ML061390380

Edwin I. Hatch, License Amendment, Issuance of Amendments Revise Operating Licenses to Support the Crediting of Potassium Iodide for an Interim Period (TAC Nos. MD0525 and MD0526)

ML061390380
Person / Time
Site:	Hatch
Issue date:	05/25/2006
From:	Gratton C NRC/NRR/ADRO/DORL/LPLC
To:	Sumner H L Southern Nuclear Operating Co
Gratton C, NRR/DORL 415-1055
Shared Package
ML061390380	List: ML061390380
References
TAC MD0525, TAC MD0526
Download: ML061390380 (18)

Text

May 25 , 2006 Mr. H. L. Su mner, Jr.Vice Presi dent - Nucle ar Hatch Project Southern Nucl ear Operating Company, Inc.Post Office Box 12 95 Birmingham, AL 35201-1295 SUB JEC T: EDWIN I. HATC H NUC LEAR PLANT, UNIT N OS. 1 A ND 2, ISSUA NCE OF AMENDMENTS RE: REVISE OPERATING LICENSES TO SUPPORT THE CREDITING OF POT ASSIUM IODIDE FOR AN INTERIM PERIOD (TAC NOS. MD05 25 AND M D0526)

Dear M r. Sumn er:

The Nuclear R egulatory Co mmission has issued the e nclosed Amen dment No. 249 to Renewed Facility Operating Licen se DPR-57 a nd Amendment No. 193 to Rene wed Faci lity Operati ng License NP F-5 for the Edw in I. Hatch N uclear Pla nt, Units 1 a nd 2. The amend ments consist of changes to the operating licenses and the Final Safety Analysis Report (FSAR) for each unit in response to y our applica tion dated M arch 17, 2006, as supplemente d on April 14, 2006.

The amendments autho rize the l icensee to c redit admini stering potassiu m iodide (K I) to reduce the 30-day post-accident thyroid dose to the occu pants of the main contr ol room for an interim period of 4 years. In addition, the design-basis accident analysis section of the Updated FSARs wil l be u pdated to refl ect cre ditin g of KI.A copy of the related Safety Evaluati on is also enclosed.

A Notice of Issu ance wi ll be in cluded in the Com mission's biweek ly Federal Reg ister notic e. Sincere ly,/RA/Christopher Gratton , Sr. Project M anager Plant Lice nsing B ranch II-1 Div isi on o f Oper atin g Rea ctor Lic ensi ng Office of Nuclear Reacto r Regulation Docket Nos. 50-32 1 and 50-366

Enclosures:

1. Amendment No. 249 to DPR

-57 2. Amendment No. 193 to NPF

-5 3. Safety Ev aluation cc w/enc ls: See nex t pag e May 25, 2006 Mr. H. L. Sum ner, Jr.Vice Pr esident - Nucl ear Hatch Proj ect Southern Nuclear Operati ng Com pany, Inc.Post Offi ce Box 1295 Birmingham, AL 35201

-1295 SUBJ ECT: EDWIN I. HAT CH NU CLE AR P LA NT, UNI T NOS. 1 A ND 2 , I SSU ANC E OF AMENDMENTS RE

REVI SE OPERA TING L ICE NSES TO SU PPORT THE CRE DITI NG OF POTASSI UM IODI DE FOR AN I NTERI M PERI OD (TAC NOS. MD052 5 AND MD0526)

Dear M r. Sum ner:

Th e N ucle ar R egu latory C om m ission has issu ed th e en clos ed A m end m ent N o. 24 9 to R ene wed Fac ility Operati ng Lice nse DPR-57 and Amendm ent No. 193 to Renewed Facil it y Operat ing Li cense NPF-5 for t he Edwin I. Hatch Nuclear Plant , Uni ts 1 and 2. The amendm ents consi st of changes to the oper ati ng li censes and t he Final Safety Analy sis Repor t (FSAR) for each uni t i n response t o your appli cati on dated March 17, 2006, as suppl emented on Apri l 14, 2006.The am endments author iz e the l icensee to cr edit administ eri ng potassi um iodide (KI) t o reduce t he 30-day pos t-acc iden t thyroid d ose to the o ccu pan ts of th e m ain co ntrol ro om for an interim perio d of 4 years. In addit ion, the desi gn-basi s acciden t anal ysi s secti on of t he Updated FSARs wil l be updated t o refl ect cre diting o f KI.A copy of the r elat ed Safet y Eval uati on is also en closed. A Noti ce of I ssuance wil l be incl uded i n the C om m iss ion's b iwe ek ly Federal Regist er notice. Sin ce re ly,/RA/Christ opher Grat ton, Sr. Pr oject Manager Plant Licensing Branc h II-1 Divi sion of Operati ng Reactor Licensi ng Office of Nuclea r Reactor Regulat ion Docket Nos. 50-321 and 50-36 6 Enclosur es: 1. Amendm ent No. 249 to DPR-57 2. Amendm ent No. 193 to NPF-5 3. Saf ety Eval uati on cc w/encl s: See next page DIS TRIB UTION: Pu blic RidsAc rsAcnw MailCenter LP L2-1 R/F GHill (4 hard copies)RidsNrrDorl Lplc(EMarinos)RidsNrrDi rsIt sb(TBoyce)

