Text

Amendment No. 149, Power Uprate (License and TS Pages)
	ML021680369
Person / Time
Site:	Clinton
Issue date:	04/05/2002
From:	; NRC/NRR/DLPM
To:	;
	Hopkins J, NRR/DLPM, 415-3027
References
	TAC MB2210
	Download: ML021680369 (28)
	v • d • e

(4)

AmerGen Energy Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

AmerGen Energy Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)

AmerGen Energy Company, LLC, pursuant to the Act and 10 CFR Parts 30, 40, and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level AmerGen Energy Company, LLC is authorized to operate the facility at reactor core power levels not in excess of 3473 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2)

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 149, are hereby incorporated into this license.

AmerGen Energy Company, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 149

Definitions 1.1 1.1 Definitions (continued)

MINIMUM CRITICAL POWER RATIO (MCPR)

MODE OPERABLE-OPERABILITY RATED THERMAL POWER (RTP)

REACTOR PROTECTION SYSTEM (RPS)

RESPONSE

TIME The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each class of fuel.

The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition,.

divided by the actual assembly operating power.

A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

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 3473 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.

(continued)

CLINTON 1.0-5 Amendment No.149

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

21.6% RTP.

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

MCPR shall be Ž 1.09 for two recirculation loop operation or Ž 1.12 for single recirculation loop operation.

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

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be

1325 psig.

2.2 SL Violations With any SL violation, the following actions shall be completed:

2.2.1 Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.2 Within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.

2.2.3 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , notify the plant manager and the corporate executive responsible for overall plant nuclear safety.

(continued)

Amendment No.

1 4 9 CLINTON I

2.0-1

Control Rod OPERABILITY 3.1.3 ACTIONS (Continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Two or more withdrawn B.1 Be in MODE 3.

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

C.

One or more control C.1

NOTE --------

rods inoperable for Inoperable control reasons other than rods may be bypassed Condition A or B.

in RACS in accordance with SR 3.3.2.1.9, if required, to allow insertion of inoperable control rod and continued operation.

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

AND 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

> 16.7% PTP.

OR Two or more inoperable D.2 Restore control rod 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months control rods not in to OPERABLE status.

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

(continued)

Amendment No.

1 4 9 CLINTON 3.1-8

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

16.7% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more OPERABLE control rods not in compliance with BPWS.

A. 1

NOTE -------

Affected control rods may be bypassed in Rod Action Control System (RACS) in accordance with SR 3.3.2.1.9.

Move associated control rod(s) to correct position.

OR A.2 Declare associated control rod(s) inoperable.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 hours (continued)

Amendment No.

1 4 9 CLINTON 3.1-18

SLC System 3.1.7

liii 1

-4 1

i i

i !

M 3SO0 k'

L iN AtRD i 9 i i i til 4000 hK x

4500 LEVEL 5000 I

5500 NET TANK VOLUME (gallons)

Figure 3.1.7-1 (page 1 of 1)

Weight Percent Sodium Pentaborate Solution Concentration/Net Tank Volume Requirements Amendment No. 149 is 14 13 z

0 0-4 ri2E rn w.

11 0

3000

-t= AoVIC iOWRa/

1 -..7 I

0 8 4

T-i-

-T-7-.

3.1-23 CLINTON

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

LCO

3.2.1 APPLICABILITY

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

THERMAL POWER Ž 21.6% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 < 21.6% 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 2 21.6% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Amendment No.

1 4 9 CLINTON I

I 3.2-1

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

LCO

3.2.2 APPLICABILITY

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

THERMAL POWER Ž 21.6% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Any MCPR not within A.1 Restore MCPR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 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 < 21.6% 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 21.6% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Amendment No.

1 4 9 3.2-2 CLINTON

LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO

3.2.3 APPLICABILITY

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

THERMAL POWER Ž 21.6% RTP.

CONDITION A.

Any LHGR not within limits.

B.

Required Action and associated Completion Time not met.

REQUIRED ACTION Restore LHGR(s) to within limits.

A. 1 B. 1 Reduce THERMAL POWER to < 21.6% RTP.

COMPETIO TIM 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 4 hours SUV-LLL

,-,r.r.to +/- lZ*-*tm*

l SURVEILLAINCE.fi REU 1MN SURVEILLANCE SR 3.2.3.1 Verify all LHGRs are the limits specified less than or equal to in the COLR.

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

> 21.6% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Amendment No.149 CLINTON 3.2-3 I

J COMPLETION TIME FREQUENCY

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

As required by E.1 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Required Action D.1 to < 33.3% RTP.

and referenced in Table 3.3.1.1-1.

F.

