ML20141M958
| ML20141M958 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/12/1986 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20141M959 | List: |
| References | |
| NUDOCS 8603030134 | |
| Download: ML20141M958 (4) | |
Text
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UNITED STATES NUCLEAR REGULATORY C0 MISSION _
ILLIN0IS POWER COMPANY _
DOCKET N0. 50-461
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ENVIRONMENTAL ASSESSMENT AND FINDING OF l
NO SIGNIFICANT IMPACT _
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j The U.S. Nuclear Regulatory Comission (the Comission) is issuing f
i exemptions from certain requirements of 10 CFR Part 50 to the Illino s Station, Unit I facility i
tower Company (the applicant) for the Clinton Power
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located in Dewitt Cobnty, Illinois.
I ENVIRONMENTAL ASSESSMENT l
Containment Airlock Testing A.
Identification of Proposed Action 1 The exemption would eliminate the full pressure test required b III.D.2(b)(ii) of Appendix J each time the air lock is opened during test when containment integrity is not required and substitute a seal leaka ifications. The to be conducted at a pressure specified in the Technical Spec 1985.
exemption is in accordance with the applicant's request dated Dec The Need for the Action:
The exemption is required to provide the applicant with' greater pla availability over the lifetime of the plant.
Environmental Impact of-the Action:
The exemption would allow the substitution of an airlock seal tes ling mode.
an airlock pressure test whife the reactor is in a shutdown or refue tl With respect to this exemption from Appendix J, the increment of en d
impact is rehted solely to the. potential increased probability i lly greater of containment leakage during an accident which would lead to potent a However, the potentici increase due to this offsite radiological consequences.
8603030134 860212 PDR ADOCK 05000461 A
PDR e
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j exemption is small and would result from the potential leakage path t
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The the door mechanism which will not be measured by this modified test.
6-month test requirement of paragraph III.D.2(b)(1) of Appendix J, the 3 test requirement of paragraph III.D.2(b)(iii) cf Appe'ndix J and the test h
requirements when maintenance is performed on the airlock, will meas leakage through the door mechanism and provide assurance that th will not leak excessively.
Alternative to the Proposed Action:
Because the staff has concluded that there is no mea impact associated with the exemption, any alternative to the exem have either no environmental impact or greater environmental impact.
This The prir.cipal alternative would be to deny the requested exemptio lt would not reduce the environmental impacts of plant operations and wo in reduced' operational flexibility and unwarranted delays in power asc Leak Rate Testing of Main Steam Isolation Valves (MSIV's)
B.
Identification of Proposed Action _:_
The exemption would exclude the measured leakage frem the MSI The proposed exemption is in summation of the local leak rate test results.
accordance with the applicant's request dated December 9,1985.
The Need for the Proposed Action:_
The exemption is needed because the NRC staff in Supplement 2 to t Clinton Safety Evaluation Report found the applicant's proposed MS leakage control test program acceptable, and concluded that the desion of the MSIV The Clinten Technical Specifications have been system at CHnton is acceptable.
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written based on the NRC staff's evaluation in Supplement 2 to the Cli
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I 3-Environmental Impact of the Action The proposed exemption would exclude the measured leaka l
The MSIV leakage control system from the combined local leak rate test results.
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d cts at Clinton is designed to control and minimize the release of fission pro u I
l t accident that could leak through the closed MSIV's af ter onset of a loss of coo an 1
l The (LOCA) by maintaining a negative pressure between the MSIV's i d by the stand-effluent will be discharged into a volume where it will be processe A radiological j
by gas treatment sys' tem before being released to the environs.
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s analysis including this potential source of containment atmosphere le l
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ify that
' performed, and the MSIV's will be periodically leak rate tested to ver!
the leakage assumed in the radiological analysis is not exceeded.
Alternative to the Proposed Action:'
The proposed CPS Technical Specification requirements will prov i
l increase reasonabV essurance against undue MSIV leakage and that no materia I
Therefore, in the probability or extent of MSIV leakage is to be expected.
l' ident there is no significant increase in the probability of higher post-acc i
ificant offsite or onsite doses related to the proposed exemption and no s gn l
increase in environmental impact beyond that experienced with no The principal alternative would be to deny the requested exempti ld This would not reduce the environmental impact of plant operations f
provide no greater assurance that offsite or onsite doses, in the ev t of an l
accident that resulted in fission product release, would be any less.
Alternative Use of Resources:_
These actions in the granting of exemptions A and B above do h " Final the use of resources not previously considered in connection with t e Environmental Statement Related to the Operation of the Clinto i
Unit 1," dated May 1982.
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Agencies and Persons Consulted:
The NRC staff reviewed the licensee's requests that support the reque The NRC staff did not consult other agencies or exemptions A and B above.
persons.
FINDING OF NO SIGNIFICANT IMPACT _
The Commission has determined not to prepare an environmental impact statement for the requested exemptions.
Based upon the foregoing environmental assessment, we conclude that t requested actions will not have a significant effect on the quality of the human environment.
For further details with respect to this action, see the requests for the exemptions as listed herein, which are available for public inspection at the Commission's Public Document Room, 1717 H Street, N.W., Wash 20555 and at the Vesparian Warner Public Library,120 West Johnson Street, Clinton, Illinois 61727.
Dated at Bethesda, tiaryland, this 12th day of February 1986 FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Director BWR Project Directorate fio. 4 Division of BWR Licensing 9
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