Text

Technical Specification Pages for Amendments 222 and 247 Extended Power Uprate
	ML021550425
Person / Time
Site:	Brunswick
Issue date:	05/31/2002
From:	; NRC/NRR/DLPM
To:	;
References
	TAC MB2700, TAC MB2701
	Download: ML021550425 (32)
	v • d • e

Definitions 1.1 1.1 Definitions (continued)

OPERABLE-OPERABILITY 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).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 2923 MWt. I REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME 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.

SHUTDOWN MARGIN (SDM) 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rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.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)

Brunswick Unit I 1.1-5 Amendment No. 222 1

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. I 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

Brunswick Unit I 2.0-1 Amendment No. 222 1

Control Rod OPERABILITY 3.1.3 RrTTAkI.I hi., I jIV ~ - I CONDITION REQUIRED ACTION COMPLETION TIME 1 4 C. (continued) C.2 Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD.

I i D.I Restore compliance 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D. ---- NOTE- with BPWS.

Not applicable when THERMAL POWER

> 8.75% RTP. OR I D.2 Restore control rod 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Two or more inoperable to OPERABLE status.

control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods.

i - t- -

Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Required Action and E.1 associated Completion Time of Condition A, C, or D not met.

OR Nine or more control rods inoperable.

________________ I-

__________________ I __________

3.1-9 Amendment No. 222 1 Brunswick Unit 1

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).

APPLICABILITY: MODES I and 2 with THERMAL POWER

8.75% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

___________ I t A. One or more OPERABLE A.I - -------- NOTE------

Control rod may be control rods not in bypassed in the rod compliance with BPWS. worth minimizer (RWM) or RWM may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation."

Move associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod(s) to correct position.

OR Declare associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months A.2 control rod(s) inoperable.

(continued) 3.1-18 Amendment No. 222 1 Brunswick Unit 1

APLHGR 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER Ž 23% RTP.

AC T ONS arTlnNq CONDITION REQUIRED ACTION COMPLETION TIME 4- I 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months A. Any APLHGR not within A.1 Restore APLHGR(s) to limits. within limits.

4-B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to < 23% RTP. I associated Completion Time not met.

L ______________________________________________________

SURVEILLANCE REQUIREMENTS FREQUENCY SURVEILLANCE FREQUENCY Verify all APLHGRs are less than or equal Once within SR 3.2.1.1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after to the limits specified in the COLR. Ž 23% RTP I

AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Amendment No. 222 I Brunswick Unit 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.

ACT TAMC CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits, within limits.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 23% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY I

Verify all MCPRs are greater than or equal Oncehours withinafter SR 3.2.2.1 12 to the limits specified in the COLR. S23% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued) 3.2-2 Amendment No. 222 I Brunswick Unit 1

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

(coninued ACTION CONDITION REQUIRED ACTION COMPLETION TIME

+/-

B.--------- NOTE------ B.1 Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months trip system in trip.

Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f. OR 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B.2 Place one trip system in trip.

One or more Functions with one or more required channels inoperable in both trip systems.

4 1 C. One or more Functions C.1 Restore RPS trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with RPS trip capability.

capability not maintained.

+ I -

D.1 Enter the Condition Immediately D. Required Action and referenced in associated Completion Time of Condition A, Table 3.3.1.1-1 for B, or C not met.

the channel.

I T E.I Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months E. As required by to < 26% RTP.

Required Action D.1 I and referenced in Table 3.3.1.1-1.

(continued) 3.3-2 Amendment No. 222 1 Brunswick Unit I

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.

of

2. When a channel is placed in an inoperable status solely for performance required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.1.3 ------------------ NOTE ------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 days (continued) 3.3-4 Amendment No. 222 I Brunswick Unit I

RPS Instrumentation 3.3.1.1 CIIDIETI I Alder DrnhtTPFMFNT -

(continuedl r

3UIXL+/-LLrI'.-L-C"DUCTIlAmri:

"s-.'(.**'*-***-**

Drnt1TQFMFNTS (continuedl I SURVEILLANCE FREQUENCY Verify Turbine Stop Valve-Closure and 24 months SR 3.3.1.1.16 Turbine Control Valve Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is Ž 26% RTP. I SR 3.3.1.1.17 -- -- - -- - -- - NOT 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.

