ML17054A213
| ML17054A213 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/02/1982 |
| From: | Perkins T, Roman T, Rich Smith NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML17054A214 | List: |
| References | |
| N1-RAP-6, NUDOCS 8311150223 | |
| Download: ML17054A213 (66) | |
Text
ATTACHMENT 1
REACTOR
~S.-".'ST ROCEDURES PROCEDURE NO. Nl-RAP-6 POST REACTOR SCRAM ANALYSIS AND'VALUATION DATE AND INITIALS AP PRO VALS Reactor Analyst Supervisor R.
G.
Smith SIGNATURES REVISION 2
REVISION 3 REVISION C's C rM~
Station Superintende ig1PNS T.
W.
Roman General Superintendent Nuclear Generation Chairman of S.O.R.C.
T. J.
Perkins
.'p~ilt gammer~of Pages Revision 2, dated November
- 1981, consists of pages 1-6, with changes on pages 1 and 4 ~
NIAGARA MOHAWK POWER CORPORATION THIS PROCEDURE NOT TO BE USED AFTER 2/84 SUBJECT TO PERIODIC REVIEW.
83iii50223 83ii08
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POST REACTOR SCRAM At ALYSIS AND EVALUATION 1.0 PUR?OS" The purpose of this procedure is to provide the review and evaluation of specific parameters associated with a Reactor Scram.
2.0 DESCRIPTION
Following a Reactor Scram various systems associated with maintaining Core Coolant Inventory and Reactor Containment Integrity must be directly monitored for proper sequential actuation and operation.
3.0 ACCEPTANCE CRITERIA Al) parameters monitored must satisfy either Tech Spec or engineering design requirements.
4.0 RESPONSIBILITIES AND CONDUCT 4.2 The Reactor Analyst Department will be directly responsible for data gathering and process evaluation.
Following scram analysis and systems parameter evaluation a
report will be provided by the Reactor Analyst Department for S.O.R.C.
review and re commend a tions.
5,0 PREREQUISITES 5.1 Process computer and post mortem trip log is available.
5.2 Control rod scram recorder connected and armed for operation.
6.0 PROCEDURE 6.1 Following a Reactor Scram obtain the post mortem trip log from the I/O typer in the Aux.
Control Room along with a
copy of the alarm typer and periodic typer printouts for the transient period.
Allow a minimum of 5 minutes lead time prior to the scram and after for a
display of conditions leading up to the scram; and after the transient period has stabilized.
6.2 In addition, obtain copies of various trend recorder parameters, ie.,
recirc flow, feed flow, Rx pressure, etc.
as required to perform and support transient analysis outlined on data sheet sections I VII.
Nl-RAP-6
-1 January 1982
lt
C~- 'e;-
the ca-a shee=
as soecif'ed a-propriate loca"ions as'ec'ree.
include all supporting
- graphs, trends, alan r:.aterial with the complete cata sheets and Analyst for his review.
Following
- review, Report.
printouts and reference forward to the Reacto file RAP-5 with Scra-.;
N l-RAP-6
-2 January 1982
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SYST" 2
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1.0 AL N STEAhj
~Oen Closed Electromatic Valve 8111
$3112
~r'113 i'p'121 l'. 122 8123 Comments 1.2 Turbine Coast Down Time (See attached graph)
Comments:
1.3 Peal< Reactor Pressure (See attached graph or strip chart) pssg Comment s 1.4 "fain Steam I.V.'s
~Oen Closed 01-01 01-02 01-03 01-04 Comments:
N1-RAP -6
-3 J a nu a ry 1982
Lowest Rector Pater Level Indicated (See attached graph or strip chart)
Comments 2
0 2.1 HPCI/Peedwater HPCI Actuation Yes No 2.2
-".11 system max flow
- .:12 system max flow
-;13 system max flow Comments:
3.0 Emer encv Condenser Actuation 811 System 812 System Comments:
Yes 4.0 Control Rod Drive System 4.1 Vent valve closure time 4.2 4.3 Drain valve closure time Air pressure indication received Drain time (3 gal. cleared from reset)
Comments:
Scram Strip Chart Times and Motion Hl-RAP-6
-4 January
.1982
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5.0 5
No.
pumps in operation Recirc run 'oack auto/-an Yes No 5 '
Recirc pump trips 6.0 Reactor Protection System Normal Ai oormal 6.1 Svstem response Comments 7.0 Containment System 7.1 Hax Drywell pressure attained
~flax Torus pressure attained Max Torus temperature attained psst.
p s l.
