ML24324A044
| ML24324A044 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/03/2024 |
| From: | Richard Guzman Plant Licensing Branch 1 |
| To: | Carr E Dominion Energy Nuclear Connecticut |
| Guzman R, NRR/DORL/LPLI, 415-1030 | |
| References | |
| EPID L-2024-LLA-0035 | |
| Download: ML24324A044 (1) | |
Text
December 3, 2024 Eric S. Carr President - Nuclear Operations and Chief Nuclear Officer Dominion Energy Nuclear Connecticut, Inc.
Millstone Power Station Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
SUBJECT:
MILLSTONE POWER STATION, UNIT NO. 3 - ISSUANCE OF AMENDMENT NO. 292 REGARDING ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER TSTF-421 (EPID L-2024-LLA-0035)
Dear Eric Carr:
The U.S Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 292 to facility operating license No. NPF-49 for Millstone Power Station, Unit No.3. This amendment is in response to the application dated March 22, 2024.
The amendment revises Millstone Power Station, Unit No. 3, technical specification requirements to extend the reactor coolant pump (RCP) motor flywheel examination frequency from the currently approved 10-year inspection interval, to an interval not to exceed 20 years, consistent with Technical Specification Task Force Standard Technical Specification Change Traveler, TSTF-421 "Revision to RCP Flywheel Inspection Program (WCAP-15666)." The availability of TSTF-421 for adoption by licensees was announced in the Federal Register on October 22, 2003 (68 FR 60422).
A copy of our related safety evaluation is also enclosed. The notice of issuance will be included in the NRCs Federal Register notice.
If you have any questions, please contact me at (301) 415-1030 or by email to Richard.Guzman@nrc.gov.
Sincerely,
/RA/
Richard Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423
Enclosures:
- 1. Amendment No. 292 to NPF-49
- 2. Safety Evaluation cc: Listserv
DOMINION ENERGY NUCLEAR CONNECTICUT, INC., ET AL DOCKET NO. 50-423 MILLSTONE POWER STATION, UNIT NO. 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 292 Renewed License No. NPF-49
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Dominion Energy Nuclear Connecticut, Inc.
(DENC, the licensee), dated March 22, 2024, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commissions regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commissions regulations, and all applicable requirements have been satisfied.
- 2.
Accordingly, paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-49 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 292 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated into the license. DENC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of the date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Hipólito González, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to Renewed Facility Operating License No. NPF-49 and the Technical Specifications Date of Issuance: December 3, 2024 HIPOLITO GONZALEZ Digitally signed by HIPOLITO GONZALEZ Date: 2024.12.03 11:36:47 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 292 MILLSTONE POWER STATION, UNIT NO. 3 RENEWED FACILITY OPERATING LICENSE NO. NPF-49 DOCKET NO. 50-423 Replace the following page of the Renewed Facility Operating License with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Remove Insert 4
4 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
Remove Insert 6-26 6-26
(2)
Technical Specifications The Technical Specifications contained in Appendix A, revised through Amendment No. 292 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated into the license. DENC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
DENC shall not take any action that would cause Dominion Energy, Inc.
or its parent companies to void, cancel, or diminish DENC's Commitment to have sufficient funds available to fund an extended plant shutdown as represented in the application for approval of the transfer of the licenses for MPS Unit No. 3.
(4)
Immediately after the transfer of interests in MPS Unit No. 3 to DNC*, the amount in the decommissioning trust fund for MPS Unit No. 3 must, with respect to the interest in MPS Unit No. 3, that DNC* would then hold, be at a level no less than the formula amount under 10 CFR 50.75.
(5)
The decommissioning trust agreement for MPS Unit No. 3 at the time the transfer of the unit to DNC* is effected and thereafter is subject to the following:
(a)
The decommissioning trust agreement must be in a form acceptable to the NRC.
(b)
With respect to the decommissioning trust fund, investments in the securities or other obligations of Dominion Energy, Inc. or its affiliates or subsidiaries, successors, or assigns are prohibited.
Except for investments tied to market indexes or other non-nuclear-sector mutual funds, investments in any entity owning one or more nuclear power plants are prohibited.
