Loss of residual heat removal system: Diablo Canyon, Unit 2, April 10, 1987
Description
This report presents the findings of an NRC Augmented Inspection Team (AIT) investigation into the circumstances associated with the loss of residual heat removal (RHR) system capability for a period of approximately one and one-half hours at the Diablo Canyon, Unit 2 reactor facility on April 10, 1987. This event occurred while the Diablo Canyon, Unit 2, a pressurized water reactor, was shutdown with the reactor coolant system (RCS) water level drained to approximately mid-level of the hot leg piping. The reactor containment building equipment hatch was removed at the time of the event, and plant personnel were in the process of removing the primary side manways to gain access into the steam generator channel head areas. Thus, two fission product barriers were breached throughout the event. The RCS temperature increased from approximately 870F to bulk boiling conditions without RCS temperature indication available to the plant operators. The RCS was subsequently pressurized to approximately 7 to 10 psig. The NRC AIT members concluded that the Diablo Canyon, Unit 2 plant was, at the time of the event, in a condition not previously analyzed by the NRC staff. The AIT findings from this event appear significant and generic to other pressurized water reactor facilities licensed by the NRC
Availability note (English)
NTIS, PC A06/MF A01 - US Govt. Printing Office. as TI87900823.
Files
Additional details
Publishing Information
- Imprint Pagination
- 105 p.
- Report number
- NUREG--1269
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19005771
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AFTER-HEAT REMOVAL; DIABLO CANYON-2 REACTOR; FAILURES; INSPECTION; REACTOR ACCIDENTS; REACTOR MAINTENANCE; STEAM GENERATORS; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- ACCIDENTS; BOILERS; ENRICHED URANIUM REACTORS; MAINTENANCE; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SYSTEMS ANALYSIS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.