ML18274A224

Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map

ML18274A224
Person / Time
Site:	Saint Lucie
Issue date:	11/02/2018
From:	Michael Wentzel Plant Licensing Branch II
To:	Nazar M Florida Power & Light Co
Wentzel M, 415-6459
References
EPID L-2018-LLA-0198
Download: ML18274A224 (14)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 November 2, 2018 Mr. Mano Nazar President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop EX/JB 700 Universe Blvd.

Juno Beach, FL 33408

SUBJECT:

ST. LUCIE PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENT NOS: 246 AND 197 REGARDING TECHNICAL SPECIFICATIONS SITE AREA MAP (EPID L-2018-LLA-0198)

Dear Mr. Nazar:

The U.S. Nuclear Regulatory Commission (the Commission) has issued the enclosed Amendment Nos. 246 and 197 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2, respectively. These amendments change the Technical Specifications in response to your application dated August 2, 2018.

These amendments revise the Technical Specifications by removing Figure 5.1-1, "Site Area Map"; removing Technical Specifications references to Figure 5.1-1; and adding a site description.

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. 50-335 and 50-389

Enclosures:

1. Amendment No. 246 to DPR-67

2. Amendment No. 197 to NPF-16

3. Safety Evaluation cc: Listserv Sincerely,

/

i

t/

Michael J. We tz I, Project Manager Plant Licensing anch 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. 246 Renewed License No. DPR-67

1.

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

A.

The application for amendment by Florida Power & Light Company (FPL, the licensee) dated August 2, 2018, 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 1 O 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 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. 246, 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 30 days of issuance.

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION lh,u ~ r

~?0) )

Undine Shoop, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: November 2, 2 O 1 8

ATTACHMENT TO LICENSE AMENDMENT NO. 246 ST. LUCIE PLANT, UNIT NO. 1 RENEWED FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace page 3 of the Renewed Facility Operating License with the attached revised page 3.

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

Remove Pages XIII 5-1 5-2 5-6a Insert Pages XIII 5-1 5-2 5-6a 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 C.

D.

The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 246, 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.

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.

Sustained Core Uncovery 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. 246

INDEX DESIGN FEATURES SECTION 5.1 SITE LOCATION......................................................................................................... 5-1 5.2 CONTAINMENT Configuration................................................................................................................ 5-1 Design Pressure and Temperature............................................................................... 5-4 Penetrations.................................................................................................................. 5-4 5.3 REACTOR CORE Fuel Assemblies........................................................................................................... 5-4 Control Element Assemblies......................................................................................... 5-5 5.4 REACTOR COOLANT SYSTEM 5.5 5.6 Design Pressure and Temperature............. :................................................................. 5-5 Volume.......................................................................................................................... 5-5 EMERGENCY CORE COOLING SYSTEMS................................................................ 5-5 FUEL STORAGE Criticality....................................................................................................................... 5-5 Drainage....................................................................................................................... 5-6 5.7 SEISMIC CLASSIFICATION......................................................................................... 5-6 5.8 DELETED................................................................................................................... 5-6a 5.9 DELETED................................................................................................................... 5-6a ST. LUCIE - UNIT 1 XIII Amendment No. 4J4, -M2, 244, 246

5,0 DESIGN FEATURES 5.1 SITE LOCATION The St. Lucie nuclear units are located on Hutchinson Island in St. Lucie County, about halfway between the cities of Fort Pierce and Stuart on the east coast of Florida. The radius of the exclusion area is 0.97 miles from the center of the St. Lucie Plant. The low population zone (LPZ) includes that area within one mile of the center of the St. Lucie Plant.

5.2 CONTAINMENT CONFIGURATION 5.2.1 The containment structure is comprised of a steel containment vessel, having the shape of a right circular cylinder with a hemispherical dome and ellipsoidal bottom, surrounded by a reinforced concrete shield building. The radius of the shield building is at least 4 feet greater than the radius of circular cylinder portion of the containment vessel at any point.

5.2.1.1 CONTAINMENT VESSEL

a.

b.

C.

d.

e.

f.

Nominal inside diameter = 140 feet.

