ML14231A634

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Issuance of Amendments Regarding Technical Specification 3.8.4, DC Sources-Operating,
ML14231A634
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 09/10/2014
From: Geoffrey Miller
Plant Licensing Branch II
To: Capps S
Duke Energy Carolinas
Miller G
References
TAC MF2983, TAC MF2984
Download: ML14231A634 (18)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2014 Mr. Steven D. Capps Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2- ISSUANCE OF

~MENDMENTS REGARDING TECHNICAL SPECIFIC~TION 3.8.4, "DC fOURCES-OPERATING" (TAC NOS. MF2983 AND M,2984)

Dear Mr. Capps:

By letter dated October 28, 2013\ as supplemented by letter dated June 3, 2014, 2 Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request to modify Technical Specification 3.8.4, "DC Sources-Operating." Specifically, the change provides a one-time extension to the completion time for Required Action A.2.2 to support replacement of the existing shared 125 VDC vital batteries.

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 274 to Renewed Facility Operating License NPF-9 and Amendment No. 254 to Renewed Facility Operating Licenses NPF-17 for the McGuire Nuclear Station, Units 1 and 2, respectively.

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

1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML133048445.

2 ADAMS Accession No. ML14164A028.

S. Capps If you have any questions, please call me at 301-415-2481.

Sincerely, ~ .

G. (£;:.,, Pr~j,:c~nager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosures:

c

1. Amendment No. 274 to NPF-9
2. Amendment No. 254 to NPF-17
3. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 27 4 Renewed License No. NPF-9

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

A. The application for amend merit to the McGuire Nuclear Station, Unit 1 (the facility),

Renewed Facility Operating License No. NPF-9, filed by Duke Energy Carolinas, LLC (the licensee), dated October 28, 2013, as supplemented by letter 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 as 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 set forth in 10 CFR Chapter I; 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 ali applicable requirements have been satisfied.

2. Accordingly, the license is hereby amended by page 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-9 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 274, 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 its date of issuance and shall be implemented within 30 days of issuance. Implementation of the amendment shall include updating the UFSAR in accordance with 10 CFR 50.71 (e). This update shall include a statement that the license shall implement the twelve compensatory measures enumerated in Section 3.6 of the licensees October 28, 2013, license amendment request.

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:

Changes to License No. NPF-9 and the Technical Specifications Date of Issuance: September 10, 2014

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 254 Renewed License No. NPF-17

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

A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility),

Renewed Facility Operating License No. NPF-17, filed by Duke Energy Carolinas, LLC (the licensee), dated October 28, 2013, as supplemented by letter 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 as 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 set forth in 10 CFR Chapter I; 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 hereby amended by page 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-17 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 254, 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 its date of issuance and shall be implemented within 30 days of issuance. Implementation of the amendment shall include updating the UFSAR in accordance with 10 CFR 50.71 (e). This update shall include a statement that the license shall implement the twelve compensatory measures enumerated in Section 3.6 of the licensees October 28, 2013, license amendment request.

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:

Changes to License No. NPF-17 and the Technical Specifications Date of Issuance: September 10, 2014

ATTACHMENT TO LICENSE AMENDMENT NO. 274 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 254 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Renewed Facility Operating Licenses and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove' Licenses Licenses NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 TSs TSs 3.8.4-1 3.8.4-1

(4) 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; *

(5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear Station, Units 1 and 2, and; (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.

C. This renewed operating 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 The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (100%). *

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No)2'74are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21(d), as revised on December 16,2002, describes certain future activities to be completed before the period of extended operation.

Duke shall complete these activities no later than June 12, 2021, 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 December 16, 2002, 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 operating license.

Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.

Renewed License_No. NPF-9

  • Amendment No:27 4

(4) 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; (5) Pursuant to the Act and 1o CFR Parts 30, 40 and 70, to possess, but not separate, such byproducts and special nuclear materials as may be produced by the operation of McGuire Nuclear 'Station, Units 1 and 2; and, (6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess and process for release or transfer such byproduct material as may be produced by the Duke Training and Technology Center.

C. This renewed operating 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 The licensee is authorized to operate the facility at a reactor core full steady state power level of 3469 megawatts thermal (1 00%).

