Document: NRC Regulatory Guide
Document ID: 7bdfde6b-2c09-49db-8a3f-863eab24747e
Document Type: regulatory_guide
Title: Control of Combustible Gas Concentrations in Containment + HISTORY - HISTORY 08/2002 – DG-1117 , Proposed Revision 3 Prior to the issuance of DG-1117, RG 1.7 was entitled "Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident," to reflect its narrower original scope
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0222/ML022210067.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.7
CFR Part: 
CFR Title: 

Content:
ory guides, both active and draft, and draft NUREG documents may be obtained free of charge by writing the Reproduction and Distribution Services Section, OCIO, USNRC, Washington, DC 20555-0001, or by fax to (301)415-2289, or by email to <DISTRIBUTION@NRC.GOV>. Active guides may also be purchased from the National Technical Information Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161; telephone (703)487-4650; online <http://www.ntis.gov/ordernow>. Copies of active and draft guides are available for inspection or copying for a fee from the NRC Public Document Room at 11555 Rockville Pike, Rockville, MD; the PDR’s mailing address is USNRC PDR, Washington, DC 20555; telephone (301)415-4737 or (800)397-4209; fax (301)415-3548; email <PDR@NRC.GOV>. 8 REFERENCES 1. SECY-00-0198, “Status Report on Study of Risk-Informed Changes to The technical Requirements of 10 CFR Part 50 (Option 3) and Recommendations on Risk-Informed Changes to 10 CFR 50.44 (Combustible Gas Control),” September 14, 2000.2 2. USNRC, “Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants,” NUREG-1150, December 1990.3 3. SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-water Reactor (ALWR) Designs,” USNRC, April 2, 1993.1 4. USNRC, “Station Blackout,” Regulatory Guide 1.155, August 1988.3 5. USNRC, “Final Safety Evaluation Report Related to the Certification of the Advance Boiling Reactor Design,” NUREG-1462, August 1994.2 6. USNRC, “Final Safety Evaluation Report Related to the Certification of the System 80+ Design, Docket No. 52-002,” NUREG-1503, July 1994.2 7. USNRC, “Final Safety Evaluation Report Related to the Certification of the AP600 Standard Design, Docket No. 52-003,” NUREG-1512, September 1998.2 8. USNRC, “Instrumentation for Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environs Conditions