Nominal inside height = 232 feet.

Net free volume = 2.5 x 106 cubic feet.

Nominal thickness of vessel walls = 2 inches.

Nominal thickness of vessel dome = 1 inch.

Nominal thickness of vessel bottom = 2 inches.

ST. LUCIE - UNIT 1 5-1 Amendment No. 69, 442, 246

Figure 5.1-1 Deleted ST. LUCIE - UNIT 1 5-2 Amendment No. W, 4-20, 246

DESIGN FEATURES DRAINAGE 5.6.2 The fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 56 feet.

CAPACITY 5.6.3 5.7 5.7.1 5.8 5.9 The spent fuel pool storage racks are designed and shall be maintained with a storage capacity limited to no more than 1706 fuel assemblies, and the cask pit storage rack is designed and shall be maintained with a storage capacity limited to no more than 143 fuel assemblies. The total Unit 1 spent fuel pool and cask pit storage capacity is limited to no more than 1849 fuel assemblies.

SEISMIC CLASSIFICATION Those structures, systems and components identified as seismic Class I in Section 3.2.1 of the FSAR shall be designed and maintained to the original design provisions contained in Section 3. 7 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirement.

DELETED DELETED ST. LUCIE - UNIT 1 5-6a Amendment No. 94-, 493, ~. 246

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.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. 197 Renewed License No. NPF-16

1.

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

A.

The application for amendment by Florida Power & Light Company, et al. (FPL, the licensee) dated August 2, 2018, 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 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. 197, 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 30 days of issuance.

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION ku/tL ~,_,,,,f ftt/Cp Undine Shoop, Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Date of Issuance: November 2, 2 O 1 8

ATTACHMENT TO LICENSE AMENDMENT NO. 197 ST. LUCIE PLANT, UNIT NO. 2 RENEWED FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace page 3 of the Renewed Facility Operating License with the attached revised page 3.

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

Remove Pages XVII XXII 5-1 5-2 5-4 Insert Pages XVII XXII 5-1 5-2 5-4 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 10 FR Part 30, Section 40.41 of 10 CFR Part 40, Section 50.54 and 50.59 of 1 O CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

A.

Maximum Power 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. 197, 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. 197

INDEX DESIGN FEATURES SECTION 5.1 SITE LOCATION......................................................................................................... 5-1 5.2 CONTAINMENT 5.2.1 CONFIGURATION........................................................................................................ 5-1 5.2.2 DESIGN PRESSURE AND TEMPERATURE............................................................... 5-1 5.3 REACTOR CORE 5.3.1 FUEL ASSEMBLIES..................................................................................................... 5-3 5.3.2 CONTROL ELEMENT ASSEMBLIES........................................................................... 5-3 5.4 REACTOR COOLANT SYSTEM 5.4.1 DESIGN PRESSURE AND TEMPERATURE............................................................... 5-3 5.5 DELETED..................................................................................................................... 5-4 5.6 FUEL STORAGE 5.6.1 CRITICALITY................................................................................................................ 5-4 5.6.2 DRAINAGE................................................................................................................... 5-4 5;6.3 CAPACITY.................................................................................................................... 5-4 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.......................................................... 5-4 ST. LUCIE - UNIT 2 XVII Amendment No. 4-38, 197

INDEX UST OF FIGURES {continued)

FIGURE PAGE 3.4-3 ST. LUCIE UNIT 2 REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS FOR 47 EFPY, COOLDOWN AND INSERVICE TEST............................................................................................................. 3/4 4-31 b J.4-4 DELETED....................................................................................................... 3/4 4-32 4.7-1 SAMPLING PLAN FOR SNUBBER FUNCTIONAL TEST.............................. 3/4 7-25 5.1-1 DELETED....................................................................................................................

5.6-1a DELETED....................................................................................................................

5.6-1b DELETED....................................................................................................................

5.6-1c DELETED....................................................................................................................

5.6-1d DELETED....................................................................................................................

5.6-1e DELETED....................................................................................................................

5.6-1f DELETED....................................................................................................................

