L-2024-043, 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
March 25, 2024 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 NEXTera ENERGY~
POINT BEACH L-2024-043 10 CFR 54.17 10 CFR 50 Appendix H 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 Attachment I Page 1 of 1 POINT BEACH NUCLEAR PLANT TRM 2.2 TECHNICAL REQUIREMENTS MANUAL PRESSURE TEMPERATURE LIMfTS REPORT TABLE 1-POINT BEACH NUCLEAR PLANT UNIT 1 REACTOR VESSEL SURVEILLANCE CAPSULE REMOVAL SCHEDULE Capsule Identification Letter Approximate Removal Date**
V EOC-1 (Sept 1972) s EOC-3 (Dec 1975)
R EOC-5 (Oct 1977)
T EOC-11 (Mar 1984) p EOC-21 (Apr 1994 - Stored in SFP)
N Standby TABLE i-m POINT BEACH NUCLEAR PLANT UNIT 2 REACTOR VESSEL SURVEILLANCE CAPSULE REMOVAL SCHEDULE Capsule Identification Letter Approximate Removal Date**
V EOC-1 {Nov 1974)
T EOC-3 (Mar 1977)
R EOC-5 (Apr 1979) s EOC-16 (Oct 1990) p EOC-22 (Jun 1997-Stored in SFP)
N Standby
(-,-,-,-,-, ~
~
Supplemental Capsule "An *'"
43 eFP¥ ( Fall ~Qi4)
/
( 51 EFPY (-Spring 2035) A
~
'* During the 13eFiad sf e>EteAdea a13eratian, i:eaetar '.'essel surw*eillaAee ea13sules will be remaved am:I tested iR aeeerdam:e with the sehea1::1le eaAtaiRee in #le mast re£eAtly NRG af)proved gress1::1rizea VVater Reaetar OwAers Gre1:1:p (PV!JROG) Master IRteg:ratea Reaetar Vessel S1:1rveillanee Pmgra.m (MIRl1SP) OeeumeAt. (Ref.
~
u For ca,psul'es that have not been withdrawn yet, the actual dates will be adjusted to coincide with the elasest sehed1:11ed plaAt refuleliA!;J et:Jta~e.
.,.,..,. Supplemental Capsule "A" (also identified as Supplemental Capsule 'W" in some documents) was installed in Cycle ~
- d is described in WCAP-15856_ (Ref 5.17) The i:eme*1al date is 9rovidea iA effeeti\\fe fu'II i;icvNer *,ears (eFPY) as aweeEI bet)*~n #><\\>1~
~n<<t,PlGJP~ '~ ~
~ ----
POINT BEACH TRM 2.2 -
REV.12 9/23/2020