ML19266A585
| ML19266A585 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/17/2019 |
| From: | Ellen Brown Plant Licensing Branch II |
| To: | Moul D Florida Power & Light Co |
| Brown, Eva | |
| References | |
| EPID L-2019-LLA-0024 | |
| Download: ML19266A585 (23) | |
Text
Mr. Don Moul Vice President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop: NT3/JW 15430 Endeavor Drive Jupiter, FL 33478 UNITED STATES December 17, 2019
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4-ISSUANCE OF AMENDMENT NOS. 289 AND 283 REGARDING TECHNICAL SPECIFICATION APPLICABILITY TO EQUIPMENT SHARED BETWEEN UNITS AND EXCEPTION TO TECHNICAL SPECIFICATION 4.0.4 (EPID L-2019-LLA-0024)
Dear Mr. Moul:
The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment No. 289 to Subsequent Renewed Facility Operating License No. DPR-31 and Amendment No. 283 to Subsequent Renewed Facility Operating License No. DPR-41 for Turkey Point Nuclear Generating Unit Nos. 3 and 4, respectively. The amendments change certain technical specifications in response to the application from Florida Power & Light Company dated February 14, 2019, as supplemented by a letter dated July 22, 2019.
The amendments revise certain technical specifications for shared equipment when one unit is defueled and also removes a footnote related to Technical Specification 4.0.4.
A copy of the related safety evaluation is also enclosed. Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Docket Nos. 50-250 and 50-251
Enclosures:
- 1. Amendment No. 289 to DPR-31
- 2. Amendment No. 283 to DPR-41
- 3. Safety Evaluation cc: Listserv Sincerely, IRA/
Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-250 TURKEY POINT NUCLEAR GENERATING UNIT NO. 3 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 289 Subsequent Renewed License No. DPR-31
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power & Light Company (the licensee) dated February 14, 2019, as supplemented by a letter dated July 22, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Subsequent Renewed Facility Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Subsequent Renewed Facility Operating License No. DPR-31 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 289, are hereby incorporated into this subsequent renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this subsequent renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.
Attachment:
Changes to the Subsequent Renewed Facility Operating License and Technical Specifications Date of Issuance: December 1 7, 2 O 1 9 FOR THE NUCLEAR REGULATORY COMMISSION Undine Shoop, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-251 TURKEY POINT NUCLEAR GENERATING UNIT NO. 4 AMENDMENT TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE Amendment No. 283 Subsequent Renewed License No. DPR-41
- 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Florida Power & Light Company (the licensee) dated February 14, 2019, as supplemented by a letter dated July 22, 2019, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 Commission's 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 Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is amended by changes to the Subsequent Renewed Facility Operating License and Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8. of Subsequent Renewed Facility Operating License No. DPR-41 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 283, are hereby incorporated into this subsequent renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this subsequent renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.
Attachment:
Changes to the Subsequent Renewed Facility Operating License and Technical Specifications Date of Issuance: December 1 7, 2 O 1 9 FOR THE NUCLEAR REGULATORY COMMISSION Undine Shoop, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
A TI ACHMENT TO LICENSE AMENDMENTS TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 AMENDMENT NO. 289 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 283 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-41 DOCKET NOS. 50-250 AND 50-251 Replace page 3 of Subsequent Renewed Facility Operating License No. DPR-31 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
Replace page 3 of Subsequent Renewed Facility Operating License No. DPR-41 with the attached revised page 3. The revised page is identified by amendment number and contains a marginal line indicating the area of change.
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 marginal lines indicating the areas of change.
Remove 3/4 5-3 3/4 5-4 3/4 7-6 3/4 8-14 3/4 8-18 3/4 8-20 Insert 3/4 5-3 3/4 5-4 3/4 7-6 3/4 8-14 3/4 8-18 3/4 8-20
3 E.
Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F.
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Units Nos. 3 and 4.
- 3.
This subsequent renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations: 10 CFR Part 20, Unit 3 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 Level
- 8.
C.
The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 289, are hereby incorporated into this subsequent renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this subsequent renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Final Safety Analysis Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on November 1, 2001, describes certain future inspection activities to be completed before the period of extended operation.