As required by F.1 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Required Action D.1 to < 21.6% RTP.

and referenced in Table 3.3.1.1-1.

G.

As required by G.1 Be in MODE 2.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

H.

As required by H.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.

I.

As required by I.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.

Amendment No.149 CLINTON I

3.3-2

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS NOTES

1.

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

2.

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

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.1.2 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 21.6% RTP.

Verify the absolute difference between 7 days the average power range monitor (APRM) channels and the calculated power

2% RTP while operating at Ž 21.6% RTP.

SR 3.3.1.1.3 Adjust the channel to conform to a 7 days calibrated flow signal.

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. 1 4 9 CLINTON 3.3-3

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.1.1.16 SR 3.3.1.1.17 Verify Turbine Stop Valve Closure and Turbine Control Valve Fast Closure Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is

', 33.3%

RTP.

NOTES

1.

Neutron detectors are excluded.

2.

For Functions 3, 4,

and 5 in Table 3.3.1.1-1, the channel sensors are excluded.

3.

The STAGGERED TEST BASIS Frequency for each Function shall be determined on a per channel basis.

Verify the RPS RESPONSE TIME is within limits.

FREQUENCY 18 months 18 months on a STAGGERED TEST BASIS 3.3-6 Amendment No.1 4 9 I

CLINTON

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

Reactor Protection System Instrumentation APEPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FIJNCTION CONDITIONS FU1NCTION ACTION D. 1 REQUIREMENTS VALUE I.

Intermediate Range Monitors

a.

Neutron Flux-High 551.)

2 H

SR 3.3.1.1.4 SR 3.3.1.1.15 5I.)

SR 3.3.1.1.5 SR 3.3.1.1.15 NA

2.

Average Power Range Monitors

a.

Neutron Flux-High, Setdownl

b.

Flow Biased Simulated Thermal P'ower -

High

c.

Fixed Neu.tron Flux -

High

d.

Inop 2

H SR SR SR SR SR SR SR SR SR SR SR SR SR SR SR G

SR SR SR SR SR SR SR H

SR SR SR 3.3.1.1.1 3.3.1.1.4 3.3.1.1.7 3.3.1.1.8 3.3.1.1.11 3.3.1.1.15 3.3.1.1.1 3.3.1.1.2 3.3.1.1.3 3.3.1.1.8 3.3.1.1.9 3.3.1.1.11 3.3.1.1.14 3.3.1.1.15 3.3.1.1.17 3.3.1.1.1 3.3.1.1.2 3.3.1.1.8 3.3.1.1.9 3.3.1.1.11 3.3.1.1.15 3.3.1.1.17 3.3.1.1.8 3.3.1.1.9 3.3.1.1.15 q 20% RTE'

<0.55 W +

62% RTE and -< 113%

RTPIbu

< 120% RTP NA (continued)

(a)

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

(b) Allowable Value is

. 0.55 (W-8)

+ 42.5% RTP' when reset for single L:- 3.4.1, "Recirculation Loops Operating."

loop operation per Amendment No.

1 4 9 4

4

b.

Inop H

SR SR SR SR SR SR SR SR SR SR 3.3.1.1.1 3.3.1.1.4 3.3.1.1.6 3.3.1.1.7 3.3.1.1.13 3.3.1.1.15 3.3.1.1.1 3.3.1.1.5 3.3.1.1.13 3.3.1.1.15

< 122/125 divisions of full scale

<122/125 divisions of full scale NA 3.3-7 CLINTON

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 REQUIRED SURVEILLANCE ALLOWABLE FUJN(.TION CONDITIONS FUNCTION ACTION D.1 REQUIREMENTS VALUE

3.

Reactor Vessel Steam Dome Pressure. -

High

4.

Reactor Vessel Water Level-Low, Level 3

5.

Reactor Vessel Water Level-High, Level 8 1,2 1,2

? 21.6 % RTP 4

4 4

6.

main Steam Isolation 14 Valve-Closure

7.

Drywell Pressure-High 1,2 H

SR SR SR SR SR SR SR SR SR SR SR SR F

SR SR SR SR SR SR G

SR SR SR SR SR SR SR SR SR 3.3.1.1.1 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 3.3.1.1.1 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 3.3.1.1.1 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 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.17 3.3.1.1.1 3.3.1.1.9 3.3.1.1.10 3.3.1.1.13 3.3.1.1.15

a.

Transmitter 1,2 4

H SR SR SR SR SR SR SR SR SR SR 3.3.1.1.1 3.3.1.1.9 3.3.1.1.10 3.3.1.1.13 3.3.1.1.15 3.3.1.1.1 3.3.1.1.9 3.3.1.1.10

3. 3. 1. 1.

