L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules

Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules

ML24087A033
Person / Time
Site:	Point Beach
Issue date:	03/25/2024
From:	Catron S Point Beach
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
L-2024-043
Download: ML24087A033 (1)

Text

NEXTera ENERGY ~

POINT BEACH

March 25, 2024 L-2024-043 10 CFR 54.17 10 CFR 50 Appendix H

U.S. Nuclear Regulatory Commission Attention: Document Control Desk 11545 Rockville Pike One \\Vhite Flint North Rockville, MD 20852-2746

Point Beach Nuclear Plant Units 1 and 2 Dockets 50-266 and 50-301 Renewed License No2. DPR-24 and DPR-27

REVISED REACTOR VESSEL MATERIALS SURVEILLANCE CAPSULE WITHDRAWAL SCHEDULES, POINT BEACH UNIT 1 AND 2

References:

1. NextEra Energy Point Beach, LLC (NEPB) Letter NRC 2020-0032 dated November 16, 2020, Application for Subsequent Renewed Facility Operating Licenses (ADAMS Package Accession No.

ML20329A292)

2. NextEra Energy Point Beach, LLC (NEPB) Letter L-2021-224 dated November 30, 2021, Subsequent License Renewal Application - First Annual Update (ADAMS Package Accession No. ML21334A293)

3. NRC Safety Evaluation Related to the Subsequent License Renewal for Point Beach Nuclear Plant, Units 1 and 2, Revision 1 dated May 25, 2022 (ADAMS Accession No. ML22140A127)

NEPB, owner and licensee for Point Beach Nuclear Plant (PBN) Units 1 and 2, has submitted a subsequent license renewal application (SLRA) for the Facility Operating Licenses for PBN Units 1 and 2 (Reference 1) and the first annual update (Reference 2). Based on the NRC's review of the SLRA, the NRC issued its Safety Evaluation for the SLRA (Reference 3).

The primary reason for this request is to revise the surveillance capsule withdrawal schedule in the Current Licensing Basis (CLB) for the Point Beach Nuclear Plant Unit 2 to that reviewed and found acceptable to the NRC, as documented in Reference 3. Specifically, changing the withdrawal of Capsule 'A' from 43 Effective Full Power Years (EFPY) to the first refueling outage that meets or exceeds 51 EFPY with a projected fluence of 8.07 x 1019 n/cm2 (E>1 MeV) to bound the projected 80-year (72 EFPY) neutron fluence for the PBN Units 1 and 2. In reaching this conclusion of acceptability, the NRC found that to achieve the peak 72 EFPY neutron fluence values identified in the Reactor Pressure Vessel (RPV) embrittlement Time Limited Aging Analysis (TLAAs) for upper-shelf energy (USE), pressurized tl1ermal shock (PTS), adjusted reference temperature (ART), and pressure-temperature P-T limits presented in Reference 1, the revision to the withdrawal schedule will provide data that will bound the 72 EFPY projected neutron fluence for the limiting PBN Unit 1 axial weld and plate material and PBN Units 1 and 2 circumferential welds.

NextEra Energy Point Beach, LLC

661 O Nuclear Road, Two Rivers, WI 54241 Document Control Desk Docket 50-301 L-2024-043 I Page 2

Upon approval, PBN will make the appropriate changes to the Technical Requirements Manual Section 2.2, Table 2, as shown in the attached sheet.

There have been no changes since the issuance of References 1 or 2 that would impact the analysis and conclusion that the NRC performed.

Should you have any questions regarding this submittal, please contact Kenneth Mack at (561) 904-3635 or Kenneth.Mack2@fpl.com.

Steve Catron Llcensing and egulatory Compliance Director - Nuclear Fleet NextEra Energy Point Beach

Attachment (1)

Cc: Administrator, Region III, USNRC Project Manager, Point Beach Nuclear Plant, USNRC Resident Inspector, Point Beach Nuclear Plant, USNRC Public Service Commission \\Visconsin L-2024-043 Atta chment I Page 1 of 1

POI NT B EACH NUCLEAR PLANT TRM 2.2 TECHN I CAL REQUIR EMENT S MANUAL

PRESSURE TEMP ERATUR E LIMfTS REPOR T

TABLE 1-POI NT BEACH N U CLEAR PLANT U NIT 1 REACTOR VESSEL SURVE ILLANCE CAPSULE REMOVA L SCHEDULE

Capsule Identification L etter Approximate Removal Date **

V EOC-1 (Sept 1972 )

s EOC-3 (Dec 1 975 )

R EOC-5 (Oc t 1977 )

T EOC-11 ( Mar 1984) p EOC -21 (Apr 1994 - Stored in SFP)

N Standby

TABLE i-m PO INT BEACH N U CLEAR PLANT UN IT 2 REACTOR VESSEL SU RVEI LLANCE CAPSULE REMOVA L SCHEDU LE

Capsule Ident ification Letter Approximate R emoval Date**

V EOC-1 {Nov 1974)

T EOC-3 (Mar 1977 )

R E OC-5 (Apr 1979) s EOC-16 ( Oct 1990 )

p EOC-22 (J u n 1997-Stored in SFP )

N Standb y (-,-,-,-,-, ~ ~

Supple m ental Capsu le "A n *'" 43 eFP¥ ( Fall ~Qi4) /...... ( 5 1 EFPY (-Spring 2035 ) A

~

'* Du ring the 13eFiad sf e>EteAdea a13eratian, i:eaetar '.'essel surw*eillaAee ea13su les will be remaved am:I tested iR aeeerdam:e with the sehea 1::1le eaAtaiRee in #le mast re£eAtly NRG af)prove d gress1::1rizea VVater Reaeta r OwA ers Gre1:1:p (PV!JROG ) Master IRteg:ratea Reaetar Vessel S1:1rveillanee Pmgra.m (MIRl1SP) Oeeum eAt. (Re f.

~

u For ca,ps u l'es that h ave not b een withdrawn ye t, the ac tua l dates will be adjusted to coincide with the elasest sehed1:11ed plaAt refuleliA!;J et:Jta~e.

.,.,..,. Supp lementa l Ca psu le "A" (a lso identified as Su pplementa l Capsu le 'W" in some docume n ts) was install1 ed in Cycle ~ - d is desc ribed in W CAP-15856 _ (Re f 5.17) The i:eme*1al date is 9rov idea iA effeeti\\fe fu'II i;icvNer *,ears (eFPY) as awe eEI bet)*~n #><\\>~ ~ n<<t,PlGJP~ '~ ~ ~ ----

POINT BEACH TR M 2.2 - REV.1 2 9/23/2020