ML15028A165

Issuance of Amendment to Revise Reactor Trip System Instrumentation Technical Specifications

ML15028A165
Person / Time
Site:	Farley
Issue date:	04/08/2015
From:	Shawn Williams Plant Licensing Branch II
To:	Pierce C Southern Nuclear Operating Co
Williams S
References
TAC MF4214, TAC MF4215
Download: ML15028A165 (19)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 8, 2015 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.

P. 0. Box 1295 I Bin - 038 Birmingham, AL 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, ISSUANCE OF AMENDMENT TO REVISE REACTOR TRIP SYSTEM INSTRUMENTATION TECHNICAL SPECIFICATIONS (TAC NOS. MF4214 AND MF4215)

Dear Mr. Pierce:

The Nuclear Regulatory Commission has issued the enclosed Amendment No.197 to Renewed Facility Operating License No. NPF-2 and Amendment No.193 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2, respectively. The amendments consists of changes to the Technical Specifications (TSs) in response to your application dated June 3, 2014.

The amendments revise the TS Limiting Condition for Operation 3.3.1 and Surveillance Requirement 3.2.4.2 in order to avoid confusion as to when a flux map for quadrant power tilt ratio monitoring is required.

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. 197 to NPF-2

2. Amendment No. 193 to NPF-8

3. Safety Evaluation cc w/encls: 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, INC.

ALABAMA POWERCOMPANY.

DOCKET NO. 50-348 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 197 Renewed License No. NPF-2

1.

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

A.

The application for amendment to the Joseph M. Farley Nuclear Plant, Unit 1, Renewed Facility Operating License No. NPF-2, filed by Southern Nuclear Operating Company, Inc. (the licensee), dated June*3, 2014, 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, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-2, is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, are hereby incorporated in the renewed facility operating license. Southern NuClear 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 120 days of issuance.

Attachment:

Changes to License No. NPF-2 And the Technical Specifications Date of Issuance: April 8, 2015.

FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, 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. INC.

ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 193 Renewed License No~ NPF-8

1.

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

A.

The application for amendment to ttie Joseph M. Farley Nuclear Plant, Unit 2, Renewed Facility Operating License No. NPF-8, filed by Southern Nuclear Operating Company, Inc. (the licensee), dated June 3, 2014, 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 1 O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Renewed Facility Operating License No. NPF-8 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 193, are hereby incorporated in the renewed facility operating license. Southern Nuclear 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 120 days of issuance.

Attachment:

Changes to License No. NPF-8 And the Technical Specifications Date of Issuance: Apr; 1 8, 2015 FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

ATTACHMENT TO LICENSE AMENDMENT NO. 197 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 AND LICENSE AMENDMENT NO. 193 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Renewed Facility Operating License and Appendix "A" Technical Specifications (TSs) with the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License NPF-2, page 4 NPF-8, page 3 TSs 3.2.4-4 3.3.1-2 3.3.1-3 License NPF-2, page 4 NPF-8, page 3 TSs 3.2.4-4 3.3.1-2 3.3.1-3

Farley - Unit 1 (2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 197, 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. 197 (2)

Alabama Power Company, p_ursuant to Section 103 of the Act and 10 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 10 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, for 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 I

Southern Nuclear is authorized to operate the faciiity 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. 193 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. 193

SURVEILLANCE REQUIREMENTS SR 3.2.4.1 SR 3.2.4.2 SURVEILLANCE

---

NOTES----------------

1.

With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER

~ 75% RTP, the remaining three power range channels can be used for calculating QPTR.

2.

SR 3.2.4.2 may be performed in lieu of this Surveillance.

Verify QPTR is within limit by calculation.

NOTE------*---*

Only required to be performed if input to QPTR from one or more Power Range Neutron Flux channels is inoperable with THERMAL POWER > 75% RTP.

Confirm that the normalized symmetric power distribution is consistent with QPTR.

QPTR 3.2.4 FREQUENCY In accordance with the Surveillance Frequency Control Program Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND In accordance with the Surveillance Frequency Control Program Farl.ey Units 1and2 3.2.4-4 Amendment No.197 (Unit 1)

Amendment No.193(Unit 2)

ACTIONS CONDITION C.

One channel or train inoperable.

D.

