ML11158A209

Issuance of Amendments Changes to the Emergency Plans

ML11158A209
Person / Time
Site:	Oconee, Mcguire, Catawba, McGuire
Issue date:	07/29/2011
From:	Stang J Plant Licensing Branch II
To:	Glover M Duke Energy Carolinas
Stang J, DORL/LPLII-1, 415-1345
References
TAC ME4446, TAC ME4447, TAC ME4448, TAC ME4449, TAC ME4450, TAC ME4451, TAC ME4452
Download: ML11158A209 (35)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 29, 2011 Mr. Michael R. Glover General Manager, Nuclear Support Nuclear Generation Duke Energy Carolinas, LLC P.O. Box 1006 Charlotte, NC 28201-1006

SUBJECT:

CATAWBA NUCLEAR STATION, UNITS 1 AND 2, MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, AND OCONEE NUCLEAR STATION, UNITS 1,2, AND 3, ISSUANCE OF AMENDMENTS REGARDING CHANGES TO THE EMERGENCY PLANS (TAC NOS. ME4446, ME4447, ME4448, ME4449, ME4450, ME4451, AND ME4452)

Dear Mr. Glover:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 265 to Renewed Facility Operating License NPF-35 and Amendment No. 261 to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, Amendment No. 263 to Renewed Facility Operating License NPF-9 and Amendment No. 243 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2, and Amendment Nos. 376, 378, and 377 to Renewed Facility Operating Licenses DPR-38, DPR-47, and DPR-55, for the Oconee Nuclear Station, Units 1, 2, and 3, respectively. The amendments approve changes to the emergency plans in response to your application dated July 28, 2010, as supplemented March 3, 2011.

These amendments approve changes to each station emergency plans to allow changes to the minimum staffing requirement during emergencies.

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.

M. Glover - 2 If you have any questions, please call me at 301-415-1345.

Sincerely, John Stang, Senior 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. 265 to NPF-35

2. Amendment No. 261 to NPF-52

3. Amendment No. 263 to NPF-9

4. Amendment No. 243 to NPF-17

5. Amendment No. 376 to DPR-38

6. Amendment No. 378 to DPR-47

7. Amendment No. 377 to DPR-55

8. Safety Evaluation cc w/encls: Distribution via Listserv

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION DOCKET NO. 50-413 CATAWBA NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 265 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 the Duke Energy Carolinas, LLC, acting for itself, and North Carolina Electric Membership Corporation (licensees), dated July 28,2010, as supplemented March 3,2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2

2. Accordingly, the Renewed Facility Operating License No. NPF-35 is amended as indicated in the attachment to this license amendment. The license is amended to authorize changes to the Catawba Nuclear Station Emergency Plan as set forth in the application for amendment by the licensee dated July 28, 2010, as supplemented by letter dated March 3, 2011, and as evaluated in the NRC staffs safety evaluation for this amendment.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION EL~

Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-35 Date of Issuance: JJly 29, 2011

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC NORTH CAROLINA MUNICIPAL POWER AGENCY NO.1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 261 Renewed License No. NPF-52

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

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

Renewed Facility Operating License No. NPF-52 filed by the Duke Energy Carolinas, LLC, acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licensees), dated July 28,2010, as supplemented March 3, 2011, 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 (ij) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2

2. Accordingly, the Renewed Facility Operating License No. NPF-52 is amended as indicated in the attachment to this license amendment. The license is amended to authorize changes to the Catawba Nuclear Station Emergency Plan as set forth in the application for amendment by the licensee dated July 28, 2010, as supplemented by letter dated March 3, 2011, and as evaluated in the NRC staff's safety evaluation for this amendment.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~/~

Eric J. Leeds, Director Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-52 Date of Issuance: July 29, 2011

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 263 Renewed License No. NPF-9

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

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

Renewed Facility Operating License No. NPF-9, filed by the Duke Energy Carolinas. LLC (licensee). dated July 28. 2010. as supplemented March 3, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954.

as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public. and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

- 2

2. Accordingly, the Renewed Facility Operating License No. NPF-9 is amended as indicated in the attachment to this license amendment The license is amended to authorize changes to the McGuire Nuclear Station Emergency Plan as set forth in the application for amendment by the licensee dated July 28,2010, as supplemented by letter dated March 3, 2011, and as evaluated in the NRC staff's safety evaluation for this amendment.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION E:::;(~

Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-9 Date of Issuance: July 29, 2011

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 243 Renewed License No. NPF-17

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

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

Renewed Facility Operating License No. NPF-17, filed by the Duke Energy Carolinas, LLC (the licensee), dated July 28,2010, as supplemented March 3, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations setforth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2

2. Accordingly, the Renewed Facility Operating License No. NPF-17 is amended as indicated in the attachment to this license amendment. The license is amended to authorize changes to the McGuire Nuclear Station Emergency Plan as set forth in the application for amendment by the licensee dated July 28, 2010, as supplemented by letter dated March 3, 2011, and as evaluated in the NRC staff's safety evaluation for this amendment.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~LZ~

Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-17 Date of Issuance: July 29, 2011

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. 376 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 the Duke Energy Carolinas, LLC (the licensee), dated July 28,2010, as supplemented March 3, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2

2. Accordingly, the Renewed Facility Operating License No. DPR-38 is amended as indicated in the attachment to this license amendment. The license is amended to authorize changes to the Oconee Nuclear Station Emergency Plan as set forth in the application for amendment by the licensee dated July 28, 2010, as supplemented by letter dated March 3, 2011, and as evaluated in the NRC staffs safety evaluation for this amendment.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION C:~:?

Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-38 Date of Issuance: July 29, 2011

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. 378 Renewed License No. DPR-47

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

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

Renewed Facility Operating License No. DPR-47 filed by the Duke Energy Carolinas, LLC (the licensee), dated July 28,2010, as supplemented March 3, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (I) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2

2. Accordingly, the Renewed Facility Operating License No. DPR-47 is amended as indicated in the attachment to this license amendment. The Ircense is amended to authorize changes to the Oconee Nuclear Station Emergency Plan as set forth in the application for amendment by the licensee dated July 28, 2010, as supplemented by letter dated March 3, 2011, and as evaluated in the NRC staff's safety evaluation for this amendment.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~/~

Eric J. Leeds, Director Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-47 Date of Issuance: July 29, 2011

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. 377 Renewed License No. DPR-55

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

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

Renewed Facility Operating License No. DPR-55 filed by the Duke Energy Carolinas, LLC (the licensee), dated July 28,2010, as supplemented March 3, 2011, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

- 2

2. Accordingly, the Renewed Facility Operating License No. DPR-55 is amended as indicated in the attachment to this license amendment. The license is amended to authorize changes to the Oconee Nuclear Station Emergency Plan as set forth in the application for amendment by the licensee dated July 28, 2010, as supplemented by letter dated March 3, 2011, and as evaluated in the NRC staff's safety evaluation for this amendment.

3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~/~

Eric J. L L . Dire:or Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-55 Date of Issuance: July 29, 2011

ATTACHMENT TO LICENSE AMENDMENT NO. 265 RENEWED FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO. 261 RENEWED FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License Pages Licenses Pages NPF-35, page 4 NPF-35, page 4 NPF-52, page 4 NPF-52, page 4

- .:)

The Technical S""f,callons contained In Appendix A, a. revised lnrougr; Amendment t>Jo. 265Nh1ch are anached hereto, are hereby incorporated inlo this renewec opt:ralU 19 license Duke Energy Carolinas. LLC snail operate trle facility In aCcordance wnh Ihe Technical Specifications (3) ~ Final Saletv Anai'l§ls ReDon The Updated Final Safety AnalYSIS Repon supplement submitted pursuanl to 10 CFR 54.21(d), as revised on December 16,2002, describes certain future activities to be compieted before the period 01 extended ooeratlon DUKe shal' complete these activities no later than December 6, 2D24, and shall notily Ihe NRC In writing wnen implementation of these actlvitres is complete and can be verified by NRC Inspection Tile Updated Final Salety AnalysIs Report supplement as revised on December 16. 2002. described above. Shall be rncluded In the nexl sCheduled update to the Updated Finai Safely Analysis Report required by 10 CFR 50 71(e)(4), (ollowlng Issuance of this renewed operating license. Untilll-ja\

update is complete, DuKe may make Changes to lne programs described In such supplement without prior Commission approval, provloed that Duke evaluales each such cha'lge pursuant to Ine crltena sel forth Jrl : C CFR 5059 and otherwise compiles with the reqUIrements in that section

(~) Ant Itrust Cond it 10 ns Duke Energy Carolinas, LL C 5.'1all comply With the anti1rusl conditions delineated In ApDer-,di>: C to this renewed operating license (5) Fire Protection Prooram (Sedlon 9.5 1, SER, SSER #2. SSER #3, SSER #4, SSER #5)'

Duke Energy Carolinas, LLC sha'f implement and mSlntai'lln effect all provIsions Of Ihe approved fire protedlon program as described In the Updated Final Safety Analysis RepOn, as amended. for tne facility and as approved in the S:::'R 1hrough Supolemenl 5. subject to the fOllOWing prOVISion Tile licensee may make changes to the approved fIre protection program without prior approval of the Commission only if those changes WOUld not adversely affeci Ine apil:ly \0 achieve i!nd maintain safe snutoDwn In 1fJe event of a fire

'Tne parenlnetlcai notation follOWing lhe hUe of :,ollS renewed operating license con dillon denotes Ihe section of the Safely Evaiuation Repoi1 andior Il:; supplement w~erein this renewed license condition is discussed Renewed Licen::;e No. NPF*35 Amenomer: No. 265

(2} TSlChn!ca! SpPglnlllJliona

.The T~I:SI'""""Ii ....tonS tui\MIned irl Ap",ndu. A, 8$ ~ ~ .. .