OF Yes No 7a4 Containment spray actuation Comments:
8.0 Core Snrav System Yes No 8.1 Core spray actuation Comments:
N1-RAP-6
-5 January 1982
1
Transient Analysis ".valuation Reviewed by Reactor Analyst Date Reviewed by Operations Supervisor Date Kl-RAP-6
-6 January 1982
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ATTACHMENT 2 FORM VI From:
SCR~~i F "PORT 1.
Operations Supervisor 2.
Station Superin endent S.S.S.
Date:
Time:
Operator:
Operator:
I.
TECH.
SPEC. 2.l.lc 1.
Process Computer In Service
/
/
Not in Service /
7 2.
Neutron flux did not exceed scram setting by more than 1.5 seconds per process computer prior to scram.
/
T 3.
Expected scram signal did
/
/
did not~ initiate scram 4.
Safety limit violation Yes /
T Reportable.
No /
T Not Reportable II.
CAUSE OF SCRAM 1.
Operator Error /
/
2.
Safety System 7
/
3.
Eauipment Failure
/
/
4.
See Description 7
/
III. MODE SWITCH 1.
Run 2.
Start
/
/
7
/
REACTOR 1.
Critical
/
T 2.
Subcritical 7
/
IV.
PLANT EVOLUTION 1.
Starting up
/
/
2.
Shutting Down 7
/
3.
Steady Operation 7
/
4.
/
7 5.
System Test 7
/
6.
See Description 7
/
V ~
PLANT CONDIUTIONS PRIOR TO SCRAM 1.
Thermal Power MW 2.
Reactor Pressure~si 3.
Vessel Level inches 4.
Core Flow 5.
Steam Flow 6.
Feed Flow x 106 lb/hr x 106 lb/hr x 106 lb/hr VI.
EQUIPMENT FAILURE DESCRIPTION Date Nl-OP-43
-44 September 1983
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~~Owv U7 (Continued)
SCF~~i REPORT Uli. SCRUB INSERTION TIMES l.
OK in accordance with Tech.
Spec. 4.1.1c 2.
Evaluation required ia accordance with 4.1.1c VIII.COPIES OF LOGS ATTACHED
/
/
/
/
1.
Alarm Typer 2.
Event Typer Reviewed By Reviewed By
/
/
3.
Post Mortom Log
/
/
7
/
7
/
Operations Supvr.
Date Station Supt.
Date Nl-OP-43
-45 Septemher 1983
1
ATTACHMENT 3 NINE MILE POINT NUCL""A. STATION UNiT NO.
1 SHORT PRE-STAPT-UP CHECK-OFF-SYSTEMS By Checked Date 1.
List any systems which were worked on during shutdown and complete a
check list, valve list and/or functional test for each System that was worked on as per Master Systems Check-off List.
a) b)
c) d)
e)
Diesel generators operable Emergency Ventilation System operable 4.
R.P.S. in service 5.* SRM channels in service, front panel test completed 6." IRM channels in service, front panel test completed 7 ~
a)
Primary and secondary containment integrity established b)
Primary containment check-off list (Form V) completed if required 8.
Liquid.Poison System operable 9.
Core Spray System operable To be completed if weekly functional test not already completed.
Nl-OP-43
-28 September 1983
ATTACHMENT 3 FOP~
(Continued)
ONE MILE POINT KiCLHZ, STATION UNIT NO.
1 SHORT PRE-START-UP CHECK-OFF-SYSTEMS By Checked Date
- 10. Stack Gas Monitor System in service
& on trend
- 11. Off-Gas Monitor System in service
- 12. Area and Process Monitors in service
- 13. Emergency Cooling System operable
- 14. Containment Spray System operable 15.
