ML16251A136

Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (FSAR)

ML16251A136
Person / Time
Site:	Point Beach
Issue date:	09/01/2016
From:	Coffey R Point Beach
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML16251A147	List: ML16251A136 ML16251A148 ML16251A149 ML16251A150 ML16251A152 ML16251A153 ML16251A154 ML16251A155 ML16251A156 ML16251A157 ML16251A158 ML16251A161 ML16251A162 ML16251A163 ML16251A165 ML16251A166 ML16251A167 ML16251A168 ML16251A169 ML16251A170 ML16251A171 ML16251A173 NRC 2016-0034, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix T NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (FSAR) NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix B NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix C NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix D NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix I NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Appendix a NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 1 - Introduction and Summary NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 10 - Steam and Power Conversion NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 11 - Waste Disposal Systems and Radiation Protection NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 12 - Conduct of Operations NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 13 - Site Surveillance and Testing Programs (Historical) NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 14 - Safety Analysis NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 15 - Aging Management Programs and Time Limited Aging Analysis NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 2 - Site and Environment NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 3 - Design Basis NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 4 - Reactor Coolant System - Design Basis NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 5 - Containment System Structure NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 6 - Engineered Safety Features NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 7 - Instrumentation and Control NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 8 - Introduction to the Electrical Distribution Systems NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), Chapter 9 - Auxiliary and Emergency Systems NRC 2016-0034, Point Beach Nuclear Plant, Units 1 and 2, Periodic Update of the Final Safety Analysis Report (Fsar), List of Effective Pages
References
NRC 2016-0034
Download: ML16251A136 (7)

Text

September 1, 2016 Document Control Desk U. S. Nµclear Regulatory Commission One White Flint North Mail Stop 08H 4A 11555 Rockville Pike Rockville, MD 20852-2738 Manual: FSAR Manual No.: 80 Issue Date: September 1, 2016 1. UFSAR 2015 Update. AFTER UPDATING YOUR MANUAL, PLEASE SIGN AND RETURN THIS RECEIPT ACKNOWLEDGMENT TO: POINT BEACH NUCLEAR PLANT, DISTRIBUTION CENTER, 6590 NUCLEAR ROAD, TWO RIVERS, WI 54241. Submit PBF..:0095 for any controlled manual changes or cancellations.

If you have any questions, please call Document Control at ext. 7638. ********Special Distribution Notes********

1-Public CD and 1-Non-Public CD Distribution Center -PBNP Security Related Information

-Withhold from Public Disclosure Under 10 CFR 2.390 NEXTera POINT BEACH September 1, 2016 NRC 2016-0034 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 Periodic Update of the Final Safety Analysis Report 10 CFR 50. 71 (e) 10 CFR 54.37(b)

In accordance with the requirements of 10 CFR 50.71 (e) and 10 CFR 54.37(b),

this letter submits a periodic update to the Point Beach Nuclear Plant Final Safety Analysis Report (FSAR). Enclosure 1 to this letter includes 1 DVD-ROM containing the non-public version of the Point Beach FSAR, including the description of changes, in electronic format and is being submitted in its entirety, constituting a total replacement copy. Enclosure 1 contains security related information as defined by 10 CFR 2.390(d) and should be withheld from public disclosure.

The enclosures reflects changes since the last periodic update of September 1, 2015. Enclosure 2 to this letter includes 1 DVD-ROM containing the public version of the Point Beach FSAR. Enclosure 3 to this letter includes a report describing how the effects of aging of newly-identified structures, systems or components (SSCs) will be managed, as required by 1 O CFR 54.37(b).

This letter contains no new Regulatory Commitments and no revisions to existing Regulatory Commitments.

Security Related Information

-Withhold Under 10 CFR 2.390. Enclosure 1 Contains Security Related Information, Upon Separation of Enclosure 1 this letter is Non-Security Related.

NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 Security Related Information

-Withhold from Public Disclosure Under 10 CFR 2.390 Document Control Desk Page 2 I declare under penalty of perjury that this submittal accurately presents changes made since the previous submittal that reflect information and analyses submitted to the NRC or prepared pursuant to NRC requirements, and changes made under the provisions of 10 CFR 50.59. Executed on September 1, 2016. Sincerely, NextEra Energy Point Beach, LLC Site Vice President Enclosures (3) cc: Administrator, Region Ill, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC PSCW (less enclosures)

Security Related Information

-Withhold Under 10 CFR 2.390. Enclosure 1 Contains Security Related Information, Upon Separation of Enclosure 1 this letter is Non-Security Related.

