ML20009B902

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Amends 67 & 64 to Licenses DPR-39 & DPR-48,respectively, Revising Tech Specs by Removing Rod Bow Penalty from Calculation in Peaking Factor Limit
ML20009B902
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 07/09/1981
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20009B901 List:
References
NUDOCS 8107170338
Download: ML20009B902 (11)
v • d • e


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.;pf 2 s,, %.-.....f COMfi3L'IALTH EDISON C0!!PA'iY D3CKET NO. 50-295 ZION STATION UJQT_1 A!1Ef;DMENT TO FACILITY OPERATIfiG LICENSE A.end.,ent No. 67 License f;o. OPR-39 1.

The Nuclear Regulatory Comission {the Commission) has found tl.at:

A.

The application for amendment by Comonwealth Edisen Company

'(the licensee) ' dated %pril 13, 1981, as supplemented by letter dated June 5,1981, 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 Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can !,a conducted without endancering the health and safety of the public, and (ii) that such activities will be conducted in compliar.ce with the Commission's recul&tions; 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 accurdance with 10 CFR Part 51 of the Comission's regulations and all applicable reouffements" have been,utisfied.

8107170338 810709 PDR ADOCK 05000295 PDR P

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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. OPR-39 is hereby amended to read as follows:

(2) Technical Seecifications The Technical Specifications contained in Appendices A and B, as revised through Amend. Tent No. 67. are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specificatiels.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY C0:011SSION

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Attachment:

Changes to the Technical Specifications Date of Issuance:

July 9,1981

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.l COMMONWEALTH EDISON COTPRlY DOCKET NO. 50- 304 ZIOil STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendnet No. 64 License No. DPR-48 l.

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

A.

The application for amendment by Commonwealth Edison Corrpany (the licensee) dated April 13, 1981, as supplemented by letter dated June 5,1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as s. ended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; 8.

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 by this amendment can be conducted without endangering the health and safety of the pinblic, and (ii) that such activities will be conducted in compliance with the Commission's reguldtions; U.

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 requirementsc have been satisfied.

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.j Accordingly, the license.is amended by changes to the Technical Specifications as indicated in the attachment to this ifcense amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-48 is hereby '. mended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices

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A and B, as revised through Acencment No. 64, are heruby incorporated in the. license. The licensee shall operate the facility in accordance with the Tecnnical Specifications.

,3. This license amendment is effective as of the date of its issuance.

FOR,THE NUCLE (Ut REGULATORY COMMISSION

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1Steven A. Varga, Chi f

, Operating Reactors S anch #1 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

July 9, 1981

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ATTACHMENT TO LICEf:SE 4tENG"Et.TS

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AMENDMENT NO. 67 TO FACILITY OPEPATING LICENSE NO. DPR-39

-i N:ENDMENT NO. 64 ' TO FACILITY OPEPATING LICENSE NO. DPR-48 DOCKET NOS. 50-295 AND 50-304 L

Revise Appendix A as follows:

Remove Pages Insert Pages vi vi 45 45 45a 45a 61 61 68 68-68a 68a-3

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  • LIST OF FIGUitES Page Fiqure 1.1-la Safety Limits, Four Loop Operation, Unit 1 15 15A 1.1-lb Safety Limits, Four Loop Operation, Unit 2 16 1.1-2a Safety Limits, Three Loop Operation, Unit 1 16A 1.1-2b Safety Limits, Three Loop Operation, Unit 2 16D 2.1-2 Flux Difference vs. Percent Flux Difference 3.2-1 Required Shutdown Margin vs. Reactor Coolant 56 Boron Concentration Control Bank Insertion Limits for:

57 3.2-2 4 Loop Operation on Unit 1 58 3.2-3 3 Loop Operation on Unit 1 59 3.2-4 4 Loop Operation on Unit 2 60 3.2-5 3 Loop Operation on Unit 2 63 3.2-8 Rod Cluster Groups 3.2-9 Hot Channel Factor Normalized Operating 63a Envelop:* for Units 1 and 2 Amendments 67 & 64

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GURVEILLANCE REQUIRE 21ENT LIll]T]Il0 CONDITION FOR OPEitATIOli 3.2.2.A.1.1 L

i The measurement of total peaking factor, v Itcas,- uhall he increased by g

three f,creent to acc(..mt for manufact.uring tolerancas and further increased by five percent'to account for t..canurement crror.

The measurement of ent.halpy rise hot chniuietfactor,Fli,g, shall be increased 1sy four percent to account for measure-ment errors.

1.2 If the atuasured hot channel factors exceed the limits in Item 3.2.2.A.l.1 of this specification, the reactor power and the high neutron flux trip sotpoints shall be reduced in direct proportion to the excess over the peaking factor which is limiting for that unit.

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Amendments 67 & 64

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lleastuements nf the. hot channel factors are requircs measurement is taken, both experimental as part of start-up. physics tests anil whenever When an F error-and manufacturing tolerance must be allowed abnormal power distribution conditio1s require a O

rcJuction of core power to a level based on measured for.

Five percent is the appropriate allowance for a full core map taken with the movable incore hot channel factors.

The incore map taken~following initial loading provides confirmation of the basic.

detector flux mapping system and three percent is nuclear design bases including proper loading the appropriate allowance for manufacturing The periodic monthly incere mapping tolerance.

patterns.

provioes additional assurance that the nuclear design bases remain inviolate and identify opera--

tional anomalies which would, otherwise, affect N

The rod bow penalty (i.e.,14.9% DNBR) on the F limit these bases.

has been eliminated by taking credit for a' ailabN generic For norm'al operation it is not necessary to-v DNBR thennal margins which include (1) the design ptch measure tnese quantities continuously.

