ML23352A275
| ML23352A275 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/23/2024 |
| From: | Scott Wall NRC/NRR/DORL/LPL3 |
| To: | Coffey B Florida Power & Light Co |
| Wall S, NRR/DORL/LPL3 | |
| References | |
| EPID L-2023-LLA-0132 | |
| Download: ML23352A275 (15) | |
Text
January 23, 2024 Mr. Robert Coffey Executive Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop: EX/JB 700 Universe Blvd Juno Beach, FL 33408
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 274 AND 276 REGARDING REVISION TO TECHNICAL SPECIFICATION 5.5.17, PRE-STRESSED CONCRETE CONTAINMENT TENDON SURVEILLANCE PROGRAM (EPID L-2023-LLA-0132)
Dear Mr. Coffey:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 274 and 276 to Renewed Facility Operating License Nos. DPR-24 and DPR-27, respectively, for the Point Beach Nuclear Plant, Units 1 and 2, in response to your application dated September 19, 2023.
The amendments revise Technical Specification (TS) 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program, to replace the reference to Regulatory Guide 1.35, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments, with a reference to Section XI, Subsection IWL of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code. Additionally, the provisions of Surveillance Requirement 3.0.2 in TS 5.5.17 are also deleted by the license amendment.
A copy of the related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions monthly Federal Register notice.
Sincerely,
/RA/
Scott P. Wall, Senior Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301
Enclosures:
- 1. Amendment No. 274 to DPR-24
- 2. Amendment No. 276 to DPR-27
- 3. Safety Evaluation cc: Listserv
NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 274 License No. DPR-24
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by NextEra Energy Point Beach, LLC (the licensee), dated September 19, 2023, 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, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment, and paragraph 4.B of Renewed Facility Operating License No. DPR-24 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 274, are hereby incorporated in the renewed operating license. NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of issuance: January 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.01.23 09:51:12 -05'00'
NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 276 License No. DPR-27
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by NextEra Energy Point Beach, LLC (the licensee), dated September 19, 2023, 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, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment, and paragraph 4.B of Renewed Facility Operating License No. DPR-27 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 276, are hereby incorporated in the renewed operating license. NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Jeffrey A. Whited, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications and Renewed Facility Operating License Date of issuance: January 23, 2024 Jeffrey A.
Whited Digitally signed by Jeffrey A. Whited Date: 2024.01.23 09:51:33 -05'00'
ATTACHMENT TO LICENSE AMENDMENT NO. 274 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-24 AND LICENSE AMENDMENT NO. 276 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Replace the following pages of Renewed Facility Operating License Nos. DPR-24 and DPR-27 and Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Renewed Facility Operating License No. DPR-24 REMOVE INSERT Renewed Facility Operating License No. DPR-27 REMOVE INSERT Appendix A, Technical Specifications REMOVE INSERT 5.5-18 5.5-18 Renewed License No. DPR-24 Amendment No. 274 D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NextEra Energy Point Beach to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E.
Pursuant to the Act and 10 CFR Parts 30 and 70, NextEra Energy Point Beach to possess such byproduct and special nuclear materials as may be produced by the operation of the facility, but not to separate such materials retained within the fuel cladding.
- 4.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A.
Maximum Power Levels NextEra Energy Point Beach is authorized to operate the facility at reactor core power levels not in excess of 1800 megawatts thermal.
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 274, are hereby incorporated in the renewed operating license.
NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.
C. Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensees application dated March 21, 1978, as supplemented and amended. In the event that the on-site verification check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.
Renewed License No. DPR-27 Amendment No. 276 C. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NextEra Energy Point Beach to receive, possess and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed source for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; D. Pursuant to the Act and 10 CFR Parts 30, 40 and 70, NextEra Energy Point Beach to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and E.
Pursuant to the Act and 10 CFR Parts 30 and 70, NextEra Energy Point Beach to possess such byproduct and special nuclear materials as may be produced by the operation of the facility, but not to separate such materials retained within the fuel cladding.
