ML20043E325
| ML20043E325 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 06/07/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20043E326 | List: |
| References | |
| NUDOCS 9006120300 | |
| Download: ML20043E325 (4) | |
Text
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t 7590-01 UNITED STATES Nt' CLEAR REGULATORY COMMISSION GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U.S. Nuclear Regulatory Comission (NRC or the Comission) is considering issuance of an amendment to Provisional Operating License No.
l DPR-16issuedtoGPUNuclearCorporation,et.al.(thelicensee),for operation of the Oyster Creek Nuclear Generating Station, located in Ocean County, New Jersey.
4 ENVIRONMENTAL ASSESSMENT Identification of Proposed Action:
The proposed ainendment would revise Technical Specification (TS) 3.3.F.2.
Specifically, the change would include limitations on operation with an idle recirculation loop which is isolated.
A revision to Section 3.3 and I
3.10 bases would also be needed to reflect this change.
The proposed amendment is in accordance with GPU Nuclear Corporation's application dated March 19, 1990.
The Need for the Proposed Action:
The proposed changes to the Technical Specifications are needed so that the recirculation pump could be isolated without requiring an unnecessary shutdown. The licensee proposed the Technical Specification change as a result of a Technical Specification - required shutdown on February 6,1990. The i
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1 shutdown was required when the unidentified leak rate approached the Technical Specification limit of 5 gallons per minute. The leakage was due to a failed recirculation pump seal on recirculation loop A.
If the pump could have been isolated, the leakage might have been reduced, and a shutdown averted. The ability to isolate a recirculation pump would prevent unnecessary shutdowns in the future.
Environmental Impacts of the Proposed Action:
The Commission has completed its evaluation of the prosed revisions to the Technical Specifications. The proposed revisions would allow an idle recirculation loop to be isolated. Oyster Creek is currently authorized to continue power operation if one of the five recirculation loops is taken out of service provided the idle loop is not isolated. The authorized configur-4 ation allows the loop discharge valve to be closed and the discharge bypass valve and suction valves to be open. The reouested change would allow the discharge bypass valve and suction valve as well as the discharge valve to be closed, thus, completely isolating the portion of the recirculation loop containing the pump. Lossofcoolantaccident(LOCA)andthermalstress analyses support the proposed change.
Based on our review, the staff has concluded that radioactive releases and thermal stress levels remain within the design basis limits since there are no physical changes being made to the facility. Operation in the proposed manner precludes the occurrence of a severe cold water addition transient which is an analyzed transient of moderate frequency.
Based on the above, the staff has determined that the proposed Technical Specifications do not alter any initial conditions assumed for the design j
basis accidents previously evaluated nor do they change operation of safety l
ie 3
e systems utilized to mitigate them. Therefore,theproposedchanges(1)donot involve a significant increase in the probability or consequences of any e
accident previously evaluated, (2) do not create the possibility of a new or different kind of accident from any accident previously evaluated and (3) do not involve a significant reduction in the margin of safety.
Therefore, the proposed changes do not increase the probability or consequences of accidents, no changes are being made in the types of any effluents that may be released offsite, and there is no significant increase in the allowable individual or cumulative occupational radiation exposure.
Accordingly, the Commission concludes that these proposed actions would result in no significant radiological environmental impact.
With regard to potential rentadiological impacts, the proposed changes to 4
the Technical Specifications involve the reactor coolant system which is located within the restricted area as defined in 10 CFR part 20. They do not affect nonradiological plant effluents and have no other environmental impacts. Therefore, the Connission concludes that there are no significant nonradiological environmental impacts associated with the proposed amendrwnt.
The Notice of Consideration of Issuance of Amendment and Opportunity for Hearing in connection with this action was published in the FFDERAL REGISTER on April 10,1990(55FR13341). No request for hearing or petition for leave to intervene was filed following this notice. Alternatives to the Proposed Action:
Since the Connission concluded that there are no significant environmental effects that would result from the proposed actions, any alternatives with equal or greater environmental impacts need not be evaluated.
The principal alternative would be to deny the requested amendment. This alternative would not reduce environmental impacts of plant operation and the inability to isolate a pump may require unnecessary shutdowns in the future.
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Alternative Use of Resources:
The action would involve no use of resources not previously considered in the Final Environmental Statement (FES) for the Oyster Creek Nuclear Generating Station.
Uf.D.C.iE.S. a,nd, P,e rs,o,n,s Con s u l ted :
The NPC staff revicwed the licensee's request and did not consult other agencies or persons.
FINDING NO SIGNIFICANT IMPACT The staff has determined not to prepare an environmental impact statement for the proposed amendment.
Based upon the foregoing enviror.n.cntal assessrent, we conclude that the proposed actions will not have a significant effect on the quality of the 4
human environment.
For further details with respect to this action, see the application for amendment dated liarch 19, 1990, which is available for public inspection in the Comissicn's Public Document Room, the Gelman Building, 2120 L Street, j
N.W., Washington, D.C., and the Ocean County Library, Reference Department, 101 Washington Street, Toms River, New Jersey 08753.
Dated at Rockville, Maryland, this June 7,1990 FOR THE NUCLEAR REGULATORY COMMISSION O
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