ML20245C172

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Forwards Supporting Documentation for Compliance W/ Requirements of ATWS Rule 10CFR50.62,for Facility.Info Re Adequacy of Isolation Devices Used as Electrical Interfaces Between safety-related & nonsafety-related Circuits
ML20245C172
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 04/19/1989
From: Morris K
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20245C174 List:
References
LIC-89-399, TAC-59096, NUDOCS 8904270040
Download: ML20245C172 (3)


Text

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Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 2247 4 5 36-4000 April 19, 1989 LIC-89-399 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 Washington, DC 20555

References:

1.

Docket No. 50-285 2.

Letter from NRC (P. D. Milano) to OPPD (K. J. Morris) dated December 7, 1988 3.

Letter from OPPD (K. J. Morris) to NRC (P. D. Milano) dated February 14, 1989 (LIC-89-149)

Gentlemen:

SUBJECT:

Supporting Documentation for Compliance with Requirements of ATWS Rule, 'O CFR 50.62, for Fort Calhoun Station (TAC 59096)

Reference 2 requested the Omaha Public Power District (0 PPD) provide additional information concerning the adequacy of isolation devices used as electrical interfaces between safety related and non-safety related circuits. This response was provided in Reference 3.

As stated in Reference 3, OPPD is providing the enclosed attachments which are the test results to document the maximum credible fault (MCF) data which support the following guidance cutlined in Reference 2:

a)

The isolation devices identified have been tested by application of the MCF voltage / current in the transverse mode to its non-safety side and b)

The isolation devices in this application are bounded by the MCF tests.

If you have questions, please contact us.

Sincerely,

/ * /~

. J. Morris Division Manager Nuclear Operations KJM/jak 8904270040 090419 ^'~

IO PDR ADOCK 05000205" P

PNU l

45 5124 Employmen h

Opponunny

U. S. Nuclear Regulatory Commission LIC-89-399 Page 2 l

Attachment:

1.

Similarity Analysis of Models Installed To Those Tested 2.

Seismic Testing of Spec 200 Current Production Model 3.

Seismic / Isolation Test Report for GE Components c:

LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator P. D. Milano, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector

ATTACHMENT 1 SIMILARITY ANALYSIS OF MODELS INSTALLED 1

TO THOSE TESTED 1

l Model Tested :

HGAllJ52 Model Installed:

HGA 111J2 Similarity:

Both the models are identical except for HGAlllJ series having better coil insulation and therefore providing longer life. The model tested conservatively envelops installed model because better insulation of the installed model provides better isolation than the tested model.

Model Tested:

HEA62C238X16 Model Installed:

HEA61A223 Similarity:

HEA62 is identical to HEA61 except for HEA62 having a diode resister combination inserted across the coil circuit to suppress any surge caused by interruption of coil contacts.

Difference between A223 and C238 are only in the number of contacts.

As contacts are in separate non-CQE circuit from the CQE coil circuit the external modification to the coil circuit or number i

t of contacts will not affect isolation capability between CQE coil and non-CQE contacts.

Model Tested:

PTKEB2381C Model Installed:

PTKE82332C Similarity:

The difference between the two is only tha key lock arrangement which will not affect isolrtion capability of contacts.

I i

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