ML17269A166

Issuance of Amendments Related to NFPA 805 Supplement (CAC Nos. MG0094 and MG0095; EPID L-2017-LLA-0261)

ML17269A166
Person / Time
Site:	Farley
Issue date:	11/01/2017
From:	Shawn Williams Plant Licensing Branch II
To:	Hutto J Southern Nuclear Operating Co
Williams S A/DORL-LPL2-1/301-415-1009
References
CAC MG0094, CAC MG0095, EPID L-2017-LLA-0261
Download: ML17269A166 (30)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 November 1, 2017 Mr. James J. Hutto Regulatory Affairs Director Southern Nuclear Operating Company, Inc.

P.O. Box 1295 /Bin -038 Birmingham, AL 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RELATED TO NFPA 805 SUPPLEMENT (CAC NOS. MG0094, MG0095; EPID NO. L-2017-LLA-0261)

Dear Mr. Hutto:

The U.S. Nuclear Regulatory Commission {NRG, the Commission) has issued the enclosed Amendment No. 215 to Renewed Facility Operating License (RFOL) No. NPF-2 and Amendment No. 212 to RFOL No. NPF-8 for the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2, respectively. The amendments consist of changes to the RFOLs in response to your application dated August 11, 2017.

Specifically, the request will extend the time to achieve full compliance with 10 CFR 50.48(c),

National Fire Protection Association (NFPA) 805, from November 6, 2017, to the conclusion of the FNP, Unit t, Spring 2018 Refueling Outage (1R28). The amendments update Attachment S, "Modification and Implementation Items," of the NFPA-805 amendments approved previously by the NRC.

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

Docket Nos. 50-348 and 50-364

Enclosures:

1. Amendment No. 2t 5 to NPF-2

2. Amendment No. 212 to NPF-8

3. Safety Evaluation cc w/enclosures: Distribution via Listserv Sincerely, Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 215 Renewed License No. NPF-2

1.

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

A.

The application for amendment to the Joseph M. Farley Nuclear Plant, Unit 1, (the facility), Renewed Facility Operating License No. NPF-2, filed by Southern Nuclear Operating Company, Inc. (the licensee), dated August 11, 2017, 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 (l) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities wiU be conducted in compliance with the Commission's regulations; D.

The issuance of this license 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, paragraph 2.C.(2) and 2.C.(4) of Renewed Facility Operating License No. NPF-2, is hereby amended to read as follows:

2.C.{2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215, are hereby incorporated in the renewed facility operating license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

2.C.(4) Fire Protection Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment requests dated September 25, 2012; April 25, 2016; and supplements dated December 20, 2012; September 16, 2013; October 30, 2013; November 12, 2013; April 23, 2014; May 23, 20t 4; July 3, 2014; August 11, 2014; August 29, 2014; October 13, 2014; January 16, 2015, and August 11, 2017, as approved in the safety evaluation reports dated March 10, 2015, October 17, 2016, and November 1, 2017. Except where NRG approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRG approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

2.C.(4).c.2)

Transition License Conditions The licensee shall implement the modifications to its facility, as described in Attachment S, Table S-2, "Plant Modifications Committed, of SNC letter NL-15-2310, dated April 25, 2016, to complete the transition to full compliance with 1 O CFR 50.48(c) before the conclusion of the 1 R28 Spring 2018 Refueling Outage as provided in SNC letter dated August 11, 2017. The licensee shall maintain appropriate compensatory measures in place until completion of these modifications.

3.

This license amendment is effective as of its date ot issuance and shall be implemented within 30 days of issuance.

Attachment:

Changes to Renewed Facility Operating License No. NPF-2 Date of Issuance: November 1, 2017 FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C 20555*0001 SOUTHERN NUCLEAR OPERATING COMPANY ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 212 Renewed License No. NPF-8

1.

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

A.

The application for amendment to the Joseph M. Farley Nuclear Plant, Unit 2 (the facility), Renewed Facility Operating License No. NPF-8, filed by Southern Nuclear Operating Company, Inc. (the licensee), dated August 11, 2017, 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 license 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, paragraph 2.C.(2) and 2.C.(6) of Renewed Facility Operating License No.

NPF-8 is hereby amended to read as follows:

2.C.(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 212, are hereby incorporated in the renewed facility operating license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

2.C.(6) Fire Protection Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 1 O CFR 50.48(c), as specified in the licensee amendment requests dated September 25, 2012; April 25, 2016; and supplements dated December 20, 2012; Sep1ember 16, 2013; October 30, 2013; November 12, 2013; April 23, 2014; May 23, 2014; July 3, 2014; August 11, 2014; August 29, 2014; October 13, 2014; January 16, 2015; and August 11, 2017, as approved in the safety evaluation reports dated March 10, 2015, October 17, 2016, and November 1, 2017. Except where NRG approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

2.C.(6).(c).2. Transition License Conditions The licensee shall implement the modifications to its facility, as described in Attachment S, Table 8*2, "Plant Modifications Committed," of SNC letter NL-15-2310, dated April 25, 2016, to complete the transition to full compliance with 1 O CFR 50.48(c) before the conclusion of the 1 R28 Spring 2018 Refueling Outage as provided in SNC letter dated August 11, 2017. The licensee shall maintain appropriate compensatory measures in place until completion of these modifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

Attachment:

Changes to Renewed Facility Operating License No. NPF-8 Date of Issuance: November 1, 2017 FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

ATTACHMENT TO JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 LICENSE AMENDMENT NO. 215 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 AND LICENSE AMENDMENT NO. 212 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License NPF pages 4, 5, and 7 NPF pages 3, 4, and 6 License NPF pages 4, 5, and 7 NPF pages 3, 4, and 6

Farley - Unit 1 (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 215, are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

(3)

Additional Conditions The matters specified in the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions indicated. The removal of these conditions shall be made by an amendment to the renewed license supported by a favorable evaluation by the Commission.

a.