One Power Range Neutron Flux channel inoperable.

Farley Units 1 and 2 REQUIRED ACTION..

C.1 Restore channel or train to OPERABLE status.

OR C.2 Open RTBs.

---

NOTES---------

1.

The.inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing and setpoint adjustment of other channels.

2.

Refer to LCO 3.2.4 for an inoperable power range channel.

0.1 Place channel in trip.

RTS Instrumentation 3.3.1 COMPLETION TIME 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 49 hours 7~ hours (continued) 3.3.1-2 Amendment No.197(Unit1)

Amendment No.193 (Unit 2)

ACTIONS CONDITION D. (continued)

E.

One channel inoperable.

F.

THERMAL POWER > P-6 and< P-10, one Intermediate Range Neutron Flux channel inoperable.

Farley Units 1 and 2 REQUIRED ACTION OR D.2 Be in MODE 3.

RTS Instrumentation 3.3.1 COMPLETION TIME 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />

--NOTE---------

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for surveillance testing of other channels. -

E.1 Place channel in trip.

OR E.2 Be in MODE 3.

F.1 Reduce THERMAL POWER to < P-6.

QB F.2 Increase THERMAL POWER to> P-10.

3.3.1-3 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 78 hours 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours Amendment No.197 (Unit 1)

Amendment No.193 (Unit 2)

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 197 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-2 AND AMENDMENT NO. 193 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

By letter dated June 3, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14154A136), Southern Nuclear Operating Company (SNC, the licensee) submitted a request to change the Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2, Technical Specifications (TSs) and surveillance requirements (SRs).

The licensee proposed to revise the TS Limiting Condition for Operation (LCO) 3.3.1 and SR 3.2.4.2 related to the reactor trip system instrumentation. The revisions clarify TS action requirements to align flux mapping requirements by revising the TS LCO 3.3.1, Condition D, for one inoperable channel of power range neutron flux - high when the channel input to the quadrant power tile ratio (QPTR} is inoperable. The licensee also proposed to revise the Note in SR 3.2.4.2 to align flux mapping requirements in the two specifications.

The proposed no significant hazards consideration determination was published in the Federal Registeron July 22, 2014 (79 FR 42551).

2.0 REGULATORY EVALUATION

The Reactor Trip System (RTS) Instrumentation initiates a unit shutdown, based on the values of selected unit parameters, to protect against violating the core fuel design limits and Reactor Coolant System pressure boundary during anticipated operational occurrences and to assist the Engineered Safety Features Systems in mitigating accidents. The protection and monitoring systems have been designed to assure safe operation of the reactor.

This is achieved by specifying limiting safety system settings in terms of parameters directly monitored by the RTS, as well as specifying LCOs on other reactor system parameters and equipment performance.

In Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.36, the U.S. Nuclear Regulatory Commission (NRC) established its regulatory requirements related to the content of

. TSs. Pursuant to 10 CFR 50.36, TSs are required to include items in the following five specific categories related to plant operation: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls. Category (2), Section 50.36(c)(2)(i), establishes the lowest functional capability or performance levels of equipment required for safe operation of the facility. Category (2) further requires, "When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met." Category (3), Section 50.36(c)(3),

establishes requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. The rule does not, however, specify the particular requirements to be included in plant LCO (Category 2) or SR (Category 3) TSs.

• In 1992, the NRC issued improved Standard Technical Specifications (STSs) to clarify the content

. and form of requirements necessary to ensure safe operation of nucl.ear power plants in accordance with all categories of requirements specified in 10 CFR 50.36. In general, a licensee cannot justify TS changes solely on the basis of adopting the model STSs. Changes that result in relaxation (less restrictive conditions) of TS requirements require detailed justification. When requirements have been shown to give little or no safety benefit, their relaxation or removal from the TSs may be appropriate.

Other changes made to adopt the model STSs are new, more conservative requirements than corresponding requirements in the current TSs (CTSs), or have additional restrictions that are not in the CTSs but are in the STSs. The NRC staff evaluates the additional restrictions on plant operation to ensure that they enhance safety. Additionally, non-technical (administrative) TSs changes that incorporated human factors principles for the preferred format into the form and structure of the TSs so that plant operations personnel can use them more easily were evaluated by the NRC staff. These changes are editorial in nature or involve the reorganization or reformatting of CTS requirements without affecting technical content or operational restrictions.

