ML23192A629
| ML23192A629 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 07/11/2023 |
| From: | Shilpa Arora Plant Licensing Branch III |
| To: | Rhoades D Constellation Energy Generation |
| Arora, S | |
| Shared Package | |
| ML23192A757 | List: |
| References | |
| EPID L-2022-LLA-0121 | |
| Download: ML23192A629 (5) | |
Text
July 11, 2023 Mr. David P. Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, CORRECTION LETTER - ISSUANCE OF AMENDMENT NOS. 281 AND 274 REGARDING TRANSITION TO GNF3 FUEL (EPID L-2022-LLA-0121)
Dear Mr. Rhoades:
On July 5, 2023, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos.
281 and 274 to Renewed Facility Operating License Nos. DPR-19 and DPR-25 for Dresden, Units 2 and 3, respectively. The amendments consisted of changes to the Dresden technical specifications (TSs) in response to your application dated August 18, 2022 (Agencywide Documents Access and Management System Accession No. ML22230C927), as supplemented by your letters dated January 23, 2023 (ML23023A128) and April 17, 2023 (ML23107A228).
Subsequent to issuance of the amendments, it was noticed that page 2 of the safety evaluation (SE) for the amendment package was not correct as it had the NRC staffs SE approval dates for reports NEDC-33930P, Revision 0, and 006N8642-P, Revision 1, which were not consistent with the SE approval dates in your amendment request.
Enclosed with this letter is the corrected page 2 of the amendment SE with the corrected approval dates. The NRC concludes that this correction is entirely editorial in nature and does not change the staffs conclusion in the SE for Amendments 281 and 274 nor does it affect the no significant hazard consideration, as published in the Federal Register on November 1, 2022 (87 FR 65833).
If you have any questions regarding this matter, please contact me at (301) 415-1421 or by e-mail at Surinder.Arora@nrc.gov.
Sincerely,
/RA/
Surinder Arora, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249
Enclosure:
Corrected SE Page 2 for Amendment Nos. 281 and 274 cc: Listserv
Enclosure Corrected SE page 2
OFFICIAL USE ONLY - PROPRIETARY INFORMATION OFFICIAL USE ONLY - PROPRIETARY INFORMATION The proprietary information in this safety evaluation (SE) input is identified by text in bold font and enclosed within double square brackets. ((This is an example)).
2.0 REGULATORY EVALUATION
2.1 Proposed TS Changes
The licensee proposes to revise the DNPS, Units 2 and 3, Technical Specification (TS) 5.6.5.b, Core Operating Limits Report (COLR), by adding the following two reports as items 21 and 22 to support the General Electric Standard Application for Reactor Fuel (GESTAR) analysis methodology to the list of approved methods to be used in determining the core operating limits in the COLR:
21.
NEDC-33930P, Revision 0, GEXL98 Correlation for ATRIUM 10XM Fuel, Global Nuclear Fuels, February 2021, as approved by the NRC staff SE dated XXX XX, 20XX.
22.
006N8642-P, Revision 1, Justification of PRIME Methodologies for Evaluating TOP and MOP Compliance for non-GNF Fuels, Global Nuclear Fuels, January 2022, as approved by the NRC staff SE dated XXX XX, 20XX.
The licensee proposes to delete the following eight Westinghouse topical reports (TRs) from TS 5.6.5.b that will no longer be used to support the COLR evaluations after the fall outage in 2023.
3.
CENPD-300-P-A, Reference Safety Report for Boiling Water Reactor [BWR] Reload Fuel.
4.
WCAP-16081-P-A, 10x10 SVEA Fuel Critical Power Experiments and CPR [critical power ratio] Correlation: SVEA-96 Optima2.
5.
WCAP-15682-P-A, Westinghouse BWR ECCS [emergency core cooling system]
Evaluation Model: Supplement 2 to Code Description, Qualification and Application.
6.
WCAP-16078-P-A, Westinghouse BWR ECCS Evaluation Model: Supplement 3 to Code Description, Qualification and Application to SVEA-96 Optima2 Fuel.
7.
WCAP-15836-P-A, Fuel Rod Design Methods for Boiling Water Reactors -
Supplement 1.
8.
WCAP-15942-P-A, Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors, Supplement 1 to CENPD-287.
9.
CENPD-390-P-A, The Advanced PHOENIX and POLCA Codes for Nuclear Design of Boiling Water Reactors.
- 10. WCAP-16865-P-A, Westinghouse BWR ECCS Evaluation Model Updates:
Supplement 4 to Code Description, Qualification and Application, Revision 1, October 2011.
ML23192A757 (Package)
ML23191A899 (Proprietary)
ML23192A629 (Non-Proprietary)
OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME SArora SRohrer JWhited SArora DATE 7/10/2023 7/11/2023 7/11/2023 7/11/2023