ML14016A248

Issuance of Amendments Regarding Standardization of Administrative Controls-Responsibility and Organization

ML14016A248
Person / Time
Site:	Saint Lucie
Issue date:	02/07/2014
From:	Siva Lingam Plant Licensing Branch II
To:	Nazar M Florida Power & Light Co
Lingam S DORL/LPL2-1 301-415-1564
References
TAC MF2496, TAC MF2497
Download: ML14016A248 (25)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 February 7, 201!+

SUBJECT:

ST. LUCIE PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING STANDARDIZATION OF ADMINISTRATIVE CONTROLS-RESPONSIBILITY AND ORGANIZATION (TAC NOS. MF2496 AND MF2497)

Dear Mr. Nazar:

The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment Nos217 andl6 7 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated July 26, 2013, as supplemented by letter dated October 16, 2013.

The amendments revise the St. Lucie TSs to align with Combustion Engineering Owners Group TS language describing the Administrative Controls requirements for Responsibility and Organization.

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

Docket Nos. 50-335 and 50-389

Enclosures:

1. Amendment No. 217 to DPR-67

2. Amendment No. 167 to NPF-16

3. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely,

~~*~~

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation

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. 217 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 26, 2013, as supplemented by letter dated October 16, 2013, 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, Renewed Facility Operating License No. DPR-67 is amended by changes to the Technical Specifications (TSs) 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. 217, are hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the TSs.

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 Operating License and Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION Jessie F. Quichocho, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: February 7, 2014

ATTACHMENT TO LICENSE AMENDMENT NO. 2J 7 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace Page 3 of Renewed Operating License DPR-67 with the attached Page 3.

Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Page XIV 6-1 6-2 6-4 6-5 Insert Page XIV 6-1 6-2 6-4 6-5 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 8, as revised through Amendment No. 217are 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.217

INDEX ADMINISTRATIVE CONTROLS SECTION 6.1 RESPONSIBILITY........................................................................................................ 6-1 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATION................................................................... 6-1 6.2.2 UNIT STAFF................................................................................................................. 6-2 6.3 UNIT STAFF QUALIFICATIONS.................................................................................. 6-6 6.4 DELETED 6.5 DELETED ST. LUCIE-UNIT 1 XIV Amendment No. 69, W, 4-d4, -Ui9, ~.

~.2.17

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor shall be responsible for the control room command function.

During any absence of the Shift Supervisor from the control room while either unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the Shift Supervisor from the control room while both units are in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.2.1 An onsite and an offsite organization shall be established for unit operation and corporate management. This onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the Quality Assurance Topical Report and updated in accordance with 10 CFR 50.54(a)(3).

The plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the UFSAR or the Quality Assurance Topical Report.

b.

A specified corporate officer shall be responsible for overall plant nuclear safety. This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.

c.

The plant manager shall be responsible for overall safe operation and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.

d.

Although the individuals who train the operating staff and those who carry out the quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.

e.

Although health physics individuals may report to any appropriate manager onsite, for matters relating to radiological health and safety of employees and the public, the radiation protection manager shall have direct access to that onsite individual having responsibility for overall unit management. Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

ST. LUCIE-UNIT 1 6-1 Amendment No. 2a, e9, 99,

-W+, 4-26, -Me, 4-+-S, ~. ~ 217

6.0 ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION (continued)

UNIT STAFF 6.2.2 The unit staff organization shall meet the requirements of 10 CFR 50.54(m) and include the following:

a.

A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4. A minimum of three non-licensed operators is required when both unites are in MODES 5 or 6.

b.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 6.2.2.a and 6.2.2.e for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c.

A health physics technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d.

The operations manager or assistant operations manager shall hold an SRO license.

e.

An individual (Shift Technical Advisor (STA)) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. The STA may be an STA qualified Shift Supervisor, or a dedicated STA. The STA shall be manned while either unit is in MODES 1, 2, 3, or 4. A single STA may fill the position for both units.

ST. LUCIE-UNIT 1 6-2 Amendment No. 4-0, ~. ~.

