february 12, 2015 · changes to license no. n pf-17 and the technical specifications for the...

UNITED STATES NUCLEAR REGULATORY COMMISSION

WASHINGTON, D.C. 20555-0001

Mr. Benjamin C. Waldrep Vice President Nuclear Corporate Duke Energy Carolinas, LLC P.O. Box 1006/EC07H Charlotte, NC 28201-1006

February 12, 2015

SUBJECT: CATAWBA NUCLEAR STATION, UNITS 1 AND 2 (CATAWBA 1 AND 2), MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 (MCGUIRE 1 AND 2), AND OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 (OCONEE 1, 2, AND 3) -ISSUANCE OF AMENDMENTS REGARDING CHANGES TO ORGANIZATION, UNIT STAFF RESPONSIBILITY, UNIT STAFF QUALIFICATIONS, PROGRAMS AND MANUALS, AND HIGH RADIATION AREAS (TAC NOS. MF4491, MF4492, MF4493, MF4494, MF4495, MF4496, AND MF4497)

Dear Mr. Waldrep:

By letter dated July 21, 2014, Duke Energy Carolinas, LLC (Duke, the licensee), submitted a license amendment request (LAR) to modify Technical Specification (TS) 5.1, "Responsibility," TS 5.2, "Organization," TS 5.3, "Unit Staff Qualifications," TS 5.5, "Programs and Manuals." Additionally, the LAR requested to modify TS 5.7, "High Radiation Area" for Catawba and McGuire. Specifically, and in addition to adm.inistrative changes, the amendment updates the licensed operator training requirements to be consistent with the National Academy for Nuclear Training (NANT) program.

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 273 to Renewed Facility Operating License NPF-35 and Amendment No. 269 to Renewed Facility Operating License NPF-52 for Catawba 1 and 2, Amendment No. 276 to Renewed Facility Operating License NPF-9 and Amendment No. 256 to Renewed Facility Operating License and NPF-17 for McGuire 1 and 2, and Amendment No. 389 to Renewed Facility Operating License DPR-38, Amendment No. 391 to Renewed Facility Operating Licenses DPR-47, and Amendment No. 390 to Renewed Facility Operating Licenses DPR-55 for Oconee 1, 2 and 3, 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.

B. Waldrep - 2 -

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

Sincerely,

1

j . 6t>if'/('«J( G. Edward Miller, Project';Janager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-413, 50-414, 50-369, 50-370 50-269, 50-270, and 50-287

Enclosures: 1. Amendment No. 273 to NPF-35 2. Amendment No. 269 to NPF-52 3. Amendment No. 276 to NPF-9 4. Amendment No. 256 toNPF-17 5. Amendment No. 389 to DPR-38 6. Amendment No. 391 to DPR-47 7. Amendment No. 390 to DPR-55 8. Safety Evaluation

cc w/encls: Distribution via Listserv



DUKE ENERGY CAROLINAS, LLC

DOCKET NO. 50-413

CATAWBA NUCLEAR STATION, UNIT 1

AMENDMENT TO RENEWED FACILITY OPERATING LICENSE

Amendment No. 273 Renewed License No. NPF-35

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

A. The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility), Renewed Facility Operating License No: NPF-35, filed by Duke Energy Carolinas, LLC (the licensee), dated July 21, 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 h.ealth and safety of the public; and

E. The issuance of this amendment is in accordance with 1 O CFR Part 51 of the_ Commission's regulations and all applicable requirements have been satisfied.

Enclosure 1

- 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 2.C.(2) of Renewed Facility Operating License No. NPF-35 is hereby amended to read as follows:

(2) Technical Specifications

The Technical Specifications contained in Appendix A, as revised . through Amendment No. 273, 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 120 days of issuance.

Attachment: Changes to License No. NPF~35

and the Technical Specifications

FOR THE NUCLEAR REGULATORY COMMISSION

Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Date of Issuance: February 12, 2015




DOCKET NO. 50-414

CATAWBA NUCLEAR STATION, UNIT 2




A. The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility), Renewed Facility Operating License No. NPF-52, filed by Duke Energy Carolinas, LLC (the licensee), dated July 21, 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;



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 -



The Technical Specifications contained in Appendix A, as revised through Amendment No. 269, 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 120 days of issuance.

Attachment: Changes to License No. NPF-52




Date of Issuance: February 12 , 2015

UNITED STATES NUCLEA~ REGULATORY COMMISSION

, WASHINGTON, D.C. 20555-0001


DOCKET NO. 50-369

MCGUIRE NUCLEAR STATION, UNIT 1




A. The application for amendment 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 July 21, 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;




E. The issuance of this amendment is in accordance with 1 O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 3

- 2 -


(2) Technical. Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No. 276, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in

, accordance with the Technical Specifications.


Attachment: Changes to License No. N PF-9








DOCKET NO. 50-370

MCGUIRE NUCLEAR STATION, UNIT 2




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 July 21, 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;


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;


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 4

- 2 -



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


Attachment: Changes to License No. N PF-17


FOR THE NUCLEAR REGULATORY COMMISSION I

01/!fJ~·

Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing · Office of Nuclear Reactor Regulation





DOCKET NO. 50-269

OCONEE NUCLEAR STATION, UNIT 1


Amendment No. 389 Renewed License No. DPR-38


A. The application for amendment to the Oconee Nuclear Station, Unit 1 (the facility), Renewed Facility Operating License No. NPF-38, filed by Duke Energy Carolinas, LLC (the licensee), dated July 21, 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 1 O CFR Chapter I;


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 1 O CFR Chapter I;


- 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 5

- 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 2.C.(2) of Renewed Facility Operating License No. DPR-38 is hereby amended to read as follows:



3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days of issuance. ·

Attachment: Changes to License No. DPR-38








DOCKET NO. 50-270



Amendment No. 391 Renewed License No; DPR-47


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 July 21, 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 1 O CFR Chapter I;





Enclosure 6

- 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 2.C.(2) of Renewed Facility Operating License No. DPR-47 is hereby amended to read as follows:


The Technical Specifications contained in Appendix A, as revised through Amendment No. 391, are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications. ·










DOCKET NO. 50-287



Amendment No. 390 Renewed License No. DPR-55


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 July 21, 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;




Enclosure 7

- 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 2.C.(2) of Renewed Facility Operating License No. DPR-55 is hereby amended to read as follows:





and the Technical SpeCifications




. '"' ATTACHMENT TO LICENSE AMENDMENT NO. 273

RENEWED FACILITY OPERATING LICENSE NO. NPF-35

DOCKET NO. 50-413

AND

LICENSE AMENDMENT NO. 269


DOCKET NO. 50-414

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 NPF-35, page 4 NPF-52, page 4

TSs 5.1-1 5.2-1 5.2-2 5.3-1 5.5-1 5.7-1


TSs 5.1-1

. 5.2-1 ·5_2-2 5.3-1 5.5-1 5.7-1

-4-


The Technical Specifications contained in Appendix A, as revised through · Amendment No.273 ,which are attached hereto, are hereby incorporated into

this renewed operating license. Duke Energy Carolinas, LLC 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 cpmplete these activities no later than December 6, 2024, 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.