(2) - Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No;,254are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Updated Final Safety Analysis Report The Updated Final Safety Analysis Report supplement submitted pursuant to 10 CFR 54.21 (d), as revised on December 16, 2002, describes certain, future activities to be completed before the period of extended operation.

Duke shall complete these activities no later than March 3, 2023, 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 December 16, 2002, described above, shall be included in the next scheduled update to the Updated Final Safety A'nalysis Report required by 10 CFR 50.71 (e)(4), following issuance of this renewed operating license.

Until that update is complete, Duke may make changes to the programs described in such supplement without prior Commission approval, provided that Duke evaluates each such change pursuant to the criteria set forth in 10 CFR 50.59, and otherwise complies with the requirements in that section. **

Renewed License No. NPF-17 Amendment No-254-

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources- Operating LCO 3.8.4 The four channels of DC sources shall be OPERABLE.

APPLICABILITY: i MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel of DC A.1 Restore channel of DC 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> source inoperable. source to OPERABLE status.

OR A.2.1 Verify associated bus tie 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> breakers are closed between DC channels.

AND I  : A.2.2 Restore channel of DC 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s*

source to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

  • The Completion' Time that one channel of DC source can be inoperable as specified by Required Action A.2.2 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" for up to 14 days as part of the battery replacement project. This allowance may be used one-time for each of the four DC channels. Upon completion of the battery replacement project, this footnote is no longer applicable and will expire on December 31, 2016.

McGuire Units 1 and 2 3.8.4-1 Amendment No.

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 274 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 254 TO RENEWED FACILITY OPERATING LICENSE NPF-17 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 1.0

  • INTRODUCTION By letter dated October 28, 2013, as supplemented by letter dated June 3, 2014, Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request (LAR) to modify Technical Specification (TS) 3.8.4, "DC Sources-Operating." Specifically, the change would provide a one-time extension to the completion time for Required Action A.2.2 to support replacement of the existing shared 125 VDC vital batteries. The supplement clarified the application, did not expand the scope, and did not change the NRC staff's original proposed no

. significant hazards consideration determination as published in the Federal Register on January 21, 2014 (79 FR 3415).

2.0 REGULATORY EVALUATION

10 CFR 50.36(c)(2)(i) states, in part, that limiting conditions for operation (LCOs) are the lowest

  • functional capability or performance levels of equipment required for safe operation of the facility.

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. Typically, the remedial actions are to return the plant to compliance with the LCO in an appropriate time-frame.

NUREG-0800, Branch Technical Position (BTP) 8-8, "Onsite Emergency Diesel Generators (EDGs) and Offsite Power Sources Allowed Outage Time Extensions," provides guidance to the NRC staff in reviewing LARs proposing to extend the allowed outage time for onsite and offsite

  • power sources beyond 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.0 TECHNICAL EVALUATION

3.1 Description of the Electrical Power System Each nuclear unit generates power at 24 Kilo-Volts (kV) and supplies power from the generator to two independent unit step-up transformers that increase the voltage from 24 kV to 230 kV. The power from Unit 1 and Unit 2 is then transmitted via four separate and independent overhead transmission lines to common 230 kV and 525 kV switching stations. The normal power supply to the auxiliary power transformers is the 24 kV unit generator and the preferred power supply is the 230 kV and 525 kV switching stations. Each unit is provided with two auxiliary power transformers which are sized to carry all of the auxiliaries of one operating nuc,Jear unit and the safety shutdown

  • loads of the other nuclear unit. The 6900 Volt Normal Auxiliary Power System provides power to all of the large station auxiliary loads and the two redundant and independent 4160 Volt Essential Auxiliary Power Systems of each unit. Each of the 4160 Volt Essential Auxiliary Power Systems has a diesel-engine generator connected to it that will automatically start and supply power in the event that power supplied from the 6900 bus is not available. Together the two 4160 Essential Auxiliary Power Systems for each unit have sufficient independence, redundancy and testability to perform their safety functions assuming a single failure.

The On site DC Power Systems consist of one 250 VDC and two 125 VDC systems. The 125 VDC Vital Instrumentation and Control (I&C} Power System is provided to supply power to nuclear safety-related I&C loads requiring an uninterrupted power source to maintain safe reactor status.