Southern Nuclear shall not operate the reactor in Operational Modes 1 and 2 with less than three reactor coolant pumps in operation.

b.

Deleted per Amendment 13

c.

Deleted per Amendment 2

d.

Deleted per Amendment 2

e.

Deleted per Amendment 152 Deleted per Amendment 2

f.

Deleted per Amendment 158

g.

Southern Nuclear shall maintain a secondary water chemistry monitoring program to inhibit steam generator tube degradation.

This program shall include:

1)

2)

3)

4)

5)

Identification of a sampling schedule for the critical parameters and control points for these parameters; Identification of the procedures used to quantify parameters that are critical to control points; Identification of process sampling points; A procedure for the recording and management of data; Procedures defining corrective actions for off control point chemistry conditions; and Renewed License No. NPF-2 Amendment No. 215

Farley - Unit 1 6)

A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events required to initiate corrective action.

h.

The Additional Conditions contained in Appendix C, as revised through Amendment No. 146, are hereby incorporated in the renewed license. The licensee shall operate the facility in accordance with the additional conditions.

i.

Deleted per Amendment 152 (4)

Fire Protection Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment requests dated September 25, 2012; April 25, 2016; and supplements dated December 20, 2012; September 16, 2013; October 30, 2013; November 12, 2013; April 23, 2014; May 23, 2014; July 3, 2014; August 11, 2014; August 29, 2014; October 13, 2014; January 16, 2015, and August 11, 2017, as approved in the safety evaluation reports dated March 10, 2015, October 17, 2016, and November 1, 2017. Except where NRC approval for changes or deviations is required by 10 CFR 50.48{c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.4B(a) and 10 CFR 50.48{c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

a.

Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRG and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at Farley. Acceptable methods to assess the risk of the change may include methods that have been used in the peer-reviewed fire PRA model, methods that have been approved by NRG through a plant-specific license amendment or NRG approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.

Renewed License No. NPF-2 Amendment No. 215

Farley - Unit 1 *

"Fire Alarm and Detection Systems" (Section 3.8);

"Automatic and Manual Water-Based Fire Suppression Systems" (Section 3.9);

"Gaseous Fire Suppression Systems" (Section 3.10); and, "Passive Fire Protection Features" (Section 3.11 ).

This License Condition does not apply to any demonstration of equivalency under Section 1.7 of NFPA 805.

2)

Fire Protection Program Changes that Have No More than Minimal Risk Impact Prior NRG review and approval are not required for changes to the licensee's fire protection program that have been demonstrated to have no more than a minimal risk impact.

The licensee may use its screening process as approved in NRG safety evaluation reports dated March 10, 2015, and October 17, 2016, to determine that certain fire protection program changes meet the minimal criterion. The licensee shall ensure that fire protection defense-in-depth and safety margins are maintained when changes are made to the fire protection program.

c.

Transition License Conditions 1 I

2)

3)

Before achieving full compliance with 10 CFR 50.48(c),

as specified by 2) below, risk-informed changes to the licensee's fire protection program may not be made without prior NRG review and approval unless the change has been demonstrated to have no more than a minimal risk impact, as described in 2) above.

The licensee shall implement the modifications to its facility, as described in Attachment S, Table S-2, "Plant Modifications Committed," of SNC letter NL-15-2310, dated April 25, 2016, to complete the transition to full compliance with 10 CFR 50.48(c) before the conclusion of the 1 R28 Spring 2018 Refueling Outage as provided in SNC letter dated August 11, 2017. The licensee shall maintain appropriate compensatory measures in place until completion of these modifications.

The licensee shall implement the items as listed in Attachment S, Table S-3, "Implementation Items," of SNC letter NL-14-1273, dated August 29, 2014, within 180 days after NRG approval, except for items 30 and

32. Items 30 and 32 shall be implemented by February 6, 2018.

Renewed License No. NPF-2 Amendment No. 215 (2)

Alabama Power Company, pursuant to Section 103 of the Act and 1 O CFR Part 50, "Licensing of Production and Utilization Facilities," to possess but not operate the facility at the designated location in Houston County, Alabama in accordance with the procedures and limitations set forth in this renewed license.

(3)

Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)

Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)

Southern Nuclear, pursuant to the Act and 1 O CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, tor sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)

Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C.

This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I 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 or incorporated below:

(1)

Maximum Power Level Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 2775 megawatts thermal.

(2)

Technical Specifications (3)

(4)

(5)

Farley - Unit 2 The Technical Specifications contained in Appendix A, as revised through Amendment No. 212 are hereby incorporated in the renewed license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications.

Deleted per Amendment 144 Deleted per Amendment 149 Deleted per Amendment 144 Renewed License No. NPF-8 Amendment No. 212 (6)

Fire Protection Farley - Unit 2 Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment requests dated September 25, 2012; April 25, 2016; and supplements dated December 20, 2012; September 16, 2013; October 30, 2013; November 12, 2013; April 23, 2014; May 23, 2014; July 3, 2014; August 11, 2014; August 29, 2014; October 13, 2014; January 16, 2015; and August 11, 2017, as approved in the safety evaluation reports dated March 10, 2015, October 17, 2016, and November 1, 2017. Except where NRG approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRG approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

(a)

Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at Farley. Acceptable methods to assess the risk of the change may include methods that have been used in the peer-reviewed fire PRA model, methods that have been approved by NRC through a plant-specific license amendment or NRC approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.

1.

2.

Prior NRC review and approval is not required for changes that clearly result in a decrease in risk. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins.

The change may be implemented following completion of the plant change evaluation.

Prior NRC review and approval is not required for individual changes that result in a risk increase less than 1x10*1/year (yr) for GDF and less than 1x10 8/yr for LERF. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.

