ML21133A125
Text
-16
-15
-14
~, *
- MONTHS RELATIVE TO INITIAL FUEL LOAD - UNIT 1
-15
-14
-13
-12
-11
-10
-8
-7
-6
-5
-4 T
T T
T T
T T
T T
T T
TEST PHASE
-3
-2 T
T
-1 T
BEGIN FUEL LOAD
+1
+2
+3
'\\l
'\\l TEST PHASES 1 --------------------------.....,.11~- Ill *I*
1v-PREOPERATIONAL TEST PROGRAM*
MONTHS RELATIVE TO INITIAL FUEL LOAD - UNIT 2
-13
-12
-11
-10
-9
-8
-7
-6
-5 T
T T
T T
T T
T TEST PHASE 1
PREOPERATIONAL TEST PAOGRAMx NOTES:
(*) REFERENCE FIGURE 14.2-6 FOR PREOPERATIONAL TEST SEQUENCE (x) REFERENCE FIGURE 14.2-7 FOR PREOPERATIONAL TEST SEQUENCE
(+) REFERENCE FIGURE 14.2-5 FOR STARTUP TEST SEQUENCE
-4
-3
-2 T
T T
BEGIN FUEL
-1 LOAD T
+1
+2 V
V TEST PHASES II -+- Ill I
I STARTUP TEST PROGRAM
+
STARTUP TEST PROGRAM
+3 V
+
+4 V
IV
+5
+6
'v LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT INITIAL TEST PROGRAM SCHEDULES FIGURE 14.2-1
QA MANAGER
( 1)
STARTUP SUPT SUPPORT UNIT2 STARTUP MANAGER
( 1)
I I
I 1
STARTUP SUPT OPERATIONS (1)
I (1)
I I
I I
I
~--------------------J------------------------------ -----------------------'
QC SUPERVISOR
( 1)
PROJECT STARTUP ENGINEER
( 1 )
- ----------~-------------~----------------~.--------~
I I
I I
QC INSPECTORS (24) l&C ANO PM COORD.
( 1 )
l&C AND PM STAFF (6)
I I
I I
a GROUPSUPV.
ELEC.
( 1 )
FIELD ENGINEERS (75)
ELECTRICAL TECHS (30)
T&L LEAD ENGINEER
( 1) l&C ENGINEERS (18) l&C TECHS (65)
COST & SCHED SUPV STARTUP SCHEDULERS
( 1)
SU ADMIN COORO.
( 1 )
CLERICAL SUPERVISOR
( 1 )
CLERICAL STAFF STARTUP TEST COORDINATOR
( 1 )
SHIFT STARTUP ENGINEERS (5)
SIU GRP. SUPV'S PECO OPS. COORD.
(1)
STARTUP ENGINEERS ENGINEERING AIDES
( 11)
(80)
( 11 )
DCP COORDINATOR (1)
LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT STARTUP ORGANIZATION FIGURE 14.2-2
3 MEMBER REVIEW COMMITTEE
+
LIMERICK PLANT MANAGER TRB CHAIRMAN r
3 MEMBER REVIEW COMMITTEE
+
3 MEMBER REVIEW COMMITTEE
+
- PERMANENT MEMBER (MAY ALSO SERVE AS REVIEW COMMITTEE MEMBER)
+ REVIEW MEMBERS ASSIGNED AS REQUIRED (MINIMUM OF 3 PER COMMITTEE).
THE TRB CHAIRMAN MAY SERVE AS ONE MEMBER OF A REVIEW COMMITTEE.
LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TEST REVIEW.BOARD ORGANIZATION FIGURE 14.2-3
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
OBJECTIVES ACCEPTANCE CRITERIA REFERENCES PRECAUTIONS, NOTES, AND DEFINITIONS TEST EQUIPMENT SYSTEM TEST 6.1 PREREQUISITES 6.2 TEMPORARY INSTALLATIONS 6:3 INITIAL STATUS 6.4 TEST INSTRUCTIONS 6.5 RESTORATION APPENDICES, FIGURES, TABLES LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TEST PROCEDURE STANDARD FORMAT (SHEET 1 of 2)
FIGURE 14.2-4
STARTUP TEST PROCEDURE STANDARD FORMAT STPXX.0 MAIN BODY STPXX.0.1 OBJECTIVES STPXX.
0.2 DESCRIPTION
STPXX.0.3 ACCEPTANCE CRITERIA STPXX.
