IR 05000315/1993023
| ML20058G130 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/02/1993 |
| From: | Belanger J, Creed J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20058G118 | List: |
| References | |
| 50-315-93-23, 50-316-93-23, NUDOCS 9312090104 | |
| Download: ML20058G130 (1) | |
Text
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r-t U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-315/93023(DRSS); 50-316/93023(DRSS)
Docket Nos. 50-315; 50-316 Licenses No. DPR-58; DPR-74 Licensee:
Indiana Michigan Power Company i
1 Riverside Plaza
'
Columbus, OH 43216 Facility Name:
Donald C. Cook Nuclear Power Station, Units 1 and 2 l
'
i Inspection Conducted:
November 17-19, 22-24, 1993 i
Date of Previous Physical Security Inspection: January 19-22, 1993 Inspector: Cawa, L Sch* Jet
/ 2./ND i
James L. BelangerV '
Date Senior Physical Security Inspector bb b
Approved By: t
'Aames R. Creed, Chief Date
$afeguards and IRC Section Inspection Summary i
Inspection on November 17-19. 22-24. 1993 (Reports No. 50-315/93023(DRSS): 50-316/93023(DRSS))
,
Areas Inspected:
Routine, onnounced physical security inspection involving:
Management Support; Security Program Plans and Audits; Protected and Vital Area Physical Barriers, Detection, Assessment Aids; Alarm Stations and Communications; Power Supply; and Testing, Maintenance and Compensatory Measures.
Results: The licensee was found to be in compliance with NRC requirements.
Continued management support for the program was demonstrated by low plant personnel errors in the security area, a security computer upgrade project, a weapons upgrade program, a new onsite Fitness.for Duty drug testing facility and new uniforms for the security force.
Inspection showed that the licensee identified and effectively resolved a technical weakness relating to the card reader system. Maintenance support for the security program was excellent _due in large measure to the experience and personal dedication of the maintenance staff.
Security force personnel errors were few and did not significantly impact the safety _ of'the plant.
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