ML19344D226

From kanterella
Jump to navigation Jump to search
Interim Deficiency Rept Re Solid State Protective Relays & Trip Devices Not Meeting Characteristic Specs.Caused by Copper Migration within Scrs.Scrs Returned to Manufacturer to Determine If Deficiency Confined to Batch
ML19344D226
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 02/29/1980
From:
DUKE POWER CO.
To:
Shared Package
ML19344D224 List:
References
SD-80-02, SD-80-2, NUDOCS 8003110564
Download: ML19344D226 (2)


Text

'

~*

. ,3 . ^

O CATAWBA NUCLEAR STATION Report No.: SD 413-414/80-02 Report Date: February 29, 1980 Facility: Catawba Nuclear Station - Units 1&2 Identification of Deficiency: Solid State Protective Relays and Trip Devices -Deficiency SCR's Init'.al Report:

On January 31, 1980, Mr. Milt Hunt of NRC Region II, Atlanta, Georgia, was notified of this deficiency by Mr. J. R. Wells, B. M. Rice, W. J.

Foley and D. M. Clark of Duke Power Company.

Supplier and/or Component:

The items found to contain the deficiency were solid state relays manu-factured by Gould-Brown Boveri. Horsham, Pennsylvania and consist of Types 1TE-51L and 1TE-51Y overcurrent relays and Type SS46 (Power Shield) solid state trip device. The component that has been identified as causing the deficiency was Motorola, Inc. SCR's types 1379 and 1235.

Additional Gould-Brown Boveri relay types GR-5, Ground Fault Relay, and

- Type ITB-50, overcurrent relay also contain similar type SCR's.

Description of Deficienev:

During relay and trip device acceptance and system startup testing, it was determined that three relays and trip devices did not meet the Time-Current characteristic specifications of the relay for its application (i.e., the relay or device would trip at a lower level of current or time than its setting). Preliminary investigations indicated that the output SCR in the relays was deficient. Ode relay was returned to the manufacturer for investigation. The relay manufacturer and SCR manu-facturer have evaluated and analyzed the deficiency and advise that the deficiency has been caused by " copper migration" within the SCR. The copper migration was from the top metal system into the bulk silicon material which would result in its failure. The migration is a direct function of temperature and time. The deficiency is further described

' in a letter dated February 11, 1980 to Mr. Victor Stello, NRC/0IE, from Mr. D. D. Duvall of Gould-Brown Boveri. However, that report incorrectly I identifies how or where the deficiencies were detected. The deficiencies were identified initially during testing at McGuire Nuclear Station rather than at Catawba Nuclear Station. The manufacturer is conducting further l'

evaluations to determine if the SCR deficiency is lot or batch related l or purely random. ,

8008110 66f .

-6

~

. .' s Analysis of Safety Implication: .

Only three relays out of 829 relays have been found deficient and none of these were in safety circuits. The investigation is continuing by Duke and the manufacturer to determine if those in safety-related circuits could be affected by the saea problem.

Corrective Action:

All relays and trip devices containing the specific type of SCR's that are within safety circuits have been identified. The SCR's that were removed from McGuire Nuclear Station are being returned to the manufacturer for further analysis and evaluation to determine if the deficiency is confined to a batch, a lot or are random. Upon completion of this avaitation or any identification of deficiencies in ti.e subject relays or trip devices in saf ety-related circuits, action will be undertaken to change out those SCR's and trip devices as required to correct,any deficiency. The change out of any SCR's and trip devices identified by the evaluation is anticipated to be completed by January 1, 1981. A final report will be provided at that time.

i l

!