ML20034A844

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Forwards Matl to Support Reactor & Senior Operator Licensing Exams,Per NRC 900323 Request
ML20034A844
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 04/12/1990
From: Wallace E
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9004240420
Download: ML20034A844 (29)
v • d • e


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TENNESSEE VALLEY AUTHORITY SN 157B Lookout Place APR 121990-U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of

)

Docket Nos. 50-259 Tennessee Valley Authority

)

50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - REFERENCE MATERIAL REQUIREMENTS FOR REACTOR /.

OPERATOR LICENSING EXAMINATIONS L

In response to the letter from NRC to TVA dated March 23, 1990, the enclosed material is submitted to support the Reactor Operator and Senior Operator Licensing Examinations. This material is being submitted under separate cover. Additionally, a material index is included as the Enclosure.

If you have any questions please telephone C. T. Dexter (205) 729-3470 or Patrick P. Carier (205) 729-3566.

t Very truly yours, TENNESSEE VALLEY AUTHORITY L-E. G. Wallace, Manager Nuclear Licensing and

+

Regulatory Affairs Enclosure cc: See page 2 9004240420 900412 f

PDR ADOCK 05000259 1

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An Equal Opportunity Employer

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U.S. Nuclear Regulatory Commission ec (Enclosure):

Ms. S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Sonalyst, Inc.

Attnt Rich Miller, 215 Parkway North Waterford,, Connecticut 06385 Mr. B. A. Wilson, Assistant Director 5lk for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Charlie Payne (Reference Material for Operator Exams)

Operator Licensing Section U. S. Nuclear Regulatory Commission, Region II 101 Marietta Street, NW, Atlanta, Georgia 30323 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000

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LESSON PLAN:

BOOK 1 OPL171.996

'NER:

Inadvertent Vessel Draining Events OPL171.035

  • Rod Block Monitor System OPL171.025

OPL171.024

' Rod Worth Minimizer OPL171.039

' Standby Liquid Control System OPL171.018

' Standby Gas Treatment System OPL171.072

'480 V. Load Shedding Logic OPL171.043

' Automatic Depressurization System OPL171.028

' Primary Containment Isolation System OPL171.044

' Residual Heat Rcmeval System OPL171.045

  • High Pressure Coolant Injection OPL171.040

' Reactor Core Isolation Cooling I

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LESSON PLANS: BOOK 2 OPL171.995

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Reactivity Events OPL171.003

  • Reactor Vessel Process Instrumentation OPL171.012
  • Feedwater Level Control OPL171.007
  • Recirculation System

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OPL171.023

  • Traversing Incore Probe System OPL171.019
  • Source Range Monitors OPL171.020
  • 1ntermediate Range Monitors OPL171.021
  • Local Power Range Monitors OPL171.022

' Average Power Range Monitors OPL171.997

  • NER: Powerhouse Flooding Events OPL171.029
  • Reactor Manual Control System l

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.'o LESSON PLANS: BOOK 3 OPL171.056

  • U1, 2. 3 Differences OPL171.087

' Introduction to Admin. Procedures and Tech. Spec.

OPL171.088

' Tech. Spec. Section 1 and 2 OPL171.058

  • Technical Specifications OPL171.071

' Conduct of Operation OPL171.085

  • implementation and Change of Procedures OPL171.078
  • Conduct of Testing OPL171.075

'ONP Radiological Emergency Plan OPL171.086

'BFN Equipment clearance Procedure OPL171.094

' Reactor Power Oscillations OPL171.080

' Trip and Transient Analysic OPL171.066

  • Standard Practices OPL171.053

'Puel Handling OPL171.060

' Refueling Operations OPL171.079

' Temporary Alterations OPL171.068

' Spill Prevention and Countermeasurec OPL171.084

' Liquid Radwaste OPL171.041

  • Control Room Abandonment OPL171.089
  • RSO 6055 - Switch Yard Manual OPL171.092

