ML102210354

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Issuance of Amendments 370, 372, 371, Regarding 230 Kilovolt Switchyard 125 Volts Direct Current Power Sources Testing
ML102210354
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 08/30/2010
From: Stang J
Plant Licensing Branch II
To: Baxter D
Duke Energy Carolinas
Stang J, NRR/DORL, 415-1345
References
TAC ME2216, TAC ME2217, TAC ME2218
Download: ML102210354 (20)


Text

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Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 SUB~IECT: OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, ISSUANCE OF AMENDMENTS REGARDING 230 KILOVOLT (kV) SWITCHYARD 125 VOLTS DIRECT CURRENT (Vdc) POWER SOURCES (BATTERIES) TESTING (TAC NOS. ME2216, ME2217, AND ME2218)

Dear Mr. Baxter:

The Nuclear Regulatory Commission has issued the enclosed Amendment l\Ios. 370, 372, and 371 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station, Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 31,2009, and as supplemented April 14, 2010.

These amendments revise the Technical Specifications to 8.lIow one of the two required 230 kV switchyard 125 Vdc power sources (batteries) to be inoperable for up to 10 days for the purpose of replacing an entire battery bank and performing the required testing.

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.

If you have any questions, please call me at 301-415-1345.

Sincerely, ~

~g, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of NUcle3r Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosures:

1. Amendment No. 370 to DPR-38
2. Amendment No. 372 to DPR-47
3. Amendment No. 371 to DPR-55
4. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 370 Renewed License No. DPR-38

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

A. The application for amendment to the OconE:I Nuclear Station, Unit 1 (the facility),

Renewed Facility Operating License No. DPR-38 filed by the Duke Energy Carolinas, LLC (the licensee), dated August :31,2009, and supplemented April 14, 2010, 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

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 3.B of Renewed Facility Operating License No. DPR-38 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 370 , are hereby incorporated in the 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.

FOR THE NUCLEAR REGULATORY COMMISSION Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-38 and the Technical Specifications Date of Issuance: August 30, 2010

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 372 Renewed License No. DPR-47

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

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

Renewed Facility Operating License No. DPR-47 filed by the Duke Energy Carolinas, LLC (the licensee), dated August 31,2009, and supplemented April 14, 2010, 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

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 3.B of Renewed Facility Operating License No. DPR-47 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 372 , are hereby incorporated in the 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.

FOR THE NUCLEAR REGULATORY COMMISSION 6'(~

Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-47 and the Technical Specifications Date of Issuance: August 30, 2010

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 371 Renewed License No. DPR-55

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

A. The application for amendment to the Oconee Nuclear Station, Unit 3 (the facility),

Renewed Facility Operating License No. DPR-55 filed by the Duke Energy Carolinas, LLC (the licensee), dated August 31, 2009, and supplemented April 14, 2010, 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 setforth 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.

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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 3.B of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 371 , are hereby incorporated in the 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.

FOR THE NUCLEAR REGULATORY COMMISSION

~{(,.......-----

Gloria Kulesa, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-55 and the Technical Specifications Date of Issuance: August 30, 2010

ATTACHMENT TO LICENSE AMENDMENT NO.370 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 372 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 371 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the 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 Pages Insert Pages Licenses Licenses License No. DPR-38, page 3 License No. DPR-38, page 3 License No. DPR-47, page 3 License No. DPR-47, page 3 License No. DPR-55, page 3 License No. DPR-55, page 3 3.8.3-3 3.8.3-3

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Part 70; 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:

A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal. .

B. Technical Specifications The Technical Srp~ifi,..~tions contained in Appendix A, as revised through Amendment No. 370 .. are hereby Incorporated in the license. The licensee shall operate the facility in dccordance with the Technical- Specifications.