Renewed License No. NPF-8 Amendment No. 212 to determine that certain fire protection program changes meet the minimal criterion. The licensee shall ensure that fire protection defense-in-depth and safety margins are maintained when changes are made to the fire protection program.

(c)

Transition License Conditions

1.

Before achieving full compliance with 10 CFR 50.48(c), as specified by 2 below, risk-informed changes to the licensee's fire protection program may not be made without prior NRG review and approval unless the change has been demonstrated to have no more than a minimal risk impact, as described in 2 above.

2.

The licensee shall implement the modifications to its facility, as described in Attachment S, Table S-2, "Plant Modifications Committed," of SNC letter NL-15-2310, dated April 25, 2016, to complete the transition to full compliance with 10 CFR 50.48(c) before the conclusion of the 1R28 Spring 2018 Refueling Outage as provided in SNC letter dated August 11, 2017. The licensee shall maintain appropriate compensatory measures in place until completion of these modifications.

3.

The licensee shall Implement the items as listed in Attachment S, Table S-3, "Implementation Items," of SNC letter NL-14-1273, dated August 29, 2014, within 180 days after NRC approval, except for items 30 and

32. Items 30 and 32 shall be implemented by February 6, 2018.

(7)

Deleted per Amendment 144 (8)

Deleted per Amendment 144 (9)

Deleted per Amendment 144 (10)

Deleted per Amendment 144 (11)

Deleted per Amendment 144 (12)

Deleted per Amendment 144 (13)

Deleted per Amendment 144 (14)

Deleted per Amendment 144 (15)

Deleted per Amendment 144 (16)

Deleted per Amendment 144 (17)

Deleted per Amendment 144 (18)

Deleted per Amendment 144 (19)

Deleted per Amendment 144 (20)

Deleted per Amendment 144 (21)

Deleted per Amendment 144 (22)

Additional Conditions The Additional conditions contained in Appendix C, as revised through Amendment No. 137, are hereby incorporated in the renewed license.

The licensee shall operate the facility in accordance with the additional conditions.

Farley - Unit 2 Renewed License No. NPF-8 Amendment No. 212

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO LICENSE AMENDMENT REQUEST TO REVISE CERTAIN PLANT MODIFICATIONS RELATED TO THE RISK-INFORMED PERFORMANCE-BASED FIRE PROTECTION PROGRAM IN ACCORDANCE WITH NFPA 805 AMENDMENT NO. 215 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 AND AMENDMENT NO. 212 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364

1.0 INTRODUCTION

On September 25, 2012 (Reference 1 ), Southern Nuclear Operating Company, Inc., (SNC, the licensee), requested to revise the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2, fire protection program (FPP) in accordance with Title 10 of the Code of Federal Regulations (10 CFR) Seclion 50.48(c). On March 10, 2015 (Reference 2), the U.S. Nuclear Regulatory Commission (NRC or the Commission) issued Amendment No. 196 to Renewed Facility Operating License (RFOL) No. NPF-2 for FNP, Unit 1, and Amendment No. 192 to RFOL No. NPF-8 for FNP, Unit 2. The amendments consisted of changes to the RFOL to transition the FNP FPP to a risk-informed, periormance-based (RI/PB) program based on National Fire Protection Association (NFPA) 805, "Periormance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants" (2001 Edition) (NFPA 805) (Reference 3), in accordance with 10 CFR 50.48(c). NFPA 805 allows the use of PB methods such as fire modeling (FM) and RI methods such as fire probabilistic risk assessment (FPRA) to demonstrate compliance with the nuclear safety periormance criteria (NSPC).

On April 25, 2016 (Reference 4), the licensee requested to change its fire protection license conditions 2.C.(4) for Unit 1 and 2.C.{6) for Unit 2 in order to change certain modifications related to the implementation of NFPA 805. On October 17, 2016 (Reference 5), the NRG issued Amendment No. 205 to RFOL No. NPF-2 for FNP, Unit 1, and Amendment No. 201 to RFOL No. NPF-8 for FNP, Unit 2, approving the licensee's proposed changes.

By application dated August 11, 2017 (Reference 6), the licensee submitted a license amendment request (LAR) to change fire protection license condition 2.C.(4) for Unit 1 and license condition 2.C.(6) for Unit 2. Transition license condition 2.C.(4).c.2) was included in Amendment No. 196, and transition license condition 2.C.{6).(c).2. was included in Amendment No. 192 (Reference 2), which referenced Table 8-2, "Plant Modifications Committed," of the licensee's letter dated August 29, 2014 (Reference 7). Subsequently, the NRC issued Amendment Nos. 205 and 201 which revised the transition license conditions to reference Table S-2, "Plant Modifications Committed," of the licensee's letter dated April 25, 2016 (Reference 4).

Table S-2 describes 12 plant modifications the licensee must complete by November 6, 2017.

In this LAA, the licensee is proposing to change the completion date for modification item 11 to its facility as described in Table S-2, "Plant Modifications Committed", of its letter dated April 25, 2016, from "November 6, 2017", to "before the conclusion of the 1 R28 Spring 2018 Refueling Outage". To support this change, the licensee has submitted revised versions of its fire protection license condition and also revised page S-2 of Attachment S, "Modifications and Implementation Items."

2.0 REGULATORY EVALUATION

Section 50.48, "Fire protection," of 10 CFR, provides the NRC requirements for nuclear power plant fire protection. The NRC regulations include specific requirements tor requesting approval for an RI/PB FPP based on the provisions of NFPA 805. Paragraph 50.48(c)(3)(i) of 10 CFR states, in part, that:

A licensee may maintain a fire protection program that complies with NFPA 805 as an alternative to complying with [10 CFR 50.48(b)] for plants licensed to operate before January 1, 1979, or the fire protection license conditions for plants licensed to operate after January 1, 1979. The licensee shall submit a request to comply with NFPA 805 in the form of an application for license amendment under

[10 CFR] 50.90. The application must identify any orders and license conditions that must be revised or superseded, and contain any necessary revisions to the plant's technical specifications and the bases thereof....

