ML19296B472
| ML19296B472 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/18/2019 |
| From: | Craven R Point Beach |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19296B589 | List:
|
| References | |
| NRC 2019-0036 | |
| Download: ML19296B472 (7) | |
Text
Security Related Information - Withhold from Public Disclosure Under 1 O CFR 2.390 1 xTera ENERGY~
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POINT BEACH October 18, 2019 NRC 2019-0036 U.S. Nuclear Regulatory Commission A TIN: 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 of the Point Beach Nuclear Plant Final Safety Analysis Report (FSAR). to this letter includes 1 DVD-ROM 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 May 2, 2018. to this letter includes 1 DVD-ROM containing the public version of the Point Beach FSAR. 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. 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 October 18, 2019.
Sincerely, NextEra Energy Point Beach, LLC
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Robert Craven Site Director 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. 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 2018 UPDATE OF THE FINAL SAFETY ANALYSIS REPORT NOT FOR PUBLIC DISCLOSURE Security Related Information - Withhold Under 10 CFR 2.390. 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 2018 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 10 CFR 54.37(b) for the period between March 30, 2018 through September 12, 2019.
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 (CLB) that meets the following criteria:
The change impacts SSCs that were not in scope for license renewal when the NRC approved the license renewal application.
The SSCs would have been in the scope of license renewal based on the CLB change if 10 CFR 54.4(a) were applied to the SSCs.
(2)
SSCs were installed in the plant at the time of the license renewal review that, in accordance with the CLB at the time, should have been included in the scope of license renewal per 10 CFR 54. 4( a) but were not identified as in scope until after issuance of the renewed license.
SSCs that are plant additions or modifications installed after the renewed license is issued are not subject to the provisions of 10 CFR 54.37(b).
Identification of SSCs under 10 CFR 54.37(b)
The language of 10 CFR 54.37(b) does not limit how or who finds newly identified SSCs. A licensee may identify SSCs that should be within the scope of its license renewal program at any time. The NRC staff may also discover newly identified SSCs. One way to identify these SSCs is through the LR-ISG process.
Newly Identified SSC In 2019, 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 (March 2018).
This review did not identify any additional components that that would be considered "newly identified" and subject to 10 CFR 54.37(b) reporting requirements.
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October 18, 2019 Document Control Desk U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 08H 4A 11555 Rockville Pike Rockville, MD 20852-2738 Manual:
FSAR Manual No.:
80 Issue Date:
October 18, 2019
- 1.
UFSAR 2018 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 ----------------