ML13164A265

Issuance of Amendments Revising Station Battery Connection Resistances Acceptance Criteria in Technical Specifications

ML13164A265
Person / Time
Site:	Saint Lucie
Issue date:	08/30/2013
From:	Siva Lingam Plant Licensing Branch II
To:	Nazar M Florida Power & Light Co
Lingam S NRR/DORL/LPL2-2
References
TAC MF0429, TAC MF0430
Download: ML13164A265 (15)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 30, 2013 Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420 SUB,JECT: ST. LUCIE PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING STANDARDIZATION OF SENIOR REACTOR OPERATOR FUEL-HANDLING DUTIES (TAC NOS. MF0429 AND MF0430)

Dear Mr. Nazar:

The Nuclear Regulatory Commission (Commission, NRC) has issued the enclosed Amendment Nos.216 and 166 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 27,2012.

The amendments revise the St. Lucie TSs to align with Combustion Engineering Owners Group TS language describing required licensed Senior Reactor Operator duties during fuel-handling activities.

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

Sincerely,

~~.~

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389

Enclosures:

1. Amendment No. 216 to DPR-67

2. Amendment No. 166 to NPF-16

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER & LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 216 Renewed License No. DPR-67

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

A. The application for amendment by Florida Power & Light Company (the licensee), dated December 27,2012, 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 (0 that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ij) 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

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

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 216 , are hereby incorporated in the renewed license.

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

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

FOR THE NUCLEAR REGULATORY COMMISSION Douglas A. Broaddus, Acting Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: Augus t 30, 2013

ATTACHMENT TO LICENSE AMENDMENT NO. 216 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-67 DOCKET NO. 50-335 Replace Page 3 of Renewed Operating License DPR-67 with the attached Page 3.

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

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

Remove Page Insert Page 6-2 6-2

- 3 applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

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

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 216 are hereby incorporated in the renewed license.

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

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

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

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

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

Renewed License No. DPR-67 Amendment No.216

6.0 ADMINISTRATIVE C(J.JTROLS 6.2 ORGANIZATION (continued)

UNIT STAFF 6.2.2 The unit organization shall be subject to the following:

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

b. Deleted.

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

d. Deleted.

e. Deleted.

1. The health physics technician may be less than the minimum requirement for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

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

69. 93,~, 149, 4+7, 400 216

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER & LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO, FLORIDA AND FLORIDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST. LUCIE PLANT UNIT NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 166 Renewed License No. NPF-16

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

A. The application for amendment by Florida Power & Light Company, et al. (the licensee), dated December 27,2012, 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

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

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 166 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the TSs.

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

FOR THE NUCLEAR REGULATORY COMMISSION Douglas A. Broaddus, Acting Chief Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of Issuance: August 30, 2013

ATTACHMENT TO LICENSE AMENDMENT NO. 166 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-16 DOCKET NO. 50-389 Replace Page 3 of Renewed Operating License NPF-16 with the attached Page 3.

Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

Remove Page Insert Page 6-2 6-2

-3 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 10 CFR Part 50, and Section 70.32 of 10 CFR Part 70; and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

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

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 166are hereby incorporated in the renewed license.

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

Renewed License No. NPF-16 Amendment No. 166

6.0 ADMINISTRATIVE CQ;lTROLS 6.2 ORGANIZATION (Continued)

UNIT STAFF 6.2.2 The unit organization shall be subject to the following:

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

b. DELETED

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

d. DELETED

e. DELETED

f. DELETED

g. The operations supervisor shall hold a Senior Reactor Operator License.

1. The health physics technician may be less than the minimum requirement for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.

ST. LUCIE - UNIT 2 6-2 Amendment No. 29, M, 5&, 93, ~,

446,+W 166

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 216 AND 166 TO RENEWED FACILITY OPERATING LICENSES NOS. DPR-67 AND NPF-16 FLORIDA POWER AND LIGHT COMPANY, ET AL.

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

1.0 INTRODUCTION

By letter dated December 27,2012 (Agencywide Documents Access and Management System Accession No. ML13004A097), Florida Power & Light Company (the licensee) requested amendments to Renewed Facility Operating License Nos. DPR-67 for St. Lucie Plant Unit 1 and NPF-16 for the St. Lucie Plant Unit 2, and Appendix A, Technical Specifications (TSs), of the Facility Operating License. The proposed changes would delete redundancies in the TS Administrative Controls section, which describes required licensed Senior Reactor Operator (SRO) duties during fuel handling.

