ML19325C671
| ML19325C671 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 10/06/1989 |
| From: | Shelton D TOLEDO EDISON CO. |
| To: | Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 1-895, NUDOCS 8910170165 | |
| Download: ML19325C671 (35) | |
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-TOLEDO-EDISONi
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A Centem Energy Cmpany I',
DONALD C. SHELTON
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. Docket Numbar 50-346 Mel ai um p
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- Licens'e Number ' NPF-3 '
b Serial. Number 1-895
- October: 6, 1989-
, kI Mr.[Geoffrey C.'
Vright, Chief.
Operations Branch United States Nuclear. Regulatory Commission s
Region.III-799 Roosevelt Road
]
..d LClen~lEllyn,:IL 60137
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Subject:
Operator and Senior Operator Licensing Examination Reference i
Material
Dear Mr."vright:
As! requested by your letter dated August-3, 1989 (Log Number.1-2131), copies
. of :the revised. reference materials were submitted to Mr. T. Reidinger of Region =III, and-Mr. R. Moffitt of Pacific Northwest Laboratory on September l 15,-' 1989.' = - This reference material. concerns Operator & Senior Operator i
~ Licensing Examinations scheduled for the week of December 11,-1989 for the O
Davis-Besse Nuclear Power Station, Unit Number 1.
s 1
Attached is the listing of-the revised materials that were submitted to the individuals above.
Should you have any questions, please call i
Mr. R. V. Schrauder, Nuclear Licensing Manager, at (419) 249-2366.
1 Sincerely, Il 3----
l GAB /ssg.
attachment cc:
P.' M. Byron, DB-1 NRC Resident Inspector T. V. Vambach, DB-1 NRC Senior Project Manager v/o SNRC Document Control Desk f
8910170165 891006 lf/
PDR ADOCK 05000346 L
.Y PNU THE TOLEDO ED! SON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDC. CWC 43652 y-y,
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'OLD BOOK NUMBER
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- DOCUMENT NAME-NUMBER y
1 3
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,( dl ABNORMAL' PROCEDURES MANUAL 1-b'$
lDB-OP-02500 AB'1203.01 Turbine Trip.
e'
~ Serious Station Fire DB-OP-02501_ ;AB'1203.02 EL
-DB-OP-02502 AB 1203.03 Cooldown Without BVST and No 4
[c Offsite Power.
bu.
DB-OP-02503
'AB.1203.04 Depressurization of the RCS with-l Only. Safety Grade Equipment h h
- DB-OP-02504, AB 1203~.07 Rapid Shutdown p
- DB-0P-02505 AB 1203.08
. Loss of Neutron Flux-Indication-u
.DB-OP-02506; AB 1203.10 Condenser Tube Leak s
DB-OP-02507..
. Traveling Screen Blockage AB 1203.11:
a s
kM LDB-OP-025081 - AB11203.12
-Control Room Evacuation ou, AB,1203.16.
Loss.of. Reactor Coolant System Lr
'DB-0P-02510 -
Boron u
'DB-OP-02511 AB 1203.17 Losstof Service Water Pumps /
Systems t
'DB-OP-02512
- AB 1203.18 Loss of RCS Makeup Pump (s)
DB-OP-02513 AB.1203.19
- Pressurizer Systems Abnormal
- Operation DB-0P-02514 AB 1203.20 Loss of Turbine Plant Cooling Vater Pump (s) l
- DB-OP-02515 AB 1203.21 Reactor Coolant Pump and Motor Abnormal Operation 2
DB 0P-02516 AB 1203.23 Control Rod Drivo Malfunctions
+
DB-0P-02517 AB 1203.24~
Circulating Vater Pump Trip /
Circulating Vater System Ruptures DB-0P-02518. AB 1203.25 High Condenser Pressure
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OLD' BOOK
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NUMBER NUMBER DOCUMENT'NAME NUMBER DB-0P-02519' AB 1203.26 Serious Control Room Fire 1
DB-OP-02520-.AB 1203.27-Load Rejection I
DB-OP-02521 AB 1203.28 Loss of AC Bus Power Sources
'I DB-OP-02522.
AB 1203.29-Small RCS Leaks-I DB-OP-02523i ~AB_1203.31 Component Cooling Vater System Malfunctions
~
.DB-OP-02524 AB 1203;32.
Steam Generator Feedvater Chemistry Out of Spec '
DB-OP-02525 AB 1203.33-Steam Leaks
'DB-0P-02526 AB 1203.34 Steam Generator Overfill DB-OP-02527 AB 1203.35 Losslof Decay Heat Removal System
'DB-OP-02528l AB 1203.36 Loss of Instrument Air DB-OP-02529 AB 1203.37 Pipe Procedure i
DB-OP-02530
~MB 1203.38 Puel Handling Accident
= DB-OP-02531-LAB 1203'40 Steam Generator Tube Leak DB-OP-02532' AB 1203.41 Loss.of NNI/ICS Power DB-OP-02533 AB 1203.42 Control Room Emergency Ventilation Load Shedding DB-0P-02535 AB 1203.30 High Activity in the Reactor Coolant System DB-OP-02536~
AB 1203.14 Toxic Gas and Liquid Release DB-0P-02537 AB 1203.39 Radioactive Spills
. DB-0P-02861 AB 1203.22 High Radiation DB-0P-02862 AB 1203.13 High Airborne Activity or Radiation
' Levels i
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16
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NEW OLD ~
BOOK-
{
' NUMBER NUMBER-DOCUMENT NAME NUMBER.
h
/ ADMINISTRATIVE PROCEDURES 2
DB-0P-00015 AD 1803.00 Safety Tagging Procedure' DB-OP-00010 "AD'1803.02-Operational Information Tags
.DB-DP-00003-AD 1805.00 Procedure Preparsi. - and-Maintenance Y
'DB-TS-00004 AD 1807.00 Control of Conditions Adverse to Quality
-n IS-DP-00506' AD'1808.06 Lock and Key Procedure DB-OP-00020-.AD"1823.00' Control of-Jumper and Lifted Vires, and Temporary Mechanical j
u Modifications 1
1 DB-DP-00013..AD 1838.00 Surveillance and Periodic Test 1;'
AD 1838.01
. Program
- DB-0P-00000
'AD.1839.00' Conduct of Operations
?
JDB-0P-00008 ADf1839.02
Operation and Control of Locked Valves L
-DB-OP-00009 AD 1839.03
' Operation and Control of Capped Valves
'DB-OP-00200 AD 1839.04
- Shift Technical Advisor DB-0P-00100-AD'1839.05-Shift Turnover 1
I-DB-0P-00005 Operating Logs and Reading Sheets DB-PN-00007' AD 1844.02 Control of Vork (MVO)
'HS-SF-00004
.AD 1844.10 Safe Work Procedure for Confined' Spaces DB-HP-00006' AD 1850.00 Radvaste Management DB-CH-00004 AD 1850.01 Radioactive Liquid Release r
DB-HP-01510 AD 1850.02.