(4) Antitrust Conditions

Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.

(5) Fire Protection Program (Section 9.5.1, SER, SSER #2, SSER #3, SSER #4, SSER #5)*

Duke Energy Carolinas, LLC shall.implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, as amended, for the facility and as approved in the SER through Supplement 5, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of.the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

*The parenthetical notation following the title of this renewed operating license condition denotes the section of the Safety Evaluation Report and/or its supplement wherein this renewed license condition is discussed. ·

Renewed License_No. NPF-35 Amendment No. 273

-4-


The Technical Specifications contained in Appendix A, as revised through Amendment No. 259which are attached hereto, are hereby incorporated into this renewed operating license. Duke Energy Carolinas, LLC 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 December 6, 2024, 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 1 O 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 therequirements in that section. ·

(4) Antitrust Conditions

Duke Energy Carolinas, LLC shall comply with the antitrust conditions delineated in Appendix C to this renewed operating license.

(5) Fire Protection Program (Section 9.5.1, SER, SSER #2, SSER #3, SSER #4, SSER #5)"

Duke Energy Carolinas, LLC shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report, as amended, for the facility and as approved in the SER through Supplement 5, subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

*The parenthetical notation following the title of this renewed operating license condition denotes the section of the Safety Evaluation Report and/or its supplement wherein this renewed license condition is discussed.

Renewed License No. NPF-52 Amendment No. 26,9

5.0 ADMINISTRATIVE CONTROLS

5.1 ResponsibH!tx

Responslbnlty 5.1

5.1.1 The Plant Manager ahall ·be responsible for overall unit operation and shall · deiegate in writing the succession to this responalblllty during hia absence .

....

5.1.2 The Control Room Supervisor (CRS) shall be responsible for the control room command function. During any absence ·of the CRS from the control room while the unit is in MODE 1, 2, 3, or 4, an Individual (other than the Shift Technical. Advtsor.(STA)) with an active Senior Reactor Operator {SRO) license shall be designated to assume the control room command function. During any absence of the CRS from the control room while the .unit la In MODE 5 or 6,· an individual with an active SRO license or Reactor Operator Ucense ahall be designated to easume the control room command function. · .

On occasion when there Is a need for both the CRS and the relief SRO to be absent from the control room In MODE 1, 2,. 3, or 4, an STA with an ac;tive SRO ficense on the unit shatl be allowed to assume the control room command function and serve as the SRO in the control room provided that:

a. the CRS or the relief SRO is available to retum to the control room within 1 o minutes, anct . · ·

. . ~. ' '

b. the assumption of CRS duties by the STA Is limited to periods not in excess of 15 minutes duration and a total time not to exceed 1 hour during any shift · · · ·

';' ..

I .

Catawba Units 1 and 2 5.1-1 Amendment Nos.2Y3; · 26911

5.o· ADMINISTRATIVE CONTROLS

5.2 OrganiZation

5.2.1 Onslte and OffaU, Qraanlzatlont

OrganiZation 5.2

Onsite and offsite organizations ·shall be established for unit operation and corporate management, respectively. The onalte and offsite organiZ&tions shall Include the positlon·s for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest manegement levels, Intermediate levels, and all operating organization positions. ~ relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationship!, and job descriptions for key personnel positions, or in equivalent forms of documer1tation. Theie requirements lhaU be documented in the UFSAR;

b. The Plant Manager shaH be responsible for overall ufe operation of the Pt&nt and shall have control over those on1ite activities necessary for eafe ~and maintenance of the plant;

c. The vice President, Cetawba Nuclear Site, shall have responsibility for overall plant nuclear safety and shBU take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety;

:. • • •J •••••

d. The Chief Nuclear Officer wm:be the 8enior Nuclear Executive and have corporate res~slbillty·fot overa11.nuclear safdty; Ind · " · ..

• J' . ·~ • •

e. The lndivfdua1s Who train the operating 11aff, .carry out vadiation protection, or perform quality assurance functions may report to the appropriate onalte manager; 91~r. ~-1~¥d.U$1~ sh~I havtp sufficient ~tional .... freedom to ensure their Independence from operating pressures.

5.2.2 Unit Staff

The unit staff organization shall Include the following:

a. A non-licensed operator shall be anigned to each reactor containing fuel and an additional non-ricensed operator shall be assigned for each control room from which a reactor Is operating in MODES 1, 2, 3, or 4. .

A total of three non-licensed operator& are required for the two units.

(continued)

Catawba Units 1 and 2 5.2-1 Amendment Nos.273~ 269 I

/

(, ' •,•,I, • ' ' •' •,I ' ,: J t

5.2.2 Unjt §taff (continued)

·Organization 5.2

b. At iWt one licensed.Reacb Operator (RO) ahall be present in the control room Yt'tlen fuel ia in the reactor. In addition, while the unit la In MOOE 1,

. · 2, 3, ·or 4,; ~a.eat °'10 licensed ~r Reactor Operator (SRO) shall be present in the control. room.

c. Shift Ctf!IN composition mey be leS8 than the minjmum .requirement of 10 CFR 50.54(m)(2)(1) and.5.2.2.e iJnd 5.2.2.g for a period of time not to exceed 2 hours in order to accommodate unexpected absence of on-duty shift crew member& provided immediate action is •en to reetore the shift C1'8W comppsltion to within the minimum requirements.

. . . . . .. . . . . d. A Radiation Protection Technician ahaH be on site when fuel 18 in the

reactor. The position may be vacant for not more than 2 houri, in order to provide for u~ ablence, provided immediate action ii taken to fill the required position.. . . ' .

... ·. . . :

e. .Deleted.

f. The Operations Manager shall hold or have held a SRO license. The Aasiatant Operations Manager • Shift, Shift Man8Qer, and Control Room Supervisor shall hold an SRO license. The Control Operator lhall hold a

.. Reactor Operator License.

g. The Shift Technical Advisor (STA) shaR provide advisory technicaJ support to the Shift Manager In the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit In eddition, the STA shaU meet the quallficationa specified by the Commission Policy Statement on Engineering Expertise on Shift.

