ML20151E482
| ML20151E482 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 07/06/1988 |
| From: | Benton C TENNESSEE VALLEY AUTHORITY |
| To: | Moorman J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8807260087 | |
| Download: ML20151E482 (13) | |
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TENNESSEE VALLEY AUTHORITY Power Operations Training Center P.O. Box 2000 Soddy-Daisy,. Tennessee 37379 July 6, 1988 y9 g
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o Mr. Jim Moorman U.S. Nuclear Regulatory Commission Operator Licensing Section 101 Marietta Street, NW Suite 2900 Atlanta, Georgia 30323
Dear Mr. Moorman:
SUBJECT:
SRQUOYAH NUCLEAR PLANT MATERIAL FOR NRC RXAMS Enclosed is the material you requested for use in preparation of the examination scheduled to be administered the week beginning December 12,'1988, with the exception of Standing Orders.
Prior to initiation of Prelicense class the Standing orders, revised Prelicense lesson plans, and any other revisions on material already sent will be mailed to you September 1988.
Refer to Attachment A for an itemized list of material.
After the examinations have been administered, it is requested that this information package be returned to me at the address given above.
Similar updated information will be sent for future Sequoyah Nuclear Plant examinations.
Please acknowledge receipt of this package to me, and if you have any questions about the material or if you desire additional information please call at (615) 874-1304.
Very truly yours.
TENNESSEE VALLEY AUTHORITY C. T. Benton Manager, SQN Operator Training Croup fY 8807260087 800706
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{,CR ADOCK 0500g7 An Equal Opportunity Employer
i ATTACHMENT A GENERAL OPERATING INSTRUCTIONS INSTRUCTION REVISION GOI-1 76 GOI-2 55 GOI-3 37 GOI-4 3
GOI-5 27 GOI-6 40 RADIOLOGICAL EMERGENCY PLAN - IMPLEMENTING PROCEDURES DOCUMENT IP-1 14 IP-2 11 IP-3 13 1
IP-4 13 IP-5 16 IP-6 19 IP-7 4
IP-8 13 IP-10 12 SQN PRELICENSE LESSON PLANS SIMULATOR MALFUNCTIONS ANNUNCIATOR RESPONSES SYSTEM DESCRIPTIONS (R0 CERTIFICATION LESSON PLANS)
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SYSTEM OPERATING INSTRUCTIONS INSTRUCTION RRVISION SOI-2.1 &-3.1 41 SOI-5.1 & 6.1 17 SOI-15 21 SOI-62.1 39 l
SOI-62.2 23 l
'I SOI-62.3 16 SOI-68.2 29 i
SOI-74.1 44 S01-83.1 9
SOI-85.1 20 l
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TECHNICAL INSTRUCTIONS i
i TI-28 CURVE BOOK 69 l
l TECHNICAL SPECIFICATIONS l
Amendment 69, 4/4/88 73 i
SQN QUESTION AND ANSWER BANK t
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ADMINISTRATIVE INSTRUCTIONS INDEX Instruction Revision Title AI-2 30 Assignment of Responsibility AI-3 43 Clearance Procedure AI-4 71 Preparation, Review, Approval and Use of Site Procedure / Instructions '
AI-5 42 Shif t and Relief Turnover AI-6 15 Log Entries and Review AI-7 48 Recorder Charts and Quality Assurance Records AI-8 19 Access to Containment - Units 1 and 2 1
AI-9 27 Control of Temporary Alterations and Use of the Temporary Alterations Order AI-10 4
Recall of Personnel to Plant AI-18 50 File Package 18-Notification and Licensee Event Report (LER)
AI-30 18 Nuclear Plant Method of Operation RADIOLOCICAL CONTROL INSTRUCTIONS RCI-1 35 Radiological Control Program RCI-10 13 Alara Planning RCI-13 8
Access Control of High Radiation Areas Where Radiation Intensity is Creater than or Equal to 1000 MREM / HOUR RCI-14 13 Radiation Work Permit (RWP) Program
ABNORMAL OPERATING INSTRUCTION INDEX Instruction Revision Title AOI-1 21 Reactor Trip, - Unit 1 or 2 - CANCELLED A01-2 12 Malfunction of Reactor. Control System, - Units 1-and 2 AOI-3 7
Malfunction of Reactor' Makeup Control, - Units l' and 2 AOI-4 9
Nuclear = Instrumentation Malfunctions, Units 1
,and 2 A01-5 10 Unscheduled Removal of an RCP(s) Below P Units 1 and 2 AOI-6 20 small Reactor Coolant System Leak, (Mode 1, 2 or-
- 3) or Shutdown LOCA (Mode 4 or 5) - Units 1 or 2 AOI-7 13 Probable Maximum Flood, - Units 1 and.2 AOI-8 18 Tornado Watch / Warning, - Units 0,1 and 2 AOI-9 10 Earthquake, - Units 1 and 2 AOI-10 13 Loss of Control Air, - Units 1 and 2 AOI-11 5
