ML20154M996

Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete

ML20154M996
Person / Time
Site:	Vogtle
Issue date:	10/15/1998
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20154M993	List: ML20154M991 ML20154M996
References
NUDOCS 9810210113
Download: ML20154M996 (8)

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C. This license shall be deemed to contain 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, regulations, and orders of the Commission now or hereafter in effect; and

is subject to the additional conditions specified or incorporated below.

t (1) Maximum Power level Southern Nuclear is authorized to operate the facility at reactor

, core power levels not in excess of 3565 megawatts thermal (100 percent power) in accordance z h the conditions specified herein.

l (2) Technical Soecifications and_; 2 ;ronmental Protection Plan The Technical Specifications contained in Appendix A, as revised l through Amendment No.103, and the Environmental Protection Plan l contained in Appendix B, both of which are attached hereto, are I hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Ttf6Turveillance Requirements (SRs) contained in the Appendix A Technical /Specifi tions and dentifie below ar not re T

performeg immed tely upo implement ion of endment . ired

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M SRs S .l.9 a d 3.8.4.J shall be successf lydemondratedprforto the first entry into MODE 4 forlowing the seventh refueling.  !

(3) nttTai Startuo Test Proaram (Section 14, SERD-l Any chan s to t e initial T st Progra escribed Section 14 o 3 the FS made accordan with the rovisions f 10 CFR 50.59 all pp f

/ re rted accordanc with 50. (b) withi one month of,3 ch 1

(4) R meroency Plannina (Section 13.3, SER and SSERs 2, 3, 4, and 5) l In the eyent tha the NRC'f ds that the lack of pr gress in complefonofteprocedu in the F ral Emer y Manage ont Agen s fina rule, 44 R Part 35 , is an in tion tha a major

sub ntiv roblem e ts in ach ving or m tining a adequate p58g st e of ergency p theprovis4nsof10fRSection 5 .54(s)( ) will app y. paredness/

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• The par thetical notat n follow g the t leofmnylicense/conditjons i V denote the sec on of he Safet Evalua on Repor and/or i)4 supp)4ments 7

where the li ense c ndition s discus ed. /

1 9810210113 981015 Amendment No.fd PDR ADOCK 05000424.

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l' l (5 e Glnerato/TubeRuoture(S tion 15. 3, SER nd SSER 3)

By Ma ch 1, 88, GPC shall s it for C revie a revis d plan -specif c steam generat tube r ture ang ysis bas d on the y Wes inghou Owner' Group neric r olution /which in udes 3et.eTut r iologi 1 conse uence a alyses, nalysis f steaml e static ad in e event of over ill, an justifi ation tha systems and' i ompone ts credi.ed in t.e analy is to mi igate acc dent j conse ences are safety related. i

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l (ti) DELETED (7) b-0737 Items / 1

a. Compliance with NUREG-073 , Item II.F.2 (Section 4.4.8, SER and SS 1 and 4)

In a ordance with N EG-0737, Item I.F.2, GPC shall submit i th proposed reacto vessel level nstrumentation 'ystem

( LIS) report by une 1, 1987.

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b. ort on Safety arameter Disp y System Supplemental (Section 18. , R,SSER 6)

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GPC shall ubmit by March , 1988, a sup emental report on /

the saf y parameter di lay system as iscussed n Section [

18.2 o SSER 6.

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, c. Sup emental Summar Report on De iled Contro Room De ign j R iew (Section 1 , SSER 5)

! # PC shall submi by March 1, 88, a Supp mental S ary l

g)stgf@ Report on the etailed contr i room desi n review iscussing:

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1. the fin results of he remainin control r om surveys j (ambi t noise; ill ination; h ting, ven lation, and air nditioning; ant safet monitorin system co ter sury y; automati turbine su ervisory i strumentati comp ter survey and commu cations) d the resol tion of any human e gineering iscrepanci s (HEDs) re iting from these su veys

2. a complete ssessme of cumula ve and int active effects of the HE 1

3. the completed r view of ann ciator nu ance alarms and modifications o minimize uisance al rms and the number (

, of annunciato windows 1 . during n mal operations i

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Amendment No.