0.4 REFERENCES
STPXX.0.5 PROCEDURE STP:XX.0-A GENERAL APPENDICES STPXX.Y SUBTEST STPXX.Y.1 DISCUSSION STPXX.Y.2 PRECAUTIONS STP:XX.Y.3 TEST EQUIPMENT STPXX.Y.4 PREREQUISITES STPXX.Y.5 INITIAL STATUS STPXX.Y.6 TEST INSTRUCTIONS STPXX.Y.7 ANALYSIS STPXX.Y-A SPECIFIC APPENDICES LEGEND XX - STARTUP TEST PROCEDURE NUMBER Y - SUBTEST NUMBER A -APPENDIX DESIGNATOR LIMERICK GENERATING STATION UNITS 1 AND2 UPDATED FINAL SAFETY ANALYSIS REPORT TEST PROCEDURE STANDARD FORMAT (SHEET 2 of 2)
FIGURE 14.2~
TEST PROCEDURE DESCRIPTION OPEN HEAT WAR-NO.
VESSEL UP l
2 3
4 5
6 RANT l
CHEMICAL ANO RADIOCHEMICAL X
X X
X X
x<6J X
2 RADIATION MEASUREMENTS X
X X
X X
LEGEND 3
FUEL LOADING X
4 FULL CORE SHUTDOWN MARGIN x<*I X
TEST INDEPENDENT OF FLOW 5
CONTROL ROD DRIVE SYSTEM X
X X
X(IIJ X
CONTROLLER MODE 6
SRM PERFORMANCE AND CONTROL ROD SEQUENCE x<*I so SCRAM DEFINITE 9
WATER LEVEL REFERENCE LEG TEMPERATURE X
X X
X X
X X
10 IRM PERFORMANCE x<*l X
NOTES 11 LRPM CALIBRATION X
X X
X 12 APRM CALIBRATION X
X X
X(I0J X
X X
(1) SEE FIGURE 14.2-9 T~ST CONDITION 13 PROCESS COMPUTER PERFORMANCE VERIFICATION X
X X
X X
(5)
REGION MAP 14 RCIC SYSTEM PERFORMANCE VERIFICATION X
X x<s,6>
(2) PERFORM TEST 5, TIMING OF 4 SLOJEST 14.1 RCIC SYSTEM STARTUP AFTER LOSS OF AC P~ER TO THE SYSTEM x<6>
CONTROL RODS IN CONJUNCTION WITH 14.2 RCIC SYSTEM OPERATION WITH A SUSTAINED LOSS OF AC POJER TO x<*>
THESE SCRAMS THE SYSTEM 15 HPCI SYSTEM PERFORMACE VERIFICATION X
X (3) FULL CLOSURE ON ONE VALVE ONLY 16 SELECTED PROCESS TEMPERATURE VERIFICATION X(IO)
X X(I0J X(IO)
(4) MAY BE DONE DURING TEST CONDITION 17 SYSTEM EXPANSION X
X x<6J x<6,a, OPEN VESSEL 18 TIP UNCERTAINITY X
X (5) SOME TEST DONE DURING APPROACH TO 19 CORE PERFORMANCE X
X X
X X
X X
TEST CONDITION 20 STEAM PRODUCTION X
(6) MAY BE DONE DURING AND EARLIER 21 DELETED TEST CONDITION IF CONDITIONS WARRANT 22 PRESSURE REGULATOR RESPONSE X
X X
X(I0J X
X (7) DONE WITH STEAM BYP.~SS CAPACITY 23 FEED,,IATER CONTROL SYSTEM DEMONSTRATION X
X X
X X
x<s1 (8) SOME TEST DONE AFTE1~ PLANNED TRIPS 24 MAIN TURBINE VALVES SURVEILLANCE TEST X
x<s,91 FROM POJER 25 MAIN STEAM ISOLATION VALVES PERFORMANCE VERIFICATION X
X x<l>
~.* ~f*
(9) DETERMINE MAXIMUM POWER LEVEL TEST 26 MAIN STEAM RELIEF VALVES PERFORMANCE X
X CAN BE PERFORMED WITHOUT CAUSING 27 TURBINE TRIP AND GENERATOR LOAD REJECTION DEMONSTRATION xP>
X, SD<2
- 11 >
x sD<2>
REACTOR SCRAM 28 SHUT~N FROM OUTSIDE THE MAIN CONTROL ROOM DEMONSTRATION x SD121 (10) TEST NOT REQUIRED FOR UNIT 2 29 RECIRCULATION FLOJ CONTROL DEMON ST RA TI ON x<s) x<s1 (11) TEST NOT REQUIRED FOR UNIT 2.
