Text

Request for License Amendments, Extended Power Uprate. Includes Typed TS Pages in Support of Requested Amendments
	ML021230318
Person / Time
Site:	Brunswick
Issue date:	04/22/2002
From:	O'Neil E; Carolina Power & Light Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	BSEP 02-0086, TAC MB2700, TAC MB2701
	Download: ML021230318 (39)
	v • d • e

SCP&L A Progress Energy Company APR 2 2 2002 SERIAL: BSEP 02-0086 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 TYPED TECHNICAL SPECIFICATION PAGES SUPPORTING REQUEST FOR LICENSE AMENDMENTS - EXTENDED POWER UPRATE (NRC TAC NOS. MB2700 AND MB2701)

Ladies and Gentlemen:

On August 9, 2001 (i.e., Serial: BSEP 01-0086), Carolina Power & Light (CP&L) Company requested a revision to the Operating Licenses (OLs) and the Technical Specifications (TSs) for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The proposed license amendments increase the maximum power level authorized by Section 2.C.(1) of OLs DPR-71 and DPR-62 from 2558 megawatts thermal (MWt) to 2923 MWt. The purpose of this letter is to provided typed TS pages in support of issuance of the requested amendments. provides page change instructions. Enclosures 2 and 3 provide typed TS pages for Unit 1 and 2, respectively.

In addition to the TS changes supporting extended power uprate, an administrative correction has been made on TS page 3.3-9, for each unit. Specifically, a Surveillance Requirement (SR), listed in Table 3.3.1.1-1, for Function 1.b, "Intermediate Range Monitors - Inop," was changed from "SR 3.3.2.2.15" to "SR 3.3.1.1.15." This change is purely administrative; no SR 3.3.2.2.15 exists in the BSEP TSs. As such, the change does not affect CP&L's conclusion that the proposed amendments do not involve a significant hazards consideration.

Please refer any questions regarding this submittal to Mr. Leonard R. Beller, Supervisor Licensing/Regulatory Programs, at (910) 457-2073.

Sincerely, Edward T. O'Neil Manager - Regulatory Affairs Brunswick Steam Electric Plant Brunswick Nuclear Plant A -C C,

Southport, NC 28461

Document Control Desk BSEP 02-0086 / Page 2 MAT/mat

Enclosures:

1. Page Change Instructions

2. Typed Technical Specification Pages - Unit 1

3. Typed Technical Specification Pages - Unit 2 cc:

U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Luis A. Reyes, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commissioi, ATTN: Mr. Theodore A. Easlick, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Ms. Brenda L. Mozafari (Mail Stop OWFN 8G9) 11555 Rockville Pike Rockville, MD 20852-2738 U. S. Nuclear Regulatory Commission ATTN: Mr. Mohammed Shuaibi (Mail Stop OWFN 8H4A) 11555 Rockville Pike Rockville, MD 20852-2738 Ms. Jo A. Sanford Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-05 10 Mr. Mel Fry Director - Division of Radiation Protection North Carolina Department of Environment and Natural Resources 3825 Barrett Drive Raleigh, NC 27609-7221

ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 TYPED TECHNICAL SPECIFICATION PAGES SUPPORTING REQUEST FOR LICENSE AMENDMENTS - EXTENDED POWER UPRATE (NRC TAC NOS. MB2700 AND MB2701)

Paae Channe Instructions

Unit 1 Page Change Instructions Remove

]

Insert 1.1-5 1.1-5 2.0-1 2.0-1 3.1-9 3.1-9 3.1-18 3.1-18 3.2-1 3.2-1 3.2-2 3.2-2 3.3-2 3.3-2 3.3-4 3.3-4 3.3-7 3.3-7 3.3-9 3.3-9 3.3-11 3.3-11 3.3-21 3.3-21 3.3-22 3.3-22 3.3-23 3.3-23 3.3-24 3.3-24 3.7-20 3.7-20

Unit 2 Page Change Instructions Remove

[

Insert 1.1-5 1.1-5 2.0-1 2.0-1 3.1-9 3.1-9 3.1-18 3.1-18 3.2-1 3.2-1 3.2-2 3.2-2 3.3-2 3.3-2 3.3-4 3.3-4 3.3-7 3.3-7 3.3-9 3.3-9 3.3-11 3.3-11 3.3-21 3.3-21 3.3-22 3.3-22 3.3-23 3.3-23 3.3-24 3.3-24 3.7-20 3.7-20

