Text

Issuance of Amendments
	ML14195A355
Person / Time
Site:	Oconee
Issue date:	10/21/2014
From:	Shawn Williams; Plant Licensing Branch II
To:	Batson S; Duke Energy Carolinas
	Williams S
References
	TAC MF4373, TAC MF4374, TAC MF4375
	Download: ML14195A355 (36)
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UNITED STATES

~ ~ NUCLEAR REGULATORY COMMISSION

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Mr. Scott Batson Site Vice President Oconee Nuclear Station Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672-0752

SUBJECT:

OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3, ISSUANCE OF AMENDMENTS REGARDING ADMINISTRATIVE CHANGES (TAC NOS.

MF4373, MF4374, AND MF4375)

Dear Mr. Batson:

The U.S. Nuclear Regulatory Commission (Commission) has issued the enclosed Amendment Nos. 388, 390, and 389 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station (ONS), Units 1, 2, and 3, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated May 20, 2014.

These amendments are administrative in nature as they remove obsolete information in TSs that no longer pertains to ONS. -

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

If you have any questions, please contact Mr. Randy Hall at 301-415-4032.

Sincerely, Shawn Williams, 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. 388 to DPR-38

2. Amendment No. 390 to DPR-47

3. *Amendment No. 389 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. 388 Renewed License No. DPR-38

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

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

Renewed Facility Operating License No. DPR-38, filed by Duke Energy Carolinas, LLC (the licensee), dated May 20,2014, 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 be~n satisfied.

Enclosure 1

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. 388, 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 60 days of issuance.

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 Renewed Facility Operating License No. DPR-38 and the Technical Specifications Date of Issuance: October 21, 2014 .

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. 390 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 Duke Energy Carolinas, LLC (the licensee), dated May 20, 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.

Enclosure 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. 390, 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 60 day~ of issuance.

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 Renewed Facility Operating License No. DPR-47 and the Technical Specifications Date of Issuance: ex: tober 21, 2014

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. 389 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 Duke Energy Carolinas, LLC (the licensee), dated May 20, 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.

Enclosure 3

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 1 through Amendment No. 389, 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 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

'?L~**

Robert J. Pascarelli, 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: Cc tober 21, 2014

ATTACHMENT TO LICENSE AMENDMENT NO. 388 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND LICENSE AMENDMENT NO. 390 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND LICENSE AMENDMENT NO. 389 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 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 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 TSs Pages TSs Pages 3.3.1-1 3.3.1-1 3.3.1-4 3.3.1-4 3.3.1-5 3.3.1-5 3.3.1-6 3.3.1-6 3.3.3-1 3.3.3-1 3.3.3-2 3.3.3-2 3.3.5-1 3.3.5-1 3.3.5-3 3.3.5-3 3.3.7-2 3.3.7-2 3.3.27-1 3.3.27-1 3.6.5-4 3.6.5-4 3.6.5-5 3.6.5-5

3.7.7-1 3.7.7-1 3.7.7-2 3.7.7-2 3.7.7-3 (Information on new TS pg. 3. 7. 7-2) 3.7.8-1 3.7.8-1

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."388 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 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 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 (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 proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-38 Amendment No. 388

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. 390 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 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 i.ncreased 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 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 1f1 (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 proposing to own or operate, facilities for the generation and transmission of electricity which meets each of Renewed License No. DPR-47 Amendment No. 390

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. 389 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 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 de,cision with respect to the desirability of participating 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 (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 proposing to own or operate, facilities for the generation and transmission of electricity which rneets each of Renewed License No. DPR-55 Amendment No. 389

RPS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Protective System (RPS) Instrumentation LCO. 3.3.1 Three channels of RPS instrumentation. for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1~1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required channel A.1 Place channel in trip. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable.

B. Two or more required 8.1 Enter the Condition Immediately channels inoperable. referenced in Table 3.3.1-1 for the OR Function.

Required Action and associated Completion Time of Condition A not met.