The licensee shall complete these activities no later than July 19, 2012.
The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following the issuance of this subsequent renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
Subsequent Renewed License No. DPR-31 Amendment No. 289
3 E.
Pursuant to the Act and 10 CFR Parts 40 and 70 to receive, possess, and use at any time 100 milligrams each of any source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactively contaminated apparatus; F.
Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of Turkey Point Units Nos. 3 and 4.
- 3.
This subsequent 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 Unit 4 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 Level B.
C.
The applicant is authorized to operate the facility at reactor core power levels not in excess of 2644 megawatts (thermal).
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 283, are hereby incorporated into this subsequent renewed license. The Environmental Protection Plan contained in Appendix B is hereby incorporated into this subsequent renewed license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Final Safety Analysis Report The licensee's Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on November 1, 2001, describes certain future inspection activities to be completed before the period of extended operation.
The licensee shall complete these activities no later than April 10, 2013.
The Final Safety Analysis Report supplement as revised on November 1, 2001, described above, shall be included in the next scheduled update to the Final Safety Analysis Report required by 10 CFR 50.71(e)(4), following the issuance of this subsequent renewed license. Until that update is complete, the licensee may make changes to the programs described in such supplement without prior Commission approval, provided that the licensee evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
Subsequent Renewed License No. DPR-41 Amendment No. 283 I
EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS -Tavg GREATER THAN OR EQUAL TO 350°F LIMITING CONDITION FOR OPERATION 3.5.2 The following Emergency Core Cooling System (ECCS) equipment and flow paths shall be OPERABLE:
- a.
Four Safety Injection (SI) pumps, each capable of being powered from its associated OPERABLE diesel generatol', with discharge flow paths aligned to the RCS cold legs,*
- b.
Two RHR heat exchangers,
- c.
Two RHR pumps with discharge flow paths aligned to the RCS cold legs,
- d.
A flow path capable of taking suction from the refueling water storage tank as defined in Specification 3.5.4, and
- e.
Two flow paths capable of taking suction from the containment sump.
APPLICABILITY: MODES 1, 2, and 3**
ACTION:
- a.
With one of the following components inoperable:
- 1.
RHR heat exchanger,
- 2.
RHR suction flow path from the containment sump,
- 3.
RHR parallel injection flow path, or
- 4.
SI parallel injection flow path Restore the inoperable component to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- b.
Deleted
- c.
With one of the four required Safety Injection pumps or its associated discharge flow path inoperable and the opposite unit in MODE 1, 2, or 3, restore the pump or flow path to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- Only three Safety Injection (SI) pumps (two associated with the unit and one from the opposite unit), each capable of being powered from its associated OPERABLE diesel generator1', with discharge flow paths aligned to the RCS cold leg are required if the opposite unit is in MODE 4, 5, 6, or defueled.
- The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 for the Safety Injection flow paths isolated pursuant to Specification 3.4.9.3 provided that the Safety Injection flow paths are restored to OPERABLE status prior to Tavg exceeding 380°F. Safety Injection flow paths may be isolated when Tavg is less than 380°F.
- lnoperability of the required diesel generators does not constitute inoperability of the associated Safety Injection pumps.
TURKEY POINT - UNITS 3 & 4 3/4 5-3 AMENDMENT NOS. 289 AND 283
EMERGENCY CORE COOLING SYSTEMS 3/4.5.2 ECCS SUBSYSTEMS - Tavg GREATER THAN OR EQUAL TO 350°F LIMITING CONDITION FOR OPERATION
- d.
With two of the four required Safety Injection pumps or their associated discharge flow paths inoperable and the opposite unit in MODE 1, 2, or 3, restore one of the two inoperable pumps or flow paths to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This ACTION applies to both units simultaneously.
- e.
With one of the three required Safety Injection pumps or its associated discharge flow path inoperable and the opposite unit in MODE 4, 5, 6, or defueled, restore the pump or flow path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- f.
With a required Safety Injection pump OPERABLE but not capable of being powered from its associated diesel generator, restore the capability within 14 days or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- g.