Catawba Units 1 and 2 5.2-2 Amendment Nos273~ 269 I

• - •• .. •••• ~ •• , • # • -·. , • '• • • •. '• ~- • •• ' I"':'

Unit Staff Qualifications 5.3

...... ~.· ... . ...... · .· . - .

5.0. ADMINISTRAT&ve CONl:ROLS · · · ~ .... · "· ·.

5.3 Unit Staff Qualifications .. .

.' \ .. . ... . 5.3.1 Each member. of .the unit staff shall meet or exceed the minimum qualifications of

ANSl-N18.1-1971 for comparable poaitiona, except:

5.3.2

1. The Radiation Protection Manager, who shall meet or exceed the qualifications of Regulatory Gulde 1.8, September 1975.

2. The education and 83Cperience eligibility requirements for licensed operators shalt meet-or exceed the guidelines outlined by the National Academy for Nuclear Training (NANT), \4\lhlch have been found acceptable by the Nuclear Regulatoty Comm1881on (NRC) for meeting 10 CFR 55.31 and have been lncorporeted into appllcllble etatton ~ng procedures .

. .... . . . . . For the purposes of 10 CFR 55.4, a Hcensed Senior Reactor Operator (SRO) and a licensed Reactor Operator (RO).are those individuals who, in addition to meeting the requirements of TS 5.3.1, perform the functions described tn 10 CFR 50.64(m).

·. .

I • ,; ·· .. . ·~ . .. : . .·•. ·• . .~. . . . :

... . - , .. l ...... •• •'•\ •• ;•

~. . . . . ~ ~ :. . :· •·: :. \ ..

: . ·· .. .. ...

I ••.

. ...

' ... ....,

Catawba Units 1 and 2 5.3-1 Amendment Nos. 273,. 269 I


5.5 P9rams.and Manuals

The following programs shall be established, ·imple,,,.,,ted, and maintained .

5.5.1 ..

Offsita Pose Calcu!atjon Manual COOCMl . .

The ODCM shall contain the methodology and par:ameters used in the calculation of offaite doaes resulting from radioactive gaseous and liquid effluents, -In- the·calculation· of _gueous and liquid effluent monitoring alann and trip satpolnts; and In the cond.uct of the radiological environmental monitoring program.

Ucensee i'11tiated changes to the OOCM:

a. Shall be documented and records of review& performed shall be retained.

b.

c.

This documentation 1han contain:

1. sufficient information to support the change(s) together with the appropriate 8nalyses or evaluations justifying the change(s), and

2. •determination that the change(s) do not adversely impact the accuracy or reliability of effluent. dose, or setpofnt calculations;

S..,I b8Come effective after~ approv$1 of _the Plant Ma~ or Radiation Protection Manager, efld. , · . : .

Shall be submitted to the NRC In the fonn of a complete, legible copy of the entire ODCM as a part of or con®"'9nt with the Radioactive Effluent Re~_Repm ~-the· period of the ~por.t in which ~ny change in the ODCM was made. Each.change shall tleJdentified by marking& in the 111$1'Qln of~-~ pages, •rty Indicating the area of the page that was changed; •rid shall indicate the date (i.e., month and year) the change was Implemented.

. .. ~ .. . ~ . .. . ·' :

5.5.2 COnfainment Leakage Bate Testing program . . . ; '• . '. ·. '

A program shall be._bllshad to l~nt the~ rate testing of the containment as required by 10CFR 50.54(0) and 10 CFR 50, AppendbtJ, Option B, as modified by approved exemptions. Thia program shall be In .accorda!'lce .wtth the guidelines contained In _Regulatory Guide 1.163; "Pef'.formance-8,ased Containment Leak-Test Program," dated September 1.995, aa.modifled·by the following exception&: · ·

.. 4 • • • •• • •

a.· The ~ntainment .visual examinations required by Regulatory .Position C.3 shall be condµcted 3 times every 10 yeal'8, including during each shutdown for SR 3.6.1.1 Type A test, prior tO initiating the Type A ~; and

(continued)

Catawba Units 1 and 2 5.5-1 Amendment Nos. 273, 269 I


5. 7 Hifilh Radiation Area

5. 7 .1 Pursuant to 10 CFR 20, paragraph 20.1601 ( c}, in lieu of the requiremems of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is> 100 mremlhr buts 1000 mrem/hr et 30 cm (12 in.) from the radiation source or from any surface \\tlich the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring Issuance of a Radiation Wortt Permit (RWP). Individuals qualified in radiation protection procedureS (e.g., Radiation Protection Technicians) or personnel continuously escorted by such individuata may be exempt from the RWP issuance requirement during the performance of their 888igned dutiet In high radiation areas with exposure rates s 1000 mrem/hr, provided they are otherwise foHowing plant radiation protection procedures for entry Into such high radiation areas.

Any individual or group of Individuals permitted to enter such areaa shall be provided with or acc:ompanied by one or more of the following:

a. A radiation monitoring &Mee that continuously Indicates the radiation dose rate In the area. ·

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose Is received. Entry into such areas with thia monitoring device may be made after the doee rate levels In the area have been established and peraoMel are aware of them ....

c. An individual queltfied ln radiatiOn protection pfOCedurea wtth a radiation dole rate monitoring device, who Is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the Radiation Protection Manager In the RWP.

5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels > 1000 mrem/hr at 30 cm (12 ln.} from the radiation source or from any surf9oe which the radiation penetrates ahalJ be provided with locked or continuously guarded doors to prevent unauthorized entry and the ~eys shall be maintained under the administrative control of the Shift Manager, Radiation Protection Manager, or radiation protection personnel. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedul'88 to provld8 positive exposure control. over the activities being performed within the area.

(continued)

Cetawba Units 1 and 2 · 5.7·1 Amendment Nos. 273,, 269 I

ATTACHMENT TO LICENSE AMENDMENT NO. 276


DOCKET NO. 50-369

AND


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


TSs 5.1-1 5.2-1 5.2-2 5.3-1 5.5-1 5.7-1


TSs. 5.1-1 5.2-1 5.2-2 5.3-1 5.5-1 5,7-1

(4)

(5)

(6)

-3-

Pursuant to the Act and 10 CFR Parts.30, 40 and 70, to receive, possess . and use in am·ounts 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 compor;ients; ·

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;

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 1 o 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%).


