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)

The MCPR shall be the smallest critical power MINIMUM CRITICAL POWER RATIO (MCPR) 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.

MODE 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.

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

RTP shall be a total reactor core heat transfer RATED THERMAL POWER (RTP) rate to the reactor coolant of 3473 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval SYSTEM (RPS) RESPONSE from when the monitored parameter exceeds its RPS TIME trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

(continued) 1.0-5 Amendment No.149 CLINTON

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. I 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) 149 2.0-1 Amendment No.

CLINTON

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) 149 3.1-8 Amendment No.

CLINTON

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

APPLICABILITY: MODES 1 and 2 with THERMAL POWER

16.7% RTP.

ACTIONS REQUIRED ACTION COMPLETION TIME CONDITION A. One or more OPERABLE A. 1 --------- NOTE -------

Affected control rods control rods not in may be bypassed in compliance with BPWS. Rod Action Control System (RACS) in accordance with SR 3.3.2.1.9.

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

(continued) 14 9 Amendment No.

CLINTON 3.1-18

SLC System 3.1.7 is

-t= AoVIC iOWRa/ LEVEL 14 z0 liii

-4 1

1 0-4 13 k' ri2E L

iN AtRD hK rn ii !9ii i i! M til w.

11 T-i- -T- 7- 4.

1-. 7. I 08 x

I 0

3000 3SO0 4000 4500 5000 5500 NET TANK VOLUME (gallons)

Figure 3.1.7-1 (page 1 of 1)

Weight Percent Sodium Pentaborate Solution Concentration/Net Tank Volume Requirements CLINTON 3.1-23 Amendment No. 149

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

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

APPLICABILITY: THERMAL POWER Ž 21.6% RTP. I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME 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 A.

limits, within limits.

B.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and associated Completion to < 21.6% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify all APLHGRs are less than or equal Once within SR 3.2.1.1 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 I AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter 14 9 3.2-1 Amendment No.

CLINTON

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

LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.

APPLICABILITY: THERMAL POWER Ž 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 149 CLINTON 3.2-2 Amendment No.

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

LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER Ž 21.6% RTP.

J COMPETIO TIM REQUIRED ACTION COMPLETION TIME CONDITION Restore LHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months A. Any LHGR not within A. 1 within limits.

limits.

B. 1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and to < 21.6% RTP.

associated Completion Time not met.

SUV- LLL lZ*-*tm*

,-,r.r.to +/- l SURVEILLAINCE.fi REU 1MN SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after COLR.

the limits specified in the > 21.6% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter I

3.2-3 Amendment No.149 CLINTON

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

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

and referenced in Table 3.3.1.1-1.

As required by F.1 Reduce THERMAL POWER 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months F.

Required Action D.1 to < 21.6% RTP. I and referenced in Table 3.3.1.1-1.

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 G.

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

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 H.

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

As required by I.1 Initiate action to Immediately I.

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.

3.3-2 Amendment No.149 CLINTON

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

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

Function.

performance of

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

SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.1.1 3.3.1.1.2 - ---------- NOTE SR 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.

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

2% RTP while operating at Ž 21.6% RTP.

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

3.3.1.1.4 ------------ NOTE SR 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) 149 3.3-3 Amendment No.

CLINTON

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

FREQUENCY SURVEILLANCE 18 months SR 3.3.1.1.16 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% I RTP.

NOTES --

SR 3.3.1.1.17

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.

within 18 months TEST on a Verify the RPS RESPONSE TIME is STAGGERED limits. BASIS 49 3.3-6 Amendment No.1 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 4 H SR 3.3.1.1.1 < 122/125

a. Neutron Flux-High SR 3.3.1.1.4 divisions SR 3.3.1.1.6 of full SR 3.3.1.1.7 scale SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.1 <122/125 551.) 4 SR 3.3.1.1.5 divisions SR 3.3.1.1.13 of full SR 3.3.1.1.15 scale NA 2 H SR 3.3.1.1.4

b. Inop SR 3.3.1.1.15 5I.) SR 3.3.1.1.5 NA SR 3.3.1.1.15

2. Average Power Range Monitors 2 H SR 3.3.1.1.1 q 20% RTE'

a. Neutron Flux-High, SR 3.3.1.1.4 Setdownl SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.1 <0.55 W +

b. Flow Biased Simulated SR 3.3.1.1.2 62% RTE Thermal P'ower - High SR 3.3.1.1.3 and -< 113%

SR 3.3.1.1.8 RTPIbu SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.14 SR 3.3.1.1.15 SR 3.3.1.1.17 G SR 3.3.1.1.1 < 120% RTP

c. Fixed Neu.tron SR 3.3.1.1.2 Flux - High SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.11 SR 3.3.1.1.15 SR 3.3.1.1.17 H SR 3.3.1.1.8 NA

d. Inop SR 3.3.1.1.9 SR 3.3.1.1.15 (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 loop operation per L:- 3.4.1, "Recirculation Loops Operating."

