Text

Technical Specifications Pages for Amendment Nos. 217 & 243, Brunswick, Units 1 & 2
	ML020740056
Person / Time
Site:	Brunswick
Issue date:	03/08/2002
From:	Goshen J, Hansen A; Carolina Power & Light Co
To:	Keenan J; Carolina Power & Light Co, Office of Nuclear Reactor Regulation
References
	TAC MB2321, TAC MB2322
	Download: ML020740056 (56)
	v • d • e

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS)

Instrumentation LCO 3.3.1.1 APPLICABILITY:

The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

According to Table 3.3.1.1-1.

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable, trip.

OR A.2 NOTE ------

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Not applicable for Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

Place associated trip system in trip.

(continued)

Amendment No.

217 i ACTIONS Brunswick Unit 1 3.3-1

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

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 Not applicable for trip system in trip.

Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

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

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

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.

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

the channel.

E.

As required by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.1 to < 30% RTP.

and referenced in Table 3.3.1.1-1.

(continued)

Amendment No. 217 I Brunswick Unit I 3.3-2

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

As required by F.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

G.

As required by G.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by H.1 Initiate action to Immediately Required Action D.1 fully insert all and referenced in insertable control Table 3.3.1.1-1.

rods in core cells containing one or more fuel assemblies.

I.

As required by I.1 Initiate alternate 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 method to detect and and referenced in suppress thermal Table 3.3.1.1-1.

hydraulic instability oscillations.

J.

Required Action and J.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 20% RTP.

Time of Condition I not met.

Amendment No. 217 1 Brunswick Unit 1 3.3-3

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 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 25% RTP.

Adjust the average power range monitor 7 days (APRM) channels to conform to the calculated power while operating at z 25%

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)

Amendment No.

217 1 Brunswick Unit 1 3.3-4

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Perform a functional test of each 7 days automatic scram contactor.

SR 3.3.1.1.6 Verify the source range monitor (SRM) and Prior to intermediate range monitor (IRM) channels withdrawing overlap.

SRMs from the fully inserted position SR 3.3.1.1.7

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

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap.

7 days SR 3.3.1.1.8 Calibrate the local power range monitors.

1100 MWD/T average core exposure SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.1.1.10 Calibrate the trip units.

92 days (continued)

Amendment No. 217 I Brunswick Unit I 3.3-5

RPS Instrumentation 3.3.1.1 r.IflIrTI nklrt nrAhITDtiJfldTC 1rnntinII0d

SURVEILLANCE SR 3.3.1.1.11 ------------------ NOTES -----------------

1. For Function 2.a, 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.

2.

For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.1.1.13 ------------------ NOTES -----------------

1. Neutron detectors are excluded.

2.

For Function 1, 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.

3.

For Functions 2.b and 2.f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION.

SR 3.3.1.1.14 (Not used.)

SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST.

Brunswick Unit 1 bUK¥1" ILL/.*IW*,r-l'*r'*u11*[-.l"ILl*llO

,.,uii*, i,,u*.*/

I 24 months 24 months (continued)

Amendment No. 217 I DrUrUTC nn+in"ad) 3UKVt1LL1AR%,C MLqV1 RPS Instrumentation 3.3.1.1 FREQUENCY 184 days 24 months 3.3-6

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 ý 30% RTP.

SR 3.3.1.1.17 ------------------

NOTES -----------------

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 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.

217 I Brunswick Unit 1 I

3.3-7

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.19 Verify OPRM is not bypassed when APRM 24 months Simulated Thermal Power is Ž 25% and recirculation drive flow is

60%.

Amendment No. 217 I 3.3-8 Brunswick Unit I

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.

Intermediate Range Monitors

a.

Neutron Flux -High

b.

Inop

2.

Average Power Range Monitors

a.

Neutron Flux -High (Setdown)

b.

Simulated Thermal Power -High (continued)

(a)

With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 5 [0.66(W - AW) + 62.0% 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.

