ML21133A125
Text
MONTHS RELATIVE TO INITIAL FUEL LOAD - UNIT 1 BEGIN FUEL
-15 -14 -13 -12 -11 -10 -8 -7 -6 -5 -4 -3 -2 -1 LOAD +1 +2 +3 T T T T T T T T T T T T T T '\l '\l TEST PHASES TEST PHASE 1 - - - - - - - - - - - - - - - - - - - - - - - - - - . . . . . , . 1 1 ~ - Ill *I* 1v-STARTUP TEST PREOPERATIONAL TEST PROGRAM* PROGRAM
+
MONTHS RELATIVE TO INITIAL FUEL LOAD - UNIT 2 BEGIN FUEL
~, 15 -14
-13 -12 T
-11 T
-10 T
-9 T
-8 T
-7 T
-6 T
-5 T
-4 T T
-3 -2 T
-1 T
LOAD +1 V
+2 V V
+3 +4 V
+5
'v
+6 TEST PHASES TEST PHASE 1 II -+- Ill I
I IV STARTUP TEST PREOPERATIONAL TEST PAOGRAMx PROGRAM +
NOTES: LIMERICK GENERATING STATION UNITS 1 AND 2
(*) REFERENCE FIGURE 14.2-6 FOR PREOPERATIONAL TEST SEQUENCE UPDATED FINAL SAFETY ANALYSIS REPORT (x) REFERENCE FIGURE 14.2-7 FOR PREOPERATIONAL TEST SEQUENCE
(+) REFERENCE FIGURE 14.2-5 FOR STARTUP TEST SEQUENCE INITIAL TEST PROGRAM SCHEDULES FIGURE 14.2-1
UNIT2 QA MANAGER STARTUP MANAGER
( 1) ( 1)
I I
I STARTUP SUPT 1 STARTUP SUPT SUPPORT : OPERATIONS ( 1)
(1)
I I I I I ; I
~--------------------J------------------------------ -----------------------'
PROJECT STARTUP QC SUPERVISOR ENGINEER
( 1) ( 1)
- ----------~-------------~
I I
I I
I I
I ----------------~.--------~
.----------- I a GROUPSUPV. COST & SCHED STARTUP TEST PECO OPS. COORD.
l&C ANO PM COORD. T&L LEAD ENGINEER SU ADMIN COORO. SIU GRP. SUPV'S ELEC. SUPV COORDINATOR
( 1) ( 1) ( 1) ( 1) ( 1) ( 1) ( 11) (1)
STARTUP SHIFT STARTUP STARTUP DCP QC INSPECTORS l&C AND PM STAFF FIELD ENGINEERS l&C ENGINEERS ENGINEERS COORDINATOR SCHEDULERS ENGINEERS (5 )
(24) (6) (75) (18) (80) (1)
ELECTRICAL l&C CLERICAL ENGINEERING TECHS TECHS SUPERVISOR ( 1) AIDES (30) (65) ( 11 )
CLERICAL STAFF LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT STARTUP ORGANIZATION FIGURE 14.2-2
LIMERICK PLANT MANAGER TRB CHAIRMAN r
3 MEMBER REVIEW 3 MEMBER REVIEW 3 MEMBER REVIEW COMMITTEE COMMITTEE 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. OBJECTIVES
- 2. ACCEPTANCE CRITERIA
- 3. REFERENCES
- 4. PRECAUTIONS, NOTES, AND DEFINITIONS
- 5. TEST EQUIPMENT
- 6. SYSTEM TEST 6.1 PREREQUISITES 6.2 TEMPORARY INSTALLATIONS 6:3 INITIAL STATUS 6.4 TEST INSTRUCTIONS 6.5 RESTORATION
- 7. 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 (5) 13 PROCESS COMPUTER PERFORMANCE VERIFICATION X X X X X 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 SD 121 (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 X(S) WHICH WILL NOT CAUSE A REACTOR SCRAM WILL OFFGAS SYSTEM PERFORMANCE VERI FI CATION X X X 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
MONTHS TO INITIAL FUEL LOAD BEGIN FUEL LOAD
-16 -15 -14 -13 -12 -11 -10 -9 -8 -7 -6 -5 -4 -3 -1 0 y y T T T T T T T T T T y T T T
- FEEDWATER (P-45.1)
STANDBY DIESEL GENERATOR SYSTEM AND LOADING (P-24.1 & P-100.4) *
- 125 VOLT DC (p 2 1)
.AC.
