ML20216B276
| ML20216B276 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/03/1998 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wadley M NORTHERN STATES POWER CO. |
| Shared Package | |
| ML20216B280 | List: |
| References | |
| 50-263-98-05, 50-263-98-5, NUDOCS 9804130410 | |
| Download: ML20216B276 (3) | |
See also: IR 05000263/1998005
Text
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April 3, 1998
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Mr. M. Wadley, Vice President
Nuclear Generation
Northern States Power Company
414 Nicollet Mall
Minneapolis, MN 55401
SUBJECT:
NRC MONTICELLO SECURITY INSPECTION REPORT 50-263/98005(DRS)
Dear Mr. Wadley:
On March 13,1998, the NRC completed an inspection at your Monticello Nuclear Generating
Station. The enclosed report presents the results of that inspection.
Areas examined during the inspection are identified in the report. Within these areas, the
inspection consisted of a selective examination of procedures and representative records,
observations, and interviews with personnel. The objective of the inspection effort was to
determine whether activities authorized by the license were conducted safely and in
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accordance with NRC requirements.
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Based on the results of this inspection, the NRC has determined that a violation of NRC
requirements occurred concerning the failure to adequately protect Safeguards Information.
The violation is cited in the enclosed Notice of Violation and the circumstances pertaining to the
violation are described in detailin the enclosed report. This is of concem because of the repeat
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nature of the violation. Although a root cause for each of the three instances was identified,
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and correctiva actions for each incident were taken, a common root cause was not identified
and previous corrective action was not completely successful.
Additionally, our earlier concern pertaining to security computer reliability has heightened since
being initially identified in our previous inspection. During this inspection we noted a decrease
in reliability, despite the actions taken to address our initial concern. Actions taken to date by
your staff have not adequately resolved the issue. Although the design of the system and your
compensatory actions reduce the safety significance of the reliability decrease, this represents
a declining performance trend.
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in contrast to the issues noted above, the self-assessment efforts and security force
performance were noted as pos:tive achievements for the security program.
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Areas examined during this inspection concern a subject matter which is exempt from
disclosure according to Part 73, Title 10, Code of Federal Regulations, Section 73.21(c)(2).
This information must be handled and protected in accordance with the provisions of 10 CFR 73.21. Consequently, our report of this inspection will not be placed in the NRC Public
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Document Room.
Sincerely,
original /s/ M. Leach for
John A. Grobe, Director
Division of Reactor Safety
Docket No. 50-263
License No. DPR-22
Enclosures:
2. Inspection Report No. 50-263/98005(DRS)
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(SAFEGUARDS INFORMATION)
cc w/encis:
Plant Manager, Monticello
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DOCUMENT NAME: A: MON 98005.DRS
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in contrast to the issues noted above, the self-assessment efforts and security force
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performance were noted as positive achievements for the security program.
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Areas examined during this inspection concern a subject matter which is exempt from
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disclosure according to Part 73, Title 10, Code of Federal Regulations, Section 73.21(c)(2).
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This information must be handMd and protected in accordance with the provisions of 10 CFR 73.21. Consequently , our re. aort of this inspection will not be placed in the NRC Public
Document Room.
Sincerely,
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John A. Grobe, Director
Division of Reactor Safety
Docket No. 50-263
License No. DPR-22
Enclosures:
2. Inspection Report No. 50-263/98005(DRS)
(SAFEGUARDS INFORMATION)
cc w/encls:
Plant Manager, Monticello
NRR/DRIS/RSGB9D
NMSS/HIDGON/4E4
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SAFEGUARDS INFORMATION:
State Liaison Officer, State
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