AmtmOm.er4 He m1 WhIctlare~,"l1Ito, ...

ht ntf'IOMIII1 Ope~..,.., o.a.

'III~ In .cconkIAOIJ wtrI'l1he TIICtniaIII ~bn.,

AI. "CDI'JIOrIttd Into E'l'IfVY CttroU"'" LlC"'~ tIpIIfIie'tIlIf

-I

.(3) ypd!J.ilf B!!!! S!lety,AnlltWhrR!P2tl

,*The U"c:Ia1eO AMI seMty AnaIyS. RepOrt 1Up~ ~ "'~l \0' 10 CFR ~.21(G), all nm.eg ~ Dill>>!ri:IIt1 1., 2D02,*dnctbft III:ftvIUR 10 IJIt OOilaplG*1 betmh ~ Of mendtId ~ t>uIW.w.

_In IUUI com*

• IhP. ilcCtvItleI nil .... tt*I ~ ?4. 2021, end 1.1 notify thll NRC In wr11ing WIlen ~ 01 \hose

'W'It~ by JotRC npeatDn, .

.CUvII.I., III CI:Jm'*- anc1 CWl De The UpdaWd .Flnil S.taty Arelflll"~ liuw!emt'm ., I1I'IIIIied 0t'1 ,

Oec:ember '8. 1002. ~ abow. IIhd,. InGlud.o 1'1 Ik, npl-t::hOduie(1 1.1"'10 \1'1e IJpcIIIflKS fNJ Sllttity ~~ti ReP9f'! r-quAd tIy 10 CFR SO.11(eX4}.lolDwlntl iOlMl"lCe'ot Ihr. I1Infted opltnlllllg liowIwIt. ,UnGllhlll ,

~Io iJ comp"". DIM m.Y~I. eta. . to1he ",\9.,.

.uprpitlMnt without prior Commiulon ~w/, pI"OYItIeclllW DuIut...... tuIIt..

ftlaibtd," lUt;n each ll.ll:tl tn.nge. P\n~ \Q the nn. ..1fortlln 10 CFR 50.~" and o1heJWI.. ~ wtth tbe ~ if thai Ht1icn.

(.:I) MI\!LYI1 eormnIQI'III DuU energy CaI'oiIwa, LlC

• compty wffh the anIiIrusl ~"' deIinBaIed in Appendl>>: C 10 thl. rel'1li'wed ~Ing license.

C~) ,E!!:!f.mmc!!9" PiogrOl'rt(~C\lon 9.!U, SER. SSER~. S$ER #3, 5SERJ4.

S5ER~"

Duke Enef'8)' Cia"*,*" LlC 1n.K Imoiltmant end m"~ In tHf~ .. ~lonll a( the DPPJ'CMld lint pI:otet:tion Pl"Cl{nn; ** ~ In . . \hIciIJ-" Fi'eI.SeI.ty Anal~ R.port It'll' _ndIod; lor hi hlelllty' WId . . IIP~ In '!til SE~ Ihr;wsIh SuppI_t 5, .ub)ec:t II> Ihoo 1.oI1ooMnO p""..... I<m' , ..

. Tn" llcermHllTHI)f ITIIIQ ~, 10 ni* .,pprvllM!h Pr:oleellO!1 Il~

wtthOUI pnor apporoVIII or tn. Cwmnlnlon'onIy 11 th~ c:n.ngtpf would not ar:tveraely _neel'".., 1Ib"1.,. 10 .t:h1.... .,0 mlllnl.ln .IIIe IIh\J1~ ~ the

_n'~II,".

'Tile ".,.,..nll'ellCal nDllltlCn 1ol11:JW\ng tile un., el11111 r~'d O~I"III",g 1iCem., \lOI"'IdIIgn denote'l .,., IIiIICSJOn t:I !he Sahtty EV6hMJoo ~ IIt1O/OC'" lIS '1J~lemenlt whIIflIlI'l l1'li1 TW!PMId ~me t;;QOd1\1cm ~ araCi.lntlC!,

Renewed l~~ Nc, NF'F*5?

AmtmcIment Nt' 261

ATTACHMENT TO LICENSE AMENDMENT NO. 263 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 243 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Renewed Facility Operating Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License Pages License Pages NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3

• 3 (4) Pursuant 10 the Act and 10 CFR Pan:. 30,40 and 7D," F9C8Mr.. I>>"en a nd use In amounllas requln!Jd Wrt byproduct, source Of ,pedal nucilrilr rna.rial without res..x:UQn to c:hem'c:laIOf physal form, tit sam,*, lnalysis or mtrurn.nt ca\lbrltlon or al5sociatltd wtlh radloactiw apparau or components:

(5) PurausntlO the Act .nd 10 CFR Parts 3D, 40 and 70, 10 possess, but I1QI separate, such bypn)d~ and IIPOClal ru;ear rT1tlerials as mrt be producecl by the operation of McGuIre Nucear SlBlion, Un~6 ,. and 2" and' (15) ~uant to the Act and 10 CFfI Parts 30 and 40,' to 1lKlOMt, possess and procellS for relene or transler IIUCh byproduct melenai BS mllY be producecf by the Dul'.e Tralnfng "TBChnology Center.