Consequently, licensees making application to change plant-specific TS requirements, even though the changes are modeled after STSs, must include a plant-specific justification that is found to be acceptable to the NRC staff for complying with the requirements of10 CFR 50.36.

Therefore, in review of the Farley Unit 1 and Unit 2 license amendment request dated June 3, 2014, the NRC staff's review made use of applicable regulations and regulatory guidance which includes the following:

10 CFR 50.36, Technical Specifications. 50.36(c)(2)(i), Limiting conditions for operation, and 50.36(c)(3) Surveillance requirements.

NUREG-1431, "Standard Technical Specifications, Westinghouse Plants," Revision 4.0, dated April 2012 (ADAMS Accession No ML12100A222).

The proposed amendment would revise TS LCO 3.3.1 Condition D, Required Actions, and the Note to SR 3.2.4.2 to align flux mapping requirements in the two specifications, and thus avoid confusion as to when a flux map for QPTR is required. Specifically, the proposed changes would revise TS 3.3.1, Condition D, and the Note in SR 3.2.4.2 as follows:

LCO 3.3.1, "RTS Instrumentation," Condition D, One Power Range Neutron Flux - High channel inoperable.

o Required Actions D.1.2, D.2.1 and D.2.2 are deleted. The remaining Required Actions are renumbered accordingly.

o A Note is added to refer to LCO 3.2.4 for an inoperable power range channel. The existing Note becomes Note 1 and the new Note is Note 2.

SR 3.2.4.2, "QPTR," the Note is revised to require performance of the surveillance when power range neutron flux QPTR inputs are inoperable. The time component of the note is moved and updated to agree with initial frequency of the deleted LCO 3.3.1 Required Action D.2.2.

The licensee stated that the proposed changes to delete Required Actions D.1.2, D.2.1 and D.2.2 will avoid confusion as to when a flux map for QPTR is required. The licensee also stated that deleting these requirements from LCO 3.3.1 eliminates requirements that are duplicated in LCO 3.2.4.

3.0 TECHNICAL EVALUATION

Power Range Neutron Flux Instrumentation The nuclear instrumentation system (NIS) power range detectors are located external to the reactor vessel and measure neutrons.leaking from the core. The NIS power range detectors provide input to the rod control system. The power range neutron flux,.. high trip function ensures that protection is provided, from all power levels, against a positive reactivity excursion leading to departure from nucleate boiling during power operations. These can be caused by rod withdrawal or reductions in reactor coolant system temperature. The LCO requires all four of the power range neutron flux - high channels to be OPERABLE in Modes 1 and 2. The four sets of power' range neutron flux instruments are equally spaced circumferentially outside the core in 4 radial quadrants. The output of each instrument is compared with the average. If a ratio > 1.02 is calculated an alarm for detector flux deviation is generated. This ratio is the TS limit for QPTR.

QPTR Limits The QPTR limit ensures that the gross radial power distribution remains consistent with the design values used in the safety analyses. Precise radial power distribution measurements are made during startup testing, after refueling, and periodically during power operation. With an NIS power range channel inoperable, tilt monitoring for a portion of the reactor core becomes degraded. Large tilts are likely detected with the remaining channels, but the capability for detection of small power tilts in some quadrants is decreased. SR 3.2.4.2 usually involves using moveable incore detectors to perform a flux map. Performing SR 3.2.4.2 at a frequency in accordance with surveillance frequency control program provides an accurate alternative means for ensuring that any tilt remains within its limits.

3.1 One Power Range Neutron Flux - High Channel Inoperable Reactor Trip System Instrumentation, LCO 3.3.1, Condition D, applies to one power range neutron flux - high channel inoperable. Condition D provides Required Actions D.1.1 and D.1.2 or, D.2.1 and D.2.2, or, Required Action D.3 which requires placing the unit in Mode 3. Either of the paired required actions (D.1.1/D.1.2 or D.2.1/D.2.2) permit continued operation with the inoperable channel as long as both required actions in the pair are met.