Pursuant to 1 O CFR 50.90, whenever a holder of a license desires to amend the license or permit, application for an amendment must be filed with the Commission describing the changes desired, and following, as far as applicable, the form prescribed for original applications.

Accordingly, a licensee who seeks to amend its NFPA 805 authorizations must file an amendment stating, as applicable, the desired changes to orders, license conditions, and technical specifications. Pursuant to 10 CFR 50.32, "Elimination of repetition," the licensee/applicant may incorporate by reference information contained in previous applications, statements or reports filed with the Commission, provided that such references are clear and specific.

In addition, 10 CFR 50.48(c)(3)(i) states, in part, that:

The Director of the Office of Nuclear Reactor Regulation, or a designee of the Director, may approve the application if the Director or designee determines that the licensee has identified orders, license conditions, and the technical specifications that must be revised or superseded, and that any necessary revisions are adequate. Any approval by the Director or the designee must be in the form of a license amendment approving the use of NFPA 805 together with any necessary revisions to the technical specifications.

In addition, 10 CFR 50.48(c)(3)(11) states that:

The licensee shall complete its implementation of the methodology in Chapter 2 of NFPA 805 {including all required evaluations and analyses) and, upon completion, modify the fire protection plan required by paragraph (a) of this section to reflect the licensee's decision to comply with NFPA 805, before changing its fire protection program or nuclear power plant as permitted by NFPA 805.

The intent of 10 CFR 50.48(c)(3)(ii) is given in the statement of considerations for the Final Rule, "Voluntary Fire Protection Requirements for Light Water Reactors; Adoption of NFPA 805 as a Risk-Informed, Performance-Based Alternative" (69 FR 33536 through 69 FR 33548; June 16, 2004), which states, in part, that:

This paragraph requires licensees to complete all of the Chapter 2 methodology (including evaluations and analyses) and to modify their fire protection plan before making changes to the fire protection program or to the plant configuration. This process ensures that the transition to an NFPA 805 configuration is conducted in a complete, controlled, integrated, and organized manner. This requirement also precludes licensees from implementing NFPA 805 on a partial or selective basis (e.g., in some Fire Areas and not others, or truncating the methodology within a given Fire Area).

Pursuant to 10 CFR 50.92(a), in determining whether an amendment to a license will be issued to the applicant, the Commission will be guided by the considerations which govern the issuance of initial licenses to the extent applicable and appropriate. Under 1 O CFR 50.40, common standards for issuance of licenses include considerations of safety and satisfaction of the requirements of the National Environmental Policy Act of 1969 as implemented in 10 CFR Part 51. Under 10 CFR 50.57(a), to issue an operating license, the Commission must find, among other things, that ( 1) there is reasonable assurance that the activities authorized by the operating license can be conducted without endangering the health and safety of the public; (2) there is reasonable assurance that such activities will be conducted in compliance with the regulations in this chapter; and (3) the issuance of the license will not be inimical to the common defense and security or to the health and safety of the public. Additional findings required to issue amendments related to fire protection are provided in 10 CFR 50.48, as discussed below.

As stated, in part, in 1 O CFR 50.48(c)(3)(i):

The Director of the Office of Nuclear Reactor Regulation, or a designee of the Director, may approve the application if the Director or designee determines that the licensee has identified orders, license conditions, and the technical specifications that must be revised or superseded, and that any necessary revisions are adequate.

The regulations also allow for flexibility that was not included in the NFPA 805 standard.

Licensees who choose to adopt 1 O CFR 50.48(c) but wish to use the PB methods permitted elsewhere in the standard to meet the fire protection requirements of NFPA 805, Chapter 3, "Fundamental Fire Protection Program and Design Elements," may do so by submitting an LAR in accordance with 10 CFR 50.48(c)(2)(vii). This regulation further provides that:

The Director of the Office of Nuclear Reactor Regulation, or a designee of the Director, may approve the application if the Director or designee determines that the performance-based approach; (A)

Satisfies the performance goals, pertormance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release; (B)

Maintains safety margins; and (C)

Maintains fire protection defense-in-depth (tire prevention, fire detection, fire suppression, mitigation, and post-fire safe shutdown capability).

Alternatively, licensees may choose to use RI or PB alternatives to comply with NFPA 805 by submitting an LAR in accordance with 10 CFR 50.48(c)(4), which states, in part.

The Director of the Office of Nuclear Reactor Regulation, or designee of the Director, may approve the application if the Director or designee determines that the proposed alternatives:

(i)

Satisfy the performance goals, performance objectives, and performance criteria specified in NFPA 805 related to nuclear safety and radiological release;

{ii)

Maintain safety margins; and (iii)

Maintain fire protection defense-in-depth (fire prevention, fire detection, fire suppression, mitigation, and post-fire sate shutdown capability).

In addition to the conditions outlined by the rule that require licensees to submit an LAR for NRC review and approval in order to adopt an RI/PB FPP, a licensee may submit additional elements of its FPP for which it wishes to receive specific NRC review and approval, as set forth in Regulatory Position C.2.2.1 of Regulatory Guide (RG) 1.205 (Reference 8). Inclusion of these elements in the NFPA 805 LAR is meant to alleviate uncertainty in portions of the current FPP licensing bases as a result of the lack of specific NRC approval of these elements. Regulatory guides are not substitutes for regulations, and compliance with them is not required. Methods and solutions that differ from those set forth in RGs will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission. Accordingly, any submittal addressing these additional FPP elements needs to include sufficient detail to allow the NRG staff to assess whether the licensee's treatment of these elements meets the 10 CFR 50.48{c) requirements.

