IR 05000263/1986007
| ML20207N024 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/07/1987 |
| From: | Guldemond W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Larson C NORTHERN STATES POWER CO. |
| References | |
| NUDOCS 8701130397 | |
| Download: ML20207N024 (2) | |
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JAN 7 igy Docket No. 50-263 Northern States Power Company ATTN: Mr. C. E. Larson Vice President, Nuclear Generation 414 Nicollet Mall Minneapolis, MN 55401 Gentlemen:
This is in reference to the routine safety inspection conducted by Mr. P. L. Hartmann of this office on August 19 through November 3, 1986, of activities at the Monticello Nuclear Generating Station authorized by NRC Operating License No. DPR-22 documented in IE Report No.
50-263/86007(DRP).
Due to a typing error, the commitment date for full implementation of SPDS on line 3 of page 8 was incorrectly listed as February 11, 1987. The correct date is January 11, 1987. A corrected page is enclosed. Please replace the incorrect page in the report.
If you have any questions concerning this matter, please contact P. L. Hartmann of my staff.
Sincerely, 8701130397 870107 ORIGINAL SIGNED BY I'. G. CPEENupN DR ADOCK 05000263 PDR
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W. G. Guldemond, Chief Reactor Projects Branch 2 Enclosure: Corrected page 8 cc w/ enclosure:
W. A. Shamla, Plant Manager DCS/RSB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII Monticello Resident Inspector, RIII Prairie Island John W. Ferman, Ph.D.,
Nuclear Engineer, MPCA RIII RIII RI L
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n (0 pen)I.D.2.3: SPDS Full Implementation. The licensee commitment V)
is to have SPDS fully implemented six months after startup of Cycle (
12. That deadline is January 11, 1987. Closecut of this item will also be by the ERF appraisal.
(0 pen) II.B.2.3:
Equipment Qualification. The licensee considers this item completed and the Region III inspection to close this item is scheduled.
(0 pen) II.F.2.3.B:
Instrumentation for Detection of Inadequate Core Cooling. The licensee completed the modifications during the Cycle 12 refueling outage. Technical specification amendments have been submitted to reflect the modification. All requirements for the modification have been completed except for drawing changes. When all drawing changes are complete, this item will be closed.
(0 pen) II.K.3.18.C: ADS Actuation Logic Modification. The modification was completed during the Cycle 12 refueling outage. Technical specifications have been submitted to reflect the modification. All requirements for the modification have been completed except for drawing changes. When all drawing changes are complete, this item will be closed.
(0 pen) II.K.3.28: Qualifications of Accumulators on ADS Valves. The
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licensee completed some of the modifications required for this item during the Cycle 12 outage. The remainder of the changes will be made during the Cycle 13 refueling outage.
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I.E. Bulletins n
(Closed) I.E. Bulletin 80-07: BWR Jet Pump Assembly Failure. This bulletin was addressed by NUREG CR3052 titled Closeout of I.E. Bulletin and required the licensee to include ultrasonic examination of the new hold down beams at 10-year intervals. The licensee has committed to adding the requirement to the Monticello Augmented Inservice Inspection program.
(Closed) I.E. Compliance Bulletin 86-01. The inspector reviewed the licensee response to the bulletin and determined it to be accurate and provided in a timely manner. Monticello has independent RHR minflow valves and minflow valve control circuitry. This review completed Temporary Instruction 2515/82.
(Closed) I.E. Compliance Bulletin 86-02. The inspector reviewed the response and determined it to be accurate and provided in a timely manner. Monticello has no static 0-ring differential pressure switches Model No. 102 or 103 installed in any system or planned for installation in any system. This review completed Temporary Instruction 2515/81.
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