3 3.3.1.1.15

< 40-1/4 inches for 1ClI N601A,B and

< 39-3/16 inches for 1C11-N601C, D

< 40-1/4 inches for ICiI N601A,B and

< 39-3/16 inches for 1C11-N601C, D (continued)

(a)

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

Amendment No.

1 4 9

< 1080 psig

Ž 8.3 inches 5 52.6 inches

< 12% closed 5 1.88 psig

8.

Scram Discharge Volume Water Level-High

.5c.)

3.3-8 CLINTON

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

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

8. "cram Discharge Volume water Level-High

b.

Float Switch 1,2 5(.)

9. Turbine Stop Valve Closure > 33.3% RTP

10. Turbine Control Valve Fast Closure, Trip Oil Pressure-Low

Ž 33.3% RTF H

SR SR SR 4

4 SR SR SR SR SR SR SR SR E

SR SR SR SR SR 3.3.1.1.9

< 763 ft. 3-1/4 3.3.1.1.13 inches msl for 3.3.1.1.15 IC1I-N013A,B and -< 763 ft.

1-11/16 inches msl for lCll N013C, D 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.16 3.3.1.1.17 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15 3.3.1.1.16 3.3.1.1.17 S763 ft.

3-1/4 inches msl for IC1l-NO13A,B and : 763 ft.

1-11/16 inches msl for IClI N013C, D

7% closed

> 465 psig 4

11. Reactor Mode Swit ch-Shultdown Position

12. Manual Scram 5 a) 1,2 5W(.

4 4

H SR 3.3.1.1.12 SR 3.3.1.1.15 I

SR 3.3.1.1.12 SR 3.3.1.1.15 H

SR 3.3.1.1.9 SR 3.3.1.1.15 I

SR 3.3.1.1.9 SR 3.3.1.1L:5 Amendment No. 14 9 CLINTON FUNCTION NA NA NA (a)

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

I 3.3-9

Control Rod Block Instrumentation 3.3.2.1 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 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 control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 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 greater than the RWL high power setpoint (HPSP)

Perform CHANNEL FUNCTIONAL TEST.

92 days 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 THERMAL POWER is

> 29.2% RTP and less than or equal to the RWL HPSP.

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 any control rod is withdrawn in MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

92 days (continued)

Amendment No.1 4 9 CLINTON I

3.3-16

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.2.1.4

- - - -NOTE Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is 5 16.7% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST.

SR 3.3.2.1.5 SR 3.3.2.1.6 SR 3.3.2.1.7 SR 3.3.2.1.8 SR 3.3.2.1.9 Calibrate the low power setpoint analog trip modules.

The Allowable Value shall be > 16.7% RTP and

29.2% RTP.

Verify the RWL high power Function is not bypassed when THERMAL POWER is

> 70% RTP.

Perform CHANNEL CALIBRATION.

- - -NOTE-Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST.

1*

Verify the bypassing and movement of control rods required to be bypassed in Rod Action Control System (RACS) is in conformance with applicable analyses by a second licensed operator or other qualified member of the technical staff.

FREQUENCY 92 days 92 days 92 days 18 months 18 months Prior to and during the movement of control rods bypassed in RACS 3.3-17 Amendment No.149 CLINTON I

I A

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 FUNCTION CONDITIONS CHANNELS REQUIREMENTS

1.

Rod Pattern Control System

a.

Rud witidrawal limiter 2

SR 3.3.2.1.1 SR 3.3.2.1.6 SR 3.3.2.1.9 Ib) 2 SR 3.3.2.1.2 SR 3.3.2.1.5 SR 3.3.2.1.7 SR 3.3.2.1.9

b.

Rod pattern controller i('),2 2

SR 3.3.2.1.3 SR 3.3.2.1.4 SR 3.3.2.1.5 SR 3.3.2.1.7 SR 3.3.2.1.9

2.

Reactor Mode Switch-Shutdown Position (d)

SR 3.3.2.1.8 (a)

THERMAL POWER greater than the RWL HPSP.

(b)

THERMAL POWER

- 29.2% RTP and less than or equal to the RWL HPSP.

(c)

With THERMAL POWER < 16.7% RTP.

(d)

Reactor mode switch in the shutdown position.

CLINTON 3.3-18 Amendment No.149

EOC-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation LCO 3.3.4.1 APPLICABILITY:

Four channels for each EOC-RPT instrumentation Function listed below shall be OPERABLE:

a.

Turbine Stop Valve (TSV) Closure; and

b.

Turbine Control Valve (TCV) Fast Closure, Trip Oil Pressure-Low.