' Unique Reporting Requirements 1

OPL171.082

  • Emergency Operating Instructions OPL171.065

' Operations Section Instruction Lett.ers l

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BOOK 4 OPL171.998

'NER: Valves OPL171.038

' Diesel Generator and Standby Auxiliary Power OPL171.036

'AC Power Distribution OPL171.037

'DC Systems OPL171.010

' Turbine Lube Oil OPL171.015

'EHC Hydraulic System OPL171.014

'EHC Pressure Control and Logic OPL171.002

' Control Rod Drive Hydraulics OPL171.001

  • BWR Chemistry OPL171.006

" Reactor Water Clean Up System OPL171.004

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BOOK 5 OPL171.050

  • condenser Circulating Water OPL171.051

' Raw Cooling Water OPL171.047

' Reactor Building Closed Cooling Water OPL171.054

  • Control and Station Air OPL171.030

'Off Cas System OPL171.011

  • Condensato System OPL171.052
  • Puel Potl Cooling and Cleanup OPL171.034

' Area Rad. Monitors OPL171.033

  • Process Rad Monitors OPL171.031

' Containment Nitrogen OPL171.026

' Reactor Feedwater System OPL171.009

' Main Steam System OPL171.067

' Heating Ventilation and Air Conditioning OPL171.031

'SSI-002 Safe Shutdown Instructions OPL171.046

'RHRSW OPL171.049

'RSW OPL171.055

  • Secondary Cont. E01-3 OPL171.083
  • Solid Radwaste OPL171.093

' Print Reading OPL171.147

' Turbine Supervisory Instruments i

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i BOOK 7 OPERATING INSTRUCTIONS: VOLUME I 01 I MAIN STEAM 01 2 CONDENSATE 01 3 FEEDWATER 01 23 RHRSW OI 26 FIRE PROTECTION 01 27 CCW OI-30A REFUEL ZONE VENTILATION OI-30B REACTOR ZONE VENTILATION 01 32 SERVICE AND CONTROL AIR 01 32A DW CONTROL AIR 01 39 C0 System 01 47 TURBINE CENERATOR 01 47A EHC SYSTEM 01 47B MAIN TURBINE LUBE OIL OI 47C SEAL STEAM SYSTEM

I-t BOOK 8 OPERATING INSTRUCTIONS: VOLUME 2 01 $7 A SWITCHYARD AND 4160 VOLT A/C 01 57B 480 V/240 VOLT A/C 01 57C 208V/120 VOLT A/C 01 57D DIRECT CURRENT SYSTEMS 01 63 SLC 01 64 CONTAINMENT 01 65 SBGT 01 66 0FF GAS 01 67 EECW 01 68 RECIRC 01 69 RWCU k

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01 70 RBCCW 01 71 RCIC 01 73

'HPCI' 01 74 RHR OI 75 CORE SPRAY 01 76 NITROGEN i

01 78 FUEL POOL COOLING OI 82 D/G's 01 85 CONTROL ROD DRIVE 01 90 RADIATION MONITORING 01 92 SRM OI 92A IRM 01 92B APRM 01 92C RBM 01 99 REACTOR PROTECTION SYSTEM

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BOOK 10 GENERAL OPERATING INSTRUCTION i'

GOI-100-1A UNIT STARTU'1 FROM COLD SHUTDOWN TO POWER OPERATIONS G01 100-1B UNIT STARTUP FROM COLD SHUTDOWN TO HOT STANDBY GOI 100-1C UNIT STARTUP FROM HOT STANDBY TO POWER OPERATIONS GOI 100-3 REFUELING OPERATIONS

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GOI 100-6 ROD WORTH MINIMIZER GOI 100-12A UNIT SHUTDOWN FROM POWER OPERATIONS TO COLD SHUTDOWN GOI 100-12B UNIT SHUTDOWN FROM POWER OPERATION TO HOT STANDBY COI 100-12C UNIT SHUTDOWN FROM HOT STANDBY TO COLD SHUTDOWN s

