RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor
| ML23216A004 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom, Nine Mile Point, Limerick, FitzPatrick, LaSalle  |
| Issue date: | 08/04/2023 |
| From: | David Gudger Constellation Energy Generation |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RS-23-087, NMP1L3549 | |
| Download: ML23216A004 (1) | |
Text
200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.55a RS-23-087 NMP1L3549 August 4, 2023 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket No. 50-333 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352 and 50-353 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220 and 50-410 Peach Bottom Atomic Power Station, Units 2 and 3 Subsequent Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor Pressure Vessel Internals and Components Inspection
References:
- 1) Letter from J. Danna (U.S. Nuclear Regulatory Commission) to B. Hanson (Exelon Generation Company, LLC), "James A. FitzPatrick Nuclear Power Plant - Relief Requests I5R-02, I5R-03, and I5R-04 for Alternatives to Certain ASME Code Requirements (CAC Nos. MG0116, MG0117, and MG0118; EPID L-2017-LLR-0083, EPID L-2017-LLR-0084, and EPID L-2017-LLR-0085)," dated May 30, 2018 (ML18039A854)
- 2) Letter from D. Wrona (U.S. Nuclear Regulatory Commission) to B. Hanson (Exelon Generation Company, LLC), "LaSalle County Station, Units 1 and 2, Relief from the Requirements of the ASME Code and OM Code RE:
Relief Requests I4R-02, I4R-03, I4R-06, I4R-07, and I4R-09, Proposed Alternatives to Various Inservice Inspection Interval (ISI) Requirements of
Revision to Approved Alternatives Associated with BWRVIP Documents August 4, 2023 Page 2 the American Society of Mechanical Engineers (ASME Code)Section XI, 2007 Edition with the 2008 Addenda for the Fourth 10-Year ISI Interval (EPID Nos. L-2017-LLR-0038 (CAC Nos. MF9760 and MF9761), L-LR-2017- 0076 (CAC Nos. MF9762 and MF9763), L-2017-LLR-0033 (CAC Nos. MF9766 and MF9767), L-2017-LLR-0035 (CAC Nos. MF9770 and MF9771), and L-2017-LLR-0037 (CAC Nos. MF9768, and MF9769)," dated November 17, 2017 (ML17305B279)
- 3) Letter from S. Koenick (U.S. Nuclear Regulatory Commission) to B. Hanson (Exelon Generation Company, LLC), "Safety Evaluation of Relief Requests I4R-02 and I4R-10 for the Fourth 10-Year Interval of the lnservice Inspection Program for Limerick Generating Station, Units 1 and 2 (CAC Nos. MF7587 and MF7588)," dated November 21, 2016 (ML16301A401)
- 4) Letter from J. Danna (U.S. Nuclear Regulatory Commission) to B. Hanson (Exelon Generation Company, LLC), "Nine Mile Point Nuclear Station, Units 1 and 2 - Issuance of Relief Requests RE: Use of Boiling Water Reactor Vessel and Internals Project Guidelines in Lieu of Specific ASME Code Requirements (EPID L-2018-LLR-0085)," dated December 13, 2018 (ML18318A275)
- 5) Letter from J. Danna (U.S. Nuclear Regulatory Commission) to B. Hanson (Exelon Generation Company, LLC), "Peach Bottom Atomic Power Station, Units 2 and 3 - Safety Evaluation of Relief Request I5R-03 Regarding the Fifth 10-Year Interval of the lnservice Inspection Program (EPID No. L-2018-LLR-0056)," dated July 18, 2018 (ML18179A394)
- 6) Letter from D. Wrona (U.S. Nuclear Regulatory Commission) to B. Hanson (Exelon Generation Company, LLC), "Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; James A. Fitzpatrick Nuclear Power Plant; Lasalle County Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; Peach Bottom Atomic Power Station, Units 2 and 3; and Quad Cities Nuclear Power Station, Units 1 and 2 -
Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines (EPID L-2019-LLR-0012)," dated April 30, 2019 (ML19098A034)
In accordance with 10 CFR 50.55a(z)(1), Constellation Energy Generation, LLC (CEG) is requesting a revision to the above referenced Safety Evaluation Reports (References 1 through 5) concerning the use of the BWRVIP Guidelines in lieu of specific ASME Code requirements on Reactor Pressure Vessel internals and components inspection.
