Text

Issuance of Amendments Regarding Request to Standardize the Required Actions for Inoperability of Auxiliary Feedwater Pumps
	ML15356A611
Person / Time
Site:	Saint Lucie
Issue date:	03/07/2016
From:	Perry Buckberg; Plant Licensing Branch II
To:	Nazar M; Nextera Energy
	Saba F, NRR/DORL/LPLII-2
References
	CAC MF6491, CAC MF6492
	Download: ML15356A611 (23)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 7, 2016 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420

SUBJECT:

ST. LUCIE PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING REQUEST TO STANDARDIZE THE REQUIRED ACTIONS FOR INOPERABILITY OF AUXILIARY FEEDWATER PUMPS (CAC NOS. MF6491 AND MF6492)

Dear Mr. Nazar:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 229 and 179 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Units 1 and 2(St. Lucie), respectively.

These amendments consist of changes to the technical specifications (TSs) in response to your application dated July 15, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15198A028), as supplemented by letter dated December 15, 2015 (ADAMS Accession No. ML16005A147).

These amendments revise the St. Lucie TSs to bring about consistency in the required actions for inoperability of auxiliary feedwater (AFW) pumps. The amendments align the St. Lucie Unit 1 TSs with NUREG-0212, Revision 2, "Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors," on which the St. Lucie Plant, Unit 2, TSs are based, with respect to the required action for the condition where all three AFW pumps are inoperable in Modes 1, 2, and 3.

All work is complete on CAC Nos. MF6491 and MF6492. Accordingly, these CAC Nos. will be closed.

M. Nazar A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

. Buckberg, Senior Project Manager Licensing Branch 11-2 Div ion of Operator Reactor Licensing Offi e of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389

Enclosures:

1. Amendment No. 229 to DPR-67

2. Amendment No. 179 to NPF-16

3. Safety Evaluation cc w/enclosures: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT; UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 229 Renewed License No. DPR-67

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Florida Power & Light Company (the licensee), dated July 15, 2015, as supplemented December 15, 2015, 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.

Enclosure

2. Accordingly, Renewed Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3.B to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 229, are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and Technical Specifications Date of Issuance: Mn:t::h 7, 2016

ATTACHMENT TO LICENSE AMENDMENT NO. 229 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace page 3 of Renewed Facility Operating License No. DPR-67 with the attached page 3.

Replace the following page of the Appendix A Technical Specifications with the attached page.

The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert 3/4 7-4 3/4 7-4

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 or incorporated below:

A. Maximum Power Level FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 3020 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 229 are hereby incorporated in the renewed license.

FPL shall operate the facility in accordance with the Technical Specifications.

Appendix B, the Environmental Protection Plan (Non-Radiological), contains environmental conditions of the renewed license. If significant detrimental effects or evidence of irreversible damage are detected by the monitoring programs required by Appendix B of this license, FPL will provide the Commission with an analysis of the problem and plan of action to be taken subject to Commission approval to eliminate or significantly reduce the detrimental effects or damage.

C. Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on March 28, 2003, describes certain future activities to be completed before the period of extended operation. FPL shall complete these activities no later than March 1, 2016, and shall notify the NRC in writing when implementation of these activities is complete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised on March 28, 2003, described above, shall be included in the next scheduled update to the Updated Final Safety Analysis Report required by 10 CFR 50.71{e)(4), following issuance of this renewed license. Until that update is complete, FPL may make changes to the programs described in such supplement without prior Commission approval, provided that FPL evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

D. Sustained Core Uncoverv Actions Procedural guidance shall be in place to instruct operators to implement actions that are designed to mitigate a small-break loss-of-coolant accident prior to a calculated time of sustained core uncovery.

Renewed License No. DPR-67 Amendment No. 229

PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a. Two motor driven feedwater pumps, and

b. One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With one auxiliary feedwater pump inoperable, restore the auxiliary feedwater pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NOTE LCO 3.0.3 and all other LCO Actions requiring MODE changes are suspended until one AFW um is restored to OPERABLE status.

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status.

d. LCO 3.0.4.b is not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a. In accordance with the Surveillance Frequency Control Program by:

ST. LUCIE - UNIT 1 3/4 7-4 Amendment No. 3§, QQ, 499, ~.

~, 229

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER & LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO, FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST. LUCIE PLANT, UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 179 Renewed License No. NPF-16

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Florida Power & Light Company, et al. (the licensee), dated July 15, 2015, as supplemented December 15, 2015, 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.

