ML20241A058
| ML20241A058 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/25/2020 |
| From: | Booma Venkataraman Plant Licensing Branch III |
| To: | Moul D Point Beach |
| Venkataraman B-NRR/DORL 301-415-2934 | |
| References | |
| EPID L-2020-LLA-0180 | |
| Download: ML20241A058 (15) | |
Text
September 25, 2020 Mr. Don Moul Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company NextEra Energy Point Beach, LLC NextEra Energy Seabrook, LLC Mail Stop: NT3/JW 15430 Endeavor Drive Jupiter, FL 33478
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 1 - ISSUANCE OF AMENDMENT NO. 267 RE: ONE-TIME EXTENSION OF RENEWED FACILITY OPERATING LICENSE CONDITION 4.I, CONTAINMENT BUILDING CONSTRUCTION TRUSS (EPID L-2020-LLA-0180 [COVID-19])
Dear Mr. Moul:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 267 to Renewed Facility Operating License No. DPR-24 for the Point Beach Nuclear Plant, Unit 1 (Point Beach Unit 1). The amendment consists of changes to the Renewed Facility Operating License in response to the NextEra Energy Point Beach, LLC application dated August 13, 2020, as supplemented by letter dated September 15, 2020.
The amendment modifies the Point Beach Unit 1 Renewed Facility Operating License Condition 4.I, Containment Building Construction Truss, to extend elements of the license condition on a one-time basis. This one-time extension was requested due to unforeseen issues as a result of the Coronavirus Disease 2019 public health emergency.
A copy of the related Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commissions Federal Register notice.
Sincerely,
/RA/
Booma Venkataraman, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-266
Enclosures:
- 1. Amendment No. 267 to DPR-24
- 2. 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. 267 Renewed 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 August 13, 2020, as supplemented by letter dated September 15, 2020, 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, by Amendment No. 267, Renewed Facility Operating License No. DPR-24 is hereby amended by changes as indicated in the attachment to this license amendment.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented in accordance with the completion dates specified in Paragraph 4.I in the attachment to this license amendment.
FOR THE NUCLEAR REGULATORY COMMISSION Nancy L. Salgado, Chief Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License Date of issuance: September 25, 2020 Robert F.
Kuntz Digitally signed by Robert F. Kuntz Date: 2020.09.25 12:57:25 -04'00'
ATTACHMENT TO AMENDMENT NO. 267 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-24 POINT BEACH NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-266 Replace the following page of Renewed Facility Operating License No. DPR-24 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 G. Secondary Water Chemistry Monitoring Program NextEra Energy Point Beach shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:
- 1.
Identification of a sampling schedule for the critical parameters and control points for these parameters;
- 2.
Identification of the procedures used to quantify parameters that are critical to control points;
- 3.
Identification of process sampling points;
- 4.
Procedure for the recording and management of data;
- 5.
Procedures defining corrective actions for off control point chemistry condition; and
- 6.
A procedure for identifying the authority responsible for the interpretation of the data, and the sequence and timing of administrative events required to initiate corrective action.
H. The licensee is authorized to repair Unit 1 steam generators by replacement of major components. Repairs shall be conducted in accordance with the licensees commitments identified in the Commission approved Point Beach Nuclear Plant Unit No. 1 Steam Generator Repair Report, dated August 9, 1982 and revised March 1, 1983 and additional commitments identified in the staffs related safety evaluation.
I.
Containment Building Construction Truss NextEra Energy Point Beach shall complete implementation items 1, 2, 3, 5, and 6 included in Attachment 3 of licensee letter NRC 2019-0007 dated March 13, 2019 in accordance with the updated descriptions and completion dates in Attachment 3 of the Enclosure to licensee letter NRC 2020-0020 dated August 13, 2020.
J.
Deleted K. All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation. All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC, as required by 10 CFR Part 50, Appendix H.
L.
Mitigation Strategy Strategies shall be developed and maintained for addressing large fires and explosions that include the following key areas:
Renewed License No. DPR-24 Amendment No. 267
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 267 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-24 NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-266
1.0 INTRODUCTION
By letter dated August 13, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML20226A313), as supplemented by letter dated September 15, 2020 (ADAMS Accession No. ML20259A372), NextEra Energy Point Beach, LLC (NextEra, the licensee) submitted a license amendment request (LAR) to modify the Point Beach Nuclear Plant, Unit 1 (Point Beach Unit 1) Renewed Facility Operating License (RFOL) Condition 4.I, Containment Building Construction Truss, to extend elements of the license condition on a one-time basis. This one-time extension is requested due to unforeseen issues as a result of the Coronavirus Disease 2019 (COVID-19) public health emergency (PHE).