R ids N rrP M C G ra tton (h ar d c op y)DChun g, NRR RidsNrrLAMO'Bri en(2 har d copie s)RidsRgn2Mail Center(CRapp)Ri dsOg cRp BSi nga l (DORL DPR)MKot za l as, NRR RDenn i g, NRR TCobe tz , NRR Package No. ML061390388 Amendment No. ML061390380 Tech Spec No. ML061500064

OFFICE NRR/LPL2-1/PM NRR/LPL2-1/

LA NRR/AADB/BC NRR/ACVB/BC NRR/ITSB/BC OGC NRR/LPL2-1/BC NAME CGratton:sx d6 MO'Brie n MKotza las BDennig TKobetz JMoore EMarinos DATE 5/19/06 5/19/06 05/10 /06 05/10/ 06 5/18/06 5/18/06 5/23/06 OFFICIAL RECORD COPY SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POW ER COMPANY OGLETHOR PE POWER COR PORATION MUN ICIPAL ELEC TRIC AU THORITY O F GEORGI A CITY OF DALTON, GEORGIA DOCKET NO. 50-321 EDWIN I. HATC H NUC LEAR PLANT, UNIT N O.1 AMENDMENT TO RENEWED FACILI TY OPERATING LICENSE Amendment No. 24 9 Renewed License No. DPR-57 1.The Nuc lear R egulat ory C ommissi on (the Commis sion) has fou nd tha t: A.The applicati on for amendment to the Edwin I. Hatch Nucl ear Plant, Un it 1 (the facili ty) Re newe d Faci lity Operati ng Lice nse No. DPR-57 fil ed by South ern Nuclear Operati ng Company, Inc. (the license e), acting for itsel f, Georgia Power Company, Ogletho rpe Power Corporation, M unicipal Electric A uthority of Georgia, and Ci ty of Dalton, Georgia (the ow ners), dated M arch 17, 2006, as suppl emented on Ap ril 1 4, 200 6, comp lies wit h the s tandar ds and requir ements of the A tomic E nergy Act of 1 954, a s amend ed (the Act), a nd the Commis sion's rules and re gulati ons as set forth in 10 CFR C hapter I;B.The facility will operate in co nformity wi th the appli cation, the pro visions of the Act, and the rul es and regulati ons of the Commissi on;C.There is reasonable assurance (i) that the activities authorized by this amendment can be conducted w ithout endangeri ng the health a nd safety of the public, and (ii) that suc h activi ties wi ll be con ducted in co mpliance w ith the Commis sion's regul ation s set for th in 10 CFR Chapt er I;D.The issuance o f this amendment w ill not b e inimical to the common de fense and security or to the health and safety of the p ublic; and E.The issuance o f this amendment is in accordan ce with 10 CFR Part 51 of the Commission's re gulations and all appl icable requi rements have been satisfied. 2.Accordingly, License Condition 2.C.(8) to Renewed Facility Operating License No. DPR-57 is hereby added to rea d as follow s: (8) Design Bases Accident Ra diological Consequences Analyses Southe rn Nuc lear i s auth oriz ed to c redit admini sterin g potass ium io dide to reduce the 30 day post-acc ident thyro id radiol ogical dose to the operators in the main control room until M ay 31, 201

0. Should design basis changes be completed rende ring the crediti ng of potassium iod ide no lo nger necessary prior to May 31, 2010, Sou thern Nuclea r will remove the c rediting of potassi um iodide from the design basi s accident ra diological consequences a nalyses (re ference Unit 2 FSAR paragraph 15.3.3.4.