The 125 VDC I&C power system consists of four independent and physically separate load channels with each serving both units. A load channel is comprised of a battery, charger connection box, battery charger, 125 VDC distribution center provided with undervoltage and ground detection equipment, and two 125 VDC power panelboards (one for each unit). Since the 125 VDC I&C power system is a safety-related system, each battery is separately housed in a ventilated room apart from its charger and distribution centers, and all related equipment is located in tt)e Auxiliary Building (Category 1 structure). Each vital battery bank consists of 60 GNB NCN-27 Flooded Lead Calcium (1945 Amp-Hr) battery cells, which were procured thro_ugh a third party qualifier, Nuclear Logistics, Inc. (NLI).

3.2 Proposed TS Change The 125 VDC vital batteries were last replaced in 1997 under a risk-informed one-time TS change.

All four battery channels are currently operable, but are nearing their 20 year nominal service life.

Battery replacement is currently scheduled for 2015 and 2016. Since battery replacement cannot be accomplished within the Completion Time (CT) currently allowed by TS 3.8.4 due to the number of activities, inspections, and tests, the licensee proposed a revision to the CT for Required Action A.2.2 of TS 3.8.4, "Restore channel of DC source to OPERABLE status," from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days on a one-time temporary basis. A footnote would be added to the TS page stating: * ,

"The Completion Time that one channel of DC source can be inoperable as specified by Required Action A.2.2 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" for up to a total of 14 days as part of the battery replacement project. This allowance may be used one-time for each of the four DC channels. Upon completion of the battery replacement project, this footnote is no longer applicable and will expire on December 31, 2016."

Battery replacement cannot be performed during a single unit refueling outage since the batteries are shared between the two units. Therefore the licensee's proposed LAR would allow replacement of the existing 125 VDC vital batteries while at power. During each vital battery replacement, the associated DC channel will remain energized by being cross-tied (bus tie with breakers) to another operable DC channel as allowed by TS 3.8.4 Condition A.2.1. The licensee also proposed a supplemental or an alternate power source consisting of a temporary battery as a backup DC power supply.

3.3 Compensatory Measures The licensee described the following compensatory measures that would be implemented to limit plant vulnerabilities during the battery replacement evolutions:

COMPENSATORY MEASURE 1a. During replacement of battery EVCA, the following systems and components will be protected and elective maintenance deferred:

  • Vital channels B, C, D
  • Unit 1 and 2 main step-up transformer yard
  • Unit 1 and 2 6.9kV switchgear room .
  • Component Cooling water trains (KC) 1B, 28
  • Unit 1 and 2 Turbine driven CA pumps
  • Diesei_Qowered Instrument Air _{VI) compressors G, H 2b. During replacement of battery EVCB, the following systems and components will be protected and elective maintenance deferred:
  • Vital channels A, C, D
  • Unit 1 and 2 main step-up transformer yard
  • Unit 1 and 2 6.9kV switctigear room
  • sss
  • KG trains KC 1A, 2A
  • RN trains RN 1A, 2A
  • Motor driven CA pumps 1A, 2A
  • . _Unit 1 and 2 Turbine driven CA pumps
    • . Diesel powered VI compressors G, H 3c. During replacement of battery EVCC, the following systems and components will be protected and elective maintenance deferred:
  • Vital channels A, B, D
  • Unit 1 and 2 main step-up transformer yard