The purpose of the FPP established by NFPA 805 is to provide assurance, through a defense-in-depth (DID) philosophy, that the NRC's fire protection objectives are satisfied.

NFPA 805 Section 1.2, "Defense-in-Depth," states the following:

Protecting the safety of the public, the environment, and plant personnel from a plant fire and its potential effect on safe reactor operations is paramount to this standard. The fire protection standard shall be based on the concept of defense-in-depth. Defense-in-depth shall be achieved when an adequate balance of each of the following elements is provided:

(1)

Preventing fires from starting; (2)

Rapidly detecting fires and controlling and extinguishing promptly those fires that do occur, thereby limiting tire damage; and (3)

Providing an adequate level of fire protection for structures, systems and components important to safety, so that a fire that is not promptly extinguished will not prevent essential plant safety functions from being performed.

In addition, in accordance with Appendix A, "General Design Criteria for Nuclear Power Plants,"

to 10 CFR Part 50, General Design Criterion {GDC) 3, "Fire protection," fire detection and fighting systems must be designed such that their rupture or inadvertent operation does not significantly impair the ability of the structures, systems, and components important to safety to perform their intended safety functions.

In addition, 10 CFR 50.32 states, in part, that the applicant may incorporate by reference information contained in previous applications, statements or reports filed with the Commission, provided, that such references are clear and specific.

The following GDC regulations address fire protection:

FNP Criterion 3, "Fire Protection," states, in part, that:

Structures, systems, and components important to safety are designed and located to minimize, consistent with other safety requirements, the probability and effect of fires and explosions. Noncombustible and heat resistant materials are used wherever practical throughout the unit, particularly in locations such as the containment and control room. Fire detection and fighting systems of appropriate capacity and capability are provided and designed to minimize the adverse effects of fires on structures, systems, and components important to safety. Firefighting systems are designed to assure that their rupture or inadvertent operation does not significantly impair the safety capability of these structures, systems, and components.

Regulations in 1 O CFR 50.48(a)(1) requires that each holder of an operating license have a fire protection plan that satisfies GDC 3 of Appendix A to 10 CFR 50.

Regulations in 10 CFR 50.48(c) incorporates NFPA 805 (2001 Edition) by reference, with certain exceptions, modifications, and supplementation. This regulation establishes the requirements for using an RI/PB FPP in conformance with NFPA 805 as an alternative to the requirements associated with 10 CFR 50.48(b) and Appendix R, "Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979," to 1 O CFR 50, or the specific plant fire protection license condition.

The NRC staff review also relied on the following additional codes, RGs, and standards:

RG 1.205, Revision 1, "Risk-Informed, Periormance-Based Fire Protection for Existing Light-Water Nuclear Power Plants," issued December 2009 (Reference 8), provides guidance for use in complying with the requirements that the NRG has promulgated for RI/PB FPPs that comply with 10 CFR 50.48 and the referenced 2001 Edition of the NFPA standard. RG 1.205 sets forth regulatory positions, emphasizes certain issues, clarifies the requirements of 10 CFR 50.48(c) and NFPA 805, clarifies the guidance in Nuclear Energy Institute (NEI) 04-02 (Reference 9), and provides exceptions to the NEl-04-02 guidance where required. Should a conflict occur between NEI 04-02 and this RG, the regulatory positions in RG 1.205 govern.

RG 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,"

Revision 2, issued May 2011 (Reference 10), provides the NRC staff's recommendations for using risk information in support of licensee-initiated licensing basis changes to a nuclear power plant that require such review and approval.

NUREG/CR-6850, "EPRl/NRC-RES Fire PRA Methodology for Nuclear Power Facilities," Volumes 1 and 2 and Supplement 1, September 2005 and September 2010, respectively (Reference 11), (Reference 12), and (Reference 13), presents a compendium of methods, data, and tools to perform an FPRA and develop associated insights.

3.0 TECHNICAL EVALUATION

3.1 Licensee's Submittal Amendment No. 196 to RFOL No. NPF-2 for FNP, Unit 1, and Amendment No. 192 to RFOL No. NPF-8 for FNP, Unit 2 (Reference 2), implemented the licensee's transition to an RI/PB FPP based on NFPA 805, in accordance with i 0 CFR 50.48(c). Amendment No. 205 to RFOL No. NPF-2 for FNP, Unit 1, and Amendment No. 201 to RFOL No. NPF-8 for FNP, Unit 2 (Reference 5), implemented changes to certain modifications being completed for NFPA 805.

As part of the transition license conditions 2.C.(4).c.2). and 2.C.(6).(c).2., the licensee is to complete 12 plant modifications as listed in Attachment S, Table S-2, of the licensee's letter dated April 25, 2016 (Reference 4), by November 6, 2017.

Subsequent to the issuance of the amendments, the licensee indicated that modification item 11 may not be able to be completed by November 6, 2017. In its LAR, the licensee proposed to change the completion date for modification item 11 to its facility as described in Attachment S, "Modifications and Implementation Items", Table S-2, "Plant Modifications Committed", of its letter dated April 25, 2016, from "November 6, 2017", to "before the conclusion of the 1 R28 Spring 2018 Refueling Outage". To support this change, the licensee submitted revised versions of its fire protection license condition and also revised page S-2 of Attachment S, "Modifications and Implementation Items."

The licensee stated that all other modifications in Table S-2 of Attachment Shave been, or will be, completed prior to November 6, 2017. Specifically, the licensee indicated the following:

Modifications Items 1 through 5, 8 through 10, and 12 are complete.

Modification Items 6 and 7 are ongoing and expected to be completed prior to the completion date.

For Modification Item 11, the licensee stated, in part, that:

The implementation date extension is requested due to possible delays in the completion of Item 11: Circuit Supervision.

