ML20137C799

Proposed Tech Specs Deleting 12 License Conditions from Unit 1 Operating License & Two License Conditions from Unit 2 Operating License

ML20137C799
Person / Time
Site:	Byron
Issue date:	03/14/1997
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20137C794	List: ML20137C791 ML20137C799
References
NUDOCS 9703250131
Download: ML20137C799 (25)

Text

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ATTACHMENT B-1 PROPOSED CHANGES TO FACILITY OPERATING LICENSE NPF-37 BYRON STATION UNIT 1 Affected Pages:

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Attachment 1 Attachment 2 l

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• Page is included for continuity only. No changes are identified.

Note: Markups _are provided on copies of the operating license that were provided j by the NRC. Several pages had handwritten notes and stamps, which were not I masked or changed in Comed's markup.

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9703250131 970314

- PDR ADOCK 05000454 p PDR t

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^ LiCf"%QT%MY NUCLEAR REGULATORY COMMISSION s FILE COPY

, 1E WASHINGTO N, D. C. 30355 W...../ .

D0 G 6 0VE 1

COMMONWEALTH EDISON COMPANY

. . . . . DOCKET NO. STN 50-454

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BYRON STATION, UNIT NO. I' P FACILITY OPERATING LICENSE ,

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i License No. NPF-37 1.

The Nuclear Regulatory Commission (the Comission) has found that:

4 A. .

i The application for license filed by Commonwealth Edison Company i

(licensee), complies with the standards and requirements of the i

Atomic Energy Act of 1954, as amended (the Act), and the Commis-sion's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; i

8.

i' Construction of the Byron Station, Unit No.1 (the facility) has been substantially completed in conformity with Construction Pemit

No. CPPR-130 and the application, as amended, the provisions of the i . .

.. Act, and the regulations of the Commission; . _

C.* _ , ,

The. facility will operate in conformity with the apr aication, as amended, the provisions of the Act, and the regulations of the Com-m Eff~on (except as exempted from compliandt in Section 2.D below);

l' D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set i

- forth in 10 CFH Cha Section 2.D bel'ow);pter I (except as exempted from compliance in ll .

. E.

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Comonwealth Edison Company is technically qualified to engage 'in the i

activities authnrized by this license in accordance with the Comis-i sion's regulations set forth in 10 CFR Chapter I; F.  :

j Commonwealth Edison Company has satisfied the applicable provisions of 10 CFR Part 140 " Financial Protection Requirements and Indemnity Agree-

/ ments," of.the Comission's regulat!ons; '

G .-

I The W issuance of this license will not be inimical to the common defense

?~:rity or to the health and safety of the public; l

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After weighing the environmental, economic, technical and other benefits

.pf.the facility agaf ast environmental. and other costs and considering '

. available alternatives, the issuance of this-Facility Operating License No. NPE-37, subject to the conditions for protection of the eavironment set forth in the Environmental Protection Plan attached as Appendix B, is in accordance with 10 CFR Part 51 of the Commission's regulations' and all* applicable requirements hcVe been-satisfied; and I.

The receipt, possession, and use of. source, byproduct and special '

4 nuclear material as authorized by this license will be in accordance with the Commission's regulai: ions in 10 CFR Parts 30, 40 and 70. i

2. .

Pursuant February 12,to1985, approval by the Nuclear Regulatory Commission at a meeting License No. NPF-23, is!.ued on Octoberthe License for Fuel Loading and Lo 31, 1984, is superseded by Facility Operating License No.

(the licensee) to read as follows:

NPF-37 hereby issued to Commonwealth Edison C l

A.

The license applies to the Byron Station, Unit No. 1. a pressurized i

, water nuclear reactor and associated equipment (the facility), owned )

by Commonwealth Edison Company. The facility is located in north cen-tral Illinois within Rockvale Township, Ogle County, Illinois and is diiscribed in the licensee's " final Safety Analysis Report", as supple; "

1 mented supplemented and amended, and in the]0%Aedlicensee's Environ and amended. .

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B.

