ML20049A010
| ML20049A010 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, Point Beach, Seabrook, Turkey Point, Duane Arnold  |
| Issue date: | 02/24/2020 |
| From: | Justin Poole Plant Licensing Branch 1 |
| To: | Moul D Florida Power & Light Co, Point Beach, NextEra Energy Seabrook |
| Poole J | |
| References | |
| EPID L-2019-LLA-0055 | |
| Download: ML20049A010 (16) | |
Text
February 24, 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, UNITS 1 AND 2; SEABROOK STATION, UNIT NO. 1; AND TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 - CORRECTION LETTER TO AMENDMENT NOS. 265, 268, 164, 290, AND 284 RE: REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-563 (EPID L-2019-LLA-0055)
Dear Mr. Moul:
On February 10, 2020, the U.S. Nuclear Regulatory Commission (NRC) issued the following amendments in response to NextEra Energy Resources/Florida Power & Light Companys application dated March 18, 2019:
Amendment Nos. 265 and 268 to Renewed Facility Operating License Nos. DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2 (Point Beach),
respectively Amendment No. 164 to Renewed Facility Operating License No. NPF-86 for the Seabrook Station, Unit No. 1; Amendment Nos. 290 and 284 to Subsequent Renewed Facility Operating License Nos. DPR-31 and DPR-41 for the Turkey Point Nuclear Generating Unit Nos. 3 and 4, respectively.
The amendments revised the current instrumentation testing definitions of channel calibration, channel operational test, and trip actuating device operational test to permit determination of the appropriate frequency to perform the surveillance requirements based on the devices being tested in each step. The changes were based on Technical Specifications Task Force Traveler, TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program, dated May 10, 2017, which was approved by the NRC on December 4, 2018.
Subsequent to issuance of the amendments, it was determined that incorrect amendment numbers were used for Point Beach, Units 1 and 2. The February 10, 2020 letter and enclosures listed Amendment Nos. 265 and 268 for Renewed Facility Operating License Nos. DPR-24 and DPR-27. Amendment Nos. 266 and 269 are the numbers that should have been used.
Enclosed with this letter are corrected pages that we ask you replace with the previously issued February 10, 2020 amendments. Change bars are added where corrected numbers appear in the enclosed documents. The corrected page 3 for each unit and corrected pages 1.1.1, 1.1-2, and 1.1-6 are also enclosed.
We apologize for any inconvenience caused. If you have any questions, please contact me at 301-415-2048 or Justin.Poole@nrc.gov.
Sincerely,
/RA/
Justin C. Poole, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-266, 50-301, 50-443, 50-250, and 50-251
Enclosures:
- 1. Corrected amendment pages
- 2. Corrected license pages cc: Listserv
Corrected amendment pages
NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 266 Renewed License No. DPR-24
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by NextEra Energy Point Beach, LLC, (the licensee), dated March 18, 2019, 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 the 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. 266, 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 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of issuance: February 10, 2020
NEXTERA ENERGY POINT BEACH, LLC DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 269 Renewed License No. DPR-27
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by NextEra Energy Point Beach, LLC, (the licensee), dated March 18, 2019, 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 the 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. 269, are hereby incorporated in the renewed operating license. NextEra Point Beach shall operate the facility in accordance with Technical Specifications.
- 3.
This license amendment is effective as of the date of issuance and shall be implemented within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
James G. Danna, Chief Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Renewed Facility Operating License and Technical Specifications Date of issuance: February 10, 2020
ATTACHMENT TO LICENSE AMENDMENTS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 AMENDMENT NO. 266 RENEWED FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 269 RENEWED FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 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 3
3 Replace the following page of Renewed Facility Operating License No. DPR-27 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 3
3 Replace the following pages of the Appendix A, Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain a marginal line indicating the areas of change.