(c)
The decommissioning trust agreement for MPS Unit No. 3 must provide that no disbursements or payments from the trust, other than for ordinary administrative expenses, shall be made by the trustee until the trustee has first given the Director of the Office of Nuclear Reactor Regulation 30 days prior written notice of payment. The decommissioning trust agreement shall further contain a provision that no disbursements or payments from the trust shall be made if the trustee receives prior written notice of objection from the NRC.
(d)
The decommissioning trust agreement must provide that the agreement cannot be amended in any material respect without 30 days prior written notification to the Director of the Office of Nuclear Reactor Regulation.
- On May 12, 2017, the name Dominion Nuclear Connecticut, Inc. changed to Dominion Energy Nuclear Connecticut, Inc.
Renewed License No. NPF-49 Amendment No. 270-291, 292
MILLSTONE - UNIT 3 ADMINISTRATIVE CONTROLS j.
Limitations on the annual dose or dose commitment to any member of the public, beyond the SITE BOUNDARY, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
The provisions of Specification 4.0.2 and Specification 4.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.
6.16 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the REMODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
a.
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the REMODCM.
b.
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and c.
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
6.17 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM This program shall provide for the inspection of each reactor coolant pump flywheel by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels at least once every 20 years.
6.18 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:
1.
A change in the TS incorporated in the license or 2.
A change to updated FSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.
Amendment No. 188, 204, 212, 215, 229, 6-26 292
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 292 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-49 DOMINION ENERGY NUCLEAR CONNECTICUT, INC MILLSTONE POWER STATION, UNIT NO. 3 DOCKET NO. 50-423
1.0 INTRODUCTION
By application dated March 22, 2024 (Agencywide Documents Access and Management System Accession No. ML24086A476), Dominion Energy Nuclear Connecticut, Inc. (the licensee), submitted a license amendment requesting changes to the technical specifications (TSs) for the Millstone Power Station, Unit No.3 (MPS3).
The proposed changes would extend the reactor coolant pump (RCP) motor flywheel examination interval. These changes are based on the U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specifications Task Force (TSTF) Change Traveler TSTF-421, Revision to RCP Flywheel Inspection Program (WCAP-15666), that has been approved generically for the Westinghouse Standard Technical Specifications, NUREG-1431. A notice announcing the availability of this proposed TS change using the consolidated line item improvement process was published in the Federal Register on October 22, 2003 (68 FR 60422).
2.0 REGULATORY EVALUATION
2.1 Description of Proposed Changes The function of the RCP in the reactor coolant system of a pressurized-water reactor plant is to maintain an adequate cooling flow rate by circulating a large volume of primary coolant water at high temperature and pressure through the reactor coolant system. Following an assumed loss of power to the RCP motor, the flywheel, in conjunction with the impeller and motor assembly, provides sufficient rotational inertia to assure adequate primary coolant flow during RCP coastdown, thus resulting in adequate core cooling.
The proposed change revises MPS3 TS 6.17, Reactor Coolant Pump Flywheel Inspection Program by modifying the examination interval. The examination interval for the RCP flywheels is changed from at least once every 10 years to at least once every 20 years.
2.2 Applicable Regulatory Requirements and Guidance Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36(c)(5) states in part that
[a]dministrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner.
A concern regarding the overspeed of the RCP and its potential for failure led to the issuance of NRC Regulatory Guide (RG) 1.14, Reactor Coolant Pump Flywheel Integrity, Revision 1, dated August 1975 (ML003739936). RG 1.14 describes a method acceptable to the NRC staff of addressing concerns related to RCP vibration and the possible effects of missiles that might result from the failure of the RCP flywheel. The need to protect components important to safety from such missiles are included in General Design Criterion (GDC) 4, Environmental and Dynamic Effects Design Basis, of Appendix A, General Design Criteria for Nuclear Power Plants, to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities, which is applicable to plants that obtained a construction permit after May 21, 1971. The MPS3 construction permit was issued in 1974 (ML23047A378).
Specific requirements to have an RCP flywheel inspection program consistent with RG 1.14 or previously issued relaxations from the regulatory guide are included in the Administrative Controls section of the TSs. The purpose of the testing and inspection programs defined in the TSs is to ensure that the probability of a flywheel failure is sufficiently small such that additional safety features are not needed to protect against a flywheel failure. The regulatory guide provides criteria in terms of critical speeds that could result in the failure of an RCP flywheel during normal or accident conditions. In addition to the guidance in RG 1.14, the NRC has more recently issued RG 1.174, Revision 3, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, in January 2018 (ML17317A256), which provides guidance and criteria for evaluating proposed changes that use risk-informed justifications.