Emergency Service Water System operable
- 16. Technical Specification surveillance test schedule up to date
- 17. Main steam lines drained 18.
Scram timing test of control rods completed per Nl-ST-Rl and data sheets attached
- 19. Post Scram Analysis completed per Nl-RAP-6 if startup follows a scram Station Shift Supervisor Date Nl-OP-43
-29 September 1983
ATTACHMENT 4 KINE Mi E POINT hUCLEPX STATION UKIT NO.
1 MODIFIED FORM START-UP CHECK-OFF SHEET By Checked Date 1.
List any systems which were worked on during shutdown and complete a
check list, valve list and/or functional test for each System that was worked on as per Master Systems Check-off List.
b) c)
d) e)
2.
Diesel generators operable 3.
Emergency Ventilation System operable 4.
Neutron Monitoring Drives, operable 5.* SRM channels in service, front panel test completed 6.* IRM channels in service, front panel test completed 7.*APRM channels in service, front panel test com-pleted.
b)
Primary and secondary containment integrity established Primary containment check-off list completed.
9.
Liquid Poison System operable
- 10. Core Spray System operable ll. Stack Gas Monitor System in service and on trend recorder To be completed if weekly functional test not already completed.
Nl-OP-43
-30 September 1983
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NIKE. MILE PO:NT NUCL:"UR STATION UNIT NO.
1 SHORT PRE-START-UP CHECK-OFF-SYSTEi~iS
- 12. OffWas Monitor System in service
- 13. Area and Process Monitors in service 14.
Emergency Cooling System operable 15.
Containment Spray System operable 16.
Emergency Service Water System operable By Checked Date
- 17. Technical Specification surveillance test schedule up to date.
- 18. Review mark-ups for no deviations from Technical Specification Requirements
- 19. Surveillance check Control Room and Auxiliary Control Room No jumpers installed No RPS relays blocked All fuses installed properly
- 20. Main steam lines drained
- 21. Recirculation pumps in service 22.
Condensate pump(s) in service to supply water to reactor vessel 23.
Shutdown cooling system out of service and isolated
- 24. Reactor vessel vented Nl-OP-43. -31 September 1983
Owv 71 (Continued)
NINE >i"LE POINT NUCLEAR STATION UNIT NO.
1 SHORT PRE-START-UP CHECK-OFF-SYSTEYiS
- 25. Turbine auxiliary oil pumps in service and turning gear oil pump shutdown By Checked Date 26.
Scram timing test of control rods completed per Nl-ST-Rl and data sheets attached
- 27. Post Scram Analysis completed per Nl-RAP-6 if startup follows a scram Station Shift Supervisor Date Date gg-Op-43
-32 September 1983
ATTACHMENT 5 NINE MILE POINT h'dCL~ "Z. STATION bYIT NO.
1 PASTER STARTUP CHECK-OFF SHEET 1.0 Nuclear Steam Sunolv Steam and Auxiliaries Initials/Dat e Reactor vessel head in place and bolts to"qued.
1.2 CRC System in operation and charging, drive and cooling water pressure adjusted.
1.3 1.4 1.5 1.6 All contzol rods inserted.
Reactor vessel water level normal for startup.
Head spray system shutdown.
Main steam lines drained.
1.7 1.8 1.9
- 1. 10 Emergency condensezs operable.
Core Spray system operable.
Auto depressurization system operable.
Containment spray system operable.
Liquid poison system operable and poison tank level, concentration and temperature within prescribed limits-1.12 Fuel pool cooling system in service.
1.13 Control rod drive system in service and accumulators charged.
1.14
- 1. 15 Cleanup system in service.
Rod worth minimizer in service.
1.16 Recirculation pumps in service or ready for service.
1.17 Shutdown cooling system in service or isolated.
Nl-Op-43 33 September 1983
FORM XII (Continued)
NINE PEALE POINT NUCL""<X STA ION UNIT NO.
1 MASTER STARTUP CHECK-OFF SHEET 2.0 Primary and Seconder Containment Systems 2.1 Primary containment pre-startup check sheet completed.