(continued)

Amendment Nos. 388 390 &38~

OCONEE UNITS 1 2, & 3 I 3.3.1-1

RPS Instrumentation 3.3.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.4 Not Applicable Not Applicable SR 3.3.1.5 Manually verify the setpoints are correct. In accordance with the I Surveillance Frequency Control Program SR 3.3.1.6 Manually actuate the output channel In accordance with the interposing relays. Surveillance Frequency Control Program SR 3.3.1.7 --*------NOTE--------

Neutron detectors are excluded from CHANNEL CALl BRATION. ,_,

Perform CHANNEL CALIBRATION. In accordance with the Surveillance Frequency Control Program OCONEE UNITS 1, 2, & 3 3.3.1-4 Amendment Nos. 388 390 389

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 2)

Reactor Protective System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS ACTION B.1 REQUIREMENTS *VALUE

1. Nuclear Overpower

a. High Setpoint 1 ,2(8 ) c SR 3.3.1.1 ~ 105.5% RTP SR 3.3.1.2 SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7

b. Low Setpoint 2(b),3(b) D SR 3.3.1.1 ~ 5% RTP 4(b),5(b) SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7

2. RCS High Outlet Temperature 1,2 c SR 3.3.1.1 ~ 618°F SR 3.3.1.5 SR 3.3.1:6 SR 3.3.1.7

3. RCS High Pressure 1,2(8 ) c SR 3.3.1.1 ~ 2355 psig SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7

4. RCS Low Pressure 1,2(8 ) c SR 3.3.1.1 ;?. 1800 psig SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7

5. RCS Variable Low Pressure 1,2(8 ) c SR 3.3.1.1 As specified in the COLR SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7

6. Reactor Building High Pressure 1,2,3(t) c SR 3.3.1.1 ~ 4 psig SR 3.3.1.6 SR 3.3.1.7

7. Reactor Coolant Pump to Power 1,2(8 ) c SR 3.3.1.1 >2% RTP with ~ 2 pumps SR 3.3.1.5 operating SR 3.3.1.6 SR 3.3.1.7

8. Nuclear Overpower Flux/Flow 1,2<*> c SR 3.3.1.1 As specified in the COLR Imbalance SR 3.3.1.3 SR 3.3.1.5 SR 3.3.1.6 SR 3.3.1.7

.I OCONEE UNITS 1, 2, & 3 3.3.1-5 Amendment Nos. m_, 39Q_ &~

RPS Instrumentation 3.3.1 Table 3.3.1-1 (page 2 of 2)

Reactor Protective System Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER . FROM SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS ACTION B.1 REQUIREMENTS VALUE

9. Main. Turbine Trip (Hydraulic ?: 30% RTP E SR 3.3.1.5 ?: 800 psig Fluid Pressure) SR 3.3.1.6 SR 3.3.1.7

10. Loss of Main Feedwater Pumps ?:2% RTP F SR 3.3.1.5 ?: 75 psig (Hydraulic Oil Pressure) SR 3.3.1.6 SR 3.3.1.7

11. Shutdown Bypass RCS High 2(bl,3(b) D SR 3.3.1.1 s 1720 psig Pressure SR 3.3.1.5 4 <bl, 5(b) SR 3.3.1.6 SR 3.3.1.7 (a} When not in shutdown bypass operation.

(b} During shutdown bypass operation with any CRD trip breakers in the closed position and the CRD System capable of rod withdrawal.

(c) With any CRD trip breaker in the closed position and the CRD System capable of rod withdrawal.

OCONEE UNITS 1, 2, & 3 3.3.1-6 Amendment Nos. 388 ,390 & 389

RPS-RTC 3.3.3 3.3 INSTRUMENTATION 3.3.3 Reactor Protective System (RPS) - Reactor Trip Component (RTC)

LCO 3.3.3 Four RTCs shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODES 3, 4, and 5 with any control rod drive (CRD) trip breaker in the closed position and the CRD System capable of rod withdrawal.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RTC inoperable. A.1 Trip the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CRD trip breaker.

OR A.2 Remove power,from 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the associated CRD trip breaker.

B. Two or more RTCs B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable in MOCE 1, 2, or 3. AND

\

OR B.2.1 Open all CRD trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months breakers.

Required Action and associated Completion OR Time not met in MODE 1, 2, or 3. B.2.2 Remove power from all 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months CRD trip breakers.