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Subject to the conditions and requirements incorp' orated herein, the i t Comission hereby licenses Commonwealth Edison Company:

(1)

' Pursuant to Section 103 of the Act and 10 CFR Part 50 to possess, use and operate the facility at the designated

' location in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part .70, to receive possess and use at any time special nuclear material as rea,ctor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the ,

SafetyAnalysisReport,assupplementedandamendedginglM ~ ,Vt

/ (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70 possess, and use at any time.any byproduct, source,and to receive, special nuclear material as sealed neutron sources for reactor startup, f

sealed sour:es for reactor instrumentation and radiation moni-

toring equipment calibration, and as fission detectors in amounts as required;

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(4)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive

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'or s,pecial.nuclea,r material without restriction -

c emical or to hpos physical form, for samp1e analysis or instrumenf calibration

'or associated with radio, active apparatus or components; and

~ (5) but not separate, such byproduct and special nu t

as may be produced by the operation of the facility.

C.

This license shall be deemed to contain and is subject to the conditions specified in the Comission's regulations set forth in 10 CFR Chapter I

and is subject to all applicable provisions of the Act and'to the rules.

I regulations, and orders of the Comission now or hereafter in effect; i and below: is subject to the additional conditions specified or incorporated (1) Naximum Power Level The licensee is authorized to operate the facility at reactor core power ower levels not in excess of 3411 megawatts thermal (100%

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accordance with the conditions 6 i w wi.11;;;;:. h specified herein;and e peepe :ti:::1 t;.te *

':rt.;, t;;t; ::d ether it T ide.,tif1W ii, Mt:fzzt 1 te- r tMsliw.... JuilL.;w kt:d:: ;;;;tfied. "tt M n nt 1

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(2) Technical Specifications i

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' The Technical Specifications contained in Appendix A as revised through Amendment No. g f,3 -.'

I and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are <

hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the

Environmental Protection Plan.

St\ehk (3)

Pos\-Fuef-loadink Initfal Teat PrAgram s (Sectish 1(, SERY i

'Any c nges.to the itial Tes Program scribed i ection'14.

! .. ,/r ' of t 50 s

SAR made ccordan ith the visions f 0 CFR ort in cor nee ith 0.59 j

mo h o%11 be f\uch ange. r wit tii one O

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(4)

_Seikiiic andgynamft Ouslifffattori (SectiM 3.10s SSER &)*

Prior o tartup foi

- ng the fi refueling ou e, the license shall compl ly qualify Westinghous Prote i System E- ),for oth uclear St~ m 300 Process i

and lan of P nt app cati s, inc ding y har ply re System changes, if ound ne ssary. .

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(5) Equbment OuatificptionT(Sect 4on 3s11. ESER #5s SSEW6) j All e etrical uipment thin the ope of 10 50.49 a

mus be nvir tally un ified N ember 1 .

! (6)

The licensee shall implement and maintain in effect all* provisions of the approved fire protection program as described in the licensee's Anut..

L Fire Protection Report C 7 x 3 f T - t-S and as approved,in the -

gio '-

! SER following datedprovision:

February 1987 through Supplement No 6, subject to the Cf .q . y I

The licensee may make changes to the#approved fire protection

}

. program without prior approval of the Consission only if those

! changes would not adversely affect the ability to achieve and

!' maintain safe shutdown in the event of a firw. -

(7) Coc o com Htagen Factors (SectionA8.2. 4SER #4f Un1 s

! the e staff et ines th t he test s do atsuport ge, the 1 nsee thall, rior to sta in ;he first efueling o ge, move t range and '

p foll cent s for

! the O CE RANGE nuc car ins t on Uni i the clear inyrumetatio cabin 'l J to he mai con 1 bo rd PM05J.'

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(A). TM( Item /I.F.1,\ Ioding/ Particulate /lamplino (Sectiom11.5/

4 155Eli W Prio to startup lowing the est r6fue n outage t li-i scen ee hall d nst te that he operati io 'ne/ rtic

! s plin syst ate will rform ts i tend funct%n.