THERMAL POWER Ž 33.3% RTP with any recirculation pump in fast speed.

ACTIONS NOTEO Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions A.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months with one required OPERABLE status.

channel inoperable.

OR A.2 NOTE Not applicable if inoperable channel is the result of an inoperable breaker.

Place one channel in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months affected Function in trip.

(continued)

Amendment No.

1 4 9 CLINTON 3.3-25

EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION B.

One or more Functions with two channels inoperable.

C.

One or more Functions with three or more channels inoperable.

D.

Required Action and associated Completion Time not met.

REQUIRED ACTION B. 1 C. 1 D. 1 OR D.2 Place one channel in affected Function in trip.

Restore two channels in affected Function to OPERABLE status.

Remove the associated recirculation pump fast speed breaker from service.

Reduce THERMAL POWER to < 33.3% RTP.

COMPLETION TIME 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 2 hours 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8 hours I

L_

SURVEILLANCE REQUIREMENTS

NOTE-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 EOC-RPT trip capability.

SURVEILLANCE SR 3.3.4.1.1 Perform CHANNEL FUNCTIONAL TEST.

FREQUENCY 92 days (continued)

Amendment No.149 CLINTON 3.3-26 FREQUENCY

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.3.4.1.2 Perform CHANNEL CALIBRATION.

The Allowable Values shall be:

a.

TSV Closure: 5 7% closed; and

b.

TCV Fast Closure, Trip Oil Pressure-Low: 2 465 psig.

SR 3.3.4.1.3 Perform LOGIC SYSTEM FUNCTIONAL TEST, including breaker actuation.

SR 3.3.4.1.4 Verify TSV Closure and TCV Fast Closure, Trip Oil Pressure-Low Functions are not bypassed when THERMAL POWER is 2 33.3%

RTP.

SR 3.3.4.1.5 5 NOTE----------------

The STAGGERED TEST BASIS Frequency shall be determined on a per Function basis.

Verify the EOC-RPT SYSTEM RESPONSE TIME is within limits.

FREQUENCY 18 months 18 months 18 months 18 months on a STAGGERED TEST BASIS 3.3-27 Amendment No.149 CLINTON I

Primary Containment and Drywell Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 6)

Primary Containment and Drywell Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION F.1 REQUIREMENTS VALUE

1. Main Steam Line Isolation

a. Reactor Vessel Water Level-Low Low Low, Level 1

b. Main Steam Line E'ressu re-Low

c. Main Steam Line Flow-High

d. Condenser Vacuum-Low

e. Main Steam Tunnel Temperature-High

f. Main Steam Line Turbine Building Temperature-High

g. Manual Initiation 1,2,3 1

1,2,3 1,2(',

3(')

1,2,3 1,2,3 1,2,3 4

4 4

4 G

SR SR SR SR SR SR H

SR SR SR SR SR SR G

SR SR SR SR SR G

SR SR SR SR G

SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.5 3.3.6.1.6 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.5 3.3.6.1.6 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.5 3.3.6.1.6 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.5 3.3.6.1.6 3.3.6.1.1 3.3.6.1.2 3.3.6.1.5 3.3.6.1.6 3.3.6.1.1 3.3.6.1.2 3.3.6.1.5 3.3.6.1.6

Ž -147.7 inches S837 psig

- 284 psid a 7.6 inches Hg vacuum e 171°F Modules 1-4 142*F, Module 5 4 150*F SR 3.3.6.1.6 NA (continued)

(a)

With any turbine stop valve not closed.

Amendment No.1 4 9 CLINTON 3.3-55

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

3.4.1 APPLICABILITY

A.

Two recirculation loops shall be in operation with:

1. Matched flows; and

2.

Total core flow and THERMAL POWER within limits.

OR B.

One recirculation loop shall be in operation with:

1.

THERMAL POWER

58% RTP;

2.

Total core flow and THERMAL POWER within limits;

3.

Required limits modified for single recirculation loop operation as specified in the COLR; and

4.

LCO 3.3.1.1, "Reactor Protection System (RPS)

Instrumentation," Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power-High),

Allowable Value of Table 3.3.1.1-1 reset for single loop operation.

NOTE Required limit and setpoint modifications for single recirculation loop operation may be delayed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after transition from two recirculation loop operation to single recirculation loop operation.

MODES 1 and 2.

CONDTTION A.

Recirculation loop jet pump flow mismatch not within limits.

REQUIRED ACTION 1

A.I Shut down one recirculation loop.