(continued)

OCONEE UNITS 1, 2, & 3 3.3.3-1 Amendment Nos - 388*390

- &389

RPS-RTc*

3.3.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Two or more RTCs C.1 Open all CRD trip 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

inoperable in MOCE 4 breakers.

or 5.

OR C.2 Remove power from all 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action and CRD trip breakers.

associated Completion Time not met in MODE4 or5.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3:3.1 Perform CHANNEL FUNCTIONAL TEST. , In accordance with the Surveillance Frequency Control Program OCONEE UNITS 1, 2, & 3 3.3.3-2 _ ,39Q Amendment Nos. 388 _ ,389

ESPS Input Instrumentation 3.3.5 3.3 INSTRUMENTATION 3.3:5 Engineered Safeguards Protective System (ESPS) Input Instrumentation LCO 3.3.5

Three channels of ESPS input instrumentation for each Parameter in Table 3.3.5-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5-1.

ACTIONS

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

Separate Condition entry is allowed for each Parameter.

CONDITION REQUIRED ACTION COMPLETION TIME A. One.or more A.1 Place channel in trip. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Parameters with one channel inoperable.

B. One or more B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Parameters with two or more channels AND inoperable.

B.2.1 ----NOTE----

OR Only required for RCS Pressure - Low.

Required Action and -------------

associated Completion Time not met. Reduce RCS pressure 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

< 1750 psig.

AND (continued)

OCONEE UNITS 1, 2, & 3 3.3.5-1 Amendment Nos. 388. 390 &389

ESPS Input Instrumentation

. 3.3.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR '3.3.5.2 , ----"-----------------N()TE------------------------------

Not applicable to Reactor Building Pressure - High High parameter.

Manually verify that the setpoints are correct. In accordance with the Surveillance Frequency Control Program SR 3.3.5.3 Not Applicable Not Applicable SR 3.3.5.4 Perform CHANNEL CALIBRATI()N. In accordance with the Surveillance Frequency Control Program

()C()NEE UNITS 1, 2, & 3 3.3.5-3 Amendment Nos. 388; 390. 389

ESPS Automatic Actuation Output Logic Channels 3.3.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.7.1 Manually actuate the output channel In accordance with the interposing relays. Surveillance Frequency Control Program SR 3.3.7.2 Perform automatic actuation output logic In accordance with the CHANNEL FUNCTIONAL TEST .. Surveillance Frequency Control Program*

OCONEE UNITS 1, 2, & 3 3.3.7-2 Amendment Nos. _388., _

390, _

389

LPSW RB Waterhammer Prevention Circuitry 3.3.27 3.3 INSTRUMENTATION 3.3.27 Low Pressure Service Water (LPSW) Reactor Building (RB) Waterhammer Prevention Circuitry LCO 3.3.27 Three LPSW RB Waterhammer Prevention analog channels and two digital logic channels shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required LPSW RB A.1 Restore required LPSW 7 days Waterhammer RB Waterhammer Prevention analog Prevention analog channel inoperable. channel to OPERABLE*

status.

B. One required LPSW RB 8.1 Restore required LPSW 7 days Waterhammer RB Waterhammer Prevention digital logic Prevention digital logic channel inoperable. channel to OPERABLE status.

(contmued)

OCONEE UNITS 1, 2, & 3 3.3.27-1 Amendment Nos. 388, 390 , &389 I

Reactor Building Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.5.1 Verify each reactor building spray and cooling In accordance with the manual and non-automatic power operated Surveillance Frequency valve in the flow path that is not locked, Control Program sealed, or otherwise secured in position is in the correct position.

SR 3.6.5.2 Operate each required reactor building In accordance with the cooling train fan unit for ~ 15 minutes. Surveillance Frequency Control Program SR 3.6.5.3 Verify each required reactor building spray In accordance with the pump's developed head at the flow test point lnservice Testing is greater than or equal to the required Program developed head.

SR 3.6.5.4 Verify that the containment heat removal In accordance with the

. capability is sufficient to maintain post Surveillance Frequency accident conditions within design limits. Control Program (continued)

OCONEE UNITS 1, 2, & 3 3.6.5-4 Amendment Nos. 388,390 , 389 I*

Reactor Building* Spray and Cooling Systems 3.6.5 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.5.5 Verify each automatic reactor building spray In accordance with the and cooling valve in each required flow path Surveillance Frequency that is not locked, sealed, or otherwise Control Program secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.6.5.6 Verify each required reactor building spray In accordance with the -

pump starts automatically on an actual or Surveillance Frequency simulated actuation signal.