C. is Th~ renewed operating license ShBII bedeemooto contain and lIUbject 10, the condlt/onll specified In the Commbsaa regulations sot fol1t1ln , 0 CFR Chapter

) and is lubject to allapplcab6e provtsions of the Act ancf to the rulell, or regulaUom, and or~ ollhe COmmlailon now hereafter f1 effect: and 1$

~ject to the aclditlonal condltlonl spec!t'ed or incorporated below:

(1 ) Maximum PQwer Level The ficensetl \, authorizDd to oprerate the fac[fily at a reBCtor core fuji steady Itat'1 ptrNer level C1f 3411 !ne9awartl thermal (100%).

(2) Tochnlsoal Spec~193tiQns The Tecm'cal Sr--tf\callo~ contaIned in AppmcUx'A, 8$ revised through Amendment No. X>.3 ,are ~ Incorporated lnto this renowed operating rlCense. The licensee shall operate !he laclltly In aceoroance with the Tee hn leal S pec/flcatlons.

(3)  !,JpsH!t!d Final Safety Anal~i3 Report

• The Updated Finel Salety AnoalyJls Report lIu~nt sv,,",itled PUT'SI.J* .,t to 10 CFR ~.Z'(d). 115 ",v~ed on OococmbOr 15. 2002, 00ltcr1~ c~ri.airl lutu~ activitJII5 10 be completed befora the period of ~ op.nII~n.

Duke Ihall complete lhuso acllvlm no later Ihan June 12,2021. and shal noutv the NRC in Wltllng when Irnpememat10n of the&e ac::tlvfl~ 1$

complete and can be verlf)ed by NRC ~pec\ion.

The Upda~d Final Salety AnlllysisRupol1 5upplclment sa reviled On Dec.m~r 1e, 2t)02, dc$C~ 8tX:7V1r, shall to. included ~ the next scheduled update 10 the Updated Final Salety Anatysta Re!)Of'l TeQulr1tO Dr 10 CFR ~.71(eX4), following "6U8I'1Ce of this renewed aporutlng fteense.

Until thaI update Is complete, Duke may make ch8J9r.1 10 the pn:!grams de~cribed j'n such supplement wtIhout prior Commission approve!, proviDed that DUKe evaluate! each such change pursuant to the criteria :setIOr1h In 10 eFR 50.59 eOO othcrw~o comDI~ wt1h !he ~lilromonw In thOl sectIOn.

Re~wltd Liceme ~'c, loJoF.9 Amendment Nc. 263

(4) Pur.suant to the Act and 10 CFR ParU! 30,40 and 71}*.to 18CC1ve, pones!

and uae In amoun1.l a. /lIqulrod'any t?rProcluet, 10llrcD or If'IICIBI nQ8f me1of1l1 wtthcxrt restnc:Uon to Chemklal or ph)'Sk;a1 fann, for IIImpie 8n81)'11a or Instrument CIIIIHu!lon or asmclated wtth radioactive 'pp8l1tus or C'ompanents; (5) P\nuan\ to the A;t WId 10 CFR P.r= 30,40 ard 70, to POSlllelS$'~ bUl ric!

s~ate. sueh bypfoducta .ncrspeclal nucle.r material. as may be pn:xtuced' by the ClfJCI181lon of McGI.;ilre Nuclear Station, UMI , and 2; .nd, (6) Pursuant to Ihe Ac1 and 10 CFR'PertI 30 antS 40, to receive, po1IlSO'IJa am procell for reloalO or transfer such byproouct materialaa may bf:,

prodUced by the Duke Tratning and Technology Cenler.

C. Thill renewed operetJ"9IiC:en'Se ,hall be deemed to contain anCl5l1UbjD'C110 the condition. Ipec:l1lea In !he Commlsskm'a reVulatlonl Ie! fonh ., 10 CFR Chapter I and II subject to all applicable prOVlslonl 0' the ACt .nd to 1he rum,

~latio"" and ordel1 of the Commlulon now or hereaner In e1tect: Ind 15 subject to the addlUon8l ccndltlona 1I~lflod or Incorporated bek;Jw:

(') M,xlwum Powvr Lew)

The licensee Is alJ'tJ'llrized to operate the facitity .,a rea::tcr cont full steady stale po'MII' level of 34" megrawllttII thermal (100%).