C, This license is SUbject to the follow;ng antitrust conditions:

Applicant makes the commItments contained herein, recognizing that bUlk power supply arrangements between neighboring entities normally tend to serve the public interest. In addition, where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability. a reduction in the cost of electric power, and minimization of the enVironmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than.to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the .

transaction. Accordingly, applicant will enter into proposed bulk power transactions of th~ types hereinafter descnbedwhich, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in ~1 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1, As used herein:

(a) "Sulk Power" means electrIc power and any attendant energy.

supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) "Neighboring Entity" means a private or public corporation, a govemmental agency or authority, 8 municipality, a cooperative. or a lawful association of any of the foregoing owning or operating, Or Renewed License No. DPR-38 Amendment No. 370

-3 Part 70; is subject to all applicable provisions of the Act ana to the rules, regulations, and orde~

of the Commission now or hereafter In effect; and is stlbject to the additional cc:mdltions specified or in~orporated below:

A. Max.imum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal.

B. Technical Specifications The T""~hnica' Specifications contained in Appenpix A, as revised through Amendment No. 37~ are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein;. recognizing that bulk power supply arrangements between neighboring entities normally tend tl;) serve the pUblic interest. In addition, where there are net benefits to all participants. such.alTangements also serve the best Interests of each of the participants. Among the benefits 01 such transactions are increased electric system reliability, a reduction In the cost of electric power, and minimization 01 the environmental effects of the production and sale of electricity.

Any partiCUlar bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small'system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, hc:>wever, should not be controlling upon a decision with respect to the desirability 01 participatir:'lg in the transaction. Accordingly. applicant will'enter Into proposed bulk power transactions of the types hereinafter described which, on balance. provide net benefits to applicant.

There are net benefits in a transaction If applicant recovers the cost of the transaction (as defined in 1}1 (d) hereof) and there is no demonstrable net detrimentto applicant arising from that transaction.

,, As used herein:

(a) "Bulk Power" means electric power and any anendant energy. supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) -Neighboring Entity" means a private or public corporation. a governmental a

agency or authority, a municipality, a cooperative. or lawful association of any of the foregoing owning or operating. or Renewed License No. DPR-47 Amendment No, 372

-3 Part 70; 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:

A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 2568 megawatts thermal, B. Technical" SpecIfications The Technical Specifications contained in Appendix A, as revised through Amendment No. 371 ,are hereby incorporated in the license. The licensee shall operate* the faCIlity in accordance with the Technical Specifications.

C. This license is subject to the following antitrust conditions:

Applicant makes the commitments contained herein, recognizjngthat bulk power

. supply arrangements between neighboring ent/ties normally tend to serve the public interest. 1n addition, Where there are net benefits to all participants, such arrangements also serve the best interests of each of the participants. Among the benefits of such transactions are increased electric system reliability, a reductlon in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to one participant than to another. The benefits realized by a small system may be proportionately greater than those realized by a larger system. The relative benefits to be derived by the parties from a proposed transaction, however, should not be controlling upon a decision with respect to the desirability of participating in the transaction. Accordingly, Clpplicant will enter into proposed bulk power transactions of the types hereinafter described Which, on balance, provide net benefits to applicant. There are net benefits in a transaction if applicant recovers the cost of the transaction (as defined in '11 (d) hereof) and there is no demonstrable net detriment to applicant arising from that transaction.

1. As used herein:

(a) "Bulk Power" means electric power and any attendant energy, supplied or made available at transmission or sub-transmission voltage by one electric system to another.

(b) "Neighboring Entity" means a private or public corporation, a governmental agency or authority. a municipality, a cooperative, or a lawful association of any of the foregoing owning or operating, or Renewed License No. OPR*55 Amendment No. 371

DC Sources - Operating 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One 230 kV switchyard D.1 ---------NOTES-------

125 VDC power source 1. Not applicable for inoperable. up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to perform equalization charge after completion of a performance or service test.

2. Not applicable for up to 10 days to replace entire battery bank and perform required tests to restore operability.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Restore power source to OPERABLE status.

