NRC 2019-0037, Technical Specification Bases Change Summary
| ML19291A039 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/18/2019 |
| From: | Schultz E Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NRC 2019-0037 | |
| Download: ML19291A039 (2) | |
Text
October 18, 2019 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 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 ENERGY POINT BEACH NRC 2019-0037 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 TS Bases without prior NRC approval.
The enclosure contains the TS Bases change summary for the period April 1, 2018, through October 1, 2019. NextEra previously submitted the TS Bases change summary for January 1, 2016, through March 31,2018 on May 2, 2018.
This letter contains no new commitments and no revisions to existing commitments.
If you have any questions or require additional information, please contact me at (920) 755-7854.
Sincerely, NextEra Energy Point Beach, LLC Eric Schultz 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, Wl54241
Affected Section 3.1.7 3.6.4 3.7.1 3.7.7 3.8.6 3.7.7 3.8.9 ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 TECHNICAL SPECIFICATION (TS) BASES CHANGE
SUMMARY
FOR April 1, 2018 - October 1, 2019 Date of Affected Change Page(s)
Summary Clarified the control room readouts, correct the April2018 B 3.1.7-2 wording from transmitter to transformer, corrected various editorial changes to make the paragraph grammatically correct September B 3.6.4-1 Corrected errors in the LOCA and steam line break 2018 containment response analyses Replaced ASME OM Code, Appendix I, lnservice Testing of Pressure Relief Devices in Light Water November B 3.7.1-6 Reactor Power Plants with ASME OM Code Case 2018 OMN-17, Alternative Rules for Testing ASME Class 1 Pressure Relief/Safety Valves [and PWR Main Steam Safety Valves].
November B 3.7.7-2 Added a new paragraph to describe the new 2018 component cooling water cross-connects The changes to TSB 3.8.1 were made to align with surveillance frequency change. Surveillance November B 3.8.6-2 Requirement (SR) 3.8.6 was changed from every 7 2018 days to every 31 days. The Surveillance Test Interval change is controlled by TS 5.5.19 Surveillance Frequency Control Program.
April2019 B 3.7.7-1 Removed blowdown evaporator from the background section. The blowdown evaporator was abandoned.
August B 3.8.9-7 Corrected the amendment numbers in the footer of 2019 page 7.
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