24 months on a STAGGERED TEST Verify the RPS RESPONSE TIME is within BASIS limits.

1 Adjust recirculation drive flow to Once within SR 3.3.1.1.18 7 days after conform to reactor core flow. reaching equilibrium conditions following refueling outage (continued) 3.3-7 Amendment No. 222 I Brunswick Unit 1

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 PER TRIP REQUIRED SURVEILLANCE ALLOWABLE SPECIFIED VALUE CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS FUNCTION

1. intermediate Range Monitors 3 G SR 3.3.1.1.2 s 120/125 of divisions

a. Neutron Flux -High 2 SR SR 3.3.1.1.4 full scale SR 3.3.1.1.5 SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1-1.13 3.3.1.1.15 H SR s 120/125 5 (a) 3 SR 3.3.1.1.2 divisions of SR 3.3.1.1.4 full scale SR 3.3.1.1.5 SR 3.3.1.1.13 3.3.1.1.15 G SR NA 2 3 SR 3.3.1.1.4

b. Inop 3.3.1.1.5 SR 3.3.1.1.15 H SR 3.3.1.1.4 3.3.1.1.5 NA 5 (a) 3 SR SR 3.3.1.1.15 I

2. Average Power Range Monitors 3 (c) G SR 5 22.7% RTP

a. Neutron Flux -High 2 SR 3.3.1.1.2 3.3.1.1.5 (Setdown) SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.13 F SR 3.3.1.1.2

b. Simulated Thermal Power -- High 1 3 (c) SR 3.3.1.1.3 SR 3.3.1.1.5 SR 3.3.1.1.8

_50.55W 62.6%

and

+

RTPIb)

_<117.1% RTP I

SR 3.3.1.1.11 SR 3.3.1.1.13 SR 3.3.1.1.18 (continued) one or more fuel assemblies.

(a) With any control rod withdrawn from a core cell containing loop operation per LCO 3.4.1, "Recirculation Loops (b) :5 [0.55 (W - AW) + 62.6% RTP] when reset for single Operating." The value of AW is defined in plant procedures.

(c) Each APRM channel provides inputs to both trip systems.

3.3-9 Amendment No. 222 1 Brunswick Unit I

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 PER TRIP REQUIRED SURVEILLANCE ALLOWABLE SPECIFIED SYSTEM ACTION D.1 REQUIREMENTS VALUE FUNCTION CONDITIONS 1,2 2 G SR 3.3.1.1.5 5 108 galLons

7. Scram Discharge Votume SR 3.3.1.1.9 Water Level -High SR 3.3.1.1.13 SR 3.3.1.1.15 (a) 2 H SR 3.3.1.1.5 _ 108 gallons 5

SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15

> 26% RTP 4 E SR 3.3.1.1.5 _s10% closed I

8. Turbine Stop 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 2!26% RTP 2 E SR 3.3.1.1.5 _ 500 psig

9. Turbine Control Valve SR 3.3.1.1.9 Fast Closure, Control SR 3.3.1.1.13 Oil Pressure--Low SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17 1,2 1 G SR 3.3.1.1.12 NA

10. Reactor Mode Switch--

Shutdown Position SR 3.3.1.1.15 (a) 1 H SR 3.3.1.1.12 NA 5

SR 3.3.1.1.15 1,2 1 G SR 3.3.1.1.9 NA

11. Manual Scram SR 3.3.1.1.15 (a) 1 H SR 3.3.1.1.9 NA 5

SR 3.3.1.1.15 assemblies.