Specifically, the proposed change to RFOL Condition 4.I would effectuate a one-time extension of implementation items 1, 2, and 6 included in Attachment 3 of the licensees letter dated March 13, 2019 (ADAMS Accession No. ML19072A179). For existing implementation items 1 and 2, the licensee requested an additional 18 months until the spring of 2022, when the Point Beach Unit 1, Cycle 40 refueling outage is currently scheduled, to complete these implementation items, as opposed to the existing completion date of the fall 2020 Point Beach Unit 1, Cycle 39 refeuling outage. For existing implementation item 6, the licensee requested a completion date of 6 months after the completion of the Point Beach Unit 1, Cycle 40 refueling outage, as opposed to the existing completion date of March 31, 2021.
The supplemental letter dated September 15, 2020, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC, the Commission) staffs original proposed no significant hazards consideration determination as published in the Federal Register on August 25, 2020 (85 FR 52370).
2.0 REGULATORY EVALUATION
2.1 Background
The proposed change to RFOL Condition 4.I to effectuate a one-time extension of implementation items 1, 2, and 6 is associated with a requirement to complete plant modifications to resolve legacy design code nonconformances associated with construction truss in the containment building of Point Beach Unit 1 as approved by the NRC by Amendment No. 263, dated March 26, 2019 (ADAMS Accession No. ML18345A110). This amendment requires the licensee to complete implementation items 1, 2, 3, 5, and 6 included in of the licensees letter dated March 13, 2019 by completion dates specified in that attachment.
In the LAR dated August 13, 2020, NextEra stated:
The plant modification items are required to be completed to improve clearance between the truss and the containment liner at specified locations around the containment circumference. The modifications to the top chord of the trusses are necessary to achieve contact forces and component stresses within acceptable limits. The proposed modification to the containment spray pipe support (Sl-301R-1-H202) increases the available seismic capacity to qualify the support for the applied loading.
NextEra also stated:
On March 13, 2020, President Donald Trump declared the Coronavirus 2019 (COVID-19) pandemic a national emergency. In addition, Wisconsin Governor Tony Evers declared a public health emergency on March 12, 2020 to support efforts to respond to and contain COVID-19. Governor Tony Evers also issued an emergency order effective August 1, 2020 requiring face coverings in certain situations to prevent the spread of COVID-19.
2.2 Applicable Regulatory Requirements Title 10 of the Code of Federal Regulations (10 CFR) 50.90, Application for amendment of license, construction permit, or early site permit, sets forth the requirements for amending operating licenses for nuclear power reactors.
In the LAR dated August 13, 2020, NextEra stated:
The proposed one-time extension to the RFOL Condition 4.I for items 1, 2, and 6 included in Attachment 3 of NextEra letter NRC 2019-0007 [ADAMS Accession No. ML19072A179] to that as specified in Attachment 3 of [the] Enclosure [to the August 13, 2020 LAR] does not alter the manner in which Point Beach [Unit 1]
will be operated and maintained. All applicable regulatory requirements will continue to be satisfied as a result of the proposed amendment.
2.3 Licensees Proposed Changes RFOL Condition 4.I, implementation items 1 and 2, involving plant modifications, are currently required to be completed during the fall 2020 Point Beach Unit 1, Cycle 39 refueling outage, and implementation item 6, involving revising the Updated Final Safety Analysis Report (UFSAR), is currently required to be completed by March 31, 2021.
The current Point Beach Unit 1 RFOL Condition 4.I states:
Containment Building Construction Truss NextEra Energy Point Beach shall complete implementation items 1, 2, 3, 5, and 6 included in Attachment 3 of licensee letter NRC 2019-0007, dated March 13, 2019, by the completion date specified in the Attachment.
In the LAR dated August 13, 2020, NextEra proposed to amend the Point Beach Unit 1 RFOL Condition 4.I, such that it would read as follows:
Containment Building Construction Truss NextEra Energy Point Beach shall complete implementation items 1, 2, 3, 5, and 6 included in Attachment 3 of licensee letter NRC 2019-0007 dated March 13, 2019 in accordance with Attachment 3 of the Enclosure to NRC Letter, NRC 2020-0020 dated August 13, 2020.
of the Enclosure to the LAR dated August 13, 2020, renumbers implementation items 1, 2, 3, 5, and 6 as 1, 2, 3, 4, and 5, respectively, deletes superceded language, and changes the completion dates for existing and revised implementation items 1 and 2 from fall 2020 to Spring 2022 and changes the completion date for existing implementation item 6 (revised implementation item 5) from by March 31, 2021 to within 6 months of the output breaker closure from [the Spring 2022 Point Beach Unit 1, Cycle 40 refueling outage]
completion.