NO 30 RECIRCULATION SYSTEM X
X X
X TC-3 SCRAM DURING S"!"P-27. NO. STP-5 31 LOSS OF TURBINE-GENERATOR ANO OFFSITE POJER x.so SCRAM TIMING TEST DUE TO NO. SCRAM 32 ESSENTIAL HVAC SYSTEM OPERATION ANO CONTAINMENT HOT X
X X
(12) FOR UNIT 2 ONLY, FULL CLOSURE OF ONE VALVE PENETRATION TEMPERATURE VERIFICATION 33 PIPING STEADY STATE VIBRATION X
X xoi X
X(S,6,8)
TO DETERMINE THE MAXIMUM PCMER LEVEL 34 OFFGAS SYSTEM PERFORMANCE VERI FI CATION X
X X
X(S)
WHICH WILL NOT CAUSE A REACTOR SCRAM WILL 35 RECIRCULATION FLCM CALIBRATION x<*>
X x<***-*1 BE PERFORMANCE AT TE~T CONDITIONS.
36 PIPING DYNAMIC TRANSIENT (13)
X X
X X
(13) MAIN STEAM TURBINE TRIP TEST FOR UNIT 2 37 DELETED (REF. STARTUP TEST STP-36) AT 100"1.
38 DELETED LEVEL WILL BE PERFORMED DURING 70 REACTOR WATER CLEANUP SYSTEM PERFORMANCE VERIFICATION X
C~ERCIAL OPERATION OF THAT UNIT.
71 RESIDUAL HEAT REMOVAL SYSTEM PERFORMANCE VERIFICATION x<6>
x<*.*1 LIMERICK GENERATING STAT I ON UNI TS 1 & 2 UPDATED FIN AL SAFETY AN ALYS IS REPORT STARTUP TEST SEQUENCE (UNI TS 1 & 2)
FIGURE 14.2-5 REV. 3 NOV. /93
-16 y
-15 y
MONTHS TO INITIAL FUEL LOAD
-14
-13
-12
-11
-10
-9
-8
-7
-6
-5
-4
-3
-1 T
T T
T T
T T
T T
T y
T T
FEEDWATER (P-45.1)
STANDBY DIESEL GENERATOR SYSTEM AND LOADING (P-24.1 & P-100.4) 125 VOLT DC REACTOR WATER CLEANUP (p 2 1)
EMERGENCY (P-61.1)
UNINTERRUPT.
.AC.
--~~~~~*-*t-------PR_1_M_A_R_Y_c_o_N_T_A~~~M-EN~T~IS~O~L~A~T~IO~N~,~IL~R~T~,~A-N_D_s_u_P_PR_E_s_s_1o_N_P_o_o_L ______ ~--
(P-57.1)
(P-54.1)
(P-59.1, P-59.2 & P-59.3)
STANDBY CLASS 1 E 440 VOLT LOAD CENTERS RESIDUAL HEAT REMOVAL FUEL HANDLING
.GAS TREATMENT.
- ~--------~~"'!"!"" ____.....,______ *
(P-5.1)
(P-49.1)
(P-81.1)
(P-70.1)
BEGIN FUEL LOAD 0
T CLASS 1 E 440 VOLT MCC'S
---I-N-ST_R ___ C_O_N_T_R_O_L_R_O_O_M""""'"""' __ (..,P--6111111.1-),...,.......
1111111111111..... _______
RH R SERVICE FIRE COLD
~
H&V CONTROL STRUCTURE H&V PROTECTION NUCLEAR INSTRUMENTATION FUNCTIONAL WATER.
(P-17.1)
(P-32.1)
(P-30.1 & P-30.2)
(P-16.1)
(P-13.1, P-13.2, P-13.3 & P-13.4)
(P-78.1, P-78.2, P-78.3)
(P-100_1)
INSTRUMENT AIR REACTOR CONTROL ROD DRIVE HYDRAULICS
~REACTOR (P-18.1)
ENCLOSURE et------D-1 E-S-EL ___
RE_A_C_T_O_R ___
"'!'! (P!!""-5'!!!5!'"1111"'!")--C-O_N_T_R_O_L___________
7W ENCLOSURE CRANE 4KV COOLING WATER~
FUEL OIL NON-NUCLEAR INST..