W, ~

..:t-1--a, 446,.t++, -W9, 217

DELETED ST. LUCIE - UNIT 1 6-4 Amendment No. 'J+, M, 92, W,.rn,

+++, 217

DELETED ST. LUCIE-UNIT 1 6-5 Amendment No. 69, W, 44-&,

~.+56, ~. +00, ~, 217

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.l67 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 26, 2013, as supplemented by letter dated October 16, 2013, 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, Renewed Facility Operating License No. NPF-16 is amended by changes to the Technical Specifications (TSs) 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. 16 7, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the TSs.

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 Operating License and Technical Specifications FOR THE NUCLEAR REGULA TORY COMMISSION Jessie F. Quichocho, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: February 7, 2014

ATTACHMENT TO LICENSE AMENDMENT NO.l67 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace Page 3 of Renewed Operating License NPF-16 with the attached Page 3.

Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Page XVIII XXV 6-1 6-2 6-5 6-6 Insert Page XVIII XXV 6-1 6-2 6-5 6-6 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 1 0 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 8, as revised through Amendment No. 16 7are hereby incorporated in the renewed license.

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

Renewed License No. NPF-16 Amendment No.l67

INDEX ADMINISTRATIVE CONTROLS SECTION 6.1 RESPONSIBILITY........................................................................................................ 6-1 6.2 ORGANIZATION........................................................................................................... 6-1 6.2.1 ONSITE AND OFFSITE ORGANIZATION................................................................... 6-1 6.2.2 UNIT STAFF................................................................................................................. 6-2 6.3 UNIT STAFF QUALIFICATIONS.................................................................................. 6-6 6.4 DELETED..................................................................................................................... 6-7 6.5 DELETED..................................................................................................................... 6-7 ST. LUCIE - UNIT 2 XVIII Amendment No. 29, -73, gg, ~. 446,

-%9, 167

INDEX LIST OF TABLES <Continued\\

TABLE PAGE 3.7-1 MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE STEAM LINE SAFETY VALVES DURING OPERA-TION WITH BOTH STEAM GENERATORS...................................................... 3/4 7-2 3.7-2 STEAM LINE SAFETY VALVES PER LOOP.................................................... 3/4 7-3 4.7-1 SECONDARY COOLANT SYSTEM SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM...................................................................................... 3/4 7-8 4.7-2 SNUBBER VISUAL INSPECTION INTERVAL................................................ 3/4 7-22 3.7-3a DELETED........................................................................................................ 3/4 7-26 3.7-3b DELETED........................................................................................................ 3/4 7-27 3.7-4 DELETED 3.7-5 DELETED 4.8-1 DIESEL GENERATOR TEST SCHEDULE........................................................ 3/4 8-8 4.8-2 BATTERY SURVEILLANCE REQUIREMENT................................................ 3/4 8-12 3.8-1 MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION BYPASS DEVICES.......................................................................................... 3/4 8-18 4.11-1 DELETED 4.11-2 DELETED 3.12-1 DELETED 3.12-2 DELETED 4.12-1 DELETED 5.6-1 MINIMUM BURNUP COEFFICIENTS................................................................... 5-4o 5.7-1 COMPONENT CYCLIC OR TRANSIENT LIMITS................................................... 5-5 ST. LUCIE-UNIT 2 XXV Amendment No. g, ~. ~. 98, 13, 4+7, +62, 167

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The Shift Supervisor shall be responsible for the control room command function.

During any absence of the Shift Supervisor from the control room while either unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the Shift Supervisor from the control room while both units are in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

6.2 ORGANIZATION ONSITE AND OFFSITE ORGANIZATION 6.2.1 An onsite and an offsite organization shall be established for unit operation and corporate management. This onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.

a.

Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. Those relationships shall be documented and updated, as appropriate, in the form of organizational charts.

These organizational charts will be documented in the Quality Assurance Topical Report and updated in accordance with 10 CFR 50.54(a)(3).

The plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the UFSAR or the Quality Assurance Topical Report.

b.

A specified corporate officer shall be responsible for overall plant nuclear safety. This individual shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support in the plant so that continued nuclear safety is assured.

c.

The plant manager shall be responsible for overall unit safe operation and shall have control over those onsite resources necessary for safe operation and maintenance of the plant.

d.

Although the individuals who train the operating staff and those who carry out the quality assurance functions may report to the appropriate manager onsite, they shall have sufficient organizational freedom to be independent from operating pressures.

e.