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4. documentation showing tradeoff analyses and other information used in resolv'ng HEDs

! I 5. the m thodology b which co trol room chan s were t factore into e operato training ogram j 6.

p cedures that incorpor te human factors review into the desigg ocess for future control room modifications -

(8) -2fric Coatina of Diesel Fuel Oil Storaae Tanks (Section 9.5.4.2, SSER 4)

Prior to resta following first ref ling, GPC shall j) replace the zinc ,

j' coatmg in diesel ge rator fue 'l storage tanks a coati d ]

j not conta' inc or (2) y March ,1988 provide acceptable tification

/ the staff at the pr ent fuel o' storage tank zi -based coat' g will not ect the ope bility a reliability the diesel ge ors over life of the ant as p

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s in IE C cular 77-1 If option (1) is chosen, GPC shall provide the NRC with a modification status

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report 30 days before the expiration of the license condition. J (9) AttEfHiWR acility (Section 11.4, SSERs 3 and 4) l Prior to re . art followin ueling, the' ntilation exh st of the l first 1 attemat radwaste f ility sh modified exhaust thro h HEPA f ers l alrea installed i. he au ary building AC system. '

D GPC shall provide the NRC with a modification status report 30 days before the )

Qpiration of the license condition. j (10) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No.102 , are hereby incorporated into this license. Southem Nuclear shall operate the facility in accordance with the Additional Conditions.

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D. The facility requires exemptions from certain requirements of ^ 0 CFR Part 50 and 10 CFR Part 70. These include (a) an exemption from the requirements of 10 CFR 70.24 for two criticality monitors around the fuel storage area,b(b) an exemption from

the requirements of Paragraph lli.D 2(b)(ii) of Appendix J of 10 CFR 50, pe testing of

, containment air locks at times when containment integrity is not requiredfand a Tchedula xemption rom 10 CFR 5pS4(b)(2)(i) as it perta3ns to uuc 2,6), and 62 of Ap ndix A to FR 50 for,th(spent fuel pool racksfor the time period before

{ the racks contai irradiated fuel.J The special ciriumstances regarding exemptiong b <

erse e identified in Sectio 6.2.6 Nof SSER Sggche:y. )

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H. eporting to the Commission Except as herwise p vided in t echni Specifi tions or Environmental Protectio lan,So em Nucle r shall re rt any lations the req mentA contai in Secti 2.C of th' license i the foll 'ng ma r: initial otification hall

'V be ma within nty-four ( 4) houry o the C Oper ions Center via the T' ,

Emer6ency Not cation Sys' tem withiuritten fdilow-up ' hin 30 da9s in accor ance (with the procedures described in 10 Cy.73(b); {cl and (e).

l. The Owners shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims, i

J. This license is effective as of the date of issuance and shall expire at midnight on

! January 16,2027.

l FOR THE NUCLEAR REGULATORY COMMISSION i

i /s/

4 i Harold R. Denton, Director l Office of Nuclear Reactor Regulation

Enclosures:

i 1. Attachment 1 - DELETED

2. Appendix A-Technical

i. Specifications

3. Appendix B - Environmental j Protection Plan i 4. Appendix C - Antitrust Conditons

5. Appendix D - Additional Conditions l i Date of lasuance

March 16,1987 1

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Amendment No.

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l FACILITY OPERATING LICENSE NO. NPF-81 VOGTLE UNIT 2

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C. This 1.icense shall be deemed to contain 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, regulations, and orders of the Commission now or hereafter in effect, and is subject to the additional conditions specified or incorporated below.

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(1) Maximum Power Level

, Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 3565 megawatts thermal (100 percent power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan

. The Technical Specifications contained in Appendix A, as revised

through Amendment No. 81, and the Environmental Protection Plan l contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications

and the Environmental Protection Plan.