Enclosure 2

2. Accordingly, Renewed Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 3. B to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 179, are hereby incorporated in the renewed license. FPL shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULA TORY COMMISSION Benjamin G. Beasley, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and Technical Specifications Date of Issuance: Mm:h 7, 201 6

ATTACHMENT TO LICENSE AMENDMENT NO. 179 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace page 3 of Renewed Facility Operating License No. NPF-16 with the attached page 3.

Replace the following page of the Appendix A Technical Specifications with the attached page.

The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Insert 3/4 7-4 3/4 7-4

neutron sources for reactor startup, sealed sources 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, FPL 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, 40, and 70, FPL to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

3. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission's regulations: 10 CFR Part 20, Section 30.34 of 1O FR Part 30, Section 40.41 of 10 CFR Part 40, Section 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 FPL is authorized to operate the facility at steady state reactor core power levels not in excess of 3020 megawatts (thermal).

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 179 are hereby incorporated in the renewed license.

FPL shall operate the facility in accordance with the Technical Specifications.

Renewed License No. NPF-16 Amendment No. 179

PLANT SYSTEMS AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a. Two feedwater pumps, each capable of being powered from separate OPERABLE emergency busses, and

b. One feedwater pump capable of being powered from an OPERABLE steam supply system.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a. With one auxiliary feedwater pump inoperable, restore the auxiliary feedwater pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NOTE LCO 3.0.3 and all other LCO Actions requiring MODE changes are suspended until one AFW pump is restored to OPERABLE status.

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status.

d. LCO 3.0.4.b is not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.2 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a. In accordance with the Surveillance Frequency Control Program by:

1. Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

ST. LUCIE - UNIT 2 3/4 7-4 Amendment No. ~. 449, ++Q,

~' 179

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 229 AND 17~

TO RENEWED FACILITY OPERATING LICENSES NOS. DPR-67 AND NPF-16 FLORIDA POWER AND LIGHT COMPANY, ET AL.

ST. LUCIE PLANT. UNITS 1 AND 2 DOCKET NOS. 50-335 AND 50-389

1.0 INTRODUCTION

By letter dated July 15, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15198A028), as supplemented by letter dated December 15, 2015 (ADAMS Accession No. ML16005A147), Florida Power & Light Company, et al. (FPL or the licensee) requested amendments to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant (St. Lucie), Units 1 and 2, respectively. The proposed amendment would modify the St. Lucie technical specifications (TSs) to bring about consistency in the required actions for inoperability of auxiliary feedwater (AFW) pumps. These amendments align the St. Lucie, Unit 1, TSs with NUREG-0212, Revision 2, "Standard Technical Specifications for Combustion Engineering Pressurized Water Reactors, on which the St. Lucie, Unit 2, TSs are based, with respect to the required action for the condition where all three AFW pumps are inoperable in Modes 1, 2, and 3.

The supplement dated December 15, 2015, 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) staff's original proposed no significant hazards consideration determination as published in the Federal Register on November 24, 2015 (80 FR 73237).

2.0 REGULATORY EVALUATION

Title 10 of the Code of Federal Regulations (10 CFR), Section 36, "Technical specifications,

paragraph (c)(2), "Limiting conditions for operation, states:

(i) Limiting conditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. When a limiting condition for operation of any process step in the system of a fuel reprocessing plant is not met, the licensee shall shut down that part of the operation or follow any remedial Enclosure 3

action permitted by the technical specifications until the condition can be met. In the case of a nuclear reactor not licensed under§ 50.21 (b) or§ 50.22 of this part or fuel reprocessing plant, the licensee shall notify the Commission, review the matter, and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude recurrence. The licensee shall retain the record of the results of each review until the Commission terminates the license for the nuclear reactor or the fuel reprocessing plant. In the case of nuclear power reactors licensed under§ 50.21 (b) or§ 50.22, the licensee shall notify the Commission if required by § 50. 72 and shall submit a Licensee Event Report to the Commission as required by§ 50.73. In this case, licensees shall retain records associated with preparation of a Licensee Event Report for a period of three years following issuance of the report. For events which do not require a Licensee Event Report, the licensee shall retain each record as required by the technical specifications.

(ii) A technical specification limiting condition for operation of a nuclear reactor must be established for each item meeting one or more of the following criteria:

(A) Criterion 1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.

(8) Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a design basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

(C) Criterion 3. A structure, system, or component that is part of the primary success path and which functions or actuates to mitigate a design basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

(D) Criterion 4. A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

The regulation in 10 CFR Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants," states:

Criterion 34 -Residual heat removal. A system to remove residual heat shall be provided. The system safety function shall be to transfer fission product decay heat and other residual heat from the reactor core at a rate such that specified acceptable fuel design limits and the design conditions of the reactor coolant pressure boundary are not exceeded.