On September 14, 2020, the NRC staff provided comments to the licensee on the language of the proposed Point Beach Unit 1 RFOL Condition 4.I. In response, on September 15, 2020, NextEra supplemented its application and revised the proposed Point Beach Unit 1 RFOL Condition 4.I to read as follows:
Containment Building Construction Truss NextEra Energy Point Beach shall complete implementation items 1, 2, 3, 5, and 6 included in Attachment 3 of licensee letter NRC 2019-0007 dated March 13, 2019 in accordance with the updated descriptions and completion dates in of the Enclosure to licensee letter NRC 2020-0020 dated August 13, 2020.
3.0 TECHNICAL EVALUATION
3.1 Description of Proposed Changes Existing Implementation Item 1 (Spatial Clearance)
This implementation item consists of modification to the Point Beach Unit 1 construction truss to improve clearance between the truss and the containment liner to achieve contact forces and component stresses within acceptable limits. The modification includes a small amount of material removal at the truss top chord structural tees. The modification will be performed at six specified locations around the circumference of containment. The licensee indicated that no change to the methods of evaluation or acceptance limits defined for associated components is necessary.
Existing Implementation Item 2 (Containment Spray Pipe Support)
This implementation item consists of modification to one containment spray pipe support, Sl-301R-1-H202, to achieve additional seismic capacity. The modification will increase the size of the supports U-bolt diameter.
Existing Implementation Item 6 (New Construction Truss Design Code Conformance)
This implementation item consists of revising the Point Beach Units 1 and 2 UFSAR to include the evaluation methods and acceptance criteria identified in NextEras response to NRCs request for additional information (RAI)-1.a in letter NRC 2018-0014, dated April 12, 2018 (ADAMS Accession No. ML18102B164). This implementation item also consists of revising the UFSAR to reclassify the construction truss as stated in the NextEra response to RAl-17 in letter NRC 2018-0014, dated April 12, 2018.
3.2 Licensees Technical Evaluation of Proposed Changes NextEra stated that the calculations prepared for Amendment No. 263 that was reviewed and approved by the NRC by letter dated March 26, 2019, are not affected by the proposed change to RFOL Condition 4.I to effectuate a one-time extension of implementation items 1, 2, and 6.
The licensee explained that these calculations supported the conclusion that the construction truss, equipment supported by the truss, and the containment liner maintain structural integrity during a design basis seismic or thermal event. Consequently, the LAR dated August 13, 2020, involves no changes to any existing design functions and no changes to station accident response credited in the safety analyses.
The licensee stated that the probabilistic risk assessment (PRA) evaluation for Point Beach Units 1 and 2, previously performed by the licensee to support Amendment No. 263, demonstrated that the risk will remain within acceptable NRC guidelines with the final configuration of the Unit 1 truss (i.e., the configuration after the completion of implementation items 1 and 2). The licensee stated that the PRA evaluation was performed for the final truss configuration, and did not include consideration of the completion time for the modifications.
Therefore, the results of the PRA evaluation do not change for the proposed one-time extension.
The licensee stated that the Point Beach Unit 1 truss structure, in the current condition, remains operable-but-nonconforming to the original design code of record for the design basis event or accident. The operability evaluations concluded that the truss structures maintain structural integrity and do not pose an interaction concern with the safety-related equipment adjacent to or below the truss structure. The proposed one-time extension of implementation items 1, 2, and 6 does not change the operable-but-nonconforming declaration for Point Beach Unit 1 structures, systems, and components (SSCs) for the proposed extended period.
Based on these statements, the licensee concluded that the proposed one-time extension of implementation items 1, 2, and 6 does not impact the continued safe operation of Point Beach Unit 1.
3.3 NRC Staffs Technical Evaluation of Proposed Changes In its LAR dated August 13, 2020, the licensee proposed to change RFOL Condition 4.I to effectuate a one-time extension of implementation items 1, 2, and 6. For existing implementation items 1 and 2, the licensee requested an additional 18 months until the spring of 2022, when the Point Beach Unit 1, Cycle 40 refueling outage is currently scheduled, to complete these implementation items, as opposed to the existing completion date of the fall 2020 Point Beach Unit 1, Cycle 39 refeuling outage. For existing implementation item 6, the licensee requested a completion date of 6 months after the completion of the Point Beach Unit 1, Cycle 40 refueling outage, as opposed to the existing completion date of March 31, 2021.
In response to the COVID-19 PHE, the licensee stated that it plans to reduce the scope of the fall 2020 refueling outage to reduce the number of employees at Point Beach Unit 1, which would, in turn, minimize the threat of the virus to station personnel and, consequently, help ensure the continued safe operation of the plant. NextEra indicated that it does not want to potentially expose and jeopardize the health and safety of station personnel during the PHE.
Based on these concerns, NextEra determined that it would not be prudent to complete the modification activities associated with implementation items 1 and 2 during the fall 2020 refueling outage; instead, the one-time extension of these implementation items to the spring 2022 refueling outage would reduce the staffing required to support the fall 2020 refueling outage and, therefore, help reduce the probability of spread of COVID-19 to station personnel.
