ML021550425
| ML021550425 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/31/2002 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MB2700, TAC MB2701 | |
| Download: ML021550425 (32) | |
Text
Definitions 1.1 1.1 Definitions (continued)
OPERABLE-OPERABILITY RATED THERMAL POWER (RTP)
REACTOR PROTECTION SYSTEM (RPS)
RESPONSE
TIME SHUTDOWN MARGIN (SDM)
A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2923 MWt.
The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:
- a.
The reactor is xenon free;
- b.
The moderator temperature is 68°F; and
- c.
All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
(continued)
Amendment No. 222 1 I
Brunswick Unit I 1.1-5
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be
- 23% RTP.
2.1.1.2 With the reactor steam dome pressure > 785 psig and core flow Ž 10% rated core flow:
MCPR shall be ! 1.12 for two recirculation loop operation or. 1.14 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be : 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
Amendment No. 222 1 Brunswick Unit I I
2.0-1
Control Rod OPERABILITY 3.1.3 RrTTAkI.I hi., I jIV ~
I CONDITION C.
(continued)
REQUIRED ACTION 1
4 C.2 Disarm CRD.
the associated I
i D.
NOTE-Not applicable when THERMAL POWER
> 8.75% RTP.
Two or more inoperable control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods.
Restore compliance with BPWS.
D.I OR D.2 Restore control rod to OPERABLE status.
i
- t -
E. Required Action and associated Completion Time of Condition A, C, or D not met.
OR Nine or more control rods inoperable.
E.1 Be in MODE 3.
COMPLETION TIME 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 12 hours I-I __________
Amendment No.
222 1 Brunswick Unit 1 I
3.1-9
Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO
3.1.6 APPLICABILITY
OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).
MODES I and 2 with THERMAL POWER
- 8.75% RTP.
ACTIONS CONDITION REQUIRED ACTION I
t A.
One or more OPERABLE control rods not in compliance with BPWS.
A.I NOTE------
Control rod may be bypassed in the rod worth minimizer (RWM) or RWM may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation."
Move associated control rod(s) to correct position.
Declare associated control rod(s) inoperable.
OR A.2 COMPLETION TIME 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8 hours (continued)
Amendment No.
222 1 Brunswick Unit 1 3.1-18
3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)
LCO
3.2.1 APPLICABILITY
All APLHGRs shall be less than or equal to the limits specified in the COLR.
THERMAL POWER Ž 23% RTP.
Any APLHGR not within limits.
4-B.
Required Action and associated Completion Time not met.
REQUIRED ACTION 4-I A.1 B.1 Restore APLHGR(s) to within limits.
Reduce THERMAL POWER to < 23% RTP.
L ______________________________________________________
COMPLETION TIME 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.1.1 Verify all APLHGRs are less than or equal to the limits specified in the COLR.
FREQUENCY Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after
Ž 23% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Amendment No. 222 I Brunswick Unit I APLHGR 3.2.1 arTlnNq I
FREQUENCY I
3.2-1
MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)
LCO
3.2.2 APPLICABILITY
All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.
THERMAL POWER Ž 23% RTP.
ACT TAMC CONDITION REQUIRED ACTION COMPLETION TIME A.
Any MCPR not within A.1 Restore MCPR(s) to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- limits, within limits.
B.
Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 23% RTP.
Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.2.1 Verify all MCPRs are greater than or equal to the limits specified in the COLR.
Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after S23% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter (continued)
Amendment No. 222 I Brunswick Unit 1 I
FREQUENCY 3.2-2
RPS Instrumentation 3.3.1.1 ACTIONS (continued)
ACTION (coninued CONDITION
+/-
B. ---------
NOTE------
Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.
One or more Functions with one or more required channels inoperable in both trip systems.
REQUIRED ACTION Place channel in one trip system in trip.
B.1 OR B.2 Place one in trip.
trip system 4
1 C.
One or more Functions with RPS trip capability not maintained.