(Form V) 2.2 2.3 Emergency ventilation system operable.
Reactor building integrity in effect.
3.0 3.1 3.2 3.3 Circulating Water and Condenser System Hotwells at normal level.
Condensate storage tank levels half full.
Condensate makeup and reject station in service.
3.4 3.5 3.6 3.7 3.8 3.9 3.10 Vacuum breakers closed.
Vacuum priming in service.
Circulating water system in service.
Gland exhauster ready for service.
Mechanical vacuum pump in service.
S.J.A.E.'s and drain tanks ready for service.
Screen wash system on "auto".
3
~ 11 Trash rake available.
3.12 OffWas system in service.
hl-OP-43
-34 Sep tember 1983
(Continued)
NINE MILE POINT %)GLAR STATiON UNIT NO.
1 MISTER STARTUP CHECK-OFF SHEET 4.0 Condensate and Feedwate" S stems Initials/Dat e 4.1 Condensate demineralizers ready for service.
4.2 4.3 4.4 4.5 4.6 Condensate and feedwater pumps ready for service.
Heater extraction 'drains open.
Heater vents open.
Reheater and moisture separator drain tanks in service.
. Condensate and feedwater lines filled and vented.
4.7 Demineralizer resin regeneration system ready for service.
5.0 5.1 5.2 5.3 5.4 5.5 5.6 Electrical System 115KV lines lines in service.
Bk's R925 and R915 and 345KV buses operable.
345 KV lines in service.
Startup transformer 101N and 101S in service.
4160 V buses in service.
600V unit substation and MCC's in service.
5.7 Control and instrument for systems in service from normal supplies.
5.8 5.9
- 5. 10 125 V DC system in service.
Diesel generators operable.
Nl OP-43
-35 September 1983
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(Conti'Duec)
PINE PILE POINT NUCL<<X STATIOh UNI NO.
1 MASTER STARTUP CHECK-OFF SHEET 6.0 6.1 6.2 Turbine Generator and Auxiliaries Generator seal oil system in service.
Generator stator cooling system in service.
Initials/Date 6.3 Generator filled with H2 and purity and pressure normal.
6.4 6.5 Shaft driven exciter ready for service.
Turbine lube oil tank level normal.
6.6 Turbine lube oil filter system in service.
'6. 7 e.s 6.9 Turning gear oil pump and bearing lift pumps on and turbine on turning gear.
Turbine supervisory instruments in service.
Control valves closed.
'6.10 6.11 6.12 6.13 6.14 6.15 6.16 6.17 Stop valves, reheat and intercept stop valves closed.
Bypass valves closed.
Load limit setting "OX" Governor run back at low speed stop.
Bypass opening jack at "0%".
Oil trip in reset position.
DC oil pump ready for service.
Steam sealing system ready for service.
Nl-OP-43
-36 September 1983
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<<(jQV T T (Con".=:"ued )
NINE YIL-POINT NUCL~R S ATION UNIT NO ~
1 RASTER STARTUP CHECK-OFF SHEET 7.0 Station A xiliarv Systems Initials/Dat e 7.1 7.2 7.3 7.4 7.5 7.6 7.7 7.8 TCLC system in service.
RCLC system in service.
Service water system in service.
Instrument and control air system in service.
Radwaste ready to receive ~ater.
Makeup water system available.
Fire protection system in service.
Heating boiler in service or available for service.
7.9 T.B. ventilation system in service.
7.10 R.B. ventilation system in service.
7.11 Radwaste ventilation system in service.
8.0 Instrumentation S stem 8.1 8.2 Neutron monitoring systems in service.
Reactor protection systems checked out and in service.
8.3 8.4 Off-gas monitoring system in service.
I Stack gas monitoring system in service.
8.5 8.6 8.7 Process radiation monitoring system in service.
Area radiation monitoring system in service.
All other required instrument checks completed.
Nl-OP-43
-37 September 1983
rTI (Cont'ued )
NINE MILE POINT NUCL>M STAT ON UNIT NO.
