NRC-97-0062, Forwards Revised Emergency Response Data Sys Data Point Library Reference File.Rev Was Implemented on 970506 & Consists of Changing Point Id Name from C32SL009 to C32DL009 & Superseding Changes in

Forwards Revised Emergency Response Data Sys Data Point Library Reference File.Rev Was Implemented on 970506 & Consists of Changing Point Id Name from C32SL009 to C32DL009 & Superseding Changes in

ML20140C921
Person / Time
Site:	Fermi
Issue date:	06/04/1997
From:	Peterson N DETROIT EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CON-NRC-97-0062, CON-NRC-97-62 NUDOCS 9706100132
Download: ML20140C921 (2)

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June 4,1997 NRC-97-0062 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555

Reference:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) Detroit Edison Letter To NRC," Submittal Of Changes To ERDS Data Point Library," NRC-95-0039, dated March 20,1995

3) Detroit Edison Letter To NRC," Submittal Of ERDS Data Point 1.ibrary For Fermi 2," NRC-92-0033, dated February 26,1992

Subject:

Submittal Of Chances To ERDS Data Point Library In accordance with 10CFR50, Appendix E, Section VI.3.a enclosed is a revised Emergency Response Data System (ERDS) Data Point LibraIy Reference File. The revision was implemented on May 6,1997, and consists of(1) changing the Point ID name from C32SL009 to C32DLOO9, and (2) superseding the changes identified in Reference 2 such that, with the exception of the Point ID name change, the file is consistent with Detroit Edison's original Data Point Library submittal (Reference 3).

If you have any questions, please contact Andrew V. Antrassian, Compliance Engineer, at (313) 586-1856.

Sincere *, J 9706100132 970604 h PR ADOCK 0500 1 orman K. Peterson

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Acting Director - Nuclear Licensing Enclosure cc: A. B. Beach j G. A. Ilarris M. J. Jordan llllll'll'$\l klh!

A. J. Kugler g.31 g Region Ill

f e '. a- NRC-97-0062 '

Enclosure EDP 27300 Rev.0 Inder Item No. A /3 Page lofI

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DATA POINT LIBRARY REFERENCE RLE Date: 02/20/92 Reactor Unit FE2 Data Feeder: N/A NRC EROS Parameter: REAC VES LEV Point 10: [b20;;;; CS2 PL.do#) REVISE Plant Spec Point Desc.:

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RPV Water Level Narrow Range Div 11 Generic /Cond Desc.: Reactor Vessel Water Level Analog / Digital: A Engr Units / Dig States: INCHES '

, Engr Units Conversion: _N/A Minimum instr Range: 160 Maximum Instr Range: 220 Zero Point

Reference:

TAF Reference Point Notes: N/A PROC or SENS: S a

Number of Sensors: 001 How Processed: _ Direct Reading Sensor Locations: Rx vessel nozzle, (N118), AZ 220 , Elev 643'-6*

Alarm / Trip / Set Points: See unique system description E- =

NI Detector Power Supply Cut-off Power Level: N/A 7"l1 i} fM4fft"lt'f

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NI Detector Power Supply 6 I Turn-on Power Level: N/A 7 J/ -Z7217 i

[ M[* I instrument Failure Mode: __ Value = -999 Quatity = Bad l

Temperature Compensation b0 HO T* l For DP Transmitters: N/A

/ A/ (a/-P#4'4M Level Reference Leg: Wet Unique System Desc:  !

Feedwater system alarm conditions are: High alarm at 202*.

Low alarm at 193*. Plant trip and computer alarm setpoints are: High at 214* and low at 173.4*.

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A) Prepar d y B) Checked y Sign =-- 0 ie Y-M"fb Sign /h M v JMosie [dhk i-DTC: TPMMES DSN: MES19004 Rev. 0 Pl/l File:1703.22 Date: 0825 Recip:

DTC: TCEDP DSN g77.300. ALT Rev: File: 1801 IP: 1 Date:fff- __ Recip: 8&