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Category:E-Mail
MONTHYEARML23271A1542023-09-28028 September 2023 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23208A3072023-07-27027 July 2023 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of Relief Requests Regarding I6-RR-1, I6-RR-2, and I6-RR-3 (EPIDs L-2023-LLR-0030, L-2023-LLR-0031, L-2023-LLR-0032) ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23136A2782023-05-0505 May 2023 Email to R Coffey Point Beach SLRA Second Annual Update - Request for Additional Information Set 1 ML23122A0132023-05-0101 May 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding Risk-Informed Approach to Address GSI-191 ML23109A1862023-04-19019 April 2023 and Turkey Point Acceptance of Requested Licensing Action Proposed Alternative to Asme Section XI Authorizing Implementation of Asme Code Case N-752-1 ML23033A0292023-01-31031 January 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI (Volume 2) - License Amendment Request Regarding TSTS-505 ML22354A1612022-12-20020 December 2022 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding TSTS-505 ML22291A3692022-10-18018 October 2022 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment Request to Use Beacon Power Distribution Monitoring System ML22249A0052022-09-0202 September 2022 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of License Amendment and Exemptions Regarding Risk-Informed Approach to Address GSI-191 ML22229A1052022-08-17017 August 2022 Response to Questions Regarding Point Beach Nuclear Power Plant with Attachment ML22229A1022022-07-18018 July 2022 Original Request - Questions Regarding Point Beach Nuclear Power Plant ML22196A0062022-07-15015 July 2022 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of Requested Licensing Action TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4b ML22094A0802022-04-0404 April 2022 NRR E-mail Capture - Point Beach Nuclear Plant, Units 1 and 2 - Acceptance of Requested Licensing Action License Amendment Request to Adopt TSTF-366 ML22006A2762022-01-0606 January 2022 SLR - FW: Subsequent License Renewal of Point Beach Nuclear Plant Unit Numbers 1 and 2, Manitowoc County, Wisconsin ML22006A1952022-01-0606 January 2022 SLR - FW: (External_Sender) 3 Additional Organizations Endorsing the Coalition (Now 50 Organizations, and 27 Individuals) Public Comments NRCs Dsgeis on NextEra Point Beach Nuclear Power Plant Subsequent License Renewal, D ML22006A2012022-01-0606 January 2022 SLR - FW: Comments of Michael J Keegan on Dseis Point Beach ML22004A1672022-01-0404 January 2022 SLR - Ref: Point Beach ML22004A3192022-01-0404 January 2022 SLR - FW: Point Beach ML22004A0012022-01-0404 January 2022 SLR - FW: Comments of Michael J Keegan on Dseis Point Beach ML22006A1942022-01-0404 January 2022 SLR - (External_Sender) 3 Additional Organizations Endorsing the Coalition (Now 50 Organizations, and 27 Individuals) Public Comments NRCs Dsgeis on NextEra Point Beach Nuclear Power Plant Subsequent License Renewal, Docke ML22004A3212022-01-0404 January 2022 SLR - FW: Comments of Michael J Keegan on Dseis Point Beach ML22004A3202022-01-0404 January 2022 SLR - FW: (External_Sender) 3 Additional Organizations Endorsing the Coalition (Now 50 Organizations, and 27 Individuals) Public Comments NRCs Dsgeis on NextEra Point Beach Nuclear Power Plant Subsequent License Renewal, D ML22004A1732022-01-0404 January 2022 SLR - FW: (External_Sender) 3 Additional Organizations Endorsing the Coalition (Now 50 Organizations, and 27 Individuals) Public Comments NRCs Dsgeis on NextEra Point Beach Nuclear Power Plant Subsequent License Renewal, D ML22004A3182022-01-0404 January 2022 SLR - FW: EPA Comment Letter - Point Beach SEIS ML22006A1992022-01-0303 January 2022 SLR - (External_Sender) Comments of Michael J Keegan on Dseis Point Beach ML22004A3172021-12-21021 December 2021 SLR - (External_Sender) EPA Comment Letter - Point Beach SEIS ML21362A6822021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final Email ML21362A6712021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final Email ML22006A2752021-12-0202 December 2021 SLR - (External_Sender) Subsequent License Renewal of Point Beach Nuclear Plant Unit Numbers 1 and 2, Manitowoc County, Wisconsin ML21341A6102021-11-16016 November 2021 SLRA Safety RAI Set 12 Final Email ML21314A4212021-11-10010 November 2021 Fws to NRC, Concurrence with ESA Determination for Point Beach Subsequent License Renewal ML21307A1522021-11-0909 November 2021 NRC to Fws, Request for Concurrence with Endangered Species Act Determinations for Point Beach Subsequent License Renewal ML21287A0852021-10-14014 October 2021 SLRA Safety RAI Set 11 Final Email ML21279A1202021-10-0505 October 2021 Email: Wi Shpo Review Point Beach Nuclear Plant SLR ML21286A6032021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final Email ML21273A0232021-09-0202 September 2021 SLRA Safety RAI Set 9 Final Email ML21242A2282021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 ML21242A2292021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 Email ML21242A2462021-08-26026 August 2021 SLRA Safety RAIs Set 8 Final Email ML21242A2222021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 ML21242A2232021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 Email ML21242A2192021-08-20020 August 2021 SLRA Safety RAI Set 7 Final Email ML21242A2132021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft Email ML21242A2142021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft ML21242A2042021-08-12012 August 2021 SLRA Safety RAIs Set 5 Final Email ML21224A2042021-08-12012 August 2021 LTR-21-0225-1-RIII. Time Sensitive: Request for Further Inspection ML21242A0142021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final Email ML21242A2382021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final Email ML21242A0112021-08-0909 August 2021 SLRA Draft Safety RAIs Set 6 Email 2023-09-28