Remove Insert 1.1-1 1.1-1 1.1-2 1.1-2 1.1-6 1.1-6
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 266 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-24 AMENDMENT NO. 269 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-27 AMENDMENT NO. 164 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-86 AMENDMENT NO. 290 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 284 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-41 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 SEABROOK STATION, UNIT NO. 1 TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 NEXTERA ENERGY RESOURCES/FLORIDA POWER & LIGHT COMPANY, ET AL.
DOCKET NOS. 50-266, 50-301, 50-443, 50-250, AND 50-251
1.0 INTRODUCTION
By letter dated March 18, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19079A240), NextEra Energy Point Beach, LLC; NextEra Energy Seabrook, LLC; Florida Power & Light Company (NextEra/FPL), requested changes to the Technical Specifications (TSs) for Point Beach Nuclear Plant, Units 1 and 2 (Point Beach);
Seabrook Station, Unit No. 1 (Seabrook); and Turkey Point Generating Unit Nos. 3 and 4 (Turkey Point) (the facilities).
Specifically, NextEra/FPL requested revisions to the current instrumentation testing definitions of Channel Calibration, Channel Operational Test (COT), and Trip Actuating Device Operational Test (TADOT) in the Point Beach TSs, and Channel Calibration, Analog COT, Digital COT, and TADOT in the Seabrook and Turkey Point TSs, to permit determination of the appropriate frequency to perform the surveillance requirement (SR) based on the devices being tested in each step. The proposed changes are based on Technical Specifications Task Force (TSTF)
Traveler, TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program, dated May 10, 2017 (ADAMS Accession No. ML17130A819). The U.S. Nuclear Regulatory Commission (NRC or the Commission) issued a final safety evaluation (SE) approving TSTF-563, Revision 0, on December 4, 2018 (ADAMS Accession No. ML18333A144).
Corrected license pages 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. 266, 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 licensee's 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-24 Amendment No. 266 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 1 O 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 1 O 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. 269, 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 licensee's 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. 269
1.0 USE AND APPLICATION 1.1 Definitions Definitions 1.1
NOTE-----------------------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
ACTIONS ACTUATION LOGIC TEST AXIAL FLUX DIFFERENCE (AFD)
CHANNEL CAUBRA TION CHANNEL CHECK Point Beach Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state required for OPERABILITY of a logic circuit and the verification of the required logic output The ACTUATION LOGIC TEST, as a minimum, shall include a continuity check of output devices.
AFD shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.
A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY.
Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
1.1-1 Unit 1 - Amendment No. 266 Unit 2 - Amendment No. 269
1.1 Definitions CHANNEL OPERATIONAL TEST (COT)
CORE OPERA TING LIMITS REPORT (COLR)
DOSE EQUIVALENT 1-131 DOSE EQUIVALENT Xe-133 INSERVICE TESTING PROGRAM Point Beach Definitions 1.1 A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The COT shall include adjustments, as necessary, of the required alarm, interlock, and trip setpoints required for channel OPERABILITY such that the setpoints are within the necessary range and accuracy. The COT may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.4. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The determination of DOSE EQUIVALENT 1-131 shall be performed using thyroid dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. 11, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion."
DOSE EQUIVALENT Xe-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body Deep Dose Equivalent as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity. The determination of DOSE EQUIVALENT Xe-133 shall be performed using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soil" or the average gamma disintegration energies as provided in ICRP Publication 38, "Radionuclide Transformations," or similar source.
The INSERVICE TESTING PROGRAM is the licensee program that fulfills the requirements of 1 O CFR 50.55a(f).
1.1-2 Unit 1 - Amendment No. 266 Unit 2 - Amendment No. 269
1.1 Definitions TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT)
Point Beach Definitions 1.1 A TADOT shall consist of operating the trip actuating device and verifying the OPERABILITY of all devices in the channel required for trip actuating device OPERABILITY. The TADOT may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
1.1-6 Unit 1 - Amendment No. 266 Unit 2 - Amendment No. 269
ML20049A010 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME JPoole LRonewicz JDanna JPoole DATE 02/18/2020 02/18/2020 02/24/2020 02/24/2020