217 I Brunswick Unit 1 2

5 (a) 2 3

3 3

3 3 (c) 3 (c) 5 (a)

G SR SR SR SR SR SR SR H

SR SR SR SR SR G

SR SR SR H

SR SR SR G

SR SR SR SR SR SR F

SR SR SR SR SR SR SR 2

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 3.3.1.1.4 3.3.1.1.5 3.3.2.2.15 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 s 120/125 divisions of full scale s 120/125 divisions of full scale NA NA 5 22.7% RTP

< 0 66W +4 62.0% RTP(b) and

_s 117.1% RTP 1

I I

I 3.3-9

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 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

2.

Average Power Range Monitors (continued)

c.

Neutron Flux -High

d.

Inop

e.

2-Out-Of-4 Voter

f.

OPRM Upscale

3.

Reactor Vessel Steam Dome Pressure -High

4.

Reactor Vessel Water Level -Low Level 1

5.

Main Steam Isolation Valve --Closure

6.

Drywett Pressure -High 1,2 1,2 3 (c) 3 (c) 2

> 20% RTP 3 (c) 1,2 1,2 1

1,2 2

2 8

2 (c)

Each APRM channel provides inputs to both trip systems.

(d)

See COLR for OPRM period based detection algorithm (PBDA) setpoint Limits.

Amendment No. 217 1 Brunswick Unit 1 F

SR SR SR SR SR SR G

SR SR G

SR SR SR SR SR SR SR SR SR SR SR SR G

SR SR SR SR SR SR SR G

SR SR SR SR SR SR SR F

SR SR SR SR SR G

SR SR SR SR SR SR s 118.7% RTP NA NA NA(d) 5 1077 psig S153 inches S10% closed s 1.8 psig 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 3.3.1.1.5 3.3.1.1.11 3.3.1.1.2 3.3.1.1.5 3.3.1.1.11 3.3.1.1.15 3.3.1.1.17 3.3.1.1.2 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 3.3.1.1.19 3.3.1.1.2 3.3.1.1.5 3.3.1.1.9 3.3.1.1.10 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.2 3.3.1.1.5 3.3.1.1.9 3.3.1.1.10 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.5 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.2 3.3.1.1.5 3.3.1.1.9 3.3.1.1.10 3.3.1.1.13 3.3.1.1.15 (continued)

I I

3.3-10

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

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MOOES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

7.

Scram Discharge Volume 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

SR 3.3.1.1.5

_5 108 gaLlons SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15

8.

Turbine Stop

> 30% RTP 4

E SR 3.3.1.1.5 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

_ 30% RTP 2

E SR 3.3.1.1.5

> 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.

Mnual Scram 1,2 1

6 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.

217 1 3.3-11 Brunswick Unit I

SRM Instrumentation 3.3.1.2 3.3 INSTRUMENTATION 3.3.1.2 Source Range Monitor (SRM)

Instrumentation LCO 3.3.1.2 APPLICABILITY:

The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.

According to Table 3.3.1.2-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Restore required SRMs 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SRMs inoperable in to OPERABLE status.

MODE 2 with intermediate range monitors (IRMs) on Range 2 or below.

B.

Three required SRMs B.1 Suspend control rod Immediately inoperable in MODE 2 withdrawal.

with IRMs on Range 2 or below.

C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B not met.

(continued)

Amendment No.

217 1 Brunswick Unit 1 3.3-12

SRM Instrumentation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.

One or more required D.1 Fully insert all I hour SRMs inoperable in insertable control MODE 3 or 4.

rods.

AND D.2 Place reactor mode I hour switch in the shutdown position.

E.

One or more required E.1 Suspend CORE Immediately SRMs inoperable in ALTERATIONS except MODE 5.

for control rod insertion.

AND E.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Amendment No. 217 I Brunswick Unit 1 3.3-13

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified condition.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2.2 NOTES -----------------

1.

Only required to be met during CORE ALTERATIONS.

2.

One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months located in:

a.

The fueled region;

b.

The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c.

A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fuel region.

SR 3.3.1.2.3 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

Amendment No.

217 1 Brunswick Unit 1 3.3-14

SRM Instrumentation 3.3.1.2 cIIDIrTI I A1JC DflhIITMfliIT

(rnntiniipd

,JUEI Li LLF1I'.L.

SSM

T SURVEILLANCE SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.6 t

NOTES -----------------

1. Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

2.

Not required to be met during a core spiral offload.

Verify--------ate --s --.-------

Verify count rate is ý 3.0 cps.

Perform CHANNEL FUNCTIONAL TEST.