Control Program SR 3.6.5.7 Verify each required reactor building cooling In accordance with the train starts automatically on an actual or Surveillance Frequency simulated actuation signal. Control Program SR 3.6.5.8 Verify each spray nozzle is unobstructed. In accordance with the Surveillance Frequency Control Program OCONEE UNITS 1, 2, & 3 3.6.5-5 Amendment Nos. 388 390 389

LPSW System 3.7.7

3. 7 PLANT SYSTEMS

3.7.7 Low Pressure Service Water (LPSW) System LCO 3.7.7 For Unit 1 or Unit 2, three LPSW pumps and one flow path shall be OPERABLE.

For Unit 3, two LPSW pumps and one flow path shall be OPERABLE.

The LPSW Waterhammer Prevention System (WPS) shall be OPERABLE.

~-----------------------------NOTE--------------------------------------------~

With either Unit 1 or Unit 2 defueled and appropriate LPSW loads secured on the defueled Unit, such that one LPSW pump is capable of mitigating the consequences of a design basis accident on the remaining Unit, only two LPSW pumps for Unit 1 or Unit 2 are required.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required LPSW A.1 Restore required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months pump inoperable. LPSW pymp to OPERABLE status.

B. LPSWWPS B.1 Restore the LPSW 7 days inoperable. WPS to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or AND B not met.

C.2 Be in MODE 5. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months OCONEE UNITS 1, 2, & 3 3.7.7-1 Amendment Nos. _ 388 ,390

_&389 ,-

LPSW System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify LPSW leakage accumulator level is within In accordance with the Water levels between 20.5" to 41 ". During LPSW Surveillance Frequency testing, accumulator level> 41" is acceptable. Control Program SR 3.7.7.2 -------NOTE----------

Isolation of LPSW flow to individual components does not render the LPSW System inoperable.

Verify each LPSW manual, and non- In accordance with the automatic power operated valve in the flow

Surveillance Frequency path servicing safety related equipment, that Control Program is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.7.3 Verify each LPSW automatic valve in the flow In accordance with the path that is not locked, sealed, or otherwise Surveillance Frequency secured in position, actuates to the correct Control Program position on an actual or simulated actuation signal.

SR 3.7.7.4 Verify each LPSW pump starts automatically In accordance with the on an actual or simulated actuation signal. Surveillance Frequency Control Program SR 3.7.7.5 Verify LPSW leakage accumulator is able to In accordance with the provide makeup flow lost due to boundary Surveillance Frequency valve leakage. Control Program SR 3.7.7.6 Verify LPSW WPS boundary valve leakage is In accordance with the s 20 gpm. Surveillance Frequency Control Program OCONEE UNITS 1, 2, & 3 3.7.7-2 Amendment Nos. 388_* , 390

_&,389-

ECCW 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Emergency Condenser Circulating Water (ECCW} System LCO 3.7.8 Two ECCW siphon headers shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ECCW A.1 Restore required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months siphon header ECCW siphon header inoperable. to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND 8.2 Be in MODE 5. 60 hours6.944444e-4 days 0.0167 hours 9.920635e-5 weeks 2.283e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify required Essential Siphon Vacuum In accordance with the (ESV) pumps are in operation. Surveillance Frequency Control Program (continued)

OCONEE UNITS 1, 2, & 3 3.7.8-1 Amendment Nos. 388 , 390 , 389

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 388 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 390 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AND AMENDMENT NO. 389 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 May 20, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14141A415), Duke Energy Carolinas, LLC (Duke Energy, the licensee), submitted a license amendment request (LAR) for the Oconee Nuclear Station, Units 1, 2, and 3 (ONS 1/2/3) to remove obsolete information in Technical Specifications (TSs) that no longer pertains to ONS.