For Item 11 multiple delays in the development of designs associated with this modification combined with late scope growth requiring design revisions resulted in the implementation starting late in the project life cycle schedule. The current schedule for design delivery is being met, however, there is very little margin in the schedule for discovery such as the items currently being resolved around legacy system interface issues in post-modification testing. To date all circuit supervision construction implementation is expected to complete prior to the commitment date, however, there remain concerns that post-modification testing may encounter legacy equipment issues and may not be able to be completed prior to the commitment date.

SNC is requesting that the completion date for the circuit supervision post-modification testing and final acceptance by site Operations be revised from November 6, 2017 to the conclusion of the 1 R28 Spring 2018 refueling outage, to ensure legacy system interface issues are fully resolved including any issues encountered which require outage to correct. This is based on Unit 2 refueling outage in October 2017 and Unit 1 refueling outage in April 2018.

3.2 NFPA 805, Section 4.2.4.2 NFPA 805, Section 4.2.4.2, requires that the "use of fire risk evaluation for the PB approach shall consist of an integrated assessment of the acceptability of risk, defense-in-depth, and safety margins."

Regarding defense-in-depth and safety margins, in SNC's letter dated August 11, 2017, the licensee stated:

The requested extension of the implementation date for the Circuit Supervision modification is an administrative change that does not impact the original defense-in-depth (DID) and safety margin evaluations associated with the original LAA.

Defense-in-Depth As a supplement to the definition of DID provided in NFPA 805, Section 1.2, the NRG-endorsed guidance in NEI 04-02, Section 5.3.5.2, states that:

In general, the defense-in-depth requirement is satisfied if the proposed change does not result in a substantial imbalance in:

Preventing fires from starting; Detecting fires quickly and extinguishing those that do occur, thereby limiting fire damage; and Providing adequate level of fire protection for structures, systems and components important to safety, so that a fire that is not promptly extinguished will not prevent essential plant safety functions [from] being performed.

Safety Margins Although not a part of the requirements of NFPA 805, and thus not required under 10 CFR 50.48(c), NFPA 805, Appendix A, Section A.2.4.4.3, provides the following background related to the meaning of the term "safety margins":

An example of maintaining sufficient safety margins occurs when the existing calculated margin between the analysis and the perlormance criteria compensates for the uncertainties associated with the analysis and data.

Another way that safety margins are maintained is through the application of codes and standards. Consensus codes and standards are typically designed to ensure such margins exist.

NEI 04-02, Section 5.3.5.3, "Safety Margins," lists two specific criteria that should be addressed when considering the impact of plant changes on safety margins:

Codes and standards or their alternatives accepted for use by the NRC are met; and, Safety analysis acceptance criteria in the licensing basis (e.g., FSAR

[Final Safety Analysis Report], supporting analyses, etc.) are met, or provides sufficient margin to account for analysis and data uncertainty.

Risk Evaluation In SNC's letter dated August 11, 2017, the licensee stated, in part, that:

The requested extension of implementation date for the Circuit Supervision does not impact the fire PRA insights. Fire detection and suppression is still effective without the supervision as credited in the fire PAA. The supervision may be beneficial to recover the detection and suppression system if failed. However, since the recovery or repair of the failed detection and suppression system is not credited in the fire PRA, the implementation of Circuit Supervision does not impact the fire PAA.

3.3 NRG Staff Evaluation In accordance with 10 CFR 50.48(c)(3)(i), the licensee submitted a LAA to revise its NFPA 805 transition license conditions 2.C.(4).c.2) and 2.C.(6).(c).2. The NRG staff reviewed the information provided by the licensee in its LAA that included discussions of the impact of the proposed change on risk, DID, and safety margin as required by NFPA 805, Section 4.2.4.2. In regard to risk, the NRG staff confirmed the proposed change does not challenge the RG 1.174 acceptance guidelines because the proposed change is an administrative change only that has no apparent impact on total plant risk. The NRG staff also confirmed that the acceptance guidelines in RG 1.205 continue to be satisfied because the results for total plant risk and change in risk are not changed when compared to the values reported in the NFPA 805 SE (Reference 2).

In regard to DID, the NRC staff confirmed the proposed change has no impact on any of the DID echelons because changing the completion date for a modification is not considered a change in methods. The proposed schedule change does not impact the level of fire protection provided so that a fire will not prevent essential safety functions from being performed.

In regard to safety margins, the NRG staff confirmed that the proposed change continues to maintain adequate safety margins, in part, because the change does not impact any codes and standards, or their alternatives accepted for use by the NRG, and because the change does not impact any safety analysis acceptance criteria used in the licensing basis.

3.4 NRC Staff Conclusion

The NRG staff reviewed the licensee's application to change the completion date for Modification Item 11 related to the RI/PB FPP in accordance with the requirements of 10 CFR 50.48(c) and NFPA 805. The licensee's application identified revisions to the license condition in accordance 10 CFR 50.48(c)(3)(i). The changes proposed by the licensee included a review of risk, DID, and safety margin, as requtced by NFPA 805, Section 4.2.4.2. The NRC staff concludes that the licensee's application provided the appropriate license conditions that must be revised as a result of the proposed change, and that the revisions meet the requirements of 10 CFR 50.48(c)(3)(i).

The NRC staff concludes that the results of the licensee's evaluation in regard to risk, DID, and safety margin is acceptable because (1) the change does not impact the FPRA and has no apparent impact on total plant risk and change in risk with respect to the values reported in the NFPA 805 SE (Reference 2), and thus, does not challenge the RG 1.174 risk acceptance guidelines; (2) the licensee's process and result followed guidance approved by the NRG staff in its NFPA 805 SE; and (3) the results of the change are consistent with guidance in NEI 04-02, Revision 2 (Reference 9); RG 1.205, Revision 1 {Reference 8); and RG 1.174, Revision 2 (Reference 10).