A proposed justification for extending the RCP flywheel inspections from a 10-year inspection interval to an interval not to exceed 20 years was provided by the Westinghouse Owners Group in topical report WCAP-15666, Extension of Reactor Coolant Pump Motor Flywheel Examination, transmitted by letter dated August 24, 2001 (ML012420149). The topical report addressed the proposed extension for all domestic Westinghouse plants. The NRC-approved the topical report for referencing in license applications in a letter and safety evaluation dated May 5, 2003 (ML031250595). The accepted version of the topical report, WCAP-15666-A, contains in part, the topical report, NRC safety evaluation, and historical review information, such as questions and accepted responses (ML18303A413).
3.0 TECHNICAL EVALUATION
In section 5.0, Technical Analysis, of the license amendment request, the licensee explained that it had reviewed the NRC staffs model safety evaluation of TSTF-421, which was published in the Federal Register on June 24, 2003 (68 FR 37590), as well as the information provided to support TSTF-421, including topical report WCAP-15666 and the related NRC safety evaluation dated May 5, 2003. The licensees evaluation concluded that justifications presented in TSTF-421 and the model safety evaluation are applicable to MPS3, a Westinghouse plant design, and appropriate to incorporate into the MPS3 TS.
MPS3 TS 6.17, Reactor Coolant Pump Flywheel Inspection Program, requires a qualified in-place ultrasonic examination over the volume from the inner bore of the RCP flywheel to the circle of one-half of the outer radius or an alternative surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheel. Currently, these examinations must be performed at least once every 10 years. The change proposed in this amendment application would revise the inspection interval to at least once every 20 years. This change deviates slightly from TSTF-421, which uses at 20-year intervals. However, the change is consistent with the phrasing in WCAP-15666 and can be viewed as more conservative than the requirement as stated in TSTF-421.
The justification for the proposed change was provided in WCAP-15666, which the NRC staff accepted for referencing in license applications by a letter and safety evaluation dated May 5, 2003. The topical report addresses the three critical speeds defined in RG 1.14: (a) the critical speed for ductile failure, (b) the critical speed for non-ductile failure, and (c) the critical speed for excessive deformation of the flywheel. The NRC staff concluded that the methodologies in the topical report adequately addressed these critical speeds and demonstrated that acceptance criteria, for normal and accident conditions defined in RG 1.14, would continue to be met for all domestic Westinghouse plants following an extension of the inspection interval. The topical report also provided a risk assessment for extending the RCP flywheel inspection interval. The NRC staffs review, documented in the safety evaluation for the topical report, determined that the analysis methods and risk estimates are acceptable when compared to the guidance in RG 1.174 dated July 1998. The current version of RG 1.174 is dated January 2018. The NRC staff compared the application of RG 1.174 principal elements of risk-informed, plant-specific decision making and determined that the NRC acceptance guidelines remain consistent between these two versions. Therefore, the NRC staff finds the topical report conclusions remain acceptable.
Based on the above, the NRC staff concludes that the regulatory criteria in RG 1.14 concerning the three critical speeds are satisfied, and that the evaluation indicating that critical crack sizes are not expected to be attained during a 20-year inspection interval is reasonable and acceptable. The potential for failure of the RCP flywheel is, and will continue to be, negligible during normal and accident conditions. The changes are, therefore, acceptable and the TSs will continue to meet the requirements of 10 CFR 50.36(c)(5) by providing the guidelines necessary to assure operation of the facility in a safe manner.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Connecticut State official was notified of the proposed issuance of the amendment on November 15, 2024. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on June 11, 2024 (89 FR 49240).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: C. Ashley, NRR Date of Issuance: December 3, 2024
ML24324A044 OFFICE NRR/DORL/LDATA/PM NRR/DORL/LPL1/PM NRR/DORL/LP1/LA NAME RDavis RGuzman KEntz DATE 11/15/2024 11/15/2024 11/20/2024 OFFICE NRR/DSS/STSB/BC NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME SMehta HGonzález RGuzman DATE 10/31/2024 11/29/2024 12/3/2024