NRC 2013-0082, Technical Specification Bases Change Summary

Technical Specification Bases Change Summary

ML13241A198
Person / Time
Site:	Point Beach
Issue date:	08/28/2013
From:	Millen M Point Beach
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NRC 2013-0082
Download: ML13241A198 (3)

Text

NEXTera ENERGY.

POINT BEACH August28, 2013 NRC 2013-0082 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 1 and 2 Dockets 50-266 and 50-301 Renewed License Nos. DPR-24 and DPR-27 Technical Specification Bases Change Summary In accordance with the requirements of Technical Specification (TS) 5.5.13 and 10 CFR 50.71(e), NextEra Energy Point Beach, LLC (NextEra), is submitting a summary of changes made to the Point Beach Nuclear Plant (PBNP) TS Bases.

The enclosure contains the TS Bases change summary for the period January 1, 2012, through December 31, 2012. NextEra previously submitted the TS Bases change summary for January 1, 2011, through December 31,2011 , on June 12,2012 (ML12165A251).

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

If you have questions or require additional information, please contact Michael Millen at 920/755-7845.

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

ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 TECHNICAL SPECIFICATIONS BASES CHANGE

SUMMARY

FOR 2012 Date of Affected Affected Change Section Page(s) Summary 5/21/12 3.3.1 B 3.3.1-27 Added information regarding the P-9 interlock and its relationship to the condenser steam dumps.

6/4/12 3.3.1 B 3.3.1-27, 28 Moved the P-9 interlock/condenser steam dumps information to the P-9 section.

6/28/12 3.3.2 B 3.3.2-14 Spray pump suction is shifted at a predetermined RWST level to the containment sump vice the low-low level setpoint.

3/26/12 3.4.5 B 3.4 .5-2, 4 The steam generator (SG) level for meeting SR 3.4.5.2 changed from 30% to 35%.

3/26/12 3.4.6 B 3.4.6-4 The SG level for meeting SR 3.4.6.2 changed from 30%

to 35%.

3/26/12 3.4.7 All References to SG level of 30% changed to 35%.

10/10/12 3.5.1 B 3.5 .1-6 Removed the words "do not" from in front of "include instrument uncertainty".

3/26/12 3.5.4 B 3.5.4-3, 5 Revisions from the parametric values amendment.

8/27/12 3.6.2 B 3.6.2-2, 7 Changed reference 1 from 10 CFR 50, App J, Option B to Technical Specification 1.1. Changed La from 0.4%

to 0.2%

3/26/12 3.6.4 B 3.6.4-2, 3 Revisions from the parametric values amendment.

3/26/12 3.6.5 B 3.6.5-2, 3 Revisions from the parametric values amendment.

6/28/12 3.6.6 B 3.6.6-1 3-5, I Added information from the FSAR and the alternate 7, 13 source term NRC safety evaluation.

3/26/12 3.6.7 B 3.6.7-2, 4 Revisions from the parametric values amendment.

8/27/12 3.7.3 B 3.7.3 Descriptions changed to match the FSAR.

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Date of Affected Affected Change Section Page(s) Summary 7/16/12 3.7.6 B 3.7.6-1, 2, The NRC safety evaluation for the auxiliary feedwater 4 system modifications dated March 25, 2011 replaced the 1990 NRC safety evaluation of the Point Beach response to station blackout rule as a reference.

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