Since the issuance of these U.S. Nuclear Regulatory Commission Safety Evaluation Reports, revisions to several Boiling Water Reactor Vessel and Internals Project (BWRVIP) documents have occurred. Specifically, "BWRVIP-25, Revision 1-A: BWR Vessel and Internals Project BWR Core Plate Inspection and Flaw Evaluation Guidelines", "BWRVIP-42, Revision 1-A: BWRVIP Vessel and Internals Project Low Pressure Coolant Injection (LPCI)
Coupling Inspection and Flaw Evaluation Guidelines", "BWRVIP-139, Revision 1-A: Steam
Revision to Approved Alternatives Associated with BWRVIP Documents August 4, 2023 Page 3 Dryer Inspection and Flaw Evaluation Guidelines", and "BWRVIP-183, Revision 0-A: Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines" have been approved. CEG is requesting the previously approved U.S. Nuclear Regulatory Commission Safety Evaluation Reports be revised to include these updated document revisions for the plants to which they are applicable as listed in Table 1.
A similar revision to approved alternatives for (CEG) Exelon Generation Company, LLC was approved in the Reference 6 U.S. Nuclear Regulatory Commission Safety Evaluation Report.
CEG requests your review and approval of this fleet request by February 1, 2024, so that the updated BWRVIP documents can be utilized in the Spring 2024 outages.
There are no regulatory commitments contained in this letter.
If you have any questions, please contact Tom Loomis at Thomas.loomis@constellation.com.
David T. Gudger Senior Manager - Licensing and Regulatory Affairs Constellation Energy Generation, LLC
Attachment:
Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor Pressure Vessel Internals and Components Inspection cc:
Regional Administrator - NRG Region I Regional Administrator - NRG Region Ill NRC Senior Resident Inspector - James A. FitzPatrick Nuclear Power Plant NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector - Limerick Generating Station NRC Senior Resident Inspector - Nine Mile Point NRC Senior Resident Inspector - Peach Bottom Atomic Power Station NRC Project Manager - James A. FitzPatrick Nuclear Power Plant NRC Project Manager - LaSalle County Station NRC Project Manager - Limerick Generating Station NRC Project Manager - Nine Mile Point NRC Project Manager - Peach Bottom Atomic Power Station A. L. Peterson, NYSERDA
Attachment Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor Pressure Vessel Internals and Components Inspection in Accordance with 10 CFR 50.55a(z)(1)
10 CFR 50.55a RELIEF REQUEST Revision 0 (Page 1 of 3)
Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor Pressure Vessel Internals and Components Inspection in Accordance with 10 CFR 50.55a(z)(1) 1.0 Reason for Request Pursuant to 10 CFR 50.55a(z)(1), a revision is requested to the U.S. Nuclear Regulatory Commission previously approved relief requests (Table 1) associated with the use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) guidelines in lieu of specific ASME Code requirements on Reactor Pressure Vessel internals and components inspection.
Since the issuance of these U.S. Nuclear Regulatory Commission Safety Evaluation Reports, revisions to several referenced BWRVIP documents have occurred. Specifically, BWRVIP-25, Revision 1-A (Reference 1), BWRVIP-42, Revision 1-A (Reference 2), BWRVIP-139, Revision 1-A (Reference 3), and BWRVIP-183, Revision 0-A (Reference 4) have been approved.
Constellation Energy Generation, LLC (CEG) is requesting approval to use the latest U.S.
Nuclear Regulatory Commission approved documents in place of the document revisions cited in the Safety Evaluation Reports on the basis that these approved BWRVIP documents provide an acceptable level of quality and safety.
