IR 05000458/1987006

Insp Rept 50-458/87-06 on 870223-27.Violation Noted:First Aid & Rescue Personnel Had Not Received Specialized Annual Retraining in Handling Injured & Contaminated Persons.Three Deficiencies Identified

ML20205B873
Person / Time
Site:	River Bend
Issue date:	03/13/1987
From:	Terc N, Yandell L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20205B845	List: IR 05000458/1987006 ML20205B841 ML20205B851
References
50-458-87-06, 50-458-87-6, NUDOCS 8703300061
Download: ML20205B873 (4)

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APPENDIX B U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-458/87-06 License: NPF-47 Docket: 50-458 Licensee: Gulf States Utilities (GSU)

P. O. Box 220 St. Francisville, Louisiana 70775 Facility Name: River Bend Station (RBS)

Inspection At: RBS, St. Francisville, Louisiana Inspection Conducted: February 23-27, 1987 Inspector: M^^^^^

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*~#7 N. P. Terc, NRC Team Leader Date Accompanied By: J. B. Baird, RIV NRC C. Hackney, RIV NRC R. Hogan, HQ, NRC G. Bethke, Comex Corporation G. Bryan, Comex Corporation Approved- 1 O O b)

L. A. Ya6 dell, Chief, Emergency Preparedness Date and Safeguards Programs Section Inspection Summary Inspection Conducted February 23-27, 1987 (Report 50-458/87-06)

Areas Inspected: Routine, announced inspection of the licensee's emergency response capabilities during an exercise of the emergency plan and procedures, Results: Within the areas inspected, one violation was identified (failure to perform training, paragraph 4). Three deficiencies were identified (paragraphs 5, 6, and 7).

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DETAILS Persons Contacted Licensee

• J. Deddens, Senior Vice President

• W. Odell, Manager, Administration

• P. Graham, Assistant Plant Manager

• J. Cook, Lead Environmental Analyst

• D. Davenport, Plant Security Supervisor

• D. Andrews, Director, Nuclear Training

• R. King, Supervisor, Nuclear Licensing

• L. Johnson, Site Representative

• L. Broussard, Nuclear Training Representative

• D. Spencer, Senior Emergency Planner

• J. Cadwallader, Supervisor, Emergency Planner

• Stafford, Director, Quality Operations

• Suhrke, Manager, Project Management

• Reilly, Health Physicist

• Cargid, Supervisor, Radiation Programs

• Feighert, Senior Emergency Planner

• Hayes, Project Engineer

• Smith, Supervising Engineer Others

• D. Chamberlain, Senior Resident Inspector, NRC

• Denotes attendance at exit intervie The NRC inspectors also held discussions with other station and corporate personnel in the areas of health physics, operations, and emergency response organizatio . Follow-up on Previous Inspection Findings (Closed) Deficiency (458/8609-01): The NRC inspector noted that plant status announcements were made by the OSC coordinator, and status boards were maintained to provide current and complete information and team briefings on plant condition . Clear Functional Areas Inspected Inspection of the following areas revealed no violations, deviations, deficiencies, unresolved items, or open items. The inspection included interviews with cognizant individuals, observations of activities, and record reviews. The depth and scope of these activities were consistent with past findings and with the current status of the facilit _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _

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The functional areas marked with an asterisk (*) either were not inspected or they require further review and evaluation during the current inspection cycl Inspection Procedure Functional Area and Inspection Requirements 82301 Evaluation of Exercises for Power Reactors (2) Technical Support Center; (5) Corporate Command Center *; (6) Offsite Monitoring Team; (7) Corrective Action / Rescue Team; (8) Security / Accountability Team; (9) Press Center; (10) Medical Team; (11) Post Accident Sampling Training During the medical scenario part of the emergency exercise, the NRC inspector observed that the first aid team members used poor radiological practices. Specifically, they did not wear protective gloves when handling the contaminated victim, they delayed surveying the victim for radiation, and they took no precautions to control the spread of contaminatio The NRC inspector determined that two of three individuals in the first aid team had not received specialized annual retraining in handling injured and contaminated person The above constitutes an apparent violation of Appendix E, paragraph IV.F, and Section 13.3.7.1.1.2 of the licensee's Emergency Plan which states, in part, that first aid and rescue personnel will receive training, at least annually, in both Red Cross multi-media first aid and in the special handling of radioactively contaminated personnel. (458/8706-01)

No other violations or deviations were identifie . Control Room - 82301 (1)

The NRC inspector noted that no sampling for radioactive contamination was performed in the Control Room during the exercise. The NRC inspector further noted that Section 4.1.4 of licensee Procedure EIP-2-013, "Onsite Radiological Monitoring," requires radiological controls to be observed during accident conditions. None were observed in the Control Room. This constitutes a deficiency (458/8706-02).

No violations or deviations were identifie . Operations Support Center (OSC) - 82301 (4)

The NRC inspector determined that the concept of operations in the OSC was not conducive to ef ficient coordination and direction of in plant team During the exercise, the OSC Coordinator was required to attend meetings

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at the Technical Support Center. At that time, in plant teams needed further direction and coordination and were not able to obtain the proper information from the person relieving the OSC Coordinator. This caused considerable delays in the performance of certain in plant tasks and caused the potential for unnecessary radiation exposure of team member This constitutes a deficiency (458/8706-03).

No violations or deviations were identifie . Emergency Operations Facility (E0F) - 82301 (3)

The NRC inspector determined that notifications to parish representatives pertaining to the General Emergency Declaration were delayed. Total notification time was 21 minutes after declaration. The NRC inspector also noted that the licensee took 32 minutes to make the initial protective action recommendation. These times exceeded the capabilities required by 10 CFR 50, Appendix E, paragraph IV.D.3. This constitutes a deficiency (458/8706-04).

No violations or deviations were identifie . Exit Interview The NRC inspector met with the NRC senior resident inspector and licensee representatives denoted in paragraph 1 on February 27, 1987, and summarized the scope and findings of the inspection as presented in this report.