ENCLOSURE 2 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 TYPED TECHNICAL SPECIFICATION PAGES SUPPORTING REQUEST FOR LICENSE AMENDMENTS - EXTENDED POWER UPRATE (NRC TAC NOS. MB2700 AND MB2701)

Typed Technical Specification Pages - Unit 1

Definitions 1.1 1.1 Definitions (continued)

OPERABLE-OPERABILITY RATED THERMAL POWER (RTP)

REACTOR PROTECTION SYSTEM (RPS)

RESPONSE

TIME SHUTDOWN MARGIN (SDM)

A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2923 MWt.

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:

a.

The reactor is xenon free;

b.

The moderator temperature is 68°F; and

c.

All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

(conti nued)

Amendment No.

222 I 1.1-5 Brunswick Unit 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.

2.1.1.2 With the reactor steam dome pressure ! 785 psig and core flow : 10% rated core flow:

MCPR shall be E 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 Reactor Coolant System Pressure SL 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.

Amendment No.

222 I I

2.0-1 Brunswick Unit 1

Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

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

D. --------- NOTE--------- D.1 Restore compliance 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Not applicable when with BPWS.

THERMAL POWER

> 8.75% RTP.

OR 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.

E.

Required Action and E.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, C, or D not met.

OR Nine or more control rods inoperable.

Amendment No.

222 1 I

3.1-9 Brunswick Unit I

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO

3.1.6 APPLICABILITY

OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).

MODES 1 and 2 with THERMAL POWER 5 8.75% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more OPERABLE A.1

NOTE------

control rods not in Control rod may be compliance with BPWS.

bypassed in the rod worth minimizer (RWM) or RWM may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation."

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

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

(continued)

Amendment No.

222 I I

Brunswick Unit 1 3.1-18

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

LCO

3.2.1 APPLICABILITY

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

THERMAL POWER ! 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 associated Completion to < 23% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal Once within to the limits specified in the COLR.

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

! 23% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Amendment No. 222 I APLHGR 3.2.1 3.2-1 Brunswick Unit 1

3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)

LCO 3.2.2 APPLICABILITY:

All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.

THERMAL POWER Ž 23% RTP.

ACTIONS 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 SR 3.2.2.1 Verify all MCPRs are greater than or equal Once within to the limits specified in the COLR.

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

Ž 23% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

Amendment No. 222 I MCPR 3.2.2 I

Brunswick Unit I 3.2-2

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 < 26% RTP.

and referenced in Table 3.3.1.1-1.

(continued)

Amendment No.

222 i I

3-3-2 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.

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

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 I 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.

222 1 I

3.3-4 Brunswick Unit I

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

26% 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.

222 I I

3.3-7 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 NODES 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-4igh (Setdown) 2 5(a) 2 5 (a) 2 3

3 3

3 3 (c) 3 (c)

G SR SR SR SR SR SR SR H

SR SR SR SR SR G

SR SR SR H

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 3.3.1.1.15 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 5 120/125 divisions of full scale s 120/125 divisions of full scale NA NA 5 22.7% RTP 5 0.55W +

62.6% RTP(b) and

-5 117.1% RTP 1

b.

Simulated Thermal Power -High (continued)

(a)

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

(b) 5 [0.55 (W - &W) + 62.6% RTP] when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."

The value of AW is defined in plant procedures.

(c)

Each APRM channel provides inputs to both trip systems.

Amendment No. 222 1 I

I 3.3-9 Brunswick Unit 1

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 Volume 1,2 2

G SR 3.3.1.1.5

< 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

_ 26% RTP 4

E SR 3.3.1.1.5

-< 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

> 26% 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)

I H

SR 3.3.1.1.9 NA SR 3.3.1.1.15 (a)

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

Amendment No.

222 I I

3.3-11 Brunswick Unit 1

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

8.75% RTP in MODE 2.

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 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

> Intermediate Power Range Setpoint specified in the COLR.

c.

High Power Range-Upscale Function is enabled (not bypassed) when APRM Simulated Thermal Power is Ž High Power Range Setpoint specified in the COLR.

(continued)

Amendment No.

222 I I

3.3-21 Brunswick Unit 1

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 8.75% 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.

