Document: NUREG-0800
Document ID: 71224475-ca63-4c09-acc1-c682d58112dd
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550082.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
ceptable Deviations and Clarifications to Revisions 2 and 3 of Regulatory Guide 1.97 Variable Deviation Acceptance Guidelines/Clarification Standby liquid control system (SLCS) flow Direct measurement Measurement of SLCS pump discharge pressure and SLCS storage tank level may be acceptable as an alternate indication that the SLCS pump is operating and that SLCS flow is occurring. Reactor building or secondary containment area radiation Category Area radiation monitors located in Mark III containments and in primary containments of other BWRs may be Category 2 as an alternative to Category 1 monitors. Area radiation monitors located in reactor building secondary containments for Mark I and Mark II plants and in other plant areas may be Category 3 in lieu of Category 2. Radiation exposure rate/variables used to monitor airborne radioactive materials released from plant Category If the instrument is located in a mild environment and is not part of a safety system, Category 3 instrumentation is acceptable in place of Category 2 instrumentation. BTP 7-10-10 Revision 5 - March 2007 Table 2. For PWRs: Acceptable Deviations and Clarifications to Revisions 2 and 3 of Regulatory Guide 1.97 Variable Deviation Acceptance Guidelines/Clarification Neutron flux Environmental qualification A non-environmentally qualified instrument is acceptable if qualified core exit thermocouples and reactor containment system (RCS) hot and cold leg temperature indications are provided in conjunction with directions in emergency procedures for operator action to assure that boric acid injection is occurring. RCS pressure (Combustion Engineering [CE] reactors) Range A range of 0-3,000 psig is an adequate alternative to 0-4,000 psig if analysis is presented or referenced in the final safety analysis report (FSAR) that shows that pressure will remain on scale for all design basis transients and accidents. However, if an anticipated transient without scram (ATWS) analysis indicates that pressures