ML20138P533

Forwards New Encl 12 Calculations & Revised Pages to Util 851108 Submittal of Confirmatory Info Re SPDS Isolation Devices Used at Facility.Encl 12 Previously Withheld Due to Mfg Info Modifying Calculations

ML20138P533
Person / Time
Site:	Fort Calhoun
Issue date:	12/09/1985
From:	Andrews R OMAHA PUBLIC POWER DISTRICT
To:	Thadani A Office of Nuclear Reactor Regulation
References
LIC-85-557, NUDOCS 8512260155
Download: ML20138P533 (22)

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Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 2247 402/536-4000 December 9, 1985 LIC-85-557 Mr. Ashok C. Thadani, Project Director PWR Project Directorate #8 Division of PWR Licensing - B Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555

References:

(1)

Docket No. 50-285 (2)

Letter from OPPD (Andrews) to NRC (Miller) dated December 7, 1984 (LIC-84-327)

(3) Letter from NRC (Butcher) to OPPD (Andrews) dated June 7, 1985 (4) Letter from OPPD (Andrews) to NRC (Butcher) dated November 8, 1985 (LIC-85-494)

Dear Mr. Thadani:

Safety Parameter Display System (SPDS)

Isolation Devices OPPD provided revisions to confirmatory information pertaining to the SPDS isolation devices used at the Fort Calhoun Station in Reference (4). The revisions were to attachments provided in Reference (2) which identified the isolation devices and were in response to your request received in Reference (3).

The Reference (4) transmittal withheld Enclosure 12, (calculations involving KTN fuses between vital instrument inverters and Scientific Columbus VT 110A2 transducers), because information received from the inverter manufacturer modified the calculations.

Please find attached, the new Enclosure 12 calculations and other assoc-iated revised pages to the Reference (4) submittal. It is recommended that the revised pages and Enclosure 12 be incorporated into Reference (4) to provide continuity to your review.

If you have further questions, please contact us.

h04g Sincerely, g

h g22ggoN O

1. dplF[

F R. L. Andrews Division Manager Nuclear Production RLA/HMT/me cc: see next page

nu -,

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.,s y 3-Mr. Ashok Thadani (LIC-85-557~

-- Page 2

~ Attachments

. cc: LeBoeuf,, Lamb Leiby & MacRae 1333-New Hampshire Ave., N.W.

Washington,.D.C. 20036 Mr. E; G..Tourigny, NRC Project Manager

-Mr.:P. H. Harrell, NRC Senior Resident Inspector 5

F' t

LIST-(F ENCLOSURES IDENTIFIED IN ATTACHMENT 4.1 Enclosure Description 1

Electronagnetic Interference for TEC Model 156 Analog Signal Isolator

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2 (Deleted)

.3 (Deleted) 4 (Deleted) 5 (Deleted) 6 (Deleted) 7 (Deleted)-

4 8

Product Application Data Sheet No. PAD P4400-006 9 (Deleted)

See Foxboro Qualification Report Q0AAA20-1 Pages 11,12, 27, 28, 59, 72, -117,118,119.

This report is very large, therefore it is not enclosed, however the specific pages which apply are listed above..It is OPPD's understanding that the device tested is-considered to be a suitable isolation device.

10 General Atomic Company Specification Sheet for Buffer Amplifier, Model BA-1A 11 (Deleted)-

12-Calculations involving KTN fuses and between Vital Instrument Inverters and Scientific Colunbus VT110A4 Transducers

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i PROPOSED IETH00 0F ISOLATION FROM SAFETY SYSTEMS c

Signal:

Y3286A/B/C/D Static Inverter Volts Device:

Fuses installed on the input leads to the voltage transducers.

a.

Describe specific testing perfonned to demonstrate that the device is acceptable for its application:

See enclosure 12 for analysis of fuses used.

a.

(cont'd)

Elementary diagrams indicating test configuration and how maximum credible faults were applied to the devices:

See enclosure 12 for analysis of fuses used.

.b.

Data verifying that the maximum credible faults applied during the test were -maximum voltage / current to which the device could be exposed, and define how maximum voltage / current was determined:

See enclosure 12 for analysis of fuses used.

I

F c.

Data verifying that the maximum credible fault was applied to the output of the device in the transverse mode and other faults were considered.

See enclosure 12 for analysis of fuses used.

d.

Pass / fall acceptance criteria for each type of device.

See enclosure 12 for analysis of fuses used.

e.

Commitment that the isolation devices comply with environmental qualifi-cations (10 CFR 50.49) and seismic qualifications which were the basis for plant licensing.

These fuses are installed in the control room, a mild environmental, therefore,10 CFR 50.49 environmental qualification is not required.

Construction of these fuses and fuse blocks (Bussman #180002) is similar to the ones installed in the alternate shutdown panel which was qualified per IEEE 344-1974.

f.

Description of measures taken to protect the safety systems from elec-trical interfirence that may be generated by the SPDS:

The measures are the same as described in the response for signal T113.

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