The Technical Soecifications contained in Appendix A, as revised through Amendment N!:f.276are 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 1 o CFR 54.21 (d), as. revised on December 16, 2002, describes certain future a_ctivities to be completed before the period of extended operation. Duke shall complete t_hese activities no later than June 12, 2021, and shall notify the NRG in writing when implementation of these activities is complete and can be verified by NRG inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, descrlbeQ 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 iss·uance of this renewed operating license .. Until that update is complete, Duke may make changes to the programs described in such ·supplement without prior Co_mmission approval. ..., provided that Duke evaluates each such change pursuant to the criteria set forth in 1 o CFR 50.59 and otherwise complies with the requirements in that section.

· Renewed license No. NPF-9 Amendment No: 276 ·

. 3.

(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 tb chemical or physical form, for sample analysis or' instrument calibration or associated with radioactive apparatus or components;

(5) Pursuant to the Act anq 1 O C.FR 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 con.tairi 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, regulalions, 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 ievel of 3469 megawatts thermal (100%).

(2) . Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No.25fure hereby incorporated into this renewed operating llcens.e. 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 NRG in writing when implementation of these activities is complete and can be verified by NRG inspection.

The Updated Final Safety Analysis Report supplement as revised on December 16, 2002, described above, shall be include~ 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 upc:Jate 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 1 O CFR 50.59, and otherwise complies with the requirements in that section. , ·

Renewed LicensA No. NPF-17 Amendment Na.· 256

Responsibility I 5.1 '


· 5.1 Reappnaiblllty -.

5.1.1

5.1.2

The Plant .Mami~r !Shall be 1J9SPOnaible for overall unit operation and shalt ctefegate in writing the succession to thil responsibility during his

.. abJenee: . :.· :::· ..

The Control Room Supervisor (CRS) shalt be responsible for the control room command function. During any absence of the CRS from the CQl;'ltrOI room while the unit is In.MODE 1, 2, 3, or 4, an individual [other than the Shift Technical Advieor (STA)) with an active Senior Reector o~ (SROlllcense shall be delignated to assume the control room command. function. During any absence of the CRS from the control room while the unit Is in MOOE 5 or 8; an.individual With an active SRO license or Reactor Operator license-shall.be designated to assume the control room command function. . . · · ·

. ' .. . .. '

On QCCa8ion when there i8 a need for both the CRS and the relief SRO to I be absent from the control room In MOOE 1, 2, 3, or 4, an STA with an

- active SRO license on the unit lhall .be allowed to assume the control . room.command function and serve• the SRO in the controt room provided that

a. .the CRS or the relief SRO is available to return to the controt room within 10 minutes, $nd . '

. . . . .

b. the 8siumption of CRS dutle$ by.the STA Is Hrnited to perioda not I · in excess of15 minutes duration and a total time not to exceed 1

· hour during any shift.. .... .. .. : · -. .

. ·. ·-:.· .. . ., .·· .... : ' ... ~. . . .. : .. ·'· •'

'•'.· ·· .. ' ;. :' ·.. . .-. : ... ~ .

McGuire Units 1 and 2 5.1·1 Amendment Nos. ?76, 256 I

. . .

Orgainlzation '. 5.2'-.

5.0 -ADMINISTRATIVE CONTROLS . ": ....

5.2 Orpanization

. 5.2.1 Onsjte ang Offl!te Oraan!zat!OQ! ... . ....

Onslte and offalte cxganizations shall be established for unit operation and corporate management. respecttvety. · The C>nsite and otflite organlzatiOns shaU include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, end c0mmunicati0n 1haU be defined and estabHshed throughout highest management levels, intermediate levels, and all operating organization positions. These relationehlps shall be dOcumented and-updated, aa appropriate, in organiZation chart&, functional description• of departmental resporislbffities and retationshJps, and Job descriptions for key personnel posltioni, or In equivalent forms of documentation. These req"ulrementa shall be documented In the UFSAR;

b. The. Plant Manager shalt be responsibte for overall aafe operation of the plant and shall.haVe control over those ·onsite aCtMties necessary for safe operation ·anct maintenance of the plant; · ·:

c. The VlCe President, McGuire NuClear Site: shall he\18 responsibility for overall plant nuclear-safety and shall take any meaiures needed to ensure acceptable performance of the staff in operating, maintaining, and proViding techniCal supporf tOthe fJfant to eneure nuclear safety;

I •" < '•, • 0 " '• •, ~· '" ' • .,

d. The Chief NUCiear Officer win be the Sen""· Nuclear EXecutMt and have corporate responsibility fOr' oV9ralf ~uele8t safety; and

e. The individuals who train the operating staff, carry out radiation protection, or perform quality assurance functions may report to the appropriate onsite manager, howevei', these ·;ndividuals shaH have sufficient' organizational freedom to ensure their Independence from operating pressures.

·. ,, ' :·. ·.·'· . .

McGuire Units 1 and 2 5.2-1

(continued)

Amendment Nos. 276, 256 I

. . . ~ .. :.°7 •'' • I ; ' : ~ • .. ..

Organization .. 5.2

5.2 Ors~nization (continued) .·· : .. ..

s.2.2 Vnlt Staff • . •• f ·• •

The unit staff organiZation afulll Include the fotlowing:

a. A non·Hcensed operator shall be assigned to each reactor containing fuel and an additional non.licensed operator shaU be assigned for each control room from which a reactor is operating in

b.

c.

d.

e.

f.

g.

MODES 1, 2, 3, or 4. · ·

A total cf three non-licehHd operatol"I are required for the two units .. · · · ·

At least one Hcensed Reactor Operator (RO) shaU be present In the control room ~ fuel ls in the reactor. In addition, while the unit ii In MOOE 1, 2, 3, or 4, at least one licensed Senior Reactor

. Operator (SRO} shall be present In the control room.

Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(1) and 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours In order to accommodate unexpected

· absence d on.wty shift Cl9W members provided immediate action 18 taken to restore the ahift craw composition to within the minimum requirements.

A Radiation Protection Technician shall be on site when fuel la in .the reactor. The position may be vacant for not more than 2 hours, in order to provide for unexpected absence, provided Immediate action Is taken to fiH the required position.

Deleted

The Operations Manager shall hold or have held an SRO licenle.

The Shift Technical Advisor (STA) shall provide advisory technical support to th8 Shift Manager in the areas of thermal hydraulic&, reactor engineering, and plant analysis with regard to the safe operation of the unit.

McGuire Units 1 and 2 AmendmentNos. 276, 256 I

..

Unit Staff Qualifications 5.3

s:o: ADMIN1s1RAr1ve··coNTROLS · · · · · · · - .... - .

