ML20128K951
| ML20128K951 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 05/28/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128K932 | List: |
| References | |
| NUDOCS 8505310256 | |
| Download: ML20128K951 (7) | |
Text
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NUCLEAR REGULATORY COMMISSION
- Ogp%f f WASHINGTON, D. C. 20L55
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CAIRYLAND POWER C06 PERATIVE LA CPOSSE BOILING VATEP P.EACTOR DOCKET NO. 50-409 AMEN 0 MENT TO PP'0 VISIONAL OPERATIPa LICEN!E Amendment No. 41 License No. OPR 45 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Dairyland Power Coopirative (the licensee) dated December 19, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as arended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; R.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this arendment 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; 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 CFP Part 51 of the Comission's regulations and all applicable requirements have been satisfied, i
DR P
2 2.
According!y, the license is amended h" changes to the Technicti Specifications as indicated in the attachment to this license arendment and Paragraph 2.C(2) of Provisional Operating License f:o. DPR-45 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A issued Octcber 31, 1969, with Authorization No. DPRA-6, as revised through Anandmant No. 41, 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.
1 FOR THE NUCLEAR REGULATORY COMMISSION I ;'/
w Y 9f' E[.
A dohn A. Zwelinski, Chief Operating Reactors Branch #5
,l Division of Licensing
Attachment:
Changes to'the Technical Soccifications Date of Issuance:
May 28, 1985.
ATTACHMENT TO LICENSE AMENCMEf!T FO 41 PROVISI0llAL OPERATING LICEN'iE fiO. OPR-45 DOCKET NO. 50 409 Revise Appendix A Technical Specifications by adding the enclosed pages identified below. The new pages contain the the captioned amendment nunbers and marginal lines which indicate the area of change.
REMOVE IflSERT 1
1 29a 29a, 29b 5-6 5-6
1.
SITE e
1.1 LOCATICN The La Crosso Eoiling Water Reactor (LACBWR) is located on the east bank of the Mississippi River, approximately 19 miles scuth of the city of'La Crossa, Wisconedn, and 1 mile south of the v.llage of Gsnoa. Wisconsin.
t
.l.2 EXOLUSION AND RESTRICTED AREAS 1.2.1 The distance from the centerline of the reactor buildine to
- the boundary of the exclusion area, as defined in 10 CFR 100,
~
shall be at least 1129 feet.
Any changes in occupancy of the exclusien area which lesd to residential uses shall be ntticed to the NRC.
4 1.3 PRINCIFAL ACTIVITIES The principal activities carried on within the exclusion area shall be the cperation of the reactor and associated poser-generating equipment, and the operation of conventional steam-electric plants and electrical transmission switching and distribution centers, all of which shall be located within the site bcundary.
2.
DESIGN AND PERFORMANCE REQUIREMENTS 2.1 REACTOR BUILDING 2.1.1 Centainment Vessel 2.1.1.1 The containment vessel shall be capable of containing an internal pressure of 52 psig at 2800F, and it shall be capable of withstanding an external-over-internal pressure of 0.5 psi.
2.1.1.~ 2 The leakage rate from the containment vessel Jhall correspond to a leakage rate that, per 24-hr. period, does not oxceed-0.1 percent by weight cf a steam-air mixture at 2720F, 28.5 psig, and a steam-to-initial-air ratio of 2.2.
/
1 krene.cnt No.,20, 41
4.
.l.9 The centainment building shall be isolated whenever the spent f uel sicrage well centains irradiated fuel which has decayed less than 43' days after exposure in a critical reactor and a ehipping cask for irradiated fuel'is being moved by the crane en the 701 foot level or located within one cask length cf the tcp of the spent fuel stcrage well or is within the spent fuel s crage well.
During casi movement near or at the FESW the water level in the FI5W must be
. least 16 ft above the top of the fuel storage rack (no more than ' feet below the t:p of the FESX).
4.2.2.
Reacter \\'e s s el, Ceolant, and Auxiliary Evstems 4.2.2.1 Additional penetrations to the systems centaining reacter c;clant shall be designed, ma'nufactured, and tested according to*
the provisions cf the ASME Soiler and Pressure '.'essel Code and the A5A Ccde fer Pressure F1 ping applicable as of June 1962.
These additional penetrations shall be limited to instrument connections and piping connections, the latter being no larger than 1-in.
inside diameter.
4.2.2.2 The reactor coolant shall be light water and shall ecnform to the following requirements.
CONDITION 1 Normal Limit P.aximum Limit Chloride cencentration
.2 ppm
.5 ppm pH 5.3 - 8.6 NA Ceriductivity 3 umho/cm 10 umho/cm The time above 3 umho/cm at 70*F - 80'F and.2 ppm chloride should not exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> per incident, nor 2 weeks per year.
When the single incident normal limit is exceeded an orderly shutdown shall be initiated within 4 hourt unless returned to within the limits. When the maximum conductivity or chloride limits are exceeded an orderly shutdown should be initiated immediately.