2.0 REGULATORY EVALUATION

Title 10 of the Code of Federal Regulations (1 0 CFR) 50.36, "Technical Specifications," provides the regulatory requirements for the contents in a licensee's TSs. Section 50.36(c) requires that the TSs include items in the following categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCO); (3} surveillance requirements (SRs); (4) design features; and (5) administrative controls. The regulation does not specify the particular requirements to be included in a plant's TSs. Title 10 of the Code of Federal Regulations (1 0 CFR) Part 50.36(c)(3} notes that SRs are requirements relating to test, calibration, or inspection to assure that 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.

10 CFR 50.59, "Changes, tests, and experiments," and 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," describe the requirements for license amendments. 10 CFR 50.59(c)(1)(i) requires licensees to submit an application tor a license amendment pursuant to 10 CFR 50.90 if a change to their Technical Specifications is Enclosure 4

required. Furthermore, the requirements of 10 CFR 50.59 necessitate that the NRC approve the TS changes before those changes are implemented.

3.0 TECHNICAL EVALUATION

3.1 Summary of Proposed Changes The licensee stated that the proposed amendment would revise the ONS 1/2/3 TSs for three distinct reasons:

1. Remove obsolete information pertaining to:

Reactor Protective System (RPS)/Engineered Safeguards Protective System (ESPS) digital upgrades (Section 3.2 of this Safety Evaluation (SE))

Low Pressure Service Water (LPSW) Reactor Building (RB) Waterhammer Prevention System (WPS) modifications (Section 3.3 of this SE)

Emergency Condenser Circulating Water (ECCW)"System Service Water upgrade modifications (Section 3.4 of this SE)

2. Eliminate the SRs to manually verify correct software set points for Reactor Protective System RB High Pressure trips and Engineered Safeguards Protective System Reactor Building Pressure - High High actuations (Section 3.5 of this SE)

3. Correct the wording of Conditio.n C of TS 3.7.7, "Low Pressure Service Water (LPSW) System" (Section 3.6 of this SE)

The licensee considers all the proposed TS changes to be administrative changes.

3.2 Removal of Obsolete Information Pertaining to Reactor Protective System/Engineered Safeguards Protective System Digital Upgrades 3.2.1 Proposed TS changes are as follows:

a. TS 3.3.1 (1) Condition A- Changed the Completion Time column from:

"1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for Unit(s) with the RPS digital upgrade not complete OR 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for Unit(s) with RPS digital upgrade complete"

~

to:

"4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months " (2) SR 3.3.1.4- Deleted the note in the Surveillance column, "Not applicable to Unit(s) with RPS digital upgrade complete;" and changed the Surveillance and Frequency columns to "Not Applicable."

(3) SR 3.3.1.5 - Deleted the note in the Surveillance column, "Only applicable to Unit(s) with RPS digital upgrade complete."

(4) SR 3.3.1.6- Deleted the note in the Surveillance column, "Only applicable to Unit(s) with RPS digital upgrade complete."

(5) Table 3.3.1 Deleted "SR 3.3.1.4" in the Surveillance Requirements column

( 11 locations).

b. TS 3.3.3 (1) Condition A- Changed numbering of Required Actions "A.1.1" and "A 1.2" to "A.1" and "A.2," respectively. Deleted "AND A.2" and its associated note, "Not applicable to Unit(s) with RPS digital upgrade complete" in the Required Action column and associated "1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months " in the Completion Time column.

c. TS 3.3.5 (1) Condition A- Changed the Completion Time column from:

"1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for Unit(s) with the ESPS digital upgrade not complete OR 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for Unit(s) with ESPS digital upgrade complete" to:

"4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months " (2) SR 3.3.5.2 - Revised the current note in the Surveillance column from "Only applicable to Unit(s) with ESPS digital upgrade complete" to "Not applicable to Reactor Building Pressure - High High parameter."

(3) SR 3.3.5.3 - Deleted the note in the Surveillance column and changed the remaining action text in the Surveillance column to "Not Applicable." Changed the text in the Frequency column to "Not Applicable." *

d. TS 3.3.7 (1) SR 3.3.7.1 - Deleted the note in the Surveillance column, "Only applicable to Unit(s) with the ESPS digi_tal upgrade complete."

