NRRPT Regulatory Compliance & Documentation 5 — Questions and Answers
Question 1: Under 10 CFR 20.1502, individual monitoring with dosimetry is required for workers likely to receive what fraction of the annual occupational dose limits?
- 1/10 (10%) (Correct answer)
- 1/4 (25%)
- 1/2 (50%)
- 3/4 (75%)
Correct answer: 1/10 (10%)
10 CFR 20.1502 requires individual monitoring for workers likely to receive 10% or more (1/10) of the applicable occupational dose limits.
Question 2: A nuclear power plant's Technical Specifications (Tech Specs) are legally binding because they are:
- Incorporated into the operating license as Appendix A (Correct answer)
- Issued separately by the NRC as standalone federal regulations
- Approved by the state radiation control program
- Required by the plant's insurance policy
Correct answer: Incorporated into the operating license as Appendix A
Technical Specifications are incorporated as Appendix A of the facility's NRC operating license, making them legally enforceable license conditions.
Question 3: Under 10 CFR 20.2203, a licensee must submit a written report to the NRC when a monitored individual's occupational effective dose exceeds what annual threshold?
- 1 rem
- 2 rem
- 5 rem (Correct answer)
- 25 rem
Correct answer: 5 rem
10 CFR 20.2203 requires a written report when an individual's annual occupational effective dose exceeds 5 rem (50 mSv), which is the annual limit.
Question 4: A 'confirmatory action letter' (CAL) issued by the NRC to a licensee is best characterized as:
- A formal Notice of Violation with civil penalty
- A document confirming commitments the licensee has volunteered to take (Correct answer)
- An order to immediately shut down operations
- An authorization to restart previously suspended activities
Correct answer: A document confirming commitments the licensee has volunteered to take
A CAL documents voluntary commitments made by a licensee to the NRC and confirms that those actions must be completed as agreed upon.
Question 5: Under the NRC's Inspection Procedure (IP) 71124.01, the inspector evaluates the licensee's:
- Emergency planning and evacuation routes
- Radiological hazard assessment and exposure controls (Correct answer)
- Spent fuel pool criticality analysis
- Environmental monitoring network
Correct answer: Radiological hazard assessment and exposure controls
IP 71124.01 focuses on radiological hazard assessment and exposure control programs including hazard identification, posting, and worker protection measures.
Question 6: The purpose of a 10 CFR 50.72 8-hour non-emergency notification to the NRC Operations Center is to report:
- Any unplanned change to the radiation protection program
- Events that could affect safety but do not require immediate notification (Correct answer)
- Monthly dose summary data
- Results of all ALARA reviews
Correct answer: Events that could affect safety but do not require immediate notification
10 CFR 50.72 requires 8-hour non-emergency notifications for events that have safety significance but do not rise to the level requiring immediate 1-hour or 4-hour reporting.
Question 7: A Licensee Event Report (LER) required under 10 CFR 50.73 must be submitted to the NRC within how many days of discovering a reportable event?
- 7 days
- 15 days
- 30 days (Correct answer)
- 60 days
Correct answer: 30 days
10 CFR 50.73 requires licensees to submit a written Licensee Event Report within 60 days of discovering a reportable condition or event.
Under 10 CFR 20.1502, individual monitoring with dosimetry is required for workers likely to receive what fraction of the annual occupational dose limits?