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~ (9)

_ Emergency / Response 9a'pab(11tyr(NUR(G-0717, Supplerp The- ensee sh as ired by t chme compi the ese' ency / res e cap lities

~

2 th ra di ot s li ns . ensef 1 is nc o-(10) miliability of/DieseJ-Generattrs (Section 9'.5 4.1, SERV 5SER

/ Pri\ to s rtup foll

/ in the first re eling o tag , the con-trols and onitoring i shall e ynamically qu ifiedntation for t the local ntrol panels install on a free st n ing floor r location r shall be

. . . .ner -( c ding-the us u ted panel such a man-that he o vibratio iso atton unt as necessary) wil not reisuitreaso ble a suranc that ny i uced ibrations in yelic o the inst nt. tigu failur for t!e'ex

! ctet life deled 4 (11)

Geheric ImpNeattorALetter 83-28%(Reouired Actihns Base #'on Ge

. of SaleAATW5 Events) / "

The l' see shall subm responsest # ond/ implement

- ments Generic Lett 3-28 on a s ec e which i co istent require-with 198 ha given in i s le ters date Nov er 5, ,:

Jun .1, 1984 nd Oct er 10 83, F ruary 29~,

984 dekd (12)  ;

For% 1 Federal Emergen'cy Management Agency Finding In th e nt that the RC inds that ack of pro es in com-pletto of the procedu in the Feder Agene final rule, 4 FR Emergency Na ement Part 350, an indicati that a majo ad* uate su tantive tate of prer lem exists in chi ving or m nta ning an

_ . . C Sectio 50.54 s)(gene 2)prepar wi appl .

ness, he pro isions of 10 (13) Contr .

comJentilation Syst/m (Section 6.5,1, SSER, #5, SSFf#6)*

'.Prio to ly 1, 1985, licensee s 1 incorporate tions, necessary, t ifica-system nsure that th con' trol room 11ation sthe it ia y be speciused du ng n accident o rotect op ator within Cri d in CFR 50 Appen ix A G eral D ign ria .

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I dektkd j (14) Turbine Missil/s (Section 3.5 I.3. SSER #5)

The 11 ns shall vol ically insp ct 11 th pressur urbine rotors unt.11 a every third fueling o age, 1

rbine system intenance p based he manufa ur 's calcul to of missil g eratio prob liti is app ved the sta .

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(15) .0ceratino Staff Egnerience Recuirements /Section 13.1.2.I

(

ISER #5) licensee s 11 have licensed sen or ope tor on ch sh t who has ind at less six months of hot o eratin exp rience o a similar ty e plant, cluding t leas six week at pow r levels great 'r than who s had start-up and sht down e perience, e' cept as of full ower and i fo11 r those shifts w re s ch an indivic avalla le n the plant staff, an , visor shall al sovided not s

who has d at least four yea ' power plant a rience, includin two years of nuclear ant experience, i d who has had least one year of e erience on shift ,s a licens nior operator at a ilar type facil ,y . Use of advi r who were licensed n at the R0 lev 1 will be evaluat o a case-by-case si Advisors sh lit be traine on p ant pr)cedures, tech ical specifi tibns and plant ystem and shall be examin on theses top cs at a level uffici t to assure familia ity with t e pla nt.

i For e ch shift the remai der of th shift c w shall be i

trai ed as to t e role o the advis s. The e advi ors shal be retain until he experien level ident fied 1 in e first sen nce ove have been achie ed. The NRC i sh 1 be notified t 1 ast 30 days pr r tc the date hat i

" th licensee proposes o release the advisors from fu ther service.

AMENDMENT NO. 67

'JM S 1995

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4 (16) Deleted.

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The facility requires ^ exemptions from secte4a requirements of

D.

?.;;;;di::: A r . a 3 to 10 CFR Part 50. Th::: i;:lede (.) ew

:;-pilun i,- the requi _-- _,d> v7 Faragrapn iii.D.2(b)(ii) '

l j , ndix J, the testing of containment air locks at ties em  !

ont nt integrity is not required (Section 6.2.6 he  :

5ER), an exemption from GDC-2 of Appendix A, t requirement i

that struc es, systems and components importa to safety be  ;

. designed to w tand the effects of natural enomena such as j earthquakes (Sect 3.10 of SSER #5), (c' n exemption from i

, GDC-13 and GDC-17 of endix A,.the r 'rement that 1 instrumentation be provi to monit variables and systems

over their anticipated range an he requirement that i provisions be included to_ mini the probability of losing

electric power (Section 9.5 . o ER #5), (d) an exemption

from GDC-19 of Appendix he requir t that the control room 4

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have adequate radiatio rotection to pe access and toccupancy under acc nt conditions (Section .1 of SSER #6) ,

i nnd (e) an exemp n from the requirement of Sec n IV.F of l Lppendix E th a full participation emergency plan g exerciue  !