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AOI 1-1 RELIEF VALVE STUCK OPEN 1-3 MSIV CLOSURE AT POWER 2-1 REACTOR COOLANT HIGH CONDUCTIVITY 3-1 REACTOR LEVEL HIGH/ LOW 6-1 FEEDWATER HEATER STRING ISOLATION 30-1 FIRE PROTECTION VENTILATION LINEUP 30B-1 REACTOR BUILDING VENTILATION FAILURE 30B-2 REACTOR BUILDING SMOKE REMOVAL ABNORMAL OPERATING INSTRUCTIONS i

300-2 TURBINE BUILDING SMOKE REMOVAL ABNORMAL OPERATING INSTRUCTIONS 31-1 CONTROL BAY INSTRUCTION (HIGH RADIATION) 31-2 CONTROL BAY SMOKE REMOVAL 7

32-1 LOSS OF CONTROL AND SERVICE AIR COMPRESSORS 32A-1 LOSS OF DRYWELL CONTROL AIR 32-2 LOSS OF CONTROL AIR 35-1 GENERATOR CONDITION MONITOR ALARM 47-1 UNPLANNED TURBINE TRIP BELOW 30% REACTOR POWER (WITHOUT REACTOR SCRAM) 47-2 REACTOR PRESSURE CONTROL UNIT FAILURE 47-3 LOSS OF CONDENSER VACUUM 57-1A LOSS OF OFFSITE POWER (161 AND 500KV) 57-1B LOSS OF 500KV ABNORMAL OPER ATING INSTRUCTIONS 57-1C LOSS OF 161V 57-2 STATION BLACKOUT 57-4 LOSS OF UNIT PREFERRED 57-5A LOSS OF I & C BUS A 57-5B LOSS OF I & C BUS B 57-6 LOSS OF NON PREFERRED 57-8 LOSS OF 48VDC ANNUNCIATOR POWER 57-9 LOSS OF ANNUNCIATOR PANEL (s) SUPPLIED BY PANEL 9-9 CABINET ONE 64-1 DRYWELL PRESSURE AND/OR TEMPERATURE HIGH, OR EXCESSIVE LEAKAGE INTO DRYWELL 64-2A GROUP 3 RWCU ISOLATION 64-2B GROUP 4 HPCI ISOLATION 64-2C GROUP 5 REACTOR CORE ISOLATION COOLING ISOLATION 64-20 GROUP 6 VENTILATION SYSTEM ISOLATION 64-2E GROUP 8 TRAVERSING INCORE PROBE ISOLATION 64-7 PRIMARY CONTAINMENT NITROGEN USAGE HIGH 66-1 OFF GAS HYDROGEN HIGH 66-2 Orr0AS POST TREATMENT RADIATION HI-HI-HI 68-1 RECIRC PUMP TRIP 68-2 JET PUMP FAILURE 68-3 RECIRCULATION LOOP A OR B SPEED CONTROL FAILURE 70-1 LOSS OF RBCCW 74-1 LOSS OF SHUTDOWN COOLING a

n BOOK 12 BROWNS FERRY ALARM RESPONSE PROCEDURES:

PANEL 2-9-3 PANEL 2-9-4 PANEL 2-9-8 PANEL 2-9-20 PANEL 2-9-7 PANEL 2-9-6 PANEL 2-9-5 i

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BROWNS FERRY FUNDAMENTAL TRAINING

' Heat Exchanges and Condensers

'Demineralizers and Ion Exchangers

' Valves

  • Temperature Sensors
  • Controllers and~Positioners
  • Radiation Detection and Nuclear Instrumentation-l

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I BOOK I4 OSIL 16 KEYS 25 OVERTIME 34

-REPORT - DAILY PLANT OPERATIONS REPORT BY PHONE 56 APPROVED CLEARANCE LIST 62 ANNUNICATOR TRACKING PROGRAM 64 SYSTEM PRE-OPERABILITY CHECKLIST WALKDOWNS 65 SIGNATURE AUTHORITY 68 DOCUMENT REVIEW AND DEFICIENCY TRENDING AND TRACKING 70 PERIODIC AUDITS

