ML14350A008

Issuance of Amendment to Revise the Requirement Regarding the Shift Technical Advisor

ML14350A008
Person / Time
Site:	Saint Lucie
Issue date:	06/01/2015
From:	Farideh Saba, Tam P Plant Licensing Branch II
To:	Nazar M NextEra Energy
Tam P, NRR/DORL/LPL2-2, 415-4098
References
TAC MF4263, TAC MF4264
Download: ML14350A008 (16)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June1,2015 Mr. Mano Nazar President and Chief Nuclear Officer Nuclear Division NextEra Energy P.O. Box 14000 Juno Beach, FL 33408-0420

SUBJECT:

ST. LUCIE PLANT, UNIT NOS. 1 AND 2 - ISSUANCE OF AMENDMENTS TO REVISE THE REQUIREMENT REGARDING THE SHIFT TECHNICAL ADVISOR (TAC NOS. MF4263 AND MF4264)

Dear Mr. Nazar:

The U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued the enclosed Amendment Nos. 221 and 171 to Renewed Facility Operating License Nos. DPR-67 and NPF-16 for the St. Lucie Plant, Unit Nos. 1 and 2, respectively. These amendments consist of changes to the technical specifications (TSs) in response to your application dated June 9, 2014, as supplemented by letter dated April 3, 2015.

The amendments clarify the requirement for the Shift Technical Advisor (STA) in TS 6.2.2.e to allow the STA position be filled for each unit by a dedicated STA, an STA qualified Shift Supervisor, or an STA qualified Senior Reactor Operator. Additionally, the dedicated STA or the STA qualified Shift Supervisor can fillthe STA position on both units.

The NRC staff's related safety evaluation of the amendments is enclosed. The Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely,

-(!far-, ~l s. ~~(_

Farideh E. Saba, Senior 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. 221. to DPR-67

2. Amendment No. l7l to NPF-16

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-335 ST. LUCIE PLANT, UNIT NO. 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 221 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 (FPL, the licensee), dated June 9, 2014, as supplemented by letter dated April 3, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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. 221 , are hereby incorporated in the renewed license.

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

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

FOR THE NUCLEAR REGULATORY COMMISSION Shana R. Helton, Chief Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: June 1, 2015

ATTACHMENT TO LICENSE AMENDMENT NO. 221 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 Appendix A, Technical Specifications, with the attached page.

The revised page is identified by amendment number and contains a vertical line indicating the area of change.

Remove Page Insert Page 6-2 6-2

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. 221 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. 221

6.0 ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION (continued)

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

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

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

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

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

e. An individual (Shift Technical Advisor (STA)) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. The STA position shall be manned in MODES 1, 2, 3, or 4 by use of either a dedicated STA, a Shift Supervisor who meets the qualifications for the STA as required by Technical Specification 6.3.1, or an individual assigned to the unit with a Senior Reactor Operator's license who meets the qualifications for the STA as required by Technical Specification 6.3.1. If the STA position is filled by an STA qualified Shift Supervisor or dedicated ST A, then the individual may fill the same position on Unit 2.

ST. LUCIE - UNIT 1 6-2 Amendment No . .W, 26, ea, S9, 96, ~. 449, 41-7, 499, ~ 221

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 FLORIDA POWER AND LIGHT COMPANY DOCKET NO. 50-389 ST. LUCIE PLANT UNIT NO. 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 171 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 (FPL, the licensee), dated June 9, 2014, as supplemented by letter dated April 3, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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 3.8 to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 171 , are hereby incorporated in the renewed license.

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

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

FOR THE NUCLEAR REGULATORY COMMISSION Shana R. Helton, Chief Plant Licensing Branch 11-2 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Renewed Facility Operating License and Technical Specifications Date of Issuance: June 1, 2015

ATTACHMENT TO LICENSE AMENDMENT NO. 171 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 Appendix A, Technical Specifications, with the attached page.

The revised page is identified by amendment number and contains a vertical line indicating the area of change.

Remove Page Insert Page 6-2 6-2

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 CFR 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).

8. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 171 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. 171

6.0 ADMINISTRATIVE CONTROLS 6.2 ORGANIZATION (Continued)

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

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

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

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

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

e. An individual (Shift Technical Advisor (STA)) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. The STA position shall be manned in MODES 1, 2, 3, or 4 by use of either a dedicated STA, a Shift Supervisor who meets the qualifications for the STA as required by Technical Specification 6.3.1, or an individual assigned to the unit with a Senior Reactor Operator's license who meets the qualifications for the STA as required by Technical Specification 6.3.1. If the STA position is filled by an STA qualified Shift Supervisor or dedicated ST A, then the individual may fill the same position on Unit 1.

ST. LUCIE - UNIT 2 6-2 Amendment No. ~. ea, 90, W, 423, 446, 4W, 4fil. 171

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 221 AND 171 TO RENEWED FACILITY OPERATING LICENSE NOS. DPR-67 AND NPF-16 FLORIDA POWER AND LIGHT COMPANY ST. LUCIE PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-335 AND 50-389

1.0 INTRODUCTION

By letter dated June 9, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14175A121), as supplemented by letter dated April 3, 2015 (ADAMS Accession No. ML15103A482), Florida Power and Light Company (FPL, the licensee) submitted a license amendment request (LAR) to change Technical Specification (TS) 6.2, "Organization," for St. Lucie Plant, Unit Nos. 1 and 2 (SL-1 and SL-2). The purpose of this LAR was to clarify the requirement for the Shift Technical Advisor (STA) set forth in TS 6.2.2.e by returning the wording to wording equivalent to that previously approved in Amendment Nos. 173 and 113 dated March 14, 2001 (ADAMS Accession No. ML010860127), for SL-1 and SL-2, respectively. The wording of TS 6.2 was inadvertently changed by Amendment Nos. 217 and 167 dated February 7, 2014 (ADAMS Accession No. ML14016A248), for SL-1 and SL-2, respectively. Returning to wording equivalent to the wording of Amendment Nos. 173 and 113, TS 6.2.2.e will allow the STA position for each unit to be manned by a dedicated STA, a Shift Supervisor who meets the qualifications for STA, or a Senior Reactor Operator (SRO) who meets the qualifications for STA. Additionally, the dedicated STA or the STA qualified Shift Supervisor can fill the STA position on both units.