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 ML23136A2802023-05-0505 May 2023 SLRA Second Annual Update RAI Set 1 ML23122A0132023-05-0101 May 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding Risk-Informed Approach to Address GSI-191 ML23033A0292023-01-31031 January 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI (Volume 2) - License Amendment Request Regarding TSTS-505 ML23003A8022023-01-0303 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22354A1612022-12-20020 December 2022 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding TSTS-505 ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22266A0872022-09-23023 September 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22172A1192022-06-27027 June 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-505 Provide Risk Informed Extended Complete Times - RITSTF Initiative 4B ML22130A5712022-05-12012 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML22041B0752022-02-10010 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000266/2022002 ML21362A6812021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final ML21362A6822021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final Email ML21362A6712021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final Email ML21362A6702021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final ML21287A0852021-10-14014 October 2021 SLRA Safety RAI Set 11 Final Email ML21286A6032021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final Email ML21286A6042021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final ML21287A0862021-09-29029 September 2021 SLRA Safety RAI Set 11 Final ML21273A0222021-09-29029 September 2021 SLRA Safety RAI Set 9 Final ML21253A1672021-09-10010 September 2021 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information Inspection Report 05000266/2022010 05000301/2022010 ML21242A2282021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 ML21242A2292021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 Email ML21242A2472021-08-26026 August 2021 SLRA Safety RAIs Set 8 Final ML21242A2232021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 Email ML21242A2222021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 ML21242A2192021-08-20020 August 2021 SLRA Safety RAI Set 7 Final Email ML21242A2202021-08-20020 August 2021 SLRA Safety RAI Set 7 Final ML21242A2132021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft Email ML21242A2142021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft ML21242A2032021-08-12012 August 2021 Srla Safety RAIs Set 5 Final ML21242A2382021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final Email ML21242A2392021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A2042021-08-12012 August 2021 SLRA Safety RAIs Set 5 Final Email ML21242A0152021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A0122021-08-0909 August 2021 SLRA Draft Safety RAIs Set 6 ML21242A1992021-08-0505 August 2021 Srla Draft Safety RAIs Set 5 ML21242A2002021-08-0505 August 2021 SLRA Draft Safety RAIs Set 5 Email ML21285A1212021-08-0505 August 2021 SLRA Public Meeting Discussion Questions August 5 2021 ML21238A2332021-08-0404 August 2021 SLRA Safety RAI Set 4 Final ML21238A2322021-08-0404 August 2021 SLRA Safety RAI Set 4 Final Email ML21237A0062021-08-0202 August 2021 SLRA Draft Safety RAIs Set 4 ML21214A0842021-07-27027 July 2021 SLRA Safety RAIs Set 3 Final ML21208A1892021-07-27027 July 2021 SLRA Safety RAIs Set 2 Final ML21172A2382021-07-21021 July 2021 (Pbn) Subsequent License Renewal Application (SLRA) Draft Requests for Additional Information (Rais) Safety - Set 2 ML21214A0722021-07-20020 July 2021 Subsequent License Renewal Application Draft Safety RAIs Set 3 ML21161A1192021-06-10010 June 2021 RAIs Set 1 Final Aging Management of Irradiated Concrete and Steel Reactor Vessel Supports Final ML21134A0582021-05-14014 May 2021 Final Request for Additional Information and Requests for Confirmation of Information - Point Beach SLRA Environmental Review (EPID No. L-2020-SLE-0002) - Email 2024-01-30
[Table view] |
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POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 (PBN)
SUBSEQUENT LICENSE RENEWAL APPLICATION (SLRA)
DRAFT REQUEST FOR ADDITIONAL INFORMATION (RAI)
SAFETY - SET 7 SLRA Section 4.7.2, Leak-Before-Break of Reactor Coolant System Auxiliary Piping DRAI 4.7.2-1 Regulatory Basis:
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Section 54.21(c), the SLRA shall include an evaluation of time-limited aging analyses (TLAAs). The applicant shall demonstrate that (i) the analyses remain valid for the subsequent period of extended operation; (ii) the analyses have been projected to the end of the subsequent period of extended operation; or (iii) the effects of aging on the intended function(s) will be adequately managed for the subsequent period of extended operation.
