ML20112E860
| ML20112E860 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 06/04/1996 |
| From: | Link B WISCONSIN ELECTRIC POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| VPNPD-96-037, VPNPD-96-37, NUDOCS 9606070105 | |
| Download: ML20112E860 (1) | |
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Wisconsin Electnc POWER COMPANY 231 W Michigan. PO Box 2046. Mdwoukee. WI 53201 2046 (4141 221-2345 VPNPD-96-037 10 CFR 50.4 10 CFR 50.90 June 4,1996 10 CFR 50.12 Document Control Desk US NUCLEAR REGULATORY COMMISSION Mail Station PI-137 Washington,DC 20555 Gentlemen:
[LQGETS 50-266 AND 50-301 WITHDRAWAL OF TECHNICAL SPECIFICATIONS CHANGE REOUEST 186 AND REOUEST FOR EXEMirrlON FROM 10 CFR 50. APPENDIX J POINT BEACH NUCLEAR PLANT. UNITS I AND 2 On February 27,1996 we submitted Technical Specifications Change Request 186 to incorporate changes to the plant Technical Specifications regarding frequency requirements for the performance of containment Integrated Ieak Rate Tests (ILRTs). Also included in our February 27,1996 submittal was a request for a one-time (temporary) exemption from 10 CFR 50, Appendix J to permit the Type A test for Unit 2 to be performed during the Fall,1997 refueling outage rather than the Fall,1996 refueling outage.
Discussions regarding our submittal were conducted with Mr. Allen Hansen and others of your staffin telephone conferences on March 14 and 19,1996. Following these discussions, we have determined that a more suitable approach would be to implement Option B to Appendix J prior to the Fall,19% Unit 2 refueling outage. Therefore, we are hereby withdrawing Technical Specifications Change Request 186 and the exemption request contained in that submittal.
Our Technical Specifications Change Request to implement Option B will include a one-time exception to the guidance provided in NRC Regulatory Guide 1.163," Performance-Based Containment Leak-Test Program," and NEl 94-01,
" Nuclear Energy institute - Industry Guideline for Implementing Performance Based Option of 10CFR Part 50, Appendix J," in that the next Type A test on Unit 2 will be performed 60 months after the last test instead of 48 months.
This will allow us to perform the Unit 2 Type A test during the Fall,1997 refueling outage.
If you require ndditional information, please contact us.
I Sincerely, hM Bob ' i Vice President 070051 Nuclear Power KVA.
cc:
NRC Resident Inspector NRC Regional Administrator, Region III PSCW 9606070105 960604 PDR ADOCK 05000266
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