With an ECCS subsystem inoperable due to an RHR pump or its associated discharge flow path being inoperable, restore the inoperable RHR pump or its associated discharge flow path to OPERABLE status within 7 days or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- h.
With the suction flow path from the refueling water storage tank inoperable, restore the suction flow path to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
TURKEY POINT - UNITS 3 & 4 3/4 5-4 AMENDMENT NOS. 289 AND 283
PLANT SYSTEMS CONDENSATE STORAGE TANK LIMITING CONDITION FOR OPERATION
Opposite Unit in MODES 4, 5, 6 1 or defueled A minimum indicated water volume of 210,000 gallons in either or both condensate storage tanks.
Opposite Unit in MODES 1, 2 or 3 A minimum indicated water volume of 420,000 gallons.
APPLICABILITY:
MODES 1, 2 and 3.
ACTION:
Opposite Unit in MODES 4, 5, 6 1 or defueled With the CST system inoperable, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> restore the CST system to OPERABLE status or be in at least HOT STANDBY in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Opposite Unit in MODES 1, 2 or 3
- 1)
With the CST system inoperable due to indicating less than 420,000 gallons, but greater than or equal to 210,000 gallons indicated, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> restore the inoperable CST system to OPERABLE status or place one unit in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
- 2)
With the CST system inoperable with less than 210,000 gallons indicated, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> restore the CST system to OPERABLE status or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. This ACTION applies to both units simultaneously.
TURKEY POINT - UNITS 3 & 4 3/4 7-6 AMENDMENT NOS. 289 AND 283
D.C. SOURCES LIMITING CONDITION FOR OPERATION ACTION:
- b.
(Continued)
With one of the required battery banks inoperable, or with none of the full-capacity chargers associated with a battery bank OPERABLE, restore all battery banks to OPERABLE status and at least one charger associated with each battery bank to OPERABLE status within two hours* or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This ACTION applies to both units simultaneously.
SURVEILLANCE REQUIREMENTS 4.8.2.1 Each 125-volt battery bank and its associated full capacity charger(s) shall be demonstrated OPERABLE:
- a.
In accordance with the Surveillance Frequency Control Program by verifying that:
- 1)
The parameters in Table 4.8-2 meet the Category A limits, and
- 2)
The total battery terminal voltage is greater than or equal to 129 volts on float charge and the battery charger(s) output voltage is:::: 129 volts, and
- 3)
If two battery chargers are connected to the battery bank, verify each battery charger is supplying a minimum of 10 amperes, or demonstrate that the battery charger supplying less than 10 amperes will accept and supply the D.C. bus load independent of its associated battery charger.
- b.
In accordance with the Surveillance Frequency Control Program and within 7 days after a battery discharge with battery terminal voltage below 105 volts (108.6 volts for spare battery D-52), or battery overcharge with battery terminal voltage above 143 volts, by verifying that:
- 1)
The parameters in Table 4.8-2 meet the Category B limits,
- 2)
The average electrolyte temperature of every sixth cell is above 60°F, and
- 3)
There is no visible corrosion at either terminals or connectors, or verify battery connection resistance is:
Battery Connection Limit (Micro-Ohms) 38, 4A inter-cell / termination
- 5.29 inter-cell (brace locations)
- 5. 30 transition cables
- 5, 125 or total battery connections
- 5. 1958 Battery Connection Limit (Micro-Ohms) 3A, 48, D-52 inter-cell / termination
- 5. 35 inter-cell (brace locations)
- 5, 40 transition cables
- 5. 125 or total battery connections
<2463
- c.
In accordance with the Surveillance Frequency Control Program by verifying that:
- 1)
The cells, cell plates, and battery racks show no visual indication of physical damage or abnormal deterioration,
- can be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the opposite unit is in MODE 5, 6, or defueled and each of the remaining required battery chargers is capable of being powered from its associated diesel generator(s).
TURKEY POINT - UNITS 3 & 4 3/4 8-14 AMENDMENT NOS. 289 AND 283
3/4.8.3 ONSITE POWER DISTRIBUTION OPERATING LIMITING CONDITION FOR OPERATION 3.8.3.1 The following electrical busses* shall be energized in the specified manner with the tie breakers open between redundant busses within the unit** and between the busses of Units 3 and 4.