149 CLINTON 3.3-7 Amendment No.

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 CONDITIONS FUNCTION ACTION D.1 REQUIREMENTS VALUE FUJN(.TION 1,2 4 H SR 3.3.1.1.1 < 1080 psig

3. Reactor Vessel Steam Dome SR 3.3.1.1.9 Pressure. - High SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.17 1,2 4 SR 3.3.1.1.1 Ž 8.3 inches

4. Reactor Vessel Water SR 3.3.1.1.9 Level-Low, Level 3 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.17 F SR 3.3.1.1.1 Reactor Vessel Water ? 21.6 % RTP 4 5 52.6 inches

5. SR 3.3.1.1.9 Level-High, Level 8 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.17 G SR 3.3.1.1.9 14 < 12% closed

6. main Steam Isolation SR 3.3.1.1.13 Valve-Closure SR 3.3.1.1.15 SR 3.3.1.1.17 SR 3.3.1.1.1 5 1.88 psig

7. Drywell Pressure-High 1,2 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.15

8. Scram Discharge Volume Water Level-High

a. Transmitter 1,2 H SR 3.3.1.1.1 < 40-1/4 inches SR 3.3.1.1.9 for 1ClI SR 3.3.1.1.10 N601A,B and SR 3.3.1.1.13 < 39-3/16 SR 3.3.1.1.15 inches for 1C11-N601C, D

.5c.) SR 3.3.1.1.1 < 40-1/4 inches 4 SR 3.3.1.1.9 for ICiI SR 3.3.1.1.10 N601A,B and SR 3. 3. 1. 1. 3 < 39-3/16 SR 3.3.1.1.15 inches for 1C11-N601C, D (continued)

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

14 9 CLINTON 3.3-8 Amendment No.

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

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

8. "cram Discharge Volume water Level-High 1,2 H SR SR 3.3.1.1.9 3.3.1.1.13 < 763 ft.

inches msl 3-1/4 for

b. Float Switch SR 3.3.1.1.15 IC1I-N013A,B and -< 763 ft.

1-11/16 inches msl for lCll N013C, D 5(.) 4 SR 3.3.1.1.9 S763 ft. 3-1/4 SR 3.3.1.1.13 inches msl for SR 3.3.1.1.15 IC1l-NO13A,B and : 763 ft.

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

9. Turbine Stop Valve Closure > 33.3% RTP SR SR SR 3.3.1.1.9 3.3.1.1.13 3.3.1.1.15

7% closed I

SR 3.3.1.1.16 SR 3.3.1.1.17 3.3.1.1.9 4 E SR > 465 psig

10. Turbine Control Valve Ž 33.3% RTF SR 3.3.1.1.13 Fast Closure, Trip Oil SR 3.3.1.1.15 Pressure-Low SR 3.3.1.1.16 SR 3.3.1.1.17 4 H SR 3.3.1.1.12 NA

11. Reactor Mode SR 3.3.1.1.15 Swit ch-Shultdown Position I SR 3.3.1.1.12 NA 5 a)

SR 3.3.1.1.15 H SR 3.3.1.1.9 NA 1,2 4

12. Manual Scram SR 3.3.1.1.15 4 I SR 3.3.1.1.9 5W(.

SR 3.3.1.1L:5 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

3.3-9 Amendment No. 1 4 9 CLINTON

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

NOTES Rod

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

performance of

2. When a channel is placed in an inoperable status solely for entry into associated Conditions and Required required Surveillances, for up to 6 hours provided the associated Function Actions may be delayed 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 less than or equal to the RWL HPSP.

POWER is > 29.2% RTP and I

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 ------------ NOTE-Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days (continued) 4 9 3.3-16 Amendment No.1 CLINTON

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued) I FREQUENCY 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. 92 days Calibrate the low power setpoint analog 92 days SR 3.3.2.1.5 trip modules. The Allowable Value shall be > 16.7% RTP and

29.2% RTP.

I Verify the RWL high power Function is not 92 days SR 3.3.2.1.6 bypassed when THERMAL POWER is > 70% RTP.

Perform CHANNEL CALIBRATION. 18 months SR 3.3.2.1.7 SR 3.3.2.1.8 - - - - - -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.

CHANNEL FUNCTIONAL TEST.

18 months Perform 1*

Verify the bypassing and movement of Prior to and SR 3.3.2.1.9 during the control rods required to be bypassed in movement of Rod Action Control System (RACS) is in control rods conformance with applicable analyses by a bypassed in second licensed operator or other RACS qualified member of the technical staff.

A 3.3-17 Amendment No.149 CLINTON

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 CONDITIONS CHANNELS REQUIREMENTS FUNCTION

1. Rod Pattern Control System 2 SR 3.3.2.1.1

a. Rud witidrawal limiter 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 i('),2 2 SR 3.3.2.1.3

b. Rod pattern controller SR 3.3.2.1.4 SR 3.3.2.1.5 SR 3.3.2.1.7 SR 3.3.2.1.9 (d) SR 3.3.2.1.8

2. Reactor Mode Switch-Shutdown Position (a) THERMAL POWER greater than the RWL HPSP.

to the RWL HPSP.