o Unit 1 and 2 6.9kV switchgear room

  • sss o EDG 18,28
  • KC trains KC 1B, 28
  • RN trains RN 1B, 28
  • Motor driven CA pumps 1B, 28
  • Unit 1 and 2 Turbine driven CA pumps
  • Diesel powered VI compressors G, H 4d. During replacement of battery EVCD, the following systems and components will be protected and elective maintenance deferred:
  • Vital channels A, B, C
  • Unit 1 and 2 main step-up transformer yard
  • Unit 1 and 2 6.9kV switchgear room '*
  • sss
  • KC trains KC 1A, 2A
  • RN trains RN 1A, 2A
  • Motor driven CA pumps 1A, 2A
  • Unit 1 and 2 Turbine driven CA pumps
  • Diesel powered VI compressors G, H
2. A temporary battery located in the Service Building is available as a defense in depth measure. The temporary battery will be charged and has the necessary connections to tie-in to any of the four DC distribution centers, if necessary.
3. The ambient temperature and hydrogen concentration of the area containing the temporary battery will be monitored once per a 12-hour shift to ensure th~}'_ remain within battery specifications.
4. The ventilation in the area containing the temporary battery will be supplemented with fans to ensure good air flow and mixing across the temporar}'_ battery.
5. Appropriate training will be provided to Operational Sliift personnel, maintenance, and vendor technicians regarding the vital battery replacement evolution, emergency procedures, and temporary battery alignment. *
6. Alignment procedures for the temporary battery will be in place for Operations.
7. The manual connections to the temporary battery are designed to be accomplished by Operations within 60 minutes once it has been determined it can be done safely and this strategy is desired to support event recovery.
8. Pre-job briefings will be provided to Maintena~*ce and Vendor personnel
  • each shift during the vital battery replacement evolutions.
9. The temporary battery will receive a full complement of TS surveillances tests including a Modified Performance Test prior to the first vital battery re_Qiacement.
10. All applicable TS surveillance tests will be performed on the temporary battery configuration during periods of battery bank re_Qiacement.
11. Prior to the start of each TS Completion Time extension and daily thereafter, McGuire will monitor the NationaiWeather Service for potential severe weather conditions. To the extent practical, severe weather conditions will be avoided.
12. Prior to the start of each TS Completion Time extension and daily thereafter, McGuire will contact the Transmission Control Center (TCC) regarding system grid stability. To the extent practical, system grid instability will be avoided.

3.4 NRC Staff Review The licensee stated that the 125 VDC vital batteries are currently operable but are nearing their 20 year nominal service life, with industry operating experience indicating that 15 to 18 years is a much closer approximation. The licensee's recent tests have indicated that three of the four*

batteries have capacity over 100% while the fourth battery has capacity of 99%. The licensee stated that the new vital batteries, which are scheduled for 2015 and 2016 installation, are essentially the same, having the same size and material and will meet the current licensing basis and perform the same safety functions as the existing batteries. Therefore, this NRC staff evaluation does not address the appropriateness of the replacement batteries. Instead, this evaluation considers the appropriateness of the one-time extension to the completion time for the required action to restore operability when one channel is inoperable. The licensee should use their existing 10 CFR 50.59 evaluation process to determine if the plant modification itself needs prior regulatory approval.

The battery replacement process will include the individual disconnection and removal of each of the old batteries cells, the individual installation of each of the new batteries cells and the installation of all the new intercell connectors, intertier jumpers and cables. After the installation of each of the batteries they will be charged, voltage and resistance measurements will be taken and tested in accordance with IEEE Standard 450. The licensee provided a timetable with all the required steps for the battery replacement process and a determination that the process will take a maximum of approximately 14 days. The NRC staff considers this a reasonable time-frame for the described evolution.

In considering the appropriateness of the one-time extension, the NRC staff considered how the compensatory measures proposed by the licensee address the following four categories:

1. Ensuring that a plant transient is unlikely when the channel is inoperable;
2. Ensuring that redundant, installed, equipment is available if a transient occurs when .the channel is inoperable;
3. Providing additional resources to supplant the inoperable equipment if a transient occurs when the channel is inoperable; and
4. Ensuring that the additional resources don't adversely affect the plant Compensatory measures 11 and 12 describe the licensee's actions to verify that conditions external to the plant do not carry an increased risk of transient. The NRC staff considers licensee's verification of weather and grid conditions to be appropriate for ensuring that a plant transient is unlikely during the battery replacement.
  • Compensatory measures 1a, 1b, 1c, and 1d, describe the plant equipment that the licensee will consider "protected" and to which they will defer elective maintenance during the extended completion time. Tlie NRC staff considers that protection of the equipment described in each compensatory measure will reasonably ensure that redundant, installed, equipment is available to respond to a transient, if one occurs during the battery replacement.