- a.
One train of AC. Susses consisting of:
- 1) 4160-Volt Bus A,
- 2) 480-Volt Load Center Susses A, C and H***. and
- 3) 480-Volt Motor Control Center Susses A (Unit 4 only), C and D***.
- b.
One train of AC. Susses consisting of:
- 1) 4160-Volt Bus B
- 2) 480-Volt Load Center Susses B, D and H***. and
- 3) 480-Volt Motor Control Center Susses Band D***
- c.
One opposite unit train of AC busses consisting of either:
- 1) 4160-Volt Bus A, 480-Volt Load Center Susses A, C and H***.
and 480-Volt Motor Control Center Susses A (Unit 4 only), C and D***, or
- 2) 4160-Volt Bus B, 480-Volt Load Center Susses B, D and H***,
and 480-Volt Motor Control Center Susses Band D***.
- d.
120 Volt AC Vital Panel 3P06 and 3P21 energized from its associated inverter connected to D.C.
Bus 38.****
- e.
120 Volt AC Vital Panel 4P06 and 4P21 energized from its associated inverter connected to D.C.
Bus 3B.****
- f.
120 Volt AC Vital Panel 3P07 and 3P22 energized from its associated inverter connected to D.C.
Bus 3A****
- g.
120 Volt AC Vital Panel 4P07 and 4P22 energized from its associated inverter connected to D.C.
Bus 3A****
- h.
120 Volt AC Vital Panel 3P08 and 3P23 energized from its associated inverter connected to D.C.
Bus 48.****
- i.
120 Volt AC Vital Panel 4P08 and 4P23 energized from its associated inverter connected to D.C.
Bus 4B.****
- For Motor Control Center busses, vital sections only.
- With the opposite unit in MODE 5, 6, or defueled, its 480-Volt Load Center can be cross-tied under conditions specified in Specification 3.8.3.2.a.
- Electrical bus can be energized from either train of its unit and swing function to opposite train must be OPERABLE for the Unit(s) in MODES 1, 2, 3, and 4.
- A back-up inverter may be used to replace the normal inverter provided the normal inverter on the same DC bus for the opposite unit is not replaced at the same time.
TURKEY POINT - UNITS 3 & 4 3/4 8-18 AMENDMENT NOS. 289 AND 283
ONSITE POWER DISTRIBUTION LIMITING CONDITION FOR OPERATION (Continued}
ACTION:
(Continued) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This ACTION applies to both units simultaneously.
- d.
With one D.C. bus not energized from its associated battery bank or associated charger, reenergize the D.C. bus from its associated battery bank within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s* or in accordance with the Risk Informed Completion Time Program, or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This ACTION applies to both units simultaneously.
SURVEILLANCE REQUIREMENTS 4.8.3.1 The specified busses shall be determined energized and aligned in the required manner by verifying correct breaker alignment and indicated voltage on the buses in accordance with the Surveillance Frequency Control Program.
- Can be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the opposite unit is in MODE 5, 6, or defueled and each of the remaining required battery chargers is capable of being powered from its associated diesel generator(s).
TURKEY POINT - UNITS 3 & 4 3/4 8-20 AMENDMENT NOS. 289 AND 283
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION AMENDMENT NO. 289 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-31 AMENDMENT NO. 283 TO SUBSEQUENT RENEWED FACILITY OPERATING LICENSE NO. DPR-41 FLORIDA POWER & LIGHT COMPANY TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4 DOCKET NOS. 50-250 AND 50-251
1.0 INTRODUCTION
By application dated February 14, 2019, as supplemented by a letter dated July 22, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML19045A617 and ML19203A039, respecitvely), Florida Power & Light Company (the licensee) submitted a license amendment request for Turkey Point Nuclear Generating Unit Nos. 3 and 4 (Turkey Point). The proposed amendments add the defueled condition to the provisions that change the Technical Specification (TS) requirements when one unit is outside the applicability of the TSs. In addition, the change removes from a TS action an inappropriate footnote that allows an exception from TS 4.0.4, which requires that surveillance requirements must be met prior to entering the applicability of a TS.
