ML20137J750
| ML20137J750 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/14/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137J755 | List: |
| References | |
| NUDOCS 8601230182 | |
| Download: ML20137J750 (8) | |
Text
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%k UNITED STATES O
NUCLEAR REGULATORY COMMISSION 3
,g WASHINGTON, D. C. 20555
%,,,,,/
COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated May 2, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-29 is hereby amended to read as follows:
8601230182 860114 Q4 DR ADOCK 0
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, B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 91, are hereby incorporated in the license. The licensee shall operate the facility in accordan'ce with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY 0 SSION e
wJ' John A. Zwolinski, Director BWR oject Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 14, 1986.
ATTACHMENT TO LICENSE AMENDMENT N0. 91 FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages'are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.3-5 3/4.3-5
OUAD C171t3 spa. 2 9 Steered inoperetle fully previse ressenable assurance insectes into the core.
that proper control res artve ans electrically sisarmed, performance is betag esintaines. The results of aessurements performes en the
- 5. If the everal) everage control res arties shall ne of the 20s insertten scree subettted in the annual operating stee sata generates to report to the stC.
e date in the current cycle escoeds 0.73 seconds, the flC pt estrating 11ett sust 3.The cycle coeulative seen be meetfted as reestres by scree time for 201 insertten Spectftcatten 3.5.t.
stil be detereines teseststely f elleming the testing reeutree in Spectftcattens 4.3.C.1 anc 4.3.C.2 and the m:pt operating limit adjustes, if necessary. as reestres by seectitcatten 3.5.E.
D. Case.I Red Aneamelssert D. Camrei Red Arra-aseeri
~
As all reacies operaung pressuren, a rod aerw-One a shifL ceert the eerse ofihr presure mutaner may be apopraber proneed that so and arvel alarna Ier each arrumstator other sentrol red in uit mane red aquary array around &as red han I. an insyrrabir earwmetsier.
- 3. a darersonal sentrol vetve ehetrisnHy.
danarmed wAk as e assfully amarrard ymianos. er
- 3. a erram inarrwn geraier man man.
dpum pernusub&r saaertsen tame lf a sentrol red with an inoperabit aartmalater as sneerted full-in and sta darecuenal asntrol vetves are tiervically danarmed. si ahall est he anna.dered is have an ineptable aerumulator.
and the red b6ars asaariaied esta than anspera-her aerumulaner ma} et Dypeaard L Esme*e> Aammenwo L EmeriMrs Aamsmalwa The reartmt) equaalent of the ederene llharvig the naartup est program and eartup.
brewarn War arsinal criur.at red maagu.reuen following refuslang ewiages. the cratar.at red een A erauens ed: he mapared is une espreisd t
and the npsesed ese Agursuem during poner eyersuen naa!! not asamed luk If uus hmat is eenAgursuena an erwned oprsung sendiuenn sameded. the rearier shall be shutdown en6l Theme comparinses will be used as tear deu for te maae has been driermined and erroreve rearvvir) monsionng during notesqwent power artsena have been tahrn In anordanse with operauen throughout der furt rycle Ai rpecanc SpeAmuea 6.a. the NRC ahall er neubed of power opraung asadiuent. the critasal red as reportabh ammemme vehm }a aseen meAgursusa edl kr esmpared na the sueAg-erauon espcird haned upon aPpropn.strPu er.
raried pau seu Tha empanion wd! te made sa imana e. wry agmtvaarnt f.1: power monia F. Ec===e6e Geesviiles Cammi 5ree.
F. Ecemmene Co mv6 Casaret Gree-Opersisen of the enn with the suma**'8 p'""-
prior to enterins ccC and once per %hitt white essen asevel syniem with automaut Asw en-operating in ECC. the ECC operating parameters wel shall be prnnsmbk enh a W reap of will be reviewed for acceptability.
4$1 en IOM of rated eart M. with r48818' power ans=e 205 363 / 4.3-5 A,end ent No. 44,91 T
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION O
- y WASHINGTON, D. C. 20555
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COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 88 License No. DPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated May 2, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-30 is hereby amended to read as follows:
. B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 88, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY OMM)$SION
/
John A. Zwolinski, Director BWR Project Directorate #1 Division of BWR Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 14, 1986.
ATTACHMENT TO LICENSE AMENDMENT NO. as FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.3-5 3/4.3-5 6
O*
QUAD-CITICS OPR-30 sidered inoperable, fully provide reasonable assurance inserted into the core, that proper control rod drive and electrically disersed.
performance is being maintained. The results of
- 5. If the overall average sessurements performed on the of the 20s fasertton scram control rod drives shall be subettted in the annual operating time data generated to report to the NRC.
acte in the current cycle eaceeds 0.73 seconds, the a
MCPR operating Itatt must 5. The cycle cumulative sean be modified as recutred by scram time for 20s insertion Specification 3.5.K.
will be determined tamediately following the testing r'eautree in Specifications 4.3.C.I and 4.3.C.2 and the MCPR operating limit adjusted. If necessary, as required by Specification 3.5.K.
D. Ceaseel Red Accommassen D, Camerei med Acreenlasers At aff resciot operating pressum. a tod acts.
mulator may be inoperabic provided that no Once a shin. etwet the saatus of the pmaure med level alarms for each ammut.sor other control rod in the nine. rod square array around this rod has
- 3. as saeperable accumulator.
- 2. a darvctional control volve elecincally danarmed whale in a nonfully innened pos4:aoo. er 1 a scram innertaon greater than man.
imum permissable insertson tarne.
If a contro! rod with an inoperable acrumulator as sanerted fullin and ses directional contrni valves are eleeirically disarmed it shall not be considered to have an snoperable acrumulasor.
and the rod bioch associated esta that snopera.
ble accumulator may be bypanud L Reactivery Amessalien L Reettivig Aasmakes The reactivity equivalent of the d:Kerence brtween the actual entical rod conngurataan During the saanup tese program and naartup folleming refuehng outages the criucal rod and the espreted conAgorasann during power operation shau not escred !"eak. If that hrris as con Agurauons =sil be enenpared io the esprcted conAgutanons at wiected operating condiuons escreded, the reacier shall be shuidown until Thew comparisons witl te used as base data for the cause has been determined and correcuve actions have been taken In accordance woh reactivity manninring during sekrquent pe=er SpreiAcanon 6 6. ihe NRC shall be nou Aed of eprauen thrnughout the fuel cycle At specik power operaung condiuans, the critical rod aus reponable oenarrenar withe 2a he os.
conAgeratson win be compared in the conhg.
uranos espected based upon appropnatch cor.
rected pasi data This compariwa =itt he enede at Isass every equivalent full power month.
F. Ere==mic Cen.coisea Consrei Syween F. Ee mme Cenm:6en Camerei Sreem Operation of the unit with the economic gener.
soon controt system with automanc Ho= con.
Prior to entering ECC and once per %hift while trol shall be permissable only in the range of operating in cCC. the cet operating parameteen 41% to 100% of reied core Row, wue reano, will be reviewed for acceptability.
po.er above 20s w c.s Amendment No. H. 88
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