DRIVE CON~~gL (P-99.1)
PROCESS & AREA (P-4.1) fP-14.1l(P-23.1)
(P-801)
(P-56.1)
RADIATION CONTAINMENT 125/250 VOLT DC (P-2.2)
CONDENSATE AND REFUELING WATER TRANSFER (P-37.1)
- SPRAY POND PUMP
. MAIN STEAM MONITORING ATMOSPHERIC CONTROL STR~1~1~r~~~~~~vt~DBY (P-83.1)
CONDENSE~ Al~P-79.1,,79.2) *
(P-73.1)
ENCLOSURE H&V STANDBY LIQUID CONTROL REMOVAL (P-28.1 & P-28.2)
P-53-1 )
(P-43.1)
REACTOR INTERNALS VIBRATION & INSPECTION REACTOR RECIRCULATION (P-64.1)
- (P-62.1).
CORE SPRAY LIQUID (P-51.1)
.RADWASTE.
(P-69.1)
(P-52.1}
HPCI CONDENSATE
- PRIMARY CONTAINMENT VENTILATION (P-44.1)
.---------(P--6-0-.1-)----------4*
FUEL POOL COOLING~
- RCIC G.SEOUS RADWAS.E (P-36.1) SOLi D (P-50.1)
(P-72.1)
EXTRACTION STEAM AND FEEDWATER HEATER (P-46.1).
CONDENSATE DEMINERALIZER COOLING (P-39-1)
TOWER (P-41.1)
- CIRCULATING WATER (P-42.1)
- MAIN TURBINE CONTROL SEISMOGRAPHICAL (P-93.2)
MONITORING
~P-99.2~
PUBLIC ADDRESS AND EVALUATION (P-99.3)
.RADWASTE.
(P-68.1)
PRIMARY REACTOR ENCLOSURE H&V CONTAINMENT **~--------(~P--34 ___ 1 )-------~**
INSTRUMENT GAS O
O O
.(P-25 1 ).
REACT (:-SPBR.l )TECTI N FIRE PROTECTION STANDBY HALON DC LIGHTING TURBINE ENCLOSURE HVAC (P-13.5)
(P-7.1)
(P-33.1) RADWASTE ENCLOSURE HVAC (P-65.1)
PROCESS SAMPLING PLANT(P-76.1 l ANNUNCIATOR (P-91.1)
LOSS OF INSTRUMENT AIR (P-100.2)
SNUBBER TESTING (P-100.3)
NOTES:
SYSTEM NAME
- 1.
TEST NUMBER(S)
- 2.
LINE DURATION INCLUDES COMPLETION OF SYSTEM TEST PREREQUISITES AND PERFORMANCE OF PREOPERATIONAL TESTING.
LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PREOPERATIONAL TEST SEQUENCE UNIT 1 FIGURE 14.2-6
Months to Fuel Load
-16
-15
-14
-13
-12
-11
-10
-9
-8
-7
-6
-5
-4
-3
-2
-1 Begin Fuel Load 0
T T
y y
y y
y T
~
~
T T
T
~
y y
y Electrical systems energized (P3. 1)
Plant annunciator Uninterruptable A.C power (P91.1)
(P57.1)
Fire protection, water and smoke detection (P13.1, P13.4)
Instrument air P18.1 Primary containment instrumen.as Process sarrpling (P25.1)
- --------------1**
(P76.1)
(P11.1)
- Reactor encl. cooling water Turbine encl cooling water (P14.1)
(P15.1)
Diesel generator fuel oil (P23.1)
- Standby diesel generators Diesel generator encl HV A.C Fuel pool cooling (P28.1)
(P24.1)
Residual heat removal StandbL DC lighting (P7.1) 125 Volt DC Public address and evacuation (P2. 1) 1251250 Volt DC DIG loading (P100.4)
(P99.3)
Fire protection, CO2 and Hin (P2.2)
(P13.2, P13.5)
Loss of instrument air
.OSI accident sampllnit ~0.2)
(P76.2)
Caiodic and freeze protiiion Emergency service water (P54.1) *
(P85.1 and P85.2)
RHR service water (P16.1)
Loss of offsite power (PHl0.1)
Fuel handling (P81.1) j°lidradwaste(P68.1-(P35.1) *
(P49.1)
- RCC Equipment drain collection and liquid radwaste CooUng tower (P41
- 1)
Circulating water (P42.1)
Core spray (PS0.1)
(P51.1)
-*~------*-
Standby liquid control (P52* 1)
Gaseous radwaste recorrbiners and filters (P69.1, P69.3)
(P72.1)
- Containment atmospheric control Area and process radiatiion monitoring (P73.1) * *
- ---------------1**
Reactor water cleanup (P53.1)
(P79.1, P79.2)
Reactor vessel instrumentation
( P61.1)