AOMPLETIO TIME 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months I~l--i~U 3.4-1 Amendment No.1 4 9 CLINTON

./-*L...'I" J. U.['.*

COMPLETION TIME tcontinued)

Recirculation Loops Operating 3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Total core flow as a B.1 Determine Average Once per 8 function of THERMAL Power Range Monitor hours POWER within Region A (APRM) and Local AND or B of Figure 3.4.1-1.

Power Range Monitor 30 minutes (LPRM) neutron flux after an noise levels.

increase of

Ž 5% RTP C.

Total core flow as a C.1 Restore APRM and LPRM 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months function of THERMAL neutron flux noise POWER within Region B level to

3 times of Figure 3.4.1-1.

established baseline levels.

AND APRM or LPRM neutron flux noise level > 3 times established baseline noise level.

D.

Total core flow as a D.1 Restore total core 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months function of THERMAL flow as a function of POWER within Region A THERMAL POWER to of Figure 3.4.1-1.

within Region B or C of Figure 3.4.1-1.

E.

THERMAL POWER > 58% RTP E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during single to

58% RTP.

recirculation loop operation.

(continued)

Amendment No.

1 4 9

1. 4-2 CLINTON

Recirculation Loops Operating 3.4.1 70 60 50 D0 I

-40 0

IL

-I 30 I-20 25 30 35 40 45 50 55 60 65 70 CORE FLOW (% rated)

Figure 3.4.1-1 (page 1 of 1)

Thermal Power/Core Flow Stability Regions Amendment No. 1 4 9 M i l I II I II l l Region A Region B I

Ii I

LI ii I I 'Mi H

I I

I.

M Ii iii H il I

w

,i l l i l M

il H

I Hi ll-

M 1 1 1 1 1 1-11 1

10 0

3.4-5 CLINTON

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.3.1 NOTES

1.

Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation.

2.

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 21.6% RTP.

Verify at least two of the following criteria (a, b, and c) are satisfied for each operating recirculation loop:

a.

Recirculation loop drive flow versus flow control valve position differs by

10% from established patterns.

b.

Recirculation loop drive flow versus total core flow differs by

10% from established patterns.

c.

Each jet pump diffuser to lower plenum differential pressure differs by

20%

from established patterns, or each jet pump flow differs by

10% from established patterns.

3.4-9 Amendment No. 14 9 CLINTON Jet Pumps 3.4.3 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

=.

-=7 ý

%7 I

RCS P/T Limits 3.4.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE SR 3.4.11.8 NOTE-------------------

Only required to be met in single loop operation during increases in THERMAL POWER or recirculation loop flow with THERMAL POWER

25% of RTP or recirculation loop flow in the operating loop 5 30% of rated flow.

Verify the difference between the bottom head coolant temperature and the RPV coolant temperature is

100'F.

SR 3.4.11.9 NOTE-Only required to be met in single loop operation during increases in THERMAL POWER or recirculation loop flow with THERMAL POWER

25% of RTP or recirculation loop flow in the operating loop

30% of rated flow, and with the idle recirculation loop not isolated from the RPV.

Verify the difference between the reactor coolant temperature in the recirculation loop not in operation and the RPV coolant temperature is

501F.

FREQUENCY Once within 15 minutes prior to an increase in THERMAL POWER or an increase in loop flow Once within 15 minutes prior to an increase in THERMAL POWER or an increase in loop flow i _______________________________

3.4-31 Amendment No.

1 4 9 I

CLINTON

Main Turbine 3.7 PLANT SYSTEMS 3.7.6 Main Turbine Bypass System LCO

3.7.6 APPLICABILITY

The Main Turbine Bypass System shall be OPERABLE.

THERMAL POWER Ž 21.6% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Main Turbine Bypass A.1 Restore Main Turbine 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months System inoperable.

Bypass System to OPERABLE status.

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 < 21.6% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify one complete cycle of each main 31 days turbine bypass valve.

SR 3.7.6.2 Perform a system functional test.

18 months SR 3.7.6.3 Verify the TURBINE BYPASS SYSTEM RESPONSE 18 months TIME is within limits.

Amendment No. 1 4 9 Bypass 3.7.6 3.7-13 CLINTON

v t e Letter Sequence Other
TAC:MB2210, (Approved, Closed)
Initiation Request Acceptance... Supplement Administration Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance Questions Answers Results Approval Other: ML020250107, ML021650636, ML021680369
MONTHYEAR2002-02-07 [Table View]

ML021680369

Text

RESPONSE

3.1.6 APPLICABILITY

3.2.1 APPLICABILITY

3.2.2 APPLICABILITY

3.2.3 APPLICABILITY

3.4.1 APPLICABILITY

3.7.6 APPLICABILITY

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