Although health physics individuals may report to any appropriate manager onsite, for matters relating to radiological health and safety of employees and the public, the radiation protection manager shall have direct access to that onsite individual having responsibility for overall unit management. Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.

ST. LUCIE - UNIT 2 6-1 Amendment No. ~. 29, 4&,

41-, ~. 8§, 4-2-1-, -+46, ~. 167

6.0 ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION (Continued)

UNIT STAFF 6.2.2 The unit staff organization shall meet the requirements of 10 CFR 50.54(m) and include the following:

a.

A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4. A minimum of three non-licensed operators is required when both units are in MODES 5 or 6.

b.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 6.2.2.a and 6.2.2.e for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c.

A health physics technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d.

The operations manager or assistant operations manager shall hold an SRO license.

e.

An individual (Shift Technical Advisor (STA)) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. The STA may be an STA qualified Shift Supervisor, or a dedicated ST A. The STA shall be manned while either unit is in MODES 1, 2, 3, or 4. A single STA may fill the position for both units.

ST. LUCIE-UNIT 2 6-2 Amendment No. 29, aa, ea, ~. ~.

-Me, +W, 167

DELETED ST. LUCIE-UNIT 2 6-5 Amendment No.~. 16 7

6.0 ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI/

ANS-3.1-1978 for comparable positions, except for:

(1) the radiation protection manager who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor who shall have specific training in plant design and plant operating characteristics, including transients and accidents, and any of the following educational requirements:

Bachelor's degree in engineering from an accredited institution; or Professional Engineer's (PE) license obtained by successful completion of the PE examination; or Bachelor's degree in engineering technology from an accredited institution, including course work in the physical, mattiematical, or engineering sciences, or Bachelor's degree in physical science from an accredited institution, including course work in the physical, mathematical, or engineering sciences.

(3) the Multi-Discipline Supervisors who shall meet or exceed the following requirements:

a.

Education: Minimum of a high school diploma or equivalent.

b.

Experience: Minimum of four years of related technical experience, which shall include three years power plant experience of which one year is at a nuclear power plant.

c.

Training: Complete the Multi-Discipline Supervisor training program.

6.3.2 For the purpose of 10 CFR 55.4, a licensed senior reactor operator and a licensed reactor operator are those individuals who, in addition to meeting the requirements of 6.3.1, perform the functions described in 10 CFR 50.54(m).

ST. LUCIE-UNIT 2 6-6 Amendment No. a, 49, 65, W,.w2, ~.

-Me,~ 167

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 217 AND 16 7 TO RENEWED FACILITY OPERATING LICENSES NOS. DPR-67 AND NPF-16 FLORIDA POWER AND LIGHT COMPANY, ET AL.

1.0 INTRODUCTION

ST. LUCIE PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-335 AND 50-389 By letter dated July 26, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13219A840), as supplemented by letter dated October 16, 2013 (ADAMS Accession No. ML13297A100}, Florida Power & Light Company (the licensee) requested amendments to Renewed Facility Operating License Nos. DPR-67 for St. Lucie Plant Unit 1 and NPF-16 for the St. Lucie Plant Unit 2, and Appendix A, Technical Specifications (TSs), of the Facility Operating License. The proposed changes would align with NUREG-1432, Revision 4, Combustion Engineering Plants Standard TSs language describing the Administrative Controls requirements for Responsibility and Organization.

2.0 REGULATORY EVALUATION

The U.S. Nuclear Regulatory Commission (NRC) staff review addresses administrative controls concerning programs and procedures related to the organizational structure and unit staff responsibilities during normal and accident conditions. The regulatory requirements, which the NRC staff considered in its review of the license amendment request are Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.54, "Conditions of licenses." 10 CFR 50.36, "Technical specifications." The NRC staff also reviewed guidance in NUREG-1432, "Standard Technical Specifications, Combustion Engineering Plants, Revision 4.0, Volume 1, Specifications," April 2012 (STSs).