C.1 Restore RPS trip capability.
COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 6 hours 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
+
I D.
Required Action and associated Completion Time of Condition A, B, or C not met.
D.1 Enter the Condition referenced in Table 3.3.1.1-1 for the channel.
I T
E.
As required by Required Action D.1 and referenced in Table 3.3.1.1-1.
E.I Reduce THERMAL POWER to < 26% RTP.
Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (continued)
Amendment No. 222 1 Brunswick Unit I I
3.3-2
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS
NOTES -----------------------------------
- 1.
Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.
- 2.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains RPS trip capability.
SURVEILLANCE FREQUENCY SR 3.3.1.1.1 (Not used.)
SR 3.3.1.1.2 Perform CHANNEL CHECK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.3.1.1.3 NOTE ------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER Ž 23% RTP.
Adjust the average power range monitor 7 days (APRM) channels to conform to the calculated power while operating at Ž 23%
RTP.
SR 3.3.1.1.4 NOTE Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
7 days (continued)
Amendment No. 222 I Brunswick Unit I 3.3-4
RPS Instrumentation 3.3.1.1 CIIDIETI I Alder DrnhtTPFMFNT
(continuedl 3UIXL+/-LLrI'.-L-
"s-.'(.**'*-***-**
r SURVEILLANCE SR 3.3.1.1.16 SR 3.3.1.1.17 SR 3.3.1.1.18 Verify Turbine Stop Valve-Closure and Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is
Ž 26% RTP.
-- -- - -- - -- - N O T ES -----------------
- 1.
Neutron detectors are excluded.
- 2.
For Functions 3 and 4, the sensor response time may be assumed to be the design sensor response time.
- 3.
For Function 5, "n" equals 4 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
- 4.
For Function 2.e, "n" equals 8 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
Testing of APRM and Oscillation Power Range Monitor (OPRM) outputs shall alternate.
Verify the RPS RESPONSE TIME is within limits.
Adjust recirculation drive flow to conform to reactor core flow.
FREQUENCY 24 months 24 months on a STAGGERED TEST BASIS
1
Once within 7 days after reaching equilibrium conditions following refueling outage (continued)
Amendment No. 222 I Brunswick Unit 1 C"DUCTIlAmri: Drnt1TQFMFNTS (continuedl I
I 3.3-7
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 1.
- a.
Neutron Flux -High 2
5 (a)
- b.
Inop 2
3 3
3 G
SR SR SR SR SR SR SR H
SR SR SR SR SR G
SR SR SR 3.3.1.1.2 3.3.1.1.4 3.3.1.1.5 3.3.1.1.6 3.3.1.1.7 3.3.1-1.13 3.3.1.1.15 3.3.1.1.2 3.3.1.1.4 3.3.1.1.5 3.3.1.1.13 3.3.1.1.15 3.3.1.1.4 3.3.1.1.5 3.3.1.1.15 s 120/125 divisions of full scale s 120/125 divisions of full scale NA 5 (a)
- 2.
Average Power Range Monitors
- a.
Neutron Flux -High (Setdown) 2 1
- b.
Simulated Thermal Power -- High 3
3 (c) 3 (c)
H SR 3.3.1.1.4 SR 3.3.1.1.5 SR 3.3.1.1.15 G
SR SR SR SR SR SR F
SR SR SR SR SR SR SR 3.3.1.1.2 3.3.1.1.5 3.3.1.1.7 3.3.1.1.8 3.3.1.1.11 3.3.1.1.13 3.3.1.1.2 3.3.1.1.3 3.3.1.1.5 3.3.1.1.8 3.3.1.1.11 3.3.1.1.13 3.3.1.1.18 (continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b)
- 5 [0.55 (W -
AW) + 62.6% RTP] when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
The value of AW is defined in plant procedures.
(c)
Each APRM channel provides inputs to both trip systems.