I f the pH is outside the limits for a period of greater than 72 hcurs an orderly shutdown shall be initiated.
CCMD1TISM 2 & 1 Normal Limit Maximum Limit Chicrido concentration
.1 ppm NA, pH 5.3 - 8.6 NA Ccnductivity 5 umho/cm NA
- a cays for cif loading less than one half of the cere, i.e.
less than 26 fuel elements.
51 days for off loading mere than 36 fuel elements.
heneent No. /.', J', J6, )f. 41 293
The time abcVe 5 sches/cm n 70 'T to SC 'T and.1 ppm chicride concentration is restricted to 45 hcurs "cr any sir.gle
- currence during Conditien 2.
h'ne n.th i s t ime
',1 ?,1: in C:ndition 2 is exceeded the reactor shall be brough te the h0: shutdown condition (Cendition 3 ) until the limits are restored.
If the limits can not be restered in e.n additicnal 7 i.
days, the reacter shall be taken to the cold shu Jewn condition l
(Cendition 4 )
!, i 6
i C0: 0:CI0:: 4 t.
5, Normal..*.imi Chieride concentration
.5 ppm l
pF.
5.3 - S.6 t
i Conductivity J.'
10 4=he/cm The primary system chemistry parameters de#ined in this section shall be determined at least once every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in i
Condition 1, 2 & 3 and at least once every 7 days in Condition 4 and 5.-
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4.2.2.3 Deleted F
r l-1 l
I i
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l-t l
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k V
I l
29b knendment No. "s.
41 l
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I 5.2.3 Tne er.ecicr s.urfaces of t'1c 1.A EllR ventila icn s:!:k and te seche 5:!:k Of the c" ventienti steam pcwer tenera-ir; s:atier, Gere! 3, ac.j a:er.:
.: :.;e '..::E!!?. pi an shall be ir ;ected fer stre::cra* in:e;rity a; an d-.e ve' re kr;er {hs,n 5 years felichg the initial c:nstru:-icr i.s;s::icr.,
u subst:ueni 1 ;)rvals nc 1 rger than 5 yer.rs a: art.
a:
'5 '2. 4 'The re$c er..veasci shall Le hydrcstatically tested a: la00'psic af:er inj Of i s gasketed.'cints have be:n c;ened and resealec.
All hydrcstati:
e s.3 shall :e per#cemed with the vessei at a te cerature n: levier than tha; 3:e:'fiec' irc Section *.2.2.4.
.v i.2.5 The f:rced circulation s.vstem controls and at:cmatically-c:erated valves shall be ested for pr:cer creratien at each refueling shutd:wn with test intervals nct '.c exceed 18 tenths.
f 2.6 The shu dewn condenser syster.1 centrol valves shall be tested at least cuarterly to dwenstrate their operability.
The integrated system shall be tested for proper operation at evh refueling shutdown with test intervals
-::ste ex:eed IB conths.
In add ticc, the c:ndenser tube bundle shall be
- -tssuri:ed :: greate PM 1250 psig ard tested for leaka;f at e,ach refuelir.;
- .utd:wn..
a.lver sr.:.M :;h-pressure core spray system controls and remotely-c;erated 5.2.7 The %
e :ested n.each cold shutdown but not recuired more often than e.very 92 cays to demon:tra* rtheir operability., The integrated systen shall te tes:=d for pr:;er cperAtion at each refueling shutdown with test intervals tc exceed IE m:nths.
This functienal ted shall include a determination cf the differential pressure between the coolant supply 1.ine and the reactor vessel.
N, 5.2.5 The low-pressure cociant injection system controls and remotely-c:erated valves shall be tested at each cold shutdown but no; recuired more ef en thar every 92 days to demons.trate their operability.
The integrated system shall be testec 'fc".orccer operation at each refueling shutdewn with test '.ntervals not to exceed 18 tenths, with the su:siy lir.e to the reactnr ves!<
'sciated anc :n.e ::nlar: flow directe: thr:ucr. the sys s! and back te tre rivc*.
.n ad:iticn, a est snall :e :eric ed a eten re#uelin" s.u;d:wn i.1-h tes- .e'vals nct :: erceed !! r:n:ns :: ca Crstrate nt.: tne check
!'ves ia *** 0,v!;!
a re f.
- 1:vek ?r ! cles d ;;siti:n.
i.2.9 Ih: : r n ff,'e
(*n CyS;m ccr. r:*! art the ra*.:*el -::aMed v?l\\es shall f.c tes;0d for pra '.e* cperaticr. curing cold shu;c;wns :v;
- rc:Vired
~;re n#tt- : Pen overy 92 days.
5.2.10, The door s.uir en the containment personnel and emergency airiceP.s will be visually inspected 'or degradatien every ~2 hours.
The door seals 'n the containment persennel and omergency 5.2.11 e
airlocks will be replaced periodies11y in accordance with manufacturcre recor.mendations.
d AententNoJ,p.';.al 5-6