! The Surveillance Requirements (SRs) contained in the Appendix A Technical Specifications and listed below are not required to be

performed immediately upon implementation of Amendment No. 74. The SRs listed.below shall be successfully demonstrated prior to the time and condition specified below for each

a) SRs 3 .1.8, 3.8.1.11 and 3.8.1.13 shall be successfully

, f dem strated ior to first try int 4f00E 4 f 11owing 4

tL fifth ueling tage.

Tg[ () b R 3.8 .9 shal be suc essfully d monstrated prior to e first entry into MODE 4 following the sixth refueling outage.

c) SR 3.8.1.20 shall be accessfully demonstrated at the first regularly scheduled performance after implementation of this license amendment.

(3) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No. 80, are hereby incorporated into this license.

Southern Nuclear shall operate the facility in accordance with the Additional Ccnditions.

O Amendment No. 1

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htJD f D.

The facility requires exemptions from certain requirements of ' O CFR Part 50 and 10 i CFR Part 70. These include (a) an exemption from the requiroments of 10 CFR j 70.24 for two criticality monitors around the fuel storage area,t(b) an exsmption from j the requirements of Paragraph lit.D.2(b)(ii) of Appendix J of 10 CFR 50, the testing of 1 i containment air locks at times when containment integrity is not requiredfand (c) an l (1txemption from the schedule requirements of 10 CFR 50.33(k)(1) related to  ;

(availability of funds for decommissionina the facility.jThe special circumstances regarding exemption / b and:e are " identified in Section/ 6.2.6 a#+22:5-of SSER 8, )

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An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1981, issued July 13,1988, and relieved GPC from the requirement of having a criticality alarm system. GPC and Southem Nuclear are hereby exempted from the enticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this heense.

These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions I.11tems b and c above are granted pursuant to 10 CFR 50.12. With I these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.

E. Southem Nuclear shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and )

safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The plans are entitled: "Vogtle Electric Generating Plant Unit 1 and Unit 2 Physical Security and Contingency Plan" (which contains Safeguards Information protected under 10 CFR 73.21) with revisions submitted through September 12,1996, and "Vogtle Electric Generating Plant Guard Training and Qualification Plan," with revisions submitted through March 13,1996. Changes made in accordance with 10 j CFR 73.55 shall be implemented in accordance with the schedule set forth therein.  ;

1 F. GPC shall comply with the entitrust conditions delineated in Appendix C to this license.

G. Southem Nuclear shall imp!ement and maintain in effect all provisiens of the approved fire protection program as described in the Final Safety Analysis Report for the facility, as approved in the SER (NUREG-1137) through Supplement 9 subject to the following provision:

Southem Nuclear 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.

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AmendmentNo./I

t j- i H. eporting to the Commission j Except a otherwise rovided i e Technical heificati s or Envi nmental i Protecti n Plan, S hem Nu ear shall rep any viol ions of the quireme s conta' ed in Se on 2.C cf is license in followi manner; i ial notifi ion hall a D6LCp bejdade withi twenty-fo (24) hours sIthe NR perations entervia /

! Emergency Nbtification ystem with w)ritten follo(v-up within 30 days in, ccord (with the procedures described in 10 CFR 50.73(b), (c), and (e). -

1. The Owners shall have and maintain financial protechon of such type and in such amounts as the Commission shall require in accordance with Section 170 of the l Atomic Energy Act of 1954, as amended, to cover public liability claims.

J. This license is effective as of the date of issuance and shall expire at midnight on FebnJary 9,2029.

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FOR THE NUCLEAR REGULATORY COMMISSION 1

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Thomas E. Murley, Director Office of Nuclear Reactor Regulation

Enclosures:

j 1. Appendix A-TechnicalSpecifications i 2. Appendix B - Environmental Protection

. Plan

! 3. Appendix C - Antitrust Conditions

4. Appendix D - Additional Conditions l

} Date of issuance: March 31,1989 I

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4 Amendment No.

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