2.2) in the next Updated Final Safety Analysis Report updat e as re quired by 1 0 CFR 50.71 (e).3.This license amendment is e ffective as of its da te of issuance a nd shall be implemented with in 30 days of issu ance. FOR THE NUCL EAR R EGULA TORY COM MISS ION/RA/Evangelos C. Marinos , Chief Plant Lice nsing B ranch II-1 Div isi on o f Oper atin g Rea ctor Lic ensi ng Office of Nuclear Reacto r Regulation Attach ment: License Ch anges to Renew ed License No. DPR-57 Date of Issuance: M ay 25, 200 6

ATTACHMENT TO LICE NSE AM ENDMEN T NO. 249 RENEWED FACILITY OPERATING LIC ENSE NO. DP R-57 DOCKET NO. 50-321 Replace the followin g pages of the Operating Li cense wi th the attached revised p ages. The revised p ages are identi fied by amend ment numbers and contain marginal lines i ndicating the areas of change. Remove Insert 4 4 6 6 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

GEORGIA POW ER COMPANY OGLETHOR PE POWER COR PORATION MUN ICIPAL ELEC TRIC AU THORITY O F GEORGI A CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATC H NUC LEAR PLANT, UNIT N O. 2 AMENDMENT TO RENEWED FACILI TY OPERATING LICENSE Amendment No. 19 3 Renew ed Li cense No. NP F-5 1.The Nuc lear R egulat ory C ommissi on (the Commis sion) has fou nd tha t: A.The applicati on for amendment to the Edwin I. Hatch Nucl ear Plant, Un it 2 (the facili ty) Re newe d Faci lity Operati ng Lice nse No. NPF-5 file d by Southe rn Nuclear Operati ng Company, Inc. (the license e), acting for itsel f, Georgia Power Company, Ogletho rpe Power Corporation, M unicipal Electric A uthority of Georgia, and Ci ty of Dalton, Georgia (the ow ners), dated M arch 17, 2006, as suppl emented on Ap ril 1 4, 200 6, comp lies wit h the s tandar ds and requir ements of the A tomic E nergy Act of 1 954, a s amend ed (the Act), a nd the Commis sion's rules and re gulati ons as set forth in 10 CFR C hapter I;B.The facility will operate in co nformity wi th the appli cation, the pro visions of the Act, and the rul es and regulati ons of the Commissi on;C.There is reasonable assurance (i) that the activities authorized by this amendment can be conducted w ithout endangeri ng the health a nd safety of the public, and (ii) that suc h activi ties wi ll be con ducted in co mpliance w ith the Commis sion's regul ation s set for th in 10 CFR Chapt er I;D.The issuance o f this amendment w ill not b e inimical to the common de fense and security or to the hea lth and safety of the public

and E.The issuance o f this amendment is in accordan ce with 10 CFR Part 51 of the Commission's re gulations and all appl icable requi rements have been satisfied. 2.Accordingly , License C ondition 2.C.(3)(f) to Renewe d Facili ty Operating Li cense No. NPF-5 i s hereby a dded to read as follows

(f) Design Bases Accident Ra diological Consequences Analyses Southe rn Nuc lear i s auth oriz ed to c redit admini sterin g potass ium io dide to reduce the 30 day post-acc ident thyro id radiol ogical dose to the operators in the main control room until M ay 31, 201

0. Should design basis changes be completed rende ring the crediti ng of potassium iod ide no lo nger necessary prior to May 31, 2010, Sou thern Nuclea r will remove the c rediting of potassi um iodide from the design basi s accident ra diological consequences a nalyses (re ference Unit 2 FSAR paragraph 15.3.3.4.

2.2) in the next Updated Final Safety Analysis Report updat e as re quired by 1 0 CFR 50.71 (e).3.This license amendment is e ffective as of its da te of issuance a nd shall be imple mented with in 30 days of issu ance. FOR THE NUCL EAR R EGULA TORY COM MISS ION/RA/Evangelos C. Marinos , Chief Plant Lice nsing Branch II-1 Div isi on o f Oper atin g Rea ctor Lic ensi ng Office of Nuclear Reacto r Regulation Attach ment: Licen se Cha nges to Renew ed Li cense No. NP F-5 Date of Issuance:

May 25 , 2006 ATTACHMENT TO LICE NSE AM ENDMEN T NO. 193 RENE WED FACILITY OPERA TING LIC ENSE NO. NP F-5 DOCKET NO. 50-366 Replace the followin g pages of the Operating Li cense wi th the attached revised p ages. The revised p ages are identi fied by amend ment numbers and contain marginal lines i ndicating the areas of change. Remove Insert 4 4 6 6 7 7 SAFETY EVAL UATION B Y THE OF FICE OF NUCL EAR R EACTOR REGUL ATION REL ATED TO AMENDM ENT NO. 249 TO RE NEWED FACILITY OPERATING LICEN SE DPR-57 AND A MEN DME NT NO. 1 93 TO R ENEWED FAC ILITY OP ERATIN G LICEN SE NP F-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