2.0 REGULATORY EVALUATION

The regulatory requirements and guidance that the U.S. Nuclear Regulatory Commission (NRC) staff considered in its review of the licensee's application are as follows:

NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light-Water Reactor] Edition," Chapter 13, "Conduct of Operations," Sections 1.2 - 13.1.3, "Operating Organization."

Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications," specifically 10 CFR 50.36(c), which identifies the categories of information to be included in the TSs.

Enclosure 3

10 CFR 50.54, "Conditions of license," specifically 10 CFR 50.54(m), which is applicable to SL-1 and SL-2, and establishes the staffing requirements for, and duties of, licensed operators.

Generic Letter (GL) 86-04, "Policy Statement on Engineering Expertise on Shift" (ADAMS Accession No. ML031150270), dated February 13, 1986, which offers licensees two options for meeting the requirements for providing engineering expertise on shift (NUREG-0800 (previously NUREG-0737), Item l.A.1.1) and meeting licensed operator staffing requirements (10 CFR 50.54 (m)(2)) .

The licensee's supplement dated April 3, 2015, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on September 30, 2014 (79 FR 58818).

3.0 TECHNICAL EVALUATION

3.1 Description of Change The licensee proposed to delete the following sentences from TS 6.2.2.e:

The STA may be an STA qualified Shift Supervisor, or a dedicated STA. The STA shall be manned while either unit is in MODES 1, 2, 3, or 4. A single STA may fill the position for both units.

The licensee, in its letter dated April 3, 2015, proposed to replace the deleted sentences with the following sentences:

The STA position shall be manned in MODES 1, 2, 3, or 4 by use of either a dedicated STA, a Shift Supervisor who meets the qualifications for the STA as required by Technical Specification 6.3.1, or an individual assigned to the unit with a Senior Reactor Operator's license who meets the qualifications for the STA as required by Technical Specification 6.3.1. If the STA position is filled by an STA qualified Shift Supervisor or dedicated STA, then the individual may fill the same position on Unit [1 or 2].

3.2 Conformance with NRC Guidance 3.2.1 Policy Statement The policy statement cited in Section 2.0 above offers licensees two options for meeting the current requirements for providing engineering expertise on shift (NUREG-0737, Item l.A.1.1) and meeting licensed operator staffing requirements (10 CFR 50.54(m)(2)). Option 1 provides for elimination of the separate STA position by allowing licensees to combine one of the required Senior Reactor Operator (SRO) positions with the STA position into a dual-role (SRO/STA) position. Option 2 states that a licensee may continue to use an NRG-approved

STA program while meeting licensed operator staffing requirements. Licensees may use either option on each shift.

The licensee's proposed TS 6.2.2.e incorporates both Option 1 and Option 2 of the policy statement by allowing for any possible combination of qualifications from dual-role Shift Supervisor to dedicated STA. The NRC staff finds that the STA program for SL-1 and SL-2, as reflected in the proposed TS 6.2.2.e, is consistent with the NRC Policy Statement on Engineering Expertise on Shift (GL 86-04).

3.2.2 Previously Approved Wording As stated in Section 1. 0 above, on March 14, 2001, Amendment Nos. 173 and 113 (ADAMS Accession No. ML010860127) approved the following wording regarding the role of STA on SL-1 and SL-2:

A single, onsite STA position shall be manned in Mode 1, 2, 3, and 4 unless the Shift Supervisor meets the qualifications for the STA as required by Technical Specification 6.3.1 or an individual on each unit with a Senior Reactor Operator's license meets the qualifications for the STA as required by Technical Specification 6.3.1.

However, the licensee, in its letter dated July 26, 2013 (ADAMS Accession No. ML13219A840),

requested to replace the above wording with the following wording:

The STA may be an STA qualified Shift Supervisor or a dedicated STA. The STA shall be manned while either unit is in MODES 1, 2, 3, or 4. A single STA may fill the position for both units.

The licensee inadvertently deleted a criterion from the previously approved amendments (Amendment Nos. 173 and 113) and requested the removal of the ability to man the STA position by an individual on each unit with an SRO license that meets the qualification for the STA. The above revised wording was approved by Amendment Nos. 217 and 167 to SL-1 and SL-2, respectively, dated February 7, 2014 (ADAMS Accession No. ML14016A248). The licensee is proposing to return TS 6.2.2.e to wording equivalent to that previously approved by Amendment Nos. 173 and 113, as stated in Section 2.1 above.

Summary of Technical Evaluation Based on review of the submitted information, the NRC staff concludes that the proposed changes to SL-1 and SL-2 TS 6.2.2.e are acceptable from the human performance stand point because the changes reinstate wording equivalent to that of a deleted criterion from previously approved amendments, and the changes are consistent with the NRC Policy Statement on Engineering Expertise on Shift (GL 86-04). The existing SL-1 and SL-2 procedures and training adequately support the proposed amendment.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Florida State official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

This amendment relates to changes in record keeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets 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 this amendment.

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 amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: George W. Lapinsky Date: June 1, 2015

ML14350A008

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