E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Associated Completion Time not met. AND E.2 Be in MODE 5. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> OCONEE UNITS 1, 2, & 3 3.8.3-3 Amendment Nos. 370,372,371

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 370 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 372 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AND AMENDMENT NO. 371 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 DOCKET NOS. 50-269. 50-270, AND 50-287

1.0 INTRODUCTION

By application dated August 31, 2009 (Agencywide Documents Access and Management System (ADAMS), Accession No. ML092450108), as supplemented by letter dated April 14, 2010 (ADAMS Accession No. ML101060513), Duke Energy Carolinas, LLC (Duke, the licensee),

requested changes to the Technical Specifications (TSs) for the Oconee Nuclear Station, Units 1, 2, and 3 (Oconee 1/2/3). The supplement dated April 14, 2010, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on March 9, 2010 (75 FR 10828).

The proposed changes would revise TS 3.8.3, "DC Sources - Operating," Required Action D.1 to allow one of the two required 230 kilovolt (kV) switchyard 125 volts direct current (Vdc) power sources (batteries) to be inoperable for up to 10 days for the purpose of replacing an entire battery bank and performing the required testing.

2.0 REGULATORY EVALUATION

The following NRC requirements and guidance documents are applicable to the NRC staff's review of the licensee's amendment request:

Title 10 of the Code of Federal Regulations (10 CFR), Appendix A of Part 50, General Design Criterion (GDC) 17, "Electric power systems," 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.

The offsite power system is required to be supplied by two physically independent circuits that are

-2 designed and located so as to minimize, to the extent practical, the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. In addition, this criterion requires provisions to minimize the probability of losing electric power from the remaining electric power supplies as a result of loss of power from the unit, the offsite transmission network, or the onsite power supplies.

Appendix A of 10 CFR Part 50, GOC 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.

Section 50.36, "Technical Specifications," requires a licensee's TSs to establish LCOs, which include allowed outage times for equipment that is required for safe operation of the facility.

Section 50.63, "Loss of All Alternating Current Power," requires that each light-water cooled nuclear power plant licensed to operate must be able to withstand for a specified duration and recover from a station blackout.

Section 50.65, "Requirements for monitoring the effectiveness of maintenance at nuclear power plants," requires that preventative maintenance activities must not reduce the overall availability of the systems, structures, or components.

3.0 TECHNICAL EVALUATION

The Oconee 1/2/3 current TSs allowed outage time for 125 Vdc power sources (batteries) (i.e.

inoperable) is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The eXisting batteries are approaching their end of life, and it will be necessary to replace them. The current TS completion time for restoring the batteries to an operable condition is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This amount of time is not enough to allow for extensive maintenance and a replacement of the batteries. The licensee has proposed a change to the TS by adding a note to Required Action 0.1 of TS 3.8.3 which makes Required Action 0.1 not applicable for 10 days to remove the existing battery; inspect, repair, or replace the battery rack; and install, charge, test, and recharge a new battery. At the end of the 10 day period if the 125 Vdc power source is not restored to operable status, the current 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TS completion time for restoring the power source to an operable status is applicable, Oconee 1/2/3 has two hydro units (Keowee) as its emergency backup power source instead of using emergency diesel generators. In addition, Oconee 1/2/3 has an additional backup offsite source provided by a dedicated circuit from the Lee combustion turbines via the 100 kilovolt (kV) transmission network. The Keowee hydro station's 2 units are rated at 87,500 kV each and generate power at 13.8 kV. Upon loss of offsite power via the Oconee 1/2/3230 kV switchyard, both of the Keowee hydro units can provide emergency power to any of the Oconee units through either the overhead Oconee 1/2/3 230 kV circuit or an underground circuit. Whenever the underground circuit from Keowee is unavailable for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, a dedicated circuit from one of two Lee combustion turbines is required by the TSs to be connected as an emergency power source.