Instead reouction, (2) the thenna! diffusion coeff alent, (3) the it has been determined that, provided certain dssign DNBR valve, and (4) the densification power spike conditions are observed, the hot channel factor factor.

For fuel with a region average burnup of greater limits will be met:

these conditions are as than 33,0Q0 tiWD/f4T, credit is also taken for the peaking follows:

factor (F 3g) burndown effect.

1.

Control rods in a single bank niove together I

with no individual rod insertic.n dif fering by more than 15 inches from th6 bank demand position.

An indicated misalignment limit l

of + 12 steps, not including-instrument error, precludes a rod misalignment no In the specified limit of F there is an 8 greater than 15 inches.

With naximum i

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instrumentation error considered the actual l

percent allowance for uncertainties which means rod &mpe h w m h N @s 4

that norma, operation of the core is expected t or 15 inches.

C 1.55/1.08.

The logic behind the result in Pyg inty in this case is that (a) i larger uncerta 2.

Control rod banks are sequences with over-abnormtm perturbations in the radial power shape lapping banks as described in 'rechnical (e.g. rod misalignment) affectFNh, in most cases Specification 3.2.

without necessarily affecting Fg, (b) the operator t

through movement of 3.

The full length control bank insertion has a direct influence on FO j

rods, and can limtt it to the desired value, he limits are not violated.

has no direct control over FMn and (c) an error l

in the predictions for radial power shape, which 4.

Axial power distribution contral procedures, may be detected during startup phy.;ics tests can which are given in terms of flax differences be compensated for in F by tighter axial control, control or additional axial poder monitoring 4

but compensation for Edgu is less readily available.

and control bank insertion limits are When a measurement of Phuistaken,. experimental observed.

Flux difference refers to the l

error must be allowed fot anu 4 percent is the difference in signals between the top and j

appropriate allowance for a full core map taken bottom halves of two-section excore neutron with the movable incore detector flux mapping detectors.

The flux difference is a measure i

j system.

of the axial offset which is defined as the differene in H rmalized Power between the Amendments G' & 64 68 top and bottom halves of the : ore.

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The permitt.ed relaxation in Fyg allows radial the indicated equi 1ihrlum value was noted, power shape changes with rod innertion limits.

n., allowances for excore detector error are it has been determined that provided the si. cessary and ind Lca Leel slevla tion of the above conditionis 1 through 4 are observed, AI EdE9"t hand as c pea mi tted f rom t.h e indi-these hot channel fact.or limits are met.

cated s'eferesice value.

During periods where is arbitrarily extennivo load followinq l a rcepiired, IL may In Specificat".ons 3.2.2, FO Le impractical to establiuh t.he required core limited for p.5 0.5.

con,dit.lons Tor measuring target flux dj.fference every anonth.

For t.hls reason, the specificat.lon provides The proccituren for attal power dintribction cinit.ro ! s e f errest to above are designed to two methods for ngulating the target fltix dif f erence, m i n liec8ze the effects of xc.s.on redistribu-War alarms provided are derived f rom the plant pa o-Llon.en the axial power dlutribution during cens computer which determines the one minute averages loadfollow maneuvern.

llaulcally control of the operabic excore detector outputs to monitor Lf ft:ix difference is respil red to limit AI in the react.or core and alerts the operator when the difference between Lt.c current value AI alarm c nditions exist.

,Two types of alarm manua-of plux p!ffcacnce ( A I) and a reference ges are output.

Above a. preset power level, an alarra value which corroupondu to the full nower message is output immediately upon determining a capiillbrium value of Axlal of fset (Axial

.della flux exceeding a preset band about a target offnet = A!/ fractional power).

The delta flux value.

Uclow this preset power level, an retenence value of flux difference varien alarm enessage is output if the ol exceeded it.s allow-with power level acid inernup buc expressed able limits for a preset cumulative amount of time in t.he past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

For periods during which the

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.oslal of f se t it. varies only wi th burnup.

alarm on flux difference is inoperable, manual sur-Thor techulect pecificatin in un power dis-velllance will be utili7ed to provide adequate warn-trisuit ion control assure tha t t.he ro llini t ing f significant varlations in expec ted flux l

is not exceeded aint xenon distributions differences.

Ilowever every attempt should be made as e not developed which at a later time, to restore the alarm to an operahic condi tion a:. noon would cause greater local power peaking as p asible.

Any deviations from the t.arget band even though the flux difference is then during manual logging shall be treated as deviations within the limits specified by the procc-during the entire precceding logging interval and dute.

approprate actions shall be taken.

Thio action la l

necessary to satisfy NitC requirements; Lowever more l

frequent readings may be logged to minimize the The t.a rg e t (or referencu ) value of flux penalty associated with a deviation from the target i

hand to justify Continued operation at the currcut d8ffencoco is determined an follows.

At p wer, any t.ine tha t espil l ibrinm xenon conditions e

have been ostablished, the inullcated flux l

The times that d3viations from the hand occur c.re l

difference is noted with the full length rod cont rol rod bank more than 190 steps normally accumulated by the compute.,.

willnirawn (i.e. normai full power operating pealLion approprlAle for the time in 1.fe, unna l1y wi Llutrawn farther as burnup proceeds).

This value, divided by the fraction of full power at which the core was operaLing,la the fuil power value of' the target flux d'fference.

Valuen for all ot.her core power IeveIn are obtained h/ molLA.lylng the ful1 power value by the fractional power.

Since

- f, n a-Amendments 67 & 64

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