Solid Radioactive Vaste Processing and Handling L
DB-CH-00006 AD 1850.03 Radioactive Gaseous Release 3
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' OLD.~
' BOOK i
3
' NUMBER '
NUMBER DOCUMENT NAME NUMBER.
j s
DB-OP-00002'-
Operations Department' Event /
'2 Incident Notifications and.
i Actions DB-0P-000035
Operations Department Monthly Activity Log
]
DB-OP-00016 Removal and Restoration of Station Equipment NG-0A-00702 Potential-Conditions Adverse to Quality Reporting ia ALARM PROCEDURES 3
DB-OP-020011 AP 3001 Series Alarm Panel l' DB-0P-02002
'AP 3002~ Series Alarm Panel 2 DB-0P-02003'. AP 3003 Series
- DB-0P-02003.01-Containment Refueling Canal Level b
DB-OP-02003.02 Spent. Fuel Pool-Temperature High DB-OP-02003.03 Spent Fuel Pool.Demineralizer Inlet. Temperature High' L'
DB-OP-02003.04 BWST Recirculation Heat Exchanger Outlet Temperature Low i'
DB-0P-02003.06 Containment Spray Pump 1 Discharge Flow Hi l'
DB-0P-02003.08.
Containment Spray Pump 2 Discharge Flov Hi' DB-0P-02003.ll Containment Refueling Canal-Skimmer Differential Pressure
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p
- DB-0P-02003.12-Spent Fuel Pool Level
' DB-0P-02003.13 Spent Fuel Pool Demineralizer Differential Pressure t
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NEV OLD
-r NUMBER NUMBER DOCUMENT NAME-NUMBER-e >.
L-8 DB-0P-02003;141 BVST Recirculation Heat Exchanger-3 Flow High J
DB-OP-02003.15 Core Flood Tank 1 Isolation Valve
.Not'Open i
DB-OP-02003.16 Containment Spray Pump 1 Discharge Flow Lo DB-OP-02003.17 Co're Flood Tank 2 Isolation Valve
'l
?
s Not Open.
DB-0P-02003.18
_ Containment. Spray Pump 2 Discharge Flow Lo.
DB-OP-02003.21; Spent Fuel Pool Skimmer Filter Differential Pra.ssure DB-0P-02003.22 Spent Fuel Pool Purification Flow I
-DB-OP-02003.23 Spent Fuel Pool.Demineralizer 1
Filter. Differential Pressure.
l DB-OP-02003.24-BUST Temperature Lo - TSL 1513
~
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Core Flood Tank 1 Level High -
.DB-OP-02003.25 CF3B1 D8-0P-02003.26 Core Flood Tank Level High - CF3B2 DB-0P-02003.27 Core Flood Tank 2 Level High -
CF3Al DB-OP-02003.28 Core Flood Tank 2 Level High -
CF3A2 1
DB-0P-02003.29 Decay Heat Removal Cooler 1 Outlet Temperature High DB-0P-02003.30:
. Decay Heat Removal Cooler 2 Outlet i
Temperature High DB-0P-02003.31 Spent Fuel Pool Heat Exchanger Combined Outlet Flow Low DB-0P-02003.32 Borated Vater Storage Tank Level Low Safety Features Actuation System Channel 1 5
+
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.- NEW OLD-BOOK i
NUMBER NUMBER DOCUMENT NAME NUMBER hj.,
DB-OP-02003.33 Borated Vater Storage Tank Level 3:
=';
Low-Safety Features Actuation
' System Channel 2
' DB-O'P-02003. 3'4'-
BVST Temperature Low - TSL 1534 l
p',
DB-OP-02003.35.
Core Flood Tenk 1 Level Low -
CF3B1
-DB-OP-02003.36
. Core Flood Tank 1 Level Lov --
r CF3B2 DB-OP-02003.~37
- Core Flood Tank 2 Level Lov -
CF3Al
'DB-OP-02003.38 Core Flood Tank 2 Level Lov -
' CF3A2
-DB-OP-02003.39-Decay Heat Pump 2 Suction Temperature High-DB-OP-02003.40-Decay. Heat Pump 2 Suction Temperature High DB-0P-02003.41 HPI 1-1 Flow Hi DB-OP-02003.42 HPI 1-2 Flov Hi DB-0P-02003.43 HPI 2-1 Flow Hi DB-OP-02003.44 HPI 2-2 Flow Hi DB-0P-02003.45 Core Flood Tank 1 Pressure High -
o CF4B1 DB-OP-02003.46 Core Flood Tank 1 Pressure High -
CF4B2 DB-0P-02003.47 Core' Flood Tank 2 Pressure High -
CF4A1 DB-0P-02003.48 Core Flood Tank 2 Pressure High -
CF4A2 DB-OP-02003.49 LPI 1 Flow Hi DB-0P-02003.50 LPI 2 Flov Hi L
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-I DB-0P-02003.51-HPIJ1-1 Flow-Lo "DB-0P-02003.52 1HPI 1-2 Flow Lo-f p
DB-0P-02003.53~
HPI-2-1 Flow Lo1 j-DB-0P-02003.54 HPI 2-2 Flow Lo1 DB-OP-02003'55 Core Flood Tank 1 Pressure Lov -
i CF4B1 s
DB-0P-02003.56 Core Flood Tank'1 Pressure Low -
CF4B2 l
.DB-0P-02003.57 Core Flood Tank 2 Pressure Low -
'CF4A1
, DB-OP-02003.58 Core Flood Tank 2. Pressure Lov -
l',
CF4A2 L, s DB-OP-02003.59 LPI 1 Flow Lo DB-0P-02003.60 LPI 2 Flov Lo-L.
.DB-OP-02004-AP 3004 Series Alarm Panel 4, hr DB-0P-02005
.AP 3005 Series Alarm Panel 5 DB-OP-02006~
AP 3006 Series Alarm Panel 6 l
DB-0P-02007 AP 3007 Series Alarm Panel 7 lDB-OP-02008 AP 3008 Series Alarm Panel 8-DB-0P-02009 AP 3009 Series Alarm Panel 9-DB-OP-02010 AP 3010 Series Alarm Panel 10~
DB-0P-02011 AP 3011 Series Alarm Panel 11 DB-0P-02012 AP 3012 Series Alarm Panel 12
'DB-0P-02013 AP 3013 Series Alarm Panel 13-
.DB-OP-02014 AP 3014 Series Alarm Panel 14 c DB-0P-02015 AP 3015 Series Alarm Panel 15 DB-0P-02016 AP 3016 Series Alarm Panel 16 7
DOCUMENT BOOK NUMBER DOCUMENT NAME NUMBER s
This volume contains its own index. Refer'to this volume for Table of Contents.