(l) Ipcnnlcal s t!~tl0(l8

. Th, Technical SOAdflt:atlom eomalned In Appendix A, BS I1!!'Ilsed 1hrough Amendment No. 243 ate ha!llb)' Incorponttad into this I"OflOIttIed operating license, ,I ne lICensee shall operate tile WHy In uccordance with

!he Technical SpeelflCatJans.

(3) Updated Final ~fety AnI.Ilynls Reoor1 Tho Updated FIMI S.j6ty.Ana~jll Report .upplemenl ~bI'I'II'ned PtJ/l;Uilnl to 10 CFR 5C.'21(d). 8S rvvi:sod on December Hi. 2002, de,onbof, cartaln luturlJ activities 10 be eomplatad 1;Mrf1)", Vl1it ~r!o)I NRC InfpeC:llgn.

~ Updated FII'I8I Safety AmllY'6!' Repor1 lupplemenl at revl.tId On December HI, 2002, deacr1betl libow, lhan be Included In the neX!

,c:neduled update 10 !he Updated Fnel Safely Anatysla RGport roqulre<! by

, 0 CFR sO.r'(eX4}, follO'Wing Ia,uant:e of Ihls ranowed opentting license.

Until thet update Is compiete, Duke may make cMli"I91111 ID Ihe progralTll oe$C(ibeod In suCh supplement without prior CtIi'T'ImlSSlon approve I, prtJ~

that Duke avs1u.' eectJ fuch change pur.uant to the crlteria aet fOl1h In

'0 CFR 50,59, Blla othervwise eomplle, With the ntqul",men1.5 in thaI sec1lon.

Re"awll'd U~on5e No. NPF.P AmendmenlNo, 243

ATTACHMENT TO LICENSE AMENDMENT NO. 376 RENEWED FACILITY OPERATING LICENSE NO. DPR-38 DOCKET NO. 50-269 AND TO LICENSE AMENDMENT NO. 378 RENEWED FACILITY OPERATING LICENSE NO. DPR-47 DOCKET NO. 50-270 AND TO LICENSE AMENDMENT NO. 377 RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DOCKET NO. 50-287 Replace the following pages of the Licenses with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove License Pages Licenses Pages DPR-38, page 3 DPR-38, page 3 DPR-47, page 3 DPR-47, page 3 DPR-55, page 3 DPR-55, page 3

~ 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 Sr'~ifications contained in Appendix A, as revised through Amendment No. 316 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 nejghboring entities normally tend to serve the public interest. In addition, where there are net benefits to all partidpants. 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 111 (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 Licen;--p. Nt'!. DPR-3S Amendment No 376 I

-3 A. Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels 110t in excess of 2568 megawatts thermal.

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 378 are hereby incorporated in the license. The licensee shall operate the facility in acconJance 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 benefrts in a transaction if applicant recovers the cost of the transaction (as defined in 111 (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 Licensl. i.\c. DPR-47 Amendment No. 378

-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 377 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 benefrts 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}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 LicenSl'" No. DPR-55 Amendment No 377

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 265 TO RENEWED FACILITY OPERATING LICENSE NPF-35 AMENDMENT NO. 261 TO RENEWED FACILITY OPERATING LICENSE NPF-52 AMENDMENT NO. 263 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AMENDMENT NO. 243 TO RENEWED FACILITY OPERATING LICENSE NPF-17 AMENDMENT NO. 376 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 378 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-47 AND AMENDMENT NO. 377 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-55 DUKE ENERGY CAROLINAS. LLC 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 application dated July 28, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102160312), Duke Energy Carolinas, LLC (Duke, the licensee), as supplemented March 3,2011 (ADAMS Accession No. ML11200A348), requested changes to the Emergency Plans (EPs) for the Catawba Nuclear Station, Units 1 and 2 (Catawba), McGuire Nuclear Station, Units 1 and 2 (McGuire), and Oconee Nuclear Station, Units 1, 2, and 3 (Oconee).

- 2 The proposed changes would revise the EPs for the Catawba, the McGuire, and the Oconee, minimum staffing requirements during emergencies for site Radiation Protection (RP) personnel and Emergency Operations Facility (EOF) staffing. The requested changes include:

1. Increasing the response time requirement for the Technical Support Center (TSC) Dose Assessor position from 45 minutes to 75 minutes;

2. Changing the EOF access control function from a staffed position to a monitored card reader process;

3. Changing the composition of a Field Monitoring Team (FMT) from two RP Technicians to one RP qualified individual and a vehicle driver;

4. Changing RP staffing during emergency response events from RP Technicians to RP qualified individuals; and

5. Editorial changes to clarify the notations in the EPs to provide fleet-wide consistency.

The supplement dated March 3, 2011, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination as published in the Federal Register on September 7, 2010 (75 FR 54393).

2.0 REGULATORY EVALUATION

The regulatory requirements and guidance on which the NRC staff based its review are as follows:

2.1 Regulatory Reguirements In Title 10 ofthe Code of Federal Regulations (10 CFR) Section 50.47(b)(1), the regulation states, in part, that: " ... each principal response organization has staff to respond and to augment its initial response on a continuous basis."

