ML20076C801
| ML20076C801 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/11/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20076C806 | List: |
| References | |
| NUDOCS 9107240321 | |
| Download: ML20076C801 (4) | |
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4 7590-01 903.Tf.p_)JbJ{}, p,0 C[{3,R, F E,Gyk 3Jp,R,Y, j 0ttM I S S 10 N PUBLIC SERVICE ELECTRIC & GAS COMPAhY PHILADELPHIA ELECTRIC COMPANY DELPARVAPOWERApp,,LJG,H,T,CpMfppl ATLANTIC CITY ELECTRIC COMPANY SALEM NUCL,E,A,R,,GENERAT!!;0 STATJp,N,, UNITS 1 AND 2 pp,C,KgJ NpS,.,50-272 AND 50-311 ENVIROHt'ENT,'i ASSESSM,E,NT AtlD FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of an amendment to Faci'ity Operating License Nos. DPR-70 and DPR-75, issued to Public Service Eleccric and Cas Company, et. al. (the licensees) for operation of the Salem Nuclear Generating Station, Units 1 and 2, located at the licensees' site in Salem County, New Jersey.
Ep,VJRppp,EpJ!,L, ASSESSMENT I d e n t i f i ca t i op, p,f,,P rpp,o,sp,d, A ctj p n :
The proposed amendment would allow the licensees to place fuel with a maximum initial enrichment of 4.55 weight percent of U-235 (w/o U-235) in the i
reactor, new fuel storage racks and the spent fuel storage racks.
The proposed action is in accordance with the licensees' application for amendments dated November 19, 1990, as supplemented by letters dated April 1, 1991, May 20, 1991 and June 14, 1991.
l The Need for the Fcop,o,spd, Ac,tjp,n:
The licensees intend to increase the fuel enrichment for the Salem-units to a maximum initial v0lue of 4.55 w/o U-235. New fuel will be stored in the l
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. new fuel storage racks while awaiting loading into the core, it is anticipated that the higher enrichment fuel will be used for the Salem 1, Cycle
- 1 reload and for the Salem 2, Cycle 8 reload. Currently, fuel with a maximum initial enrichment of 4.05 w/o U-235 can be stored in the new fuel storagr racks, placed in the reactor or stored in the spent fuel storage pool.
Ea ironnental Impa,c,t,s, o,f_th,e proposeo,Ac,t,1,o,n:
The Commission has completed.its evaluation of the proposed revisions to the Technical Specifications (TSs).
The proposed amendments would allow fusi L
with a maximum initial enrichirent of 4.55 w/o U-235 to be stored in the new fuel storage racks, placed in the reacter or stored in the spent fuel storage pool. Currently, feel with a maximum enrichment of 4.05 w/o U-235 may be placed in the aforemantioned locations.
Changes to the burnup limits have not been requested. Therefore, use of fuel with a maximum enrichment of 4.55 w/o U-235 would not significantly increase the probability of consequences of any accidents previously analyzed. No significant changes in the types or amounts of radiological effluents, during normal operation or postulated accidents, that may be released offsite are incurred by the increased w/o U-235 enrichment. As a result, no significant increase in the individual or_ cumulative occupational radiation exposure is noted.
Therefore, because the proposed changes do not increase the probability cr consequences of accidents, no changes are being made in the types or amounts of any radiological effluents that may be released offsite and there is no significant increase in the allowable individual or cumulative occupational radiation exposure, the Commission concludes that this proposed action would result in no significant radiological environmental impact.
e With regard to pctential nonradiological impacts, the proposed change to the TSs involves systems located within the restricted area as defined by 10 CFR part P0. The proposed change will not result in a measurabic change to the nonradiological plant effluents and therefore will not have any environmental impact.
The environmental impacts of transportation resulting from the use of higher enrichment fuel and extended irradiation are discussed in the staff assessment entitled, "HRC Assessment of the Environmental Effects of Transportation Resulting from Extended Fuel Enric.hment and Irradiation",
published in the FEDEPAL-REGISTER on August 11, 1988 (53 FR 30355).
As indicated thetein, the environmental cost contribution of the proposed increase in the fuel enrichment and irradiation limits are either unchanged or may, in fact, be reduced from those summarized in Table S-4 asset forth in 10 CFR 51.52(c). The licensees confirmed that this analysis is applicable to the recuested change.
i Therefore, the Commission concludes that there are-no significant nonradiological envirormental impacts associated with the proposed amendments.
Alternative to the P,r,opo,se,d, Ac_ tion:
Since the Commission' concluded that there are no significant environmental effects that would result from the proposed action, any alternatives with equal or greater environmentai impacts need not be evaluated.
The principal alternative would be to deny the requested amendments. This would not reduce environmental impacts of plant operation and would result in reduced operational flexibility.
', AlternativeUseofResources:
This action does not involve the use of any r..ources not previously considered in the " Final Environmental Statement Related to Operation of Salem Nuclear Generating Station, Units 1 & 2," dated April 1973.
Ajencies and Persons Consulted:
The NRC staff reviewed the licensees' request and did not consult other agencies or persons.
FINDING OF N0 SIGNIFICANT IMPACT:
The Commission has determined not to prepare an environmental impact statement for the proposed license amendments.
Based on the foregoing environmental assessment, we conclude that the proposed action will not have e significant effect on the quality of the human environment.
For further details with respect to this action, see the applica'cibr. for amendments dated November 11, 1990, and supplements dated April 1
- 1991, 3
May 20, 1991 and June 14, 1991, which are available for publin ?hsp;ction at the Commission's Public Document Room, 1120 L Street, NW w uh'14toa, DC l
20Ta5 and at the Salem Free County Public LiF rary, %. Brocacy, Salem, i
Fw Jersey 08079.
Octed at Rockville, Maryland, this lith day luly 1991.
l FOR THE MCLJk Ris.JTORY COMMISSION D '.n '
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y Walter k. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation l
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