ML050470191

Tech Spec Pages for Amendment 180 Administrative Changes to Technical Specifications

ML050470191
Person / Time
Site:	Kewaunee
Issue date:	02/15/2005
From:	NRC/NRR/DLPM
To:
Lyon C, NRR/DLPM, 415-1292
Shared Package
ML050460402	List: ML050470191
References
TAC MC4957
Download: ML050470191 (2)

Text

g.

Inoperable Rod Limitations

1. An inoperable rod is a rod which does not trip or which is declared inoperable under TS 3.10.e orTS 3.10.h.

2. Not more than one inoperable full length rod shall be allowed at any time.

3. If reactor operation is continued with one inoperable full length rod, the potential ejected rod worth and associated transient power distribution peaking factors shall be determined by analysis within 30 days unless the rod is made OPERABLE earlier. The analysis shall include due allowance for nonuniform fuel depletion in the neighborhood of the inoperable rod. If the analysis results in a more limiting hypothetical transient than the cases reported in the safety analysis, the plant power level shall be reduced to an analytically determined part power level which is consistent with the safety analysis.

h.

Rod Drop Time At OPERATING temperature and full flow, the drop time of each full length rod cluster control shall be no greater than 1.8 seconds from loss of stationary gripper coil voltage to dashpot entry. If drop time is > 1.8 seconds, the rod shall be declared inoperable.

i.

Rod Position Deviation Monitor If the rod position deviation monitor Is inoperable, individual rod positions shall be logged at least once per eight hours and after a load change> 10% of rated power or after> 24 steps of control rod motion.

j.

Quadrant Power Tilt Monitor If one or both of the quadrant power tilt monitors is inoperable, individual upper and lower excore detector calibrated outputs and the quadrant tilt shall be logged once per shift and after a load change > 10% of rated power or after > 24 steps of control rod motion. The monitors shall be set to alarm at 2% tilt ratio.

k.

Core Average Temperature During steady-state power operation, Tave shall be maintained within the limits specified in the COLR, except as provided byTS 3.10.n.

I.

Reactor Coolant System Pressure During steady-state power operation, Reactor Coolant System pressure shall be maintained within the limits specified in the COLR, except as provided byTS 3.10.n.

Amendment No. 180 TS 3.10-6

I

3. Deleted.

4. Core Operating Limits Report (COLR)

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

(1)

(2)

(3)

(4)

(5)

(6)

(7)

(8)

(9)

(10)

(11)

(12)

(13)

(14)

(15)

(16)

(17)

TS 2.1 TS 2.3.a.3.A TS 2.3.a.3.B TS 3.1.f.3 TS 3.8.a.5 TS 3.10.a TS 3.10.b.1.A TS 3.10.b.1.B TS 3.10.b.5 TS 3.10.b.6.C.i TS 3.10.b.8 TS 3.10.b.8.A TS 3.10.d.1 TS 3.10.d.2 TS 3.10.k TS 3.10.1 TS 3.10.m.1 Reactor Core Safety Limit Overtemperature AT Setpoint Overpower AT Setpoint Moderator Temperature Coefficient (MTC)

Refueling Boron Concentration Shutdown Margin FoNzZ) Limits Limits F0 °(Z) Limits F0 (Z) penalty Axial Flux Difference Target Band Axial Flux Difference Envelope Shutdown Bank Insertion Limits Control Bank Insertion Limits Core Average Temperature Reactor Coolant System Pressure Reactor Coolant Flow B. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. When an initial assumed power level of 102% of the original rated power is specified in a previously approved method, 100.6% of uprated power may be used only when the main feedwater flow measurement (used as the input for reactor thermal output) is provided by the Crossflow ultrasonic flow measurement system (Crossflow system) as described in report (15) listed below. When main feedwater flow measurements from the Crossflow System are unavailable, a power measurement uncertainty consistent with the instrumentation used shall be applied.

Future revisions of approved analytical methods listed in this Technical Specification that currently reference the original Appendix K uncertainty of 102% of the original rated power should include the condition given above allowing use of 100.6% of uprated power in the safety analysis methodology when the Crossflow system is used for main feedwater flow measurement.

Amendment No. 180 TS 6.9-3