ML20086T908

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Withdraws Relief Request 66 from ASME Code Section XI Insp & Testing Requirements for Certain Nozzles.Util Proposes to Obtain One or More Nozzle Knockouts Each Yr.One New Nozzle Will Be Examined Each Cycle on Each Unit
ML20086T908
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 12/30/1991
From: Parker T
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9201070107
Download: ML20086T908 (2)


Text

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Northem States Power Company 414 Neollet Mall Minneapohs. Minnesota $54011927 Telephone (012) 330-5500 December 30, 1991 10 CFR Part 50 Section 50.55(g)

U S Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555 PRAIRIE ISTAND NUCLEAR CENERATING PLANT Docket Nos. 50 282 License Nos. DPR 42 50 306 DPR 60 ASME Code Section XI Inspection and Testing Program Recuest for Relief No. 66 Request for Relief No. 66 is hereby withdrawn for both units.

Technological improvements now allow a meaningful calibration.

Request for Relief No. 66 was originally submitted for relief from examination of certain Prairie Island nozzles.

At the time the relief request was made, it was anticipated that better examination technology would shortly be available.

Since that time technology has improved.

In addition, we have evaluated the use of a " Knock out" type calibration standard as opposed to an ASME " basic calibration" block as a means to achieve a meaningful calibration.

Based on the above, we are withdrawing the relief request and submitting a request for an extension of schedule for examining the subject nozzles. We propose to obtain one or more nozzle knockouts each year.

Material availability is a limitation to obtaining the knockouts at a faster rate.

The appropriate nozzle (s) on each Prairie Island unit will be examined as the knockouts become available and as procedure development allows. At a minimum, one new nozzle would be examined each cycle on each unit.

The first examination under this schedule would be one of the Unit 2 Steam Generator Feeiwater Nozzles during 1992 (the Unit 1 Steam Generator Feedwater Nozzles hase already been examined), We will include the current status in each suumary report.

After all of the subject nozzles have been examined, the examination schedule will revert to the normal Section XI schedule, i

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' December _30.-1991 Page 2 uf 2 Northern States Power Company Please contact us if you have any questions related to this request,

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n Thomas M Parker Manager Nuclear Support Services c: Regional Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC State of Minnesota llartford Insurance J E Silberg l

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