ML19331E144
| ML19331E144 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/30/1976 |
| From: | Boyd R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19331E143 | List: |
| References | |
| TAC-07125, TAC-7125, NUDOCS 8009050557 | |
| Download: ML19331E144 (9) | |
Text
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[paasco UNITED STATES NUCLEAR REGULATORY COMMISSION
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Fwn.wA Amca daduwA2 ids CI2r vF A1.ACnuA CIrz vf custuicLL CIAi vF @ t.bv1LLS CATI vF AIo6Irnurd CITI Of L.coddzw CIrz 0F t46W :wtic.<A dr. ace Av utILIlIGo Co 64Io510W, CIII VP nc.4 disin4A ocAca CI21 UF at.AEA Oi<!A4th uPILIi'Ir 5 mitiosius Md CIrY OF Ohu>
Sr.:inite Ui'iLh'ILS Cuh4IodIud St4 tut 6 ciaCic1C CUurt.RAl' ivc., Inc.
CITI 0F 'rALf.MAost.t.
DvCaff tu. 5u-302 Cniorau &Ivi.n u.iLi 3 odCLEAk Ghn2ATI.43 Mt2 A4sua464r 1V FACILII'i Ordz<AfL6 LICwod Aalena.Jent do. 1 License c40. CPR-/2 1.
Tne duclear Regulatory Cociaission (tne Co6.nission) naving rouna taat:
A.
Ine application rilea cy Florica Power Corporation, City of Alacnua, City or cusnnell, City of Gainesville, City of i
hissnauee, City or ueesourg, City or dew 5.uyrna meacn anc utilities Coa.11ssion, City of tiew Smyrna meacn, City of Ocala, ur2anco veilities Conaission anu City of Orlanco, seoring deilit.Aes Cocanission, dealnole Electric Cooperative, Inc., anc w
City of ralianassee (tne licensees) as suppieraentec cry letter cateo Geceacer 3,1:37o, co.. plies witn tne stancaros ana require-
..ents or tne Atoinic c.nergy Act or 1934, as aaencea (une Act) ana tne Comission's rules anc regulations set forta in 10 CFR Cnaprer 1; Ine racility will operate in conrormity witu tne application, i
B.
tne provisions or tne Act, ana tne rules anu regulations of cne Cartaission; C.
2aere is reasonaale assarance (1) tnat une activities autaorizeu of tnis amenu..ent can a conouctea witnout enaan ering cne v
8000050 F N
-g-nealtn ano safety of tne puolic, ana (ii) tnat sucn activities will ce conouctec in compliance with tne Comission's regulations; 0.
Tne issuance of tais amenoment will not ce inimical to tne comon oefense ano security or to tne healta anc safety of the puolic, ana E.
Tne issuance or tais amenacent is in accorcance with 10 CFR rarc 51 of tne Comnission's regulations and all applicaole requirements have oeen satisfieu.
2.
Accorcingly, tne license is amenceo oy (1) a cnange in Paragraph 2.C.(1) as inoicaceo celow, (2) a cnange to tne reennical_ specifi-cations as incicatec in ene attacn ent to tais license amnsnent ano paragrapa 2.C.(2), ano (3) tue aooition or Paragraphs 2.C.(3),
2.c.( ), 2.C.(s), 2.C.(b), 2.c.(7), ana 2.C.(o).
2.'C.(1) c6axitaum Power Level Florica Power Corporation is autnorized to operate the tacility at a steacy state reactor core power level not in excess of 24s2 megawatts (luu percent of raceo cora power level). Prior to proceecing to operational doces 1-ano 2 Floriaa Power Corporaticn snall W ate the items inentified in Attacament i to tais licetuse and approval for preing to Operational Hose 1 anali ce granted oy tue Commission oy asenasent to tnis license. Prior to operation oeyala o2 percent 'of rateo power as limiter.
oy tne revised Tecnnical specifications attached to thia license a.nenament, tne analyses ioentifica in Attemment 1 to tais license snail oe compleceu and approval una11 oe grantec cy taa Comaission oy amencunent to tnis license.
acrac1=nt 1 is an integral part or tais amen =d license.
4.C.(e.;
l'ecnnical specifications Ine n cnnical 3pecifications containeu in Appenaix A, as reviseo, are incorporateo in License do, w&-72.
Florlua Power corporation san 11 perform tests anu operate une facility in accorcance with tne recanicai specifi-cations as revisec.