3.0 BACKGROUND

3.1 St. Lucie, Unit 1 St. Lucie Updated Final Safety Analysis Report (UFSAR, Unit 1) Section 10.5, "Auxiliary Feedwater System," provides a description of the AFW system. The design basis of the AFW system is to provide cooling water to either one or both steam generators during normal shutdown and accident conditions to ensure (1) sufficient capability for the removal of sensible and decay heat from the reactor coolant system (RCS) during forced or natural circulation cooldown, assuming a single active failure concurrent with a loss of offsite power, and (2) sufficient capacity to reduce RCS temperature to the entry conditions for the shutdown cooling system (SOCS) under normal conditions, assuming a single active failure and loss of offsite power.

UFSAR Section 10.5 also states that the major active components of the system consist of three AFW pumps. One of the three AFW pumps is driven by a noncondensing steam turbine.

The other two AFW pumps are motor-driven pumps and are powered from the emergency diesel generators (EDGs) in case of loss of normal power. The three AFW pumps take suction from the condensate storage tank (CST) and discharge to the steam generators (SGs). The turbine-driven AFW pump is capable of supplying AFW flow to the SGs for the total expected range of SG pressure by means of a variable speed turbine driver controlled by a variable speed hydraulic governor. The turbine-driven AFW pump relies solely on a direct current (de) power supply; the valves associated with the turbine-driven pumps also are powered from a de source. Each motor-driven AFW pump generally supplies feedwater to one SG. A cross connection has been provided to enable the routing of the flow of the two motor-driven AFW pumps to one SG. The turbine-driven AFW pump supplies feedwater to both SGs by means of two separate lines, each with its own control valve. The control of AFW flow and SG level is normally accomplished by means of control-room operated control valves, each sized to pass the full flow.

During normal operation, feedwater is supplied to the SGs by the feedwater system. If this system is unavailable due to loss of feedwater pumps or offsite power, SG feedwater levels will decrease. The AFW system is provided with complete sensor and control instrumentation to enable the system to automatically respond to a loss of SG inventory. Should the SG level decrease to the low SG level trip setpoint, a signal starts the AFW pumps associated with the SG with a low water level and fully opens the isolation valves, thus providing AFW flow to that SG. If the AFW pumps were operating when offsite power was lost, the AFW pumps would automatically restart using EOG power.

The St. Lucie, Unit 1, TSs are based on NUREG-0212, Revision 1(August1979).

NUREG-0212, Revision 1, has the following Action for TS 3. 7 .1.2:

With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two capable of being powered from separate emergency busses and one capable of being powered by an OPERABLE steam supply system) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The St. Lucie, Unit 2, TSs are based on NUREG-0212, Revision 2. NUREG-0212, Revision 2, has the following Action for TS 3.7.1.2:

a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With two auxiliary feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

NUREG-1432, Revision 4, Volume 1, "Standard Technical Specifications - Combustion Engineering Plants: Specifications," TS 3.7.5, "Auxiliary Feedwater (AFW) System," states:

CONDITION REQUIRED ACTION COMPLETION TIME B. One AFW train B.1 Restore AFW train to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable in MODE 1, OPERABLE status.

2, or 3 [for reasons other than Condition Al.

C. Turbine driven AFW train C.1 Restore the steam [24 or 48] hours inoperable due to one supply inoperable steam supply. to the turbine driven train to OPERABLE status.

AND OR One motor driven AFW train [24 or 48] hours inoperable. C.2 Restore the motor driven AFW train to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A [, B, or C]

not met.

[OR AND

[Two] AFW trains D.2 Be in MODE 4. [18] hours inoperable in MODE 1, 2, or 3 for reasons other than Condition C. l E. [ [Three] AFW trains E.1 inoperable in MODE 1, 2, or ---------------NOTE--------------

3. LCO 3.0.3 and all other

LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.

Initiate action to restore one Immediately ]

AFW train to OPERABLE status.

3.2 St. Lucie. Unit 2 St. Lucie, Unit 2, is similar to the Unit 1 AFW system design. UFSAR, Unit 2, Section 10.4. 9, "Auxiliary Feedwater System," provides a description of the AFW system. The design basis of the AFW system supplies sufficient cooling water to either one or both SGs to (1) provide sufficient capability for the removal of decay heat from the reactor core, (2) reduce the RCS temperature to entry temperature for actuating the SOCS, and (3) prevent lifting of the pressurizer safety valves when considered in conjunction of the power-operated relief valves.