1 MASTER STARTUP CHECF;OFF SHEET 9.0 Prenarations for Aonroach to Critical Initials/Dat e 9.1 9.2 9.3 Master systems pre-startup check-off sheet completed Master startup check-off sheet completed through F 0
'ecirculation pumps in service.
9,4 Condensate pump(s) in service to supply water to reactor vessel.
9.5 9.6 Shutdown cooing system out of service and isolated Reactor vessel vented.
9 ~ 7 Turbine auxiliary oil pumps in service and turning gear oil pump shutdown.
9.8 Record of alarms indicating 9.9 Scram timing test of control rods completed per Nl-ST-Rl and data sheets attached.
10.0 Post Scram Analysis Completed Per Nl-RAP-6 if startup follows a scram 11.0 Nl-MST-V Visual inspection of snubbers complete and satisfactory.
Station Shift Supervisor Date Time Nl-Op-43
-38 September 1983
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NINE MILE POINT NUCLEM STATION UNIT NO ~
1 MASTER SYSTEMS PRE-START-UP CHECK-OFDF LIST The following system check-off lists must be completed or the system in operation prior to reactor startup.
Checked by (or)
System Operatin Da te 1.
Make Up Demineralizer 2.
Condensate and Transfer 3.
Codensate Demineralizers 4.
Feedwater System 5.
Condenser 6.
Circulating Water 7.
S.J.A.E.
and Vacuum Pumps
~
~
~
~
8.
OffWas System 9.
Reactor Building Ventilation System
- 10. Reactor Bldg. Emergency Vent System
- 11. Waste Building Ventilation System
- 12. Drywell Ventilation System
- 13. Liquid Poison System
- 14. Reactor Clean-Up System
- 15. Reactor Shutdown Cooling S ystem
- 16. City Water System 17.
Core Spray System
- 18. Containment Spray System Nl-OP-43
-39 September 1983
"ORM IV (Continued)
NINE MILE POINT NUCL:.4R STATION UNiT NO.
1 MASTER SYSTEMS PPX-START-UP CHECK-OFDF LIST
- 19. Fire Protection System S stem 0 crating Date
- 20. Instrument and Breathing Air System
- 21. Service Air System
- 22. Control Rod Drive System
- 23. Process Radiation Monitoring System
- 24. Area Radiation Monitoring System
- 25. Continuous Leak Rate Monitoring System
- 26. Stack and OffWas Radiation Monitoring System
- 28. Recirculation System
- 29. TIP System Available
- 30. Radioactive Waste System in Service to Receive Water
- 31. Reactor Bldg. Closed Loop Cooling Sys.
- 32. Turbine Bldg. Closed Loop Cooling Sys.
- 33. Service Water System 34-Emergency Cooling System Nl-OP-43
-40 September 1983
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FORM IV (Continued)
NINE MILE POINT hViCL~UR STATION UNIT NO.
1 MASTER SYSTEMS PRE-START-UP CHECK-OFDF LIST
- 35. Turbine Generator System 0 crating Date
- 36. Control Room Ventilation S ystem
,37.
Main Steam System
- 38. Rx. Vessel Hydro Test Nl OP 43 4l
'September 1983
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ATTACHMENT 6 Manufacturer GE GE GE GE GE GE GE Model-No; 50-531112CCKLIEKL 50-53111 2AAKDISGM 50-531233ACKLIP22 50-531110AAKALEKN 50-521110AAKLIPYL 50-5311 233CAKLIPZ X 50-531112BBKLZEKL 50-21110AAKAIPWA 50-521110AAKALPWC No;-of -Pens Two Two Two Two Two Two Two Two Two Function Scram discharge holding tank.
Scram solenoid air header pressure Total recirculation flow Core differential pressure Turbine steam flow Reactor pressure Total steam flow Reactor pressure Steam conductivity Rx vessel level Total Feedwater flow Condenser Vacuum Intake/discharge tunnel Differential temperature Condensate dissolved 02 Feedwater dissolved 02 Condensate demineral izer conductivity in.