Loss of Condenser Vacuum, - Units 1 and-2
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AOI-12 6
Loss of Containment Integrity, - Units 1 and 2 AOI-13 10 Loss of Essential Raw Cooling Water, - Units 1 and 2 AOI-14 8
Loss of RHR Shutdown Cooling - Units 1 and 2 AOI-15 9
Loss of Component Cooling Water, - Units 1 and~2 AOI-16 9
Loss of Normal Feedwater, - Units 1 and 2 AOI-17 13 Turbine and Generator trips, - Units 1 and 2 AOI-18 8
Malfunction of Pressurizer Pressure Control System. - Units 1 and 2 A01-19 15 Recovery From a Spurious Safety Injection - Unit 1 or 2 - CANCELLED
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ABNORMAL OPERATING INSTRUCTION INDEX Instruction Revision Title
-AOI-20 7
Malfunction of Pressurizer Level Control System,
- Units 1 and 2 AOI-21.1 10 Loss of 125V DC Vital Battery Board I, - Unit 1 AOI-21.2 11 Loss of 125V DC Vital Battery Board II,
. Unit 1 AOI-21.3 7
Loss of 125V DC Vital Battery Board III. - Unit 1 AOI-21.4 7
Loss of 125V DC Vital Battery Board IV, - Unit 1 AOI-21.5 5
Loss of 125V DC Vital Battery Board I - Unit 2 AOI-21.6 6
Loss of 125V DC Vital Battery Board II, - Unit 2 AOI-21.7 7
Loss of 125V DC Vital Battery Board III, - Unit 2 AOI-21.8 7
Loss of 125V DC Vital Battery Board IV, - Unit 2 AOI-22 7
Break of Downstream Dam, - Units 1 and 2 AOI-23 6
Reactor Coolant Pump Seal Abnormalities, - Units 1 and 2 AOI-24 6
Steam Generator Tube Leak, - Unit 1 or 2 AOI-25.1 5
Loss of 120V AC Vital Instrument Power Board 1-I,
- Unit 1 AOI-25.2 5
Loss of 120V AC Vital Instrument Power Board 1-II, - Unit 1 AOI-25.3 5
Loss of 120V AC Vital Instrument Power Board 1-III. - Unit 1 AOI-25.4 5
Loss of 120V AC Vital Instrument Power Board 1-IV, - Unit 1 AOI-25.5 4
Loss of 120V AC Vital Instrument Power Board 2-I,
- Unit 2 AOI-25.6 4
Loss of 120V AC Vital Instrument Power Board 2-II - Unit 2
ABNORMAL OPERATING INSTRUCTION INDEX Instruction Revision Title AOI-25.7 4'
Loss of 120V AC Vital Instrument Power Board 2-III, - Unit 2 AOI-25.8 4
Loss of 120V AC Vital Instrument Power Board 2-IV, - Unit 2 AOI-26 1
Loss of Control Room Annunciators - Units 1 and 2 AOI-27 9
- Control Room Inaccessibility. - Units 1 and 2 A01-28 2
Fuel Cladding Failure or High Activity in Reactor Coolant, - Units 1 and 2 AOI-29 3
Dropped or Damaged Fuel Assembly or Refueling Cavity Seal Failure, - Units 1 and 2 AOI-30 5
Plant Fires, - Units 0, 1 and 2 AOI-31 4
Abnormal Release of Radioactive Materials, -
Units 1 and 2 AOI-32 1
Emergency Shutdown, - Units 1 and 2 AOI-33 2
Chlorine Release, - Units 1 and 2 AOI-34 2
Emergency Boration, - Units 1 and 2 AOI-35 10 Loss of Offsite Power, - Units 1 and 2 AOI-36 2
Loss of Reactor Coolant Flow Due to RCP Locked Rotor, - Units 1 and 2 - Cancelled
SQN SURVEILLANCE INSTRUCTIONS INDEX INSTRUCTION REVISION TITLE' i
SI-2 55 Shift Log - Units 1 and 2 SI-3 63 Daily. t!)ekly and Monthly Logs - Units 0, 1 and 2 SI-7 43 Electrical Power System:
Diesel Generators -
Unit 0 SI-7.1 11 Diesel Generator AC Electrical Power Source 1
Operability Verification (Diesel Generator /Offsite Source) - Unit 0 SI-8 11 Boric Acid Flow Paths - Temperature Verification
. Units 1 and 2 SI-17 23 Containment Shield Building Emergency Gas Treatment System Flow - Unit 0 SI-21 20 Auxiliary Building Gas Treatment System - Units 1 and 2 SI-24 13 Control Room Air cleanup Subsystem - Unit 0 SI-32 22 Component Cooling Water Valves (Position Verificatien) - Units 1 and 2 l
SI-33 28 ERCW Valves Servicing Safety Related Equipment (Common) - Unit 0 SI-33.1 9
ERCW Valves Servicing Safety Related Equipment -
Units 1 and 2 SI-64 15 Boric Acid Flow Paths - Valve Position Verification - Unito 1 and 2 SI-78 11 Power Range Neutron Flux Channel Calibration by Heat Balance Comparison'(Daily) - Units 1 and 2
EMERGENCY INSTRUCTION INDEX i
Instruction Revision Title E-0 3
Reactor Trip or Safety Injection - Units y
1 and 2 i
ES-0.1 2
Reactor Trip Response, Units 1 and 2.
