Document: NRC Regulatory Guide
Document ID: 74c49394-8dbf-46e7-b62a-b85de93b47d8
Document Type: regulatory_guide
Title: Initial Test Programs for Water-Cooled Nuclear Power Plants + HISTORY - HISTORY 11/2012 – DG-1259 , Proposed Revision 4 11/2006 – DG-1166 , Proposed Revision 3 (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1229/ML12298A071.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.68
CFR Part: 
CFR Title: 

Content:
ding and at the completion of loading, and shutdown margin verifications should not involve a planned approach to criticality using nonstandard rod patterns or with operational interlocks bypassed) 9. determination of the boron concentration in borated reactors and the frequency of determination (the frequency of determination should be commensurate with the worst possible dilution capability, as determined by consideration of piping systems that attach to the reactor coolant system) 10. actions (especially those pertaining to flux monitoring) for periods when fuel loading is interrupted 11. maintenance of continuous voice communication between the control room and loading station Appendix C to DG-1259, Page C-7 12. the minimum crew required to load fuel (the procedure should require the presence of at least two persons at any location where fuel handling is taking place, and a senior reactor operator with no other concurrent duties should be in charge) 13. crew work time (if personnel are scheduled for consecutive daily duty, they should not normally be expected to work more than 12 hours out of each 24) 14. approvals required for changing the procedure c. Limitations and Actions 1. Establish criteria for stopping fuel loading. Some circumstances that might warrant this are unexpected subcritical multiplication behavior, loss of communications between the control room and fuel loading station, an inoperable source range detector, and inoperability of the emergency boration system. 2. Establish criteria for emergency boron injection. 3. Establish criteria for containment evacuation. 4. Outline actions to be followed in the event of fuel damage. 5. List actions to be followed or approvals to be obtained before routine loading may resume after one of the above limitations has been reached or invoked. C-3. Initial Criticality Procedures This section provides some specific guidance for the detailed procedure for operations associated with bringing the reactor critical