ML20080T602
| ML20080T602 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/03/1995 |
| From: | Wadley M NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9503140026 | |
| Download: ML20080T602 (2) | |
Text
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Northem States Power Company Prairie Island Nuclear Generating Plant 1717 Wakonade Dr East Welch, Mmnesota 55089 10 CFR Part 50 March 3, 1995 Section 50.12 Section 50.90 U S Nuclear Regulatory Commission Document Control Desk Attn:
Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLA Docket Nos. 50-282 DPR-60 50-306 Specific Exemption from 10CFR50, Appendix J,
- 23. 1991 II. dated February i
Tyne A Periodic Schedule Reouirements for Un t s in support of the subject i
This letter is submitted to provide clarificat on e Amendment Request.
i dix J, Type A containment Prairie Island Nuclear Generatin5 l period is scheduled to be refueling in May 1995. The third 10CFR50, Appenleakag 1995. The performed during this outage. The subject f this test on Unit II durin5visi.,n to the Prairie Islan temporary relief from performance o d Technical Specifications k
associated License Amendment Request see s reh ll apply to both l
Technical Specifications. Since the Prairie Is an are identical, the License Amendment s a d steel structures basis accident and low leakage. A The Prairie Island containment vessels are free-stan designed for the peak pressure of the designtainment vessel, providing a concrete shield building surrounds the con trations of the containment building annulus between the two structures. Peneducts and access hatches are vessel for piping, electrical conductors,k provided with double barriers against lea age.
t structure, the vessel shell Due to the free-standing design of the containmenfrom both inside containment i
and penetrations are accessible for inspect on and outside in the shield building annulus.
d on seals and f
10CFR50, Appendix J, Type B and C tests will be per ormeAs further ass 11 1995 outage.
penetrations during the Unit gIh i
- I 9503140026 950303 gg ADDCK 05000306 PDR PDR P
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,7-4 USNRC March 3; 1995 Page 2 containment structuras integrity and leak-tightness, a general inspection of I
I the containment structures and components shall be parformeu in accordance with the provisions of 10CFR50, Appendix J, Section V.A.
If you have any questions related to this Request for Specific Exemption or associated License Amendment f.equest please contact myself or Dale. Vincent at (612) 388-6758 extension 4107.
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M. D. Wadley
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Plant Manager p
i Prairie Island Nuclear Generating Plant c: Regional Administrator-III', NRC NRR Project Manager, NRC Senior Resident Inspector, NRC State of Minnesota Attn: Eris Sanda J E Silberg i
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