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Loss of Residual Heat Removal System, Diablo Canyon, Unit 2, April 10, 1987 (Augmented inspection Team Report April 15-21, 29 and 1 May 87).

NUREG1269

Publication Date	1987
Personal Author	Crews, J. L.; Trammell, C. M.; Lyon, W. C.; Narbut, P. P.; Prendergast, K.
Page Count	122
Abstract	The 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. The 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 87 deg F to bulk boiling conditions without RCS temperature indication available to the plant operators. The RCS was subsequently pressurized to approximately 7-10 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.
Keywords	After-heat removal PWR type reactors Reactor shutdown Inspection Reactor cooling systems Fission product release Nuclear reactor accidents Diablo Canyon -2 reactor
Source Agency	Nuclear Regulatory Commission
NTIS Subject Category	77H - Reactor Engineering & Nuclear Power Plants 97Q - Selected Studies In Nuclear Technology
Corporate Authors	Nuclear Regulatory Commission, Walnut Creek, CA. Region V.
Supplemental Notes	Also available from Supt. of Docs.
Document Type	Technical Report
NTIS Issue Number	198723

Loss of Residual Heat Removal System, Diablo Canyon, Unit 2, April 10, 1987 (Augmented inspection Team Report April 15-21, 29 and 1 May 87).

Loss of Residual Heat Removal System, Diablo Canyon, Unit 2, April 10, 1987 (Augmented inspection Team Report April 15-21, 29 and 1 May 87).
NUREG1269

Publication Date	1987
Personal Author	Crews, J. L.; Trammell, C. M.; Lyon, W. C.; Narbut, P. P.; Prendergast, K.
Page Count	122
Abstract	The 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. The 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 87 deg F to bulk boiling conditions without RCS temperature indication available to the plant operators. The RCS was subsequently pressurized to approximately 7-10 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.
Keywords	After-heat removal PWR type reactors Reactor shutdown Inspection Reactor cooling systems Fission product release Nuclear reactor accidents Diablo Canyon -2 reactor
Source Agency	Nuclear Regulatory Commission
NTIS Subject Category	77H - Reactor Engineering & Nuclear Power Plants 97Q - Selected Studies In Nuclear Technology
Corporate Authors	Nuclear Regulatory Commission, Walnut Creek, CA. Region V.
Supplemental Notes	Also available from Supt. of Docs.
Document Type	Technical Report
NTIS Issue Number	198723