' si· unit sttiff auatifiCationa:· · ~- · ·: · · · · · ·

5.3.1 . Each member· of the unit staff shall meet or exceed the minimum qualifications.of ANSl-N18. ~-1971 for cooiparable posftlona, except

1. The. RadlatiOO Protection Manager, who shall meet or exceed the qualification•~ Regulatory Gulde 1.8, September 1975.

2. The education and experience eligibility requirements for lieensed · operatora shall meet or exceed the guidelines outlined by the National Academy for Nuclear Training (NANT). which have been found acceptable by the Nuclear Regulatory Commission (NRC) for meeting 10 CFR 55.31 and have been incorporated into applicable station training procedures.

5.3.2 For the purpose of 10 CFR 55.4, ~licensed Senior Reactor C)penm (SRO) and a licensed Reactor Operator (RO) are those indMduala who, In addition to meeting the requirements or TS 5.3.1, perform the functions described in 10 CFR 50.54(m).

' " . ~· . : . . . . -

. '

. . . .. · , .

McGuire Units 1 and 2 5.3-1 Amendment Nos. 276, 256 I·


5.5 f!r2srama and Marnrars

The following programs shaD be eitabllshed; implemented, and maintained. ' .. ,:. . ..

5.5.1 Offsite Dose Qalcu!at!on Manual <QQCM> .. ·

The ODCM ah811 contain the methodology and parameters used in the calculation of offaite dosel resulting frQm radioactive gaseous and liquid . effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpolnts, and in the conduct ·of the radiological environmental monitoring program. · · · ·

' . Licensee Initiated Changea to the ODCM: ·

. . -a. Shall be documented and records of reviews performed shall be retained.

This documentation ehall contain: ·

1. sufficient lnfonnation to support the change( a) together with the ·appropriate_ analysea or evaluations justifying the change(s), and

2. • determination that the change(a) do not adversely impact the accuracy or reliability of effluent, dose, or aetpoint calculations:

b. Shall become effective after the approval of the Plant Manager or · Radiation Protection Manager; and

c. Shall be submitted to the N~ in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release ·Report for the period of the report k1 which any change in the ODCM was made.-· Each change ahan be tdentifled by marttingl In.the margin of the affected pages, ctearty indicating thll areaof-the-page that waa changed, anchhall indicate the date (I.e., month end year) the change W88 implen'tented.

5.5.2 ContSinO;Jeot .... A Rate TestjOg Pr9st1m . . .

A program shall be •bulhed to !mp1ement the leakage rate testing of the contalr\roent as required bY.10 CFR. 50.54(0) and 10 CFR 50, Appendix J, Option B, al modified by approved exem~. ·This program ~II be in accordance with the guidelln~ contained in R~ulatory Guide 1.163, "~nee-Based COntainment Leak-T~ Pi'CgrriJ1'.'," d~ ~mber 1995, as modified by the foUow111g ext:eptions: . . . ' .

: . · ... NEI 94-01-1995, Section 9.2.3: ·The first Type A test performed after the May 27, 1993 (Unit 1) and August 20, 1993 (Unit 2) Type A test shall be performed no later than plant restart after the End Of Cycle 19 Refueling Outage (Unit 1) and August 19, 2008 (Unit 2); · and

. I

McGuire Units 1 and 2 5.5-1 Amendment Nos-.. 276, 256 I


5. 7 Hij!h Radiation Area

5.7.1 Pursuant to 10 CFR 20, paragraph 20.1601(c), in lieu of the requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the Intensity of radiation ls > 100 mrem/hr but s 1000 mremlhr. at 30 cm ( 12 in.) from the radiation source or from any surface which the radiation penetrates, shall be banieaded and conspicuously posted as a high radiation area and entrance thereto shell be controlled by requiring iuuanee of a Radiation Wortt Permit (RWP). Individuals qualified In radiation protection procedures {e.g., Radiation Protection Technicians) or personnel continuously escorted by such Individuals may be exempt from the RWP issuance requirement during the performance of their assigned dutiea In high radiation areas with exposure rates s 1000 mremlhr, provided they are otherwise following plant radiation pi'otectlon procedures for entry into such high radiation areas.

Any individual or group of Individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a A rac:riation monitoring device that continuously Indicates the radiation dose rate In the area. · ·

b. A radtatiOn monitoring device that continuously Integrates the radiation dose rate in the area and alarms when a preset integrated dose is receNed. Entry into such areas with thia monitoring deviCe may be made after the dose rate levels in the area have been established and personnel are aware of them.

c. An Individual qualified in radiation protection procedure& with a radiation dose rate monitoring device, who is responsible for providing positive control over the actfvitiel within the area and shall perform penodic radiation surveillance at the frequency apecified by the Radiation Protection Manager in the RWP.

5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels > 1000 mrem/hr at 30 cm (12 in.) from the radiation source or from any surface which the radiation penetrates shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the adminiStrative control of the Shift Manager, Radiation Protection I · Manager, or his or her designee. Doore shall remain locked except during periods of ac:cess by personnel under an approved RWP that shall specify the dose rate levels In the immediate work areas and the maximum allowable stay times for individuals In those areas. In lieu of the.stay time specification of the RWP, direct or remote {such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

(continued)

McGuire Units 1 and 2 5.7-1 Amendment Nos> 276, 256 I

ATTACHMENT TO LICENSE AMENDMENT NO. 389

RENEWED FACILITY OPERATING LICENSE NO. DPR-38

DOCKET NO. 50-269

AND


RENEWED FACILITY OPERATING LICENSE NO. DPR-47

DOCKET NO. 50-270

AND


. 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

Lic,enses DPR-38, page 3 DPR-47, page 3 DPR-55, page 3

TSs 5.0-1 5.0-2 5.0-3 5.0-4 5.0-5 5.0-7

Licenses DPR-38, page 3 DPR-47, page 3 DPR-55, page 3

TSs 5.0-1 5.0-2 5.0-3 5.0-4 5.0-5 5.0-7

- 3 -

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 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 iT1 (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. 389

\

- 3 -


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

C.

The Technic.al Specifications contained in Appendix A, as revised through Amendment No. 391 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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 ~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 rnade available at transmission or sub-transmission voltage by one electric system to another.


Renewed License No. DPR-47 Amendment No. 391

- 3 -


The llcensee is authorized to operate the facility at steady state reactor core power. levels not in excess of 2568 megawatts thermal.

8. Technical Specifications

The Technical Specifications contained in Appendix A, as revised through Amendment No.3QO .are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specif~cations.

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

Applicant makes the commitments contain.ed 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 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.