UNINTERRUPT.
- EMERGENCY SERVICE WATER REACTOR WATER CLEANUP (P-61.1) *
--~~~~~*-*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)
CLASS 1 E 440 VOLT LOAD CENTERS (P-5.1)
(P-54.1)
RESIDUAL HEAT REMOVAL (P-49.1)
(P-59.1, P-59.2 & P-59.3)
FUEL HANDLING (P-81.1)
- - STANDBY
.GAS TREATMENT.
(P-70.1)
- CLASS 1 E 440111111VOLT MCC'S
---I-N-ST_R___C_O_N_T_R_O_L_R_O_O_M""""'"""'__(..,P--6 .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-1E-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- 2 3.1) (P-801) (P-56.1) RADIATION CONTAINMENT 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) *
- 125/250 VOLT DC (P-2.2) *
- ENCLOSURE H&V (P-28.1 & P-28.2)
- P- 53 -1)
- REMOVAL (P-43.1) REACTOR INTERNALS REACTOR RECIRCULATION VIBRATION & INSPECTION (P-64.1) * (P-62.1).
LIQUID
- CORE SPRAY (P-51.1) *
.RADWASTE.
(P-69.1)
- CONDENSATE *
(P-44.1)
HPCI (P-52.1}
- PRIMARY CONTAINMENT VENTILATION
.---------(P--6-0-.1-)----------4* NOTES:
FUEL POOL COOLING~ *
- G.SEOUS RADWAS.E (P-36.1) SOLi D (P-50.1) (P-72.1) SYSTEM NAME
- 1. * *
.RADWASTE. TEST NUMBER(S)
(P-68.1)
PRIMARY REACTOR ENCLOSURE H&V 2. LINE DURATION INCLUDES COMPLETION CONTAINMENT INSTRUMENT GAS
- ~--------(~P--34 O O
___1)-------~**
O OF SYSTEM TEST PREREQUISITES AND PERFORMANCE OF PREOPERATIONAL EXTRACTION STEAM AND .(P- _ ).
- REACT (:-SPBR.l )TECTI N
- TESTING.
25 1 FIRE PROTECTION STANDBY FEEDWATER HEATER CONDENSATE AND HALON DC LIGHTING REFUELING * (P-46.1). TURBINE * * *
- WATER TRANSFER CONDENSATE DEMINERALIZER ENCLOSURE HVAC (P-13.5) (P-7.1)
- (P-37.1)
- COOLING (P- 39 -1)
TOWER
- (P-33.1) RADWASTE ENCLOSURE HVAC
- (P-41.1) * * (P-65.1)
- CIRCULATING PROCESS WATER SAMPLING
- (P-42.1)
- MAIN TURBINE PLANT(P- 76.1 l CONTROL LIMERICK GENERATING STATION SEISMOGRAPHICAL (P-93.2)
MONITORING ANNUNCIATOR (P-91.1) LOSS OF INSTRUMENT AIR UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT
~P-99.2~
PUBLIC ADDRESS (P-100.2)
PREOPERATIONAL TEST SEQUENCE AND EVALUATION UNIT 1 SNUBBER TESTING (P-99.3) (P-100.3) FIGURE 14.2-6
Begin Months to Fuel Load Fuel Load
-16 -15 -14 -13 -12 -11 -10 -9 -8 -7 -6 -5 -4 -3 -2 -1 0 y y y y y T T Electrical systems energized (P3. 1)
Plant annunciator T ~ ~
.*.______ T StandbLDC lighting (P7.1)
T 125 Volt DC T ~ y y y Uninterruptable A.C power (P91.1) (P57.1) Fire protection, water and smoke detection (P13.1, P13.4)
Public address and evacuation (P99.3) *
(P2. 1)
Fire protection, CO2 and Hin * (P2.2)
- 1251250 Volt DC
- Instrument air P18.1
- --------------1**
Process sarrpling Primary containment instrumen.as
- (P25.1) .OSI
- (P13.2, P13.5) accident sampllnit ~0.2)
Loss of instrument air
- *
- Service water (P76.1) (P76.2) Caiodic and freeze protiiion (P11.1)
