ML20236V612
| ML20236V612 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 07/30/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wadley M NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20236V614 | List: |
| References | |
| 50-263-98-09, 50-263-98-9, NUDOCS 9808040083 | |
| Download: ML20236V612 (2) | |
See also: IR 05000263/1998009
Text
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' July 30, 1998
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Mr. M. Wadley, President
. Nuclear Generation
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Northern States Power Company
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414 Nicollet Mall
Minneapolis, MN 55401
SUBJECT:
NRC.lNSPECTION REPORT 50-263/98009(DRS)
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Dear Mr. Wadley;
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On June 12,1998, the NRC completed an inspection of your Monticello Nuclear Generating .
Plant and conducted a final exit by telephone with the Plant Manager and others of your staff.
The inspection was conducted from May 11 to June 12,1998. At the conclusion of the onsite
inspection on June 9,1998, the inspection results were discussed with members of your staff.
In order to clarify or resolve NRC questions in some areas, a number of additional documents
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were provided and, per request of members of your staff, these documents were reviewed later
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in the NRC regional offices. The results of the additional reviews were provided in the June 12,
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1998, telephone exit.
' The inspection was an engineering and technical support inspection combined with a corrective
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. action inspection. Areas examined during the inspection are identified in the report. The
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inspection included an assessment and evaluation of engineering support, design change and
modification activities including 10 CFR 50.59 safety evaluations and screenings, as well as
correction action and intemal assessment activities. Within these areas, we selectively
observed activities in progress, examined procedures and representative records, observed
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plant conditions, and discussed activities and concems with your staff.
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Overall, inspection results indicated that engineering and problem identification and resolution
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activities at the Monticello Station were effective. In most cases, design changes and
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. modifications were well controlled and implemented. Overall, safety evaluations and
screenings were thorough, with one exception noted. Problem identification and corrective
action were considered very good, however, the trending program was weak and timeliness of
some corrective actions were poor.
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No violations were identified during the course of this inspection. An unresolved item related to
the procedure controlling temporary modifications was identified. The procedure allowed
bypass of 10 CFR 50.59 requirements for an " urgent or emergency condition" without defining
or qualifying these terms within the context of the provisions of 10 CFR 50.54(x). This item is
documented in Section E1.2 of the report. Please respond to this item describing the actions
you have taken or will take to resolve the issue within 30 days of receipt of this letter,
in accordance with 10 CFR 2.790 of the NRC's " Rules and Practices," a copy of this letter, the
enclosure and your response will be placed in the NRC Public Document Room (PDR).
9808040083'980730
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ADOCK 05000263
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M. Wadley
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We will gladly discuss any questions you have concerning this inspection.
Sincerely,
s/ John A. Grobe
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John A. Grobe, Director
Division of Reactor Safety
Docket No.: 50-263
License No.: DPR-22
Enclosure:
Inspection Report 50-263/98009(DRS)
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cc w/ enc!:
Plant Manager, Monticello
State Liaison Officer, State
of Minnesota
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Distribution:
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CAC (E-Mail)
Project Mgr., NRR w/enci
C. Paperiello, Rlll w/ encl
J. Caldwell, Rllt w/enci
B. Clayton, Rlli w/enci
SRI Monticello w/enci
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DRP w/enci
TSS w/ encl
DRS (2) w/ encl
Rill PRR w/ encl
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PUBLIC IE-01 w/ encl
Docket File w/enci
GREENS
LEO (E-Mail)
DOCDESK (E-Mail)
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DOCUMENT NAME: G:DRS\\ MON 98009.DRS
T. receive a copy of this eacunwnt. Indicate in the box: c = c@y Mthout arm.J. .J.'..J.,i ure T e Cgy wth attachmenuencloswa T e No copy
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DATE
07/69/98
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07/ 9 98
DFFICIAL RECORD COPY
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