Reactor internals, vibration, inspection (P62.1)
(PS0.1)
Reactor recirculation (P64.1)
Control rod drive hydraulic system (P55.1)
Control rod drive control
- Reactor protection, redundant reactivity control system (P56.1)
Condensate filter demlneralizers (P58.1, P58.2)
- Nuclear instrumentation (P78.1, P78.2, P78.3)*
Primary containment isolation, suppression pool and ILRT (P59.1, P59.2, P59.3)
Condenser and air removal (P43-1)
- 1----------------------~--
(P39.1)
- Condensate (P44.1)*
(P45.1)
Extraction steam and feedwater heaters *
(P46.1)
Main steam, automatic depressurization, steam leak detection Turbine supervisory
- Main turbine control (EHC) *
(P83.1, P83.2, P83.3)
(P93.3)
Reactor encl unit cooler (P66.1)
(P93.2)
Reactor encl and refuel floor HVAC ( P34.1, P34.2)
Drywall HVAC Turbine encl unit coolers*
(P60.1)
(P66.2)
- Standby gas treatment Turbine encl HVAC (P70.1)
(P33.1)
NOTES:
- 1.
System Name Test No.
- 2. Line durations include completion of system test prerequisites and performance of preoperational testing LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT PREOPERATIONAL TEST SEQUENCE UNIT2 FIGURE 14.2-7
- 6.
SYSTEM TEST 6.1 PREREQUISITES 6.1.1 SYSTEM LEVEL PREREQUiblTES 6. L 1. 1 SYSTEM TURNOVER Turnover from Bechtel Construction to PECo Startup is complete.
6.1.1.2 SYSTEM WALK THROUGH The system has been walked througL and verified complete to the extent required to conduct this test.
6.1.1.3 HYDROSTATIC TESTING AND CLEANNESS VERIFICATIONS Hydrostatic testing and cleanness verifications have been completed to the extent required to perform this test, and records are on file.
6.1.1.4 STARTUP WORK LIST The Startup Work List has been reviewed, and outstanding or closed items (if any) have been evaluated as to the effect on this test.
A summary list of outstanding items is attached.
6.1.1.5 STARTUP FIELD REPORTS Startup Field Reports pertaining to this system have been reviewed, and outstanding or closed items (if any) have been evaluated as to their effect on this test.
A summary list of outstanding items is attached.
6.1.1.6 TEMPORARY MODIFICATIONS The Log of Temporary Modifications has been reviewed, is current, and is satisfactory for testing.
6.1.1.7 STARTUP WORK ORDERS AND MAINTENANCE REQUEST FORMS Startup Work Orders and Maintenance Request Forms pertaining to this system have been reviewed, and outstanding items (if any) have been evaluated as to their effect on this test.
Verified by Date LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TYPICAL TEST PREREQUISITES (SHEET 1)
FIGURE 14.2-8
6.1.2
'COMPONENT LEVEL PREREQUISITES 6.1.2.1 COMPONENT TECHNICAL TESTS The required inspections and tests, as indicated in the Component Technical Test Summary, Appendix A, have been
- completed and verified by the responsible group.
6.1.2.2 COMPONENT CALIBRATIONS The required inspections and calibrations, as indicated in the Component Calibration Summary, Appendix B, have been completed and verified by the responsib]e group.
Verified by Date LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TYPICAL TEST PREREQUISITES.