Renewed LicensP No. DPR-55 Amendment No. 390

· 5.0 ADMINISTRATIVE CONTROLS

5.1 Responsiblll'X

ResponSlbiUty 5.1

5.1.1 The Plant Manager sttett be responslbfe for overall plant operation and shall delegate in writing the succession to this responslbilJty during his absence.

. '

The Plant Manager or hlnSeslgnee shall approve, prior to 1mplementation, each proposed test. experiment or modlfic:atior) to syatems or. equipment that affect nuclear safety.

5.1.2 The Control Room Supervtsor (CRS) sh811-be responsible for the control room command function. During any absence of the CRS from the control room while the unit is in MOOE·· 1,. 2, 3, or 4, an lndlvidUal :[other than the Shfft Technical · Advisor (STA)) with an active Senior Reactor Operator (SRO)'Ucenae shall be designated to assume the c:ontrot roam·commanct function. During any absence of the CRS from the. cOntrol room whH& the unit la in MOOE 5 or 6, an individual with an active SRO license or Reactor Operator lioense shall be designated to assume the control room command function. · ·

. ,• , .. . . . .. . .

.•'

: ..

' ..

OCONEE UNITS 1, 2, & 3 5.0-1 ArnendrnentNos.389,391,390 I

Organization 5.2

5.Q ADMINISTRA1'.1~ CONTROL$.·

5.2 orsanization ,.

5.2.1 . . . . ~ .

Qnsjtl and Offl!tg QmanptlQns ·, .· ... '

.. Oneite and offslte organiZationa shall be establiShed for unit operation and corporate management, respectively. T_he onsite and offsite organizations shall Include the positions for activities affecting safety of the nuclear pawer plant.

. .

a. Lines of authortty, responaibiHty;i and communication Shaff be defined and established throughout highest management level&, intermediate levels, and all opef8ting organization positions. These relationships shall be documented and updatect, as appropriate, .1n organlZation chalt&, functional descriptions of departmental responsibilities anct relationships, and job descriptions for key peraonnet positions, or in equivalent forms of documentation. These requirements shall be documented In the UFSAR;

b. The Plant Manager shalt be responsible for overatl eafe operation of the plant and shall have control over those onaite actMties necessary for safe operation and maintenance of the plant; .. " ·

c. The Vice-President, Oconee Nuclear Site, shall have re9P0nslblllty for overall pl8nt nuclear safety .and shall take any measures needed to ensure acceptable p8riormance·of the staff In operating, maintaining. and providing technical suj>Pert to the plant to ensure nuclear safety;

d. The Chief Nuclear .Officer will be th8 ·senior Nuclear Executive and have I · corporate responslbiflty for overall nuclear safety; and

e. The individuals who train tt,e operating staff, carry out radiation protection, or perform quality assuraice functions may report to the appropriate onsite manager; however, theee individuals shall have sufficient organizational freedom to ensure their independence from operating pressuf98.

5.2.2 Unit Staff

The unit staff organization shall include the foHowing:

a. A non-licensed operator shall be onsJte for each reactor containing fuel and an additional norMlc:ensed operator shall be onsite for each control room from which a reactor la operating In MODES 1, 2, 3, or 4.

OCONEE UNITS 1, 2, & 3 5.0-2 Amendment Noa. 389, 391 , 390 I

Organization . 5.2

5.2 Organization

5.2.2 Unit Staff (continued)

b. At teast one licensed Reactor Operator (RO) per unit shall be present In the control room· when fuel Is in ·ttie ructor. In addition; white the unit is in MODE 1, 2, 3,· or 4, at least :one licensed Senior Reactor Operator (SRO) ·•hall be present In the control room ..

c. Shift cmN composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(1) and 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours in order tO aC::commodate unexpected absence of on-duty · shift CfflN members provided Immediate action is taken to restore the shift CfflN composition to within the minimum requirements.

d. A Radiation Protection Technician shall be on site when fuel is In the reactor. The position may be vacant for not more than 2 hours, In order to provide for une>cpeeted absence, provided Immediate action Is taken to flll the required position.

e. Deleted.

f. The Operationa ~nager or Assistant OperationS Manager - Shift shall hold an SRO license.

g. The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Manager in the areas of thermal hydrauliel, reactor engineering, and plant analysis with regard to the safe operation of the unit. In addition, the STA shall meet the qualifications specified by the Commission Policy ~tement on Engineering Expertise on Shift. -

OCONEE UNITS 1, 2, & 3 5.0.3 Amendment Nos. 389, 391 , 390 I

5.2 Organization

s.2.2 Unit stiff (continued)

Organization 5.2

· h.: : _,The ·.cl~lifi~ man~ necessary for lilCh~vlog &Jtemate.ahutdown using the Standby Shutdown Facility (SSF) wiH be available at the plant at all times. The manpower i1eceiSary to operate the SSF will be exclusive of the fire brigade and the minimum opetBtlng shift that is required to be present In the Control Room ..

. ·. · .. .;

OCONEE UNITS 1, 2, & 3 5.<M Amendment Nos. 389_,391,390 I


s.3 Unit Staff Qualifications · . .

. Unit Staff QuaHflcatlons 5.3

5.3.1 Each member of the unJt staff shall meet or exceed the minimum qualifications described in Section 4 of'AN$1/A~S-3.1-1978, "Selection and Training of Nuclear Power Plant Personnel'' except:

1. The Operations Manager shall have a minimum of eight years of responsible nuclear or fossil station experience, of which a minimum of . three years &hall be nudear etatlon e>eperience. A maximum of two years of the remaining five yeara of e>eperience may be fulfilled ey academic

· training, or A9fated technical training, on a one-for-one time basis. \

2. The Aalistant O~ons Manager - Shift lhall have a minimum of eight years of respons1t)1e nuclear or fossil etatlon experience; of which a . minimum of three yeara shall be nuclear station experience. A maximum of two years of the remaining five years of ~xperience may be fulfilled by academic training, or related technical training on a one-for-one time basis.

. . 3. The education and experience eligibility requirements for licensed

operators shall meet or exceed the guidelines outlined by the National Academy. for Nudear Training (NANT), which have been found acceptable by the Nuclear Regulatory Commission (NRC) for meeting 10 CFR 55.31 end have been lncorpOrated into epp11cable station training proc:edurH.

5.3.2 For the purpose of 10 CFR 55.4, a licented Senior Reactor Operator (SRO) and a llcenMd Reactor Operator (RO) .are th08$ individuals who, in addition to meeting the requirements of TS· 5.3.1, :perfonn the functions described In 10 CFR 50.54(m).