5.6-1 ALLOWABLE REGION 1 STORAGE PATTERNS AND FUEL ARRANGEMENTS................................................................................................ 5-4h 5.6-2 ALLOWABLE REGION 2 STORAGE PATTERNS AND FUEL ARRANGEMENTS (Sheet 1 of 3).......................................................................... 5-4i 5.6-2 ALLOWABLE REGION 2 STORAGE PATTERNS AND FUEL ARRANGEMENTS (Sheet 2 of 3).......................................................................... 5-4j 5.6-2 ALLOWABLE REGION 2 STORAGE PATTERNS AND FUEL ARRANGEMENTS (Sheet 3 of 3)......................................................................... 5-4k 5.6-3 INTERFACE REQUIREMENTS BETWEEN REGION 1 AND REGION 2 (Sheet 1 of 2)......................................................................................................... 5-41 5.6-3 INTERFACE REQUIREMENTS BETWEEN REGION 1 AND REGION 2 (Sheet 2 of 2)....................................................................................................... 5-4m 5.6-4 ALLOWABLE CASK PIT STORAGE RACK PATTERNS..................................... 5-4n 6.2-1 DELETED............................................................................................................... 6-3 6.2-2 DELETED............................................................................................................... 6-4 ST. LUCIE - UNIT 2 XXII Amendment No. 8, 29, 63, 4-04-, ~.

44+,43a,4a4,4-e2,466, 197

5,0 DESIGN FEATURES 5.1 SITE LOCATION EXCLUSION AREA The St. Lucie nuclear units are located on Hutchinson Island in St. Lucie County, about halfway between the cities of Fort Pierce and Stuart on the east coast of Florida. The radius of the exclusion area is 0.97 miles from the center of the St. Lucie Plant. The low population zone (LPZ) includes that area within one mile of the center of the St. Lucie Plant.

5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel building of cylindrical shape, with a dome roof and having the following design features:

a.

Nominal inside diameter= 140 feet.

b.

Nominal inside height = 232 feet.

c.

Net free volume = 2.506 x 106 cubic feet.

d.

Nominal thickness of vessel walls = 2 inches.

e.

Nominal thickness of vessel dome= 1 inch.

f.

Nominal thickness of vessel bottom = 2 inches.

5.2.1.2 SHIELD BUILDING

a.

Minimum annular space = 4 feet.

b.

Annulus nominal volume = 543,000 cubic feet.

c.

Nominal outside height (measured from top of foundation mat to the top of the dome) = 228.5 feet.

d.

Nominal inside diameter= 148 feet.

e.

Cylinder wall minimum thickness = 3 feet.

f.

Dome minimum thickness = 2.5 feet.

g.

Dome inside radius= 112 feet.

DESIGN PRESSURE AND TEMPERATURE 5.2.2 The steel reactor containment building is designed and shall be maintained for a maximum internal pressure of 44 psig and a temperature of 264°F.

ST. LUCIE - UNIT 2 5-1 Amendment No. 8, 197

Figure 5.1-1 Deleted ST. LUCIE - UNIT 2 5-2 Amendment No. eJ, 197

DESIGN FEATURES 5.5 DELETED 5.6 FUEL STORAGE CRITICALITY 5.6.1

a.

The spent fuel storage racks are designed and shall be maintained with:

1.

A keff equivalent to less than 1.0 when flooded with unborated water, including a conservative allowance for biases and uncertainties as described in Section 9.1 of the Updated Final Safety Analysis Report.

2.

A keff equivalent to less than or equal to 0.95 when flooded with water containing 500 ppm boron, including a conservative allowance for biases and uncertainties as described in Section 9.1 of the Updated Final Safety Analysis Report.

3.

A nominal 8.965 inch center-to-center distance between fuel assemblies placed in the spent fuel pool storage racks and a nominal 8.80 inch center-to-center distance between fuel assemblies placed in the cask pit storage rack.

4.

For storage of enriched fuel assemblies, requirements of Specification 5.6.1.a.1 and 5.6.1.a.2 shall be met by positioning fuel in the spent fuel pool storage racks consistent with the requirements of Specification 5.6.1.c.

5.

