NRC 2009-0062, Technical Specification Bases Change Summary

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Technical Specification Bases Change Summary
ML091770612
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 06/25/2009
From: Jim Costedio
Nextera Energy
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC 2009-0062
Download: ML091770612 (2)


Text

June 25,2009 NRC 2009-0062 TS 5.5.13 10 CFR 50.71(e)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Point Beach Nuclear Plant, Units Iand 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Technical Specification Bases Change Summarv In accordance with the requirements of Technical Specification 5.5.1 3 and 10 CFR 50.71(e),

NextEra Energy Point Beach, LLC, is submitting a summary of changes made to the Point Beach Nuclear Plant (PBNP) Technical Specification Bases.

Enclosure Icontains the Technical Specification (TS) Bases change summary for the period July I, 2008, through December 31,2008. NextEra previously submitted the TS Bases change summary for January I, 2008, through June 30,2008, on June 27,2008 (ML081820650).

This letter contains no new commitments and no revisions to existing commitments.

If you have questions or require additional information, please contact me at 9201755-7427.

Very truly yours, NextEra Energy Point Beach, LLC Licensing Manager Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241

ENCLOSURE I NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS I AND 2 TECHNICAL SPECIFICATIONS BASES CHANGE

SUMMARY

Date of Affected Affected Summary Change Section Page(s) 07/18/08 B 3.3.3 . B 3.3.3-6 Changed last paragraph to clarify that the Containment Wide Range Pressure indication is a Regulatory Guide I.97 Type B variable.

08/05/08 B 3.4.1 B 3.4.1-1 Changed fifth paragraph to clarify that the RCS flow rate is determined by a precision calorimetric, and not by flow rate averaging, for comparison to the DNBR limit.

B 3.4.1-3 Changed second paragraph under ACTIONS to clarify that the calorimetric RCS total flow rate, not the indicated RCS flow rate, determines whether power must be reduced, etc.

08/06/08 B 3.4.1 6 B 3.4.1 6-1 Incorporates TSTF 490, Deletion of E-Bar definition and through Revision to Reactor Coolan't System Specific Activity, per B 3.4.16-5 Amendments 2331238. Replaced the limits on primary coolant gross activity with limits on primary coolant noble gas activity. Replaced the figure of primary coolant iodine concentration as a function of reactor power with a single value applicable to any power level.

10/03/08 B 3.4.2 B 3.4.2-2 Corrected reference to special test exception in second paragraph of APPLICABILITY section from LC0 3.1 -9, Mode 2 Physics Test Exceptions, to LC0 3.1.8, Physics Tests Exceptions - MODE 2.

10115/08 B 3.8.7 B 3.8.7-4 Added second and third paragraphs under SURVEILLANCE REQUIREMENTS to clarify that the inverters are within industry standards, regulate voltage within a narrow range that does not vary significantly between normal and accident conditions, and the design features and alarms ensure that the inverter frequency is maintained within desirable limits.

1Ill7/08 B 3.4.3 B 3.4.3-7 Changed Reference Ifrom Wisconsin Electric Calculation 2000-0001, Revision 0, P-T and LTOP Setpoints, to Technical Requirements Manual, TRM 2.2, Pressure Temperature Limits Report.

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