Amendment No. 222 1 Brunswick Unit I NA 5 22.7% RTP
_5 0.55W +
62.6% RTPIb) and
_< 117.1% RTP I
I 3.3-9
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 7.
Scram Discharge Votume 1,2 2
G SR 3.3.1.1.5 5 108 galLons Water Level -High SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 5 (a) 2 H
_ 108 gallons SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15
- 8.
Turbine Stop
> 26% RTP 4
_s 10% closed Valve -- Closure SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17
- 9.
Turbine Control Valve 2! 26% RTP 2
_ 500 psig Fast Closure, Control SR 3.3.1.1.9 Oil Pressure--Low SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17
- 10.
Reactor Mode Switch--
1,2 1
G SR 3.3.1.1.12 NA Shutdown Position SR 3.3.1.1.15 5 (a) 1 H
SR 3.3.1.1.12 NA SR 3.3.1.1.15
- 11.
Manual Scram 1,2 1
G SR 3.3.1.1.9 NA SR 3.3.1.1.15 5 (a) 1 H
SR 3.3.1.1.9 NA SR 3.3.1.1.15 (a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
Amendment No. 222 1 Brunswick Unit 1 I
3.3-11
Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.3.2.1.2
NOTE ------------------
Not required to be performed until I hour after any control rod is withdrawn at S8.75% RTP in MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
NOTE........
Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is
- 8.75% RTP in MODE 1.
Perform CHANNEL FUNCTIONAL TEST.
SR 3.3.2.1.4 Verify the RBM:
- a.
Low Power Range-Upscale Function OR Intermediate Power Range-Upscale Function OR High Power Range-Upscale Function is enabled (not bypassed) when APRM Simulated Thermal Power is
Ž 29%.
- b.
Intermediate Power Range-Upscale Function OR High Power Range-Upscale Function is enabled (not bypassed) when APRM Simulated Thermal Power is
Ž Intermediate Power Range Setpoint specified in the COLR.
- c.
High Power Range-Upscale Function is enabled (not bypassed) when APRM Simulated Thermal Power is Ž High Power Range Setpoint specified in the COLR.
(continued)
Amendment No.
222 I Brunswick Unit I FREQUENCY 92 days 92 days 24 months I
I I
3.3-21
Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.2.1.5 Verify the RWM is not bypassed when 24 months THERMAL POWER is o 8.75% RTP.
NOTE ---------------.--
Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after reactor mode switch is in the shutdown position.
Perform CHANNEL FUNCTIONAL TEST.
24 months SR 3.3.2.1.7
NOTE ------------------
Neutron detectors are excluded.
Perform CHANNEL CALIBRATION.
24 months SR 3.3.2.1.8 Verify control rod sequences input to the Prior to RWM are in conformance with BPWS.
declaring RWM OPERABLE following loading of sequence into RWM Amendment No.
222 1 Brunswick Unit I I
3.3-22
Control Rod Block Instrumentation 3.3.2.1 TabLe 3.3.2.1-1 (page 1 of 1)
Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE
- 1. Rod Block Monitor
- a.
Low Power Range -Upscale (a) 2 SR 3.3.2.1.1 (h)
SR 3.3.2.1.4 SR 3.3.2.1.7
- b.
Intermediate Power (b) 2 SR 3.3.2.1.1 (h)
Range --Upscale SR 3.3.2.1.4 SR 3.3.2.1.7 C.
High Power Range -UpscaLe (c),(d) 2 SR 3.3.2.1.1 (h)
SR 3.3.2.1.4 SR 3.3.2.1.7
- d.
Inop (d),(e) 2 SR 3.3.2.1.1 NA
- 2.
Rod Worth Minimizer 1(f),
2 (f) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8
- 3.
Reactor Mode Switch -Shutdown (g)
SR 3.3.2.1.6 NA Position (a)
THERMAL POWER is ? 29% RTP and MCPR Less than the limit specified in the COLR except not required to be OPERABLE if the Intermediate Power Range -UpscaLe Function or High Power Range -Upscale Function is OPERABLE.