N O T E -----------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST.

FREQUENCY 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 7 days 31 days (continued)

Amendment No.

217 I Brunswick Unit 1 CHMICT11AKirr DrnHTDPMPNTq trnntinuedl I

-- T--

-I 3.3-15

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.7

NOTES--------------

1. Neutron detectors are excluded.

2.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL CALIBRATION.

24 months Amendment No. 217 I Brunswick Unit 1 3.3-16

SRM Instrumentation 3.3.1.2 Table 3.3.1.2-1 (page 1 of 1)

Source Range Monitor Instrumentation APPLICABLE MODES OR OTHER REQUIRED SURVEILLANCE FUNCTION SPECIFIED CONDITIONS CHANNELS REQUIREMENTS

1. Source Range Monitor 2(a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3,4 2

SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5

2 (b)

SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a)

With IRMs on Range 2 or below.

(b)

Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.

Amendment No.

217 1 3.3-17 Brunswick Unit I

Control Rod Block Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod Block Instrumentation LCO 3.3.2.1 APPLICABILITY:

The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

According to Table 3.3.2.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One rod block monitor A.1 Restore RBM channel 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (RBM) channel to OPERABLE status.

inoperable.

B.

Required Action and B.1 Place one RBM channel I hour associated Completion in trip.

Time of Condition A not met.

OR Two RBM channels inoperable.

C.

Rod worth minimizer C.1 Suspend control rod Immediately (RWM) inoperable movement except by during reactor scram.

startup.

OR (continued)

Amendment No. 217 I 3.3-18 Brunswick Unit 1

Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2.1.1 Verify > 12 rods Immediately withdrawn.

OR C.2.1.2 Verify by Immediately administrative methods that startup with RWM inoperable, for reasons other than bypassed control rod(s), has not been performed in the last calendar year.

AND C.2.2 Verify movement of During control bypassed control rod movement rod(s) is in compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.

D.

RWM inoperable during D.1 Verify movement of During control reactor shutdown.

bypassed control rod movement rod(s) is in accordance with BPWS by a second licensed operator or other qualified member of the technical staff.

(continued)

Amendment No. 217 I Brunswick Unit I 3.3-19

Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

One or more Reactor E.1 Suspend control rod Immediately Mode Switch-Shutdown withdrawal.

Position channels inoperable.

AND E.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS

NOTES -----------------------------------

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2.

When an RBM 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST.

184 days (continued)

Amendment No. 217 I Brunswick Unit 1 I

3.3-20

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.2 NOTE ------------------

Not required to be performed until I hour after any control rod is withdrawn at

! 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.2.1.3 NOTE ------------------

Not required to be performed until I hour after THERMAL POWER is < 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.2.1.4 Verify the RBM:

24 months

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 SIntermediate 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. 217 I Brunswick Unit 1 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 a 10% RTP.

SR 3.3.2.1.6

v

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

Not required to be performed until I hour 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.

217 I 3.3-22 Brunswick Unit 1

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)

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 :5 10% RTP.

(g)

Reactor mode switch in the shutdown position.

(h)

Allowable Value specified in the COLR.

Amendment No.

217 I 3.3-23 Brunswick Unit I

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched recirculation pump speeds shall be in operation, OR One recirculation loop may be in operation provided the following limits are applied when the associated LCO is applicable:

a.

LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR),"

single loop operation limits specified in the COLR;

b.

LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

loop operation limits specified in the COLR; and single

c.

LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," Function 2.b (Average Power Range Monitors Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.

APPLICABILITY:

MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Satisfy the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months LCO not met.

requirements of the LCO.

(continued)

Amendment No. 217 I I

Brunswick Unit 1 3.4-1

SDM Test-Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling LCO 3.10.8 APPLICABILITY:

The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a.

LCO 3.3.1.1, "Reactor Protection System Instrumentation," MODE 2 requirements for Functions 2.a, 2.d, and 2.e of Table 3.3.1.1-1;

b.

1. LCO 3.3.2.1, "Control Rod Block Instrumentation,"

MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence, OR

2.

Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c.

Each withdrawn control rod shall be coupled to the associated CRD;

d.

All control rod withdrawals during out of sequence control rod moves shall be made in notch out mode;

e.

