ML15056A772

Issuance of Amendments Regarding

ML15056A772
Person / Time
Site:	Quad Cities
Issue date:	03/30/2015
From:	Mozafari B Plant Licensing Branch III
To:	Bryan Hanson Exelon Generation Co
Brenda Mozafari, NRR/DORL 415-2020
References
TAC MF4589, TAC MF4590
Download: ML15056A772 (18)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001

~crrch 3J, 2015 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)

Exelon Generation Company, LLC 4300 Winfield Road Rorhers Warrenville, IL 60555

SUBJECT:

QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2-ISSUANCE OF AMENDMENTS REGARDING (TAC NOS. MF4589 AND MF4590).

Dear Mr. Hanson:

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 256 to Renewed Facility Operating License No. DPR-29 and Amendment No. 251 to Renewed Facility Operating License No. DPR-30 for Quad Cities Nuclear Power Station, Units 1 and 2 (the licensee). The amendments are in response to your application dated June 10, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13161A315). The changes revise the technical specifications and surveillance requirements 3.8.4.2 and 3.8.4.5 to add new acceptance criteria for total battery connection resistance.

In response to the NRC staff's request for additional information, the licensee provided supplemental information in letters dated October 24, 2013, March 5, 2014, and February 4, 2015 (ADAMS Accession Nos. ML13297A266, ML14064A527, and ML15035A266, respectively).

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

Docket Nos. 50-254 and 50-265

Enclosures:

1. Amendment No. 256 to DPR-29

2. Amendment No. 251 to DPR-30

3. Safety Evaluation cc w/encls: Distribution via Listserv Brenda L. Mozafari, Senior Project Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 256 Renewed License No. DPR-29

1.

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

A.

The application for amendment by the Exelon Generation Company, LLC (the licensee) dated June 10, 2013, as supplemented by letter(s) October 24, 2013, March 5, 2014, and February 4, 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, 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. DPR-29 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 256, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULA TORY COMMISSION

~

/. ~-

c/~ ~~

Attachment:

Changes to the Technical Travis L. Tate, Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Specifications and Renewed Facility Operating License Date of Issuance: ~

.J), 2015

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 251 Renewed License No. DPR-30

1.

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

A.

The application for amendment by the Exelon Generation Company, LLC (the licensee) dated June 10, 2013, as supplemented by letter(s) October 24, 2013, March 5, 2014, and February 4, 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, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.8. of Renewed Facility Operating License No. DPR-30 is hereby amended to read as follows:

B.

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 251, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

Attachment:

Changes to the Technical FOR THE NUCLEAR REGULATORY COMMISSION

~d~

Travis L. Tate, Chief Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Specifications and Renewed Facility Operating License Date of Issuance: M3rch.30, 2015

ATTACHMENT TO LICENSE AMENDMENT NOS. 256 AND 251 RENEWED FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Replace the following pages of the Renewed Facility Operating License and Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

Remove License DRP-29 Page 4 License DPR-30 Page 4 TSs Page 3.8.4-4 Page 3.8.4-5 License DPR-29 Page 4 License DPR-30 Page 4 TSs Page 3.8.4-4 Page 3.8.4-5 B.

Technical Specifications The Technical Specifications contained in Appendix A. as revised through Amendment No. 256 are hereby incorporated into this Renewed Operating I

License. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.

D.

Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.

E.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.59 ad 10 CFR 50.54(p). The combined sets of plans1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 249.

F.

The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan Renewed License No. DPR-29 Amendment No. 256 B.

Technical Specifications The Technical Specifications contained in Appendix A. as revised through Amendment No. 251 are hereby incorporated into this Renewed Operating I

License. The licensee shall operate the facility in accordance with the Technical Specifications.

C.

The licensee shall maintain the commitments made in response to the March 14, 1983, NUREG-0737 Order, subject to the following provision:

The licensee may make changes to commitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59. Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.

D.

Equalizer Valve Restriction Three of the four valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation with one bypass valve open to allow for thermal expansion of water.

E.

The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822), and the authority of 10 CFR 50.59 ad 10 CFR 50.54(p). The combined sets of plans 1, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Quad Cities Nuclear Power Station Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 2," submitted by letter dated May 17, 2006.

Exelon Generation Company shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Exelon Generation Company CSP was approved by License Amendment No. 244.

F.

The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Safety Evaluation Reports 1 The Training and Qualification Plan and Safeguards Contingency Plan are Appendices to the Security Plan Renewed License No. DPR-30 Amendment No. 251

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 SR 3.8.4.4 SURVEILLANCE Verify battery terminal voltage on float charge is:

a.