The supplemental letter dated July 22, 2019, 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 or the Commission) staff's original proposed no significant hazards consideration determination as published in the Federal Register on May 7, 2019 (84 FR 19971).
2.0 REGULATORY EVALUATION
2.1
System Description
The application states that certain plant systems and components that are controlled by the TSs are shared between the two units and that some TS requirements change when only one unit is operating and the other unit is shut down in Mode 4 (Hot Shutdown), 5 (Cold Shutdown), or 6 (Refueling). The systems and components identified in the application are described below.
Safety Injection System The purpose of the safety injection (SI) system, which includes four high head SI pumps, is to automatically deliver cooling water to the reactor core in the event of a loss-of-coolant accident.
With one SI pump associated with the non-accident shutdown unit inoperable and the failure of an emergency diesel generator associated with the accident unit, the emergency core cooling equipment available is two of four SI pumps, one of two residual heat removal pumps, and two of three accumulators. This combination of equipment meets the emergency core cooling design objectives for all break sizes.
Condensate Storage Tanks Two 250,000-gallon condensate storage tanks serve as the normal supply to the auxiliary feedwater pumps. The required volume is sufficient for each unit to achieve hot standby following a loss of offsite power and then either maintain hot standby for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> followed by a cooldown to 350 degrees in 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> or maintain hot standby for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />.
Alternating Current Power System Each unit has three safety-related 4.16 kilovolt (kV) buses. Two of the buses provide power to the A and B trains of engineered safety features in each unit, and the third safety related
- 4. 16 kV bus is utilized as a swing bus. It can be manually aligned to either the train A or train B 4.16 kV bus of its respective unit.
Each unit has five safety-related 480 volt (V) load center buses, four of which are arranged in double-ended load center configuration. Each of the four double ended load center buses is fed from its associated unit by a separate load center transformer. The two transformers of each double-ended unit are energized from different 4.16 kV buses, which ensure the availability of equipment associated with a particular function in the event of loss of one 4.16 kV bus.
The fifth safety-related 480 V load center in each unit is a swing load center. When the 480 V swing load center is connected to either 480 V supply bus, it is an extension of that 480 V supply bus. While the swing load center can be manually aligned to either train A or B, the swing load center bus will automatically transfer in the event of a loss of power on the supply load center to which it was aligned.
Direct Current (DC) Power System Emergency power for vital instrumentation and controls is supplied by a station DC power system, which contains five safety-related 125 V batteries and four DC distribution panels. Two battery banks are associated with each unit, and a spare battery bank can be substituted to allow for testing or maintenance on any of the other four battery banks.
One of the two safety-related battery chargers associated with each battery is powered by a vital motor control center in the same train and unit of its associated battery. The second safety-related battery charger is powered by the vital swing motor control center of the opposite unit.
2.2 Regulations and Guidance Regulations that are applicable to the proposed TS changes include:
1 O CFR 50.36, which requires that TSs include items in the following categories:
(1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCOs); (3) surveillance requirements; (4) design features; (5) administrative controls; (6) decommissioning; (7) initial notification; and (8) written reports.
The regulations in 10 CFR 50.36(c)(2) establish the requirements for LCOs. LCOs are the lowest functional capability or performance level of equipment required for the safe operation of the facility. When an LCO is not met, the licensee must shut down the reactor or follow any remedial action permitted by the TSs until the LCO can be met.
10 CFR 50.90, which requires NRC approval for any modification to, addition to, or deletion from the TSs.
2.3 Licensee's Proposed Changes The licensee's proposed changes modify the following specific LCOs by adding a new "defueled" condition (added text shown in bold):
The footnote associated with LCO 3.5.2 in TS 3/4.5.2, "ECCS [Emergency Core Cooling System] Subsystems - Tavg Greater than or Equal to 350°F," item a, is modified to add the defueled condition:
- Only three Safety Injection (SI) pumps (two associated with the unit and one from the opposite unit), each capable of being powered from its associated OPERABLE diesel generator#, with discharge flow paths aligned to the RCS cold leg are required if the opposite unit is in MODE 4, 5, 6 or defueled.