EDW IN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-32 1 AND 50-36 6 1.0 INTRODU CTION By letter d ated March 17, 2006, as supplemented b y letter da ted April 1 4, 2006, (Agency wide Documents Acces s and Ma nagement System (A DAMS) ac cession numbe rs ML0611 80036 and ML06 1070078, respe ctively) Southern Nuc lear Operating C ompany, Inc. (S NC, the lice nsee), propo sed a lice nse ame ndment for the E dwi n I. Ha tch Nu clear Plan t, Uni t Nos. 1 and 2 (HNP). The pr opose d chan ge wou ld rev ise th e oper ating l icens es to s upport compen satory use o f potass ium io dide (KI) for a n inte rim pe riod o f approx imatel y 4 y ears. This license amendment wi ll authori ze HNP to credit admin istering KI to re duce the 30-da y post-accident thyroid radiological dose to t he operators in the main control room (MCR). This change is requested to support Ameri can Society for Testing and M aterials E7 41 tracer gas testin g to det ermine actua l MC R unfil tered i nleaka ge, as re quested by N uclea r Regul atory Commission (N RC) Generic L etter 2003-01, "Co ntrol Room Ha bitabili ty." The suppl emental letter dated A pril 14, 20 06, provid ed clarifyi ng information that di d not change the scope of the March 17, 2006, appli cation nor the initial proposed no significant haz ards conside ration determination.

SNC has ass erted that credi ting KI wi ll permit the plant to con tinue to meet th e dose accept ance c riteri a spec ified in Sta ndard Revi ew P lan (S RP) 6.4, "Co ntrol Room H abita bili ty Sy ste m," and Tit le 10 of t he Cod e o f Federa l Reg ulati ons, Part 50 (10 CFR Part 50), Appendix A, General De sign Criterion 19 (GDC-19) rad iological dose acceptanc e limits for con trol room habit abil ity fo r loss-of-cool ant ac ciden ts (LOC As) us ing 11 0 cubi c feet pe r minu te (cfm)unfiltered inl eakage. The LOCA is the limiti ng design-basis accident (DB A) for radiologic al expo sures t o the o perato rs in the M CR. Th e curre nt HNP lice nsing b asis d oes no t assum e any unfiltere d inleakage throu gh the control ro om envelop e boundary and only 10 cfm from ingress and egress.

Any test mea surement that ex ceeded 0 cfm w ould not be bounded by the HNP current l icensing basi s DBA control room dose ana lyses. Thi s amendment w ill all ow interim credi t for the administra tion of KI to ena ble SNC to conduct M CR tracer gas testi ng and remain within its licensing basis for test resu lts of unfiltered inleak age of up to 110 cfm. This will provide ti me for SNC to impl ement appropria te design-basis changes to addre ss the impact of any u nfiltered inl eakage. The proposed license amendment will add a license condition to Sections 2.C of the HNP Operating Licenses.

This license condition will authorize SNC to credit the administering KI and reduce the 30-day po st-accident thy roid radiol ogical dose to the operators in the M CR for an interim pe riod of approx imately 4 years. The pro posed lice nse conditi on states:

Design Bases Accident Ra diological Consequences Analyses Southe rn Nuc lear i s auth oriz ed to c redit admini sterin g potass ium io dide to reduce the 30 day post-acc ident thyro id radiol ogical dose to the operators in the main control room until M ay 31, 201

0. Should design basis changes be completed rende ring the crediti ng of potassium iod ide no lo nger necessary prior to May 31, 2010, Sou thern Nuclea r will remove the c rediting of potassi um iodide from the design basi s accident ra diological consequences a nalyses (re ference Unit 2 FSAR paragraph 15.3.3.4.

2.2) in the next Updated Final Safety Analysis Report updat e as re quired by 1 0 CFR 50.71 (e).By l etters dated Marc h 17 a nd Apr il 14 , 2006 , SNC made th e foll owi ng regul atory commitments:

1.SNC wi ll end the crediting of potas sium iodid e to reduce the 30-day po st-accident thyroid rad iological dose to the mai n control room operators prior to May 31, 2010.2.Should des ign basis cha nges be complete d rendering the crediting of potassi um iodide no longer nece ssary prior to May 31, 2010, SNC will remove the c rediting of potassi um iodide f rom th e design basis acc ident ra diologic al conseq uences a nalyses in t he next Update d Fin al Sa fety An alys is Re port up date a s requi red by 10 CF R 50.7 1(e).3.SNC wi ll submit a license a mendment request suppo rting full scope implementation of an alternativ e source term (AS T) in accordance with the requirements of 10 C FR 50.90 and 10 CFR 50.67 no l ater than August 3 1, 2006.2.0 REGUL ATORY E VALUA TION The regulatory re quirements on w hich the NR C staff based its acc eptance are the accident dose guideli nes in 10 CFR 100.11, a s supplemented by acci dent-specific cri teria in Se ction 15 of the SRP, and 10 CFR Part 50, Appendi x A, GDC 1 9, "Control Ro om," as supplemen ted by Section 6.4 of NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nucle ar Power P lants." Ex cept where the license e proposed a suitable al ternative, the NRC staff used th e regulatory gui dance provi ded in the following d ocuments in pe rforming this r evie w. *Regulatory Gui de 1.3, "Assumpti ons Used for Ev aluating the P otential Ra diological Consequences of a Loss-of-Coolant A ccident for Boi ling Water Reactors"*SRP Sectio n 15.6.5, "Loss-of-Coo lant Accide nts Resultin g from Spectrum of Postulated Piping Breaks W ithin the Reactor Coolant Pressure Boundar y," Appendix A, Appendix B, and Appendix D *SRP S ectio n 6.4, "Contr ol Ro om Hab itabi lity Syst ems" *Regulatory Gui de 1.196, "Con trol Room Hab itability at Light-Water Nuclear Pow er Reactors" The NRC staff also considered relevant information in the HNP Updated Final Saf ety Analysis Report (UFSAR

), Technical S pecifications, and a prior amendment (Amendment No. 132, Licen se No. NPF-5).3.0 TECHNI CAL E VALUA TION The NRC staff revie wed the re gulatory and technical a nalyses, a s they rel ated to the radio logica l con sequenc es of a D BA LOC A, that were performe d by SNC i n supp ort of i ts proposed li cense amendment.

Information regarding these analyse s was prov ided in Enclosure 1 of the licensee

's letter date d March 1 7, 2006, and in a suppl ementary lette r dated April 14, 2006. The NRC staff reviewed the assumptions, inputs, and methods used by SNC to assess the i mpacts of the propose d license amendment. The NRC staff performed ind epen dent cal cul atio ns to con firm t he c onse rva tism of th e li cens ee's ana lys es. The fi ndi ngs of this safety ev aluation i nput are based on the descri ptions of the l icensee's an alyses an d other s upport ing in formatio n docke ted by SNC. SNC has ev aluated the HNP MC R dose w ith an assumed unfiltered in leakage of 110 cfm for the boundin g LOCA DBA. B y taking credit for the operator recei ving KI w ithin 2 ho urs after the start of the accident as part of a licensee-administer ed KI program, the MCR LOCA thyroid dose me ets the regula tory d ose ac ceptan ce cri teria of 30 re m thyr oid s et forth in SR P 6.4. The MCR LOC A whole-bod y dose cont inues to m eet the GDC-19 lim it of 5 r em whole bod y, with 110 c fm of unfil tered i nleaka ge. The DBA LOCA dose analy sis inclu des three rele ase paths: co ntainment lea kage, main stack release, and main steam iso lation v alve (M SIV) leakage. Lea kage through each of these paths releases fission product s to the environment and contributes to the dose to personnel in the MCR. HNP Uni ts 1 and 2 h ave a common control room. The MCR is located betw een the open end ba ys of the HNP Units 1 an d 2 turbine buildings.

The LOCA MC R radiologi cal dose analysi s input parame ters are given in Table 1 (Attachment 1). The atmospheric di spersion factors (X/Qs) are provi ded in Table 2 (Attachment 2), and are the sa me as those use d in the HNP c urrent lice nsing b asis. The Un it 2 c ontrol room re ceptor X/Q val ues ar e large r and w ere used as the b asis for a bound ing calcula tion.In the NRC s taff's evaluation of the licensee

's revised dose analy sis, the confirmati on of the MCR dos e is supporte d by a rev iew of a pri or amendment that i ncluded M SIV dose cal culation as well as an NRC staff independent ca lculation of the dose from each o f the LOCA releas e paths. The ca lcul ation s wer e base d on th e lic ensee's assu mption s give n in Ta ble 1 and w ere performed wit h the c omputer code RADTRA D, des cribe d in N UREG/C R-6604 , "RAD TRAD: A Simpl ified Mode l for RA Dionu clid e Trans port an d Remo val And D ose Es timati on." The thyroid d ose receiv ed by the operators is b ased on the a ssumption that K I would be administered within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the acc ident ini tiation. In the dose cal culation, the 1/10 reduct ion o f thyro id do se is appli ed to t he ent ire ti me peri od (as recomme nded b y NE I 99-03). The 30-day L OCA M CR do se is the su m of the d oses fro m the th ree rel ease p aths. The assumptions u sed in the revised L OCA dose anal ysis in support of this a mendment request are the same as those in the current li censing basis , with the exceptio n of the increased co ntrol room unfilte red inleakage an d credit for admin istration of KI for red uction of the control room thyroid dose. A review of an earlier LOCA dose calculation, as descr ibed in the safety ev aluation for Ame ndment No. 132 for Unit 2, prov ides reasona ble assuranc e of the SNC calcul ation and co nfirms the SNC ca lculated 30-day thyro id dose i n MCR a s reasonable