No other CORE ALTERATIONS are in progress; and

f.

CRD charging water header pressure > 940 psig.

MODE 5 with the reactor mode switch in startup/hot standby position.

Amendment No.

217 I Brunswick Unit 1 3.10-20

SDM Test-Refueling 3.10.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

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

Separate Condition Inoperable control rod may be entry is allowed for bypassed in the rod worth each control rod.

minimizer (RWM) or RWM may be bypassed as allowed by LCO 3.3.2.1, "Control Rod One or more Block Instrumentation," if control rods not required, to allow insertion coupled to its of inoperable control rod and associated CRD.

continued operation.

A.1 Fully insert 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months inoperable control rod.

AND A.2 Disarm the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated CRD.

B.

One or more of the B.1 Place the reactor Immediately above requirements not mode switch in the met for reasons other shutdown or refuel than Condition A.

position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for According to LCO 3.3.1.1, Functions 2.a, 2.d, and 2.e of the applicable Table 3.3.1.1-1.

SRs (continued)

Amendment No.

217 I 3.10-21 Brunswick Unit 1

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1.

The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for Specification 3.2.1;

2.

The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.2;

3.

The period based detection algorithm (PBDA) setpoint for Function 2.f, Oscillation Power Range Monitor (OPRM)

Upscale, for Specification 3.3.1.1; and

4.

The Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions for Specification 3.3.2.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1.

NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel" (latest approved version).

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

Amendment No. 217 I Brunswick Unit 1 5.0-20

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.6 Post Accident Monitoring (PAM)

Instrumentation Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days.

The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

Amendment No.

217 I Brunswick Unit I 5.0-21

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS)

Instrumentation LCO 3.3.1.1 APPLICABILITY:

The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

According to Table 3.3.1.1-1.

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable, trip.

OR A.22 NOTE---

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

Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

(continued)

Amendment No.

243 1 ACTIONS Brunswick Unit 2 3.3-1

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

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 Not applicable for trip system in trip.

Functions 2.a, 2.b, 2.c, 2.d, or 2.f.

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

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

C.

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

capability not maintained.

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

the channel.

E.

As required.by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.1 to < 30% RTP.

and referenced in Table 3.3.1.1-1.

(continued)

Amendment No.

243 I Brunswick Unit 2 3.3-2

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

As required by F.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action D.1 and referenced in Table 3.3.1.1-I.

G. As required by G.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

H.

As required by H.1 Initiate action to Immediately Required Action D.1 fully insert all and referenced in insertable control Table 3.3.1.1-1.

rods in core cells containing one or more fuel assemblies.

I.

As required by I.1 Initiate alternate 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 method to detect and and referenced in suppress thermal Table 3.3.1.1-1.

hydraulic instability oscillations.

J.

Required Action and J.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion to < 20% RTP.

Time of Condition I not met.

Amendment No.

243 I Brunswick Unit 2 3.3-3

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 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

25% RTP.

Adjust the average power range monitor 7 days (APRM) channels to conform to the calculated power while operating at Ž 25%

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)

Amendment No.

243 I I

3.3-4 Brunswick Unit 2

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.5 Perform a functional test of each 7 days automatic scram contactor.

SR 3.3.1.1.6 Verify the source range monitor (SRM) and Prior to intermediate range monitor (IRM) channels withdrawing overlap.

SRMs from the fully inserted position SR 3.3.1.1.7 NOTE ------------------

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap.

7 days SR 3.3.1.1.8 Calibrate the local power range monitors.

1100 MWD/T average core exposure SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.1.1.10 Calibrate the trip units.

92 days (continued)

Amendment No. 243 I Brunswick Unit 2 3.3-5

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.1.1.11

NOTES--------------

1.

For Function 2.a, not required to be performed when entering MODE 2 from MODE I until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

2.

For Functions 2.b and 2.f, the CHANNEL FUNCTIONAL TEST includes the recirculation flow input processing, excluding the flow transmitters.

Perform CHANNEL FUNCTIONAL TEST.

FREQUENCY 184 days SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

24 months SR 3.3.1.1.13 ------------------ NOTES -----------------

1. Neutron detectors are excluded.

2.

For Function 1, not required to be performed when entering MODE 2 from MODE I until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

3.

