ML062360256
| ML062360256 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/21/2006 |
| From: | NRC/NRR/ADRO/DORL/LPLIV |
| To: | |
| Donohew J N, NRR/DORL, 415-1307 | |
| Shared Package | |
| ML062370104 | List: |
| References | |
| TAC MC6897 | |
| Download: ML062360256 (10) | |
Text
TABLE OF CONTENTS 1.0 USE AND APPLICATION................................
1.1-1 1.1 D efinitions..........................................................................................
1.1-1 1.2 Logical C onnectors............................................................................
1.2-1 1.3 Com pletion Tim es..............................................................................
1.3-1 1.4 Frequency..........................................................................................
1.4-1 2.0 SAFETY LIMITS (SLs)....................................................................
2.0-1 2.1 S Ls...................................................................................................
2.0-1 2.2 S L V iolations....................................................................................
2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY..... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS....................................................
3.1-1 3.1.1 SHUTDOWN MARGIN (SDM) 3.1-1 3.1.2 Core Reactivity 3.1-2 3.1.3 Moderator Temperature Coefficient (MTC)......................................
3.1-4 3.1.4 Rod Group Alignment Limits............................................................
3.1-7 3.1.5 Shutdown Bank Insertion Limits 3.1-11 3.1.6 Control Bank Insertion Limits............................................... :.......... 3.1-13 3.1.7 Rod Position Indication....................................................................
3.1-16 3.1.8 PHYSICS TESTS Exceptions - MODE 2........................................
3.1-19 3.1.9 RCS Boron Limitations < 500°F......
3.1-21 3.2 POWER DISTRIBUTION LIMITS 3.2-1 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))
(Fa M ethodology)......................................................................
3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F')
......................... 3.2-6 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology)..................................................
3.2-9 3.2.4 QUADRANT POWER TILT RATIO (QPTR) 3.2-10 3.3 INSTRUMENTATION............................................................................
3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation.................
3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)
.Instrum entation..........................................................................
3.3-25 3.3.3 Post Accident Monitoring (PAM) Instrumentation..............
3.3-46 CALLAWAY PLANT 1
'Amendment 174
TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.4 Remote Shutdown System 3.3-51 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation..................................
3.3-54 3.3.6 Containment Purge Isolation Instrumentation 3.3-56 3.3.7 Control Room Emergency Ventilation System (CREVS)
Actuation Instrumentation 3.3-61 3.3.8 Emergency Exhaust System (EES) Actuation Instrumentation 3.3-66 3.3.9 Boron Dilution Mitigation System (BDMS) 3.3-71 3.4 REACTOR COOLANT SYSTEM (RCS)................................................
3.4-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits...................................................
3.4-1 3.4.2 RCS Minimum Temperature for Criticality.......................................
3.4-3 3.4.3 RCS Pressure and Temperature (P/T) Limits..................................
3.4-4 3.4.4 RCS Loops - MODES 1 and 2.........................................................
3.4-6 3.4.5 RCS Loops - MODE 3.....................................................................
3.4-7 3.4'6 RCS Loops - MODE 4.....................................................................
3.4-10 3.4.7 RCS Loops - MODE 5, Loops Filled................................................
3.4-12 3.4.8 RCS Loops - MODE 5, Loops Not Filled.........................................
3.4-15 3.4.9 Pressurizer...............................................
3.4-17 3.4.10 Pressurizer Safety Valves................................................................
3.4-19 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)...........
3.4-21 3.4.12 Cold Overpressure Mitigation System (COMS)............................... 3.4-25 3.4.13 RCS Operational LEAKAGE..........................................................,3.4-30 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage 3.4-32 3.4.15 RCS Leakage Detection Instrumentation........................................
3.4-36 3.4.16 RCS Specific Activity.......................................................................
3.4-40 3.4.17 Steam Generator (SG) Tube Integrity..............................................
3.4-44 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)........................... 3.5-1 3.5.1 A ccum ulators...................................................................................
3.5-1 3.5.2 ECCS - Operating 3.5-3 3.5.3 ECCS - Shutdown............................................................................
3.5-6 3.5.4 Refueling Water Storage Tank (RWST) 3.5-8 3.5.5 Seal Injection Flow...........................................................................
3.5-10 3.6 CONTAINMENT SYSTEMS.........................................
........................ 3.6-1 3.6.1 C ontainm ent 3.6-1 3.6.2 Containment Air Locks.....................................................................
