ML20202C746
| ML20202C746 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 02/04/1998 |
| From: | Grant G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wadley M NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20202C752 | List: |
| References | |
| 50-263-97-18, NUDOCS 9802130018 | |
| Download: ML20202C746 (2) | |
See also: IR 05000263/1997018
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NUCLEAR RE ULATORY COMMISSION
UNITO STATES
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801 WARRENVILLE nOAD
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LISLE. ILLINOIS 60532-4351
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february 4,1998
Mr. M. Wadley, Vice President
Nuclear Generation
Northom States Power Company
414 Nicollet Mall
Minneapolis, MN 55401
SUBJECT:
MONTICELLO NRC INSPECTION REPORT NO. 50 263/97018(DRP)
Dear Mr. Wadley;
On January 12,1998, the NRC completed an inspection at the Monticello reactor facility. The
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enclosed report presents the results of that inspection.
During the seven week period covered by this inspection, the conduct of activities at the
Monticello facility was acceptable. For example, operations personnel responded appropriately
to a loss of both recombiner trains and a resultant manual reactor scram. The subsequent
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reactor startup and two planned power changes were completed in a controlled rnanner.
Engineering personnelidentified that a Technical Specification required test was not performed
en an automatic depressurization system initiation inhibit switch. Radiation protection personnel
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demonstrated a strong commitment in reducing personnel exposure during a maintenance
activity in a high dose area. However, inadequate planning on two occasions for performance of
a surveillance test and maintenance activity resulted in generation of a reactor scram signal for
f
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13 control rods and a reactor water level transient. Planning, maintenance, and operations
personnel did not consider the compatibility of performing activities simultaneously.
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During this period, the inspectors identified two discrepancies between the as built plant
condition, Technical Specifications, and the Updated Safety Analysis Report. Although these
findings were not safety significent, they indicate technicat inconsistencies between design
documents. We understand that your staff is involved in an effort to validate the Updated Safety
Analysis Report and we encourage you to continue to su2 port this effort.
"
9002130010 990204
ADOCK 05000263
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M. Wadley
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In occordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its
enclosure will be placed in the NRC Public Document Room.
Sincerely,
/s/ Marc L. Dapas for
Geoffrey E. Grant, Director
Division of Reactor Projects
Dock 6, No.: 50-263
License No.: DPR 22
Enclosure:
Inspection Report
No. 50 263/97018(DRP)
cc w/ encl:
Plant Manager, Monticello
State Liaison Officer, State
of Minnesota
Distribution:
Docket File w/ encl
Rlli PRR w/ encl
PUBLIC IE 01 w/ encl
Project Manager, NRR w/enct
SRI Monticello w/ encl
Rlli Enf. Coordinator w/enct
A. B. Beach w/ encl
CAA1 w/enet (E rnell)
Deputy RA w/enci
DRS (2) w/ encl
TSS w/enci
DOCDESK (E mail)
,
DRP w/ encl
DOCUMENT NAME: G:\\MONT\\ MON 97018.DRP
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DATE
02/;L/98
02/%/98
02/3 /98
OFFICIAL RECORD COPY