Published November 1976
| Version v1
Report
Restricted
Staff discussion of fifteen technical issues listed in attachment to November 3, 1976 memorandum from Director, NRR to NRR staff
Description
Issues discussed include: treatment of non-safety grade equipment in evaluation of a postulated steamline break accidents, lack of independence of interlocks in ECCS valves, acceptability of swing bus design of BWR-4 plants, loss of offsite power subsequent to manual safety injection reset following a LOCA, postulated reactor coolant pump rotor seizures, single failures in reactivity control, passive failures following a LOCA, probabilistic assessment of reliability, frequency decay, grid stability, interpretation of GDC 19, load break switch, instrument trip setpoints, computer protection system, and overpressurization
Availability note (English)
MF available from INIS under the Report Number.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- v p.
- Report number
- NUREG--0138
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8318472
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; REACTOR LICENSING; REACTOR SAFETY; REVIEWS; US NRC
- Descriptors DEC
- ACCIDENTS; DOCUMENT TYPES; LICENSING; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; THERMAL POWER PLANTS; US ORGANIZATIONS
Optional Information
- Notes
- Available from NTIS. $7.75.