ML20195D226

Ro:On 860428,core Spray Sys a Failed Required Quarterly Inservice Test.Caused by Inaccurate Temporary Flow Indicator Scale Resulting in Undersize Orifices in Injection Test Line.Indicator Replaced & Orifices Sized & Retested

ML20195D226
Person / Time
Site:	Hope Creek
Issue date:	06/02/1986
From:	Salvesen R Public Service Enterprise Group
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
NUDOCS 8606020211
Download: ML20195D226 (2)

Text

.

O PSIEG Public Service Electric and Gas Company P. O. Box A Hancocks Bridge, New Jerscy 08038 Hope Creek Generating Station U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 28555 Dear Sir HOPE CREEK GENERATING STATION DOCKET NO.50-354 UNIT NO. 1 CLARIFICATION OF FOUR-HOUR NON EMERGENCY EVENT REPORT OF APRIL 28, 1986 On April 28, 1986, the Hope Creek Generating Station Senior Nuclear Shift Supervisor (SNSS) made a four-hour non emergency report regarding the failure of the A Core Spray System to pass the required quarterly inservice test. The SNSS reported that an undersized orifice may be installed in the injection line thus preventing the core spray pumps from developing the required flow at the required pressure. The orifice sizing problem was tracked to the inaccuracy of a temporary flow indicator scale that was used during preopera-tional testing. The indicator has since been replaced.

1BCFR59.72 (b) (1) requires a four-hour report for "any event found while the reactor is shutdown that, had it been found while the reactor was in operation, would have resulted in the nuclear power plant, including its principal safety barriers, being seriously degraded...". The SNSS considered the event reportable pursuant to this requirement.

To correct the problem, resized orifices were installed in both the test line and injection line for the A core Spray System and the orifices were tested on May 16, 1986. The new orifices were found to be sized correctly.

8606020211 860602 PDR ADOCK 05000354 S PDR M

tuu

'j"

[jpf f

% 21 l':) p W, ? O 84 s.

a After review by station management, the event does not appear to meet the intent of 18CFR.59.72(b) (i) since only one core spray loop was affected and the other loop was not subject to the same problem. Thus, even if the condition had been discovered at power, the plant would not have been in a seriously degraded condition. For this reason, the four-hour notification is considered a conservative measure taken by the Senior Nuclear Shift Supervisor but not one required by 18CFR59.72. Similarly the event is not reportable under 18CFR59.73 since, again, the condition affected only one loop of a redundant safety system. Thus, a Licensee Event Report will not be submitted for this event.

Sincerely, R. S. Salvesend)

General Manager Hope Creek Operations WJM:bar SORC Mtg.86-121 C Distribution L