(b)
THERMAL POWER is > Intermediate Power Range Setpoint specified in the COLR and MCPR less than the Limit specified in the COLR except not required to be OPERABLE if the High Power Range -UpscaLe Function is OPERABLE.
(c)
THERMAL POWER ?: High Power Range Setpoint specified in the COLR and < 90% RTP and MCPR Less than the Limit specified in the COLR.
(d)
THERMAL POWER _ 90% RTP and MCPR Less than the Limit specified in the COLR.
(e)
THERMAL POWER ? 29% and < 90% RTP and MCPR Less than the Limit specified in the COLR.
(f)
With THERMAL POWER _< 8.75% RTP.
(g)
Reactor mode switch in the shutdown position.
(h)
Allowable Value specified in the COLR.
Amendment No. 222 1 Brunswick Unit I 3.3-23
Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 APPLICABILITY:
Three channels of feedwater and main turbine high water level trip instrumentation shall be OPERABLE.
THERMAL POWER Ž 23% RTP.
- - - - - - - - - - - - - - - - - - - N O T E..............................
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION I
I A.
One feedwater and main turbine high water level trip channel inoperable.
B.
Two or more feedwater and main turbine high water level trip channels inoperable.
C.
Required Action and associated Completion Time not met.
A.1 B.1 C.1 Place channel in trip.
Restore feedwater and main turbine high water level trip capability.
iT Reduce THERMAL POWER to < 23% RTP.
COMPLETION TIME 7 days 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours Amendment No. 222 1 Brunswick Unit 1 ACTIONS I
I 3.3-24
Main Turbine Bypass System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 The Main Turbine Bypass System LCO
3.7.6 APPLICABILITY
The Main Turbine Bypass System shall be OPERABLE.
OR The following limits are made applicable:
- a.
LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR),"
limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and
- b.
LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR.
THERMAL POWER - 23% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Requirements of the LCO not met.
A.1 Satisfy the requirements of the LCO.
B.
Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 23% RTP.
Time not met.
Amendment No. 222 I Brunswick Unit I 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> I
3.7-20
Definitions 1.1 1.1 Definitions (continued)
OPERABLE-OPERABILITY RATED THERMAL POWER (RTP)
REACTOR PROTECTION SYSTEM (RPS)
RESPONSE
TIME SHUTDOWN MARGIN (SDM)
A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2923 MWt.
The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:
- a.
The reactor is xenon free;
- b.
The moderator temperature is 68°F; and
- c.
All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
(continued)
Amendment No.
247 I 1.1-5 Brunswick Unit 2
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow < 10% rated core flow:
THERMAL POWER shall be 5 23% RTP.
2.1.1.2 With the reactor steam dome pressure Ž 785 psig and core flow Ž 10% rated core flow:
MCPR shall be Ž 1.09 for two recirculation loop operation or Ž 1.10 for single recirculation loop operation.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be
- 1325 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
Amendment No.
247 I Brunswick Unit 2 I
2.0-1
Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION C.
(continued)
D. ---------- NOTE------
Not applicable when THERMAL POWER
> 8.75% RTP.
Two or more inoperable control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods.
REQUIRED ACTION jCOMPLETION TIME C.2 D.I OR D.2 Disarm the associated CRD.
Restore compliance with BPWS.
Restore control rod to OPERABLE status.
i i
E. Required Action and associated Completion Time of Condition A, C, or D not met.
OR Nine or more control rods inoperable..I E.1 Be in MODE 3.
Amendment No.
247 I Brunswick Unit 2 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 12 hours 3.1-9
Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO
3.1.6 APPLICABILITY
OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).
MODES I and 2 with THERMAL POWER
- 8.75% RTP.
iWTTANS CONDITION A.