OCONEE UNITS 1, 2, & 3 5.1).5 Amendment Nos.3$9, 391 , 390 I


5.5 Prcgrams and Manuals

Programs and Manuals 5.5

The fottowlng programs lhaU be established, Implemented, end maintained.

5.5.1 Off!ito QoM ea1cu1at1oo Manual <OOCMl

The ODCM shall contain the methodology and parameters used In the calculation of offslte doses resulting from radJoactive gaseous and liquid effluents, in the calculation Of gaseous and liquid effluent monitoring alarm and · trip setpolnta, and in the conduct of the radiological environmental monitoring program.

Licensee Initiated changes to the ODCM:

a. ShaH be documented and records of revtewa perfonned shall be retained. Thia documentation shafl contain:

1. sufficient infonnation to support the change(&) together with the appropriate analyses or evaluations Justifying the change(•). and

2. a determination that the change(&) do not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shalt become effective after the approval of the Plant Manager or Radiation Protection Manager; and ·

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent

· Release Report for the period of the report in which any change in the ODCM was made. Each change shall be Identified by markings In the margin of the affected pages, clearty Indicating the area of the page that was changed, and shalt indicate the date (i.e., month and year) the change was Implemented.

5.5.2 CoQt@jnmeot Lgkage Bate IestiDQ Program

A prog~ shall e8tablish the leakage rate testing of the containment as required by 10 CFR 50.54(0) and 10 CFR 50, Appendix J, Option B. as modified by approved exemptions. The next Unit 1 ILRT following the December 8, 2003 test shall be performed no later than March 8, 2015. The next Unit 2 ILRT following the May 29, 2004 test shaJI be performed no later than December 29, 2015. The

OCONEE UNITS 1, 2, & 3 5.0-7 Amendment Nos. 389, 391 , 390

l



SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION

RELATED TO

AMENDMENT NO. 273 TO RENEWED FACILITY OPERATING LICENSE NPF-35;




AMENDMENT NO. 389 TO RENEWED FACILITY OPERATING LICENSE DPR-38;

AMENDMENT NO. 391 TO RENEWED FACILITY OPERATING LICENSE DPR-47; AND

AMENDMENT NO. 390 TO RENEWED FACILITY OPERATING LICENSE DPR-55;


CATAWBA NUCLEAR STATION, UNITS 1 AND 2

DOCKET NOS. 50-413 AND 50-414

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2

DOCKET NOS. 50-369 AND 50-370

OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3

DOCKET NOS. 50-269, 50-270, AND 50-287

1.0 INTRODUCTION

By letter dated July 21, 2014, Duke Energy requested changes to several sections of the Technical Specifications (TS), for the above Duke Energy Stations (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14212A502). Amongst the proposed changes, the amendment will revise TS Section 5.3 "Administrative Controls -Unit Staff Qualifications," to add a section indicating that licensed operator education and experience qualifications will meet or exceed the guidelines outlined by the National Academy for Nuclear Training (NANT). In addition, several other administrative and editorial changes were made to

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update organizational titles to more closely reflect the current respective organizations and to improve the formatting of the document.

2.0 REGULATORY EVALUATION

In March 1985, the NRC issued the Commission Policy Statement on training and qualification of nuclear power plant personnel which endorsed the training accreditation process and the NANT guidelines. In Generic Letter 87-07, "Information Transmittal of Final Rulemaking for Revisions to Operator Licensing - 10 CFR 55 and Conforming Amendments," dated March 19, 1987, and in NUREG-1262, "Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators' Licenses," published November 1987, the NRC indicated it would accept a facility's licensed operator training program if the facility certified in writing that the program was accredited and based on a systems approach to training (SAT). This certification would supersede the requirements of ANSI N18.1-1971, "Selection and Training of Nuclear Power Plant Personnel," and ANSl/ANS-3.1-1978, "Selection and Training of Nuclear Power Plant Personnel." Facility licensees were advised to submit a request to the NRC for an administrative change to their licensing documents to conform to their accredited program status.

In January 1992, the NRC published its proposed rule 10 CFR 50.120, "Training and Qualification of Nuclear Power Plant Personnel." The proposed rule/stated that, if adopted, the rule would supersede the Commission's Policy Statement on training and qualification of nuclear power plant personnel and would not result in any change to accredited programs. The Commission concluded that accredited programs, implemented consistently with industry objectives and

· criteria, would be in compliance with this regulation.

In April 1993, the NRC published its final rule on training and qualification of nuclear power plant personnel. The rule.requires nuclear power plant licensees to establish, implement, and maintain SAT-based training programs for nine non-licensed positions. Accreditation of these nine training programs is an acceptable means of meeting the requirements of 10 CFR 50.120.

In January 2001, the NRC published NRC Regulatory Issue Summary (RIS) 2001-1, "Eligibility of Operator License Applicants," to familiarize licensees with the NRC's current guidelines for the qualification and training of reactor operator and senior operator license applicants. RIS 2001-01 acknowledged that 10 CFR 55.31 (a)(4) allows the NRC to accept an application for an operator's license if the facility certifies that the applicant has successfully completed a Commission approved training program that is based on a SAT. In addition, RIS 2001-01 stated that: (1) a training program would be considered approved by the NRC when it receives or renews accreditation from the National Nuclear Accrediting Board (NNAB); (2) accreditation of operator training programs suggests that facilities are implementing the education and experience guidelines ~ndorsed by the NNAB; (3) NANT guidelines for education and experience outline acceptable methods f.or implementing the Commission's regulations; and (4) the staff encourages all facility licensees to review their requirements and commitments related to licensed operator and senior operator education and experience and to update their documentation (e.g., Final Safety Analysis Report, Technical Specifications, and training program descriptions) to enhance consistency and minimize confusion.

10 CFR 50.36(c)(5), "Administrative controls," states that administrative controls are the provisions relating to organization and management, procedures, recordkeeping, review and

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audit, and reporting necessary to assure the operation of the facility in a safe manner. Each licensee shall submit any reports to the Commission pursuant to approved technical specifications as specified in § 50.4.

