PLA-7904, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments (PLA-7904)

Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments (PLA-7904)

ML20293A240
Person / Time
Site:	Susquehanna
Issue date:	10/19/2020
From:	Cimorelli K Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-7904
Download: ML20293A240 (3)

Text

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Kevin Cimorelli Susquehanna Nuclear, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3795 Fax 570.542.1504 Kevin.Cimorelli@TalenEnergy.com ENERGY 10/19/2020 Attn: Document Control Desk 10 CFR50.59 U. S. Nuclear Regulatory Commission 10 CFR 72.48 Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION BIENNIAL 10 CFR 50.59 AND 72.48

SUMMARY

REPORT AND CHANGES TO REGULATORY COMMITMENTS Docket No. 50-387 PLA-7904 and 50-388 This letter submits the biennial summary reports required by 10 CPR 50.59(d)(2) and 10 CFR 72.48(d)(2) and the commitment revision summary report required by SECY-00-0045 and NEI 99-04, "Guidelines for Managing NRC Commitment Changes."

During the period of September 1, 2018, to August 31, 2020, there were no changes, tests or experiments approved pursuant to 10 CFR 50.59(c) and 10 CFR 72.48(c). The Enclosure to this letter provides the summary report of changes to regulatory commitments made in the same period.

This letter contains no new or revised regulatory commitments.

Should you have any uestions regarding this submittal, please contact Ms. Melisa Krick, Manage N r eg atory Affairs, at (570) 542-1818.

Enclosure:

Summary of Changes to Regulatory Commitments Copy: NRC Region I Mr. C. Highley, NRC Senior Resident Inspector Ms. S. Goetz, NRC Project Manager Mr. M. Shields, PA DEP/BRP Director, Division of Fuel Management

Enclosure to PLA-7904 Page 1 of2 SUSQUEHANNA COMMITMENT CHANGES NEI 99-04 states that the intent of the regulatory commitment summary report is to provide a brief summary of commitments changed since the last rep mi in lieu of filing individual notifications as commitments are revised. As such, this report contains commitment changes for reporting period September 1, 2018, to August 31, 2020, that have not been previously reported to the NRC.

Summary of Commitment Change - SSES License Renewal Commitments The Boiling Water Reactor Vessel and Internals Program (BWRVIP) develops technical topical reports related to protection of Boiling Water Reactor (BWR) reactor components. Susquehanna Nuclear, LLC (Susquehanna), has committed to the NRC to follow the guidance of the BWRVIP via a letter contained in BWRVIP-94, Revision 2 (Reference 1). The BWRVIP developed a guidance document BWRVIP-25, Revision 0, that recommended a plant specific analysis and inspection of the core plate bolts. NUREG-1931 (Reference 2) contains a commitment, in part, to obtain NRC approval for a plant-specific evaluation consistent with BWRVIP-25 to demonstrate that the core plate rim hold-down bolts will be capable of preventing lateral displacement of the core plate for the period of extended operation (PEO).

In March 2020, the NRC approved BWRVIP-25, Revision 1, "BWR Core Plate Inspection and Evaluation Guidelines." The NRC Safety Evaluation (Reference 3) concludes that once the utility has demonstrated that BWRVIP-25, Revision 1 is applicable to the design of their BWR Core Plate assembly components, they may use the report as the basis for managing age-related degradation in components during the PEO or subsequent PEO.

The Regulatory Commitment prior to BWRVIP-25 Revision 1 approval stated:

"PPL will either: (1) obtain NRC approval of a SSES plant-specific evaluation consistent with BWRVIP-25 to demonstrate that the core plate rim hold-down bolts will be capable of preventing lateral displacement of the core plate for the period of extended operation (the plant-specific evaluation will be submitted for NRC review no less than 2 years prior to the period of extended operation and will address the inspection strategy for the hold-down bolts); or (2) install core plate wedges to structurally replace lateral load resistance provided by the bolts. "

Enclosure to PLA-7904 Page 2 of2 Susquehanna modified this Regulatory Commitment to state:

"SSES will address the loss ofpre load on the core plate rim hold-down bolts by conforming to BWRVIP-25, Revision 1 (as approved by NRC SER ML19290G703). The evaluation will be completed no less than two years prior to the period of extended operation. "

References

1. BWRVIP-94NP, "BWR Vessel and Internals Project Program Implementation Guide,"

Revision 2, dated September 2011 (ADAMS Accession No. ML11271A058).

2. NRC NUREG-1931, "Safety Evaluation Report Related to the License Renewal of Susquehanna Steam Electric Station, Units 1 and 2," dated November 2009 (ADAMS Accession Nos. ML093 l 70786).

3. NRC Letter to BWRVIP, "Final Proprietary Safety Evaluation for BWRVIP-25, Revision 1: BWR Vessel and Internals Project, BWR Core Plate Inspection and Flaw Evaluation Guidelines," Dated March 23, 2020 (ADAMS Accession No. ML19290G703).