3.6-3 CALLAWAY PLANT 2
Amendment 174
TABLE OF CONTENTS 3.6 CONTAINMENT SYSTEMS (continued) 3.6.3 Containment Isolation Valves 3.6-7 3.6.4 Containment Pressure.....................................................................
3.6-16 3.6.5 Containment Air Temperature.........................................................
3.6-17 3.6.6 Containment Spray and Cooling Systems 3.6-18 3.6.7 Recirculation Fluid pH Control.(RFPC) System...............................
3.6-21 3.6.8 Hydrogen Recombiners.................................................................. 3.6-22 3.7 PLANT SYSTEMS................................................................................
3.7-1 3.7.1 Main Steam Safety Valves (MSSVs)...............................................
3.7-1 3.7.2 Main Steam Isolation Valves (MSIVs) 3.7-5 3.7.3 MFIVs and MFRVs and MFRV Bypass Valves........
3.7-8 3.7.4 Atmospheric Steam Dump Valves (ASDs)......................................
3.7-11 3.7.5 Auxiliary Feedwater (AFW) System.................................................
3.7-14 3.7.6 Condensate Storage Tank (CST)....................................................
3.7-18 3.7.7 Component Cooling Water (CCW) System.....................................
3.7-20 3.7.8 Essential Service Water System (ESW)..........................................
3.7-22 3.7.9 Ultimate Heat Sink (UHS)..................................................................
3.7-24 3.7.10 Control Room Emergency Ventilation System (CREVS)................... 3.7-26 3.7.11 Control Room Air Conditioning System (CRACS)............................. 3.7-29 3.7.12 Not Used..
...................... 3.7-32 3.7.13 Emergency Exhaust System (EES)...................................................
3.7-33 3.7.14 N ot U sed............................................................................................
3.7-36 3.7.15 Fuel Storage Pool Water Level..........................................................
3.7-37 3.7.16 Fuel Storage Pool Boron Concentration............................................
3.7-38 3.7.17 Spent Fuel Assembly Storage...........................................................
3.7-40 3.7.18 Secondary Specific Activity................................................................
3.7-42 3.8 ELECTRICAL POWER SYSTEMS..........................................................
3.8-1 3.8.1 AC Sources - Operating.....................................................................
3.8-1 3.8.2 AC Sources - Shutdown....................................................................
3.8-16 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air.........................................
3.8-19 3.8.4 DC Sources - Operating....................................................................
3.8-22 3.8.5 DC Sources - Shutdown....................................................................
3.8-25 3.8.6 Battery Cell Parameters.....................................................................
3.8-27 3.8.7 Inverters - Operating..........................................................................
3.8-31 3.8.8 Inverters - Shutdown..........................................................................
3.8-33 3.8.9 Distribution Systems - Operating.......................................................
3.8-35 3.8.10 Distribution Systems - Shutdown.......................................................
3.8-37 CALLAWAY PLANT 3
Amendment 174
RCS Boron Limitations < 500'F 3.1.9 3.1 REACTIVITY CONTROL SYSTEMS 3.1.9 RCS Boron Limitations < 500° F LCO 3.1.9 APPLICABILITY:
The boron concentration of the Reactor Coolant System (RCS) shall be greater than the all rods out (ARO) critical boron concentration.
MODE 2 with keff < 1.0 with any RCS cold leg temperature < 5000 F and with Rod Control System capable of rod withdrawal, MODE 3 with any RCS cold leg temperature < 5000 F and with Rod Control System capable of rod withdrawal, MODES 4 and 5 with Rod Control System capable of rod withdrawal.
I.
ACTIONS COMPLETION CONDITION REQUIRED ACTION TIME TIME A.
RCS boron concentration A.1 Initiate boration to Immediately not within limit, restore RCS boron concentration to within limit.
OR A.2 Initiate action to place Immediately the Rod Control System in a condition incapable of rod withdrawal.
OR A.3 NOTE -----------
Not applicable in MODES 4 and 5.
Initiate action to increase Immediately all RCS cold leg temperatures to >_ 500 OF.
CALLAWAY PLANT 3.1-21 Amendment No. 174
RCS Boron Limitations < 500'F 3.1.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.9.1 Verify RCS boron concentration is greater than the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ARO critical boron concentration.
