ML20205J974
| ML20205J974 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/30/1999 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20205J963 | List: |
| References | |
| NUDOCS 9904120282 | |
| Download: ML20205J974 (14) | |
Text
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Attachment B Marked Up License Pages SVP 99-001
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DPR-29 Page 4 Page 5 Page 6 Appendix C DPR-30 Page 4 !
Page 5 Page 6 Appendix C l
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9904120282 990330 II~
PDR ADOCK 05000254 >
P ~' P DR $J l.
l Attachment B DPR-29 l 1
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- 3. This license shall be deemed to contain and is subject to the conditions specified in the following Comeission regulations in 10 CFR Chapter I:
Part 20, Section 30.54 of Part 30, Section 40.41 of Part 40, Sections - -
50.54 and 50.59 of Part 50 and Saction 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations and orders of the Cossiission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
A. Maximum Power level 1 Commionwealth Edison is authorized to cNrate Quad-Cities Unit No. t power levels not in excess of 2511 megawatts (thermal).
B. Technical soecifications f
The Technical Specifications contained in Appendices A and B, as revised through Ame:1dment No. are hereby incorporated in the ,
license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. The licensee shall maintain the commitments made in response to the March 14,1983, NUREG-0737 Order, subject to the following provision:
k The licensee may make changes to cournitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of the Commission as long as the change would be permitted without NRC approval, pursuant to the requirements of 10 CFR 50.59.
Consistent with this regulation, if the change results in an Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation ,
I of the change.
D. Eaualizer Valve Restriction hete
- A valves in the equalizer piping between the recirculation loops _ ,
four s all be closed at all timmt during reactor operationgc M 3 M , e Q (v.his e, peer +. u.w f.c N m .) e3,. 4 s t..a .( u .A e .u E. The licensee 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 of 10 CFR 73.55 (51 Fp 27817 and 27822), and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). 4 These plans, which contain Safeguards Information protected under l 10 CFR 73.21, are entitled: " Quad-Cities Nuclear Power Station Security Plan," with revisions submitted through September 17, 1992;
" Quad-Cities Nuclear Power Station Security Personnel Training and Qualification Plan," with revisions submitted through July 15, 1992; and " Quad-Cities Nuclear Power Station Safeguards Contingency Plan,"
i Amendment No. H+,
DRP-29 with revisions submitted through July 15,1992. Changes made in accordance with 10 CFR 73.55, shall be implemented in accordance with the schedule set forth therein.
F. Commonwealth Edison Company shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis lteport for the facility 27, 1979 and as with approved in the Safety Evaluation Reports dated July supplements dated November 5,1980 and February 12, 1981; December 30, 1982; December 1,1987 with supplement dated April 20, 1988; December 11, 1987 with supplement dated July 21, 1988; and February 25, 1991, subject to the following provision:
The licensee may make changes to the approved fire protection j
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.
G. Deleted.
H. Deleted by incorporation into 3.E above, per Amendment No. 64 dated March 19, 1981.
I. (0?!N) l J. Deleted.,
K. Deletedby Amendment No.103 dated December 15, 1987.
L. Deleteif.
M 4 il Medi ts D _
Th S ry il an e eq ir me s o ai d n e Ap en .x T ch ic 1 c' i at'on a s d el w re o i'ed o e er o S
n at on of t to :
} ele 4e d. 1 i el o i 1 1
/. 2 u ei la ce Re ui fo I ol t .2 A. -
in et ti n ns r n t1 , Ta le c ys em u t n
.c a 2 d, Se n ry C ta a t s a o
. .A t, t s
- b. u ei 1 c Re uf nt .9 A. .h - en y i el r to 4 o es .
.9 c n tu 1 e r or
. rv i a e e ir t .
ul a re ec t st L .
Amendment No. 444, M e, He,
ce Re hI T v r 1 ie n1 n r i rt tWi g nt )E 2 n/; is t 1o n t i tet rfu ig ut ge ( R -
N. Addi21onal conditient / g,,,
kaddi/c/alMiln//o[t[g((j/i 3as revised through
- 4. This license is effective as of the date of issuance, and shall expire at midnight, December 14, 2012.
FOR THE ATOMIC ENERGY COMMISSION Original signed by:
A. Giambusso, Deputy Director for Reactor Projects Division of Licensing
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Enclosures:
Appendixes A and B --
Technical Specifications Appendix C -- Additional Concitions o
I e
J Amendment,Fo.. H +
APPENDIX C ADDITIONAL CONDITIONS
. FACILITY OPERATING LICENSE NO. DPR-29 Commonwealth Edison Company shall comply with the follow ng conditions on the schedules noted below:
Amendment Number one Implementation Additional Conditions Date
(((hiN This ndmen autho zes t ' lice se to 6 da . fM e inco orate n the dated inal fety t of f su e Ana sis R e des iptio i
ortC( lantSAR),stem of the R eter sign assur , temp ature d vol tha was -
emove from chnic Speci icatio Sect n 5.4 and ev uated n staf sa ty eva ation ated y 23, 97.