Implementation of the RI/PB FPP under 10 CFR 50.48(c) must be in accordance with the fire protection license condition, which identifies the list of modifications and implementation items that must be completed in order to support the NRG staff's conclusion and establishes a date by which full compliance with 10 CFR 50.48(c) must be achieved. Before the licensee is able to fully implement the transition to an FPP based on NFPA 805 and apply the new fire protection license condition to its full extent, the modifications and implementation items must be completed within the timeframe specified.

4.0 FIRE PROTECTION LICENSE CONDITION On March 1 O, 2015, the NRG issued Amendment No. 196 to RFOL License No. NPF-2 for FNP, Unit 1, and Amendment No. 192 to RFOL No. NPF-8 for FNP, Unit 2 (Reference 2), which revised the existing tire protection license conditions to ones that address the transition to a risk-informed, performance-based FPP under NFPA 805 in accordance with 10 CFR 50.48(c)(3)(i). The new license conditions adopted the guidelines of the standard fire protection license condition promulgated in RG 1.205, Revision 1, Regulatory Position C.3.1, as issued on December 18, 2009 (74 FR 67253). Plant-specific changes were made to the sample license condition; however, the plant-specific FPP license conditions are consistent with the standard fire protection license condition and incorporated all of the relevant features of the transition to NFPA 805 at FNP.

In SNC letter dated April 25, 2016, the licensee submitted a LAR (Reference 4) for license amendments to change fire protection license condition 2.C.(4) for Unit 1 and license condition 2.C.(6) for Unit 2. The changes made to the license conditions include adding the licensee's April 25, 2016 LAR, and adding the issuance date of the SE. No other changes to the license conditions were requested by the licensee or identified by the NRC staff. On October 17, 2016, the NRG issued Amendment No. 205 to RFOL No. NPF-2 for FNP, Unit 1, and Amendment No. 201 to RFOL No. NPF-8 for FNP, Unit 2 (Reference 5), approving the licensee's proposed changes.

In SNC letter dated August 11, 2017, the licensee proposed the following license condition for FNP, Units 1 and 2, to replace RFOL Nos. NPF-2 and NPF-8, Condition 2.C.(4) and Condition 2.C.(6):

Fire Protection Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment requests dated September 25, 2012; April 25, 2016; and supplements dated December 20, 2012; September 16, 2013; October 30, 2013; November 12, 2013; April 23, 2014; May 23, 2014; July 3, 2014; August 11, 2014; August 29, 2014; October 13, 2014; January 16, 2015, and August 11, 2017, as approved in the safety evaluation reports dated March 10, 2015, October 17, 2016, and November 1, 2017. Except where NRG approval for changes or deviations is required by 1 O CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRG approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 1 O CFR 50.48(c),

the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

a.

Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at Farley. Acceptable methods to assess the risk of the change may include methods that have been used in the peer-reviewed fire PRA model, methods that have been approved by NRG through a plant-specific license amendment or NRC approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.

1)

Prior NRC review and approval is not required for changes that clearly result in a decrease in risk. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.

2)

Prior NRG review and approval is not required for individual changes that result in a risk increase less than 1x10-1/year (yr) for GDF and less than 1x10-8/yr for LERF. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.

b.

Other Changes that May Be Made Without Prior NRG Approval

1)

Changes to NFPA 805, Chapter 3, Fundamental Fire Protection Program Prior NRG review and approval are not required for changes to the NFPA 805, Chapter 3, fundamental fire protection program elements and design requirements for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is functionally equivalent or adequate for the hazard. The licensee may use an engineering evaluation to demonstrate that a change to an NFPA 805, Chapter 3, element is functionally equivalent to the corresponding technical requirement. A qualified fire protection engineer shall perform the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard.

The licensee may use an engineering evaluation to demonstrate that changes to certain NFPA 805, Chapter 3, elements are acceptable because the alternative is "adequate for the hazard."

Prior NRG review and approval would not be required for alternatives to four specific sections of NFPA 805, Chapter 3, for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is adequate for the hazard. A qualified fire protection engineer shall pertorm the engineering evaluation and conclude that the change has not affected the functionality of the component, system, procedure, or physical arrangement, using a relevant technical requirement or standard. The four specific sections of NFPA 805, Chapter 3, are as follows:

"Fire Alarm and Detection Systems" (Section 3.8);

"Automatic and Manual Water-Based Fire Suppression Systems" (Section 3.9);

"Gaseous Fire Suppression Systems" (Section 3.1 O); and "Passive Fire Protection Features" (Section 3.11 ).

This License Condition does not apply to any demonstration of equivalency under Section 1.7 of NFPA 805.

2)

Fire Protection Program Changes that Have No More than Minimal Risk Impact Prior NRG review and approval are not required for changes to the licensee's fire protection program that have been demonstrated to have no more than a minimal risk impact. The licensee may use its screening process as approved in the NRC safety evaluations dated March 10, 2015 and October 17, 2016, to determine that certain fire protection program changes meet the minimal criterion.

The licensee shall ensure that fire protection DID and safety margins are maintained when changes are made to the fire protection program.

c.

Transition License Conditions

1)

Before achieving full compliance with 10 CFR 50.48(c), as specified by 2) below, risk-informed changes to SNC's fire protection program may not be made without prior NRG review and approval unless the change has been demonstrated to have no more than a minimal risk impact, as described in 2) above.

2)

The licensee shall implement the modifications to its facility, as described in Attachment S, Table S-2, "Plant Modifications Committed," of SNC letter NL-15-2310, dated April 25, 2016, to complete the transition to full compliance with 10 CFR 50.48(c) before the conclusion of the 1 R28 Spring 2018 Refueling Outage as provided in SNC letter dated August 11, 2017. The licensee shall maintain appropriate compensatory measures in place until completion of these modifications.