3.2.2 Licensee Justification Duke Energy replaced the analog-based Reactor Protective System and Engineered Safeguards Protective System at ONS with a TELEPERM XS (TXS) digital protection system. The digital _

upgrade was implemented for each ONS unit during recent refueling outages with the final upgrade occurring for ONS Unit 2 during the fall 2013 refueling outage. Thus, the TS

requirements for the analog-based RPS/ESPS equipment no longer apply to any of the three units at ONS.

3.2.3 NRC Staff's Assessment The NRC staff finds that, because the digital upgrades to the RPS/ESPS are complete for all three units, the existing TSs related to analog equipment no longer apply to ONS and should be deleted.

3.3 Removal of Obsolete Information Pertaining to Low Pressure Service Water System Reactor Building Waterhammer Prevention System Modifications 3.3.1 Proposed TS changes are as follows:

a. TS 3.3.27 (1) LCO 3.3.27- Deleted the LCO Note, "Applicable on each unit after completion of the LPSW RB Waterhammer Modification on the respective Unit."

b. TS 3.6.5 (1) SR 3.6~5.1 - Deleted the note in the Surveillance column, "Applicable for RB cooling system after the completion of the LPSW RB Waterhammer Modification on the respective Unit."

(2) SR 3.6.5.5 - Deleted the note in the Surveillance column, "Applicable for RB cooling system after the completion of the LPSW RB Waterhammer Modification on the respective Unit."

c. TS 3.7.7 (1) LCO 3.7.7- In the third statement, deleted "on Units where the LPSW RB Waterhammer modification is installed."

(2) Condition B- Deleted "on Units with LPSW RB Waterhammer modification installed" in the Condition column.

(3) SR 3.7.7.1 -In the Surveillance column, deleted for Units with LPSW RB Waterhammer modification installed."

(4) SR 3.7.7.5 -In the Surveillance column, deleted "on Units with LPSW RB Waterhammer modification installed."

(5) SR 3.7.7.6 -In the Surveillance column, deleted for Units with LPSW RB Waterhammer modification installed."

3.3.2 Licensee Justification Duke Energy installed a waterhammer prevention system modification on the low pressure service water system reactor building piping. Since the ONS TSs apply to all three ONS units, the new LPSW RB WPS and LPSW RB waterhammer prevention circuitry TS requirements needed clarification statements and notes to indicate that they only applied if the LPSW RB WPS modification was installed. The LPSW RB WPS and LPSW RB waterhammer prevention circuitry modifications have since been installed on all three ONS units. Thus, the associated TS clarification statements and notes are no longer needed.

3.3.3 Staff's Assessment The NRC staff finds that because the new LPSW RB WPS and LPSW RB waterhammer prevention circuitry modifications are complete on all three ONS units, the associated TS clarification statements and notes specifying that the requirements only apply for the Units with the waterhammer modification installed are no longer necessary in the TSs and should be deleted from the TSs.

3.4 Removal of Obsolete Information pertaining to Emergency Condenser Circulating Water System Service Water Upgrade Modifications 3.4.1 Proposed TS changes are as follows:

a. TS 3.7.8 (1) LCO 3.7.8- Deleted the LCO Note, "Not applicable on each Unit until after completion of the Service Water upgrade modifications on the respective Unit" 3.4.2 Licensee Justification The emergency condenser circulating water system service water upgrade modifications are complete and have been implemented for each ONS unit. Thus, the associated TS clarification statement no longer applies.

3.4.3 Staff's Assessment The NRC staff finds that, because the service water upgrade modifications are complete for each .

ONS unit, the service water upgrade modification applicability note is no longer needed and should be deleted from the TSs.

3.5 Eliminate the Surveillance Requirements to Manually Verify Correct Software Setpoints for RPS RB High Pressure Trips and ESPS RB Pressure - High High Actuations 3.5.1 Proposed TS changes are as follows:

a. TS 3.3.1 (1) Table 3.3.1-1, RPS Function No. 6, "Reactor Building High Pressure," deleted SR 3.3.1.5.

b. TS 3.3.5

( 1) SR 3.35.2 - Revised the current note in the Surveillance column from "Only

\applicable to Unit(s) with ESPS digital upgrade complete" to "Not applicable to Reactor Building Pressure - High High parameter."