One or more OPERABLE control rods not in compliance with BPWS.
REQUIRED ACTION
-I A.1 N O T E ------
Control rod may be bypassed in the rod worth minimizer (RWM) or RWM may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation.
Move associated control rooas) to correct position.
Declare associated control rod(s) inoperable.
OR A.2 COMLETON IM 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8 hours (continued)
Amendment No.
247 I Brunswick Unit 2 I
COMPLETION TIME 3.1-18
3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)
LCO
3.2.1 APPLICABILITY
All APLHGRs shall be less than or equal to the limits specified in the COLR.
THERMAL POWER Ž 23% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- limits, within limits.
B.
Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 23% RTP.
Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal Once within to the limits specified in the COLR.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after 23% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter Amendment No.
247 I Brunswick Unit 2 APLHGR 3.2.1 I
I 3.2-1
MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)
LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.
APPLICABILITY:
THERMAL POWER Ž 23% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Any MCPR not within A.1 Restore MCPR(s) to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
- limits, within limits.
B.
Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 23% RTP.
Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal Once within to the limits specified in the COLR.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after
Ž23% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter (continued)
Amendment No. 247 I Brunswick Unit 2 3.2-2
RPS Instrumentation 3.3.1.1 ACTIONS (continued)
CONDITION B. -------- NOTE----
Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.
One or more Functions with one or more required channels inoperable in both trip systems.
C.
One or more Functions with RPS trip capability not maintained.
D. Required Action and associated Completion Time of Condition A, B, or C not met.
E.
As required by Required Action D.1 and referenced in Table 3.3.1.1-1.
REQUIRED ACTION B.1 Place channel in one trip system in trip.
OR B.2 Place one trip system in trip.
C.1 Restore RPS trip capability.
D.1 Enter the Condition referenced in Table 3.3.1.1-1 for the channel.
E.I Reduce THERMAL POWER to < 26% RTP.
COMPLETION TIME 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 6 hours I hour Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (continued)
Amendment No.
247 I Brunswick Unit 2 I
3.3-2
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS NOTES.............................
- 1.
Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.
- 2.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains RPS trip capability.
SURVEILLANCE FREQUENCY SR 3.3.1.1.1 SR 3.3.1.1.2 SR 3.3.1.1.3 SR 3.3.1.1.4 (Not used.)
Perform CHANNEL CHECK.
NOTE ------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER
Ž 23% RTP.
Adjust the average power range monitor (APRM) channels to conform to the calculated power while operating at, 23%
RTP.
NOTE ------------------
Not required to be performed when entering MODE 2 from MODE 1 until 19 hnors after enterina MODE 2.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 7 days Perform CHANNEL FUNCTIONAL TEST.
7 days (continued)
Amendment No.
247 1 3.3-4 Brunswick Unit 2
RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.1.1.16 Verify Turbine Stop Valve-Closure and 24 months Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is Ž 26% RTP.
SR 3.3.1.1.17 ------------------ NOTES --------------
I.
Neutron detectors are excluded.
- 2.
For Functions 3 and 4, the sensor response time may be assumed to be the design sensor response time.
- 3.
For Function 5, "n" equals 4 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
- 4.
For Function 2.e, "n" equals 8 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
Testing of APRM and Oscillation Power Range Monitor (OPRM) outputs shall alternate.
24 months on a Verify the RPS RESPONSE TIME is within STAGGERED TEST limits.
BASIS SR 3.3.1.1.18 Adjust recirculation drive flow to Once within conform to reactor core flow.
7 days after reaching equilibrium conditions following refueling outage (continued)
Amendment No.
247 1 I
3.3-7 Brunswick Unit 2
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE MODES OR R
OTHER SPECIFIED F
FUNCTION CONDITIONS REQUIRED HANNELS PER TRIP SYSTEM CONDITIONS CONDITIONS REFERENCED FROM REQUIRED ACTION D.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
- a.