Condensate deminer alizer conductivity out Tracor Westronics DDllE Four Plant intake water temperature Plant discharge water temperature Condenser inlet water temperature Plant water temper ature differential GE GE GE 50-31110BBKLIPMY 50-521112BBKALPKN 50-521112BBKALPJP 50-531113BBKNlPLZ Two Two Two Two Off-gas system flow Off-gas sample flow Feedwater into reactor conductivity Reactor water into cleanup system Cleanup Deminerlizer 11 conductivity out Cleanup Demineralizer 12 conductivity out Cleanup system flow Cleanup pump suction press.
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ATTACHMENT 6 Page 2
Manufacturer Texas Inst.
Baily Babcock
& Wilcox Baily Model.No; Tl-Graph 100 50-732110AAAA1 50-772331AAAA1 No; -of -Pens Multichannel Two Two Function Windspeed
& direction (Fitzpatrick)
Cooling water pump discharge ll & 12 Circul ating water intake pH Circulating water discharge pH Leeds
& Northrup Texas Inst.
Texas Inst.
Texas Inst.
Ser.
C-80-65094-1-1 TI-GRAPH-100 TI-GRAPH-100 TI-GRAPH-100 Two Drywell radiation monitors Multichannel Meteorological Tower Temperatures Multichannel Wind Speed
& Direction Multichannel Wind Speed
& Direction GE 50-521122BBEClEEC Two Shutdown cooling system temperature in Shutdown cooling system temperature out Leeds
& Northrup C 80-34263-1-1 Leeds
& Northrup C 80-34263-1-2 Two Two Containment pressure channel 12 Torus H20 level channel 12 Containment pressure channel ll Torus H20 level channel ll GE GE GE Taylor 50-531112CCKL3TYK 50-531112BBKL3EKL 50-531112CCKL3TYK 825400 Two Two Two Two
¹11 Drywell Equipment Drain Tank Level
¹12 Drywell Equipment Drain Tank Level
¹11 Drywell Floor Drain Tank Level
¹11 Drywell Floor Drain Tank Leak Rate
¹12 Drywell Floor Drain Tank Level
¹12 Drywell Floor Drain Tank Leak Rate System 12 Containment 02 Containment H2
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ATTACHMENT 6 Page 3
Manufacturer Taylor GE GE GE GE Texas Instrument Tractor Westronics GE GE Model.No.
825400 50-521113BBKL 50-521113BBKL 50-521113BBKL 50-521113BBKL 50-521112AAKL Tl Graph 100 D5E Cat.
¹50-521110 ABJE1PKA Cat.
¹50-521110 ABJE1PKA Cat. ¹50-521113 BBJEPKD Cat.
¹50-531112 BBKLIEKL Cat.
¹50-520110 CZKLIRCF No;-of Pens Two Two Two Two Two Two Three Two Two Two Two TWO One Function System ll Containment 02 Containment H2 Selectable IRM/APRN 11/12 Power Selectable IRM/APRN 13/14 Power Selectable IRM/APRN 15/16 Power Selectable IRN/APRN 17/18 Power (Selectable)
SRM counts per second Accurex Channel A
Fuel zone water level Drywell reference column temp.
Instrument room reference column temperature Inlet and discharge tunnel temperature Cond. inlet and discharge temperature Stack Gas Radiation Monitor channel ll Air ejector off-gas radiation monitor channel ll Stack Gas Radiation Monitor channel 12
'ir ejector off-gas radiation monitor channel 12 Stack Gas Rad Monitor Channel 11 Stack Gas Rad Monitor Channel 12 Drywell pressure Dew Point Temperature I
345 kV line frequency recorder Multichannel GE Cat.
¹50-521233B3 One Leeds 8 Northrup Cat. ¹ 251-15-006-30 4999-69-4999-69 499-6-EKOOO-058-056-360-016 345 kV line voltage Turbine Vibration
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ATTACHMENT 6 Page 4
Manufacturer Model.No; No;.of-Pens Function Leeds 8 Northrup Cat.
Number 251-20-000-20-69-4999-01-0999 6-EKOOO-057-360-056-553-016 Multichannel Turbine movement Westinghouse Westinghouse Westinghouse Leeds 5 Northrup GE GE GE GE GE Type KM45 Type KM45 Type KM45 821-49 1A020662 1A0900059 1A080139 1A020697 1A070016 Cat.