LCO 3.5.2 Action e is modified to add the defueled condition:
With one of the three required Safety Injection pumps or its associated discharge flow path inoperable and the opposite unit in MODE 4, 5, 6, or defueled....
LCO 3.7.1.3 and action in TS 3/4.7, "Plant System - Condensate Storage Tank," are modified to add the defueled condition:
Opposite Unit in MODES 4, 5, 6, or defueled The Action b footnote associated with SR 3.8.2.1 in TS 3/4.8.2, "D.C. Sources -
Operating," Action b, is modified to add the defueled condition:
- Can be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the opposite unit is in MODE 5, 6, or defueled and each of the remaining required battery chargers is capable of being powered from its associated diesel generator(s).
The footnote associated with LCO 3.8.3.1 in TS 3/4.8.3, "Onsite Power Distribution -
Operating," regarding tie breakers between redundant buses is modified to add the defueled condition:
- With the opposite unit in MODE 5, 6, or Defueled, its 480-Volt Load Center can be cross-tied under conditions specified in Specification 3.8.3.2.a.
The Action D footnote associated with LCO 3.8.3.1 in TS 3/4.8.3 regarding the 2-hour completion time is modified to add the defueled condition:
- Can be extended to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the opposite unit is in MODE 5, 6, or defueled and each of the remaining required battery chargers is capable of being powered from its associated diesel generator(s).
In addition, the licensee proposes a change to LCO 3.5.2, Action c, which addresses the condition of one inoperable SI pump when both units are in the applicability of the TSs. The action has an associated footnote that states:
- The provisions of Specification 4.0.4 are not applicable.
The proposed change deletes this footnote.
3.0 TECHNICAL EVALUATION
3.1 Addition of Defueled Condition The licensee's application provides the following explanation regarding its proposed addition of the defueled condition in certain shared systems:
Certain systems and components, such as SI pumps and 125 volt DC batteries and battery chargers, are shared by Turkey Point Units 3 and 4. The TS below establish requirements for shared systems and components.
TS 3/4.5.2, "ECCS Subsystems-Tavg Greater than or Equal to 350°F," for shared SI pumps TS 3/4.7, "Plant System - Condensate Storage Tank" TS 3/4.8.2, "D.C. Sources - Operating," for shared batteries and battery chargers TS 3/4.8.3, "Onsite Power Distribution - Operating," for shared electrical buses Each of the above TS establishes the operability requirements for the shared equipment when both units are operating in the Applicability of the TS. These TS also contain provisions that change certain requirements when one unit is outside the applicability of the TS. For example, with both units operating in Mode 1, TS 3/4.5.2 requires four operable SI pumps. However, with one unit in Mode 4, 5, or 6 (outside the Applicability of TS 3/4.5.2), the operating unit is required to have only three operable safety injection pumps. Similarly, LCO
- 3. 7.1.3 in TS 3/4. 7 requires a condensate storage tank volume of 420,000 gallons of water with both units operating in Modes 1, 2, or 3; however, with one unit in mode 4, 5, or 6, the required volume is reduced to 210,000 gallons.
The changes in the TS requirements are based on one unit being in a Mode outside the applicability of the TS when the shared equipment only needs to support the operating unit. The provisions in the current TS, however, do not recognize that the non-operating unit could also be in defueled condition, which is outside the applicability of the TS and not a TS-defined Mode. Consequently, a literal application of the current TS would prevent implementing the changes TS requirements when the non-operating unit is in the defueled condition.
The NRC staff evaluated the proposed changes to the TSs in accordance with the requirements in 10 CFR 50.36.