In 10 CFR 50.47(b)(2), the regulation states, in part, that: "...adequate staffing to provide initial facility accident response in key functional areas is maintained at all times," and that "timely augmentation of response capabilities is available .... "

In 10 CFR 50, Appendix E, Section IV, Part A, "Organization," the regulation states, in part, that:

"The organization for coping with radiological emergencies shall be described, including definition of authorities, responsibilities, and duties of individuals assigned to the licensee's emergency organization .... "

2.2 Guidance Regulatory Guide (RG) 1.101, "Emergency Response Planning and Preparedness for Nuclear Power Reactors," provides guidance on methods acceptable to the NRC staff for implementing specific parts of the NRC's regulations, specifically 10 CFR 50.47(b) and Appendix E to Part 50.

Revision 2 of RG 1.101 endorses Revision 1 to NUREG-0654/FEMA-REP-1 (NUREG-0654),

"Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," which provides specific acceptance criteria

- 3 for complying with the standards set forth in 10 CFR 50.47. These criteria provide a basis for NRC licensees and State and local governments to develop acceptable radiological emergency plans and improve emergency preparedness.

In NUREG-0654,Section II, "Planning Standards and Evaluation Criteria," Evaluation Criteria 11.8.1 and II.B.5 address the 10 CFR 50.47{b){2) planning standard. Evaluation Criterion II.B.1 specifies the onsite emergency organization of plant staff personnel for all shifts, and its relation to the responsibilities and duties of the normal shift complement. Evaluation Criterion 11.8.5, states, in part, that:

Each licensee shall specify the positions or title and major tasks to be performed by the persons to be assigned to the functional areas of emergency activity. For emergency situations, specific assignments shall be made for all shifts and for plant staff members, both onsite and away from the site. These assignments shall cover the emergency functions in Table B-1 entitled, "Minimum Staffing Requirements for Nuclear Power Plant Emergencies." The minimum on-shift staffing levels shall be as indicated in Table B-1.

The licensee must be able to augment on-shift capabilities within a short period after declaration of an emergency. This capability shall be as indicated in Table B-1.

Pursuant to 10 CFR 50.54(q}, a nuclear power reactor licensee is required to seek Commission approval of any changes to its emergency plan{s) that decrease the effectiveness of the plans.

Regulatory Issue Summary 2005-02, "Clarifying the Process for Making Emergency Plan Changes," was issued by the NRC to clarify the meaning of "decrease in effectiveness" and the process for making changes to emergency plans, and to provide some examples of changes that are considered to be a decrease in effectiveness.

3.0 TECHNICAL EVALUATION

The NRC staff has reviewed the licensee's regulatory and technical analyses in support of its proposed changes to the EPs for Catawba, McGuire, and Oconee, as described in the application dated July 28, 2010, and as supplemented by the letter dated March 3, 2011. The NRC staff's technical evaluation is detailed below.

3.1 Increase the response time requirement for the TSC Dose Assessor from 45 minutes to 75 minutes.

The licensee states that the function of TSC dose assessment members at each nuclear station is to provide the Emergency Coordinator with dose assessment capability and protective action recommendations if needed. The proposed change is to require the TSC Dose Assessor to be available within 75 minutes of an Alert or higher classification rather than the current 45 minute time requirement. The on-shift dose assessment is performed by using a dose assessment computer program (referred to as RADDOSE) and is currently performed by a shift RP qualified individual that is assigned the on-shift dose assessment role each shift for all three sites. Duke energy RP qualified individuals are trained and qualified to perform dose assessment. Each site has three RP qualified individuals minimum per shift. One RP qualified individual is assigned to on-shift dose assessment and two RP qualified individuals are currently available to support other emergency response actions as described in the emergency plans for each site, which is in

-4 excess of on-shift RP staffing identified in Table B-1 of NUREG-0654. This excess on-shift RP staffing allows for the extension of response time for the TSC dose assessment member.

The RADDOSE program is capable of performing in an "automatic" mode as described in each site's respective emergency plan implementing procedures and will produce dose projection reports automatically every 15 minutes after being initiated. If the automatic capability is not available, the one shift RP qualified individual will provide dose assessment capability for the Emergency Coordinator by manually inputting data into the dose assessment computer program.

The NRC staff performed a review of each site's Emergency Plan implementing Procedures (EPIPs) for on-shift dose assessment (Oconee - HP/0/B/1009/022, "On-shift Off-site dose assessment;" McGuire - HP/0/B11009/029, "Initial Response On-shift Dose Assessment;"

Catawba - HP/0/B/1009/026, "On-shift dose assessment") to verify the ease of use for Automatic and manual modes. In automatic mode, the RADDOSE program will automatically populate current meteorological data into the program and produce reports as described above. The manual mode does require the data to be entered manually and the process repeated each time an assessment is run, but due to the increased staffing of RP personnel on-shift, one RP qualified personnel is dedicated to this one task. The other two RP qualified personnel are available for other RP tasks which allows for the increase in augmentation time of the TSC Dose Assessor.