850-520140 AZKLIRGD Cat.
850-521110 AAKLIPRG 50-521233BBJ One One One One Power Board ll Voltage Power Board 101 Voltage 115 kV Bus Voltage Generator core monitor Multichannel Generator stator temperatures One Multichannel Turbine rotor temperature Generator hydrogen coolers and transformer temperatures One Turbine Revolutions Per Minute TWO TWO Control valve position Bypass valve position Torus - Atmos. Differential Pressure Drywell - Torus Differential Pressure Multichannel Turbine temperatures Multichannel Stator water cooling parameters GE GE GE GE GE 50-531112AAL 50-531112AAKL 50-531140AAKL 50-531140AAKL 50-531140AAKL Two TWO TWO Two TWO Off-gas temperature Air-ejector condensate flow (Selectable) 11-12-13 off-gas chillers discharge temperature Turbine oil pressure; spare Off-gas radiation; spare Stack gas radiation monitor 112-07 Stack gas radiation monitor 112-08
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Page 1
ATTACHMENT 7 WOOO W001 W002 W003 W004 W005 W006 W007 W008 W009 W010 W011 W012 W013 W014 W015 W016 W017 W018 W019 W020 W021 W022 W023 W024 W025 W026 W027 W028 W029 W030 W031 W032 W033 APRM BIAS11 COMPAR RDBLK APRM BIAS12 COMPAR RDBLK APRM BIAS11 UPSCALE INOP APRM BIAS12 UPSCALE INOP
- "RPS Cll/1 RX HI PRS A
- RPS Cll/12 RX HI PRS C
- %PS Cll/1 RX LO LVL A
- RPS Cll/2 RX LO LVL C
- %PS Cll/1 SCRDP LVL A
- %PS Cll/2 SCRDP LVL C
- %PS Cll/1 DW PRS A
- RPS Cll/2 DW PRS C
- %PS Cll/1 COND LO VAC
- RPS Cll/2 COND LO VAC
- RPS Cll/1 MSL RAD ill
- %PS Cll/2 MSL BRK 12
- %PS Cll/1 RX LOLO LVL
- RPS Cll/2 RX LOLO LVL
- %PS Cll MAN RX TRIP
- RPS Cll/1 RX NUMON ll
- %PS Cll/1 RX NUMON 12
- "RPS'll/2 RX NUMON 13
GEN LOCKOUT TRIP RELAY 2 GEN LOCKOUT TRIP RELAY 3
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ATTACHMENT 7 W034 W035 W036 W037 W038 W039 W040 W041 W042 W043 W044 W045 W046 W047 W048 W049 W050 W051 W052 W053 W054 W055 W05.6 W057 W058 W059 W060 W061 W062 W063 W064 W065 W066 W067 TURB GROUP TRIP RELAY GEN FIELD AUTO TRIP DSL GEN 102 STARTED DSL GEN 103 STARTED
- %PS Cll/1 RX LO PRS A
- RPS Cll/2 RX LO PRS C
- "Cl1 TURB TRIP EMERG GOVERNOR ELEC TRIP
- %DIST SEP TANK ill LVL
- %DIST SEP TANK 112 LVL VALUUM 1
TRIP EMERG, GOVERNOR TRIP
- RPS C12/2 RX HI PRS B
- RPS C12/1 RX HI PRS 0
- RPS C12/2 RX LO LVL B
- RPS C12/1 RX LO LVL D
- '%PS C12/2 SCRDP LVL B
- RPS C12/1 SCRDP LVL D
- RPS C12/2 DW HI PRS B
- %PS C12/1 DW HI PRS D
- RPS C12/1 COND LO VAC
- RPS C12/2 COND LO VAC
- RPS C12/1 MSL RAD 112
- RPS C12/2 MSL RAD 122
- %PS C12/1 MSL BRK 11
- RPS C12/2 MSL BRK
- RPS C12/1 RX NUMON 15
- %PS C12/1 RX NUMON 16
- "RPS C12/2 RX NUMON 17
- RPS C12/2 RX NUMON 18
- "RPS C12/2 RX LOLO LVL
- RPS C12/1 RX LOLO LVL
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ATTACHMENT 7
'H068 W069 W070 W071 W072 W073 W074 W075 W076 W077 W078 W079 W080 W081 W082 W083 W084 W085 W086 W087 W088 W089 W090 W091 W092 W093 W094 W095 W096 W097 W098 W099 W100
- %PS C12 MAN RX TRIP TURB STOP VALVE 11 TURB STOP VALVE 12 TURB STOP VALVE 13 TURB STOP VALVE 13 E.C.
