBILITY............................................

6-1 6.2 ORGANIZATION 6.2.1 0FESITE..............................................

6-1 6.2.2 FACILITY STAFF.......................'................

6-1 6.2.3 ONSITE NUCLEAR SAFETY (CNS) l Function.............................................

6-8' Responsibilities.....................................

6-8 Authority............................................

6-8 6.2.4 SHIFT TECHNICAL ADVIS0R..............................

6-8 6.3 FACILITY STAFF QUALIFICATION..............................

6-8 6.4 TRAININC..................................................

6-8 6.5 REVIEW AND AUD_IT o.5.1 NUCLEAR SAFETY REVIEWERS.............................

6-9 6. 5. ".

SAFETY EVALUATIONS AND INDEPENDENT REVIEW CONTROL i

Safety Evaluations...................................

6-9 Procedures, Tests, and Experiments...................

6-10

)

l Modifications........................................

6-10 i

Operating License / Technical Specificatio..s...........

6-10 6.5.3 PLANT NUCLEAR SAFETY COMMITTEE (PNSC)

Function.............................................

6-11 Composition...........................................

6-11 Alternates.............

6-11 Meeting Frequency....................................

6-11 l

Quorum..................

6-11 Activities...........................................

6-12 Authority............................................

6-13 Records..............................................

6-13 BRUNSWICK

'JNIT 2 XIV Amendment No.

1

._.,,-...-_.,._._.,_m I

(BSEP-2-137)

INDEX ADMINISTRATIVE CONTROLS l

l

[

1 i

SECTION PACE l

l 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 0UTSIDE AGENCY INSPECTION AND AUDIT PROGRAM..........

6-18 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 1

l 1

l l

BRUNSWICK - UNIT 2 XV Amendment No.

's, (BSEP-2-137)

INDEX ADMINISTRATIVE CONTROLS SECTION

PtCE 6.10 RECORD RETENTION.........................................

6-25 6.11 RADIATION PROTECTION PROGRAM..

6-27 i

6.12 HICF RADIATION AREA......................................

6-27 6.13 0FFSITE DOSE CALCULATION MANUAL (0DC:Q...................

6-28 6.14 PROCESS CONTROL PROCRAM (PCP'............................

6-28 6.15 MAJOR CHANCES TO LIQUID, CASEOUS, AND SOLID WASTE TREATMENT SYSTEMS.........................

6-29 l

i BRUNSWICK - UNIT 2 XVI Amendment No.

.m--

_,,,,y

-- 1

(BSEP-2-137)

REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE HOUSING SUPPORT LIMITING CONDITION FOR OPERATION 3.1.3.8 The control rod drive housing support shall be its place when there is fuel in the reactor vessel.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With the control rod drive housing support not in place, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN with!n the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.3.8 The control rod drive housing support shall be inspected after reassembly and verified to be in place prior to start-up any time it has been disassembled or when maintenance has been performed in the control rod drive housing support area.

BRUNSWICK - UNIT 2 3/4 1-13 Amendment No.

_j

o ** e (BSEP-2-137) l RADIOACTIVE EFFLUENTS LIQUID RADWASTE TREATMENT SYSTEM l

LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the

-projected doses due to the'li' quid effluent from the site to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed 0.12 mrem to the total-body or 0.4 meem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

a.

With radioactive liouid waste being discharged without treatment and in excess of the above limits, in lieu of a Licensee Event Report, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1.

Explanation of why liquid radwaste was being discharged without treatment, identification of any inoperable equipment or sub-system, and reason for the inoperability.

2.

Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.

Summary of description of action (s) taken to prevent a recur-rence.

b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS-4.11.1.3 Doses due to liquid releases from the site to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the ODCM.

NOTE: See Bases 3/4.11.1.3 BRUNSWICK - UNIT 2 3/4 11-9 Amendment No.

.