ML18130A037

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Point Beach Nuclear Plant, Units 1 & 2, Submittal of 2017 Update of Final Safety Analysis Report
ML18130A037
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 05/02/2018
From: Craven R
Point Beach
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML18130A031 List:
References
NRC 2018-0016
Download: ML18130A037 (7)
v • d • e


Text

Security Related Information

-Withhold from Public Disclosure Under 10 CFR 2.390 NEXTera ENERGY,& POINT BEACH May 2, 2018 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 NRG 2018-0016 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 of the Point Beach Nuclear Plant Final Safety Analysis Report (FSAR). Enclosure 1 to this letter includes 1 DVD-HOM containing the non-public version of the Point Beach FSAR, including the description of changes. The FSAR 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 enclosure reflects changes since the last periodic update of September 1, 2016. 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 10 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 NRG or prepared pursuant to NRG requirements, and changes made under the provisions of 1 O CFR 50.59. Executed on May 2, 2018. Sincerely, ~:;::;B2C

___ _ Robert Craven Plant General Manager Enclosures (3) cc: Administrator, Region 111, 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 2017 UPDATE OF THE FINAL SAFETY ANALYSIS REPORT NOT FOR PUBLIC DISCLOSURE 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.

~** ENCLOSURE 2 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 2017 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 information as required by 1 O CFR 54.37(b) for the period between July 15, 2016 through March 30, 2018. Regulatory Requirements and Guidance 10 CFR 54.37(b) After the renewed license is issued, the FSAR update required by 10 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, if they 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

  • 1n 2018, 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 2016). This review identified 143 components that would be considered "newly identified" and subject to 10 CFR 54.37(b) reporting requirements.

Of these 143 components, 136 are associated with existing plant components that are now being credited for NFPA-805.

The remaining 7 are components that are now being credited for flood mitigation.

117 of the 143 are Active components, not requiring aging management.

The remaining 26 are passive, long lived components (doors, valves, pumps) are already represented within the aging management tables submitted with the PBNP LRA. These 26 passive, long-lived components have been evaluated and assigned to existing Aging Management Programs as required.

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 tlie 143 newly identified components is not"provided in this document, consistent with the level of detail provided in the LRA. Page 2 of 2 May 2, 2018 Document Control Desk U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08H 4A 11555 Rockville Pike Rockville, MD 20852~2'738 Manual: FSAR Manual No.: . 80 Issue Date: May 2, 2018 1. UFSAR 2017 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. 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 Date ----------------

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