Neutron Flux -High 2
5 (a)
- b.
I nop 2
5(a)
- 2.
Average Power Range Monitors
- a.
Neutron Flux--High (Setdown)
- b.
Simulated Thermal Power -High 2
1 3
3 3
3 3 (c) 3 (c)
G SR SR SR SR SR SR SR H
SR SR SR SR SR G
SR SR SR 3.3.1.1.2 3.3.1.1.4 3.3.1.1.5 3.3.1.1.6 3.3.1.1.7 3.3.1.1.13 3.3.1.1.15 3.3.1.1.2 3.3.1.1.4 3.3.1.1.5 3.3.1.1.13 3.3.1.1.15 3.3.1.1.4 3.3.1.1.5 3.3.1.1.15 S120/125 divisions of full scale 5 120/125 divisions of full scale NA H
SR 3.3.1.1.4 NA SR 3.3.1.1.5 SR 3.3.1.1.15 G
SR SR SR SR SR SR F
SR SR SR SR SR SR SR 3.3.1.1.2 3.3.1.1.5 3.3.1.1.7 3.3.1.1.8 3.3.1.1.11 3.3.1.1.13 3.3.1.1.2 3.3.1.1.3 3.3.1.1.5 3.3.1.1.8 3.3.1.1.11 3.3.1.1.13 3.3.1.1.18
_< 22.7% RTP
_5 0.55W +
62.6% RTP(b) and
_5 117.1% RTP (continued)
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
(b)
< EO.55(W -
AW) + 62.6% RTP] when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."
The value of AW is defined in plant procedures.
(c)
Each APRM channel provides inputs to both trip systems.
Amendment No. 247 I Brunswick Unit 2 I
3.3-9
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)
Reactor Protection System Instrumentation REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS CONDITIONS REFERENCED FROM REQUIRED SURVEILLANCE ALLOWABLE ACTION D.1 REQUIREMENTS VALUE
- 7.
Scram Discharge Volume Water Level -High
- 8.
Turbine Stop Valve -- Closure
- 9.
Turbine Control Valve Fast Closure, Control Oil Pressure -Low
- 10.
Reactor Mode Switch Shutdown Position
- 11.
Manual Scram 1,2 5 (a)
?_
26% RTP
_ 26% RTP 1,2 5 (a) 1,2 5 (a) 2 2
4 G
SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 H
SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 E
SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17 E
SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17 G
SR 3.3.1.1.12 SR 3.3.1.1.15 H
SR 3.3.1.1.12 SR 3.3.1.1.15 G
SR 3.3.1.1.9 SR 3.3.1.1.15 H
SR 3.3.1.1.9 SR 3.3.1.1.15 2
1 1
(a)
With any control rod withdrawn from a core cell containing one or more fuel assemblies.
Amendment No. 247 1 Brunswick Unit 2 FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS S108 gatlons
- 108 gallons
- 10% closed S500 psig NA NA NA NA I
3.3-11
Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.3.2.1.2
NOTE............
Not required to be performed until I hour after any control rod is withdrawn at
!58.75% RTP in MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
NOTE............
Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is 5 8.75% RTP in MODE 1.
Perform CHANNEL FUNCTIONAL TEST.
SR 3.3.2.1.4 Verify the RBM:
- a.
Low Power Range-Upscale Function OR Intermediate Power Range-Upscale Function OR High Power Range--Upscale Function is enabled (not bypassed) when APRM Sio1ulated Thermal Power is
Ž 29%.
- b.
Intermediate Power Range-Upscale Function OR High Power Range-Upscale Function is enabled (not bypassed) when APRM Simulated Thermal Power is
Ž Intermediate Power Range Setpoint specified in the COLR.
- c.
High Power Range-Upscale Function is enabled (not bypassed) when APRM Simulated Thermal Power is Ž High Power Range Setpoint specified in the COLR.