EMERGENCY PLAN ADMINISTRATIVE PROCEDURES, VOLUME A 5
This volume contains its own index. Refer to this volume for Table of Contents.
EMERGENCY PLAN ADMINISTRATIVE PROCEDURES, VOLUME B 6
.Thir. volume contains its own index.
Refer to this volume for Table of Contents.
EMERGENCY PLAN IMPLEMENTING PROCEDURES, VOLUME A 7
This volume contains its own inoex. Refer to this volume for Table of Contents.
EMERGENCY PLAN IMPLEMENTING PROCEDURES, VOLUME B B
This volume contains its own index. Refer to this volume for Table of Contents.
EMERGENCY PLAN IMPLEMENTING PROCEDURES, VOLUME C 9
This volume contains its own index. Refer to this volume for Table of Contents.
EMERGENCY PLAN - 0FF NORMAL OCCURRENCE 10 This volume contains its own index. Refer to this volt:me for Table of Contents.
l EMERGENCY PROCEDURE 11 DB-PF-02000 EP 1202.01 Emergency Procedure (RPS, SFAS, SFRCS Trip, or SG Tube Rupture) 8
[
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NEW OLD BOOK NUMBER _
NUMBER _
DOCUMENT NAME NUMBER i
FUEL HANDLING MANUAL 12 I
DB-PF-06300 PP 1501.01 Fuel Loading and Refueling Limits and Precautions DB-PF-06101 PP 1502.04 Fuel / Control Component Shuffle l
DB-PF-06301 PP 1506.01 Fuv1 and Control Component Handling GENERAL ORIENTATION AND RADIOLOGICAL CONTROLS TRAINING 13 INFORMATION HANDBOOK HEALTH PHYSICS PROCEDURES 12 DB-HP-01201 HP 1601.01 Guides and Limits for Exposure to i
Radiation DB-HP-01901 HP 1601.03 Radiation Vork Permits DB-HP-01100 HP 1601.04 Radiation, Contamination, and Airborne Radioactivity Areas t
DB-HP-01101 HP 1603.00 Containment Entry ICS ANALOG / DIGITAL DRAVINGS 15 F
INDUSTRIAL SAFETY GUIDELINES 14 This volume contains its own index. Refer to this volume for Table of Contents.
JOB TASK LIST (JTL) 15 i
-l 9
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i I'
DOCUMENT BOOK
{
NUMBER DOCUMENT NAME NUMBER r
JOB PERFORMANCE MEASURES (JPM) 15 Procedure JPN/ Task No.
JPM Title Reference 000-068-05-01000 Serious control Room Fire, DB-0P-02519 000-068-05-0100D Reactor Operator 1 Actions 000-068-05-0100E Serious Control Room Fire, DB-OP-02519 000-068-05-0100G Reactor Operator 2 Actions 000-068-05-0100A Serious Control Room Fire, DB-OP-02519 A.S.S. Actions 1-4 000-068-05-0100B Serious Control Eoom Fire, DB-0P-02519 A.S.S. Actions 5 7 000-068-05-0100F Serious Control Room Fire, DB-OP-02519
', 3, Steps 1, 2 002-011-04-0100A Determine Possible Sources DB-OP-02510 l
of Boron Dilution 076-002-04-0100A Replace SVP 1-1 vith DB-OP-06261 i
SVP 1-3 076-002-04-0100B Loss of Primary Side DB-0P-02511 Service Water 004-034-04-0100 Loss of Makeup Pumps DB-OP-02512 004-034-04-0100A 027-002-05-0100A Onerate EVS for High Rad.
DB-OP-02530 034-011-04-0100A in Fuel Handling Area 004-045-04-0100A Recover from Letdown DB-0P-02606 Isolation 008-001-01-0100A Component Cooling Vater DB-OP-06262 Pump Rotation 008-011-04-0100A Perform Actions During to DB-0P-02523 CCV Surge Tank Level 012-011-04-0100A Shutdown Bypass Operation DB-OP-06403 040-009-04-0100A Operate AVVs after SFRCS DB-PF-02000 Trip 001-044-04-0100A Dropped Rod DB-OP-02516 1
10
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DOCUMENT BOOK NUMBER DOCUMENT NAME NUMBER 000-050-05-0100A MDFP Supplying AFV System DB-PF-02000 000-001-05,010DA Rx Trip DB-PF-02000 005-002-04-0100A Piggyback Operation DB-0P-06012 004-019-04-02.00B HPI Operation DB-PF-02000 026-004-04-0100A Perform Post Accident DB-0P-06012 Recire.
061-003-01-01000 Exercising AFPT-1 Trip DB-OP-06233 Throttle Valve 061-003-01-0100B AFPT-1 Manual Cor. trol at DB-0P-06233 Trip Throttle Valve 000-032-05-0100A Battery Load Shed DB-0P-02521 008-013-04-0100A Loss of Both CCV Pumps DB-OP-02523 000-046-05-0100A Re-energize D2 from C1 DB-PF-02000 000-046-05-0100A OTSG Tube Leak, Appendix B DB-0P-02531 001-054-04-0100A Trip Rx from No. 2 Lo DB-PF-02000 Volts SVGR Room 064-006-01-0100A Local D.G. Operations DB-0P-06316 000-041-05-0100A Loss of Instrument Air DB-0P-02528 Actions - Control Room 000-041-05-0100B Loss of Instrument Air DB-0P-02528 Actions - In Plant 012-003-01-0100 Manually Trip an RPS SP 1105.02 Channel LESSON PLANS Lesson Plans are in the following order in books 16 through 20.