. be conduct within one year before issuance of the f t i sperati license for full power and prior to operation a ve ! %

af ed power (Section 13.3 of SSER #6). These exemptions e i s orized by law and wi" ret e-d==a-- life or orocerty or th#

1 AMENDMENT NO. $7,85

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er- - defe se sad <* cur 3tf :nd ere etherwi;, in th; ;;5?ic interest.

Therefer.,f t.

WitE~th'E sr:,tt:;:

ting ::;;ptign; Of theseere h;r:5y cemated ex;;ptica; oursuant ihe i.uiiity +a'!0 trato

.111 eper;te, 30.12.

the

.eytent ::th:rized herete, 4: confermity w;ih ine applicativ... :: e-ded, the ;rrJf:f:n; ef the Act, end th; r;1e; end r;gi?: tier ef the Cr :f::fon, w&k wss.

E, GEco shall fully implement and maintain in effect all provisions of the Commission approved physical security, guard training and . Eknad,.

4 qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search 4g gg 4

Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the g_q_g authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " Byron Nuclear Power Station Security Plan," asith rrei:ien; avhmitted thre;;h J: ::ry 14,1^00, " Byron Nuclear Power Station Security Personnel

' Training and Qualification Plant"-with rew;;ivu. submiii J thr:2;h Sept--Ae- 26. 19" ContingencyPlan(5;-and"ByronNuclearPowerStationSafeguards

" with revisien: seb-itted thr ;gh Jely OO,1985.

Chea;-e ==de in meenrdance-with 10 CF", 73.50 shat' be imp 1...~nied in

rt nce eith forth therstm

F. Except as otherwise provided in the Technical Specifications or Eavironmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center 1 -

via the Emergency Notification System with written followup within thirty days in accordance with the procedures described in 10 CFR 50.73(b), (c) and (e).

G. The licensee shall have and maintain financial protection of such type and i

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 j cl aims.-

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I *The Security Personnel Training and Qualification Plan and the Safeguards - ,

Contingency Plan are Appendices to the Security Plan.

A 4

i H. 'This license is effective as of the date of issuance and sha11 expire at Midnight. 0,ctob.er 31,2024..

~ FOR THE NUCLEAR REGULATORY COMMISSION l

/ -

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

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[ Appendices: ,

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n3. Appendix A - Technical I Specifications (NUREG-1113) l'4. Appendix B - Environmental Protection Plan '

Date of Issuance: FEB 141985 O

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l ATTACHMENT 1 0/E This attachment iden fies certain preoperat nal tests 'and other items which must timingbe forcompleted to t e Comission's satis action and identifies the required

,thei.r ,,c,tuple on., -

l A.. ,Preoperattonal test VA 4.11 (auxi) ary building' ventilation) shall be '

'July completed, 1, 1985. including the esolut 6n of any retest deficiencies, prior to  ;

B. For initial startup test p m tests in the'50%, 75%, 90% and 100% power sequences, procedures wM ha shall be provided to Re f n III imen approved by both the Station and PED date of r.he applicable equence. least 30 calendar days before the start 1 l

C. Prior to July 1,19 . the licensee s 11 c the Control Room (VC), Auxiliary Buildi lete integrated testing of -

i (VA , Miscellaneous Electric }

Equipment Room ( E), and ESF Switchgear om VX) ventilation systems in all modes of o ration to demonstrate tha the Control Room envelope can i be maintained t a positive 1/8 inch water uge differential pressure with respect to adjacent areas.

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LiCm2 /gTHOalTY FILE COPY .

ATTACHMENT 2 { -}- ((,rgy~ ,

EMERGENCY RESPONSE CAF/,BILITIES The 11 .

nsee shall complete. the following requirements of

- ment #1 .n.the sch.edule.noted below UREG-0737 Supple-1.

De iled Control Room Design' Review (DCRDR) l The 1 ,

ensee shall s'ubmit the final sumary report for the DCRDR by 4 ,

, Decemb 1, 1986. **

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2. Regulator Guide 1.97. Revisil5h 2 Como ance i

The licensee describing h ha11' submit by March ',1987, a preliminary report.

sthe requirements of egulatory Guide.l.97, Revision 2 havebeenorwillbemet.

