ML20195K128

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Environ Assessment & Finding of No Significant Impact Re 880812 Application.Amend Revises Tech Specs 4.9.6.1.c & 4.9.6.2.c to Permit Descreaing Min Water Coverage for Irradiated Fuel & Control Rods During Handling
ML20195K128
Person / Time
Site: River Bend Entergy icon.png
Issue date: 11/29/1988
From: Calvo J
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20195K134 List:
References
NUDOCS 8812050141
Download: ML20195K128 (5)


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7590-01 J

l ffllED,531ES,[pgEAR REGPLATORY COMPilSSION Gt!LF STATES UTILITIES COMPAfiY i

.D.O.C.K.E.T..N.O 5 0..4 58 ENVIRONFEKTAL ASSES! PENT Af!D FINDING OF NO SIGNIFICANT IMPACT 1he U.S. !Juclear Regulatory Cornission (the Consission) is considering the issu6nce cf en atiendr.ent to Facility Operatir.g License No. NPF-47 issued to Gulf Statn Utilities Conpany, (the licensee), for operatior, cf the Ftver 4

l Eend Statien, Unit 1, located in West Feliciana Parish, Lcuisiane.

i ENVIR0hPEhTAL ASSESSMENT Idet.tificatict: cf the Propp,se,d, Ac,t,ip,n

.The proposed atendrent veuld revise the provisiot.s in Technical Specifications (TS) 4.0.f.1.c and 4.9.f.0.c te pernit decreasing the sainic.un.

water covtrage for irradiated fuel and control rods during their h6ndlirs.'

The proposed action is it, accordance with the licensee's application for arendrer t dated August I?, !?ff.

f:eed for the Frcppo, sed Action The proposed chance to the TS is required to relieve the licensee from the unnecessary hardship dut to the narrow cperatil.g bands for pool levels in the containtier.t and fuel building. The narrow operating barids have siade it difficult to a.aintain the pool levels where the high or low water level annunciators are not actuated. The proposed actier wculd also perrnit an

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2 easier transfer through the fuel transfer shield and would permit placing control rods on hangers provided for their storage in the fuel building pool.

Environmenta Q Lacts of the proposed Action The Commission has completed its evaluation of the proposed revisions to the Technical Specifications. The proposed revisions would reduce the minimum i

l water coverage above a single spent fuel assembly in the storage pool from 8 feet 6 inches to 8 feet 2 inches, and above an irradiated control rod from 8 feet ( inches to 6 feet 9 inches.

TS 4.9.6.1 would be modified to require demonstration that the normal uptravel stop interlock of the refueling platform main hoist maintains at least 8 feet 2 inches of water coverage above the' top of the active irradiated fuel and that the normal uptravel stop interlock of the frame-mounted and mencrai'-meunted auxiliary hoists maintain at least 6 4

feet 9 inches of water coverage above the top of the irradiated control rod, s

j The surveillance requirerents of TS 4.9.6.2 would be modified in a similar manner to require demonstration that the normal uptravel stop interlock en the fuel handling platform main hoist maintains at least 8 feet 2 inches of water coverage above the top of the active irradiated fuel and that the normal uptravel stop interlock of the monorail-mounted auxiliary hoist maintains at least E feet 9 inches of water coverage above the top of the irradiated control rod.

The pool water (as well as the water level above the reactor pressure vessel flange) will remain unchanged at a minimum of 23 feet above the spent fuen in the storage racks. Therefore, the proposed change would not increase the probability or consequences of any accident previously evaluated.

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.. I Ttt licensee estimattd a radiatier. dose rate increase to personnel on the refuelir.s platform of 0.2 inrem per hour due to the reduction of water coverage f

atove the active zene of the irradiated fuel and 0.3 r. rem per hour fron are s

irradiated control rod.

In addition, the licensee estiri.ated that personnel l

l radittien exposure over the plar.t design life would iricrease by 0.2 man-Ren frcr.irrediated fuel and 0.01 r.an-Ren from irradiated control rods. Thus, I

lr thers is r,o significent increase in the allowable individual or curolative a

occupatienal radi6 tion exposure.

.here art no changes beitig rnade in the types of any effluer.ts that rey be rele6 sed effsite orid the offsite dose consequences of a pcstulated fuel bar d11r.g accident will net be effected by the propcsed changes to the TS ar.d the resultir.g tifsite dose wculd rerait,well witbin the 10 CFR Part 100 guitelir.t s.

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1.cccrdinoly, tre Cocrissico concludes thct this proposed action wculd

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result in tie sigt ificent radiolcsical environterital impact.

l 1:ith regard to potet:ti61 rer. radiological itpacts, the proposed change to l

1 the TS invohe systers located withir. the restricted areas as defined in 10 CFR j

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Fart 20.

It dees not affect nonr6diological plant effluents and has rio other

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environeerital inpact. Therefore, the Corr.ission concludes that there are no i

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significant rionradiological enviror. mental impacts associated with the proposed art endctnt.

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The I:ctice of Consideration of Issuance of Amendirents end Opportunity for

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i Hearing in connection with this action was published in the FEDERAL FEGISTER i

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on August PS, 1988 (53 FR 324f 4) and a correction was tublished on Octcber 24, 1908 (E3 Fp 41034). ho request for hearing or petition for leave to intervene wcs filed folicwing these retices.

Alternative _ tp, th,e, Prpppsed, A,c,t,ipn Since the Comissico cor.cluded that there is no significant adverse invironner.tal effect that would result fron the proposed action, alternatives with equal er greater er.vircrrei tal irrects need not be evaluated.

The principel alttri.etive would be tc dery the recuested arner;dtrent. This wcult r.ot redt,ct er.vircrr, ental irtacts of plar t operation er d would result ir.

reduced operatienal f1thibility.

A l t t r r a,t,iy,t, l',s t, p,f, P,e,spu r,cy,s This actiori does not imc1ve the use of resources not previously considered iri the Fir a1 Er,vironner.tti Stetteer.t fcr the Fiver Bend Station, l'r.it 1, dated Jarvary Ifff.

Acencies er d Persons Cersulted The t:RC staff h<s revitwed the licer.see's request er.d did r.ct consult Other ager.cies or per sor.s.

F11:0!P1 Of f.'0 $16f:1FICAl.1 lt: PAC 1 The Comission h6s deterr. ired not to prepare an environrental irpact statenes.t for the propcstd lictnse orendnent.

Eased upon this er.viror.r er tal assessrent, we conclude that the proposed action will not have a sigriificant adytrse effect on the quality of the hucan environrent.

l For further details with respect to this action, see the applicaticr. for l

l eret.drer.t dated August I?,1968 which is available for public irispectier, at the 1

...o 5-Corr.issicn's Fcblic Docurent Roor, ?120 L Street, N.W., Washington. 0.C., ard at the Goverrtent Cocurents Departrent, Louisiana State University. Eston Rouge, Lcuisiana 70803.

Dated at Rociville, Faryland, this FCR THE NUCLEAR REGULATORY COPJ'15510h n

d. (adM Jo'se A. Calvo, Director Project Directorate - IV Division of Feector Projects - III.

!Y, V and Special Projects Office of Nuclear Fe6ctor Regulation

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