(SHEET 2)
FIGURE 14.2-8
200 180 160 140 120 a:
w ;:
0
~
100 z
w 0 a:
w
~
80 60 40 20 A. NATURAL CIRCULATION B. MINIMUM RECIRCULATION PUMP SPEED C. ANALYTICAL LOWER LIMIT OF MASTER POWER FLOW CONTROL D. ANALYTICAL UPPER LIMIT OF MASTER POWER FLOW CONTROL
,~~
~\\>-~\\.,
~SC
\\)-,~~
TYPICAL STARTUP PATH MINIMUM POWER LINE 10 20 30 40 50 60 PERCENT CORE FLOW 70 80 90 100 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT POWER-FLOW OPERATING MAP (UNIT 1)
(SHEET 1 OF 4)
FIGURE 14.2-9 (UNIT 1 - HISTORICAL)
Rev. 16 09/12
TEST CONDITION (TC) REGION DEFINITIONS TEST CONDITION NO.
1 2
3 4
5 6
POWER-FLOW MAP REGION AND NOTES BEFORE OR AFTER MAIN GENERATOR SYNCHRONIZATION BETWEEN 5 AND 20%
THERMAL POWER-WITHIN +10, -0% OF M-G SET MINJMUM OPERATING SPEED LINE IN LOCAL MANUAL MODE..
AFTER MAIN GENERATOR SYNCHRONIZATION BETWEEN THE 45 AND 75% POWER ROD LINES BETWEEN M-G SET MINIMUM SPEEDS FOR LOCAL MAN~AL AND MASTER MANUAL MODES.
FROM 45 TO 75% CONTROL ROD LINES-CORE FLOW BETWEEN 80 AND 100% OF ITS RATED VALUE.
ON THE NATURAL CIRCULATION CORE FLOW LINE-WITHIN +o, -5% OF THE INTERSECTION WITH THE 100% POWER ROD LINE.
WITHIN +o, -5% OF THE 100% CONTROL ROD LINE-WITHIN -0, +5% OF THE ANALYTICAL LOWER LIMIT OF MASTER FLOW CONTROL.
WITHIN +o, -5% OF RATED 100% POWER -WITHIN
+o, -5% OF RATED 100% CORE FLOW RATE.
LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT POWER-FLOW OPERATING MAP (UNIT 1)
(SHEET 2 OF 4)
FIGURE 14.2-9 Rev. 16 09/12 (UNIT 1 - HISTORICAL)
a:
w
~
0
- 0.
.... z w u a:
w
- 0.
110------------------------------------
100 90 80 70 60 50 40 30 20 10 D
A. NATURAL CIRCULATION B. MINIMUM REICRCULATION PUMP SPEED C. ANALYTICAL LOWER LIMIT OF MASTER POWER FLOW CONTROL D. ANALYTICAL UPPER LIMIT OF MASTER POWER FLOW CONTROL 10 TYPICAL STARTUP PATH 20 30 40 50 60 PERCENT CORE FLOW MINIMUM POWER LINE 70 80 90 100 110 LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT POWER-FLOW OPERATING MAP (UNIT 2)
(SHEET 3 OF 4)
FIGURE 14.2-9 (UNIT 2 - HISTORICAL)
Rev. 16 09/12
TEST CONDITION (TC) REGION DEFINITIONS TEST CONDITION NO.
1 2
3 4
5 6
POWER-FLOW MAP REGION AND NOTES BEFORE OR AFTER MAIN GENERATOR SYNCHRONIZATION BETWEEN 5 AND 20%
THERMAL POWER-WITHIN +10, --0% OF M-G SET MINIMUM OPERATING SPEED LINE IN LOCAL MANUAL MODE.
AFTER MAIN GENERATOR SYNCHRONIZATION BETWEEN THE 45 AND 75% POWER ROD LINES BETWEEN M-G SET MINIMUM SPEEDS FOR LOCAL MANUAL AND MASTER MANUAL MODES.
FROM 45 TO 75% CONTROL ROD LINES-CORE FLOW BETWEEN 80 AND 100% OF ITS RATED VALUE.
ON THE NATURAL CIRCULATION CORE FLOW LINE-WITHIN +o, -20% OF THE INTERSECTION WITH THE 100% POWER ROD LINE.
WITHIN +o, -5% OF THE 100% CONTROL ROD LINE-WITHIN -0, +5% OF THE ANALYTICAL LOWER LIMIT OF MASTER FLOW CONTROL.
WITHIN +o, -5% OF RATED 100% POWER -WITHIN
+o, -5% OF RATED 100% CORE FLOW RATE.
LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT POWER-FLOW OPERATING MAP (UNIT 2)
(SHEET 4 OF 4)
FIGURE 14.2-9 (UNIT 2 - HISTORICAL)
Rev. 16 09/12