NRC 2019-0032, CFR 50.59 Evaluation and Commitment Change Summary Report
| ML19291A037 | |
| 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 2019-0032 | |
| Download: ML19291A037 (4) | |
Text
October 18, 2019 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 10 CFR 50.59 Evaluation and Commitment Change Summary Report POINT BEACH NRC 2019-0032 10 CFR 50.71(e)
NextEra Energy Point Beach (NextEra), LLC, is submitting the 10 CFR 50.59 Evaluation and Commitment Change Summary Report for the Point Beach Nuclear Plant (PBNP), Units 1 and 2, for January 1, 2018 to October 1, 2019.
Sincerely, NextEra Energy Point Beach, LLC Licensing Manager Eric Schultz Enclosure cc:
Administrator, Region Ill, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Project Manager, Point Beach Nuclear Plant, USNRC NextEra Energy Point Beach, LLC 6610 Nuclear Road, Two Rivers, Wl54241
ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 10 CFR 50.59 & COMMITMENT CHANGE
SUMMARY
REPORT FOR January 1, 2018-OCTOBER 1, 2019 10 CFR 50.59 EVALUATIONS Calculation: EC 289805, Owners Acceptance Review and Incorporation of Corrected Westinghouse Calculations CN-CRA-12-26 and CN-CRA-12-27 Activity
Description:
Owner Acceptance Review and Incorporation of Westinghouse Calculations CN-CRA-12-26 Revision 2 (LOCA Containment Response Analysis), and CN-CFR-12-27 Revision 2 (Steamline Break Containment Response Analysis).
Summary of Evaluation:
The 50.59 evaluated the following:
These analyses provide the inputs to the environmental qualifications of equipment important to safety located inside the containment. The existing qualifications are predicated on temperature history that is exceeded, early in the transient, by these new analytical results.
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Conclusion:==
No activity requiring prior NRC approval per 10 CFR 50.59 was identified and no Technical Specification changes are involved, UFSAR Section 14.2.5 and 14.3.4 were updated to reflect the revised results of the two calculations. [EVAL 2018-003]
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Modification: EC 290522, Replace Units 1 and 2 Narrow Range Resistance Temperature Detectors (RTDs)
Activity
Description:
EC 290522 replaces the Unit 1 and Unit 2 Narrow Range Resistance Temperature Detectors (RTDs) at the Reactor Coolant System (RCS) hot and cold leg bypass manifold.
Summary of Evaluation:
The 50.59 evaluated the following:
The replacement RTDs have a slower response time, which will delay reactor trips actuated by either the OT Delta T or OP Delta T reactor trip functions.
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Conclusion:==
No activity requiring prior NRC approval per 10 CFR 50.59 was identified, and no Technical Speicification change is involved. Updates to UFSAR Section 14.0, 14.1.2, 14.1.9, and 14.2.5 and TRM 2.1 Unit 1 and 2 (COLR) are required due to this modification. [EVAL 2018-004]
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COMMITMENT CHANGE EVALUATIONS Steam Generator Secondary Side Inspections: The original commitment was to perform visual inspections of accessible areas to verify the integrity of steam generator secondary-side components will be performed at least every six effective full power years (EFPY). Indications of degradation or unacceptable conditions are entered into the corrective action program to perform an evaluation and look at extent of condition. Cancelled commitment and replaced with a preventive maintenance strategy for visual inspections of select secondary-side components for potential degradation mechanisms.
Justification for Change: Performance-based preventive maintenance strategy incorporated industry and site-specific operating experience to better schedule monitoring and visual inspections. The scope of components which are monitored or visually inspected in the upper bundle region are restricted to the ones that have potential degradation mechanisms. Apart from visual inspection, diverse monitoring techniques such as scale profiling, deposit mapping and thermal performance monitoring may be utilized to assess the level of tube fouling and flow blockage. The proposed changes align with the technical bases for visual inspections in these areas. (CCE 2019-001)
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