OLC-G0P-001 Abnormal Operating Procedures 16 AB 1203.01 - Turbine Trip AB 1203.02 - Serious Station Fire 11
i 4
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DOCOMENT BOOK NUMAER_
DOCUMENT NAME NUMBER AB 1203.03'- Cooldovn Vithout SVST and No 16 I
Offsite Power 1
E AB 1203.04 - Depressurization of the RCS with Only Safety Gradt Equipment AB 1203.07 - Rapid Shutdown Attachment B AB 1203.08 - Loss of Neutron Flux l
Indication
-Attachment 10 AB 1203.10 - Condenser Tube Leak
"' 3 AB 1203.13 - High Airborne Activity 4 AB 1203.14 - Toxic Gas and Liquid Release j 6 AB 1203.16 - Loss of Reactor Coolant System Boron Attachment l'i AB 1203.17 - Loss of Service Vater Pumps /
Systems
, 8 AB 1203.18 - Loss of ?.CS Hakeup Pump (s) l 9 AB 1203.19 - Pressurize: Systems Abnormal Operation 0 AB 1203.20 - Loss of Turbine Plant Cooling Vater Pupms
. 1 AD 1203.21 - Reactor Coolant Pump and Motor Abnormal Operation 2 AB 1203.22 - High Radiation 3 AB 1203.23 - Control Pnd Drive Halfunctionn 4 AB 1203.24 - Circulating Vater Pump Trip /
Circulating Vater System Ruptures L
i 5 AB 1203.25 - High Condenser Pressure L
L 6 AB 1203.26 - Serious Control Room Fire L 7 AB 1203.27 - Load Rejection 1
12 1
l
DOCUMENT BOOK NUMBER DOCUMENT NAME NUMBER
' 8 AB 1203.28 - Loss of AC Bus Power Sources 16 9 AB 1203.29 - Small RCS Leaks 0 AB 1203.30 - High Activity in the Peactor Coolant System
- 1 AB 1203.31 - Compontnt Cooling Vater System Kalfunctions
, ?
AB 1203.32 - Steam Genetator Feedvater Chemistry Out Spec Attschment 33 AB 1203.33 - Steam Leaks
. 4 AB 1203.34 - Steam Generator Overfill 5 AB 1203.3! - Loss of Decay Heat Removal System 6 AB 1203.36 - Loss of Instrument Air l-l 7 AB 1203.37 - Fire Procedure 8 AB 1203.38 - Fuel Handling Accident
( 9 AB 1203.39 - Radioactive Spills l
- l. 0 AB 1203.40 - Steam Generator Tube Leak 1 AB 1203.41 - Loss of NMI rover
- 2 AB 1203.42 - Control Room EVS Load Shedding OLC-GOP-002 Plant Procedures 16 02 Reactor Operator Curve Book l 01 Pre-Startup Checklists
-A*tachment 202 Plant Startup
' 03 Trip Recovery 04 Power Operations 10 Plant Shutdown and Cooldovn 08 Approach to Criticality l
13
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DOCUMENT BOOK-NUMBut-DOCUMENT NAME NUhBER h
i OLC-GOP-003 Emergency Procedure-16 I 1 Specific Rules l 2' Symptoms Auton'. tic Immediate Actions I
I 3 Supplemental Actions Attnchment 04 Lack of Subcooling l
f 5 Lack of Heat Transfer 6 Excessive Heat Transfer
, 7 SG Tube Rupture
! 8 Inadequate Core Cooling Attacheent 09 L0ct.
Attachsent 10 RCS SAT SG Remounting Heat
, 1 MV/HPI Cooling
- 2 Solid CID or PZR Recovery OLC-PVR-001 Nitrogen System 17 OLC-PVR-002 Fuel Oil OLC-PVR-003 Fire Protection / Detection i
OLC-PVR-004 Gaseoun Radvaste OLC-PVR-005 Miscellaneous Radvaste OLC-PVR-006 Clean Liquid Radvastee OLC-PVR-007 Spent Fuel Pooling / Cooling OLC-PVR-008 Containment Vessel / Integrity OLC-PVR-009 Control Room Ventilation OLC-PVR-010 Radvaste Ventilation OLC~PVR-011 Non-Radvaste Ventilation t
14 b
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t DOCUMENT SOOK NUNSER DOCUMENT NAME NUMBER OLC-PVR-012 Traveling Screens and Screen Vash 17 OLC-PVR-013 Chlorine System OLC-PVR-014 '
Circulating Vater System i
OLC-PVR-015 Vacuum System OLC-PVR-016 Turbine' Plant Cooling Vater OLC-PVR-017 Auxiliary Steam / Heating i
OLC-PVR-018 Plant Air System OLC-PVR-019 Service Vater OLC-PVR-020 component Cooling Vater OLC-PVR-021 Condensate System OLC-PVR-022 Lov Pressure Feedvater Heaters l
OLC-PVR-023 Feedvater t
OLC-PVR-024 MFPT/ Pump Control OLC-PVR-025 H. P. Feedvater Heaters and Demerator l
OLC-Pb?, 026 Once Through Steam Generator (OTSG)
I-OLC-PVR-027 Main Steam n
OLC-PVR-028
' Moisture Separator Reheaters L
OLC-PVR-029 Auxiliary Feedvater OLC-PVR-030 SFRCS OLC-PVR-031-Reactor Vessel wiJ Internals OLC-PVR-032 Pressuriter OLC-PVR-033 Reactor Coolant Pumps and Motots OLC-PWR-034 Reactor Coolant System 18 OLC-P7R-035 Non-Nuclear Instrumentation 15
- }
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i DOCUMENT BOOK l
f-NUMBER DOCUMENT NAME NUMBER OLC-PVR-036 Control Rod Drive 18 j
OLC-PVR-037 Nuclear Instruaentat10;.
OLC-PVR-038 Nuclear Instrumentation (Incores)
OLC-PVR-039 Reactor Protection System f
OLC-PVR-040 Anticipatory Reactor Trip System OLC-PVR-041 Core Plood System
+
OLC-PVR-042 High Pressure Injection /DVST OLC-PVR-043-Decay Heat Removal /Lov Pressure Injection OLC-PVR-044 Makeup and Purification OLC-PVR-045 Chemical Addition / Sampling OLC-PVR-046 CTNT 1:<at Removal l
OLC-PVR-047.
Containment Hydrogen Systems OLC-PVR-048 Containment Ventilation OLC-PVR-049 CTMT Air Sampling
~0LC-PVR-050 CTNT Vent / Drain OLC-PVR-051
. Safety Peatures Actuation System OLC-PVR-052 365KV 4
OLC-PVR-053 13.8KV OLC-PUR-054 4160 Volt OLC-PVR-055.