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BOOK 15 SITE DIRECTOR STANDARD PRACTICES 2.11 IMPLEMENTATION AND CHANGE OF SITE PROCEDURES AND INSTRUCTION 3.8 NONCONFORMING MATERIALS, PARTS OF COMPONENTS 3.12 CSSC AND NON-CSSC LISTING 3.15 INDEPENDENT VERIFICATION 7.6 MAINTENANCE REQUEST AND TRACKING u

9.1 PROCESSING DRAWING DISCREPANCIES 11.5 PROTECTED ARRA ACCESS AUTHORIZATION - PERSONNEL 11.6 VITAL AREA ACCESS AUTHORIZATION - PERSONNEL 11.11 VISITOR CONTROL AND RESPONSIBILITIES t -

12.5 TECHNICAL SPECIFICATION INTERPRETATIONS 12.11 SPECIAL REQUIREMENTS AND COMPENSATORY MEASURES 14.9 EQUIPMENT CLEARANCE PROCEDURE 14.11 PERSONAL PROTECTIVE EQUIPMENT 14.15 ENTRY AND WORK IN THE PRIMARY CONTAINMENT 22.1 TORNADO PROCEDURE 22.3 PERSONNEL ACCOUNTABILITY AND EVACUATION 34.2 MEDICAL EMERGENCY RESPONSE 34.3 RAZARDOUS MATERIALS RESPONSE

'T BOOK 16 EMERGENCY PLAN IMPLEMENTING PROCEDURE 4

01 EMERGENCY PLAN CLASSIFICATION LOGIC i

02 NOTIFICATION OF UNUSUAL EVENT 03 ALERT 04 SITE AREA EMERGENCY 05 GENERAL EMERGENCY 06 ACTIVATION AND OPERATION OF THE TECHNICAL SUPPORT CENTER

i 07 ACTIVATION AND OPERATION OF THE OPERATIONS SUPPORT CENTER 08 PERSONNEL ACCOUNTABILIT).' AND EVACUATION.

10 MEDICAL EMERGENCY PEOCEDURE 11 SECURITY AND ACCESS CONTROL 13 RADIOCHEMICAL LABORATORY PROCEDURE 14 RADIOLOGICAL CONTROL PROCEDURES 15 EMERGENCY EXPOSURS 16 RECOVERY PROCEDUEES 17 EMERGENCY EQUIPMENT AND SUPPLIES 18 TORNADO EMERGENCY PROCEDURE 19 COMMUNICATIONS SYSTEMS AND EMERGENCY NOTIFICATION LI6T 20 PLANT DATA APP. A EMERGENCY ACTION LEVELS

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BOOK 17 PLANT KANAGER INSTRUCTIONS 7.2 PREVENTION OF FOREIGN MATERIAL IN THE REACTOR VESSEL CAVITY AND TORUS 8.1 TEMPORARY ALTERATIONS 12.1 DUTIES AND RESPONSIBILITIES OF THE SHIFT TECHNICAL ADVISOR 12.6 IMPLEMENTATION AND MAINTENANCE OF EMERGENCY OPERATINC INSTRUCTIONS 12.10 PLANT EQUIPMENT DEFICIENCY TAGS 12.11 LOST OR UNSECURED ARTICLE RECOVERY 12.12 CONDUCT OF OPERATIONS 12.15 SYSTEM STATUS CONTROL 15.4 UNIQUE REPORTING REQUIREMENTS 15.6 LICENSE EVENT REPORT

-i 15.8 UNIT TRIP REACTOR TRANSIENT, AND PLANT TRANSIENT ANALYSIS 15.10 TRACK!NG OF LIMITING CONDITIONS FOR OPERATIONS 4

17.1 CONDUCT OF TESTING 4

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E01 2 PRIMARY CONTAINMENT CONTROL E01 3 SECONDARY CONTAINMENT.AND RADI0 ACTIVE RELEASE CONTROL

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