1987, the NRC approvesthe final t ettport and a se edule.for implementation (

DCRDR by arch 1,1987).

3.

Upgrade Emergency 094 ting Procedures (EOPs)

The licensee shall submi a Procedures Generation Package within 3 months of NRC approval f estinghouse Owners Group (WOG) Emergency Procedure Guidelines tPG) the up9raded E0Ps b ed on vision 1. The licensee shall implement l i

, approval of WOG EP Revisio n K.1. E0Ps Revision 1 within 12 months of NRC ~

4. Emergency Respo e Facilities )

The licensee logical A del hall implement the Eme ency Response Facility meteoro-by January 1,1986.

5. Safety Parameter Display System (SPDS)

The 1 nsee shall have SPDS operational b arch 30, 1985.

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! i ATTACHMENT B-2 i l

PROPOSED CHANGES TO FACILITY OPERATING LICENSE NPF-66 BYRON STATION UNIT 2 i

Affected Pages:

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3a 4

5 Attachment 1  ;

Figure 1 l

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• Page is included for continuity only. No changes are identified.

Note: Markups are provided on copies of the operating license that were provided by the NRC. Several pages had handwritten notes and stamps, which were not masked or changed in Comed's markup.

l-f I

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un itcy

/ ~,o UNITED STATES

[ " ) ,, j NUCLEAR REGULATORY COMMISSION g a wassiNoToN,0. c. 20sss e j i t

%, . . . . . sf COMMONWFALTH EDISON COMPANY j

DOCKET NO. STN 50-455  !

BYRON STATION, UNIT 2 FACILITY OPERATING LICENSE 4 4 License No. NPF-66

1. The Nuclear Regulatory Commission (the Commission or the NRC) has found that-1 1

A. The application for a license filed by Commonwealth Edison Company (the licensee) complies with the standards and reouirements of the Atomic Energy Act of 1954, as amended (the Act), and the i Commission's regulations set forth in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly l made; B. Construction of Byron Station, Unit 2 (the facility) has been substantially completed in conformity with Construction Permit No.

CPpR-131 and the application, as amended, the provisions of the Act and the regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the regulations of the Commission (except as exempted from compliance in Section 2.D.

4 below);

D. There is reasonable assurance: (i) that the activities authorized by this operating license 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 (except as exempted from compliance in

~

Section 2.D. below);

E. Commonwealth Edison Company is technically qualified to engape in the activities authorized by this license in accordance with the Commission's regulations set forth in 10 CFR Chapter I; F. Commonwealth Edison Company has satisfied the applicable provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; I

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G. I' The issuance of this license will not be inimical to the comon

defense and security or to the health and safety of the public; H.- After weighing the environmental, economic, technical, and other

. benefits of the facility against environmental and other costs and  !

i considerino available alternatives, the issuance of Facility Operating License No. NPF-66, subject to the conditions for protection of the  !

environment set forth in the Environmental Protection Plan attached {

as Appendix R to License No. NPF-37, issued February 14, 1985, is in accordance with 10 CFR Part 51 of the Consnission's regulations and all applicable requirements have been satisfied; and I.

The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the Comission's regulations in 10 CFR Parts 30, 40 and 70.

2. Based on the foregoing findings regarding this facility, Facility  !

Operating License No. NPF-66 is hereby issued to Comonwealth Edison i Company (the licensee) to read as follows:

i A. This license applies to Byron Station, Unit 2, a pressurized  !

water reactor, and associated equipment (the facility) owned by  !

, Comonwealth Edison Company. The facility is located in north

. central Illinois within Rockvale Township, Ogle County, Illinois .,r, and is described in the "yr;,/C..;Jae;d Ct;;;;;';3 Final Safety Analysis Report, as. supplemented and amended, and in the licensee's .

l Environmental Report, as supplemented and amended. k Ltcen,u's g p Md B. Sub,iect to the conditions and requirements incorporated herein,  !

the Comission hereby licensest Co d E4.- Coq (twEd) i 9

(1) C E x a d th E M - t 2,y fCCCs h pursuant to Section  !