For Functions 2.b and 2.f, the recirculation flow transmitters that feed the APRMs are included.

Perform CHANNEL CALIBRATION.

24 months SR 3.3.1.1.14 (Not used.)

SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months (continued)

Amendment No. 243 I Brunswick Unit 2 I

I 3.3-6

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 ý 30% RTP.

SR 3.3.1.1.17 ------------------

NOTES -----------------

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 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 refuel ing outage (continued)

Amendment No.

243 I I

3.3-7 Brunswick Unit 2

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.19 Verify OPRM is not bypassed when APRM 24 months Simulated Thermal Power is Ž 25% and recirculation drive flow is 5 60%.

Amendment No. 243 I Brunswick Unit 2 3.3-8

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

Reactor Protection System Instrumentation APPLICABLE LUNUL iuN

APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIOUNS REFERENCED FROM REQUIRED ACTION 0.1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE 1.Unteme Iat ORNg

1.

Intermediate Range Monitors

a.

Neutron Flux -High 2

5 (a)

b.

Inop 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 SR SR SR SR SR G

SR SR SR SR SR SR G

SR SR SR SR SR SR F

SR SR SR SR 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 3.3.1.1.4 3.3.1.1.5 3.3.2.2.15 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 S120/125 divisions of full scale s 120/125 divisions of full scale NA NA

_< 22.7% RTP

_s 0.66W +._

62.0% RTP*b) and

s 117.1% RTP (continued)

(a)

With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b)

CO.66(W -

AW) + 62.0% 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.

243 I Brunswick Unit 2 FIJUCT I tI 3.3-9

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 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

2.

Average Power Range Monitors (continued)

c.

Neutron Flux -High

d.

Inop

e.

2-Out-Of-4 Voter

f.

OPRM Upscale

3.

Reactor Vessel Steam Dome Pressure -High

4.

Reactor Vessel Water Level --Low Level 1

5.

Main Steam Isolation Valve --Closure

6.

DrywelL Pressure -High 3 (c) 1,2 3 (c) 1,2 2

20% RTP 3 (c) 1,2 1,2 1,2 2

2 a

2 (c)

Each APRM channel provides inputs to both trip systems.

(d)

See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.

Amendment No.

243 1 I

F SR SR SR SR SR SR G

SR SR G

SR SR SR SR SR SR SR SR SR SR SR SR G

SR SR SR SR SR SR SR G

SR SR SR SR SR SR SR F

SR SR SR SR SR G

SR SR SR SR SR SR 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 3.3.1.1.5 3.3.1.1.11 3.3.1.1.2 3.3.1.1.5 3.3.1.1.11 3.3.1.1.15 3.3.1.1.17 3.3.1.1.2 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 3.3.1.1.19 3.3.1.1.2 3.3.1.1.5

.3.3.1.1.9 3.3.1.1.10 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.2 3.3.1.1.5 3.3.1.1.9 3.3.1.1.10 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.5 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.2 3.3.1.1.5 3.3.1.1.9 3.3.1.1.10 3.3.1.1.13 3.3.1.1.15 (continued) 5 118.7% RTP NA NA NA(d) 5 1077 psig

ý 153 inches 5 10% closed 5 1.8 psig cont

~Inud 3.3-10 Brunswick Unit 2

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 Votune 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

SR 3.3.1.1.5 S 108 gaLlons SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15

8.

Turbine Stop

- 30% RTP 4

E SR 3.3.1.1.5 5 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

> 30% RTP 2

E SR 3.3.1.1.5

>: 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. 243 I Brunswick Unit 2 3.3-11

SRM Instrumentation 3.3.1.2 3.3 INSTRUMENTATION 3.3.1.2 Source Range Monitor (SRM)

Instrumentation LCO 3.3.1.2 APPLICABILITY:

The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.

According to Table 3.3.1.2-1.

ALI IiUNI'.

CONDITION A.

One or more required SRMs inoperable in MODE 2 with intermediate range monitors (IRMs) on Range 2 or below.

B. Three required SRMs inoperable in MODE 2 with IRMs on Range 2 or below.

C.

Required Action and associated Completion Time of Condition A or B not met.

REQUIRED ACTION A.1 Restore required SRMs to OPERABLE status.

B.1 Suspend control rod withdrawal.