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1 Attachment B DPR-30 !
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- 3. This license shall be deemed to cont:5 and is subject to the conditions specified in the following Commission. regulations in 10 CFR Chapter I:
Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections -
50.54 and 50.59 of Part 50 and Section 70.32 of Part 70; 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:
A. Maximum Power level Commonwealth Edison is authorized to operate Quad-Cities Unit No. 2 at power levels not in excess of 2511 megawatts (thermal).
B. Technical Soecifications j The Technical Specifications contained in Appendices A and B, as revised through Amendment No. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. , i C. The licensee shall maintain the commitments made in response to the Narch 14,1983, NUREG-0737 Order, subject to the following provision:
The licensee may make changes to constitments made in response to the March 14, 1983, NUREG-0737 Order without prior approval of j the Commission as long as the change would be permitted without -
NRC approval, pursuant to the requirements of 10 CFR 50.59. ,
Consistent with this regulation, if the change results in an l Unreviewed Safety Question, a license amendment shall be submitted to the NRC staff for review and approval prior to implementation of the change.
D. Ecualizer Valve Restriction i valvas in the equalizer piping between the recirculation loons Th,, ggQ ghall s bef losed at all timas durina remetne anaratigenpass om four cnive o pew f. at w c., nem.\ espause.w ef uder, E. The licensee shall fu'ly implement and maintain in effect all provisions of the Commission approved physical security, guard training and qualification, and safeguards contingincy plans including amendments made pursent to provisions of the Miscellaneous Amendments and Search Requirements revisions of 10 CFR 73.55 (51 FR 27817 and 27822), and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
These plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: " Quad-Cities Nuclear Power Station Security Plan," with revisions submitted through September 17, 1992;
" Quad-Cities Nuclear Power Station Security Personnel Training and
/ Qualification Plan," with revicions submitted through July 15, 1992; and " Quad-Cities Nuclear Power Station Safeguards Contingency Plan,"
Amenoment No. W. M4, M.
1 DRP-33 with revisions submitted through July 15, 1992. Changes made in.
accordance with 10 CFR 73.55, shall be implemented in accordance with o the schedule set forth therein.
F. Commonwealth Fdison Company shall implement and maintain in affect all provisions of the approved fire protection program as described in ths l Updated Final S:fety Analysis Report for the facility and as approved in the Safety Evaluation Reports dated July 27, 1979 with supplements ;
dated November 5, 1980 and February 12, 1981; December 30, 1982; December 1, 1987 with supplement dated April 20, 1988; December 11, 1987 with supplement dated July 21, 1988; and February 25, 1991, subject to the following provision:
The iteensee may make changes to the approved fire protection program without prior approval of the Commiission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
G. Deleted by incorporation into 3.E above, per Amendment No. 58 dated March 19, 1981.
H. Deleted.
I. Deleted.
J. Deleted.
K. Deleted.
L. G e/11a e ce R ir nts cont ined eA nd AT n al Su ill
,e 0.t.4ea, s cif ati s an iist d he ow a o r ire to t No 16 :
o d tel upon mpi nta ion f n ury illan Re i nt 4 2.A. - ic yst Fu ti iTt
- a. 4. A-1 It 4.a for sola on tuat on I st nt ion, Tabl dby Liq dC tro.
Re ctor ter lean p ( CU) sol ion nS
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- b. urve lanc Re ir nt 4 .A. -L ic yst Fu ti 1Tt nta ion. Tabl 4. A-1 1 2.a ( l for olat on A uat on I st 1.b 2.c, and .d. eco ary onta iso ati .
eil ance equ reme t 4. .C.2 L ic 5 st Fun ion Te
. S rA icip ted rans ont itho Sc am ( )- i ati amp rip pT)
Cl u taui emen 4.1 .1 [Tu ne top aly ,
d su eill nce RP Cal rat on, able 4.1. 1, gem .
