NRC 2013-0082, 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
August28, 2013 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 NEXTera ENERGY.
POINT BEACH NRC 2013-0082 TS 5.5.13 10 CFR 50.71(e)
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
Date of Change 5/21/12 6/4/12 6/28/12 3/26/12 3/26/12 3/26/12 10/10/12 3/26/12 8/27/12 3/26/12 3/26/12 6/28/12 3/26/12 8/27/12 ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 TECHNICAL SPECIFICATIONS BASES CHANGE
SUMMARY
FOR 2012 Affected Affected Section Page(s)
Summary 3.3.1 B 3.3.1-27 Added information regarding the P-9 interlock and its relationship to the condenser steam dumps.
3.3.1 B 3.3.1-27, 28 Moved the P-9 interlock/condenser steam dumps information to the P-9 section.
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.
3.4.5 B 3.4.5-2, 4 The steam generator (SG) level for meeting SR 3.4.5.2 changed from 30% to 35%.
3.4.6 B 3.4.6-4 The SG level for meeting SR 3.4.6.2 changed from 30%
to 35%.
3.4.7 All References to SG level of 30% changed to 35%.
3.5.1 B 3.5.1-6 Removed the words "do not" from in front of "include instrument uncertainty".
3.5.4 B 3.5.4-3, 5 Revisions from the parametric values amendment.
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%
3.6.4 B 3.6.4-2, 3 Revisions from the parametric values amendment.
3.6.5 B 3.6.5-2, 3 Revisions from the parametric values amendment.
3.6.6 B 3.6.6-1 I 3-5, Added information from the FSAR and the alternate 7, 13 source term NRC safety evaluation.
3.6.7 B 3.6.7-2, 4 Revisions from the parametric values amendment.
3.7.3 B 3.7.3 Descriptions changed to match the FSAR.
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Date of Change 7/16/12 Affected Section 3.7.6 Affected Page(s)
B 3.7.6-1, 2, 4
Summary The NRC safety evaluation for the auxiliary feedwater 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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