The purpose of LCOs, among other things, is to ensure that safety analysis assumptions are met for accidents that are assumed to occur during reactor operation. Certain LCOs do not apply when the plant is in a condition where the accident is not assumed to occur, such as the condition that the reactor is not operating and contains no fuel. If a unit is operating outside the applicability of the LCO when in Mode 4, 5, or 6, it is similarly operating outside the applicability of the LCO when it is in a defueled condition. The licensee's supplemental letter states:
With the proposed change that clarifies a unit is outside the applicability of a particular TS when fuel has been removed from the reactor, the TS continue to comply with 10 CFR 50.36. For example; when the reactor is defueled, a fuel handling accident remains plausible. Therefore, consistent with 10 CFR 50.36, the TS continue to require operability of TS equipment that is assumed in the safety analysis for mitigation of a fuel handling accident. In this case, the relevant TS have an applicability of "during movement of irradiated fuel," which would be applicable even if the reactor is defueled and the plant is not in a TS-defined operational mode.
Section 50.36 of 10 CFR requires, in part, that the TSs are derived from the analyses and evaluation included in the final safety analysis report and contain safety limits, limiting safety system settings, LCOs, and surveillance requirements. The NRC staff's review of the licensee's Unit 4 Cycle 29 Updated Final Safety Analysis Report (applicable to Turkey Point),
Chapter 14.2.1, "Fuel Handling Accidents Analysis," finds that the licensee's fuel handling accidents evaluation ensures that no hazards are created for two scenarios (and also applies for the unit which is in a "defueled condition"): (a) a fuel assembly is dropped in containment and (b) a spent fuel cask is dropped in the passage between the spent fuel pits of Unit Nos. 3 and 4, while transferring a fuel element between the spent fuel pits.
The NRC staff has also noted the licensee's statement, "The proposed change does not modify any surveillance requirements (SRs) or the applicability of any TS and does not alter the technical requirements of any TS; therefore, the proposed change has no effect on the way the TS comply with 10 CFR 50.36. Following the proposed change, the TS will continue to comply with 10 CFR 50.36 as they do currently."
In response to the NRC staff's request for the licensee to review its licensing basis to confirm that there are no safety requirements, accidents, or events that would need to be reanalyzed if the proposed change is implemented, the licensee stated:
The proposed amendment makes no changes to the technical requirements of any TS and does not modify the applicability of any TS. Therefore, the safety analysis assumptions currently maintained by the TS are unchanged by the proposed amendment. The proposed change is associated only with the status of the opposite unit when it is operating outside the applicability of certain TS.
The current TS relax certain requirements when one unit is operating outside the applicability of the TS and refer to this condition in terms of an operational mode (mode 4, 5, or 6). However, if all fuel is removed from the reactor, the relaxation also applies since, just like in modes 4, 5 and 6, the defueled condition precludes the plant condition in which most accidents are assumed to occur. The proposed amendment makes no changes involving the applicability or technical requirements of TS that apply under conditions for which safety requirements, accidents, or events are assumed to occur. Therefore, no re-analyses are necessary for this change because it does not affect any safety requirements, accidents, or events.
The NRC staff finds the above statement acceptable since no changes to the technical requirements of any TSs are proposed, and the proposed changes do not modify the applicability of any TSs; therefore, no re-analysis is necessary.
Regarding the licensee's proposed changes to the LCO in TS 3/4.5.2, the NRC staff's request for additional information dated July 3, 2019 (ADAMS Accession No. ML19184A100), requested that the licensee explain how the ECCS equipment and flow paths are ensured operable when the opposite unit is in a defueled condition, consistent with current requirements in Mode 4, 5, or
- 6. The licensee's July 22, 2019, response stated:
Surveillance requirements (SRs) demonstrate that LCOs are met, and Turkey Point TS 4.0.1 requires that SRs must be met for LCOs when operating in the modes or other specified conditions in the applicability of the TS. The operability of ECCS equipment and flow paths is ensured by meeting the requirements in SR 4.5.2. Similarly, operability of the condensate storage tank in TS 3. 7.1.3 and operability of the onsite power distribution system in TS 3.8.3.1 are demonstrated by meeting the SR 4. 7.1.3 and SR 4.8.3.1, respectively. The proposed change has no impact on any LCO or the method of demonstrating compliance with LCOs.