Fissile material, not contained in a fuel assembly lattice, shall be stored in accordance with the requirements of Specifications 5.6.1.a.1 and 5.6.1.a.2.

6.

The Metamic neutron absorber inserts shall have a 10B areal density greater than or equal to 0.015 grams 10B/cm2.

b.

The cask pit storage rack shall contain neutron absorbing material (Baral) between stored fuel assemblies when installed in the spent fuel pool.

c.

Loading of spent fuel pool storage racks shall be controlled as described below.

1.

The maximum initial planar average U-235 enrichment of any fuel assembly inserted in a spent fuel pool storage rack shall be less than or equal to 4.6 weight percent.

2.

Fuel placed in Region 1 of the spent fuel pool storage racks shall comply with the storage pattern definitions of Figure 5.6-1 and the minimum burnup requirements as defined in Table 5.6-1. (See Specification 5.6.1.c. 7 for exceptions)

3.

Fuel placed in Region 2 of the spent fuel pool storage racks shall comply with the storage pattern definitions or allowed special arrangement definitions of Figure 5.6-2 and the minimum burnup requirements as defined in Table 5.6-1. (See Specification 5.6.1.c. 7 for exceptions)

ST. LUCIE - UNIT 2 5-4 Amendment No. 7, 96, 4-0+, 4-ae, 4-JS, 462,197

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 246 AND 197 TO RENEWED FACILITY OPERATING LICENSE 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 application dated August 2, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18218A075), Florida Power & Light Company (the licensee) requested changes to the Technical Specifications (TSs) for the St. Lucie Plant, Unit Nos. 1 and 2 (St. Lucie 1 and 2), which are contained in Appendix A of Renewed Facility Operating License Nos. DPR-67 and NPF-16, respectively. The proposed amendments would revise the Technical Specifications by removing Figure 5.1-1, "Site Area Map"; removing TS references to Figure 5.1-1; and adding a site description.

2.0 REGULATORY EVALUATION

2.1.

Site Area Description St. Lucie 1 and 2 are located on Hutchinson Island in St. Lucie County, Florida, approximately 7 miles southeast of the city of Fort Pierce, and 8 miles north of the city of Stuart. The licensee maintains an exclusion area of 0.97 miles surrounding the plant. The low population zone includes the 1-mile area surrounding the plant, and there are no residents within this zone.

2.2 Licensee's Proposed Changes In addition to removing Figure 5.1-1 from both the St. Lucie 1 and 2 TSs, the licensee proposes to make the following changes (deletions shown in strike-through text and additions shown in bold text):

St. Lucie 1 TS 5.1 5.1 SITE LOCATION Exclusion Area 5.1.1 The exclusion area is shown on Figure 5.1 1.

Low Population Zone 5.1.2 Tho low population zone is shown on Figure 5.1 1.

The St. Lucie nuclear units are located on Hutchinson Island in St. Lucie County, about halfway between the cities of Fort Pierce and Stuart on the east coast of Florida. The radius of the exclusion area is 0.97 miles from the center of the St. Lucie Plant. The low population zone (LPZ) includes that area within one mile of the center of the St. Lucie Plant.

St. Lucie 2 TS 5.1 5.1 SITE LOCATION EXCLUSION AREA 5.1.1 Tho exclusion area shall be as show in Figure 5.1 1.

LOW POPULATION ZONE 5.1.2 Tho low population zone shall be as show on Figure 5.1 1.

The St. Lucie nuclear units are located on Hutchinson Island in St. Lucie County, about halfway between the cities of Fort Pierce and Stuart on the east coast of Florida. The radius of the exclusion area is 0.97 miles from the center of the St. Lucie Plant. The low population zone (LPZ) includes that area within one mile of the center of the St. Lucie Plant.

St. Lucie 1 TS 5.8 5.8 METEOROLOGICAL TOWER LOC/\\.TION DELETED

. 5.8.1 Tho meteorological tower location shall be as shown on Figure 5.1 1.

St. Lucie 2 TS 5.5 5.5 METEOROLOGICAL TOWER LOCATION DELETED 5.5.1 Tho meteorological to*.vor location shall be as shown on Figure 5.1 1.