222 I I

Brunswick Unit 1 3.3-22

Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page 1 of 1)

Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

1.

Rod Block Monitor

a.

Low Power Range -Upscale (a) 2 SR 3.3.2.1.1 (h)

SR 3.3.2.1.4 SR 3.3.2.1.7

b.

Intermediate Power (b) 2 SR 3.3.2.1.1 (h)

Range -Upscale SR 3.3.2.1.4 SR 3.3.2.1.7

c.

High Power Range -Upscale (c),(d) 2 SR 3.3.2.1.1 (h)

SR 3.3.2.1.4 SR 3.3.2.1.7

d.

Inop (d),(e) 2 SR 3.3.2.1.1 NA

2.

Rod Worth Minimizer 1(f),2(f) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8

3.

Reactor Mode Switch -Shutdown (g) 2 SR 3.3.2.1.6 NA Position (a)

THERMAL POWER is k 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 k 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 k 29% and < 90% RTP and MCPR Less than the limit specified in the COLR.

(f)

With THERMAL POWER _5 8.75% RTP.

(g)

Reactor mode switch in the shutdown position.

(h)

Allowable Value specified in the COLR.

Amendment No.

222 1 I

Brunswick Unit I 3.3-23

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 APPLICABILITY:

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

THERMAL POWER : 23% RTP.

ACTIONS

-NO NOTE.....................-.....

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One feedwater and main A.1 Place channel in 7 days turbine high water trip.

level trip channel inoperable.

B.

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

C.

Required Action and C.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.

Amendment No.

222 1 I

I 3.3-24 Brunswick Unit 1

Main Turbine Bypass 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.

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.

Time not met.

Amendment No. 222 I System 3.7.6 I

I 3.7-20 Brunswick Unit 1

ENCLOSURE 3 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 TYPED TECHNICAL SPECIFICATION PAGES SUPPORTING REQUEST FOR LICENSE AMENDMENTS - EXTENDED POWER UPRATE (NRC TAC NOS. MB2700 AND MB2701)

Typed Technical Specification Pa2es - Unit 2

Definitions 1.1 1.1 Definitions (continued)

OPERABLE-OPERABILITY RATED THERMAL POWER (RTP)

REACTOR PROTECTION SYSTEM (RPS)

RESPONSE

TIME SHUTDOWN MARGIN (SDM)

A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2923 MWt.

The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:

a.

The reactor is xenon free;

b.

The moderator temperature is 68 0F; and

c.

All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

(continued)

Amendment No. 247 i 1.1 Definitions (continued)

I Brunswick Unit 2 1.1-5

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

THERMAL POWER shall be 5 23% RTP.

2.1.1.2 With the reactor steam dome pressure Ž 785 psig and core flow Ž 10% rated core flow:

MCPR shall be -

1.09 for two recirculation loop operation or Ž-1.10 for single recirculation loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Reactor Coolant System Pressure SL 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.

Amendment No.

247 I I

2.0-1 Brunswick Unit 2

Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

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

D. ---------- NOTE--------- D.1 Restore compliance 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Not applicable when with BPWS.

THERMAL POWER

> 8.75% RTP.

OR 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.

E.

Required Action and E.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, C, or D not met.

OR Nine or more control rods inoperable.

Amendment No.

247 I I

Brunswick Unit 2 3.1-9

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO

3.1.6 APPLICABILITY

OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).

MODES I and 2 with THERMAL POWER

8.75% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more OPERABLE A.1

NOTE------

control rods not in Control rod may be compliance with BPWS.

bypassed in the rod worth minimizer (RWM) or RWM may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation."

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

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

(continued)

Amendment No. 247 1 I

Brunswick Unit 2 3.1-18

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 equa specified in the COLR.

1 to the limits APPLICABILITY:

THERMAL POWER _ 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 associated Completion to < 23% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal Once within to the limits specified in the COLR.

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

Ž 23% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Amendment No.

247 I I

Brunswick Unit 2 3.2-1

MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)

LCO

3.2.2 APPLICABILITY

All MCPRs operating shall be greater than or equal to the MCPR limits specified in the COLR.

THERMAL POWER Ž 23% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Any MCPR not within A.1 Restore MCPR(s) to 4 hours4.62963e-5 days 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 SR 3.2.2.1 Verify all MCPRs are greater than or equal Once within to the limits specified in the COLR.