3.5.2 Licensee Justification Technical Specification Surveillance Requirements SR 3.3.1.5 and SR 3.3.5.2 for the digitally-upgraded RPS and ESPS, respectively, require manual verification that parameters/.

functions in these instrumentation systems trip at the proper setpoints. The intent of these Surveillance Requirements is to retrieve the setpoints from software periodically to confirm that they have not been incorrectly entered.

The ONS Technical Specifications are written such that these Surveillance Requirements apply to all functions of the RPS and to all parameters of the ESPS. However, the RB High Pressure trip function for the RPS and RB Pressure - High High actuation parameter for the ESPS (which actuates ESPS Channels 7 and 8) have no software setpoints associated with them. For every other parameter/function associated with both the RPS and the ESPS, there is some value in the software which can be assessed to satisfy the SR (even for other functions which involve pressure switches). For the RPS RB High Pressure trip function (i.e., RPS Function No. 6 on TS Table 3.3.1-1) and ESPS RB Pressure- High High actuation parameter (i.e., ESPS Parameter No. 4 on TS Table 3.3.5-1 ), there is nothing in the software to assess since the trip function/actuation parameter consists of pressure switches which only provide contact status to the system. Currently, ONS TS Bases B 3.3.1 and B 3.3.5 contain a clarification statement in the description sections of SR 3.3.1.5 and SR 3.3.5.2, respectively, that states the SR is not applicable to the trip function/actuation parameter since there is nothing to verify.

3.5.3 Staff's Assessment The NRC staff f_inds that, because the RPS RB High Pressure trips and ESPS RB Pressure- High High actuations do not have software setpoints associated with them, it is acceptable to remove TS SR 3.3.1.5 as a SR in Table 3.3.1-1, RPS Function No. 6, "Reactor Building High Pressure" and to add a note in SR 3.3.5.2 that the SR is not applicable to the Reactor Building Pressure -

High High parameter.

3.6 Correct the Wording of Condition C of TS 3.7.7, "Low Pressure Service Water System" 3.6.1 Proposed TS changes are as follows:

a. TS 3.7.7 (1) Condition C - Chang*e the word "and" in "Condition A and B" to the word "or."

3.6.2 Licensee Justification On October 16, 2007, Duke Energy submitted ONS LAR No. ./

2006-05 for the addition of the

LPSW RB WPS modification to mitigate waterhammers, as described in NRC Generic Letter 96-06. In response to NRC requests for additional information on that LAR submittal, and issues raised in subsequent conversations with the NRC, Duke Energy submitted a revised LAR to the NRC on October 23, 2008, which included a new Condition C forTS 3.7.7, "Low Pressure Service Water System." However, the revised LAR inadvertently included the wording error described in Section 1 in newTS 3.7.7 Condition C. The TS 3.7.7 Bases provided with the revised LAR did not reflect the wording error and is correct as stated. The NRC subsequently approved the revised LAR by issuing Amendment Nos. 363, 365, and 364 on October 29, 2008. The NRC-issued amendments also contained the wording error in TS 3.7.7 Condition C.

3.6.3 Staff's Assessment The NRC staff finds it acceptable to correct the wording error in TS 3.7.7, Condition C, noting that the use of the term "or is more restrictive than the current wording, and that the corrected wording reflects the staff's intent when it issued the prior amendments ..

3. 7 Staff's Summary Conclusion The NRC staff finds all the proposed ONS TS changes acceptable and agrees they are administrative in nature. ,

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, which was published in the Federal Register on August 5, 2014 (79 FR 45473). 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 al)1endments.

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 s_afety of the public.

Principal Contributor:

Shawn Williams, NRR/DORL Date: October 21, 2014

ML14195A355 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/LPL2-1/PM OGC NRR/LPL2-1/BC NRR/LPL2-1/PM NAME SWilliams SFigueroa RHall <

BMizuno* RPascarelli SWilliams DATE 08/06/14 08/06/14 08/26/14 09/02/14 10/21/14 10/21/14

v t e Letter Sequence Approval
TAC:MF4373, (Approved, Closed) TAC:MF4374, (Approved, Closed) TAC:MF4375, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval Other: ML14189A393
MONTHYEAR2014-05-20 [Table View]

ML14195A355

Text

SUBJECT:

Dear Mr. Batson:

Enclosures:

Attachment:

Attachment:

Attachment:

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

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