~ 260.4 voe for each 250 voe subsystem; and

b.

~ 125.9 voe for each 125 voe subsystem.

Verify no visible corrosion at battery terminals and connectors.

Verify battery connection resistance is

~ l.5E-4 ohm for inter-cell connections and

~ l.5E-4 ohm for terminal connections.

Verify total battery connection resistance is:

a.

~ 6.0E-3 ohm for each 250 voe subsystem, and

b.

~ 2.4E-3 ohm for each 125 voe subsystem.

Verify battery cells, cell plates, and racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.

Remove visible corrosion and verify battery cell to cell and terminal connections are coated with anti-corrosion material.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Survei 11 ance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Quad Cities 1 and 2 3.8.4-4 Amendment No(s7.

256/251

DC Sources-Operating 3.8.4 SURVEILLANCE REQUIREMENTS SR 3.8.4.5 SR 3.8.4.6 SR 3.8.4.7 SURVEILLANCE Verify battery connection resistance is

~ l.5E-4 ohm for inter-cell connections and

~ l.5E-4 ohm for terminal connections.

Verify total battery connection resistance i s :

a.

~ 6.0E-3 ohm for each 250 VDC subsystem, and

b.

~ 2.4E-3 ohm for each 125 VDC subsystem.

Verify each required battery charger supplies:

a.

~ 250 amps at ~ 250 VDC for ~ 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the 250 VDC subsystems; and

b.

~ 200 amps at ~ 125 VDC for ~ 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the 125 VDC subsystems.

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

The modified performance discharge test in SR 3.8.4.8 may be performed in lieu of the service test in SR 3.8.4.7 provided the modified performance discharge test completely envelopes the service test.

Verify battery capacity is adequate to supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)

Quad Cities 1 and 2 3.8.4-5 Amendment No(s).

256/251

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 256 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-29 AND AMENDMENT NO. 251 AND TO RENEWED FACILITY OPERATING LICENSE NO. DPR-30 EXELON GENERATION COMPANY, LLC AND MIDAMERICAN ENERGY COMPANY QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265

1.0 INTRODUCTION

By application dated June 10, 2013, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML13161A315), Exelon Generation Company, LLC (the licensee) requested an amendment to Renewed Facility Operating License Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station (QCNPS). Units 1 and 2, respectively. The proposed changes would revise QCNPS Technical Specification (TS) Surveillance Requirements (SRs) 3.8.4.2 and 3.8.4.5 by adding a requirement to verify the safety-related batteries' total battery connection resistances are within pre-estabiished limits to ensure their intended design functions are met.

In response to the U.S. Nuclear Regulatory Commission (NRC, the Commission) staff's requests for additional information, the licensee provided supplemental information in letters dated October 24, 2013, March 5, 2014. and February 4, 2015 (ADAMS Accession Nos. ML13297A266, ML14064A527, and ML15035A266, respectively).

2.0 REGULATORY REQUIREMENT~

The following NRC requirements and guidance docurnents are applicable to the NRC staff's review of the license amendment request {LAR).

Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix A. General Design Criterion (GDC) 17, "Generai Design Criteria for Nuclear Power Plants," requires, in part, that nuclear power plants have onsite and offsite electric power systems to permit the functioning of structures, systems, and components that are important to safety. The onsite system is required to have sufficient independence, redundancy, and testability to perform its safety function, assuming a single failure.

10 eFR 50, Appendix A, GDe-18, "Inspection and testing of electric power systems," requires that electric power systems that are important to safety must be designed to permit appropriate periodic inspection and testing.

10 eFR 50.36(c)(3), "Technical Specifications," requires that TSs include SRs, which are 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.

Background

As stated in Section 8.3.2 of the aeNPS Updated Final Safety Analysis Report (UFSAR), the safety-related direct current (de) electrical power systems include the 125 volt de (VDe) and 250 voe systems that provide a source of power for certain vital loads and control power. The de electrical power system is designed to have sufficient independence, redundancy, and testability to perform its design function, assuming a single failure.

The 250 voe system provides motive power to large de loads such as de motor-driven pumps and valves. Each aeNPS unit includes a 250 voe source consisting of a 250 voe battery, and an associated 250 voe full capacity battery charger. An additional 250 voe full capacity charger is available for use between the units. Each 250 voe battery and charger supplies power to both QeNPS, Units 1 and 2, loads. The minimum required battery terminal voltage for the 250 voe batteries is 210.