Diesel Generator OLC-PVR-056 480 Volt OLC-PVR-057-Instrument AC/DC OLC-PVR-058 Main Exciter OLC-PVR-059 Main Turbine Lube 011 16
DOCUMENT BOOK NUMBER DOCUMENT NAME NUMBER OLC-PVR-060 Generator Seal 011 18 OLC-PVR-061 Generator Hydrogen /CO, OLC-PWR-062 '
-)
OLC-PWR-063 Puel Handling OLC-PWR-064 Makeup Water Treatment,% mineralized Water OLC-PWR-065 ICS Big Picture OLC-PWR-066 ICS Drt. wings, Hardware, and Power Supplies OLC-PWR-067 Unit Load Demand System OLC-PWR-068 Integrated Master Subsystem OLC-PWR-069 Feedwater Subsystem 19 OLC-PWR-070 Reactor Control Subsystem 1
OLC-PWR-071 ICS Load Maneuvering OLC-PWR-072 Hand / Auto Stations OT C-PWR-073 RCP Trip Transient OLC-PWR-074 ICS railure Modes OLC-PWR-075 Main Ei!C OLC-PWR-07T Seismic Monitoring System OLC-PWR-078 Vibration and Loose Parta Monitoring OLC-PWR-079 Proceus and Aree Radiation Monitoring OLC-PWR-080 Main Turbine OLC-PWR-081 Main Generator l
OLC-RTR-001 Nuclear Physics Review 19 l
OLC-RTR-002 Radioactive Decay OLC-RTR-003 Nuclear Reactions 17
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NL3ssR DOCUGNT NMIE tRMBER 1:
M, OLC-Rn-004 Nuclear Cross Sections 19 (6C-Rn-C*5 Neutton Flux and Reaction Rates 5
~
.I
'OLC-Rn-006.
Fission Products OLC-Rn-007-Neutron thermalltation OLC-Rn-008 Neutron Balance and Six-Factor Formula
'0' OLC-RrR-009 2eactivity OLC-RTR-010-Proupt and Delayed Neutrons 4
OLC RTR-011 Moderator Tenperature Coefficient i
OLC-RTR-012 Doppler Coefficier.t OLC-RTR-013 variations in Doppler coefficient I
OLC-RTR-014 Void and Pressure Coefficient
.0LC-Rn-015 Power and Isothermal Temperature CoeffJcient OLC-RTR-016
- Reactivity Defects OLC-RTR-017 Excese neactivity and Chemical Shim OLC-RTR-018 Control Rod Notth OLC-RTR-019 Differential and Integral Rod Worth OLC-RTR-020 Samarium Posior.ing OLC-RTR-021 Xenon Poisoning OLC-RTR-022 Neutron Sources OLC-RTR 023 Shutdown Margin and Estimated Critical
-Position OLC-RTR-024 Suberitical Multiplication OLC-RTR-025 Reactor Kinetics - Part 1 OLC-RTR-026 Reactor Kinetics - Part 2
)
10
i
,y Docum Nr nook NLMBER DoctMENT NhME NLMBER SRO-ADM-001 Station operations 20 SRO-ADM-002 Shift Technical Advisor 5RO-ADM-003 ~
Conditions Adverse to Quality i
SRO-ADM-004 shift Turnover SRO-ADM-005 Safety Tagging Procedure S W ADM-006 Junper and Lifted Wire control SRO-ADM-007 operation and control of Locked valves SRO-ADM-008 operation and Control of Capped Valves SRO-ADM-009 operational Information Tags SRO-ADM-010 Maintenance
, 1 Davis-Besse Maintenance Mew gement System SRO-ADM-011 Radwaste Ma. gement w
SRO-ADM-012 Procedure P:eparation and Maintenance SRO-ADM-013 Surveillance and Periodic Test Program SRO-ADM-014 Generic Guidance Program SRO-ADM-015 Fire Ptotection Admin.
SRO-ADM-016 Industry Safety Guidelines SRO-EPT-001 Emergency Plan - Session 1 20 SRO-EPT-002 Dnergency Plan - Session 2 SRO-THT-001 Puel Handling Fystems 20 SRO-HTr-001 Properties and Forms of Energies 20 SRO HTT-002 Energy, Work, Heat, and Power STD-HTr-003 Phases of Matter and Property Diagrams 19
. ~
. m.,
1; a-j g
NLEGER D3CUMDrf NhME NUMBER-SFO-HTT-004 rirst Law of 'thersedynamics -
20 1
SRNrrr-005 '
second Law of ' thermodynamics 1
SRO-HTr-006
' thermodynamic Cycle and Efficiency SRO-HTr-007 Modes of Heat Transfer l
- SRO-HTP.-908 Combined and Boiling Heat Trans?.or j
SRO-HTr-009 Reactor Heat Transfer SRO-HTr-010 Core ' thermal Limits 1
SRO-HTT-011 riuid riow rundamentals SRO-HTr-012 Bernoulli's Equation
[
SRO-HTT-013 Pumps and Core riow p
p m paoegoungs I-DB-OP-06901 PP 1102.02 Plant Startup Procedure 21 l
DB-OP-06902-PP 1102.04 Power Operations' DB-OP-06903
- PP 1102.10 Plant Shutdown and Cooldown l-DB-OP-0691tt PP 1102.03 Trip Recovery L
i DB-Pr-06201 PP 1101.02 Reactor Operators Curve Book
' DB-Pr-06203 PP 1103.08 Approach to criticality DB-PF-06305 PP 1101.01 Nuclear Steam Supply System Limits
[
f l
and Precautions p
l-DB-Pr-06703 Pi 1101.07 Miscellaneous Operation Curves DB-Pr-06704 ' PP 1101.08 Pump Performance Curves 22 DB-PF-06705 PP 1101.09 Tank revel Calibration curves DB-PN-06900 PP 1102.01 Pre-Startup Checklist t
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p NDt OLD B0oK l
NunBn wunBen DoCum mr w.nz wunBen SYSTEM PROCEDURES DB-OP-06001 F/ 1103.04 Boron concentration control 23 DB-OP-06003 SP 1103.05 Pressurizer Operation DB-OP-06004 SP 1103.17 Quench Tank DB-OP-06005 S' 1103.06 RC Puep Operation DR-OP-06006 SP 1104.02 Makeup and Purification System DB-OP-06011 SP 1104.07 High Pressure Injection System Procedure DB-OP-06012-SP 1104.04 Decay Heat and Low Pressure Injection Operation Procedure l
i DB-OP-06013 SP 11N.O Containment Spray System DB-OP-06014 SP 1104.01 Core Plooding System Operating Procedure SU System No. 51 DB OP-06015 SP 1104.66 Borated Water Storage Tank Operating Procedure DB-OP-06016 SP 1104.08 Containment Air cooling System Procedure DB-OP-06021 SP 1104.42 Spent Fuel Pool Operating Procedure DB-OP-06022 SP 1104.06 Spent ruel Pool Pocling and cleanup System Operating Procedure DB-OP-06101 SP 1104.29 Clean Liquid Radweste DB-OP-06111 SP 1104.30 Miscelle.neous Liquid Waste Disposal DB-OP-06131 SP 1104.27 Gaseous Radioac*.ive Waste System DB-OP-06201 SP 1106.24 Main Steam System Operating Procedure DB-OP-06202 SP 1106.01 Turbine Operating Procedure DB-OP-06204 SP 1105.12 EHC System Operating Procedure 24 21