(b) THERMAL POWER :- 29.2% RTP and less than or equal (c) With THERMAL POWER < 16.7% RTP.

(d) Reactor mode switch in the shutdown position.

3.3-18 Amendment No .149 CLINTON

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 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.

APPLICABILITY: 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 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 A.

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) 14 9 3.3-25 Amendment No.

CLINTON

EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

COMPLETION TIME CONDITION REQUIRED ACTION B. 1 Place one channel in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. One or more Functions affected Function in with two channels trip.

inoperable.

C. 1 Restore two channels 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months C. One or more Functions in affected Function with three or more to OPERABLE status.

channels inoperable.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D. 1 Remove the associated D. Required Action and recirculation pump associated Completion fast speed breaker Time not met. from service.

OR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D.2 Reduce THERMAL POWER to < 33.3% RTP.

I _ _ _ _ _ _ _ _ _ L_ _ _ _ _

SURVEILLANCE REQUIREMENTS

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

FREQUENCY SURVEILLANCE FREQUENCY Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.4.1.1 (continued) 3.3-26 Amendment No.149 CLINTON

EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

FREQUENCY SURVEILLANCE The 18 months SR 3.3.4.1.2 Perform CHANNEL CALIBRATION.

Allowable Values shall be:

a. TSV Closure: 5 7% closed; and

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

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

18 months 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. I

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

SR 3.3.4.1.55 The STAGGERED TEST BASIS Frequency shall be determined on a per Function basis.

18 months on a Verify the EOC-RPT SYSTEM RESPONSE TIME STAGGERED TEST is within limits. BASIS 3.3-27 Amendment No.149 CLINTON

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 ACTION F.1 REQUIREMENTS VALUE FUNCTION CONDITIONS

1. Main Steam Line Isolation

a. Reactor Vessel Water 1,2,3 4 G SR SR 3.3.6.1.1 3.3.6.1.2 Ž -147.7 inches Level-Low Low Low, SR 3.3.6.1.3 Level 1 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 H SR 3.3.6.1.1

b. Main Steam Line 1 4 SR 3.3.6.1.2 S837 psig E'ressu re-Low SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 G SR 3.3.6.1.1 - 284 psid 1,2,3 4

c. Main Steam Line SR 3.3.6.1.2 Flow-High SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.7 G SR 3.3.6.1.1

d. Condenser Vacuum-Low 1,2(' , 4 SR 3.3.6.1.2 aHg 7.6 inches vacuum SR 3.3.6.1.3 3(')

SR 3.3.6.1.5 SR 3.3.6.1.6 G SR 3.3.6.1.1 e 171°F 1,2,3

e. Main Steam Tunnel SR 3.3.6.1.2 Temperature-High SR 3.3.6.1.5 SR 3.3.6.1.6 G SR 3.3.6.1.1 Modules 1-4 1,2,3 4

f. Main Steam Line Turbine SR 3.3.6.1.2 - 142*F, Building SR 3.3.6.1.5 Module 5 Temperature-High SR 3.3.6.1.6 4 150*F 1,2,3 4 SR 3.3.6.1.6 NA

g. Manual Initiation (continued)

(a) With any turbine stop valve not closed.

4 9 3.3-55 Amendment No.1 CLINTON

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating A. Two recirculation loops shall be in operation with:

LCO 3.4.1

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.

APPLICABILITY: MODES 1 and 2.

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

AOMPLETIO TIME REQUIRED ACTION COMPLETION TIME CONDTTION

_____________________ 1 A.I Shut down one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months A. Recirculation loop jet recirculation loop.

pump flow mismatch not within limits.

I~l--i~U tcontinued) 49 3.4-1 Amendment No.1 CLINTON

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) 149 CLINTON 1. 4-2 Amendment No.

Recirculation Loops Operating 3.4.1 70 M i l I II I II l l 60 Region A Region B IiI

- 50 D0 I

-40 I 0

IL

-I 30 I-20 LI I'Mi ii I I H I I.

,, Ii iii M H il I M il H 10 _______________

w * ,i l l i l I ____________ Hi ll- M 1 1 1 1 1 1- 11 1 0

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 149 CLINTON 3.4-5 Amendment No.

Jet Pumps 3.4.3 SURVEILLANCE REQUIREMENTS

=. -=7 ý

--- %7 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. I 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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. 1 4 9 CLINTON

RCS P/T Limits 3.4.11 SURVEILLANCE REQUIREMENTS (continued) FREQUENCY 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.

Once within 15 minutes Verify the difference between the bottom head coolant temperature and the RPV prior to an increase in coolant temperature is

100'F.

THERMAL POWER or an increase in loop flow 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 I flow in the operating loop

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

Once within 15 minutes Verify the difference between the reactor prior to an coolant temperature in the recirculation increase in loop not in operation and the RPV coolant THERMAL POWER temperature is

501F. or an increase in loop flow i _______________________________

149 3.4-31 Amendment No.

CLINTON

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

APPLICABILITY: 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.

1 49 CLINTON 3.7-13 Amendment No.

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

ML021680369

Text

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