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

> 23% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter (continued)

Amendment No.

247 I I

I 3.2-2 Brunswick Unit 2

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 < 26% RTP.

and referenced in Table 3.3.1.1-1.

(continued)

Amendment No. 247 I I

3-3-2 Brunswick Unit 2

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS NOTES........................

1.

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

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 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 ý 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)

Amendment No. 247 I 3.3-4 Brunswick Unit 2

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

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

SR 3.3.1.1.17 ------------------ NOTES--------------

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. 247 1 Brunswick Unit 2 3.3-7

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

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

1. 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 [0.55(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.

per LCO 3.4.1, "Recirculation Loops Amendment No.

247 I 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 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 3.3.1.1.15 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 5 120/125 divisions of full scale 5 120/125 divisions of full scale NA NA 5 22.7% RTP 5 0.55W +

62.6% RTP(b) and

_5 117.1% RTP 2

1 I

I 3.3-9 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 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

< 108 gallons SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15

8.

Turbine Stop

> 26% RTP 4

E SR 3.3.1.1.5

< 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

> 26% 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. 247 I 3.3-]11 Brunswick Unit 2

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

Amendment No. 247 i SURVEILLANCE FREQUENCY 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

8.75% RTP in MODE 2.

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 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

> Intermediate Power Range Setpoint specified in the COLR.

c.

High Power Range-Upscale Function is enabled (not bypassed) when APRM Simulated Thermal Power is z High Power Range Setpoint specified in the COLR.

(continued)

Brunswick Unit 2 3.3-21

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.5 Verify the RWM is not bypassed when 24 months THERMAL POWER is o 8.75% RTP.

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.

247 I 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 APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

1.

Rod Block Monitor

a.

Low Power Range -Upscale (a) 2 SR 3.3.2.1.1 (h)

SR 3.3.2.1.4 SR 3.3.2.1.7

b.

Intermediate Power (b) 2 SR 3.3.2.1.1 (h)

Range -Upscale SR 3.3.2.1.4 SR 3.3.2.1.7

c.

High Power Range-Upscale (c),(d) 2 SR 3.3.2.1.1 (h)

SR 3.3.2.1.4 SR 3.3.2.1.7

d.

Inop (d),(e) 2 SR 3.3.2.1.1 NA

2.

Rod Worth Minimizer 1(f), 2 (f) 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8

3.

Reactor Mode Switch -Shutdown (g) 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 k 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 k 90% RTP and MCPR less than the limit specified in the COLR.

(e)

THERMAL POWER k 29% and < 90% RTP and MCPR less than the limit specified in the COLR.

(f)

With THERMAL POWER 5 8.75% RTP.

(g)

Reactor mode switch in the shutdown position.

(h)

Allowable Value specified in the COLR.

Amendment No.

247 I I

Brunswick Unit 2 3.3-23

Feedwater and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 APPLICABILITY:

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

THERMAL POWER Ž 23% RTP.

NOTE OTE-------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One feedwater and main A.1 Place channel in 7 days turbine high water trip.

level trip channel inoperable.

B.

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

C.

Required Action and C.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.

Amendment No.

247 1 ACTIONS I

Brunswick Unit 2 3.3-24

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

3.7.6 APPLICABILITY

The Main Turbine Bypass System shall be OPERABLE.

OR The following limits are made applicable:

a.

LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," limits for an inoperable Main Turbine Bypass System, as specified in the COLR; and

b.

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

THERMAL POWER Ž 23% RTP.

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.

Time not met.

Amendment No. 247 I I

I Brunswick Unit 2 3.7-20

v t e Letter Sequence Request
TAC:MB2700, (Approved, Closed) TAC:MB2701, (Approved, Closed)
Initiation Request, Request, 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 24 January 2002 12 March 2002 Results Approval, Approval Other: BSEP 02-0070, Additional Information on License Amendments Re Extended Power Uprate, ML020370417, ML021350651, ML021490134, ML021550425
MONTHYEAR2002-03-20 [Table View]

ML021230318

Text

Enclosures:

RESPONSE

3.1.6 APPLICABILITY

3.2.1 APPLICABILITY

RESPONSE

3.1.6 APPLICABILITY

3.2.2 APPLICABILITY

3.7.6 APPLICABILITY

Navigation menu

Search