Required Actions D.1.1 and D.1.2 Changes With one power range neutron flux - high channel inoperable, Required Action D.1.1 allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place the inoperable channel in trip. In addition to placing the inoperable channel in

• the tripped condition, thermal power must be reduced to s 75 percent(%) rated thermal power (RTP) within 78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br /> per Required Action D.1.2.

In the time period between when the channel is known to be inoperable and before thermal power is reduced to s 75% RTP, current TSs would also require performance of SR 3.2.4.2 after 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and per the surveillance frequency control program thereafter. Performing SR 3.2.4.2 confirms that the normalized symmetric power distribution is consistent with QPTR. Upon

. meeting the requirements of Required Action D.1.2, the requirements of SR 3.2.4.2 are no longer required to be performed because reducing the power level to s 75% RTP (Required Action D.1.2) prevents operation of the core with radial power distributions beyond the design limits even though with one NIS power range detector inoperable, 1/4 of the radial power distribution monitoring capability is lost.

The NRC staff reviewed the proposed D.1.1 and D.1.2 changes. The requirement to place the inoperable NIS channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is retained as new Required Action D.1: This results in a partial trip condition requiring only one-out-of-three logic for actuation of the reactor protection system. Deleting Required Action D.1.2 eliminates the requirement to reduce THERMAL POWER to s 75% RTP. Reducing thermal power to s 75% RTP is an unnecessary complication based on the proposed revision to SR 3.2.4.2 since the new surveillance note requires performing SR 3.2.4.2 when the NIS channel input to QTPR is inoperable. Performing SR 3.2.4.2 at the specified once within 12-hour frequency and thereafter in accordance with the surveillance frequency control program will be an accurate alternative means for ensuring that any core power tilt remains within core operating limits, thus adequate protection will be assured.

The NRC staff finds these changes acceptable because the partial trip condition requirement is retained, thus ensuring the core is protected against a positive reactivity excursion leading to departure from nucleate boiling during power operations, and the SR 3.2.4.2 Note changes (discussed below) to perform SR 3.2.4.2 only when power range neutron flux - high channel QPTR inputs are inoperable above 75% RTP ensure the core power distributions will not exceed design limits.

The NRC staff finds deleting Required Action D.1.2 acceptable because the requirements that remain are equivalent to the STSs, do not result in any substantive change in operating requirements, and are consistent with the Commission's regul~tions. These changes will provide for a consistent application of the TS actions and required tests.

Required Actions D.2.1 and D.2.2 Changes With one power range neutron flux - high channel inoperable, Required Action D.2.1 allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to place the inoperable channel in trip. In addition to placing the inoperable channel in the tripped condition, Required Action D.2.2 provides the appropriate action for the condition when the NIS channel input to QPTR is also inoperable (at any power level) by requiring performance of SR 3.2.4.2 once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The NRC staff reviewed the proposed D.2.1 and D.2.2 changes. D.2.1 is deleted, but the requirement to place the inoperable NIS channel in trip within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is retained as new Required Action D.1. This would result in a partial trip condition. requiring only one-out-of-three logic for actuation. D.2.2 is deleted. Retaining this requirement would essentially duplicate equivalent flux mapping requirements that are included with SR 3.2.4.2 when the NIS channel QPTR inputs are inoperable above 75% RTP. Flux mapping requirements do not apply at or below 75% RTP when the NIS channel QPTR inputs are inoperable. The licensee stated that the existing layout of LCO 3.3.1, Condition D, could incorrectly lead an operator to believe that only the options of D.1.1 and D.1.2 could apply, potentially overlooking the requirement to do a flux map for QPTR within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

The NRC staff finds that replacing D.2.1 with D.1 and deleting Required Action D.2.2 are acceptable because the requirements that remain are equivalent to the STSs, do not result in any substantive changes in operating requirements, and are consistent with the Commission's regulations. These changes will provide for a consistent application of the TS actions and required tests.

Addition of Note 2 to Required Action D Required Action D is revised by inserting a note directing operators to refer to LCO 3.2.4 upon discovery of an inoperable power range channel.

The reference to LCO 3.2.4 replaces the need to specify performing SR 3.2.4.2 requirements in Required Action D.2.2 when the NIS input to QPTR is inoperable. This is acceptable because

• D.2.2 restates the requirements of SR 3.2.4.2 to calculate QPTR every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as compensation for lost monitoring capability due to an inoperable NIS channel input to QPTR for thermal power>.

