Issue Date: 3/06/02
NRC Inspection Manual IRSB
PROGRAM APPLICABILITY: | 2515 |
01.01 | The objective of this procedure is to gather information to determine whether a licensee is meeting the objective of this cornerstone which is to ensure adequate protection of worker health and safety from exposure to radiation from radioactive material during routine nuclear reactor operation. |
02.01 | Baseline inspection requirements are identified in each of the attached inspectable areas: |
Access Control to Radiologically Significant Areas (Attachment 01) | |
02.02 | These requirements represent the minimum inspection activity to be conducted at each reactor site at the frequencies shown in each inspectable area. Whenever practicable, inspections under this procedure's Attachment 01 should be performed during maintenance or refueling outages. During outages a facility's radiation protection program faces the highest sustained challenges with frequent, prolonged work in high radiation areas. In addition to inspecting during the outage, a significant portion of Attachment 02 may be performed both before and after an outage, to focus on licensee outage preparation and post-outage results and lessons learned. |
02.03 | The effectiveness of each licensee to identify and resolve problems in this cornerstone area will also be inspected biennially using the baseline inspection program procedure for evaluating licensee Problem Identification and Resolution programs. However, for certain potentially high risk, high dose rate areas, Attachment 01 requires an annual verification of continued licensee controls and awareness of these challenging areas. |
03.01 | The Performance Indicator in this cornerstone either directly measures the occurrence of unanticipated and unintended dose exceeding an established percentage of regulatory limits or identifies non-compliances with the access requirements established to prevent unauthorized entry into those areas having dose rates exceeding 1000 mrem/hour. This Performance Indicator may also identify declining performance in procedural guidance, training, radiological monitoring, and in exposure and contamination control prior to exceeding a regulatory dose limit. |
03.02 | No inspection guidance provided. |
03.03 | Early identification of potentially weak licensee program areas can allow for improved on-site inspection sample selection. Therefore, whenever practical, review of the licensee's identification and resolution program activities should be done either prior to, or at the beginning of the onsite inspection. |
Estimates of inspection resources are identified within each inspectable area. However, the total resources for this cornerstone typically should be between 137 hours and 167 hours.
END
1. 71121.01 Access Control to Radiologically Significant Areas
2. 71121.02 ALARA Planning and Controls
3. 71121.03 Radiation monitoring Instrumentation and Protective Equipment