.Based on the above, the NRC staff conclud es that there i s reasonable assurance that the require ments o f GDC 19 wil l con tinue to be met for un filtere d cont rol ro om inl eakage o f up to 110 sc fm. The NR C staff do es not genera lly allo w cre dit for KI unl ess it is an inter im comp ensato ry measure neede d to ad dress a degrad ed non conformi ng cond ition whi le co rrecti ve ac tions are being taken. Regul atory Guide 1.196 describ es the use of KI for addressing degraded or nonconforming condi tions. For thi s amendment, the l icensee requeste d that credit for K I be authorized for up to 4 ye ars to support A STM E471 tracer gas testing of the ma in control ro om and to all ow time to implement any design basi s changes to add ress the impact of control room unfiltered i nleakage. The desi gn-basis changes a re expected to include the full scope implementation of an alternati ve source te rm followin g NRC staff approval , and could also include o ther design and licensin g bases changes. The NRC staff considered this justificati on when revi ewi ng the a mount o f time th at KI c ould be par t of the lice nsing b asis a nd foun d it to be acceptabl e.The licensee included a total of three regulatory commitmen ts to support i ts license amendment request, tw o regulatory c ommitments in En closure 6 of the licensee's March 1 7, 2006, appli cation, and o ne regulatory commitment in En closure 2 of the licensee's April 14

, 2006, appli cation suppl ement. The NRC staff finds that reasonabl e controls for the imple mentati on and subse quent e valu ation of prop osed c hanges pertai ning to the re gulato ry commitment in En closure 2 of the licensee's April 14 , 2006, appl ication sup plement is b est provided by the li censee's ad ministrativ e processes, i ncluding its commitment management program (See R egulat ory Is sue Su mmary 2 000-17 , "Ma naging R egulat ory C ommitmen ts Made by Power R eactor License es to the NRC Staff"). The regulatory co mmitment does not warrant the c reation of regulatory requirements (items requiring prior N RC approv al of subsequ ent ch anges). The NR C staff no tes tha t the tw o regul atory commit ments o f Enclo sure 6 of the licen see's M arch 17, 2006, applicatio n also are contained i n the lice nse conditi on, and, therefore, woul d require prior NRC approv al of subsequent ch anges, if needed.

This amendment al so include s a revise d page 7 to Re newed Li cense No. NP F-5. The revi sed page contains te xt previ ously l ocated on page 6, but was moved to page 7 due to chan ges on page 6. The changes to page 7 of Renew ed License No. NPF-5 are editorial and acceptab le. Technical Ev aluation C onclusion The NRC staff revie wed the a ssumptions, in puts, and methods used by SNC to asses s the radiological impacts of a desi gn-basis LOCA a t HNP. The NR C staff finds that SNC used analy tical method s and assump tions consi stent w ith th e cons ervat ive regula tory r equire ments and guidance identified i n Section 2

.0 above.