The requested change to increase the response time is consistent with other previously NRC-approved changes. Emergency Response Organization augmentation times have historically been approved on a site-specific basis. For example, one licensee has 30 and 60 minute responders similar to the guidance in NUREG-0654, Table B-1, but another licensee has 120 minute responders. There are site-specific compensations that the NRC reviewed to approve the augmentation times for each site.

Based on the staffing of three on-shift RP qualified individuals which is in excess of NUREG-0654, Table B-1, (one Health Physics Technician on-shift), technological advancements and procedural improvements for dose assessment, the NRC staff finds the compensation described above to be acceptable. The NRC staff finds the proposed changes to increase the response time requirement for the TSC Dose Assessor from 45 minutes to 75 minutes continues to meet the intent of the NRC-approved EP, and continues to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR Part 50.

3.2 Change the access control function for access to the EOF from a staffed position to a monitored card reader process.

The licensee states that the Access Control Function at the EOF is currently performed by duty personnel who verify the identity of authorized personnel against a preapproved access list and permit entry by manually overriding an electronic solenoid lock on the EOF entrance door.

The EOF is located in the Energy Center, Headquarters for Duke Energy in Charlotte, North Carolina, which is restricted to authorized personnel by an industrial security system. Access to the EOF facility is limited prior to activation and is only provided for authorized personnel with Duke Energy identification badges that have been preapproved.

The proposed change to the staffing requirement will no longer require a person assigned to duty as EOF Access Control Director, but would use a monitored card reader process to maintain

- 5 controlled access to the EOF. The licensee provides that the elimination of the Access Control Director is considered a reduction in commitment for the EPs but does not result in any reduction in the capability of the emergency response organization (ERO) to respond to an emergency.

Based on the preceding analysis and the additional information provided in the licensee's March 3, 2011, supplement, the NRC staff finds the compensation described above to change the access control function for access to the EOF from a staffed position to a monitored card reader process to be acceptable. The proposed changes to the EOF access control continues to meet the intent of the NRC-approved EP, and continues to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR Part 50.

3.3 Chanqe the composition of a FMT from two RP Technicians to one RP qualified individual and a vehicle driver.

The Oconee EP currently requires one individual to have FMT qualifications for the specific function and duty of offsite radiological monitoring, and uses a vehicle driver to operate the vehicles. Catawba and McGuire EPs currently require FMTs to consist of two RP qualified individuals. To achieve fleet consistency the proposed change will revise the Catawba and McGuire EPs and clarify the Oconee EP to document that each FMT will consist of one RP qualified individual and one vehicle driver. This allows an efficient use of RP qualified individuals in emergencies and gives management more resources to address other priority work requiring radiological support and protection activities during a declared emergency.

The licensee states that this change in the FMT is considered a reduction in commitment for the Catawba and McGuire emergency plans but will not result in any reduction of the capability of the emergency response organization to respond to an emergency.

The licensee states that the original intent was for each team to consist of two RP qualified individuals with one of the RP qualified individuals to be the vehicle driver. One RP qualified individual can adequately perform contamination surveys and sampling tasks and other site work groups provide additional personnel to be the vehicle driver. The licensee further states that the vehicle driver will be required to maintain radiation worker qualifications and a valid state driver's license.

The licensee's March 3, 2011, letter provided additional information related to the respirator qualifications of the proposed vehicle driver; the licensee stated that the Oconee and McGuire FMT drivers are required to be respirator qualified. At Catawba, currently only RP qualified individuals serve as FMT drivers and are required to be respirator qualified. The licensee further stated that upon approval of this License Amendment, any new non-RP qualified individual FMT drivers will be required to be respirator qualified.

The use of non-RP qualified personnel as vehicle drivers for FMTs is a current practice in use at multiple licensees. This practice allows for a more efficient use of the RP personnel during an event.

Based on the preceding analysis and the licensee's supplemental information provided in the March 3, 2011, letter, the NRC staff finds the change in composition of a FMT from two RP Technicians to one RP qualified individual and a vehicle driver, as described, to be acceptable.

- 6 The proposed change to the FMT staffing continues to meet the intent of the NRC approved emergency plan, and continues to meet the standards of 10 CFR 50.47(b) and the requirements of Appendix E to 10 CFR 50.

