10 CFR 76.89, Criticality Accident Requirements

Criticality accident requirements

a

(a) The Corporation must maintain and operate a criticality monitoring and audible alarm system meeting the requirements of paragraph (b) of this section in all areas of the facility. The Corporation may describe for the approval of the Commission defined areas to be excluded from the monitoring requirement. This submittal must describe the measures that will be used to ensure against criticality, including kinds and quantities of material that will be permitted and measures that will be used to control those kinds and quantities of material.

b

(b) The system must detect and annunciate a criticality that produces an absorbed dose in soft tissue of 20 rads of combined neutron and gamma radiation at an unshielded distance of 2 meters from the reacting material within 1 minute. Coverage of all monitored areas must be provided by two detectors.

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NRC website 10 CFR 76.89

v t e Code of Federal Regulations
Title 10 Part 76 - CERTIFICATION OF GASEOUS DIFFUSION PLANTS
10 CFR: 1 2 4 5 7 9 10 11 12 13 14 15 16 19 20 21 25 26 30 31 32 33 34 35 36 37 39 40 50 51 52 54 55 60 61 62 63 70 71 72 73 74 75 76 81 95 100 140 150 160 170 171
1, General Provisions, Purpose 2, Scope 4, Definitions 5, Communications 6, Interpretations 7, Employee protection 8, Information collection requirements: OMB approval not required 9, Completeness and accuracy of information 10, Deliberate misconduct 21, Certificate required 23, Specific exemptions 31, Application, Periodic application requirement 33, Application procedures 35, Contents of application 36, Renewals 37, Federal Register notice 39, Public meeting 41, Record underlying decisions 43, Date for decision 45, Application for amendment of certificate 51, Certification, Conditions of certification 53, Consultation with Environmental Protection Agency 55, Timely renewal 60, Regulatory requirements which apply 62, Issuance of certificate and/or approval of compliance plan 64, Denial of certificate or compliance plan 65, Inalienability of certificates 66, Expiration and termination of certificates 68, Plant changes 70, Post issuance 72, Miscellaneous procedural matters 74, Computation and extension of time 76, Backfitting 81, Safety, Authorized use of radioactive material 83, Transfer of radioactive material 85, Assessment of accidents 87, Technical safety requirements 89, Criticality accident requirements 91, Emergency planning 93, Quality assurance 95, 76.95 Training 111, Safeguards and Security, Physical security, material control and accounting, and protection of certain information 113, Formula quantities of strategic special nuclear material--Category I 115, Special nuclear material of moderate strategic significance--Category II 117, Special nuclear material of low strategic significance--Category III 119, Security facility approval and safeguarding of National Security Information and Restricted Data 120, Reports and Inspections, Reporting requirements 121, Inspections 123, Tests 131, Enforcement, Violations 133, Criminal penalties Appendices:

10 CFR 76.89, Criticality Accident Requirements

a

b

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