Compensatory measures 2, 5, 6, 7, 8, 9, and 10 describe temporary equipment, activities, and procedures that the licensee will provide and implement during the extended completion time to supplant the inoperable battery. During the replacement of the vital batteries the licensee will have a temporary battery ready to be used in the event of the loss of the battery supporting the cross-tied channels. The temporary battery is identical to the new batteries and prior to the removal of the fourth battery it will be installed as one of the new vital batteries, while one of the old batteries will be set up as the temporary battery. The temporary battery will be connected to the DC side of a standby battery charger and it will remain electrically isolated from the Vital DC distribution centers. By letter dated May 12, 2014 (ADAMS Agencywide Documents Access and Management System Accession No. ML14127A462), the NRC staff requested additional*

information on the design and capability of the temporary battery charger. In its June 3, 2014, response, the licensee stated that the temporary charger is a commercial grade charger powered from a non-safety source and it's intended to maintain the temporary battery on a float charge.

The temporary charger will be isolated via a breaker or disconnect switch if the temporary battery is required. Per design the battery will be manually tied in and the operation can be accomplished within an hour. In its October 28, 2013, applic~tion, the licensee stated that all applicable TS surveillance tests will be pertormed on the temporary battery, prior to and during battery repiacement evolutions. The NRC staff considers the alternate means of providing DC power to the affected channel supportive of the one-time completion time extension for the battery replacement.

Compensatory measures 3 and 4 describe equipment, activities, and procedures that the licensee will provide and implement during the extended completion time to ensure that temporary equipment does not have an adverse impact on the plant.

The proposed temporary installation of the back-up battery/charger would introduce fire hazards in terms of potential hydrogen concentration and combustible loading increase in the affected areas. The licensee stated that an analysis of the temporary battery hydrogen production has validated that the existing ventilation in the affected area prevents hydrogen concentrations greater than 2%. In addition, ventilation in the area will be supplemented with fans to ensure good air flow and mixing across the temporary battery. The ambient terT)perature and hydrogen concentration in the area will also be monitored once per 12-hour shift to endure they remain within battery specifications.

The temporary equipment introduGes additional combustibles to the fire area (Room 700 of the Service Building). Any fire involving the temporary battery is not expected to impact the ,

  • permanent batteries, because the temporary battery area is separated from the permanent battery rooms by 3-hour rated barriers. The licensee also indicated a fire in the temporary battery ar~a will not impact other plant areas since the temporary battery area is separated from other plant areas by 3-hour rated barriers, and existing hatch door and fire stops would prevent a fire from spreading into the Auxiliary Building. Whenever the hatch door is opened, a security guard will be stationed there to close the hatch if necessary. Fire detection instrumentation is also

provided in the area, which annunciate to the Main Control Room. Therefore, there is a low likelihood that the temporary equipment wi'll adversely affect the plant during the battery replac'ement.

The NRC staff notes that the temporary TS change also will not impact McGuire's transition to 10 CFR50.48(c), National Fire Protection Standard NFPA 805, which is currently under separate NRC review. This is because the temporary TS change can be carried forward during transition as a previously approved fire protection program element per NFPA 805, Chapter 2.

Based on the above, the NRC staff concludes that the licensee has provided adequate compensatory measures and maintained defense-in-depth such that the proposed one-time extension of the completion time for Required Action A.2.2 is consistent with 10 CFR 50.36 and the guidance provided in BTP 8~8.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components 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, which was published in the

  • Federal Register on January 21, 2014 (79 FR 3415). 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: T. Dinh S. Basturescu E. Miller Date: September 10, 2014

ML14231A634 *Via e-mail OFFICE N RRILPL2-1 /PM NRR/LPL2-1/LA NRRIDRA/AFPB/BC DSS/STSB/BC NAME GEMiller SFigueroa AKiein* REIIiot DATE 08/22/14 08/20/14 04/04/14 08/25/14 OGC OFFICE NRR/DE/EEEB/BC NRR/LPL2-1/BC NRR/LPL2-1/PM

/NLO w/coments NAME JZimmerman Jlindell RPascarelli GEMiller DATE 08/22/14 09/08/14 09/10/14 09/10/14

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