ML20010B255
| ML20010B255 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/31/1981 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20010B256 | List: |
| References | |
| NUDOCS 8108140273 | |
| Download: ML20010B255 (2) | |
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Northe.n States Power ' ampany (V) 414 Nicollet Mall Meneapons. Menesota 55401 Telephone (812) 330-5500 July 31, 1981 clMQ/
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Director of Nuclear Reactor Regulation 01
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(;63.s.eu m m e n U S Nuclear Regulatory Commit son 4
Washington, DC 20555 u
po gra m PRAIRIE ISLAND NUCLEAR GENERATING PLANT g
Docket No. 50-282 License No. DPR-42 50-306 DPR-60 N
Information Required for NRC Review of Inservice Inspection and Testing Program and Requests for Relief from ASME Code Section XI Requirements Attached for your review you will find 40 copies of Revision Number 6 to our report entitled, "ASME Code Section XI Inservice Inspection and Testing Program and Information Required for NRC Review of Requests for Relief
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from ASME Code Section XI Requirements." This is a revision of our inservice inspection and testing program description and requests for relief submitted to the Commission on February 1, 1978.
The purpose of this revision is to update the Prairie Island Inservice Inspection and Testing Program to include the conclusions of the NRC Staff's Safety Evalua-tion of the Prairie Island Inservice Inspection Program. This Safety Evalua-tion was issued in conjunction with Amendment No.'43 and DPR-42 and Amendment No. 37 to DPR-60 dated November 14, 1980. Staff review of the Inservice Testing portion of the Prairie Island program is.still in progress.
All program changes required by the Safety Evaluation are included in this revision.
It'em VII of the Safety Evaluation, " Augmented Inspection for Units 1 and 2," was implemented by adding to the regular inspection program all those systems and components previously exempted due to IWC-1220(c)
(chemistry control). This addition far exceeds the ten percent of the total number of welds in each individual system required by Safety Evaluation Item VII.
No augmented inservice inspection program as such was added to the program.
A small number of typographical errors and other discrepancies are also corrected by this revision. Additions to the program reflecting plant modifi-cations since the last revision are included as well as two additional requests for relief (No. 63 and No. 64).
These revisions are being submitted for NRC Staff review and approval in
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accordance with the provisions of 10 CFR Part 50, Section 50.55a(g).
Attached is one copy of the Licensing Fee Determination and a check in the amount of C.
$4400.00 as required by 10 CFR Part 170, Section 170.22.
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8108140273 810731 PDR ADOCK 05000282 y\\
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NORTHMN STATES POWM COMPANY O
Director of Nuclear Reactor Regulation July 31, 1981 Page Instructions are provided for entering Revision 6 in the or'iginal February 1,~1978 report. Please contact us if you have any questions related to this revision.
o L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh cc J G Keppler G Charnoff State of Minnesota (H Baron)
Hartford Insurance (S Tack)
NRC Resident Inspector O
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