3.4 Change RP staffing during emergency response events from RP Technicians to RP qualified individuals.

The licensee states that the current ERO minimum staffing requirements for augmenting the functions of "RP coverage for repair/corrective action, access control, search & rescue, radiochemistry, contaminated injury medical response, personnel monitoring, dosimetry, firefighting" is limited to RP technicians. RP qualified individuals perform the tasks required as referenced in Figure 8-8 (Oconee) and Figure 8-1 (Catawba and McGuire). RP qualified individuals can include RP supervisors and RP staff who routinely administer RP programs, policies and procedures. 8ased on their training and experience, these individuals maintain the level of knowledge required to perform the tasks described on Figure 8-8 (Oconee) and Figure 8-1 (Catawba and McGuire).

The licensee further states that RP qualified individuals currently have other functional assignments in the ERO but are available during an augmentation (all call) to perform technician duties when not performing their primary function. Minimum staffing requirements for the other ERO RP functions will continue to be met by personnel in the organization qualified to perform the required functions. Twenty-four hour coverage of an ERO position requires only two personnel (two 12-hour shifts). The licensee further states that since the expected ERO staffing level is five personnel per position and an implemented augmentation is an "all call" event, there are RP qualified individuals at the facilities without a position to staff. These extra personnel, who are capable of functioning as RP technicians can be used to staff the above coverage functions. The alternate use of RP qualified individuals improves the ERO staffing capability to meet current minimum staffing requirements for RP technicians.

The licensee stated in the March 3, 2011, supplemental letter that the Catawba, McGuire and Oconee, RP supervisors and staff personnel participate in the same training as the RP qualified individuals. RP supervisors and staff personnel who have task qualification must maintain the same training qualifications and requalification as the RP qualified individuals. ERO task requalification is covered in RP continuing training at least every 2 years.

The on-shift minimum staffing levels referenced in Figure 8-8 (Oconee) and Figure 8-1 (Catawba and McGuire), specify whether other personnel on-shift would be able to perform the RP functions in the "Major Functional Area of Protective Actions (In-plant)" (Oconee) and "Major Functional Area of Radiological Support and Protective Actions" (Catawba and McGuire). The licensee stated in the March 3, 2011, letter that no other personnel on-shift will be assigned those ERO duties - only RP qualified individuals.

The practice of maintaining the qualifications of RP supervision current with the RP Technicians allows for more flexible staffing of the emergency plan by increasing the number of personnel available to respond to an event. This practice is in use at multiple licensees.

8ased on the maintenance of the level of training and qualifications for the RP Qualified Personnel to the standards of training and qualifications provided to the RP Technicians, the NRC staff finds the change in RP staffing during emergency response events from RP Technicians to

-7 RP qualified individuals to be acceptable. The proposed change to the RP staffing continues to meet the intent of the NRC approved emergency plan, and continues to meet the standards of 10 CFR 50A7(b) and the requirements of Appendix E to 10 CFR 50.

3.5 Editorial changes to clarify the notations in the EPs to provide fleet-wide consistency.

Section 2.2 of the application contains a listing of the proposed editorial changes affecting the Catawba, McGuire, and Oconee EPs. These editorial changes clarify position titles, provide identifying notations made per the functional changes proposed and provide consistency with the figures located in each EP. Since these changes are editorial and nonsubstantive, a technical evaluation of each is not required.

The NRC staff reviewed the editorial changes related to the proposed changes to the Catawba, McGuire, and Oconee EPs, and finds that the proposed changes continue to meet the intent of the NRC approved emergency plan, and continue to meet the standards of 10 CFR 50A7(b) and the requirements of Appendix E to 10 CFR 50. Therefore, the NRC staff finds these changes acceptable.

4.0

SUMMARY

The NRC staff finds that the proposed changes to the Catawba, McGuire and Oconee EPs continue to meet the standards in 10 CFR 50A7(b) and the requirements in Appendix E to 10 CFR Part 50, and provide reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency. Therefore, the NRC staff finds the licensee's proposed changes to the Catawba, McGuire and Oconee EPs in its application dated July 28, 2010, and as supplemented by letter dated March 3, 2011, to be acceptable.

5.0 STATE CONSULTATION

In accordance with the Commission's regulations, the North and South Carolina State officials were notified of the proposed issuance of the amendments. The State officials had no comments.

6.0 ENVIRONMENTAL CONSIDERATION

The amendments change an administrative procedure. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding published in the Federal Register on September 7, 2010 (75 FR 54393). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(1 0). 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.

-8

7.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: Michael Norris Date: July 29, 2011

ML11158A209 *transmitted via memo NRRlLPL2/PM OGC/NLO OFFICE NRRlLPL2IPM NRRlLPL2ILA NSIRlDPRlDDEP/ORlBC w/changes JThompson MO'Brien NAME JStang (BClayton for) JAnderson* STurk DATE 7111/11 7111/11 7111111 04/25/11 7112111 OFFICE NRRlLPL2/BC DORUD NRRlDD NRRlD NRRlLPL2IPM GKulesa JGiitter BBoger Jstang NAME (PBoyle for) (ELeeds for) ELeeds (GKulesa for)

DATE 7/13/11 7119/11 7129/11 7/29/11 7/29/11