m s
tc NEW OLD BOOK NUMBER
!U BEM DOCUMFNT !W.E
!UlBER I
i
.y DB-OP-06221 SP 1106.16 Condensate System DB-OP-06223 SP 1106.07 Main reedwater System
~
DB-OP-06224 SP 1106.20 Main reedpump and Tuttine DB-OP-06225 SP 1106.28 Motor Driven reedpunp Operating Procedure j
i DR-OP-06231 SP 1104.35 Vacuum Systems Operating Procedtre I
DB-OP-06232 SP 1104.09 Circulat!ng Water System and Cooling Tower Operation DB-OP-06233 SP 1106.06 h2xiliary reedeater System i
DB-OP-06251 SP 1104.24 Station and Instrument Air System Operacing Procedure 3 -
DB-OP-06261 SP 1104.11 Service Water System operating Procedure DB-OP-06262 SP 1104.12 Conponent Cooling Water System Operating Procedure DB-OP-06263 SP 1104.39 Turbine Pl u t Cooling Water System DB-OP-06301 SP 1106.09 Generator Operation DB-OP-06311 SP 1107.01 345KV Switchyard, No. 1 (Main)
L Transformer, No. 11 (Auxiliary)
Transformer and Startup L
Transformers (01 and 02)
DB-CP-06314 SP 1107.04 13.8KV Buses Switching Procedure DB-OP-06315 SP 1107.05 4160V System Switching Procedure DB-OP-06316 SP 1107.11 Diesel Generator Operating 25 Procedure DB-OP-06319 SP 1107.09 Instrument AC System Procedure l
L DB-OP-06401 SP 1105.04 Integrated control System Operating Procedure DB-OP-06402 SP 1105.09 Control Rod System Operating
[
Procedure 22
r NDt OLD BOOK j
NLDSER NLDSER Doct*ENT NME NLPBPR j
DD-OP-Of403 SP 1105.02
'/4 actor Protection System (RPS) 25 and Nuclear Instrumentation (NI)
Operating Procedure ES-OP-06404 SP 1105.21 Anticipato y Reactor Trip System (ARTS) Pro edure DB-OP-06405 SP 1105.03 Safety Features Actuation System Ds-OP-06406 SP 1105.16 Steam ard Feedwater Rupture Control system Operating Procedure DB-OP-06407 SP 1105.06 iM System Operating Procedure r
DB-OP-06412 SP 1105.07 Process and Area Radiation Monitor De-OP-06431 SP 1105.20 Power Operated and Safety Relief
^,
Valve Monitoring System Onerating Procedure DB-OP-06501 SP 1104.54 Contairment Recirculation DB-OP-06502 SP 1104.55 Containment Hydrogen Diluti m and Hydrogen Purge Dd-OP-06503 SP 1104.21 Containment Purge System Procedure DB-OP-06504 SP 1104.35 Emergency Ventilation System l-DB-OP-06505 SP 1104.69 Control Room Emergency Ventilaticn System Procedure DB-OP-06511 SP 1104.14 Cu trol Room Heating, Ventilation, and Air conditioning System Procedure DB-OP-06512 SP 1104.16 Auxiliaty Building Radioactive Ventilation System P
DB-OP-06513 SP 1104.17 Auxiliary Building Non-Radioactive Areas ventilation 4
I 23
Ff9f OLD POOK i
Nr.WSER NLDBER DOCUMDrr Nr.ME NUMBER SURVEILLANCE TESTING PROCEDURES Y
k DB-oP-03006
-ST 5099.01 Miscellaneous Instrument Shift 26
[
Uheck DB-OP-03007 ST 5099.02 Miscellaneous Instrument Daily Checks DB-SC-030E9 ST 5011.01 Boric Acid riowpath Heat Tracing Weekly Test 3
DB-SP-03370 ST 5011.03 Monthly Makeup Pump 1 Opsrablity Test DB-SP-03380 ST 5011.05 Boron Injection riowpath Quarterly valve Testing DB-SP-03382 ST 5011.02 Boron Injection Flowpath Monthly valve Verification Test 18-SP-03383 ST 5011.04 thron Injection Flowpath Boric Acid Pump Test DB-SC-03272 ST 5013.04 control Rod Exercising n st DB-SC-03022 ST 5080.02 Independent Off-site AC Se'."ces 27 Bus Transfer Test DB-SC-03165 ST 5038.02 Psat/Isat Monthly Channel Check DB-SP-03134 ST 5051.05 Containment Emergency Sung Visual Inspection DB-SP-03170 ST 5050.02 Core riood System Monthly Isolation 4
Valve Status check 4
DB-SP-03179 4
Core ricod Tanks Isolation Valve Refueling 4
Interval Operability Test DB-SP-03212 ST 5051.11 Venting of IcCs Piping D3-SP-03213 ST 5051.12 ECCS Verifkation of Flowpath DB-SP-03356 ST 5042.01 RCS Leakage (Monthly)
DB-SP-03357 ST 5042.02 RCS Water Inventory Balance 24
NEW OLD BOOK TUBER NUSER DOCUMENT NAME NUMBER DB-SP-03150 ST 5071.11 Auxiliary reedwater Pump 1 Monthly Jog Test DB-SP-03151.ST 5071.12 Auxiliary reedwater Pump 1 Quarterly Test DB-SP-03153 ST 5071.14 Auxiliary reedwater Train 1 Monthly Valve Verification DB-SP-03154 ST 5071.15 Auxiliary feedwater Train 1-1 Quarterly vale Test DB-SP-03155 ST 5071.16 Auxiliary reedwater Train 1 Flow Path Verification on Auxiliary i
Steam DB-SP-03159 SY 5071.21 Auxiliary reedwater Pune 2 Monthly Jog 7tst DB-SP-03271 St 5060.01-Containment Integrity Monthly verification DB-SP-03294 ST 5063.03 containment Air Cooling Unit 1-1 i
Monthly Test DB-SP-03060 ST 5074.01 Component Cooling Water Pump 1 Monthly Test t
DB-SP-03090 ST 5074.02 Conponent Cooling Water Pump 1 1
Refueling Test DB-SP-03160 ST 5071.22 Auxiliary feedwater Pump 2 6
DB-SC-03023 ST 5080.01 Indeperdent off-site AC Sources i
Lined Up and Available DB-SC-03041 ST 5082.01 on-Site AC Bus Sources L..;ed Up Available and Isolated (Modes 1, 2, 3, and 4)
DB-SC-03042 ST 5082.02 on-Site AC Bus Sources Lined Up and Available (Modes 5 and 6)
DB-SC-03200 ST 5099.05 Shift Channel check of the Radiation Monitoring System DB-SP-03270 ST 5092.01 Containment Atmosphere Penetration Lineup Refueling Check 25 u.-.-.-
t t
I NIBf OLD BOOK NUMBER NUPSER DOCUMENT NME NUMBER l
1 DB-SS-03041 ST 5076.01 Control Room Emergency Ventilation l
g.