The 125 voe system provides control power to selected safety-related equipment, certain 4160 volt alternating current (VAe) and 480 VAe circuit breakers, and certain control relays and alarm annunciators. Each QeNPS unit includes a 125 voe source consisting of two 125 voe batteries (one normal and one alternate) and two 125 voe full capacity chargers (one normal and one backup). Both QeNPS' units 125 voe battery systems (i.e., 125 voe battery and associated charger) supply power to the associated QeNPS unit Division 1 125 voe electrical power distribution subsystem and the opposite aeNPS unit Division 2 125 voe electrical power distribution subsystem. The alternate 125 voe battery can be used when the normal 125 voe battery is out-of-service for maintenance. The minimum required battery terminal voltage for the 125 voe batteries is 105.

Normally, the 250 and 125 voe battery chargers carry the de loads, while maintaining their associated battery's terminal voltage. In the event of a loss of alternating current (ac) power to the battery charger, the de loads are automatically powered from their associated battery. Each battery has adequate storage capacity to supply the required normal loads plus the safe shutdown loads on one unit and the loads required to limit the consequences of a design basis event on the other unit for a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

aeNPS's SRs 3.8.4.2 and 3.8.4.5 establish the requirement to perform visual inspections and resistance measurements to detect localized battery connection degradation. Visual inspection to detect corrosion of the battery terminals and connections (SR 3.8.4.2) or measurement of the resistance of each battery inter-cell and terminal connection (SRs 3.8.4.2 and 3.8.4.5) provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance if left uncorrected.

The current SR 3.8.4.2 states:

Verify no visible corrosion at battery terminals and connectors Verify battery connection resistance is

~ 1.5E-4 ohm for inter-cell connections and

~ 1.5E-4 ohm for terminal connections The current SR 3.8.4.5 states:

Verify battery connection resistance is

~ 1.5E-4 ohm for inter-cell connections and

~ 1.5E-4 ohm for terminal connections The frequencies for SRs 3.8.4.2 and 3.8.4.5 are "In accordance with the Surveillance Frequency Control Program."

In the NRC Component Design Bases Inspection report dated November 28, 2006 (ADAMS Accession No. ML063330597), the NRC identified a noncited violation (NCV) for the licensee's failure to verify that the 125 VDC safety-related batteries would remain operable if all the inter-cell and terminal connections were at the maximum resistance value (i.e., 150E-6 ohm) allowed by TS SRs 3.8.4.2 and 3.8.4.5. In response to the NCV, the licensee initiated administrative controls as a short-term corrective action to ensure the safety-related batteries continue to be capable of performing their safety function in the interim until a license amendment correcting the non-conservative TS is approved.

To resolve the nonconservative TS, the licensee previously submitted an LAR dated December 21, 2007 (ADAMS Accession No. ML073580004), to propose an additional SR acceptance criterion for total battery connector resistance, which would be maintained in the TS Bases, such that future changes would be evaluated in accordance with 1 O CFR 50.59, "Changes, tests, and experiments." However, the licensee withdrew the LAR in letter dated June 25, 2009 (ADAMS Accession No. ML091770381) following numerous interactions with the NRC regarding whether maintaining the total battery connector resistance limits in the TS Bases met the requirements of 1 O CFR 50.36, "Technical specifications."

3.0 TECHNICAL EVALUATION

The licensee resubmitted this LAR to propose changes to correct the non-conservative TS. The proposed changes would add a new requirement to the TS to verify total battery connection resistances of the 125 voe and 250 voe safety-related batteries are within pre-established limits. This new requirement would be included within the TS SRs 3.8.4.2 and 3.8.4.5 and would be performed at the current frequencies of the SRs. The current requirement for individual battery inter-cell and terminal connections resistance (i.e., less than 150E-6 ohm) would remain in the SRs.

The revised SR 3.8.4.2 would state:

Verify no visible corrosion at battery terminals and connectors OR Verify battery connection resistance is

1.5E-4 ohm for inter-cell connections and

1.5E-4 ohm for terminal connections AND Verify total battery connection resistance is

a.

6.0E-3 ohm for each 250 VDC subsystem, and

b.

2.4E-3 ohm for each 125 VDC subsystem.

The revised SR 3.8.4.5 would state:

Verify battery connection resistance is

1.5E-4 ohm for inter-cell connections and

1.5E-4 ohm for terminal connections Verify total battery connection resistance is

a.