C.1 Be in MODE 3.

COMPLETION TIME COMPLETION TIME 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Immediately 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Amendment No.

243 I Brunswick Unit 2 3.3-12 A*IIUNb

SRM Instrumentation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more required D.1 Fully insert all 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SRMs inoperable in insertable control MODE 3 or 4.

rods.

AND D.2 Place reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

E.

One or more required E.1 Suspend CORE Immediately SRMs inoperable in ALTERATIONS except MODE 5.

for control rod insertion.

AND E.2 Initiate action to Immediately fully insert all insertable control rods in core cells containing one or more fuel assemblies.

Amendment No.

243 I Brunswick Unit 2 3.3-13

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified condition.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.2.2 NOTES ----------------

1.

Only required to be met during CORE ALTERATIONS.

2.

One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months located in:

a.

The fueled region;

b.

The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c.

A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

SR 3.3.1.2.3 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

Amendment No. 243 I Brunswick Unit 2 3.3-14

SRM Instrumentation 3.3.1.2 Q1i0iUriiaI rrJ P17nITPFMFNTS 1continued~)

'-'-...--,r SURVEILLANCE SR 3.3.1.2.4

NOTES -----------------

1. Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

2.

Not required to be met during a core spiral offload.

Verify count rate is 2: 3.0 cps.

FREQUENCY 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.2.5 Perform CHANNEL FUNCTIONAL TEST.

7 days SR 3.3.1.2.6

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST.

31 days (continued)

Amendment No.

243 1 Brunswick Unit 2 i

3.3-15

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.7

NOTES -----------------

1. Neutron detectors are excluded.

2.

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

24 months Perform CHANNEL CALIBRATION.

Amendment No. 243 I Brunswick Unit 2 3.3-16

SRM Instrumentation 3.3.1.2 TabLe 3.3.1.2-1 (page 1 of 1)

Source Range Monitor Instrumentation APPL I CABLE MODES OR OTHER REQUIRED SURVEILLANCE FUNCTION SPECIFIED CONDITIONS CHANNELS REQUIREMENTS

1. Source Range Monitor 2(a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 3,4 2

SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 5

2 (b)

SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a)

With IRMs on Range 2 or below.

(b)

SpeciaL movable detectors may be used in place of SRMs if connected to normal SRM circuits.

Amendment No. 243 I Brunswick Unit 2 3.3-17

Control Rod Block Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod Block Instrumentation LCO 3.3.2.1 APPLICABILITY:

The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

According to Table 3.3.2.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rod block monitor (RBM) channel inoperable.

B.

Required Action and associated Completion Time of Condition A not met.

OR Two RBM channels inoperable.

C.

Rod worth minimizer (RWM) inoperable during reactor startup.

A.I B.I C.1 Restore RBM channel to OPERABLE status.

Place one RBM channel in trip.

Suspend control rod movement except by scram.

OR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1 hour Immediately (continued)

Amendment No.

243 1 Brunswick Unit 2 3.3-18

Control Rod Block Instrumentation 3.3.2.1 ACTIONS CONDITION C. (continued)

D.

RWM inoperable during reactor shutdown.

REQUIRED ACTION C.2.1.1 Verify _ 12 rods withdrawn.

OR C.2.1.2 Verify by admini strative methods that startup with RWM inoperable, for reasons other than bypassed control rod(s), has not been performed in the last calendar year.

AND C.2.2 Verify movement of bypassed control rod(s) is in compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.

I I

D.1 Verify movement of bypassed control rod(s) is in accordance with BPWS by a second licensed operator or other qualified member of the technical staff.

COMPLETION TIME Immediately Immediately During control rod movement During control rod movement (continued)

Amendment No. 243 I Brunswick Unit 2 3.3-19

Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)

CONDITION E.

One or more Reactor Mode Switch-Shutdown Position channels inoperable.

REQUIRED ACTION Suspend control rod withdrawal.

E.I AND E.2 Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies COMPLETION TIME Immediately Immediately

__________________________________________________ 1

______________________________________________________ 1 ________________________________

SURVEILLANCE REQUIREMENTS

NOTES -----------------------------------

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2.

When an RBM 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST.

(continued)

Amendment No.

243 I Brunswick Unit 2 I

184 days 3.3-20

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at

< 10% RTP in MODE 2.

