LG-26-030, Supplement to License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency
| ML26030A249 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/30/2026 |
| From: | Para W Constellation Energy Generation, Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| LG-26-030 | |
| Download: ML26030A249 (0) | |
Text
200 Energy Way Kennett Square, PA 19348 www.constellation.com LG-26-030 10 CFR 50.90 January 30, 2026 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket No. 50-352 and 50-353
Subject:
Supplement to License Amendment Request for One-Time Extension of the Containment Type A Integrated Leakage Rate Test Frequency
Reference:
1.
Constellation Energy Generation (CEG) letter to the U.S. Nuclear Regulatory Commission (NRC), License Amendment Request for One-Time Extension of the Containment Type A Integrated Leakage Rate Test Frequency, dated August 15, 2025 (ADAMS Accession No. ML25227A183) 2.
U.S Nuclear Regulatory Commission (NRC) letter to Constellation Energy Generation (CEG), NRC Acceptance Review for Limerick LLRT LAR (L-2025-LLA-0167) and updated schedule for ILRT LAR (L-2025-LLA-0126), dated December 15, 2025 (ADAMS Accession No.ML25353A570)
In Reference 1, Constellation Energy Generation, LLC (CEG) requested a License Amendment Request (LAR) that would allow for a one-time extension to the 15-year frequency of the containment leakage rate test (i.e., integrated leakage rate test (ILRT) or Type A test) for Limerick Generating Station (LGS) Units 1 and 2. This test is required by LGS Technical Specifications (TS) Section 6.8.4.g, "Primary Containment Leakage Rate Testing Program." The proposed one-time change would allow the ILRT to be completed during the LGS, Unit 1 Spring 2028 Refueling Outage and Unit 2 Spring 2029 Refueling Outage, respectively.
CEG no longer wishes to pursue the one-time extension request for LGS, Unit 1, and formally withdraws the Unit 1 portion of Reference 1 in entirety. The one-time extension request for LGS, Unit 2 is unaffected by this change.
Constellation
January 30, 2026 U.S. Nuclear Regulatory Commission Page 2 In Reference 2, the NRC identified two (2) items requiring clarification. CEG reviewed the items and has revised the wording in the proposed TS pages to remove the word mode and replace it with the OPERATIONAL CONDITION consistent with the LGS TS Definitions. CEG has also revised the wording in the proposed TS page to clarify the proposed timing requirements for the Type A testing.
A revised TS page markup is provided in the Attachment to this letter.
CEG has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, which was previously provided to the NRC in the Reference 1 submittal. CEG has concluded that the information provided in this letter does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92. In addition, CEG has concluded that the information in this letter does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendments.
The proposed TS change has been reviewed by the Plant Operations Review Committee in accordance with the requirements of the CEG Quality Assurance Program.
There are no new regulatory commitments contained in this submittal.
Should you have any questions concerning this submittal, please contact Lane Oberembt at 267-533-5301.
I declare under the penalty of perjury that the foregoing is true and correct.
Executed on the 30th day of January 2026.
Respectfully, Wendi Para Sr. Manager - Licensing Constellation Energy Generation, LLC Attachment Markup of Technical Specifications Page cc:
USNRC Region I, Regional Administrator w/ Attachments USNRC Senior Resident Inspector, LGS USNRC Project Manager, LGS Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Protection p_
Para, Wendi E 2026.01.30 14:54:49
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ATTACHMENT License Amendment Request Limerick Generating Station, Unit 2 Docket No. 50-353 Markup of Technical Specification Page Unit 2 TS Page 6-14c
ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)
- g.
Primary Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54 (o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in NEI 94-01, Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix Revision 3-A, dated July 2012, and the Limitations and Conditions specified in NEI 94-01, Revision 2-A, dated October 2008.
The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 44.0 psig.
The maximum allowable primary containment leakage rate, La, at Pa, shall be 0.5% of primary containment air weight per day.
Leakage rate acceptance criteria are:
- a.
Primary Containment leakage rate acceptance criterion is less than or equal to 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are less than or equal to 0.60 La for the Type B and Type C tests and less than or equal to 0.75 La for Type A tests;
- b.
Air lock testing acceptance criteria are:
- 1) Overall airlock leakage rate is less than or equal to 0.05 La when tested at greater than or equal to Pa.
- 2) Seal leakage rate is less than or equal to 5 scf per hour when the gap between the door seals is pressurized to 10 psig.
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Primary Containment Leakage Rate Testing Program.
The provisions of Specification 4.0.3 are applicable to the tests described in the Primary Containment Leakage Rate Testing Program.
- h.
Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.
- a.
Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.
- b.
Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
A change in the TS incorporated in the license; or A change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
- c.
The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.
- d.
Proposed changes that meet the criteria of b. above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).
LIMERICK - UNIT 2 6-14c Amendment No. 81, 124, 151, 204 Insert B "Industry J,,,
TS 6.8.4.g TS change Insert B as modified by the following exemptions: [1] the next Type A test shall be performed no later than April 30, 2029, and [2] if the Type A test has not been performed by April 30, 2029, and the unit is in OPERATIONAL CONDITION 4 or 5, the Type A test shall be performed prior to entering an OPERATIONAL CONDITION where PRIMARY CONTAINMENT INTEGRITY is required.