• 75% RTP. This proposed change will help eliminate potential confusion regarding the completion time to perform SR 3.2.4.2.

The NRC staff reviewed all of the administrative changes proposed by Southern Nuclear to eliminate the potential confusion regarding duplicating the requirement to perform SR 3.2.4.2 and finds them acceptable because they are equivalent to the STSs, do not result in any substantive changes in operating requirements, and are consistent with the Commission's regulations. These changes will provide for a consistent application of the TS actions and required tests.

.., 6 -

3.2 SR 3.2.4.2 Changes The existing note to SR 3.2.4.2 limits performing this SR 'to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after input from one or more power range neutron flux channels are inoperable with THERMAL POWER> 75% RTP. The note is clarified in two ways.

The time period of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is relocated from the note to the frequency column as once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Adding the words "once within" before the time limit will ensure that initial occurrence of the appropriate actions are taken "within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />" rather than "12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after" therefore making the change more conservative than the current SR 3.2.4.2 and having the change match the frequency requirements originally located in TS LCO 3.3.1, Required Action D.2.2.

Additionally, the language is changed to require performance only if the input to QPTR from one or more power range neutron flux - channels is inoperable with THERMAL POWER > 75% RTP.

If the inoperable power range channels remain capable of providing a valid input to QPTR, there is no need to perform SR 3.2.4.2.

The NRC staff reviewed the modified portions of the note and the relocation of the time component of the note to the frequency column as proposed by Southern Nuclear and finds the changes acceptable because they are compatible with the STSs, do not result in any substantive change in operating requirements, and are consistent with the Commission's regulations. These changes will help eliminate potential confusion and provide for a consistent application of the TS remedial actions and required tests.

3.3 Changes to Bases Pages The licensee included in its application the revised TS Bases pages to be implemented with the TS change. The NRC staff finds that the TS Bases Control Program is the appropriate process for updating the affected TS Bases pages, and has, therefore, not included the revised Bases pages with these amendments.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change requirements 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 (79 FR 42551, July 22, 2014). Accordingly, the 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 the amendments.

6.0 CONCLUSION

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

Principal Contributors:

Peter Snyder, NRR/DSS/STSB Date: April 8, 2015

Mr. C. R. Pierce Regulatory Affairs Director April 8, 2015 Southern Nuclear Operating Company, Inc.

P. 0. Box 1295 I Bin - 038 Birmingham, AL 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2, ISSUANCE OF AMENDMENT TO REVISE REACTOR TRIP SYSTEM INSTRUMENTATION TECHNICAL SPECIFICATIONS (TAC NOS. MF4214 AND MF4215)

Dear Mr. Pierce:

The Nuclear Regulatory Commission has issued the enclosed Amendment No.197 to Renewed Facility Operating License No. NPF-2 and Amendment No.193 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2, respectively. The amendments consists of changes to the Technical Specifications (TSs) in response to your application dated June 3, 2014.

The amendments revise the TS Limiting Condition for Operation 3.3.1 and Surveillance Requirement 3.2.4.2 in order to avoid confusion as to when a flux map for quadrant power tilt ratio monitoring is required.

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 !".-Jos. 50-348 and 50-364

Enclosures:

1. Amendment No. 197 to NPF-2

2. Amendment No. 193 to NPF-8

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

PUBLIC LPL2-1 R/F RidsAcrs AcnwMailCTR Resource RidsRgn2MailCenter Resource RidsNrrDssStsb Resource Sincerely,

/RA/

Shawn A. Williams, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrLASFigueroa Resource RidsNrrDorlDpr Resource RidsNrrPMFarley Resource PSnyder, NRR ADAMS A N

ML15028A165 ccess1on o.:

• B d t d 03/04/15

y memo a e OFFICE LPL2-1/PM LPL2-1/LA DSS/STSB/BC NAME SWilliams SFigueroa RElliott*

DATE 03/11/15 03/10/15 03/04/15 OFFICE OGCINLO LPL2-1/BC LPL2-1/PM NAME BMizuno RPascarelli SWilliams DATE 03/24/15 04/08/15 04/08/15 OFFICIAL RECORD COPY