103 of the Act and 10 CFR Part 50, to possess, use and operate the facility at the designated location in  !

Ogle County, Illinois, in accordance with the procedures '

.and limitations set forth in this license; 4

(2) -Cf6er Dursuant to the Act and 10 CFR Part 70, to receive, l possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for  ;

storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended-(3) . Ceco, ursuant p% to the Act and 10 CFR Parts 30, 40 and 70, to ~

receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources- for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required;

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(4) GemE4, pursuant'to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and t

(5) 'GenEds pursuant to the Act and 10 CFR Parts 30, 40 and 70, to posses, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This license shall be deemed to contain and is subject to the '

conditions specified in the Connaission'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:

(1) Maximum Power tevel

! The licen:ee is authorized to operate the facility at

- reactor core power levels not in excess of 3411 megawatts-thermal (100 percent rated power) in accordance with the conditions specified herein. %e it;;. id::ti.'i 4 ;n e** - M -1 I t: thi: 1i:;r.se .i. 11 L. so yleted ::-

mitid AAt :h;...t 1 is he.et, inuv.rerei.u inie this 1/k.nse.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A (NUREG-lll3), as revised through Amendment No.'If and m ! H hy A.tt -h;,...t 2 te T F 00, and the Er.vironmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, i 1985, are hereby incorporated into this license.

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' Att::t- t 2 m t:ir.; . ... .lun iu App... dix A ht:h i:-

h;r .i; in;;re:7.i.d iniu inis liu.u... The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

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AMENDMENT NO. 67

'JM 6 1995

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i delektd (3) Initial / Test Procras/

Any anges to Initial ta up Test Pr ra described l in pter 14 o the FSAR ma' in accordance th the i

pro is ons of R50.59/1 1 be report i accordance i wi h 5 59 with onefonth such ch ge.

deleJ<dGuide.l.97.

Reaula<:ory, (b Revision 2 Comol/ance (4)

The ic see shall subai by Mar 1 1987, a reli ary repo escribing h e requir ts of Regu t Guide 1.97, vision 2 hav en or wil met. The ensee shal s it by Sep er 1,198 , t e final re and a se dule or impi nt ion (as using he NRC pro s the DR by M ch 1 1987).

(5) Deleted.

AMENDMENT NO. SJ, 85

l

. +o D. The facility requires m exemptions from the reouirements of A;;M4 A to 10 CFR Part 50,. 8:n;ne !!!.".?(b)f fi) :f th: ::: tin; f ::nt:fa-rent :f- !: & Ot tir:: t:r ::nt:ia... ni ini.3,it) is an 7:; fn L (GG 5ecuan 6.2.6).

This emption authori ed by la , will ot present an undue k to the ublic ealth and s fety, nd is co siste with th co n defense nd curity. This ex tion is he eby ranted. ie ! ecial circumst c regarding the x ption are id ified in the 'erenced section o he safety evalua on report and e supplements ereto.

This ex fon is granted p uant to 10 CF .12 (51 FR 3 ) 6 dated October 7,1986). With t s xemption, e f cility will ope ate, to the xten authorized erei in conf rmity ith the a plic tion, as ame ded, t e provisi s of t Act, nd the rules and regula ions of t Comiss on.

An exemption was previously granted pursuant to 10 CFR 70.24. The exemption was granted with NRC materials license No. SNM-1916, issued l March 4, 1985, and relieved the licensee from the requirement of havina

a criticality alam system. Therefore, the licensee is exempted from the criticality alarm system provision of 10 CFR 70.24 so far as this section applies to the storage of fuel assemblies held under this license.

E. The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the licensee's Fire Protection Report thr: 9 'P:t

• and the i licensee's letters dated September 23,1986, October 23, 1986, 1 November 3, 1986, December 12 and 15, 1986, and January 21, 1987, l and as approved in the SER dated February 1982 through Supplement i j No. 8, sub,iect to the following provision:  !

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and i

maintain safe shutdown in the event of a fire. )

l M Ed .