The BWRVIP guidelines have recommended aggressive specific inspection by BWR operators to identify material condition issues with BWR components. A wealth of inspection data has been gathered during these inspections across the BWR industry. These guidelines focus on specific and susceptible components, specify appropriate inspection methods capable of identifying anticipated degradation mechanisms, and require re-examination at conservative intervals. In contrast, the code inspection requirements were prepared before the BWRVIP initiative and have not evolved with BWR inspection experience.
2.0 Proposed Revision The CEG units listed in Table 1 have submitted relief requests proposing to use the BWRVIP guidelines as an alternative to the requirements of Section XI of the ASME Code for the ISI of the Reactor Pressure Vessel (RPV) interior surfaces, attachments, and core support structures.
Relief requests have been approved by the NRC with specific revisions of BWRVIP documents identified. In some Safety Evaluation Reports, language is included which restricts the use of the relief request to the BWRVIP document revisions specifically identified within the relief request submittal. In the time since the Staff's approval of CEG's proposed alternatives, several BWRVIP documents were revised by the BWRVIP and approved by the NRC. CEG requests that the latest NRC approved revision of BWRVIP-25, BWRVIP-42, BWRVIP-139, and BWRVIP-183 be used as an alternative to the revision currently listed in the respective Safety Evaluation Reports as delineated in Table 1 for the remainder of the current intervals.
3.0 References
- 1. BWRVIP-25, Revision 1-A: BWR Vessel and Internals Project BWR Core Plate Inspection and Flaw Evaluation Guidelines. EPRI, Palo Alto, CA: 2020. 3002018310.
- 2. BWRVIP-42, Revision 1-A: BWRVIP Vessel and Internals Project Low Pressure Coolant Injection (LPCI) Coupling Inspection and Flaw Evaluation Guidelines. EPRI, Palo Alto, CA:
2017. 3002010548.
10 CFR 50.55a RELIEF REQUEST Revision 0 (Page 2 of 3)
- 3. BWRVIP-139, Revision 1-A: Steam Dryer Inspection and Flaw Evaluation Guidelines. EPRI, Palo Alto, CA: 2017. 3002010541
- 4. BWRVIP-183, Revision 0-A: Top Guide Grid Beam Inspection and Flaw Evaluation Guidelines.
EPRI, Palo Alto, CA: 2017. 3002010551 4.0 Precedence
- 1. Letter from D. Wrona (U.S. Nuclear Regulatory Commission) to B. Hanson (Exelon Generation Company, LLC), "Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; James A. Fitzpatrick Nuclear Power Plant; Lasalle County Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; Peach Bottom Atomic Power Station, Units 2 and 3; and Quad Cities Nuclear Power Station, Units 1 and 2 - Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines (EPID L-2019-LLR-0012)," dated April 30, 2019 (ML19098A034).
10 CFR 50.55a RELIEF REQUEST Revision 0 (Page 3 of 3)
Table 1 Plants with Updated BWRVIP Document Revisions Unit SER ADAMS Accession No.
Listed BWRVIP-25 Revision Requested BWRVIP-25 Revision Listed BWRVIP-42 Revision Requested BWRVIP-42 Revision Listed BWRVIP-139 Revision Requested BWRVIP-139 Revision Listed BWRVIP-183 Revision Requested BWRVIP-183 Revision James A.
Fitzpatrick Nuclear Power Plant ML18039A854 0
1-A Not included N/A Not included N/A 0
0-A LaSalle County Station, Units 1 and 2 ML17305B279 0
1-A 1
1-A Not included N/A Not included N/A Limerick Generating Station, Units 1 and 2 ML16301A401 0
1-A 1
1-A 0-A 1-A 0-A No change required Nine Mile Point, Units 1 and 2 ML18318A275 0
1-A 1-A (U2 only)
No change required Not included N/A 0-A No change required Peach Bottom Atomic Power Station, Units 2 and 3 ML18179A394 0
1-A Not included N/A Not included N/A 0-A No change required