FREQUENCY 92 days 92 days 24 months (conti nued)
Amendment No. 247 I Brunswick Unit 2 I
3.3-21
Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.2.1.5 Verify the RWM is not bypassed when 24 months THERMAL POWER is
- 8.75% RTP.
NOTE ------------------
Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after reactor mode switch is in the shutdown position.
Perform CHANNEL FUNCTIONAL TEST.
24 months SR 3.3.2.1.7
NOTE ------------------
Neutron detectors are excluded.
Perform CHANNEL CALIBRATION.
24 months SR 3.3.2..1.8 Verify control rod sequences input to the Prior to RWM are in conformance with BPWS.
declaring RWM OPERABLE following loading of sequence into RWM Amendment No.
247 1 Brunswick Unit 2 3.3-22
Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page I of 1)
Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECI FIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE
- 1. Rod Block Monitor
- a.
Low Power Range -- Upscale (a) 2 SR 3.3.2.1.1 (h)
SR 3.3.2.1.4 SR 3.3.2.1.7
- b.
Intermediate Power (b) 2 SR 3.3.2.1.1 (h)
Range -Upscale SR 3.3.2.1.4 SR 3.3.2.1.7
- c.
High Power Range -Upscale (c),(d) 2 SR 3.3.2.1.1 (h)
SR 3.3.2.1.4 SR 3.3.2.1.7
- d.
Inop (d),(e) 2 SR 3.3.2.1.1 NA
- 2.
Rod Worth Minimizer 1 (f),
2 (f) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8
- 3.
Reactor Mode Switch -Shutdown (g) 2 SR 3.3.2.1.6 NA Position (a)
THERMAL POWER is
> 29% RTP and MCPR less than the limit specified in the COLR except not required to be OPERABLE if the Intermediate Power Range -Upscale Function or High Power Range -Upscale Function is OPERABLE.
(b)
THERMAL POWER is
?: Intermediate Power Range Setpoint specified in the COLR and MCPR Less than the limit specified in the COLR except not required to be OPERABLE if the High Power Range -Upscale Function is OPERABLE.
(c)
THERMAL POWER ?_ High Power Range Setpoint specified in the COLR and < 90% RTP and MCPR Less than the limit specified in the COLR.
(d)
THERMAL POWER
> 90% RTP and MCPR less than the limit specified in the COLR.
(e)
THERMAL POWER
_ 29% and < 90% RTP and MCPR less than the limit specified in the COLR.
(f)
With THERMAL POWER < 8.75% RTP.
(g)
Reactor mode switch in the shutdown position.
(h)
Allowable Value specified in the COLR.
Amendment No. 247 I Brunswick Unit 2 I
3.3-23
Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 APPLICABILITY:
Three channels of feedwater and main turbine high water level trip instrumentation shall be OPERABLE.
THERMAL POWER Ž 23% RTP.
ACTIONS NOTE ------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One feedwater and main turbine high water level trip channel inoperable.
B.
Two or more feedwater and main turbine high water level trip channels inoperable.
A.I B.1 Place channel in trip.
Restore feedwater and main turbine high water level trip capability.
7 days 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C.
Required Action and C.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 23% RTP.
Time not met.
Amendment No.
247 I Brunswick Unit 2 I
I I
3.3-24
Main Turbine Bypass 3.7 PLANT SYSTEMS 3.7.6 The Main Turbine Bypass System The Main Turbine Bypass System shall be OPERABLE.
OR The following limits are made applicable:
- a.
System, as "AVERAGE PLANAR LINEAR HEAT GENERATION RATE limits for an inoperable Main Turbine Bypass specified in the COLR; and
- b.
LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR.
APPLICABILITY:
THERMAL POWER Ž 23% RTP.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> LCO not met.
requirements of the LCO.
B.
Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> associated Completion to < 23% RTP.
Time not met.
Amendment No.
247 1 System 3.7.6 LCO 3.7.6 I
I 3.7-20 Brunswick Unit 2