Amendment No. 58, 408, +36, 446, W
abo S eil anc Reg re ts all e cce full d nst ted p or oe eri in 2 th fir t p nt art fo owi th ift nth efu ing uta ( 15) . _
s N. Additional Conditiens # g
@e ad61ti(nal /ndi/ ions /condine/in /noan/Me as revised through AWndment lo. Q7)L,are ere y i orp aT.ec/ int thi l'c se w Ah nd Vens/ / / / / /
- 4. This license is effective as of the date of issuance, and shall expire at midnight, December 14, 2012, FOR THE ATOMIC ENERGY CONilSSION Original signed by:
A. Glanbusso, Deputy D'irector for Reactor Projects Division of Licensing
Enclosures:
Appendixes A and B -- -
Technical Specifications Appendix C -- Additional Conditions Ameno.*nt Nos fru , 177
, APPENDIX C ADDITIONAL CONDITTONS FACILITY OPERATING LICENSE NO. OPR-30 Amendment Implementation Number Additional Conditions 0" Date his nd t autb6rizes he 11 nsee o inc porat in th( Updat d Fin- Safe .
An ysis port JFSAR) the scrip on - d a the actor oolan Syste desig ssur , t ratur and v uma t tw v from (chni 1 Spe ficat n l Sect n S.4 and e luate in st ff s ety eva ation ated ay 23 997. ;
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! l Attachment C l Information Supporting < Finding of No Significant Hazards
! SW-99-001 (Page 1 of 2)
The proposed license request involves an administrative change to License Condiiion 3.D. The proposed changes will modify the license condition by providing a clear description of the plant configuration and minimize the potential for an undesirable pressure increase between the equalizer line valves.
Comed has evaluated the proposeJ license amendment and has determined it does not represent a significant hazard consideration. Based on the criteria for defining a significant hazard consideration established in 10 CFR 50.92(c), operation of Quad Cities Nuclear Power Station in accordance with the proposed amendnent will not represent a significant hazard consideration for the following reasons:
These changes do not: l Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The initial conditions and methodologies used in the accident analyses remain unchanged. The proposed changes do not change or alter the design assumptions for the systems or components used to mitigate the consequences of an accident.
Therefore, accident analyses results are not impacted.
The proposed changes delete various license conditions that have been l
complued, make editorial changes, and provide clarifying information. The changes are administrative. No physical or operational changes to the facility will result from the proposed changes.
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l Therefore, this proposed amendment dee., not involve a significant increase in the l probability or consequences of an accident previously evaluated.
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! Does the 'hange create the possibility of a new or different kind of accident from
! any accident previously evaluated?
l The proposed changes do not affect :he 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 nunner, nor is the reliability of any stmetures, systems, or component reduced. The changes do not affect the manna 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.
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1 Attadiment C Information Supporting a Finding of No Significant IIazards i SVP-99 001
. . (Page 2 >f 2) 1 The proposed changes delete various license conditions that have been completed, make editorial changes, and provide clarifying infonnation. The char.ges are administrative. No physical or operational changes to the facility will resiilt from the proposed changes.
Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any previously evaluated.
l i Does the change involve a significant reduction in the margin of safety for the following reasons:
The proposed changes are administrative in nature and have no impact on the I 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 proposed changes delete various license conditions that have been completed, make editorial changes, and provide clarifying information. _ No physical or operational changes to the facility will result from the proposed changes.
1 Therefore, the proposed clnulges do not involve a significant reduction in the margin of safety.
This proposed license amendment request does not involve a significant relaxation of the criteria used to establish the safety limits, a significant relaxation of the bases for the limiting safety system settings, or a significant relaxation of the bases for the limiting conditions for operations. Therefore, based on ti.e guidance provided in 10 CFR 50.92(c), the proposed change does not constitute a significant hazards consideration.
n Attachment D Information Supporting an Environmental Assessment SVP-99-001
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Comed has evaluated this proposed operating license amendment request against the criteria for identification oflicensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51.21. Comed has determined that this proposed license anendnrnt request nrets the criteria for a categorical exclusion set forth in 10 CFR 51.22(c)(9) and as such, has determined that no irreversible consequences exist in accordance with 10 CFR 50.92(b). This detemlination is based on the fact that this change is being proposed as an anendnent to a license issued pursuant to 10 CFR 50 that changes a requirenwnt with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or that changes an inspection or a surveillance requirement, and the amendment meets the following specific criteria:
(i) the amendment involves no significant hazards consideration.
As demonstrated in Attaclunent C, this proposed amendment does not involve any significant hazards consideration.
(ii) there is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.
As docmnented in Attachnent C, there will be no change in the types or significant increase in the amounts of any effluents released offsite.
(iii) there is no significant increase in individual or cumu?ative occupational radiation exposure.
The proposed changes will not result in changes in the operation or configuration of the facility. There will be no change in the level of controls or methodology used for processing of radioactive effluents or handling of solid radioactive waste, nor will the proposal result in any change in the normal radiation levels within the plant. Therefore, there will be no significant increase in individual or cumulative occupational radiation exposure resulting from this change.
a-