Published June 1987 | Version v1
Report Restricted

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

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The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
105 p.
Report number
NUREG--1269

Optional Information

Notes
Portions of this document are illegible in microfiche products.