F. VE(o shall fully implement and maintain in effect all provisions of the Comission approved physical security, guard training and Anlal i

qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search

1. k 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, which contain 6 '7-98 i Safeguards Infomation protected under 10 CFR 73.21, are entitled: " Byron Nuclear Power Station Security Plan," n'th -avie 4a= W itt:d thre"gh ha ;r) M,49884 " Byron Nuclear Power Station Security Personnel Training and Qualification Plan," etth =vistun; 5.5,Titted +hre!sh Sep.muer 26,146+ and " Byron Nuclear Power Station Safeguards Contingency Pland 9th nvie vi.s sui,mi Li;d n-angh .1oly an_1 cat.

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G. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirments contained in Section 2.C of this license in the following manner: initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC Operations Center via the Emergency ,

Notification System with written followup within thirty days in  !

accordance with the procedures described in 10 CFR 50.73(b), (c),  !

and (e).*

H. The licensee shall have and maintain financial protection of such j type and in such amounts as the Comission shall require in '

accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims. 1 l

I.

This license is effective as of the date of issuance and shall  !

4 expire at midnight on November 6, 2026.

FOR THE NUCLEAR REGULATORY COMMISSION If Harold R. Denton, Director {

Office of Nuclear Reactor Regulation Attachmenti:

1. M Itr: te h e r; ht:d A Revision to Appendix A - l Technical Specifications (NUREG-1113)

Date of Issuance: January 30, 1987 PD#3 RAB P OGb./

[PD#3 %nitz LOlshan* CVogan Wlambe Rut) erg

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..a- - ,.n...a - x -w ATTACHMENT 1 TO BYRON STATION UNIT 2 OPERATING LICENSE NPF-66 This at,tachment identifies specific items which must be completed to the Commission's satisfaction in accordance with the operational modes as identified low:

A. The preoperational tests and testing deficiencies in Attachments A I and B, respectively, of the November 3,1986 letter from K. A. ger i on, as modified by the January 14, 1987 letter fr o to H.Ainger K. A. R. De'h(to H. R. Denton, shall be completede with in accorda the schedule commitments contained in those attachments.

B.

\

Until testing of t e Unit 2 Auxiliary Building ventilption system is complete, includn(g post test review and approval bfPED, the license shall not operate cyton Unit 2 at power levels ex eding 30%, unless the Auxiliary Building \(CCS leakage can be show to be below the i

corresponding limit presinted in Figure 1 of i e October 24, 1986 letter i S. C. Hunsader to H. R. Dhton. Leak rate temination shall be in i accordance with the October 0,1986, let r, S. C. Hunsader te H. R. Denton, and performed e times:

1. Prior to exceeding 30% power,

2. During the first two weeks pril 1987, and 1

3. During the first two wee of Ju y 1987.

4. Should Unit 2 be in a outage cond ion during the periods specified in paragrap s B.2, B.3 abo y, the leakage rate deteminations sha 4 be performed witn n the first two weeks after returning power.

In the event that tal leakage during any of t ese tests is GREATER than the value for th orresponding power level, the icensee shall, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, initiat CTION to reduce the leakage to a acceptable value or reduce power i accordance with Figure 1 within the ext 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

C. Prior to e eeding 5% power, the licensee shall seal a 1 construction design p etration openings in designated' fire barriers. Completion of nine(9 seals may be accomplished as requested in the S. C. Hunsader to J. . Keppler letter dated January 13, 1987, and in add) ion, pene): rations may be left unsealed to facilitate a requireme(n of a plant mo ification or plant maintenance requirement; however, the 1 ensee s all provide compensatory measures.

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20. 25. 30. as. 40. 5 50. ss. so. T :-

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RUXILIRRY BUILoINo ECCS LERK RATE fORL'/l.R) i FIGURE 1- MAXIMUM POWER LEVEL VS. ECCS EQUIP .NT LERKAGE N..

Assumptions:

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'25 CFM Control Room Unfiltered Inteakage g g Thyroid Dose' Calculations Include Contributions From:

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1. Containment Leakage; . y-

. 2. Massive ECCS Leakage (50gpm for 30 min. at g '.

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-3 . Th i'r t y ( 30 ) day ECCS Continuous Leakage i.,,..- . . - . .

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L ATTACHMENT C EVALUATION OF SIGNIFICANT HAZARDS CONSIDERATIONS l

Commonwealth Edison has evaluated this proposed amenoment and determined that it involves no significant hazards considerations. According to l 10CFR50.92(c), a proposed amendment to an operating license involves no significant hazards if operation of the facility in accordance with the proposed amendment would not:

1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3. Involve a significant reduction in a margin of safety.

