Document: NUREG-0800
Document ID: 866c6ef6-2f4a-45c7-9e71-43e1f66a8422
Document Type: srp
Title: Draft Revision 3– July 2018
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1807/ML18071A066.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5
CFR Part: 
CFR Title: 

Content:
margin in temperature over the pressure-temperature limits as determined for heatup and cooldown in 2.2.2 above. The minimum temperature, regardless of pressure, is the temperature calculated for the inservice hydrostatic test according to 2.2.1 above. 2.2.4 Upset Conditions The pressure-temperature limits described in 2.2.2 and 2.2.3 above are applicable to upset conditions. Normal operating procedures should permit variations from intended operation, including all upset conditions, without exceeding the limit curves. 2.2.5 Emergency and Faulted Conditions It is recognized that the severity of a transient resulting from an emergency or faulted condition is not directly related to operating conditions, and resulting temperature-stress relationships in the reactor coolant boundary components are primarily system dependent, and therefore not under direct control of the operator. BTP 5-3-6 Draft Revision 3 – July 2018 For these reasons, operating limits for emergency and faulted conditions are not a requirement of the TS. The safety analysis report (SAR) should present descriptions of the continued integrity of all vital components of the Reactor Coolant Pressure Boundary (RCPB) during postulated faulted conditions. These descriptions should be made in as realistic a manner as possible, avoiding grossly over conservative assumptions and procedures. 2.3 Reporting Requirements The TS should include the operating and test limits discussed above, and the basis for their determination. The TS should also include information on the intended operating procedures, and justify that adequate margins between the expected conditions and the limit conditions will be provided to protect against unexpected or upset conditions. Sites with an approved PTLR must remain consistent with the requirements delineated on this topic concerning both the TS and PTLR. 3. Inservice Surveillance of Fracture Toughness The reactor vessel may be exposed to significant neutron radiation during the