3.0 TECHNICAL EVALUATION

3.1 Administrative Controls - Responsibility

The licensee has proposed to make conforming and clarifying changes to TS 5.1, "Responstbility," for Catawba, McGuire, and Oconee. Specifically, the following changes were proposed:

All Sites • The title of Station Manager is replaced with Plant Manager

Catawba • The title of Shift Supervisor is replaced with Control Room Supervisor (CRS) • Replaces the title of Shift Work Manager.with Shift Technical Advisor (STA) • Add the term "relief" to describe the SRO, when acting in a relief function • Relocates the requirement that the STA have an Senior Reactor Operator (SRO) license

when assuming the control room command function and clarifies that it must be active • In Section 5.1.1, replaces SRO duties with CRS duties

McGuire • The term "Reportability" is corrected to read "Responsibility" • The title of Control Room SRO is replaced with CRS • Relocates the requirement that the STA have an Senior Reactor Operator (SRO) license

when assuming the control room command function and clarifies that it must be active • In Section 5.1.1, replaces SRO duties with CRS duties

Oconee • A new section 5.1.2 is added that is identical to those currently contained in the MNS and

CNS TSs.

The proposed changes administratively align the terminology for positions of equivalent responsibility between the three sites and do not reduce the required staffing of the control room.

For Oconee, the proposed to addition of a description of the responsibility for the control room supervisor (CRS), including delegation of responsibility requirements in the event of an absence of the CRS aligns the Oconee TSs with Catawba and McGuire. Additionally, the requirements specified for an absence of the CRS are appropriate.

The licensee also proposed editorial corrections, which are acceptable.

Based upon the aforementioned considerations, the NRC staff finds the proposed changes to TS 5.1 to be acceptable.

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3.2 Administrative Controls - Organization

The licensee has proposed to make conforming and clarifying changes to TS 5.2, "Organization," for Catawba, McGuire, and Oconee. Specifically, the following changes were proposed:

All Sites "• The title of Station Manager is replaced with Plant Manager • The title Group Vice President Nuclear Generation Department is replaced with Chief

Nuclear Officer

Catawba • The title Operations Superintendent is replaced with Operations Manager • The title Shift Operations Manager is replaced with Assistant Operations Manager - Shift • The title Shift Supervisor is replaced with Shift Manager • The title Shift Work Manager is replaced with .STA ·

McGuire· • The title of Control Room SRO is replaced with Shift Manager

Oconee • , The term "health physics" is replaced with "radiation protection" • The heading "Station Staff' is replaced with "Unit Staff' • Adds an introductory statement to the unit staff composition list • The title Operations Superintendent is replaced with Operations Manager • The title Shift Operations Manager is replaced with Assistant Operations Manager - Shift • The title Shift Work Manager is replaced with STA

The proposed changes administratively align the terminology for positions of equivalent responsibility between the three sites and do not .reduce the associated responsibility. Removal of the designation of "corporate" responsibility for nuclear safety from the site vice president role is appropriate because the site vice president position is specific to a site and the corporate responsibility for nuclear safety is maintained by the Senior Nuclear Executive.

Based upon the aforementioned considerations, the NRC staff finds the proposed changes to TS 5.2 to be acceptable.

3.3 Administrative Controls - Station Staff Qualifications

The licensee has proposed to make conforming and clarifying changes to TS 5.3, "Station Staff," for Catawba, McGuire, and Oconee. Specifically, the following changes were proposed:

All Sites • The term Station Staff is replaced with Unit Staff • Adds. a requirement that each member of the unit staff shall meet or exceed the guidelines

outlined by the National Academy for Nuclear Training • A paragraph is added clarifying the role of ROs and SROs • A colon is added to the end of the introduetory paragraph for TS 5.3.1

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Oconee • The titles Operations Superintendent and Shift Operations Manager are deleted from the

list header • ·· The title Operations Superintendent is replaced with Operations Manager • The title Shift Operations Manager is replaced with Assistant Operations Manager - Shift

The licensee stated in its letter dated July 21, 2014, that the licensed operator training programs are based on a SAT and are accredited by the NANT. Since 10 CFR 55.31 (a)(4) allows the NRG to accept an application for an operator's license if the facility licensee certifies that the applicant has successfully completed a Commission-approved training program that is based on a SAT in lieu of providing details of the applicant's education and experience, this change meets the 10 CFR 55.31 (a)(4) requirements to apply for an operator's license and ensures the facility licensee maintains administrative controls that assure the operation of the facility in a safe manner by properly qualified licensed operators. Therefore, the proposed change to add a reference to the NANT is acceptable.

The proposed conforming and clarifying changes to TS 5.3, "Station Staff Qualification.s," for Catawba, McGuire, and Oconee administratively align the terminology for positions of equivalent responsibility between the three sites and do not reduce the associated responsibility.

Based on the above discussion, the NRG staff concludes that the proposed revision is consistent with 10 CFR Part 55 and does not adversely affect nuclear safety or plant operations. Therefore, the NRG staff concludes that the proposed changes to TS Section 5.3 are acceptable.

3.4 Administrative Controls - Programs and Manuals

The licensee has proposed to make conforming and clarifying changes to TS 5.5, "Programs and Manuals," for Catawba, McGuire, and Oconee. Specifically, the following changes were proposed:

All Sites • The title of Station Manager is replaced with Plant Manager • The title Radiation Protection Manager is added to those who can approve changes to the

ODCM

The proposed changes administratively align the terminology for positions of equivalent responsibility between the three sites and do not reduce the associated responsibility. Therefore, the proposed changes to TS 5.5 are acceptable.

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3.5 Administrative Controls - High Radiation Area

The licensee has proposed to make conforming and clarifying changes to TS 5.7, "High Radiation Area," for Catawba and McGuire. Specifically, the following changes were proposed:

Catawba • The title of Shift Supervisor is replaced with Shift Manager • The Radiation Protection Manager is added to those who can maintain keys for doors to .

high radiation areas.

McGuire e The title of Operations Shift Manager is replaced with Shift Manager

The proposed changes administratively align the terminology for positions of equivalent responsibility between the three sites and do not reduce the associated responsibility. Therefore, the proposed changes to TS 5.7 are acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the North Carolina and South Carolina State officials were notified of the proposed issuance of the amendments. The State officials 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 1 O 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 November 12, 2014 (79 FR 67199). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). 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.

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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: B. Green . G. Lapinsky G. E. Miller

Date: February 12, 2015

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

Sincerely,

/RA/

G. Edward Miller, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos. 50-413, 50-414, 50-369, 50-370 50-269, 50-270, and 50-287

Enclosures: 1. Amendment No. 273 to NPF-35 2. Amendment No. 269 to NPF-52 3. Amendment No. 276 to NPF-9 4. Amendment No. 256 to NPF-17 5. Amendment No. 389 to DPR-38 6. Amendment No. 391 to DPR-47 7. Amendment No. 390 to DPR-55 8. Safety Evaluation

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ADAMS Accession No. ML 15002A324

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