Commonwealth Edison (Comed) proposes to delete 12 license conditions from the Byron Unit 1 operating license and two license conditions from the Byron Unit 2 operating license. The license conditions to be deleted have been satisfied and are no longer _ required to be listed in the operating license. The conditions to be - 3

-deleted from the Unit 1 license are 2.C.3, " Post-Fuel Loading initial Test Program," 2.C.4, " Seismic and Dynamic Qualification," 2.C.5, " Equipment

- Qualification," 2.C.7, " Control Room Human Factors," 2.C.8, "TMI Item II.F.1, lodine / Particulate Sampling," 2.C.9, " Emergency Response Capability," 2.C.10,

" Reliability of Diesel Generators," 2.C.11, " Generic Letter 83-28 (Required Actions based on Generic Implications of Salem ATWS Events)," 2.C.12, " Formal '

Federal Emergency Management Agency Finding," 2.C.13, " Control Room Ventilation System," 2.C.14, " Turbine Missiles," and 2.C.15, " Operating Staff Experience Requirements." The conditions to be deleted from the Unit 2 license are 2.C.3, " Initial Test Program," and 2.C.4, " Regulatory Guide 1.97, Revision i 2." Other license conditions are revised to delete parts that no longer apply.

Certain items in the licenses have been revised to reflect revisions to the referenced documents. Throughout the license, editorial changes are proposed for clarity and consistency.

l 1

._. . ~. _ . _ _ _ _ _ . . . _ . . _ _ _ . . . _ . _ __

s

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A. The proposed changes do not involve a significant increase in the probability }

or consequences of an accident previously evaluated. l i

i The initial conditions and methodologies used in the accident analyses remain i unchanged. The proposed changes do not change or alter the design l assumptions for the systems or components used to mitigate the  ;

consequences of an accident. Therefore, accident analyses results are not  !

impacted. l The license conditions were one-time commitments that have been satisfied.  !

There are no physical changes to the facility, and all operating procedures,_ l

. limiting conditions for operation, limiting safety system settings, and safety j limits are unchanged. Removal of these license conditions is appropriate and l safe. l i

i Therefore, the proposed changes do not involve a significant increase in the l probability or consequences of an accident previously evaluated, j B. The proposed changes do not create the possibility of a new or different kind {

of accident from any accident previously evaluated. l l

Many of the proposed changes delete references to items that have been _i completed. The NRC required these items as a condition of granting the )

license. Since they have been satisfied as intended, deleting them is ]

administrative.

None of the proposed changes affect the design or operation of any system, structure, or component in the plant. The safety functions of the related structures, systems, or components are not changed in any manner, nor is the reliability of any structure, system, or component reduced by the revised surveillance or testing requirements. The changes do not affect the manner by which the facility is operated and do not change any facility design feature, structure, system, or component. No new or different type of equipment will be installed. Since there is no change to the facility or operating procedures, and the safety functions and reliability of structures, systems, or components are not affected, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. _j l

i The remaining changes are editorial in nature and have no impact on plant j operation or design. 1 i

l 2

I l .

C. The proposed changes do not involve a significant reduction in a margin of l

safety.

i The proposed changes to the Operating License are generally administrative in -l nature and have no impact on the margin of safety of any Technical ,

Specification. There is no impact on safety limits or limiting safety system '

settings. The changes do not affect any plant safety parameters or setpoints.  !

The operating license conditions have been satisfied, as required. There are ,

no changes to the conditions themselves. Therefore, the proposed changes do not involve a significant reduction in a margin of safety. ,

Therefore, based on the above evaluation, Commonwealth Edison has concluded  !

that these changes do not involve significant hazards considerations. r i

r l

r l

l

ATTACHMENT D l ENVIRONMENTAL ASSESSMENT l

Commonwealth Edison has evaluated the proposed amendment against the criteria for identification of licensing and regulatory actions requiring environmental '

assessment in accordance with 10CFR51.21. It has been determined that the proposed change meets the criteria for a categorical exclusion as provided for under 10CFR51.22(c)(10). This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10CFR50 that changes recordkeeping, reporting, or administrative procedures or requirements.

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