System Train 1 Monthly Test i
Db-PF-03220.ST 5020.01 Imbalance, Tilt & Rod Index Cales
- Group 38 Alarms Inoperable
[
.DB-Pr-03230 ST 5030.01 RPS Daily Heat balance Check DB-SC-03076 ST 5081.05 Deergency Diesel Generator 1 184 i
Day Test l
DB-SP-03022 ST 5075.21 Service W ter Punp 2 Monthly Test i
DB-PF-03292 ST 5092.02 Core Alteration Prerequisites and Periodic Checks DB-S1 03136 ST 5051.30 Decay Heat Pung #1 Quarterly Pump and valve Test N SP-03138 ST 5051.32 Decay Heat Pung #1 Monthly Jog Test DEHtP-03216 ST 5051.09 HPI Pung #1 Monthly Jog Test DB-SS-03090 ST 5071.08 Motor Driven reed Pump Monthly Test DB-SS-03091 ST 5071.09 Motor Driven reed Pump Quarterly Test DB-SS-03250 ST 5067.01 Emergency ventilation System Train 1 Monthly Test DB-SC-03070 ST 5081.01 Emergency Diesel Generator 1 Monthly Test DB-SC-03110 ST 5031.01
$ RAS Channel 1 runctional Test DB-SP-03214 ST 5051.13 ECCS Valves Train #1 Quarterly Test DR-SP-03175 ST 5051.07 Decay Haat Valve Pit Leak Test DB-SP-03320 ST 5065.06 H2 Dilution System Train 1 Quarterly Test DB-SP-03400 ST 5095.01 Spent ruel Pool Water Level DB-PF-03811 ST 5099.00 Miscellaneous Valve Quarterly Test Db-PT-03813 ST 5099.11 Operational checks of Passive Valves l
26
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to-FF-03001 ST 5016.01 Diesel Fire Protect System Pump j
Weekly Surveillance Test i
r L
DS-FP-03002 ST 5010.02' Seven-day Electric Driven Fire Pump i
T*st j 7, DB-FP-03006 ST 5016.08 Electric Fire Pu g Annual Flow I
Test 4
+
e S'ml@ LNG ORDERS 15 i
s TEDNICAL BASES DOCLMENT 28 TECHNICAL SPECIFICATIONS 29 t
- TRAINING INFCRMATION G40ALS Training Information Muual, Volume 1 has a complete index.
Volume IL 10 i
Volume ~2' 31
.I Volume 3 32 USAR, SECTION 15 i
Section 15-Accident Analysis 15.0 Accident Analysis 15.1 General
[
15.2 Mass 1 - Events Leading to No Radioactive Release ae Exclusion Area Boundary 15.3 Class 2 - Events Leading to Small to Moderate Radioactive Releases at Exclut.icn Area Boundary 15.4 Class 3 - Design Basis Accidents
[
15.5 References Appendix 15A Radiation Sources 9/89 27 1
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i l
PIPING AND INSTRUMENT DRAVING INDEX M-001 Piping Symbols and Diagrams Index L
M-002 Instrumentation Symbols M-003A Main Steam and Reheat System, Sh. 1 M-003B Main Steam and Reheat System, Sh. 2 M-003C Main Steam and Reheat System, Sh. 3 1
M-0048 High Pressure Extraction Steam System P
M-004C Lov Pressure Extraction Steam System Loop 2 M-004D Lov Pressure Extraction Steam System Loop 1 M-005 Moisture Separator Reheater Drains M-005A Moisture Separator Reheater Drains M-0060-Main Feedvater System M-006D Auxiliary Feedvater System M-006E Condensate System M-006F Condensate System M-007A Steam Generator Secondary System M-007B Steam Generator Secondary System M-008A Turbine Condensate Demineralizers M-008B Turbine Condensate Demineralizers M-009A Cooling Vater System M-009B Cooling Vater System M-010A Makeup Vater Treitment System M-0100 Makeup Vater Treatment System M-010D Makeup Vater Treatment System M-011 Domestic Vater System 1
M-012B Cire. Water Pump Flushing System M-012C Cooling Tower Acid Injection System 1
2
~
- ^
M-012D Circulating Vater System Jo M-012E Screen Vash and Cooling Tower Makeup System
'M-013 Chlorination System
.M-014 Vacuum Systems M-015A Instrument Air System t
M-015C Station Air System i
M-015D Station Air System i
M-015E Station Air System M-015F Station Air System Containment M-016A Station Fire Protection System 4
i M-016B Station Fire Protection System M-017A Diesel Generators-M-0178 Diesel Generators Air Start M-017C Fuel Oil M-018 Turbine Lube 011 System t
M-019 Nitrogen Supply System M-020A Vater Tcestment and Intake Structure Auxiliary Steam System l
M-020B Auxiliary Building Auxiliary Steam System M-0200 Turbine Building Auxiliary Steam System M-020D Turbine Building Auxilfary Steam System M-021 Station Heating System M-022A Main Turbine Gland Steam Seal and Drain System M-022B Main Feed Pump Turbine Gland Steam Seal and Drain Systems M-023 containment Leak Rate Test Diagram M-024A Turbine Instrumentation Details Main and Auxiliary Turbine Driven Feed Pumps, Startup Feed Pump, and Motor 2
F 1
i M-024C, Sh. 1.
Turbine Control Diagram, Sheet 1
?
M-024C, Sh. 2 Turbine control Diagram, sheet 2 M-024C, Sh. 3 Turbine Control Diagram, Sheet 3 M-0240, Sh. 4
. Turbine Control Diagram, Sheet 4
)
M-024C, Ch. 5 Turbine Control Diagram, Sheet 5 l
i M-024D Main Generator Seal Oil System M-024E
. Main Generator Stator Vinding Cooling Water i
Systea M-024F Main Generator H, System M-024G No. 1 Main and Auxiliary Turbine Driven Feed Pumps j
M-024H No. 2 Main and Auxiliary Turbine Driven Feed Pumps
. M-024J Start-up and Motor Driven reed Pumps M-025 W and VC Air Flow Diagram - office Building M-026A W and VC Air Flw Diagram - Turbine Building and Auxiliary Feed Pump Room M-026B W and VC Air Flow Diagram - Water Treatment Building a:r. Miscellaneous Yard Structures M-027A W and VC Air Flow Diagram - Auxiliary.
Building Non-Radioactive Areas and Control Room M-027B.
