ML20137L056

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Forwards PSCC-1-EIP-24, Test Procedure for Qualification of Fort St Vrain Electrical Isolation Sys... & Rev 0 to EIP-24, Test Procedure for Performance & Isolation Testing..., Per NRC Request for SPDS Review
ML20137L056
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 08/26/1985
From: Warembourg D
PUBLIC SERVICE CO. OF COLORADO
To: Hunter D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20137L062 List:
References
P-85300, TAC-51242, NUDOCS 8509120326
Download: ML20137L056 (2)


Text

-

1.,

PublicService .no s., .

Company of Colorado 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211

, August 25, 1985

,s Fort St. Vrain 1 SEP - 31985  : , unit No. 1 P-85300 Regional Administrator Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012 Attn: Mr. Dorwin Hunter Docket No. 50-267

SUBJECT:

Safety Parameter Display System Safety Analysis Report

REFERENCES:

1) NRC Letter Johnson to Lee dated 9/14/84 (G-84355)
2) PSC Letter Warembourg to Johnson dated 7/19/84 (P-84372)
3) PSC Letter Warembourg to Johnson dated 11/13/84 (P-84487)

Dear Mr. Hunter:

Attached please find test plan and preliminary test report for Safety Parameter Display System isolation (SPDS). This letter also provides ,

the action taken in regard to the information needed for staff review  !

discussed in Reference 3, Item 7.C. and 7.D.

NRC requested "With regard to isolation devices between the SPDS and n ,

safety systems, provide the following information:"

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. .1 Item 7.C. For each type of device used to accomplish electrical

. isolation, describe the specific testing performed to demonstrate that the device is acceptable fcr its application (s). This description should include the test configuration and how the maximum credible faults were applied to the devices.

ITEM 7.D. Data to verify that the maximum credible fault was applied to the output of the device in the transverse mode (between signal and return) and other faults were considered (i.e. open and short circuits).

Item 7.C. is addressed by Attachments 1 and 2 to this letter. Item 7.D. is addressed by Attachments 3 thru 7. If you have any questions regarding this matter, please call Mr. M. H. Holmes at(303) 571-8509.

Very truly yours, 0JY.fYw d wy D. W. Warembourg, Mandtjer Nuclear Engineering Division DWW/DW:pa Attachments cc: Mr. E. H. Johnson