The NRC staff compared the doses estimate d by SN C to th e acce ptance crite ria i denti fied i n Sect ion 2.0. The NRC s taff finds, wit h reasonable a ssurance, that the licensee's estimates of the co ntrol room thy roid doses, w hen credi ting do se red uctio n from KI , wi ll co ntinu e to co mply with these crite ria. The NRC staff also finds the license condition that authorizes the credit ing of KI for an inter im perio d not t o exc eed M ay 31 , 2010 , accep table. This condi tion i s cons isten t wi th regul atory guidance that states t hat the prophylactic use of KI can be credited as an inter im compen satory measur e wh ile fi nal c orrecti ve ac tions are be ing take n. 4.0 FINAL NO SIGN IFICAN T HAZA RDS C ONSIDE RATION D ETERM INATION The Commission' s regulations i n 10 CFR 5 0.92(c) state that th e Commission may make a final determination that a license amendm ent involves no significant hazards consideration if operat ion o f the faci lity in ac cordan ce wi th the amendme nt wo uld n ot: (1) Involve a significant increase in the probability or conseq uences of an accident previously eval uated; or, (2) Create the p ossibili ty of a new or different kind of acci dent from any prev iously evaluated;or, (3) Invo lve a signif icant re duction in a marg in of saf ety.The foll owi ng anal ysis was provi ded by the l icens ee in its M arch 1 7, 200 6, let ter: 1.Does the prop osed change i nvolve a significant i ncrease in th e probabili ty or consequen ces of an accid ent previo usly ev aluated?This proposed change wil l authoriz e SNC to cre dit KI for an i nterim period in the DBA radiological consequences analyses to address t he impact of MCR unfiltered inl eakage. This proposed change does n ot result in any functiona l or operational change to any systems, structure s, or components and has no impact on any assumed ini tiator of any a nalyze d accident. There fore, the proposed chan ge does not resul t in an in crease in the probabili ty of an acci dent previousl y eval uated.This proposed change intr oduces an additional method of mitig ating the thyroid dose to M CR occupants in the ev ent of a loss-of-cool ant accident (LOCA). The upda ted L OCA MC R ra dio logi cal dos e, co nsi deri ng 11 0 cfm u nfil tere d in lea kage and creditin g KI, continues to meet GDC 19 a cceptance li mits. In the conte xt of the current licensing basis with MCR unfiltered inleakag e considered, LOCA continues to be the limiting event for radiological exposures to the operators in the M CR. Ra diol ogical doses to M CR oc cupan ts are with in the regula tory l imits of GDC 19 wi th MCR u nfiltered inl eakages of up to 1000 cfm without the crediting of KI for the main steam li ne break accide nt (MSLB), control rod dro p accident (CR DA), and fuel h andling acci dent (FHA). Therefore, the proposed change does not result in a significant inc rease in the consequences of an accid ent pre viou sly eval uated. 2. Does the prop osed change crea te the possib ility o f a new or di fferent kind of accident from any previ ously ev aluated?This proposed change wil l authoriz e SNC to cre dit KI for an i nterim period in the DBA radiological consequences analyses to address t he impact of MCR unfiltered inl eakage. This proposed change does n ot result in any functiona l or operational change to any systems, structure s, or components.

Therefore, the proposed chan ge does not create the possibi lity of a n ew or di fferent kind of accid ent from a ny pr evio usly eval uated. 3. Does the proposed change involve a significant decr ease in the margin of safety?

This proposed change wil l authoriz e SNC to cre dit KI for an i nterim period in the DBA radiological consequences analyses to address t he impact of MCR unfiltered inl eakage. This proposed change does n ot result in any functiona l or operational change to any systems, structure s, or components.

This proposed change introduces an additional meth od of mitigating the thyroid dose to MCR occupants in the event of a LOCA. The upda ted LOCA M CR radiol ogical dose, considering 11 0 cfm unfiltered inl eakage and crediti ng KI, continues to meet GDC 19 accep tance limit s. In th e cont ext o f the cur rent l icens ing ba sis w ith MCR unfil tered inlea kage considered, LOC A continues to be the li miting event for radi ologi cal e xpos ures to the op erators in th e MC R. Rad iolo gical doses to MCR occu pants are w ithin the re gulatory li mits of GDC 19 w ith MCR unfiltered inleakages of up to 1000 cfm witho ut the crediti ng of KI for the main stea m line break accident (M SLB), control rod drop acci dent (CRDA), a nd fuel handl ing accident (FHA

). Therefore, the proposed change does n ot invol ve a signi ficant decrea se in the mar gin of sa fety. The NRC staff has rev iewed th e licensee

's analy sis and, bas ed on this review , has conclu ded that the three sta ndards of 10 CFR 50.92(c) are sa tisfied. Therefore, the N RC staff has determi ned th at the propos ed amen dment i nvol ves n o signi ficant h azard s cons idera tion. 5.0 STATE C ONSUL TATION In accordance w ith the Commiss ion's regulati ons, the Georgia S tate official w as notified of the proposed iss uance of the amend ments. The State official had no comments

. 6.0 ENVIR ONME NTAL C ONSIDE RATION The amen dments change a requi rement with respe ct to th e ins talla tion o r use o f facili ty com pon ent s l oca ted wi thi n th e re str ict ed are a a s de fin ed in 10 CF R P art 20. Th e N RC sta ff has determined that the amendments involv e no significan t increase i n the amounts an d no significant change in the typ es of any effluents th at may be rel eased offsite and tha t there is no significant inc rease in i ndividu al or cumula tive occup ational rad iation ex posure. The Commission ha s previou sly issu ed a proposed finding that the a mendments inv olve no significant haz ards conside ration, and the re has been n o public comment on such fin ding (71 FR 15223

). Accordingly , the amendments mee t the eligibi lity cri teria for categorical exclusio n set forth in 10 CFR 51.22(c)(9

). Pursuant to 1 0 CFR 51.22 (b) no envi ronmental impact statement or environmenta l assessment n eed be prepa red in conne ction wi th the issuance of the amendments.