(a) With any control rod withdrawn from a core cell containing one or more fuel 3.3-11 Amendment No. 222 1 Brunswick Unit 1

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued) I FREQUENCY 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. I Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 ------------------- NOTE ........

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is

8.75% RTP in I MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days Verify the RBM: 24 months SR 3.3.2.1.4

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) 3.3-21 Amendment No. 222 I Brunswick Unit I

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. I SR 3.3.2.1.6 ------------------ NOTE ---------------.--

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 3.3-22 Amendment No. 222 1 Brunswick Unit I

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 REQUIRED SURVEILLANCE ALLOWABLE SPECIFIED CHANNELS REQUIREMENTS VALUE FUNCTION CONDITIONS

1. Rod Block Monitor 2 SR 3.3.2.1.1 (h)

a. Low Power Range -Upscale (a)

SR 3.3.2.1.4 SR 3.3.2.1.7 (b) 2 SR 3.3.2.1.1 (h)

b. Intermediate Power 3.3.2.1.4 SR Upscale Range -- SR 3.3.2.1.7 2 SR 3.3.2.1.1 (h)

C. High Power Range -UpscaLe (c),(d)

SR 3.3.2.1.4 SR 3.3.2.1.7 2 SR 3.3.2.1.1 NA

d. Inop (d),(e)

(f) 1 SR 3.3.2.1.2 NA

2. Rod Worth Minimizer 1 (f), 2 SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8 (g) SR 3.3.2.1.6 NA

3. Reactor Mode Switch -Shutdown Position specified in the COLR except not required to be (a) THERMAL POWER is ? 29% RTP and MCPR Less than the limit Range -UpscaLe Function or High Power Range -Upscale Function is OPERABLE if the Intermediate Power OPERABLE.

specified in the COLR and MCPR less than the Limit (b) THERMAL POWER is > Intermediate Power Range Setpoint if the High Power Range -UpscaLe Function is specified in the COLR except not required to be OPERABLE OPERABLE.

the COLR and < 90% RTP and MCPR Less than the (c) THERMAL POWER ?: High Power Range Setpoint specified in Limit specified in the COLR.

in the COLR.

(d) THERMAL POWER _ 90% RTP and MCPR Less than the Limit specified the Limit specified in the COLR.

(e) THERMAL POWER ? 29% and < 90% RTP and MCPR Less than (f) With THERMAL POWER _<8.75% RTP.

(g) Reactor mode switch in the shutdown position.

(h) Allowable Value specified in the COLR.

3.3-23 Amendment No. 222 1 Brunswick Unit I

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 Three channels of feedwater and main turbine high water level trip instrumentation shall be OPERABLE.

APPLICABILITY: THERMAL POWER Ž 23% RTP.

ACTIONS

- - - - - - - - - - - - - - - - - - - NOT E. . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

Separate Condition entry is allowed for. each channel.

CONDITION REQUIRED ACTION COMPLETION TIME I I A. One feedwater and main A.1 Place channel in 7 days trip.

turbine high water level trip channel inoperable.

Restore feedwater and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Two or more feedwater B.1 main turbine high and main turbine high water level trip water level trip capability.

channels inoperable.

iT Required Action and C.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C.

to < 23% RTP. I associated Completion Time not met.

I 3.3-24 Amendment No. 222 1 Brunswick Unit 1

Main Turbine Bypass System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 The Main Turbine Bypass System LCO 3.7.6 The Main Turbine Bypass System shall be OPERABLE.

OR The following limits are made applicable:

RATE LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION Bypass a.

(APLHGR)," limits for an inoperable Main Turbine System, as specified in the COLR; and limits

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"as for an inoperable Main Turbine Bypass System, specified in the COLR.

APPLICABILITY: THERMAL POWER - 23% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.1 Satisfy the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months A. Requirements of the requirements of the LCO not met. LCO.

B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and I associated Completion to < 23% RTP.

Time not met.