2.0 REGULATORY EVALUATION

The regulatory requirements and guidance that the Nuclear Regulatory Commission (NRC) staff considered in its review of the license amendment request (LAR) are as follows:

a. Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.120, "Training and qualification of nuclear power plant personnel" provides the requirements for the training program including a systems approach to training as defined in 10 CFR 55.4.

b. Section 55.4 of 10 CFR, "Definitions" includes the definitions for operator, senior operator, their active functions, and systems approach to training.

c. Section 50.54 of 10 CFR, "Conditions of licenses" describes senior operator duties during alteration of the reactor core.

d. NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition":

• Chapter 13 addresses "Conduct of Operations," specific sub-chapters considered in this review were Chapters 13.2.1, "Reactor Operator

- 2 Requalification Program; Reactor Operator Training," Rev. 3, and 13.5.2.1, "Operating and Emergency Operating Procedures," Rev. 2.

• Chapter 18, Rev. 2, provides review guidance for "Human Factors Engineering."

3.0 TECHNICAL EVALUATION

The licensee requests to delete TS 6.2.2.d, which specifies licensed SRO duties during fuel handling. This deletion is being requested in order to align St. Lucie TSs with Combustion Engineering Owners Group (CEOG) Standard TS NUREG-1432, Standard Technical Specifications for Combustion Engineering Plants, Volume 1, Revision 4.0, Section 5.3.2 language. TS 6.3.2 will remain as currently written, as it is consistent with the above CEOG Standard TS verbiage that directly references the requirements in regulation 10 CFR 50.54(m),

whereas TS 6.2.2.d uses custom language that is redundant. TS 6.2.2.d specifies:

Either a licensed SRO or licensed SRO limited to fuel handling who has no concurrent responsibilities during this operation shall be present during fuel handling and shall directly supervise all CORE ALTERATIONS.

Section 50.54(m)(2)(iv) of 10 CFR describes required licensed SRO duties during core alteration fuel load:

Each licensee shall have present, during alteration of the core of a nuclear power unit (including fuel loading or transfer), a person holding a senior operator license or a senior operator license limited to fuel handling to directly supervise the activity and, during this time, the licensee shall not assign other duties to this person.

TS 6.3.2 addresses licensed SRO duties to encompass fuel-handling operations using standard language, and will remain:

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

Because TS 6.2.2.d is not consistent with the regulation, removing it resolves potential conflict with TS 6.3.2 that was added in NRC-approved license amendments 210 and 159 (Units 1 and 2 respectively). Since TS 6.3.2 meets the requirements of 10 CFR 50.54(m), the NRC staff considers the deletion of TS 6.2.2.d acceptable.

5.0 STATE CONSULTATION

Based upon a letter dated May 2, 2003, from Michael N. Stephens of the Florida Department of Health, Bureau of Radiation Control, to Ms. Brenda L. Mozafari, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida does not desire notification of

-3 issuance of license amendments. In an email dated July 25,2012 (ADAMS Accession No. ML12208A014), from Cynthia Becker, Florida State Bureau of Radiation Control, to Farideh Saba, Senior Project Manager, U.S. Nuclear Regulatory Commission, the State of Florida confirmed that the May 2003 letter continues to reflect the State's position on notification of issuance of license amendments.

6.0 ENVIRONMENTAL CONSIDERATION

These amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding (78 FR 16884, dated March 19,2013). Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.

7.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) there is reasonable assurance that such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: M. Keefe K. Hemphill Date: August 30, 2013

August 30,2013 Mr. Mano Nazar Executive Vice President and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420

SUBJECT:

ST. LUCIE PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS REGARDING STANDARDIZATION OF SENIOR REACTOR OPERATOR FUEL-HANDLING DUTIES (TAC NOS. MF0429 AND MF0430)

Dear Mr. Nazar:

The Nuclear Regulatory Commission (Commission, NRC) has issued the enclosed Amendment Nos. 216 and 166 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 27,2012.

The amendments revise the st. Lucie TSs to align with Combustion Engineering Owners Group TS language describing required licensed Senior Reactor Operator duties during fuel-handling activities.

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

Sincerely, IRA!

Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-335 and 50-389

Enclosures:

1. Amendment No. 216 to DPR-67

2. Amendment No. 166 to NPF-16

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

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