Two separate 230 kV switchyard 125 Vdc batteries supply redundant distribution centers which provide power to all components necessary for performing the safety functions of the 230 kV switchyard and 125 Vdc systems. Each distribution center has an associated battery charger and

-3 there is a sWing charger which can be connected to either switchyard battery bank. A bus tie with normally open breakers is provided between the distribution centers for cross connecting in the event that a battery bank needs to be taken out of service.. The capacity of a single battery bank is sufficient to carry the loads of both distribution centers. The NRC staff reviewed the analysis of the battery load profile provided by the licensee in the April 14, 2010, supplement and confirmed that one battery bank has sufficient capacity to supply both trains for the required 60-minute mission time and that the condition of the existing batteries is adequate for that evolution. The redundant panel boards supply power to separate channels of the degraded grid protection system (DGP5) circuits, separate channels of other protective relaying circuits, and separate feeds for each 230 kV power circuit breakers closing and tripping coils. For each Keowee hydro unit, separate and independent direct current (dc) power systems are provided to assure a source of reliable continuous power for normal and emergency operation. These dc systems will not be affected during this battery replacement.

The licensee states that the proposed T5 change will allow replacement of a single battery bank and performance of the maintenance surveillance testing required to return the battery bank back to service. The NRC staff reviewed maintenance plan/schedule and the supporting operating experience, and confirmed that the planned 1O-day duration requested is reasonable to complete the task. In addition, plant operating experience of battery replacement was comparable in terms of duration to the 1O-day duration requested in the proposed T5 change.

The NRC staff requested a detailed description of the compensatory measures to be in place during the battery repair/replacement including more details about measures to be taken for the availability and protection of all offsite and onsite power sources and delivery paths to the plant safety systems during this maintenance/replacement evolution. The licensee plans to implement the following compensatory measures:

1. The switchyard batteries will be replaced one bank at a time. The health of the inservice battery will be evaluated prior to beginning the replacement. Once good health is established, the loads will be tied together on the remaining, inservice battery which is fully capable of powering all of the loads.
2. Verify the grid reliability for the duration of the evolution.
3. Verify that the transmission operator's Real Time Contingency Analysis Program is functioning
4. Ensure that work on the Lee circuit is restricted during the evolution and that it is protected.
5. Verify the underground path circuit from Keowee is available and protected.
6. Ensure the standby charger is aligned to the alternate power source from the inservice battery
7. Treat the 480 VAC power system as a protected train.

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8. No discretionary maintenance or testing will be performed in the standby shutdown facility, emergency feedwater system, and 230 kV relay house The NRC staff's finds these compensatory measures satisfactory to mitigate the risks associated with the repair and replacement of the batteries.

To replace each of the 2 battery banks one at a time, the licensee has proposed a TS change that allows TS 3.8.3 Required Action D.1 to be not applicable for up to 10 days to replace entire battery bank and perform required tests to restore operability. The NRC staff has reviewed the licensee's submittal and concluded that adequate basis for the extension of the completion time in the existing TS has been provided. Based on the above evaluation, the NRC staff has determined that Oconee 1/2/3 can be operated safely without undue risk to the health and safety of the public and there is reasonable assurance that adequate power sources will be available to mitigate credible events that might occur during the period of 11 days, therefore, the NRC staff concludes that the proposed TS change is acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the South 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 published in the Federal Register on March 9, 2010 (75 FR 10828). 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) 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: K. Miller Date: August 30, 2010

August 30, 2010 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 SUB..IECT: OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, ISSUANCE OF AMENDMENTS REGARDING 230 KILOVOLT (kV) SWITCHYARD 125 VOLTS DIRECT CURRENT (Vdc) POWER SOURCES (BATTERIES) TESTING (TAC NOS. ME2216, ME2217, AND ME2218)

Dear Mr. Baxter:

The Nuclear Regulatory Commission has issued the enclosed Amendment Nos. 370,372, and 371 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station, Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 31, 2009, and as supplemented April 14, 2010.

These amendments revise the Technical Specifications to allow one of the two required 230 kV switchyard 125 VDC power sources (batteries) to be inoperable for up to 10 days for the purpose of replacing an entire battery bank and performing the required testing.

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.

If you have any questions, please call me at 301-415-1345.

Sincerely, IRA!

John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287

Enclosures:

1. Amendment No. 370 to DPR-38
2. Amendment No. 372 to DPR-47
3. Amendment No. 371 to DPR-55
4. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

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