ML070680350

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License and Technical Specification Pages - Amendment No. 182 Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
ML070680350
Person / Time
Site: Callaway Ameren icon.png
Issue date: 03/21/2007
From: Donohew J
NRC/NRR/ADRO/DORL/LPLIV
To:
Donohew J N, NRR/DORL/LP4, 415-1307
Shared Package
ML070470147 List:
References
TAC MD2362
Download: ML070680350 (7)
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Text

(4) U E, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source of special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) UE, 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 UE is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100% power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan*

The Technical Specifications contained in Appendix A, as revised through Amendment No. 182 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Environmental Qualification (Section 3.11. SSER #3) **

Deleted per Amendment No. 169 Amendments 133, 134, &135 were effective as of April 30, 2000 however these amendments were implemented on April 1, 2000.

The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report and/or its supplements wherein the license condition is discussed.

Amendment 182

Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 The Digital Rod Position Indication (DRPI) System and the Demand Position Indication System shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each inoperable rod position indicator and each demand position indicator.

COMPLETION CONDITION REQUIRED ACTION TIME TIME A. One DRPI per group A.1 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable for one or more rods with inoperable groups. position indicators indirectly by using core power distribution measurement information.

OR A.2 Reduce THERMAL 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to

(continued)

CALLAWAY PLANT 3.1-16 Amendment No. 182

Rod Position Indication 3.1.7 ACTIONS (continued)

COMPLETION REQUIRED ACTION TIME CONDITION TIME B. More than one DRPI per B.1 Place the control rods Immediately group inoperable for one or under manual control.

more groups.

AND B.2 Monitor and record RCS Once per 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Tavg.

AND B.3 Verify the position of the Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> rods with inoperable position indicators indirectly by using core power distribution' measurement information.

AND B.4 Restore inoperable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> position indicators to OPERABLE status such that a maximum of one DRPI per group is inoperable.

C. One or more rods with C.1 Verify the position of the 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable DRPIs have rods with inoperable been moved in excess of 24 position indicators steps in one direction since indirectly by using core the last determination of the power distribution rod's position. measurement information.

OR C.2 Reduce THERMAL 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> POWER to _ 50% RTP.

(continued)

CALLAWAY PLANT 3.1-17 Amendment No. 182

FQ(Z) (FQ Methodology) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.1.2 NUll------------------------------

If Fc(Z) measurements indicate z FZ)]

maximum over has increased since the previous evaluation of F&(Z)

a. Increase F '(Z) by the appropriate factor specified in the COLR and reverify Fw(Z) is within limits; or
b. Repeat SR 3.2.1.2 once per 7 EFPD until two successive power distribution measurements I indicate

[FF(Z)]

K(Z) J maximum over z has not increased.

Verify Fw(Z) is within limit Once after each refueling prior to THERMAL POWER exceeding 75%

RTP AND (continued)

CALLAWAY PLANT 3.2-4 Amendment No. 182

QPTR 3.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 ----------------------- NOTE ---------------

1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER

< 75% RTR the remaining three power range channels can be used for calculating QPTR.

2. SR 3.2.4.2 may be performed in lieu of this Surveillance.

Verify QPTR is within limit by calculation. 7 days SR 3.2.4.2 ---------- ----- NOTE ---------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after input from one or more Power Range Neutron Flux channels are inoperable with THERMAL POWER

> 75% RTP.

Verify QPTR is within limit using power distribution 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> measurement information. I CALLAWAY PLANT 3.2-13 Amendment No. 182

RTS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS I............------------- NOTE-------------------------------

Refer to Table 3.3.1 1 to determine which SRs apply for each RTS Function.

SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.1.2 ----------------------- NOTE ----------------

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is > 15% RTP.

Compare results of calorimetric heat balance 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> calculation to power range channel output. Adjust power range channel output if calorimetric heat balance calculation results exceed power range channel output by more than +2% RTP.

SR 3.3.1.3 ------------------ NOTE ---------------

Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after THERMAL POWER is > 50% RTP.

Compare results of incore power distribution 31 effective full I measurements to Nuclear Instrumentation System power days (NIS) AFD. Adjust NIS channel if absolute difference (EFPD) is Ž 2%.

(continued)

CALLAWAY PLANT 3.3-12 Amendment No. 182

RTS Instrumentation 3.3.1 SURVEILLANCE FREQUENCY SR 3.3.1.4 ----------------------- NOTE ---------------

This Surveillance must be performed on the reactor trip bypass breaker for the local manual shunt trip only prior to placing the bypass breaker in service.

Perform TADOT. 62 days on a STAGGERED TEST BASIS SR 3.3.1.5 Perform ACTUATION LOGIC TEST. 92 days on a STAGGERED TEST BASIS SR 3.3.1.6 ----------------------- NOTE ---------------

Not required to be performed until 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after achieving equilibrium conditions with THERMAL POWER > 75 % RTP.

Calibrate excore channels to agree with incore power 92 EFPD distribution measurements. I SR 3.3.1.7 ----------------------- NOTE ---------------

1. Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entry into MODE 3.
2. Source range instrumentation shall include verification that interlocks P-6 and P-10 are in their required state for existing unit conditions.

Perform COT. 184 days (continued)

CALLAWAY PLANT 3.3-13 Amendment No. 182

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