HV and V C Air Flow Diagram - t.uxiliary l
Building Non-Radioaccive Areas 1
L-M-028B W and VC Air Flow Diagram - Auxiliary Building Radwaste, Fuel Handling, and Access control Areas M-028C W and VC Air Flow Diagram - Auxiliary Building Radwaste Ventilation M-028D W and VC Air Flow Diagram - Fuel Handling Area Ventilation M-029B W and VC Air Flow Diagram - Containment and Penetration Rooms, Sheet 1 l
M-029C W and VC Air Flow Diagram - Containment and Penetration Rooms, Sheet 2 L
3
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M-029D W and NC Air Flow Diagram - Containment and Por.etration Rooms, Sheet 3 i
M-029E HV and VC Air Flow Diagram - Contsinnent and
)
Penetration Rooms, Sheet 4 1
'M-030A Reactor Coolant System M-030s Reactor Coolant System Instrumentation
.M-031A Makeup and Purification System I
J M-0318 Makeup and Purification System 1
M-031C P.akeup and Purification System M-033A High Pressure Injection l
M-0338 Decay Meat Train 1 M-033C Decay Heat Train 2
. M-034..
Emergency Core Cooling System, Containment Spray, and Core Flooding Systems M-035 Spent Fuel Pool Cooling System M-036A Component Cooling Water System l
M-036B Component Cooling Water System M-036C Component Cooling Water System M-037C Clean Liquid Radioactive Waste System M-037D Clean Liquid Radioactive Waste System i
M-037E Clean Liquid Radioactive Waste System M-037F Clean Waste Monitor Tanks M-037G Gaseous Radwaste Boric Acid Evaporator 1-1 Hydrogen and Oxygen Monitoring Systems M-037H Gaseous Radwaste Boric Acid Evaporator 1-2 Hydrogen and Oxygen Monitoring Systems M-038A' Hydrogen Oxygen Monitoring System M-0388 Gaseous Radioactive Waste System M-038C Gaseous Radioactive Waste System 4
[g
.t
- g M-039A Miscellaneous Liquid Radioactive Weste t
M-039s Miscellaneous Liquid Radioactive Waste M-040A.
Reactor Coolant System Details M-040C Reactor Coolant Pung and Motor M-040D Reactor Coolant Pung and Motor M-041A Service Water System and Secondary Service Water System M-0418 Primary Service Water System M-041C' Service Water System for Containment Air Coolers M-042A Sanpling System, Sheet 1 I
M-042B Sampling System, Sheet 2 Local Grab Sanples M-042C Sampling System, Sheet 3 M-043 Auxiliary Building Chilled Water System M-044 H, and CO, Systems M-045 Chemical Addition Systems M-046 Station Drainage Systems i.
M-047 Radweste Drumming Station M-050A Main Steam Line and Main reedwater Line Rupture Control System Logic M-050s Main Steam Line and Main reedwater Line Rupture Control System Logic l
M-051 Auxiliary reedwater Pung Turbine Start Control System Logic ls ELECTRICAL DRAWINGS E-1, Sheet 1 AC Electrical System One-Line Diagram E-1, Sheet 2 AC Electrical System One-Line Diagram E-1, Sheet 3 Station Distribution Transformer Tap Settings 5
u
't E-2 25KV and 13.8KV Metering and Relaying one-Line Diagram t
E-3 4.16KV Metering and Relaying one-Line Diagram l
E-4, Sheet 1 "E" Buses 480V Unit substations one-Line Diagram E-4, Sheet 2 "r" Buses 480V Unit substations one-Line Diagram E-4, Sheet 3 Water Treatment and Turbine Building 480V Unit Substations One-Line Diagram E-4, Sheet 4 480V Unit Substhtions Lighting Distribution f
One-Line Diagram E-4, Sheet 5
-Pressuriser and Annulus Heaters 480V Unit Substations PPP and rabrication shop 4.16 KV Disconnect One-Line Diagram E-5, Sheet 1 480 Volt MCC (Non-Essential) One-Line Diagram E-5, Sheet 2 480 Volt MCC (Non-Essential) One-Line Diagram E-5, Sheet 3 480 Volt MCC (Non-Essential) One-Line Diagram E-5, Sheet'4 480 Volt MCC (Non-Essential) One-Line Diagram E-5, Sheet 5 480 Volt MCC (Non-Essential) One-Line Diagram E-6, Sheet 1 480 volt MCC (Essential) One-Line Diagram l
E-6, Sheet 2 480 Volt MCC (Essential) One-Line Diagram l
E-6, Sheet 3 125/250 VDC MCC No. 1 (Essential) Single Line Diagram l
l E-6, sheet 4 125/250 VDC MCC No. 2 (Essential) Single Line i
Diagram l
E-6, Sheet S 480V AC MCC (Essential) One-Line Diagram l
E-7 250/125V DC Instrumentation AC One-Line
. Diagram E-9 240 VAC and 120 VAC MCO (Essential) One-Line Diagram l
6 l
_ ~ ~.. _ _.._.,.
I safety Features Actuation System logic Diagram j
E-16, sheet 1 b
E-16, sheet 2 safety Features Actuation system signal Diagram
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i E-18, sheet 1 srRCS Logic Diagram, Logic Channel 1 and 3 and Actuation Channel 1 L
E-18, sheet 2 SrRCS Logic Diagram, Logic Channel 2 and 4 and j
Actuation Channel 4 1
1 1
l E-18, sheet 3 srRCS Logic Diagram Miscellaneous Circuits I
E-20 Generator and Transformer Relay and Metering Wree-Line Diagram E-21, sheet 1 13.8 KV Relay and Metering Wree-Line Diagram Bus A
[
E-21, sheet 2 13.8 KV Relay and Metering tree-Line Diagram Bus B e
E-22, sheet 1 4.16 KV Relay and Metering Wree-Line Diagram Bus C1 and C2 E-22, sheet.2 4.16 KV Relay and Metering Wree-Line Diagram Bus D1 and D2 l
E-22, sheet 3 4.16 TC! Relay and Metering Three-Line Diagram l
Bus D2 and C2 I
E-23, sheet 1 Generator Excitation System Diagram E-23, sheet 2 Generator Excitation System Diagram
(
E-24 Relay House and Control Room Synchronizing E-25 Phasing Diagram E-27 Emergency Diesel Generator 1-1, 1-2 Relay and Metering Wree-Line Diagram E-28 Anticipatory Reactor Trip System Logic Diagram
'E-132 345 KV Switchyarel connaction Diagram 125 VDC Station Setvice Equipment l'
l-E-133 345 KV Switchyard Connection Diagram AC Station Service Equipment l-w Lg 7
.. -.