Certain systems and components that are controlled by the TS are shared between the two units, and some TS requirements change when only one unit is operating, and the other unit is outside the applicability of the TS. (Appendix A to the Turkey Point Updated Final Safety Analysis provides an evaluation of systems shared by the two units.) In some cases, such as the safety injection pumps required by current TS 3.5.2, the operating unit relies on TS equipment associated with the unit that is in a shutdown or refueling mode to meet the LCO for the unit that is operating. The processes currently in place for demonstrating operability of the required equipment in the unit that is in a shutdown or refueling mode will also be used to demonstrate operability of that equipment when the non-operating unit is in the defueled condition.
The NRC staff's review finds the licensee's response acceptable, since the proposed change does not alter the design, function, or operation of any plant structure, system, or component.
3.2 Elimination of Exception to TS 4.0.4 As stated in Section 2.3 of this safety evaluation, LCO 3.5.2, Action c, addresses the condition of one inoperable SI pump when both units are in the applicability of the TSs. The action has an associated footnote that states, "The provisions of Specification 4.0.4 are not applicable... " The proposed change deletes this footnote.
TS 4.0.4 establishes the requirement that entry into a mode or other specified condition in the applicability of an LCO shall only be made when the LCO's surveillances have been met within their specified frequency, except as provided by Specification 4.0.3. However, in some cases, a surveillance requirement cannot be met or performed prior to entering the mode or other specified condition in the applicability of an LCO. In these situations, the TSs provide an exception to TS 4.0.4 for the affected surveillance requirement.
The current TS contains a footnote that applies the exception from TS 4.0.4 to an action.
Because TS 4.0.4 does not apply to actions, the proposed change deletes this inappropriate footnote. This change does not alter the technical requirements of the TS; rather, it is an administrative change that removes an irrelevant footnote from Action c in LCO 3.5.2.
The NRC staff finds the change acceptable since TS 4.0.4 is not altered and the change is consistent with the Standard Technical Specifications.
3.3 Technical Evaluation Conclusion
The NRC staff finds that the proposed addition of the defueled condition to the LCOs identified above clarifies that the plant conditions outside the applicability of a TSs include not only lower modes but also the defueled condition where the plant is no longer in a TS-defined mode.
Further, since (a) the proposed change does not alter the design, function, or operation of any plant structure, system, or component; (b) the change does not adversely affect the accident analyses analyzed in the licensing basis; and (c) between the combinations of operating unit and shutdown unit ( defueled or in Mode 6 following being defueled with the shutdown unit refueling cavity level greater than 23 feet above top of reactor vessel flange), the capability of any operable TS-required equipment to perform its specified safety function is not impacted, and the outcomes of the accidents previously evaluated remain unaffected upon implementation of the change. Accordingly, the addition of the defueled condition to the licensee's TSs is acceptable. In addition, the NRC staff concurs that deletion of TS 4.0.4 from LCO 3.5.2, Action c, is an administrative change. Based on these considerations, the NRC staff concludes that the proposed changes are acceptable per the applicable regulations specified in Section 2.2 of this safety evaluation.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the NRC staff notified the State of Florida official (Ms. Cynthia Becker, M.P.H., Chief of the Bureau of Radiation Control, Florida Department of Health) on September 20, 2019 (ADAMS Accession No. ML19263E296), 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. 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 issued a proposed finding, which was published in the Federal Register on May 7, 2019 (84 FR 19971 ), 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 Commission's 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: Ravinder Grover Pete Snyder Date: December 17, 2019
SUBJECT:
TURKEY POINT NUCLEAR GENERATING UNIT NOS. 3 AND 4-ISSUANCE OF AMENDMENT NOS. 289 AND 283 REGARDING TECHNICAL SPECIFICATION APPLICABILITY TO EQUIPMENT SHARED BETWEEN UNITS AND EXCEPTION TO TECHNICAL SPECIFICATION 4.0.4 (EPID L-2019-LLA-0024) DATED DECEMBER 17, 2019 DISTRIBUTION:
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DATE 10/1/2019 9/27/2019 9/18/2019 OFFICE NRR/DSS/SRXB/BC(A)** NRR/DE/EEOB/BC(A)**
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