Existing implementation item 6 is an administrative task to revise the Point Beach UFSAR to reflect the as-built plant after the completion of the plant modifications. Since implementation items 1 and 2 are proposed to be extended, the completion date for implementation item 6 would also have to be extended in order for it to continue to be due after the completion of implementation items 1 and 2.
The NRC staff reviewed the licensees request and notes that the proposed one-time extension of implementation items 1, 2, and 6, through amending RFOL Condition 4.I as described above, is due to unforeseen issues as a result of the COVID-19 PHE. The NRC staff notes that reducing the probability of the spread of COVID-19 at the facility and, thereby, reducing the probability of a decrease in the station personnel available to be onsite, decreases operational risk. The NRC staff also notes that the implementation items are requirements based on the NRCs previous approval of Amendment No. 263 and that the licensee continues to satisfy all regulatory requirements for this approval.
The NRC staff notes that the proposed one-time extension of implementation items 1, 2, and 6 does not involve any physical changes to the facility or any changes in the operation of the facility. The NRC staff also notes that the proposed one-time extension does not change the operable-but-nonconforming declaration for Point Beach Unit 1 SSCs for the proposed extended period, and does not impact the current safe operation of Point Beach Unit 1. Finally, the proposed one-time extension does not affect the validity of the staffs prior approval of Amendment No. 263, which was not dependent on the completion time for the modifications.
Accordingly, the NRC staff finds that the proposed one-time extension continues to provide reasonable assurance of adequate protection of public health and safety for Point Beach Unit 1.
Based on the foregoing, the NRC staff concludes that the proposed one-time extension of implementation items 1, 2, and 6, as proposed in the LAR dated August 13, 2020, as supplemented, is acceptable.
4.0 FINAL NO SIGNIFICANT HAZARDS CONSIDERATION
DETERMINATION The NRC proposed to determine that the LAR involves no significant hazards consideration in the Federal Register on August 25, 2020 (85 FR 52379). The NRCs regulation in 10 CFR 50.92(c) states that the NRC may make a final determination, under the procedures in 10 CFR 50.91, that a proposed license amendment involves no significant hazards consideration if operation of the facility, in accordance with the proposed amendment, would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.
An evaluation of the issue of no significant hazards consideration is presented below.
- 1.
Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The probability of an accident previously evaluated is not changed. The containment structures and the containment spray piping and ventilation ducts attached to the construction truss are accident mitigation equipment. They are not accident initiators.
The calculations prepared for Amendment No. 263 that was reviewed and approved by the NRC are not affected by the requested deferral of the elements noted in Attachment 3 of the Enclosure to the LAR. The Unit 1 truss structure, in the current condition, remains operable but nonconforming to the original design code of record for the design basis event or accident. The affected structures, systems, and components are passive and there is no adverse effect on accident mitigation strategies.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2.
Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
This request does not install any new or different type of equipment in the plant.
The proposed change does not create any new failure modes for existing equipment or any new limiting single failures.
Evaluations performed in support of operability under the original design basis conclude the construction truss, equipment supported by the truss, and containment liner remain capable of withstanding design basis seismic and thermal events and remain capable of performing their designated design functions. Additionally, the proposed change does not involve a change in the methods governing normal plant operation, and all safety functions will continue to perform as previously assumed in the accident analyses. Thus, the proposed change does not adversely affect the design function or operation of any structures, systems, and components important to safety.
There are no new accidents identified associated with acceptance of the final modified configuration of Point Beach Unit 1 or in the current configuration.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3.
Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The containment structures and liner, construction truss, and equipment supported by the truss remain fully capable of performing their specified design functions as concluded by supporting the operability evaluations for the original design basis.
The proposed change does not affect the margin of safety associated with confidence in the ability of the fission product barriers (i.e., fuel cladding, reactor coolant system pressure boundary, and containment structure) to limit the level of radiation dose to the public. The proposed change does not alter any safety analyses assumptions, safety limits, limiting safety system settings, or methods of operating the plant. The changes do not adversely impact the reliability of equipment credited in the safety analyses. The proposed change does not adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above evaluation, the NRC staff concludes that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff has made a final determination that no significant hazards consideration is involved for the proposed amendment.
5.0 STATE CONSULTATION
In accordance with the Commissions regulations, on September 4, 2020, the NRC staff notified officials from the State of Wisconsin of the proposed issuance of the amendment. The State officials had no comments.
6.0 ENVIRONMENTAL CONSIDERATION
The amendment changes requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20. 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 August 25, 2020 (85 FR 52379). 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.
7.0 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: B. Venkataraman Date: September 25, 2020
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