2.C. (.s > Elorica Power corporation shall not operate tne reactor in Operational acces 1 ana 2 witn less tnan tnree reactor coolant p in operation until sarety analyses for less tnan three guap operation nave cean suu.titteu oy tne licensees ano approval nas vean granted of tne wo:raission of asen an'ent to talls 11 Cense.
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2.C.(4) Until permanent.aouifications, sucmitteo ror review ana approvec oy tne Comission, have oeen mme to tne enemical acoltive system, Florica Power Corporation snall isolate tne socium tniosulfate aouition tanx from tne plant system cy locxing closeo the valves (dVd-97 ano BVS-:fo) in the tank cisenarge line. Witnin nine mentns of tne cate of issuance of tais license, Florica Power Corporation snail sucmit mooifications, inclucing proposeo enanses to tne plant Tecnnical specifications, waich sn:J.1 s.e installeo prior to or curing tne rirst refueling outage.
2.C.(5) n1 thin six montns of tne cate of issuance of this license, Florica Power Corporation snali conglete mooitic4tions to tne level inoication of tne corateo water storage tank, instalia-tion a.% testing or flow inoicators in ene emergency core cooling system to provice inaication of 40 gallons per minute riow for coron ollution, anc installation of oual setpoint pi2ot-operateo relief valve on ene pressurizer.
2.c.(o)
Prior to startup following tne first regularly seneculeo rerueling outage, Florica sower Corporation snail install',
to tne satisfaction or tne Comission, a long-tern means of protection against reactor coolant system over-pressurization.
4.C.t?)
Prior to startup rollowing the rirst regularly seneculeo rerueAing outage, Florica Power Corporation snail mouify to tne satisfaction of tne Conaission, tne reactor coolant system flow inoication to meet tne single tailure criterion witn regato to pressure sensing lines to tne flow oifferen-tial pressure transmitters. -
2.C.Le) nithin tnree.Tontns of issuance or tnis license, Florloa cower Corporation snall saoait to tne Concission a proposeo surveillance program for monitoring tne containnent for tne purpose of oetermining any ruture ueiamination of tne QCGE.
- J.
Tais license ataennaent is efrective as or tne cate et its issuance, rNR Tac: 14) CLEAR NRY CAhISSIui
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s R:ger S. soy, Direcyor Division of/ Project rianageuent Office of auclear neactor Regulation attacnr.ents:
(1) Attacanent 1 to Aasmaent wo.1 or License do. W a-?2 (z) er$3e unanges to une fectulical dpeciIiCations, AppesT iX A cate or Issuance:
DEC 308 l
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3 DEC 3 0 G75 l
MTACouff 1 f0 MELirMr.*.>.1 VP LICst:iE OPR-72 1
inis attacccent icentifies certain tests wnica must ce completea to tue Costission's. satisfaction prior to proceecing to 0perational
)
doce 2 (startup) and certain analyses walch must ce completea to i
tne Cor: mission's sacisfaction prior to operacion oeyona o2 percent of j
ratec power.
A.
Prior to proceecing to operational noce 2 (startup) Florloa rower Corporacion snail coglete tne following items:
1.
W 1su rest Accident u2 Purge Test - Retest for correct flow rate TP 160-3 anc ovu Reactor Builcing Cooling - Resolve e.
fan calance uericiency.
Ir 100-7 neactor Cavity Cooling - netest for aoaitional data.
a.
4.
TP 267-s - Cr<0 Cooling Functional - Flow catancing requirec to resolvec low ualta P on original test.
- i.
TP 304-2 and 3 - Incore System - Resolve caole oeficiencies.
Suosequent to tne verification oy the Office of Inspection ana
~
Enforcement of tne accepcaole completion of taase items, and upon written authorization of tne Cohaission, Florica Power Corpora-cion may procesa to Operational euxne 2 (startup).
+
I d.
Prior to proceecing to operacional acue 1 (power operation) tne Co aission ancil confiria its evaluation of tne containraent structurai integrity test ano Florica Power Corporation anall provice any accitional inforiaation that may be neecea to complete ene evaluation oy tne Coinaission.
F.cric a iower Corporatio.1 way proceec to Operational Hooe 1 (power a;eracion) upon e.aeno,aent of tnis license oy tae j
J.T.aldslon.
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Prior to exceecing tne regulating roo group insertion limits for 4 pump operation ano axial power imoalance as specifiac in Figures 3.1 A ano J.4-1 of cne Tecnnical specifications as revisec ey A. tenement ilo.1, the following itetas snail ce completed:
1.
