JSP-473-92, Forwards Clinton Power Station Ipe,Final Rept, in Response to GL 88-20,Suppl 1, Initiation of IPE for Severe Accident Vulnerabilities. Results Not Significantly Different from Results Reported to NRC During 920520 Meeting

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Forwards Clinton Power Station Ipe,Final Rept, in Response to GL 88-20,Suppl 1, Initiation of IPE for Severe Accident Vulnerabilities. Results Not Significantly Different from Results Reported to NRC During 920520 Meeting
ML20106B795
Person / Time
Site: Clinton Constellation icon.png
Issue date: 09/23/1992
From: Jamila Perry
ILLINOIS POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20106B800 List:
References
GL-88-20, JSP-473-92, U-602040, NUDOCS 9210050174
Download: ML20106B795 (2)


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"tinois Power Company

>. Unton Power Station P O Box 678

  • . Citnton. IL 61727 Tel 217 935-0226 Fu 217 935-4632 J. Stephen Perry

&not Vice Pre 90ent ILLIN(SIS

- POWER u-6 2040 L30-92(09-23)LP 1A.120 JSP-473-92 September 23, 1992 Docket No. 50-461 U. S. Nuclear Reguletory Commission Docum3nt Control Desk Washington, D.C. 20555 Subj ect: Clinton Power Station Response to Generic Letter 88-20, Supplement 1

Dear Sir:

This letter is in response to Generic Letter (GL) 88 20, Supplement 1, " Initiation of the individual Plant Examination for Severe Accident Vulnerabilities". In letter U-601549 dated October 27, 1989, Illinois Power (IP) committed to perform an Individual Plant Examination (IPE) on Clinton Power Station (C15) and provide the results by September, 1992. The results of the IPE are forwarded as the attachment to this letter.

The IPE was conducted as :leseribed la IP letter U-601549, as a level 1 Probabilistic Risk Assessment (FRA) with containment analysis in eccordance with Appendix A to NUREG-1335 " Individual Plant Examination Submittal Guidance". The attached report is structured as specified in NUREG-1335. Additional recond-tier documentation of the methods, models l and data used to perform the IPE is available for future use and audit by the Nuclear Regulatory Commission (NRC).

The IPE results show that the analyzed frequency of core damage events f CPS is 2.6E-5 events per reactor year, and that the expected trequency of release from the containment -is 1.3E-6 per t eactor year, including small and scrubbed releases. The expected frequency of major L release from-the containment is 4.8E-8 per reactor year.

The CPS IPE results are not significantly different from the preliminary results reported to the NRC during the meettug with the domestic LWR-6 plants on May 20, 1992. CPS is available to meet with the NRC to discuss any questions on the results or the process employed.

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., .Page 2 of 2 i to U-602040, l

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IP' intends to inaintain the risk assessment models' consistent with the -

plant configuration and apply the PRA as a management tool and is still-evaluating potential future applications.

1 hereby affirm that the information in this letter is correct to the-best:of my knowledge, q

l Sincerely yours, i l

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.i J. , Perry l Senior Vice President WSI/msh cc: NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC 1111nois Department of Nuclear Safety Nuclear Management and Resources Council l

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