ML20106E305
| ML20106E305 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 11/03/1992 |
| From: | Parker T NORTHERN STATES POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9211060319 | |
| Download: ML20106E305 (2) | |
Text
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,V Northem States Power Cornpany 414 Nicollet Mah Menneapohs. Minnesota 55401 1927 Telephone (612) 330-5500 November 3, 1992 U S Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PIANT Docket Nos. 50-282 License Nos. DPR-42 l
50-306 DPR-60 1
Renorting of Steam Generator ',ngnaction Results The propose of this letter is to clarify when the detailed results of the No.
j 72 steam generator oddy current inspection, completed October 2, 1992, will be l
provided to the NRC.
Our letter, dated Oct. - t 14, 1992, " Steam Generator Tube Plugging and Sleeving", mistakenly reported the inspection of Unit 1 steam generator No. 12, which was corapleted on Oceber 2,1992, as an inservice inspection.
This steam generator tube inspection was performed in response to increased Unit 1 primary to secondary leakage. This leakage did not exceed the limits of Technical Specification 3.1.C.2.e before the unit was shutdown, and therefore, the inservice inspection requirements of Technical L
Specification 4.12 were nor implemented.
Prairie Island Technical Specification 4.12.E.2 requires that the results of steam generator tube inservice inspections, not associated with a refueling outage, be submitted within 90 days of the completion of the inspection.
In l
accordance with these requiremerits, our October 14, 1992-letter stated that l;
expanded information sn the No, 12 steam generator-inspection would be provided in an inservice inspection report within 90 days of the completion of -
the inspection.
However, because this a.pection was not performed in response to Technical Specification 4.12, or as part of the normal scheduled l
inse,vice inspection program; it was not considered an. inservice inspection.
Rather, it was considered an engineering surveillance intended to identify sources of steam generator tube leakage.
L l
P>ccause the requirements of Technical Specification 4.12 E.2 do not apply to this' inspection,-an expanded inservice inspection report will not be provided within 90 days of the completion of the inspection as stated in our October 14, 1992 letter.
Rather, the expanded information on the No. 12 steam-generator inspection will be included with the summary reports ASME Code Section XI inspections to be submitted witbin 90 days of the completion of the currant two unit outage.
9211060319 921103
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,_ November 3, 1992 Page 2
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Nodhem States Power Oxnpa, y We apologize for any inconvenience that may result from this change.
Please contact us if_you have any questions with regards to the reporting of the results of the No. 12 steam generator inspection.
/ $
Thomas M Parker Manager Nuclear Support Services c: Regional-Administrator - Region III, NRC Senior Resident Inspector, NRC NRR Project Manager, NRC J E Silberg
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