UFSAR Section 10.4.9 also states that during normal operation, feedwater is supplied to the SGs by the feedwater system. The AFW system may be utilized during normal plant startup, hot standby, and cooldown. During plant startup and hot standby, the system can provide a source of water inventory for the SGs.

During cooldown, the AFW system can provide a means of heat removal to bring the RCS to the SOCS activation temperature. With offsite power and the main condenser available, the condenser may be used as a heat sink.

The major active components of the system consist of one steam-driven AFW pump and two motor-driven AFW pumps. The larger AFW pump is driven by a noncondensing steam turbine.

The turbine receives steam from upstream of the main steam isolation valves, and exhausts to the atmosphere. The AFW pumps take suction from the CST and discharge to the SGs. The turbine-driven AFW pump is capable of supplying AFW flow to the SGs for the total expected range of SG pressure by means of a turbine driver controlled by a variable speed mechanical governor.

Each motor-driven AFW pump supplies feedwater to one SG. A cross connection is provided to enable the routing of the flow of the two motor-driven AFW pumps to one SG. The turbine-driven AFW pump supplies feedwater to both SGs by means of two separate lines, each with its own control valve and each sized to pass the full flow. AFW valves needed for system operation under design-basis events have control switches in the control room and locally as well. Each of the motor-driven AFW pumps utilize a Class 1E alternating current (ac) power supply (4.16 kilovolt safety-related bus). The turbine-driven pump train relies strictly on a de power supply.

4.0 TECHNICAL EVALUATION

4.1 Current TS 3.7.1.2 Actions 'a' and 'b' for St. Lucie, Unit 1 TS 3. 7.1.2 Actions currently state the following:

a. With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two motor driven pumps and one capable of being powered by an OPERABLE steam supply system) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. LCO 3.0.4.b is not applicable.

4.2 Proposed TS 3.7.1.2 Action Changes for St. Lucie, Unit 1

a. With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status.

d. LCO 3.0.4.b is not applicable.

In addition, add the following NOTE in a text box before Action c:

[Limiting Condition for Operation] LCO 3.0.3 and all other LCO Actions requiring MODE changes are suspended until one AFW pump is restored to OPERABLE status.

4.3 Current TS 3.7.1.2 Actions for St. Lucie, Unit 2 TS 3. 7.1.2 Actions currently state the following:

a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status.

d. LCO 3.0.4.b is not applicable.

4.4 Proposed TS 3.7.1.2 Actions for St. Lucie, Unit 2

a. With one auxiliary feedwater pump inoperable, restore the required auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status.

d. LCO 3.0.4.b is not applicable.

In addition, add the following NOTE in a text box before Action c:

LCO 3.0.3 and all other LCO Actions requiring MODE changes are suspended until one AFW pump is restored to OPERABLE status.

4.5 NRC Staff Evaluation 4.5.1 St. Lucie, Unit 1 - TS 3.7.1.2 4.5.1.1 Action 'a' Action 'a' was revised to be consistent with Action 'a' of NUREG-0212, Revision 2, and was corrected for grammar. The proposed change is:

a. With one auxiliary feedwater pump inoperable, restore the auxiliary feedwater pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The NRC staff finds that the 72-hour completion time (CT) is reasonable, based on the redundant capabilities afforded by the AFW system, the time needed for repairs, and the low probability of a design-basis accident event occurring during this period. Two AFW pumps and flow paths remain to supply feedwater to the SGs. Therefore, the NRC staff finds the change to Action 'a' acceptable.

4.5.1.2 Action 'b' Action 'b' was added to be consistent with Action 'b' of NUREG-0212, Revision 2, and was corrected for grammar. The proposed change is:

b. With two auxiliary feedwater pumps inoperable, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The NRC staff finds that the 6-hour CT is reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. Therefore, the NRC staff finds the change to Action 'b' acceptable.

4.5.1.3 Action 'c' Action 'c' was added to be consistent with Action 'c' of NUREG-0212, Revision 2. The proposed new action is:

c. With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status.

The NRC staff finds that with all AFW trains inoperable in MODE 1, 2, or 3, the unit is in a seriously degraded condition with no safety-related means for conducting a cooldown, and only limited means for conducting a cooldown with non-safety grade equipment. In such a condition, the unit should not be perturbed by any action, including a power change that might result in a trip. The seriousness of this condition requires that action be started immediately to restore one AFW train to OPERABLE status. Therefore, the NRC staff finds the addition of Action 'c' is acceptable.