3.0 TECHNICAL EVALUATION

The licensee requests to revise TS Sections 6.1 and 6.2, which currently use plant specific language to ensure compliance with the requirements of 10 CFR 50.54(m) to be consistent with STSs Sections 5.1 and 5.2. Section 6.1.2 of the St. Lucie TS currently reads:

Enclosure

The Shift Supervisor, or during his absence from the control room a designated individual, shall be responsible for the control room command function. A management directive to this effect, signed by the corporate officer with direct responsibility for the plant, shall be reissued to all station personnel on an annual basis."

This section will be revised to read:

"6.1.2 The Shift Supervisor shall be responsible for the control room command function.

During any absence of the Shift Supervisor from the control room while either unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the Shift Supervisor from the control room while both units are in MODE 5 or 6, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function."

Section 6.2.2 of St. lucie currently reads:

"The unit organization shall be subject to the following.

a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b.

Deleted.

c.

A health physics technician# shall be on site when fuel is in the reactor.

d.

Deleted.

e.

Deleted.

f.

Deleted.

g.

The operations supervisor shall hold a Senior Reactor Operator license."

The proposed language in TS 6.2.2 will be revised for consistency with STS 5.2.2 to read:

"6.2.2 The unit staff organization shall meet the requirements of 10 CFR 50.54(m) and include the following:

a.

A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, 3, or 4. A minimum of three non-licensed operators is required when both units are in MODES 5 or 6.

b.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 6.2.2.a and 6.2.2.e for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

c.

A health physics technician shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d.

The operations manager or assistant operations manager shall hold an SRO license.

e.

An individual (Shift Technical Advisor (STA)) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. The ST A may be an ST A qualified Shift Supervisor or a dedicated ST A. The STA shall be manned on while either unit is in MODES 1, 2, 3, or 4. A single STA may be filled the position for both units."

As part of the request, the current TS Table 6.2-1 and TS 6.2.3 would be deleted and replaced with proposed TS 6.2.2 language. Also, there are associated proposed editorial changes to the TS Index. The proposed license changes to TS 6.1.2 and 6.2.2 by the licensee are editorial in nature and would have no technical implications with respect to the station organization, responsibilities, or unit staffing requirements. Therefore, the NRC staff has determined that nuclear safety is still maintained.

The proposed changes in support of aligning the St. Lucie Unit 1 and 2 TSs with STSs NUREG-1432 are acceptable because there are no changes to the station organization, responsibilities, or unit staffing requirements. The changes are in accordance with 10 CFR 50.54(m) and continue to satisfy the regulations. Therefore, the NRC staff finds the proposed TS changes acceptable.

5.0 STATE CONSULTATION

Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Ms. Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of issuance of license amendments. In an email dated July 25, 2012 (ADAMS Accession No. ML12208A014), from Cynthia Becker, Florida State Bureau of Radiation Control, to Farideh Saba, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida confirmed that the May 2003 letter continues to reflect the State's position on notification of issuance of license amendments.

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 (78 FR 67406, dated November 12, 2013). 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: S. Galbreath Date: February 7, 2014

Mr. Mane Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 February 7, 2014

SUBJECT:

ST. LUCIE PLANT, UNIT NOS. 1 AND 2-ISSUANCE OF AMENDMENTS REGARDING STANDARDIZATION OF ADMINISTRATIVE CONTROLS-RESPONSIBILITY AND ORGANIZATION (TAC NOS. MF2496 AND MF2497)

Dear Mr. Nazar:

The Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment Nos. 217 and167 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated July 26, 2013, as supplemented by letter dated October 16, 2013.

The amendments revise the St. Lucie TSs to align with Combustion Engineering Owners Group TS language describing the Administrative Controls requirements for Responsibility and Organization.

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

Docket Nos. 50-335 and 50-389

Enclosures:

1. Amendment No. 217 to DPR-67

2. Amendment No. 167 to NPF-16

3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

Sincerely, IRA/

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation PUBLIC RidsNrrDorllpl2-2 RidsNrrDssStsb LPL2-2 R/F RidsNrrPMStlucie RidsRgn2MaiiCenter RidsAcrsAcnw_MaiiCTR RidsNrrDoriDpr RidsNrrLABCiayton RidsNrrDraAhpb SGalbreath, NRR KHemphill, NRR ADAMS A ccess1on N o.: ML14016A248

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DATE 1/22/14 1/1714 11/15/13 1/29/14 2/6/14 2/7/14 2/7/14 OFFICIAL RECORD COPY