An analysis of tne eargency core cooling systes snall oe ccupletea wnica anall not use the nucleate coiling heat transfer correlations after critical neat flux is first predicted at an axial fuel rod location during nie in conformance witn Apfenuix K to 10 CFR Part s0.
1 2.
An analysis of tne emersency core cooling system snall be j
complaceo for tne railowing orsas sizes (a) a u.04 square foot creas using tne small creak mocel, (o) a transition creax using tne large crean mocel sna the smaiA creak h, ana (c) a core floooing tans Aine creax using the small creax r.ccel.
Florica Power Corporacion may proceeu to full power operation u;cn acceptance oy tne C = 4== ion of taese analyses, anc revision or tna limitations in the reviseo recanicai 5pecifica-tions and amenoment of tais license oy the C==iaaion.
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DEC 3 0 576 ATTACHMENT TO LICENSE AMEN 0 MENT NO. 1 FACILITY OPERATING LICENSE NO. DPR-72 DOCKET NO.60-302 Replace the following pages of th'e Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified of Amendment number and contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.
Pages 3/4 1-27 3/4 2-2 6
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CRYSTAL RIVER - UNIT 3 3/4 1-27 Amdndment No. 1
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Figure 3.21 AXIAL POWER IMBALANCE Envelope for Operation Up to 400f.10 EFPD CRYSTAL RIVER - UNIT 3 3/4 2-2 Anendment No.1
U;ITED STATES MUCLEAR REG _ULMORY COBE4ISSI,02 DOCCP NO. 50-30,2 FICRIDA POWER CORPORATION, et al CRYSTAL RIVER UNIT 3 NUCLEAR GENERATI'.4G PIANT NOTICE OF ISSUNiCE OF NE4Df1Efr 'IO FACILITY OPERATING LICENSE Notice is hereoy given that the Nuclear Regulatory Commission (the C:.Inission) has issued Amenoment do.1 to Facility Operating License No.
E7?.-72, issued to the Florida Power Corporation, City of Alachua, City of Bushnell, City of Gainesville, City of Kissinnee, City of Leesburg, City of New Srirna Beach and Utilities Coraission, City of New 5myrna Beach, City of Ccala, Orlando Utilities Coanission and City of Orlando, Sebring teilities Comissica, Seminole Electric Cooperative, Inc. and the City of Tallanassee for the Crystal River Unit 3 Nuclear Generating Plant located in Citrus County, Florida.
Mendment No.1 authorizes Florida Power Corporation to operate the facility within five percent of rated power. The amended license is conditioned to require the corgletion of certain tests prior to initial c:iticality and tne com),r.tnn of certain design changes and corresponding codifications to be completed within specific time periods fro:n the date of issua.ce of the license and sets forth specific requirements to be satisfied prior to authorizing increased operating power levels from s:artup :: full power.
Tne Comnission has made appropriate findings as required by the A:::ic E.ergy A:: of 195 *, as amended, and the Coanission's rules and i
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regulations in 10 CFR Chapter I, whic'1 are set forth in the ar. ended license. The application as supplemented by letter dated December 9, 1976 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended, and the Comission's rules and regulations.
This action is in furtherance of the licensing action encompassed in the " Notice of Consideration of Issuance of Facility Operating Licenses and Notice of Opportunity for Hearing," dated October 14, 1972.
A copy of (1) Amendment No.1 to Facility Operating License No.
cPR-72, and Attachment 1 thereto, with revised Technical Specifications (Appendix A); and (2) the office of duelear Reactor Regulation's Safety Evaluation and Supplements 1, 2 and 3 dated July 5, 1974, January 13, 1975, December 3, 1976, and December 30, 1976 areavailableharpublicinspec-tion at the Comission's Public Document Room at 1717 't Street, N.W.,
Washington, D.C. and the Crystal River Public Library, Crystal River, Florida 32629.
The Comission's findings with respect to environmental considera-
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tions are described in the Comission's Notice of Issuance of Facility Operating License (published Decerter 23, 1976, 41 F.R. 55952).
Single copies of items (1) and (2) may be obtained upon request addressed to the United States Nuclear Regulatory Comission, Washington, D.C. 20555, Attention: Director, Division of Project Management.
Dated at Bethesda, Maryland, this I day of [r<1 m[+ t- /h [ b '
!OR THE NUCLEAR REGULATORY CO 41I5SI0d d'>c e.f W Jl 4h nlhnF.Stolz, Chief-}
s Jo f.ight Water Reactors Branch No.1 Division of Project Management
,