3.7-20 Amendment No. 222 I Brunswick Unit I

Definitions 1.1 1.1 Definitions (continued)

OPERABLE-OPERABILITY 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).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer (RTP) rate to the reactor coolant of 2923 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME 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.

SHUTDOWN MARGIN (SDM) 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)

Brunswick Unit 2 1.1-5 Amendment No. 247 I

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs or core 2.1.1.1 With the reactor steam dome pressure < 785 psig flow < 10% rated core flow:

I THERMAL POWER shall be 5 23% RTP.

With the reactor steam dome pressure Ž 785 psig and core 2.1.1.2 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.

the top 2.1.1.3 Reactor vessel water level shall be greater than 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

2.0-1 Amendment No. 247 I Brunswick Unit 2

Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION jCOMPLETION TIME Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. (continued) C.2 CRD.

D.I Restore compliance 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D.---------- NOTE------ with BPWS.

Not applicable when THERMAL POWER

> 8.75% RTP. OR

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months D.2 Restore control rod to OPERABLE status.

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.

i i E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months E. Required Action and associated Completion Time of Condition A, C, or D not met.

OR Nine or more control rods inoperable. .I 3.1-9 Amendment No. 247 I Brunswick Unit 2

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).

APPLICABILITY: MODES I and 2 with THERMAL POWER

8.75% RTP. I iWTTANS COMLETON IM CONDITION REQUIRED ACTION COMPLETION TIME

-I A. One or more OPERABLE A.1 NOTE------

Control rod may be control rods not in bypassed in the rod compliance with BPWS. worth minimizer (RWM) or RWM may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation.

Move associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rooas) to correct position.

OR Declare associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months A.2 control rod(s) inoperable.

(continued) 3.1-18 Amendment No. 247 I Brunswick Unit 2

APLHGR 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months limits, within limits.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to < 23% RTP. I associated Completion 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

- 23% RTP I AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter 3.2-1 Amendment No. 247 I Brunswick Unit 2

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.1 Restore MCPR(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months A. Any MCPR not within limits, within limits.

B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and associated Completion to < 23% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY 3.2.2.1 Verify all MCPRs are greater than or equal Once within SR to the limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

Ž23%RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued) 3.2-2 Amendment No. 247 I Brunswick Unit 2

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

COMPLETION TIME CONDITION REQUIRED ACTION 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. - ------- NOTE---- B.1 Place channel in one trip system in trip.

Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f. OR

-- - - - - ------- 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B.2 Place one trip system in trip.

One or more Functions with one or more required channels inoperable in both trip systems.

I hour C.1 Restore RPS trip C. One or more Functions capability.

with RPS trip capability not maintained.

Immediately D.1 Enter the Condition D. Required Action and referenced in associated Completion Table 3.3.1.1-1 for Time of Condition A, the channel.

B, or C not met.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months E.I Reduce THERMAL POWER E. As required by to < 26% RTP. I Required Action D.1 and referenced in Table 3.3.1.1-1.

(continued) 3.3-2 Amendment No. 247 I Brunswick Unit 2

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

NOTES .............................

RPS

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each Function.

of

2. When a channel is placed in an inoperable status solely for performance associated Conditions and Required required Surveillances, entry into Function Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated maintains RPS trip capability. . . . . . . . ..--------------

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 (Not used.)

Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.1.2 SR 3.3.1.1.3 ------------------ NOTE ------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 , 23%

RTP.