RETURN V
11 E.C.
RETURN V 12 M.S. RELIEf VALVE ill M.S.
RELIEF VALVE 112 M.S.
RELIEF VALVE 113 M.S.
RELIEF VALVE 121 M.S.
RELIEF VALVE 122 M.S.
RELIEF VALVE 123
- RPS C12/1 RX LO PRS 0
- RPS C12/2 RX LO PRS B
C12 TURB TRIP
- "MOIST SEP TANK 122 LVL
- "MAINGEN OVRVOLT 118/
IA 413 MOTOR BRKR IA 813 RCVR IA 813 FILTER DELTA P LIQUID POiSON SCRAM -
FROM SCRAM READER LIQUID POISON SCRAM -
t.
page 4
ATTACHMENT 7 W101 W102 W103 W104 W105 W106 W107 TEST SWTCH MS VALVE tlll MS I V 8121 TEST SWTCH MS VAI VE gl21 NSIV t112 TEST SWTCH NS VALVE t112 MSIV if122 TEST SWTCH NS VALVE f122
e
~i
ATTACIQlENT 8 110828 POST TRIP LOG " DEMAND BOP ROW 1
BOP ROW 2 BOP ROW 3 E337 E338 E339 E340 E341 E343 A427 A430 A438 A446 C685 H496 NSS APRN 12 NUT FLX LVL APRN 13 NUT FLX LVL APRN 14 NUT FLX LVL APRN 15 NUT FLX LVL APRN 16 NUT FLX LVL APRN 18 NUT FLX LVL RRECIRC Pl 1 SUC TEMP RRECIRC PNP 11 FLOW RRECIRC P13 FLOW RRCIRC P15 FLOW CIRC WTR TEMP RISE AVERAGE TORUS TEMP-B X
X F
K0/H K4/H K//IH F
F A387 FW PMP11 DISCH FLOW KO/H A388 FW PNP12 DISCH FLOW K0/H A389 FW PNP13 DISCH FLOW K///H A390 FW ENTERG REAC TENP W
F A434 RRCIRC PNP 12 FLOW K0/H A442 RRCIRC PNP 14 FLOW K4/H A327 GENAC COLUNN TEMP F
H478 AVERAGE TORUS TEMP-A F
A363 O'12 ARW REF COLUMN TOP F
A448 012YARW VAR COLUMN TOP F
B470 TURB.
SPEED RPN B451 TURB BRGOIL HDRPRES PSIG B487 C865 D324 D374 D369 D370 D371 D367 D368 D366 C311 B473 TURB BYPAS VALVS OPENG
/
CONDENSER TENP DIFFERENC TORUS PRES PSIC NN STN INSTANT E K4/H NN STN REL V 121 LEAK F
NN STN REL V 122 LEAK F
NN STN REL V 123 l EAK F
NN STN REL V 112 LEAK F
NN STN REL V 113 LEAK F
NN STN REL V 111 LEAK F
HT WELL CHRG LVL
F CONDSR VAC LP SECT HGA F372 F374 D377 D378 A445 A391 D320 D372 D373 D375 ENERG COND SHELL111TNP F
ENERG COND SHELL121TNP F
RX WATER LVL COL-11 FT RX WATER LVL COL-12 FT RRCIRC TOTL FL CH11 K4/H FW TOTAL INST FLOW Kf/H DRYW PRES PSIG REAC PRES COL 11 PSI REAC PRES COL 12 PSI NN STN INSTANT W
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