Security Related Information

-Withhold from Public Disclosure Under 10 CFR 2.390 ENCLOSURE 1 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 2015 UPDATE OF THE FINAL SAFETY ANALYSIS REPORT NOT FOR PUBLIC DISCLOSURE Security Related Information

-Withhold Under IO CFR 2.390. Enclosure 1 Contains Security Related Information, Upon Separation of Enclosure 1 this letter is Non-Security Related.

ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 2015 UPDATE OF THE FINAL SAFETY ANALYSIS REPORT REDACTED

-PUBLIC VERSION ENCLOSURE 3 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 REPORT CONSISTENT WITH 10 CFR 54.37(b)

ON HOW EFFECTS OF AGING OF NEWLY-IDENTIFIED STRUCTURES,

SYSTEMS, OR COMPONENTS ARE MANAGED This update follows the guidance regarding the appropriate level of detail for reports under 10 CFR 54.37(b) that is presented in Frequently Asked Questions (FAQs) About License Renewal" Inspection Procedure (IP) 71003, "Post-Approval Site Inspection for License Renewal."

This report provides summary informatfon as required by 10 CFR 54.37(b) forthe period between July 10, 2015 through July 15, 2016. Regulatory Requirements and Guidance 10 CFR 54.37(b)

After the renewed license is issued,,

the FSAR update required by 1 O CFR 50. 71 (e) must include any systems, structures, and components newly identified that would have been subject to an aging management review or evaluation of time-limited aging analysis in accordance with §54.21. This FSAR update must describe how the effects of aging will be managed such that the intended function(s) in §54.4(b) will be effectively maintained during the period of extended operation.

RIS 2007-16, Revision 1 Newly Identified Systems.

Structures.

and Components (SSCs) The intent of 10 CFR 54.37(b) is to capture those SSCs that, ifthey had been identified at the time of the license renewal application, would have been subject to an aging management review or evaluation of TLAAs. In the context of 10 CFR 54.37(b),

newly identified SSCs that should be included in the next FSAR update required by 10 CFR 50. 71 (e) are those SSCs that meet one of the two following conditions:

Page 1 of 2 (1) There is a change to the current licensing basis (GLB) that meets the following criteria:

The change impacts SSGs that were not in scope for license renewal when the NRG approved the license renewal application.

The SSGs would have been in the scope of license renewal based on the GLB change if 10 GFR 54.4(a) were applied to the SSGs. (2) SSGs were installed in the plant at the time of the license renewal review that, in accordance with the GLB at the time, should have been included in the scope of license renewal per 1 O GFR 54. 4( a) but were not identified as in scope until after issuance of the renewed license.

SSGs that are plant additions or modifications installed after the renewed license is issued are not subject to the provisions of 10 GFR 54.37(b).

Identification of SSGs under 10 GFR 54.37(b)

The language of 10 GFR 54.37(b) does not limit how or who finds newly identified SSGs. A licensee may identify SSGs that should be within the scope of its license renewal program at any time. The NRG staff may also discover newly identified SSGs. One way to identify these SSGs is through the LR-ISG process.

Newly Identified SSC In 2016, using the guidance of RIS 2007-16, Rev. 1, PBNP staff reviewed changes to the plant that had taken place since the last 54.37(b) review of the Current Licensing Basis (July 2015). This review identified 21 components that would be considered "newly identified" and subject to 1 O CFR 54.37(b) reporting requirements.

These 21 components are all associated with existing plant components that are now being credited for flood mitigation.

Eight of these 21 are Active components, not requiring aging management.

The remaining 13 passive, long lived components (doors, walls, structural components, valve) are already represented within the aging management tables submitted with the PBNP License Renewal Application (LRA). These 13 passive, long-lived components have been assigned to existing Aging Management programs (Structures Monitoring and One-Time Inspection Programs) and appropriate aging management strategies have been invoked to adequately detect and manage the applicable aging effects throughout the period of extended operation.

A list of the 21 newly identified components is not provided in this document, consistent with the level of detail provided in the LRA. Page 2 of 2