3)

The licensee shall implement the items as listed in Attachment S, Table S-3, "Implementation Items," of SNC letter NL-15-2310, dated April 25, 2016, within 180 days after NRG approval, except for items 30 and 32. Items 30 and 32 shall be implemented by February 6, 2018.

5.0 STATE CONSULTATION

In accordance with the Commission's regulations, the State of Alabama official was notified of the proposed issuance of the amendments on October 5, 2017. The State official had no comments.

6.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements with respect to the installation or use of a facility component located within the restricted area as defined in 1 O 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 published in the Federal Register on August 29, 2017 (82 FR 41059). Accordingly, the amendments meet the eligibility criteria tor categorical exclusion set forth in 10 CFR 51.22(c)(9).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

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.

8.0 REFERENCES

1.

Ajluni, M. J., Southern Nuclear Operating Company, letter to U.S. Nuclear Regulatory Commission, "Joseph M. Farley Nuclear Plant, License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants {2001 Edition)," dated September 25, 2012, Agencywide Documents Access and Management System (ADAMS) Accession No ML12279A235).

2.

Williams, Shawn, U.S. Nuclear Regulatory Commission, letter to C. R. Pierce, Southern Nuclear Operating Company, Inc. "Joseph M. Farley Nuclear Plant, Units 1 and 2 -

Issuance of Amendment Regarding Transition to a Risk-Informed, Periormance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) (TAC Nos. ME9741 and ME9742) Amendment Nos. 196 and 192, March 10, 2015 (ADAMS Accession No. ML14308A048).

3.

National Fire Protection Association, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," Standard 805 (NFPA 805), 2001 Edition, Quincy, Massachusetts.

4.

Pierce, Charles R., Southern Nuclear Operating Company, Inc., letter to U.S. Nuclear Regulatory Commission, "Joseph M. Farley Nuclear Plant - Units 1 and 2 Supplemental License Amendment Request to Revise Existing Facility Operating License Commitments Regarding NFPA-805 Periormance Based Standard for Fire Protection for Light Water Reactor Generating Plants," April 25, 2016 (ADAMS Accession No. ML16120A294).

5.

Williams, Shawn A., U.S. Nuclear Regulatory Commission letter to Charles R. Pierce, Southern Nuclear Operating Company, Inc., "Joseph M. Farley Nuclear Plant, Units 1 and 2 - Issuance of Amendments Related to NFPA-805 Supplement (CAC NOS.

MF7617 and MF7618) - Amendment Nos. 205 and 201, October 17, 2016 (ADAMS Accession No. ML16232AOOO).

6.

Meier, Michael, Southern Nuclear Operating Company, letter to U.S. Nuclear Regulatory Commission, "Joseph M. Farley Nuclear Plant, Units 1 and 2, NFPA-805 Transition Due Date Extension," August 11, 2017 (ADAMS Accession No. ML17226A291).

7.

Pierce, Charles R., Southern Nuclear Operating Company, letter to U.S. Nuclear Regulatory Commission, "Joseph M. Farley Nuclear Plant Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA-805 Periormance Based Standard for Fire Protection for Light Water Reactor Generating Plants," August 29, 2014 (ADAMS Accession No. ML14246A523).

8.

U.S. Nuclear Regulatory Commission, Regulatory Guide 1.205, Revision 1, (RG 1.205)

"Risk-Informed, Periormance-Based Fire Protection for Existing Light-Water Nuclear Power Plants," December 2009 (ADAMS Accession No. ML092730314).

9.

Nuclear Energy Institute, NEI 04-02, Revision 2, "Guidance for Implementing a Risk-Informed, Periormance-Based Fire Protection Program Under 10 CFR 50.48(c),"

April 2008 (ADAMS Accession No. 081130188).

1 O.

U.S. Nuclear Regulatory Commission, Regulatory Guide 1.174, Revision 2, (RG 1.174)

"An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," May 2011 (ADAMS Accession No. ML100910006).

11.

U.S. Nuclear Regulatory Commission, NUREG/CR-6850, "EPRl/NRC-RES Fire PRA Methodology for Nuclear Power Facilities, Volume 1: Summary & Overview Final Report, September 2005 (ADAMS Accession No. ML052580075).

12.

U.S. Nuclear Regulatory Commission, NUREG/CR-6850, Final Report, "EPRl/NRC-RES Fire PAA Methodology for Nuclear Power Facilities, Volume 2: Detailed Methodology,"

September 2005 (ADAMS Accession No. ML052580t 18).

13.

U.S. Nuclear Regulatory Commission, NUREG/CR-6850, Supplement 1, "Fire Probabilistic Risk Assessment Methods Enhancements," Technical Report, September 2010 (ADAMS Accession No. ML103090242).

Principal Contributor: Jay Robinson Date: November 1, 2017

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT. UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RELATED TO NFPA 805 SUPPLEMENT (CAC NOS. MG0094, MG0095: EPID NO. L-2017-LLA-0261) DATED NOVEMBER 1, 2017 DISTRIBUTION:

PUBLIC RidsACRS_MailCTR Resource RidsNrrLAKGoldstein Resource RidsRgn2MailCenter Resource RidsNrrPMFarley Resource RidsNrrDorllpl2-1 Resource RidsNrrDraAfpb Resource JRobinson, NRR ADAM s Accession No.: ML17269A166 OFFICE DORULPL2-1/PM NAME SWilliams DATE 10/05/17 OFFICE OGG (NLO)

NAME DRo1h DATE 10/17/17 DORULPL2-1/LA KGoldstein 10/04/17 DORULPL2-1/BC MMarklev 10/31/17 OFFICIAL RECORD COPY

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>v 1nterna memo DRA/AFPB/BC*

GCasto 09/29/17 DORULPL2-1/PM SWilliams 11/01/17