Document: NRC Regulatory Guide
Document ID: 39669ad0-0ad7-442d-8e1c-64c0e1607f1d
Document Type: regulatory_guide
Title: Reporting of Operating Information -- Appendix A Technical Specifications (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003739954.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.16
CFR Part: 
CFR Title: 

Content:
e technical specifications, the limiting condition for operation is not considered to have been violated and need not be reported under this item, but it may be reportable under item 2.b(2) below. (3) Abnormal degradation discovered in fuel cladding, reactor coolant pressure boundary, or primary containment. The following are examples: (a) Through-wall failure of piping or com ponents of the reactor coolant pressure boundary. (b) Steam generator tube thinning in excess of acceptance limits in Regulatory Guide 1.83, "Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes." (c) Welding or material defects greater than those allowable by applicable codes. Note: Leakage of valve packing or gaskets within the limits for identified leakage set forth in technical specifi cations need not be reported under this item. 8Examples are intended to be illustrative only. (4) Reactivity anomalies involving disagreement with the predicted value of reactivity balance under steady-state conditions during power operation greater than or equal to 1% Ak/k; a calculated reactivity balance indicating a shutdown margin less conservative than specified in the technical specifications; short-term react ivity increases that correspond to a reactor period of less than 5 seconds or, if subcritical, an unplanned reactivity insertion of more than 0.5% Ak/k; or occurrence of any unplanned criticality. S(5) Failure or malfunction of one or more com ponents which prevents or could prevent, by itself, the fulfillment of the functional requirements of system(s) used to cope with accidents analyzed in the SAR. The following are examples: (a) Clogged fuel line(s) resulting in failure to supply fuel to the emergency generators. (b) Multiple instrument drift resulting in loss of protective function. (c) HPCI failure to start or failure to con tinue running once initiated. (6) Personnel error or procedural inadequacy which prevents or could prevent, by itself, the fulfill ment of the