ES-0.2 3
SI Termination, Units 1 and:2 ES-0.3 4
Natural Circulation Cooldown, Units 1 i
and 2
.j E-1 4
Loss of Reactor or Secondary Coolant, j
Unit 1 and 2 1
ES-1.1 1
Post LOCA Cooldown, Unit 1 and 2 ES-1.2 5
Transfer to RHR Containment Sump, Units 1 and 2 ES-1.3 1
Transfer to Hot Leg' Recirculation E-2 3
Faulted Steam Generator Isolation, Units 1 and 2' E-3 4
Steam Generator Tube Rupture, Units 1 and 2 ES-3.1 1
SI Termination Following SGTR, Units 1 and 2 l
ES-3.2 1
Post - SGTR Cooldown Using Backfill ES-3.3 1
Post - SGTR Cooldown by Ruptured S/G Depressurization i
E-FOP 1
Foldout Page, Units 1 and 2 l
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FUEL HANDLING' INSTRUCTIONS INDEX Instruction Revision Title FHI-l 55 Receiving, Returning. Inspecting, and Storing'New I
' Fuel and Inserts - Units 1 and 2.
FHI-2 12' Spend Fuel P!t Bridge and Spent Fuel Handling Tool - Units 1 and 2 FHI-3 13 Upender and Fuel Transfer' Device and New Fuel Elevator - Units 1 and 2 FHI-4 12 Hanipulator Crano - Units 1 and 2 FHI-5 6
RUC Change Fixture - Units l' and 2 i
FHI-6 22 Preparation for Refueling - Units 1 and 2 FHI-7 23 Refueling Operation - Units 1 and 2 FHI-8 9
Recovery From Refueling - Units 1 and 2 FHI-10 6
Fuel Length Control Rod Drive Shaft Latching ~and Unlatching - Units 1 and 2 i
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Emergency Contingency Actions ECA-0.0 2
Loss of All AC Power. Units 1 and 2 ECA-0.1 0
Recovery from Loss of All AC Power without SI=
Required ECA-0.2 0
Recovery from Loss of All AC Power with SI Required ECA-1.1 0
Loss of'RHR Sump Recirculation, Units 1 and 2 ECA-1.2 0
LOCA Outside Containment, Units 1 and 2
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ECA-2.1 0
Uncontrolled Depressurization of ALL Steam Generators, Units.1 and 2 ECA-3.1 0
SGTR and LOCA - Subcooled Recovery, Unit 1 and 2 ECA-3.2 0
SGTR and LOCA - Saturated Recovery, Units 1 and 2
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FUNCTION RESTORATION GUIDELINES INDEX Instruction Revision Titlo FR-0
'A Status Trees FR-S.1 3
Response'to Nuclear Power Generation /ATWS FR-S.2 0
Response to Loss of Core Shutdown FR-C.1 1
Response to Inadequate Core Cooling FR-C.2 0
Response to Saturated Core Cooling FR-H.1 2
Response to Loss of Secondary Hoat Sink -
Units 1 and 2 FR-H.2 1
Response to Steam Generator Overpressure -
Units 1 and 2 FR-H.3 2
Response to Steam Generator High Level FR-H.4 1
Response to Loss of Normal Steam Release Capabilities - Units 1 and 2 FR-H.5 0
Response to Steam Generator Low Level FR-P.1 2
Response to Pressurized Thermal Shock -
Units 1 and 2 FR-P.2 2
Response to Cold Overpressure Condition FR-2.1 2
Response to High Containment Pressure FR-2.2 1
Response to Containment Flooding - Units 1 and 2 FR-2.3 2
Response to High Containment Radiation -
Units 1 and 2 I
FR-I.1 1
Response to High Pressurizer Level --
Units 1 and 2 FR-I.2 0
Response to Low Pressurizor Level FR-I.3 2
Response to Voids in. Reactor Vessel -
Units 1 and 2
SEQUOYAH FLOW & ELECTRICAL PRINTS 47W809-1 Chemical'and Volume Control System 47W810-1 Residual Heat Removal. Control System 47W811-1 Safety Injection System 47W811-2 SIS Upper Head Injection System 47W812-1 Containment Spray System 47W813-1 Raactor Coolant System 45N721-1 6900V Unit Boards 1A & IB Single Lines 45N724-1 6900V Shutdown Board 1A-A Single Line 45N724-2 6900V Shutdown Board IB-B Single Line 45N505 Main Single Line 15E500-1,-2 Station Aux Power System u
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