SR 3.3.1.1.4 ------------------ NOTE ------------------

Not required to be performed when entering MODE 2 from MODE 1 until 19 hnors after enterina MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 days (continued) 3.3-4 Amendment No. 247 1 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. I 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)

Brunswick Unit 2 3.3-7 Amendment No. 247 1

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation CONDITIONS APPLICABLE CONDITIONS REFERENCED MODES OR RREQUIRED HANNELS FROM OTHER REQUIRED SPECIFIED FPER TRIP SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE SYSTEM ACTION D.1 FUNCTION CONDITIONS

1. Intermediate Range Monitors 2 3 G SR 3.3.1.1.2 3.3.1.1.4 S120/125 divisions of

a. Neutron Flux -High SR SR 3.3.1.1.5 full scale SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.15 H SR 3.3.1.1.2 5 120/125 5 (a) 3 SR 3.3.1.1.4 divisions of SR 3.3.1.1.5 full scale SR 3.3.1.1.13 SR 3.3.1.1.15 G SR 3.3.1.1.4 NA

b. I nop 2 3 SR 3.3.1.1.5 SR 3.3.1.1.15 5 (a) 3 H SR 3.3.1.1.4 NA SR 3.3.1.1.5 SR 3.3.1.1.15

2. Average Power Range Monitors (c) G SR 3.3.1.1.2 _<22.7% RTP

a. Neutron Flux--High 2 3 SR 3.3.1.1.5 (Setdown) SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.13 (c) F SR 3.3.1.1.2 _50.55W +

I 3

b. Simulated Thermal 1 SR 3.3.1.1.3 62.6% RTP(b)

Power -High SR 3.3.1.1.5 and SR 3.3.1.1.8 _5117.1% RTP SR 3.3.1.1.11 SR 3.3.1.1.13 SR 3.3.1.1.18 (continued) assemblies.

(a) With any control rod withdrawn from a core cell containing one or more fuel per LCO 3.4.1, "Recirculation Loops (b) < EO.55(W - AW) + 62.6% RTP] when reset for single loop operation Operating." The value of AW is defined in plant procedures.

(c) Each APRM channel provides inputs to both trip systems.

3.3-9 Amendment No. 247 I Brunswick Unit 2

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)

Reactor Protection System Instrumentation CONDITIONS APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM PER TRIP REQUIRED SURVEILLANCE ALLOWABLE SPECIFIED SYSTEM ACTION D.1 REQUIREMENTS VALUE FUNCTION CONDITIONS 1,2 2 G SR 3.3.1.1.5 S108 gatlons

7. Scram Discharge Volume SR 3.3.1.1.9 Water Level -High SR 3.3.1.1.13 SR 3.3.1.1.15

108 gallons 5 (a) H SR 3.3.1.1.5 2

SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15

10% closed E SR 3.3.1.1.5

8. Turbine Stop ?_26% RTP 4 SR 3.3.1.1.9 Valve -- Closure 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 S500

_ 26% RTP 2 psig I

9. Turbine Control Valve SR 3.3.1.1.9 Fast Closure, Control SR 3.3.1.1.13 Oil Pressure -Low SR 3.3.1.1.15 SR 3.3.1.1.16 SR 3.3.1.1.17 1,2 G SR 3.3.1.1.12 NA

10. Reactor Mode Switch SR 3.3.1.1.15 Shutdown Position NA 5 (a) 1 H SR 3.3.1.1.12 SR 3.3.1.1.15 SR 3.3.1.1.9 NA 1,2 1 G

11. Manual Scram SR 3.3.1.1.15 (a) SR 3.3.1.1.9 NA 5 H SR 3.3.1.1.15 fuel assemblies.

(a) With any control rod withdrawn from a core cell containing one or more 3.3-11 Amendment No. 247 1 Brunswick Unit 2

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued) FREQUENCY 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.

92 days Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.2.1.3 ------------------- NOTE ............

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is 5 8.75% RTP in I MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days Verify the RBM: 24 months SR 3.3.2.1.4

a. Low Power Range-Upscale Function OR Intermediate Power Range-Upscale Function OR High Power Range--Upscale Function is enabled (not bypassed) when APRM Sio 1ulated 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.

(conti nued) 3.3-21 Amendment No. 247 I Brunswick Unit 2

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.