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 < 10% 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 S: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 FREQUENCY 92 days 92 days 24 months enabled knot bypa u; j n",,,

Simulated Thermal Power is a High Power Range Setpoint specified in the COLR.

(continued)

Amendment No. 243 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 < 10% RTP.

SR 3.3.2.1.6

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

Not required to be performed until I hour 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.

243 I Brunswick Unit 2 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 APPL I CABLE 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) 2 SR 3.3.2.1.6 NA Position (a)

THERMAL POWER is 2t 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 < 10% RTP.

(g)

Reactor mode switch in the shutdown position.

(h)

Allowable Value specified in the COLR.

Amendment No.

243 1 Brunswick Unit 2 3.3-23

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO

3.4.1 APPLICABILITY

Two recirculation loops with matched recirculation pump speeds shall be in operation, OR One recirculation loop may be in operation provided the following limits are applied when the associated LCO is applicable:

a.

LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;

b.

LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR),"

single loop operation limits specified in the COLR; and

c.

LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," Function 2.b (Average Power Range Monitors Simulated Thermal Power-High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.

MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the LCO not met.

Satisfy the requirements of the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (continued)

Amendment No.

243 I Brunswick Unit 2 A.1 I

LCO.

3.4-1

SDM Test-Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM)

Test-Refueling LCO 3.10.8 APPLICABILITY:

The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a.

LCO 3.3.1.1, "Reactor Protection System Instrumentation,"

MODE 2 requirements for Functions 2.a, 2.d, and 2.e of Table 3.3.1.1-1;

b.

1. LCO 3.3.2.1, "Control Rod Block Instrumentation,"

MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence, OR

2.

Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c.

Each withdrawn control rod shall be coupled to the associated CRD;

d.

All control rod withdrawals during out of sequence control rod moves shall be made in notch out mode;

e.

No other CORE ALTERATIONS are in progress; and

f.

CRD charging water header pressure 2 940 psig.

MODE 5 with the reactor mode switch in startup/hot standby position.

Amendment No.

243 I I

3.10-20 Brunswick Unit 2

SDM Test-Refueling 3.10.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ----------NOTE -------- ----------- NOTE -----------

Separate Condition Inoperable control rod may be entry is allowed for bypassed in the rod worth each control rod.

minimizer (RWM) or RWM may be bypassed as allowed by LCO 3.3.2.1, "Control Rod One or more Block Instrumentation," if control rods not required, to allow insertion coupled to its of inoperable control rod and associated CRD.

continued operation.

A.1 Fully insert 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months inoperable control rod.

AND A.2 Disarm the 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated CRD.

B.

One or more of the B.1 Place the reactor Immediately above requirements not mode switch in the met for reasons other shutdown or refuel than Condition A.

position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for According to LCO 3.3.1.1, Functions 2.a, 2.d, and 2.e of the applicable Table 3.3.1.1-1.

SRs (continued)

Amendment No. 243 I Brunswick Unit 2 I

3.10-21

Reporting Requiremenzs 5.6 5.6 Reporting Requirements (continued) 5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1.

The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) for Specification 3.2.1;

2.

The MINIMUM CRITICAL POWER RATIO (MCPR) for Specification 3.2.2;

3.

The period based detection algorithm (PBDA) setpoint for Function 2.f, Oscillation Power Range Monitor (OPRM)

Upscale, for Specification 3.3.1.1; and

4.

The Allowable Values and power range setpoints for Rod Block Monitor Upscale Functions for Specification 3.3.2.1.

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1.

NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel" (latest approved version).

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SOM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

(continued)

Amendment No.

243 I

Brunswick Unit 2

5.0-19

Reporting Requirements 5.6 5.6 Reporting Requirements (continued) 5.6.6 Post Accident Monitoring (PAM)

Instrumentation Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM)

Instrumentation,"

a report shall be submitted within the following 14 days.

The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

Amendment No.

243 Brunswick Unit 2 5.0-20

v t e Letter Sequence Other
TAC:MB2321, (Approved, Closed) TAC:MB2322, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers 14 January 2002 Results Approval Other: ML020740056
MONTHYEAR2002-02-01 [Table View]

ML020740056

Text

3.4.1 APPLICABILITY

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