ML20077S210
| ML20077S210 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/09/1995 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9501230328 | |
| Download: ML20077S210 (2) | |
Text
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Northern States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr. East Welch, Minnesota 55089 January 9, 1995 10 CFR Part 50 Section 50.90 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISIAND NUCLEAR CENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 License Amendment Request Dated December 5, 1994 Channes in Containment Refuelinz Interrity Reauirements This letter is submitted to provide clarifications in support of the subject
' License Amendment Request.
The proposed amendment to Technical Specification 3.8.A.l.a requires, "At least one door in each airlock is OPERABLE and under procedural control." The requirement to maintain the airlock OPERABLE will preclude installing cables and hoses in the airlock since these obstacles could not be readily removed.
It is our current practice and continuing intent to install small platforms on the floor of the airlock and adjacent containment floor to facilitate safe movement of personnel and materials into containment, These platforms are readily removable from the airlock by a single designated individual. Once the a. platfor:ns are removed, the airlock doors are completely unobstructed and can be closed.
The airlock doors will be under control of a plant procedure which will designate an individual to remove the platforms and close the airlock.
The requested amendment also requires that, "The containment (high flow) purge system is isolated.
" It is our intent to meet this requirement by either closing the isolation valve in the. annulus or installing the blind flange or both. The isolation valve is not a containment isolation valve because the j
blind flange is always installed at power operation. Nonetheless, this valve will satisfactorially provide containment isolation to meet this proposed Technical Specification under the low pressure conditions following a fuel handling accident.
200051 i l.0 9501230328 950109 PDR ADOCK 05000282 P
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/' USNRC January 9,*1995 Page 2 If you have any questions related to this License Amendment Request please contact myself or Dale Vincent at (612) 388-6758 extension 4107.
lf lV AA M. D. Wadley Plant Manager Prairie Island Nuclear Generating Plant c: Regional Administrator-III, NRC NRR Project Manager, NRC Senior Resident Inspector, NRC State of Minnesota Attn: Kris Sanda J E Silberg i
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