6.0E-3 ohm for each 250 VDC subsystem, and

b.

2.4E-3 ohm for each 125 VDC subsystem.

The frequencies for revised SR 3.8.4.2 and SR 3.8.4.5 would remain "In accordance with the Surveillance Frequency Control Program."

As stated in the LAR, the safety-related batteries at QCNPS are formed by strings of battery cells. All batteries utilize GNB NCN-21 cells. Each 125 VDC battery has 58 cells and each 250 VDC battery has 120 cells. The strings are comprised of a series connection of the positive and negative terminal posts of adjacent cells. The inter-cell and terminal connectors between the cells contribute to the total battery connection resistance, which reduces the overall battery terminal voltage. During normal operation of the battery, corrosion can occur on the battery posts, which can also increase the inter-cell and terminal connection resistance and further reduce battery terminal voltage. If the battery is not properly maintained, this condition could eventually reduce the affected battery's terminal voltage to a point where the minimum required voltages (i.e., 105 voe for the 125 voe battery and 210 voe for the 250 voe battery) cannot be met.

In Attachment 4 of the LAR, the licensee provided Calculation QDC-8300-E-1587, "Determination of Battery lntercell Connector Resistance Limits," Revision 2, which includes the determination of the proposed total battery connection resistance limiting values. The first calculated a total allowable connection resistance for each 125 VDC and 250 VDC battery, then selected the proposed total connectior:i resistance limiting values (i.e., 2.4E-3 ohm for each 125 VDC battery and 6.0E-3 ohm for each 250 VDC battery) below the total allowable connection resistances. The proposed total connection resistance limits do not include the resistances of the inter-tier and inter-rack jumper cables.

The NRC staff reviewed the proposed changes and requested the licensee to clarify the intent of leaving the 150E-6 ohm limit for individual inter-cell and terminal connection resistance in the TS. In its response letter dated October 24, 2013, the licensee stated that the resistance value of 150E-6 ohm was initially established to provide a threshold for identifying localized degradation so that issues potentially affecting battery performance are promptly identified and corrected. The 150E-6 ohm limit will continue to provide that function in the TS. The NRC staff finds the licensee's response acceptable.

The existing SRs 3.8.4.2 and 3.8.4.5 include acceptance criteria for battery inter-cell and terminal connections resistances. The NRC staff requested the licensee to clarify whether the same acceptance criteria are applicable to the battery inter-tier and inter-rack connections. In its response letter dated October 24, 2013, the licensee clarified that the terminal connections refer to the connections between a cable lug and the battery post, whether it is for the inter-tier and inter-rack jumper cables, or the cable terminations that connect the battery terminals to the external DC system. Thus, the acceptance criteria are applicable to all these connections. The NRC staff finds the licensee's response acceptable.

The NRC staff requested an explanation from the licensee to explain how the field measured battery resistance values will be evaluated for compliance with the proposed TS total battery connection resistance limits. In its response letter dated October 24, 2013, the licensee stated that QCNPS procedures for SRs 3.8.4.2 and 3.8.4.5 will be updated to include a means of recording and totaling connection resistances for each safety related battery. The total recorded connection resistances will be compared to the proposed TS limits for total connection resistance. Based on the discussion above regarding battery resistance limits, the NRC staff finds the licensee's response to be acceptable.

The NRC staff requested the licensee to validate that the batteries' required minimum terminal voltages will be maintained when the resistances of the inter-tier and inter-rack jumper cables are added to the proposed total connection resistances. In its response letter dated February 4, 2015, the licensee provided alternate calculations to demonstrate that the proposed total connection resistance limiting values will maintain the required minimum battery terminal voltages under worst-case design basis loading conditions.

For QCNPS, Units 1 and 2, 125 VDC subsystems, the licensee performed the calculation using the parameters of the Unit 2 125 VDC normal battery because it is the most limiting battery (highest load current, lowest voltage margin, longest jumper cables lengths). The lowest recorded voltage during the latest discharge test for the Unit 2 125 VDC normal battery is 108.1 VDC using a maximum current of 678 amps. For the total battery connection resistance of 2.4E-3 ohm and a cable length of 162 E-6 ohm, the voltage drop across the connections and cables would be 1. 73 VDC (678 amps*(2.4E-3 ohm + 0.162E-3 ohm)). The battery terminal voltage would be approximately 106.3 VDC (180.1 VDC-1.73 VDC), which is greaterthan the required minimum battery terminal voltage of 105. The licensee stated that the resistance for maintaining the required minimum battery terminal voltage for the Unit 2 125 VDC normal normal battery is 2. 713E-3 ohm. Thus, there is an available margin of 11.5 percent in the proposed total connection resistance of 2.4E-3 ohm. The NRC staff finds that the 125 voe batteries will have adequate voltage to supply the loads under worst-case design basis conditions if the battery total connection resistance reaches 2.4E-3 ohm. Therefore, the NRC staff finds that the proposed total connection resistance for the QCNPS, Units 1 and 2, 250 VOC batteries are acceptable.