- 4.
This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Section 30.34 of 10 CFR Part 30, Section 40.41 of 10 CFR Part 40, Sections 50.54 and 50.59 of 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:
A.
Maximum Power Levels NextEra Energy Point Beach is authorized to operate the facility at reactor core power levels not in excess of 1800 megawatts thermal.
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 276, are hereby incorporated in the renewed operating license.
NextEra Energy Point Beach shall operate the facility in accordance with Technical Specifications.
C. Spent Fuel Pool Modification The licensee is authorized to modify the spent fuel storage pool to increase its storage capacity from 351 to 1502 assemblies as described in licensees application dated March 21, 1978, as supplemented and amended. In the event that the on-site verification check for poison material in the poison assemblies discloses any missing boron plates, the NRC shall be notified and an on-site test on every poison assembly shall be performed.
Point Beach 5.5-18 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Reactor Coolant System (RCS) Pressure Isolation Valve (PIV)
Leakage Program A program shall be established to verify the leakage from each RCS PIV is within the limits specified below, in accordance with the Event V Order, issued April 20, 1981.
a.
Minimum differential test pressure shall not be less than 150 psid.
b.
Leakage rate acceptance criteria are:
- 1. Leakage rates less than or equal to 1.0 gpm are considered acceptable.
- 2. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
- 3. Leakage rates greater than 1.0 gpm but less than or equal to 5.0 gpm are considered unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
- 4. Leakage rates greater than 5.0 gpm are considered unacceptable.
5.5.17 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity.
The program shall include baseline measurements prior to initial operations. The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC.
The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.
Unit 1 - Amendment No. 274 Unit 2 - Amendment No. 276
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 274 AND 276 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-24 AND DPR-27, RESPECTIVELY NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301
1.0 INTRODUCTION
By application to the U.S. Nuclear Regulatory Commission (NRC, the Commission) dated September 19, 2023 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML23262B018), NextEra Energy Point Beach, LLC (the licensee) submitted a license amendment request (LAR) for the Point Beach Nuclear Plant, Units 1 and 2 (Point Beach).
The proposed amendments consist of changes to the Point Beach technical specifications (TSs) that would revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program, to replace the reference to Regulatory Guide (RG) 1.35, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments, with a reference to Section XI, Subsection IWL of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code). The proposed amendments would also delete the provisions of Surveillance Requirement (SR) 3.0.2 in TS 5.5.17. Additionally, the proposed amendments would align the Point Beach TSs with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, Codes and standards, and the required containment inservice inspection (ISI) program.
2.0 REGULATORY EVALUATION
The guidance for developing a containment ISI program was provided with the issuance of RG 1.35 in February 1973 (ML12305A260). The final revision of RG 1.35, Revision 3, was issued in July 1990 (ML003740007). In a Federal Register notice dated August 8, 1996 (61 FR 41303), the NRC amended 10 CFR 50.55a to incorporate, by reference, Subsections IWE and IWL of Section XI of the ASME Code. Subsection IWL includes the requirements for ISI of concrete containments and includes the guidance provided in RG 1.35. Therefore, RG 1.35 was made obsolete when the requirements of ASME Section XI, Subsection IWL, were incorporated by reference into 10 CFR 50.55a. The NRC withdrew RG 1.35 in August 2015 (ML15040A665).
Pursuant to 10 CFR 50.55a(g)(4), Inservice inspection standards requirement for operating plants, throughout the service life of a nuclear power facility, components that are classified as Class CC pressure retaining components must meet the requirements, except design and access provisions and preservice examination requirements, set forth in Section XI of the ASME Code, Subsection IWL, as incorporated by reference in 10 CFR 50.55a(a)(1)(ii), ASME Boiler and Pressure Vessel Code,Section XI, subject to the conditions listed in 10 CFR 50.55a(b)(2)(ix),Section XI condition: Metal containment examinations.Section XI, Subsection IWL of the ASME Code provides rules for ISI and repair/replacement activities of the reinforced concrete and post-tensioning system components of Class CC containment structures. The appropriate edition of the code to be used for successive 120-month inspection intervals is determined pursuant to 10 CFR 50.55a(g)(4)(ii), Applicable ISI Code: Successive 120-month intervals.