Reactor encl. cooling water (P14.1)
- *
- Emergency service water (P54.1) * (P85.1 and P85.2)
Turbine encl cooling water RHR service water (P15.1)
- Diesel generator fuel oil (P23.1)
Diesel generator encl HVA.C Standby diesel generators (P24.1)
DIG loading (P100.4)
(P16.1)
Loss of offsite power (PHl0.1)
(P28.1)
Fuel handling Fuel pool cooling *
(P35.1)
Residual heat removal (P81.1) j°lidradwaste(P68.1-(P49.1)
Equipment drain collection and liquid radwaste
- Core spray RCC (PS0.1) ***
Gaseous radwaste recorrbiners and filters (P69.1, P69.3) *
(P51.1)
-*~------*-
- ---------------1**
HPCI (P72.1)
- Containment atmospheric control (P 52
- 1)
Area and process radiatiion monitoring Standby liquid control (P73.1)
- (P53.1) (P79.1, P79.2)
Reactor vessel
( P61.1)
- Reactor internals, vibration, inspection instrumentation (P62.1)
- Reactor recirculation (PS0.1)
(P64.1)
Control rod drive hydraulic system (P55.1)
Control rod drive control *
- Reactor protection, redundant reactivity control system (P58.1, P58.2)
(P56.1) *
- Nuclear instrumentation (P78.1, P78.2, P78.3)* NOTES:
- Primary containment isolation, suppression pool and ILRT System Name 1.
- CooUng tower * (P59.1, P59.2, P59.3) Condenser and air removal Test No.
(P 41 *1) Circulating water
- **1----------------------~--
Condensate filter demlneralizers (P 43-1)
- (P42.1) (P39.1) *Condensate (P44.1)*
- Feedwater (P45.1)
- 2. Line durations include completion of system test prerequisites and performance
- of preoperational testing (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) LIMERICK GENERATING STATION UNITS 1 AND 2 Reactor encl and refuel floor HVAC ( P34.1, P34.2) Standby gas treatment UPDATED FINAL SAFETY ANALYSIS REPORT
- Drywall HVAC * (P70.1)
- Turbine encl unit coolers* (P60.1) PREOPERATIONAL TEST SEQUENCE (P66.2)
- Turbine encl HVAC (P33.1)
- FIGURE 14.2-7 UNIT2
Verified by Date
- 6. SYSTEM TEST 6.1 PREREQUISITES 6.1.1 SYSTEM LEVEL PREREQUiblTES 6.L 1.1 SYSTEM TURNOVER Turnove r from Bechtel Constru ction 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 Hydrost atic testing and cleanne ss verifica tions have been complete d 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 outstand ing or closed items (if any) have been evaluate d as to the effect on this test. A summary list of outstand ing items is attached .
6.1.1.5 STARTUP FIELD REPORTS Startup Field Reports pertaini ng to this system have been reviewed , and outstand ing or closed items (if any) have been evaluate d as to their effect on this test.
A summary list of outstand ing items is attached .
6.1.1.6 TEMPORARY MODIFICATIONS The Log of Tempora ry Modific ations has been reviewed , is current, and is satisfac tory for testing.