For QCNPS, Units 1 and 2, 250 VOC subsystems, the licensee used the parameters of the Unit 2 250 VOC battery in the calculation because it is most limiting (highest load current and longest jumper cables lengths). The lowest recorded voltage during the latest discharge test for the Unit 2 250 voe normal battery is 222.0 voe with a maximum current of 784 amps. For the total battery connection resistance of 6.0E-3 ohm and a cable length of 395E-6 ohm, the voltage drop across the connections and cables would be 5.0 VOC(784 amps* (6.0E-3 ohm +0.395E-3 ohm)). The battery terminal voltage would be approximately 217 VOC (222 VOC - 5VOC), which is greater than the required minimum battery terminal voltage of 205 voe.

The licensee stated that the resistance for maintaining the required minimum battery terminal voltage for the Unit 2 250 VOC battery is 11,557E-6 ohm. Thus, there is a margin of 48 percent available in the proposed total connection resistance of 6.0E-3 ohm. The NRC staff finds that the 250 VOC batteries will have adequate voltage to supply the loads under worst-case design basis conditions if the battery total connection resistance reaches 6.0E-3 ohm. Therefore, the NRC staff finds the proposed total connection resistance for the QCNPS, Units 1 and 2, 250 voe batteries are acceptable.

In summary, the NRC staff finds that verifying the total battery connection resistance ensures that the safety-related batteries will be able to maintain required minimum terminal voltages in order to perform their design safety functions. In addition, the proposed connection resistance values include sufficient margins to allow the batteries to remain operable. Based on the discussion above, the NRC staff finds that the proposed TS changes satisfy the requirements in 10 CFR 50.36 because the safety-related batteries can perform their design safety functions.

4.0 CONCLUSION

The NRC staff reviewed the licensee's proposed changes to the TS SRs 3.8.4.2 and 3.8.4.5.

The proposed changes would modify SRs 3.8.4.2 and 3.8.4.5 by adding new acceptance criteria for total battery connection resistance to ensure that QCNPS safety-related batteries can perform their specified safety function.

Based on the above technical evaluation, the NRC staff concludes that the proposed TS changes provide reasonable assurance of the continued availability of the required electrical power to shut down the reactor and keep it in a safe condition following an anticipated operational occurrence or a postulated design basis accident. Furthermore, the NRC staff concludes that the proposed TS changes are in compliance with 10 CFR 50.36(c) and the licensee continues to meet the intent of GOCs 17 and 18. Therefore, based on the previous discussion, the NRC staff finds the proposed changes in the LAR are acceptable.

5.0 STATE CONSULTATION

The amendments make a change to SRs. 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 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 findings (78 FR 54283, dated September 3, 2013). Accordingly, the amendments met the eligibility criteria for categorical exclusion set forth in 10 CFR, Section 51.22(c)(9) and no environmental impact statement or environmental assessment need to 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 Contributor: R. Mathew A. Foli Date of issuance: M3rch 3J, 2015

ML13297A266, ML14064A527, and ML15035A266, respectively).

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/

Brenda L. Mozafari, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing

• Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265

Enclosures:

1. Amendment No. 256 to DPR-29

2. Amendment No. 251 to DPR-30

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

PUBLIC LPL3-2 R/F RidsNrrDorllp13-2 Resource RidsNrrDirsltsb Resource RidsNrrDorlDprResource RidsNrrPMQuadCities Resource RidsNrrLASRohrer Resource RidsRgn3MailCenter Resource RidsAcrsAcnw_MailCTR Resource RecordsAmend Resource Accession Number* ML15056A772 OFFICE LPL3-2/PM LPL3-2/LA DIRS/ITSB*

NRR/DE/EEEB*

NAME BMozafari SRohrer RElliott JZimmerman w/comments DATE 3/12/15 3/ 25 /15 3/ 25/15 2/ 3 /15