Background:
SLRA Section 4.7.2, Leak-Before-Break [LBB] of Reactor Coolant System Auxiliary Piping, identifies the potential for thermal aging of the auxiliary line piping components and fatigue crack growth as the aging effects that must be addressed for subsequent license renewal (SLR). SLRA Section 4.7.2 states that thermal aging of the stainless steel weld material was considered in the evaluations of the pressurizer surge line, the residual heat removal (RHR) system, and the accumulator line (see WCAP-15065-P-A, Revision 1, Technical Justification for Eliminating Pressurizer Surge Line Rupture as the Structural Design Basis for Point Beach Units 1 and 2 Nuclear Plants, June 2001; WCAP-15105-P-A, Revision 1, Technical Justification for Eliminating Residual Heat Removal (RHR) Rupture as the Structural Design Basis for Point Beach Units 1 and 2 Nuclear Plants, June 2001; and WCAP-15107-P-A, Revision 1, Technical Justification for Eliminating Accumulator Rupture as the Structural Design Basis for Point Beach Units 1 and 2 Nuclear Plants, June 2001) by assuming saturated conditions (fully aged).
In addition, SLRA Section 4.7.1, Leak-Before-Break of Reactor Coolant System Loop Piping, and WCAP-14439-P, Revision 4, Technical Justification for Eliminating Large Primary Loop Pipe Rupture as the Structural Design Basis for the Point Beach Nuclear Plant Units 1 and 2 for the Subsequent License Renewal Program (80 Years), June 2020, address thermal aging effects on the cast austenitic stainless steel components for the LBB analyses of the Point Beach reactor coolant loop piping.
Issue:
SLRA Enclosure 4, Attachment 17, Westinghouse LTR-SDA-II-20-06, Revision 1, Leak-Before-Break Reconciliation of the Point Beach Units 1 and 2 Pressurizer Surge Line, Residual Heat Removal Line, and Accumulator Line Piping Systems for the Subsequent License Renewal Program, May 4, 2020, does not discuss the disposition of thermal aging of the stainless steel welds as described in SLRA Section 4.7.2 and does not provide a basis for that disposition in the SLRA.
In addition, the equation used to implement the assumption of saturated conditions (fully aged) in the calculations is Eq. 3
= 73.4 + 83.5 ()0.643 2
in NUREG/CR-6428, Effects of Thermal Aging on Fracture Toughness and Charpy-Impact Strength of Stainless Steel Pipe Welds, May 1996 (Revision 0), which is described as the lower-bound J-R curve for both SAWs [submerged arc welds] and SMAWs [shielded metal arc welds]. A more recent report, NUREG/CR-6428, Revision 1, Effects of Thermal Aging on Fracture Toughness and Charpy-Impact Strength of Stainless Steel Pipe Welds, August 2018 (Revision 1), identifies Eq. 22
= 117 ()0.45 2
as the recommended lower bound J-R curve for thermally aged SAWs and SMAWs.
Eq. 22 of Revision 1 is approximately 25% lower than Eq. 3 of Revision 0 at a crack growth (a) value of 1 mm.
Request:
- 1. What is the basis for the disposition of 10 CFR 54.21(c)(1)(i) in SLRA Section 4.7.2 as it pertains to thermal aging of stainless steel welds?
- 2. In its consideration of the TLAA related to LBB analyses for the reactor coolant system auxiliary piping, did the applicant consider the updated analysis on lower bound thermal aging of stainless steel welds from NUREG/CR-6428, Revision 1, relative to the assumptions made in WCAP-15065-P-A, Revision 1, WCAP-15105-P-A, Revision 1, and WCAP-15107-P-A, Revision 1?
- 3. Would the use of the updated lower bound thermal aging curves for stainless steel welds from NUREG/CR-6428, Revision 1 affect the conclusions in SLRA Section 4.7.2?
- 4. As cited in SLRA Section 4.7.1, WCAP-14439-P, Revision 4 addresses thermal aging effects on the cast austenitic stainless steel components for the LBB analyses of the Point Beach reactor coolant loop piping. Was thermal aging of the stainless steel welds considered in this report, and would use of the updated lower bound thermal aging curves for stainless steel welds from NUREG/CR-6428, Revision 1 affect the conclusions in SLRA Section 4.7.1?