4.5.1.4 Addition of Note The Note between Action 'b' and 'c' was added to be consistent with NUREG-1432, Revision 4.

The proposed new note is:

NOTE LCO 3.0.3 and all other LCO Actions requiring MODE changes are suspended until one AFW pump is restored to OPERABLE status.

The NRC staff finds that LCO 3.0.3 (plant shutdown statement to Hot Standby-Hot Shutdown-Cold shutdown) is not applicable, as it could force the unit into a less safe condition. Entering Hot Standby or Hot Shutdown may require the AFW to perform core decay heat removal; however, there are no Operable AFW pumps to perform core cooling function. Therefore, the NRC staff finds the addition of a Note is acceptable.

4.5.1.5 Action 'd' New Action 'd' was old Action 'b' and was just adjusted only for renumbering. The proposed change is:

d. LCO 3.0.4.b is not applicable.

The NRC staff finds this is acceptable due to the addition of new Action 'b' and 'c'. There was no change to the text.

In summary, the NRC staff finds that the proposed changes to TS 3.7.1.2, Unit 1, are consistent with regulatory requirements General Design Criterion (GDC) 36 and reflect the language of NUREG-0212, Revision 2, and NUREG-1432, Revision 4, which have been previously approved by the NRC staff. Therefore, the NRC staff finds the changes to TS 3. 7 .1.2 acceptable.

4.5.2 St. Lucie, Unit 2, TS 3.7.1.2 4.5.2.1 Note St. Lucie, Unit 2, TS 3. 7 .1.2 was revised to add a Note between existing Action 'b' and 'c' to be consistent with NUREG-1432, Revision 4. The proposed new note is:

NOTE LCO 3.0.3 and all other LCO Actions requiring MODE changes are suspended until one AFW pump is restored to OPERABLE status.

The NRC staff finds that with all AFW trains inoperable in MODE 1, 2, or 3, the unit is in a seriously degraded condition with no safety-related means for conducting a cooldown, and only limited means for conducting a cooldown with non-safety grade equipment. In such a condition, the unit should not be perturbed by any action, including a power change that might result in a trip. The seriousness of this condition requires that action be started immediately to restore one AFW train to OPERABLE status. LCO 3.0.3 is not applicable, as it could force the unit into a less safe condition. Entering Hot Standby or Hot Shutdown may require the AFW to perform core decay heat removal; however, there are no Operable AFW pumps to perform core cooling function. Therefore, the NRC staff finds the addition of the Note acceptable.

In summary, the NRC staff finds that the proposed changes to TS 3.7.1.2, Unit 2, are consistent with regulatory requirements of GDC 34, and reflect the language of NUREG-0212, Revision 2, and NUREG-1432, which have been previously approved by the NRC staff. Therefore, the NRC staff finds the change to TS 3. 7 .1.2 acceptable.

5.0 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 January 5, 2016, 1 of the proposed issuance of the amendments.

The State official had no comments.

6.0 ENVIRONMENTAL CONSIDERATION

These amendments change a requirement with respect to installation or use of a facility component 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 that the amendments involve no significant hazards consideration and there has been no public comment on such finding (80 FR 73237, dated November 24, 2015). Accordingly, these 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 these amendments.

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 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: L. Wheeler Date: Mm:h 7, 2016 1 The NRC staff notified the State official by e-mail. The e-mail is in ADAMS under Accession No. ML16005A432.

ML15356A611 *via memo OFFICE DORL/LPL 1-2/PM DORL/LPL2-2/LA DSS/STSB/BC DSS/SBPB/BC*

NAME JLamb (LRonewicz) BClayton RElliott GCasto*

DATE 12/29/2015 12/28/2015 1/04/2016 1/15/2016 OFFICE OGC- NLO DORL/LPL2-2/BC DORL/LPL2-2/PM DORL/LPL 1-2/PM NAME SF owler BBeasley PBuckberg JLamb DATE 2/16/2016 3/07/2016 3/07/2016 3/07/2016

v t e Letter Sequence Approval
CAC:MF6491, (Approved, Closed) CAC:MF6492, (Approved, Closed)
Initiation Request, Request, Request Acceptance... Administration Questions 23 November 2015 Answers Results Approval Other:
MONTHYEAR2015-12-15 [Table View]

ML15356A611

Text

SUBJECT:

Dear Mr. Nazar:

Enclosures:

Attachment:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 BACKGROUND

4.0 TECHNICAL EVALUATION

5.0 STATE CONSULTATION

6.0 ENVIRONMENTAL CONSIDERATION

7.0 CONCLUSION

Navigation menu

Search