II I
CALLAWAY PLANT 3.1-22 Amendment No. 174
RTS Instrumentation 3.3.1 ACTIONS (continued)
ACTIONCOMPLETION CONDITION REQUIRED ACTION TIME Q
One train inoperable.
NOTE One train may be bypassed for up to
.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing provided the other train is OPERABLE.
Q.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status..
OR Q.2 Be in MODE 3.
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> R
One RTB train inoperable.
NOTE One train may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing provided the other train is OPERABLE.
R.1 Restore train to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.
OR R.2 Be in MODE 3.
30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> S.
One or more required S.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> channel(s) inoperable, required state for existing unit conditions.
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> (continued)
CALLAWAY PLANT 3.3-8 Amendment No. 174
RTS Instrumentation 3.3.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME T.
One or more required T.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> channel(s) inoperable, required state for existing unit conditions.
OR T.2 Be in MODE 2.
7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> U. One trip mechanism A.1 Restore inoperable trip 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable for one RTB.
mechanism to OPERABLE status.
OR U.2 Be in MODE 3.
54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> (continued)
CALLAWAY PLANT 3.3-9 Amendment No. 174
RTS Instrumentation 3.3.1 ACTIONS (continued)
I T COMPLETION CONDITION REQUIRED ACTION TIME V.
One channel inoperable.
NOTE The inoperable channelmay be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
V.1 OR Place channel in trip.
V.2.1 AND V.2.2.1 Be in MODE 2 with keff < 1.0.
Initiate action to fully insert all rods.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> 78 hours 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> AND V.2.2.2 Initiate action to place the Rod Control System in a condition incapable of rod withdrawal.
OR V.2.3 Initiate action to borate the RCS to greater than the all rods out (ARO) critical boron concentration.
+
+
W Not used.
(continued)
CALLAWAY PLANT 3.3-10 Amendment No. 174
RTS Instrumentation 3.3.1 ACTIONS (continued)
COMPLETION CONDITION REQUIRED ACTION TIME X
One or more Containment X.1 Place channel(s) in trip.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Pressure - Environmental Allowance Modifier OR channel(s) inoperable.
X.2 Be in MODE 3.
78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> Y.
One channel inoperable NOTE The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels.
Y1 Place channel in trip.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Z
Required Action and Z.1.1 Initiate action to fully Immediately associated Completion insert all rods.
Time of Condition Y not met.
AND OR Z.1.2 Initiate action to place Immediately the Rod Control System Two or more channels in a condition incapable inoperable, of rod withdrawal.
OR Z.2 Initiate action to borate Immediately the RCS to greater than the all rods out (ARO) critical boron concentration.
I CALLAWAY PLANT 3.3-11 Amendment No. 174
RTS Instrumentation 3.3.1 TABLE 3.3.1-1 (PAGE 1 OF 8)
Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE(a)
- 1.
Manual Reactor 1,2 2
B SR 3.3.1.14 NA Trip 3 (b) 4 (b), 5 (b) 2 C
SR 3.3.1.14 NA
- 2.
Power Range Neutron Flux
- a. High 1,2 4
- 5 112.3% RTP SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.16
- b. Low 1(c),2(0 4
- 5 28.3% RTP SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16 2 (h),3(i) 4 Y, Z SR 3.3.1.1
- 5 28.3% RTP SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.16
- 3.
Power Range 1,2 4
- 4.
Intermediate 1(c), 2 (d) 2 F, G SR 3.3.1.1
_< 35.3% RTP Range Neutron SR 3.3.1.8 Flux SR 3.3.1.11 (a)
The Allowable Value defines the limiting safety system setting except for Trip Functions 14.a and 14.b (the Nominal Trip Setpoint defines the limiting safety system setting for these Trip Functions). See the Bases for the Nominal Trip Setpoints.
(b)
With Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(c)
Below the P-10 (Power Range Neutron Flux) interlock.
(d)
Above the P-6 (Intermediate Range Neutron Flux) interlock.
(f)
With keff _ 1.0.
(h)
With keff < 1.0, and all RCS cold leg temperatures > 500°F, and RCS boron concentration _ the ARO critical boron concentration, and Rod Control System capable of rod withdrawal or one or more rods not fully inserted.
(i)
With all RCS cold leg temperatures _> 500°F, and RCS boron concentration < the ARO critical boron concentration, and Rod Control System capable of rod withdrawal or one or more rods not fully inserted I
CALLAWAY PLANT 3.3-17 Amendment No. 174