Paragraph 50.55a(g)(5)(ii), ISI program update: Conflicting ISI Code requirements with technical specifications, of 10 CFR requires that if a revised ISI program for a facility conflicts with the TSs for the facility, the licensee must apply to the Commission for amendment of the TSs to conform the TSs to the revised program.
Paragraph 50.36(c) of 10 CFR requires TSs to include items in the following categories:
(1) safety limits, limiting safety systems settings, and limiting control settings; (2) limiting conditions for operation; (3) SRs; (4) design features; (5) administrative controls; (6) decommissioning; (7) initial notification; and (8) written reports. Paragraph 50.36(c)(5),
Administrative controls, of 10 CFR states 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.
3.0 TECHNICAL EVALUATION
The licensee proposed to revise Point Beach TS 5.5.17 to replace the reference to RG 1.35 with a reference to Section XI, Subsection IWL of the ASME Code. In addition, the licensee proposed to delete the applicability of SR 3.0.2 to the tendon surveillance program inspection frequencies. Specifically, the TS will be revised to state, in part:
The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption or relief has been authorized by the NRC.
The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.
The NRC staff reviewed the proposed TS changes and noted that RG 1.35 has been withdrawn by the NRC and that concrete containment ISI requirements are now captured in the ASME Code,Section XI, Subsection IWL, as incorporated by reference in 10 CFR 50.55a. Therefore, it is no longer appropriate to reference RG 1.35 in Point Beach TS 5.5.17; the proposed revision updates the TS to accurately reflect the Point Beach containment ISI program. Additionally, Point Beach SR 3.0.2 states, in part:
The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified In the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
The NRC staff notes that the ASME Code,Section XI, Subsection IWL specifies how frequently inspections must occur and provides requirements for extending inspection frequencies.
Therefore, it is no longer necessary for SR 3.0.2 to apply to TS 5.5.17.
The NRC staff also notes that proposed wording to both TS 5.5.17 and BASES B 3.6.1 are consistent with the wording contained in NUREG-1431, Standard Technical Specifications -
Westinghouse Plants, Volume 1, Specifications, and Volume 2, Bases, Revision 5.0, dated September 2021 (ML21259A155 and ML21259A159, respectively).
Based on its review, the NRC staff finds that it is acceptable for the licensee to update Point Beach TS 5.5.17 to remove the references to RG 1.35 and SR 3.0.2 and to revise the TS to note that the Tendon Surveillance Program is in accordance with the ASME Code,Section XI, Subsection IWL. These changes align TS 5.5.17 with the requirements of 10 CFR 50.55a and continue to meet 10 CFR 50.36(c)(5) by providing administrative controls to assure operation of the facility in a safe manner.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, on December 15, 2023, the Wisconsin State official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR part 20 or change surveillance requirements. The NRC staff has determined that the amendments involve 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 published a proposed finding in the Federal Register on October 31, 2023 (88 FR 74526) that the amendments involve no significant hazards consideration and there has been no public comment on such finding.
Accordingly, the amendments meet 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 amendments.
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: S. Wall, NRR C. Ashley, NRR S. Lai, NRR Date of issuance: January 23, 2024
ML23352A275 NRR-058 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DEX/ESEB/BC NAME SWall SRohrer (ABaxter for)
ITseng (GThomas for)
DATE 12/15/2023 12/19/2023 12/19/2023 OFFICE NRR/DSS/STSB/BC (A)
OGC - NLO NRR/DORL/LPL3/BC NAME SMehta(ARussell for)
AGhosh-Naber JWhited DATE 12/19/2023 01/22/2024 01/23/2024 OFFICE NRR/DORL/LPL3/PM NAME SWall DATE 01/23/2024