6.1.1.7 STARTUP WORK ORDERS AND MAINTENANCE REQUEST FORMS Startup Work Orders and Mainten ance Request Forms pertaini ng to this system have been reviewed , and outstand ing items (if any) have been evaluate d as to their effect on this test.
LIMERICK GENERATIN G STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TYPICAL TEST PREREQUISITES (SHEET 1)
FIGURE 14.2-8
Verified by Date 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.
LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT TYPICAL TEST PREREQUISITES.
(SHEET 2)
FIGURE 14.2-8
200 180 A. NATURAL CIRCULATION B. MINIMUM RECIRCULATION PUMP SPEED C. ANALYTICAL LOWER LIMIT OF MASTER POWER FLOW CONTROL 160 D. ANALYTICAL UPPER LIMIT OF MASTER POWER FLOW CONTROL 140 120 ,~~
~\>-~\.,
a: ~SC w \)-,~~
0
...z
~
100 w
0 a:
w
~
80 60 40 TYPICAL STARTUP PATH MINIMUM POWER LINE 20 10 20 30 40 50 60 70 80 90 100 PERCENT CORE FLOW LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT POWER-FLOW OPERATING MAP (UNIT 1(UNIT
- HISTORICAL) 1)
(SHEET 1 OF 4)
FIGURE 14.2-9 Rev. 16 09/12
TEST CONDITION (TC) REGION DEFINITIONS TEST CONDITION NO. POWER-FLOW MAP REGION AND NOTES 1 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 ..
2 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.
3 FROM 45 TO 75% CONTROL ROD LINES-CORE FLOW BETWEEN 80 AND 100% OF ITS RATED VALUE.
4 ON THE NATURAL CIRCULATION CORE FLOW LINE-WITHIN +o, -5% OF THE INTERSECTION WITH THE 100% POWER ROD LINE.
5 WITHIN +o, -5% OF THE 100% CONTROL ROD LINE-WITHIN -0, +5% OF THE ANALYTICAL LOWER LIMIT OF MASTER FLOW CONTROL.
6 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 (UNIT
- HISTORICAL) 1)
(SHEET 2 OF 4)
FIGURE 14.2-9 Rev. 16 09/12
110------------------------------------
D A. NATURAL CIRCULATION B. MINIMUM REICRCULATION PUMP SPEED 100 C. ANALYTICAL LOWER LIMIT OF MASTER POWER FLOW CONTROL D. ANALYTICAL UPPER LIMIT OF MASTER POWER FLOW CONTROL 90 80 70 a:
w
~ 60 0
0.
....z w
u a: 50 w
0.
40 30 TYPICAL MINIMUM POWER LINE STARTUP 20 PATH 10 10 20 30 40 50 60 70 80 90 100 110 PERCENT CORE FLOW LIMERICK GENERATING STATION UNITS 1 AND 2 UPDATED FINAL SAFETY ANALYSIS REPORT POWER-FLOW OPERATING MAP (UNIT 2(UNIT
- HISTORICAL) 2)
(SHEET 3 OF 4)
FIGURE 14.2-9 Rev. 16 09/12
TEST CONDITION (TC) REGION DEFINITIONS TEST CONDITION NO. POWER-FLOW MAP REGION AND NOTES 1 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.
2 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.
3 FROM 45 TO 75% CONTROL ROD LINES-CORE FLOW BETWEEN 80 AND 100% OF ITS RATED VALUE.
4 ON THE NATURAL CIRCULATION CORE FLOW LINE-WITHIN +o, -20% OF THE INTERSECTION WITH THE 100% POWER ROD LINE.
5 WITHIN +o, -5% OF THE 100% CONTROL ROD LINE-WITHIN -0, +5% OF THE ANALYTICAL LOWER LIMIT OF MASTER FLOW CONTROL.
6 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 (UNIT
- HISTORICAL) 2)
(SHEET 4 OF 4)
FIGURE 14.2-9 Rev. 16 09/12