ML20086C022
| ML20086C022 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/07/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086C028 | List: |
| References | |
| NUDOCS 9111210323 | |
| Download: ML20086C022 (4) | |
Text
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4; 7590-01 i
UNITED STATES NUCLEAR REGULATORY COMMISSION i
GPU NUCLEAR CORPORATION l
DOCKET NO. 50-289 ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT The U. S. Nuclear Regulatory Comission (the Comission) is considering i
issuanceofexemptionsfromtheprovisionsoft(1)-10CFR50.46,whichrequires the calculation of emergency core cooling system (ECCS) performance for reactors with Zircaloy clad fuel; (2) 10 CFR 50.44, which gives requirements to control the hydrogen generated by Zircaloy clad fuel after a postulated loss of-coolant-accident (LOCA)!and(3)AppendixKto10CFRPart50,whichpresumestheuse 1.
of Zircaloy fuel when doing calculations for energy release, cladding oxidation and hydrogen generation af ter a postulated LOCA, to GPU Nuclear Corporation, the licensee for Three Mile Island Nuclear Generating Station, Unit No. I (TMI-1),locatedinDauphinCounty, Pennsylvania.
ENVIRONMENTAL ASSESSMENT Identificat_ ion of proposed Action:
The proposed action wauld allow the licensee to use fuel assemblies whose cladding composition falls outside the definition of Zircaloy in the cited regulations. Twooftheseassemblies(leadtestassemblies)wouldbeloaded
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into the TN!-1 reactor core during the refueling outage in the fall of 1991.
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The licensee informed the NRC of its intention to install these special assemblies during a meeting on January 18, 1991. The exemption is being undertaken on the Comission's own initiative.
TheNeedfortheProposedAgion:
Theexemptionunderconsiderationisreededbecause10CFR50.46(a)(1)(1) and Appendix K to 10 CFR Part 50 require the demonstration of adequate ECCS performance for light water reactors that contain fuel consisting of uranium oxide pellets enclosed in Zircaloy tubest furthermore, 10 CFR 50.44(a) addresses requirements to control hydrogen generated by Zircaloy fuel.after a postulated LOCA.- Since some of the cladding the licensee proposed to use in these lead-test assemblies f alls outside the definition of Zircaloy, the Commission, on its own initiative, took into consideration exemptions from 10 CFR 50.44, 10 CFR 50.46, and Appendix K to 10 CFR Part 50.
The Comission believes that special circumstances exist since application of the rule in this
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case would not achieve the underlying purpose of the rule for those test assemblies. The underlying purpose of 10 CFR 50.46 and Appendix K to 10 CFR Part 50 is to establish requirements for emergency core cooling systems. The underlying purpose of 10 CFR 50.44 is to control hydrogen generated by the
- metal / water reaction after a postulated LOCA, regardless of whether that metal isZircaloyadttjrlo. The licensee has addressed the safety impact of installing asseab Mes under the provisions of 10 CFR 50.59. The staff has evaluated use of Zirio in its Safety Evaluations regarding Westinghouse
_ Topical Report WCAP-12610 dated July 1,1991, and October 9,1991. These evaluations concluded that facilities can continue to comply with the purpose of the appropriate regulations with Zirlo clad fuel. Therefore, the underlying I
purpose of the rule has been fulfilled.
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i Envircnmental Impacts of the Proposed Actioni With regard to potential radiological impacts to the general public, the j
exemption under consideration involves features located entirely within the restricted area as defined in 10 CFR Part 20.
It does not affect the potential i
for radiological accidents and does not affect radiological plant effluents.
The test fuel assemblies meet the same design bases as the fuel that is currently in the reactor. No safety limits have been changed or setpoints. altered _as a result of the use of these assemblies.
The FSAR analyses are bounding for the test assemblies, as well as for the rest of the core. The advanced zirconium-based alloys have been shown through testing to perform satisfactor,ily under conditions representative of a reactor environment and the material properties of-Zirlo and Zirealoy are very similar. The exemption under consideration, therefore, does not affect the consequences of radiological accidents; consequently, the Comission concludes that there are no significant radiological impacts associated with the exemption.
With regard to the potential environmental impact associated with the transportation of the Zirlo clad fuel assemblies, the advanced cladding has no impact on previous assessments determined in accordance with 10 CFR 51.52.
With regard to non-radiological impacts, the exemption under consideration 4
does not effect non-radiological plant effluents and has no other environmental impact. Therefore, the Comission concludes that there are no significant non-radiological environmental-impacts associated with the exemption.
Alternative to the-Proposed Actio_n:
t Since the Comission has concluded that there are no significant I
environmental effects that would result from the proposed action, any alternatives to this exemption will have either no significantly different environmental l
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impact or greater tMyironmental impact. The principal alternative would be to not allow the licensee to install the lead test assemblies. This would not reduce environmental imparts as a result.of plant operations and would have no regulatory technical basis.
Alternative use of Resources:
This action does not involve the use of resources not previously considered
-in the " Final Environmental Statement Related to the Operation of Three Mile Island Nuclear Ltation, Units -1 and 2," dated December 1972.
Agencies and Persons Consulted:-
The staff reviewed the licensee's request and did not consult other agencies or persons.
FINDING OF NO SIGNIFICANT IMPACT
.The Comission has determined not to prepare an environmental impact statement for the exemption under consideration.
Ba
" an the foregoing environmental assessment, the staff concludes that the pr. #,ed action will not have a significant effect on the quality of the human...vironment.
Dated at Rockville, Maryland this 7thday of November 1991.
FOR THE NUCLEAR REGULATORY COMISSION ej i
Johr F. Stolz, Direc Pr ect Directorate
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ision of Reactor Projects - I/II Office of Nut. lear Reactor Pegulation l
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