ML043580006

Tech Specs - Issuance of Amendment Deletion of Requirements for Submittal of Occupational Radiation Exposure Reports, Reports of Challenges to and Failures of the Pressurizer Power Operated Relief Valves and Safety

ML043580006
Person / Time
Site:	Kewaunee
Issue date:	12/22/2004
From:	NRC/NRR/DLPM
To:
Lyon C, NRR/DLPM, 415-2296
References
TAC MC4621
Download: ML043580006 (2)

Text

B. Deleted.

C. Deleted.

D. This report shall document the results of specific activity analysis in which the reactor coolant exceeded the limits of TS 3.1.c.1.A during the past year. The following Information shall be Included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample In which the limit was exceeded.

(2) Results of the last Isotopic analysls for radiolodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.

Each result should indude date and time of sampling and the radiolodine concentrations.

(3) Clean-up system flow history starting 4B hours prior to the first sample In which the limit was exceeded.

(4) Graph of the 1-131 concentration and one other radioiodine Isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level.

(5) The time duration when the specific activity of the reactor coolant exceeded the radiolodine limit.

X Deleted

' Deleted.

TS 6.9-2 Amendment lb. 179

3. Deleted. I

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) TS 2.1 Reactor Core Safety Limit (2) TS 2.3.a.3.A Overtemperature AT Setpoint (3) TS 2.3.a.3.B Overpower AT Setpoint (4) TS 3.1.f.3 Moderator Temperature Coefficient (MTC)

(5) TS 3.B.a.5 Refueling Boron Concentration (6) TS 3.10.a Shutdown Margin (7) TS 3.10.b.1.A Fa N,iZ)Limits (8) TS 3.10.b.1.B FLimits (9) TS 3.1 0.b.4 Fo0 0 (Z) Limits (10) TS 3.10.b.5.C.i Fo (Z) penalty (1 1) TS 3.1 0.b.9 Axial Flux Difference Target Band (12) TS 3.10.b.11.A Axial Flux Difference Envelope (13) TS 3.10.d.1 Shutdown Bank Insertion Limits (14) TS 3.10.d.2 Control Bank Insertion Limits (15) TS 3.10.k Core Average Temperature (16) TS 3.10.1 Reactor Coolant System Pressure (17) TS 3.10.m.1 Reactor Coolant Flow B. The analytical methods used to determine the core operating limits shall be Ihose 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.

TS 6.9-3 Amendment No. 179