SR 3.3.2.1.6 ------------------ NOTE ------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 Brunswick Unit 2 3.3-22 Amendment No. 247 1

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 CONDITIONS CHANNELS REQUIREMENTS VALUE FUNCTION

1. Rod Block Monitor (a) 2 SR 3.3.2.1.1 (h)

a. Low Power Range -- Upscale SR 3.3.2.1.4 SR 3.3.2.1.7 (b) 2 SR 3.3.2.1.1 (h)

b. Intermediate Power SR 3.3.2.1.4 Range -Upscale SR 3.3.2.1.7 (c),(d) 2 SR 3.3.2.1.1 (h)

c. High Power Range -Upscale SR 3.3.2.1.4 SR 3.3.2.1.7 (d),(e) 2 SR 3.3.2.1.1 NA

d. Inop 1 SR 3.3.2.1.2 NA

2. Rod Worth Minimizer 1 (f), 2 (f)

SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8 (g) 2 SR 3.3.2.1.6 NA

3. Reactor Mode Switch -Shutdown Position in the COLR except not required to be (a) THERMAL POWER is > 29% RTP and MCPR less than the limit specified Intermediate Power Range -Upscale Function or High Power Range -Upscale Function is OPERABLE if the OPERABLE.

in the COLR and MCPR Less than the limit (b) THERMAL POWER is ?: Intermediate Power Range Setpoint specified to be OPERABLE if the High Power Range -Upscale Function is specified in the COLR except not required OPERABLE.

COLR and < 90% RTP and MCPR Less than the (c) THERMAL POWER ?_ High Power Range Setpoint specified in the limit specified in the COLR.

COLR.

(d) THERMAL POWER > 90% RTP and MCPR less than the limit specified in the in the COLR.

(e) THERMAL POWER _ 29% and < 90% RTP and MCPR less than the limit specified (f) With THERMAL POWER < 8.75% RTP. I (g) Reactor mode switch in the shutdown position.

(h) Allowable Value specified in the COLR.

3.3-23 Amendment No. 247 I Brunswick Unit 2

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION Instrumentation 3.3.2.2 Feedwater and Main Turbine High Water Level Trip LCO 3.3.2.2 Three channels of feedwater and main turbine high water I

level trip instrumentation shall be OPERABLE.

THERMAL POWER Ž 23% RTP. I APPLICABILITY:

ACTIONS

NOTE ------------------------------------

Separate Condition entry is allowed for .each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.I Place channel in 7 days A. One feedwater and main trip.

turbine high water level trip channel inoperable.

B.1 Restore feedwater and 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Two or more feedwater main turbine high and main turbine high water level trip water level trip capability.

channels inoperable.

Required Action and C.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. I associated Completion to < 23% RTP.

Time not met.

3.3-24 Amendment No. 247 I Brunswick Unit 2

Main Turbine Bypass System 3.7.6 3.7 PLANT SYSTEMS 3.7.6 The Main Turbine Bypass System LCO 3.7.6 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.

APPLICABILITY: THERMAL POWER Ž 23% RTP. I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LCO not met. requirements of the LCO.

B. Required Action and B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 23% RTP. I Time not met.

Brunswick Unit 2 3.7-20 Amendment No. 247 1

v t e Letter Sequence Other
TAC:MB2700, (Approved, Closed) TAC:MB2701, (Approved, Closed)
Initiation Request, Request Acceptance... Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Questions 22 February 2002 Answers 24 January 2002 4 February 2002 1 February 2002 13 February 2002 21 February 2002 14 February 2002 25 February 2002 21 February 2002 25 February 2002 25 February 2002 4 March 2002 5 March 2002 7 March 2002 14 March 2002 14 March 2002 20 March 2002 26 April 2002 12 March 2002 Results Approval, Approval Other: BSEP 02-0070, Additional Information on License Amendments Re Extended Power Uprate, ML020370417, ML021350651, ML021490134, ML021550425
MONTHYEAR2002-03-14 [Table View]

ML021550425

Text

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