ML19347F301
| ML19347F301 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 05/12/1981 |
| From: | Mayer L NORTHERN STATES POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19347F302 | List: |
| References | |
| NUDOCS 8105180303 | |
| Download: ML19347F301 (2) | |
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Northem States Power Con'oany 414 Nicollet Mall Mar neapoks. Minnesota 55401 Telephone (612) 330-5500 s
May 12, 1981
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11 Director of Nuclear Reactor Regulation Q
M@ y[g Q U S Nuclear Regulatory Commission
,s Washington, DC 20555 f'
PRAIRIE ISLAND NUCLEAR GENERATING PLANT d
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Docket No. 50-306 License No. DPR-60 Unit 2 Inservice I'nspection Summary Report Attached for your review are four copies of the report, " Inservice Inspection-Examination Summary, Prairie Island Nuclear Generating Plant - Unit II, February 23 to March 23, 1981."
Your attention is directed to the following sections of the report which contain results of special inspections of components with potential deficiences as reported to the NRC Staff in earlier 'correspendence:
Section 4 Examination of Reactor Pressure Vessel and Outlet Nozzles As noted in the report, outlet nozzle underclad cracking examina-tions disclosed 22 discrete reflectors in the cylindical section of the Loop A nozzle bore and 83 discrete reflectors ir, the Loop B nozzle bore. The reflectors are shown to meet the acceptance standards of the ASME Code,Section XI.
Detailed fracture mechanics analyses performed by Westinghouse have been performed which confirm this conclusion.
No indications were found in the Unit 1 outlet nozzles as noted in Section 3 of the Unit 1 Inservice Inspection - Examination Summary transmitted for NRC review on December 19, 1980.
l Our inspection program was previously described in correspondence l
dated December 28, 1979 and July 7,1980.
l Section 5 Seismic Bolting l
As noted in the report, Unit 2 Steam Generator Bolting was inspected and replaced during the outage. Additional indications were found in the thread relief area on 36 bolts by magnetic particle examination. One additional bolt was found with a reduced back reflection using ultrasonic testing.
l 8305180 N 9
P NORTMEMN STATES POWER COMPANY j
Director of Nuclear Reactor Regulation May 12, 1981 Page This problem was initially reported to the NRC as License Event Report 80-25 on September 18, 1980 with corrected informa-tion supplied on September 25, 1980 and supplemental information supplied on December 3, 1980.
This report is being submitted in accordance with the Prairie Island ASME Code Section XI Inservice and Testing Program submitted to the Commission for review on February 1,1978 (revised through Revision 5 dated September 3,1980). As noted in that program, submittel of the attached summary is intended to satisfy the inspection reporting requirements contained in IWA-6220 of Section XI of the ASME Code.
Detailed inservice inspection reports are available at our General Office for review by the Region III Office of Inspection and Enforcement.
he s
L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh J G Keppler (2 copies of attachment) cc H Baron, Chief Boiler Inspector, State of Minnesota (1 copy of attachment)
S Tack, Hartford Insursnce (2 copies of attachment)
G Charnoff (w/o attachment)
NRC Resident Inspector (w/o attachment)