The licensee also proposes to update the applicable St. Lucie 1 and 2 TS index pages to reflect the changes proposed above. The changes to the index pages are administrative in nature and, therefore, are acceptable.

2.3 Regulatory Review The U.S. Nuclear Regulatory Commission (NRC, the Commission) staff reviewed the licensee's application to determine whether (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 the activities proposed 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. The NRC staff considered the following regulatory requirements, guidance, and licensing and design-basis information during its review of the proposed changes.

Title 1 O of the Code of Federal Regulations (10 CFR) 50.36(a)(1) states, in part, that each applicant for an operating license shall include in the application proposed TSs in accordance with the requirements of 10 CFR 50.36, "Technical specifications." Paragraph 50.36(c) requires that the TSs include items in the following categories related to station operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.

Paragraph 50.36(c)(4) states, in part, that design features to be included in the TSs are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety.

NUREG-1432, Revision 4, "Standard Technical Specifications [STS] - Combustion Engineering Plants" (ADAMS Accession No. ML12102A165), contains the STS for Combustion Engineering plants. Although the St. Lucie 1 and 2 TSs are not based on the guidance in NUREG-1432, the STS present an acceptable method for licensees of Combustion Engineering plants to meet the NRG requirements in 10 CFR 50.36.

St. Lucie 1 Updated Final Safety Analysis Report (UFSAR), Chapter 2, "Site Characteristics" (ADAMS Accession No. ML17298A046), describes the relevant site and environmental characteristics of St. Lucie 1 and 2.

St. Lucie 2 UFSAR, Chapter 2, "Site Characteristics" (ADAMS Accession No. ML16193A335),

describes the relevant site and environmental characteristics of St. Lucie 1 and 2.

3.0 TECHNICAL EVALUATION

The NRG staff evaluated the licensee's application to determine whether the proposed changes are consistent with the regulations, guidance, and plant-specific licensing and design-basis information discussed in Section 2.3 of this safety evaluation.

The licensee proposed to remove Figure 5.1-1 from Section 5.0, "Design Features," of the St. Lucie 1 and 2 TSs, rename TS 5.1, and replace the text in TS 5.1 with a text description of the site location. TS 5.1 currently states that the exclusion area boundary and low population zone are shown on Figure 5.1-1. In addition, the licensee proposed to delete TS 5.8 and TS 5.5 from the St. Lucie 1 and 2 TSs, respectively. TS 5.8 and TS 5.5 state that the meteorological tower is shown on Figure 5.1-1. The licensee proposed no changes to the actual locations of anything depicted on Figure 5.1-1.

The NRG regulations regarding design features at 10 CFR 50.36(c)(4) do not contain a requirement to include a site map in the TSs, nor is a site map a feature, which, if altered or modified, would have a significant effect on safety. Therefore, the NRG staff finds that the inclusion of a site map is not necessary to meet the requirements of 10 CFR 50.36(c)(4).

Further, Section 4.0, "Design Features," in the STS does not include a site map or references to locations depicted on a site map. As such, the removal of Figure 5.1-1 and associated references to the figure in TS 5.1 and TS 5.8 for St. Lucie 1, and TS 5.1 and TS 5.5 for St. Lucie 2, is acceptable.

Regarding the licensee's proposed change to rename TS 5.1 to "Site Location" and to add a text description of the site location, the NRG staff finds the proposed changes consistent with STS 4.1 in NUREG-1432. Further, the NRC staff finds the proposed text description consistent with that in Chapter 2 of the St. Lucie 1 and 2 UFSARs. As such, the proposed changes meet the requirements of 10 CFR 50.36(c)(4) and are acceptable.

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 October 18, 2018, of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

These amendments relate to changes in the format of the license or permit or otherwise make editorial, corrective, or other minor revisions. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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.

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: Michael Wentzel Date: November 2, 2018

SUBJECT:

ST. LUCIE PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENT NOS. 246 AND 197 REGARDING TECHNICAL SPECIFICATIONS SITE AREA MAP (EPID L-2018-LLA-0198) DATED NOVEMBER 2, 2018 DISTRIBUTION:

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