7.0 CONCL

USION The Com missi on has concl uded, based on the consi derati ons di scusse d abov e, that: (1) th ere is reasonabl e assurance tha t the health and safety of the p ublic w ill not b e endangered by operation i n the proposed manner, (2) such activiti es wil l be condu cted in compl iance w ith the Commission's re gulations, and (3) the issua nce of the amendments will not be ini mical to the common defense and security or to the health and safety of the p ublic.Attachments:

1. Tabl e 1 - L OCA M CR Ra diol ogical Dose Analy sis In put Pa rameter s 2. Tabl e 2 - M CR Atm osphe ric Di spersi on Fac tors Pri nci pal Con trib utor: D. Chu ng Date: May 25, 2006 ENCLOSURE 1 Table 1 LOCA MCR Radiologic al Dose A nalysis Input Parameters PARAMETER VALUE Contai nment V olume 2.6X10 5 cub ic fee t (ft 3)Contai nment L eakage R ate 1.2 % per day Seco ndar y C onta inme nt B ypa ss L eaka ge 0.9% of 1.2% per day Iodin e Form Elemental Organic Partic ulate 91%4%5%Standby Gas Treatment System Fi lter Efficiency 95% iodine, 0% noble gases MS IV l eaka ge 250 standard c ubic feet per ho ur Contro l Roo m Env elope Volu me 93, 500 ft 3 Contro l Roo m Occupa ncy F actors 0-8 ho urs 1.0 8-24 h ours 1.0 1-4 days 0.6 4-30 days 0.4 MCR Brea thing Rate (0-30 days)3.47X10-4 cubi c meters (m 3)/sec Filte red Outs ide A ir Inta ke Rate 400 cfm Unfilt ered In take Ra te 110 cfm KI Administered 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> aft er start of LOCA MCR Filt ered R ecircu latio n Rate 210 0 cf m Filter Efficiency 95% iodine, 0% noble gases ENCLOSURE 2 Table 2 MCR A tmospheric Dispe rsion Factors x/Q (se c/m 3)Release Po int->Unit 1 Con tainment Unit 2 Con tainment Plant Stack Recep tor ->MC R In take MC R In take MC R In take 0-2 hr 9.90E-4 1.26E-3 4.85E-6 2-8 hr 3.97E-4 3.87E-4 1.17E-6 8-24 hr 4.3E-4 4.17E-4 9.69E-7 1-4 day 3.22E-4 3.56E-4 8.27E-7 4-30 day 2.62E-4 2.37E-4 5.49E-7 Edwin I. Hatch Nuclear Plant, Units 1 & 2 cc: Laurence Bergen Oglethorpe Pow er Corporation 2100 E. Ex change Place P.O. Box 134 9 Tucker, GA 30085-1349 Mr. R.D. Ba ker Manager - Li censing Southern Nucl ear Operating Compa ny, Inc.P.O. Box 129 5 Birmingham, AL 35201-1295 Resident Insp ector Plant Hatch 11030 Hatch Parkway N.

Baxley , GA 31531 Harold Reh eis, Director Department of Natural Resources 205 Butler S treet, SE., Suite 1252 Atlanta, GA 3 0334 Steven M. Jackson Senior Engineer - Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 3 0328-4684 Mr. Reece McAlis ter Exec utiv e Secr etary Georgia Publi c Service Commission 244 W ashington St., SW Atlanta, GA 3 0334 Arth ur H. Do mby , Esq.Troutman Sande rs Nations Bank Plaza 600 Peachtree St, NE, Suite 5200 Atlanta, GA 3 0308-2216 Chairman Appli ng Coun ty Co mmissi oners County Co urthouse Baxley , GA 31513 Mr. Jeffrey T. Gasser Executiv e Vice Pres ident Southern Nucl ear Operating Compa ny, Inc.P.O. Box 129 5 Birmingham, AL 35201-1295 Mr. G. R. Fred erick, General M anager Edwin I. Hatch Nucle ar Plant Southern Nucl ear Operating Compa ny, Inc.U.S. H ighwa y 1 N orth P.O. Box 201 0 Baxley , GA 31515 Mr. K. R osan ski Resident M anager Oglethorpe Pow er Corporation Edwin I. Hatch Nucle ar Plant P.O. Box 201 0 Baxley , GA 31515