ML20196C429

Forwards Rev to ERDS Data Point Library for Ccnpp,Unit 2,per 10CFR50,App E,Section VI.3.a.Table Provides Brief Summary of Changes

ML20196C429
Person / Time
Site:	Calvert Cliffs
Issue date:	06/21/1999
From:	Lemons J BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9906240032
Download: ML20196C429 (3)

Text

, c JAMES R. LEMUNS Baltimore Gas and Electric Company Afanager Calvert Clifs Nuclear Power Plant Nuclear Support Services 1650 Calvert Chfs Parkway Lusby, Afaryland20657 410 $86-2200 Ext. 3693 li> cal 410 ?fn3693 Baltimore June 21,1999 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Emergency Response Data System The attached revision to the Emergency R.esponse Data System (ERDS) Data Point Library for the Calvert Cliffs Nuclear Power Plant is provided pursuant to 10 CFR Part 50, Appendix E, Section VI.3.a.

The table below provides a brief summary of the changes:

C PointL '

' V 43 - ' - - - ^'-

a1 New. Rangel

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lOld hoge F131 A 2 RCS Total Flow Channel A -51.70:146.2 % Flow -53.49:151.25% Flow Revised ERDS Data Point Library sheets are attached.

Should you have questions regarding this matter, we will be pleased to discuss them with you.

f Very truly yours, q))b W

JRI/TWG/ dim N

Attachment:

As Stated cc: R. S. Fleishman, Esquire IL J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I-1, NRC R.1. McLean, DNR A. W. Dromerick, NRC J. H. Walter, PSC J. R. Jolicoeur, NRC l

' 9906240032 990621 PDR ADOCK 05000318 F PDR _.

e e5 E131A's CUTPtFF SCREEN PWR DATA POINT LIBRARY REFERENCE FILE REV DATER 07/23/97

,fm - PAGE  : 5

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%sl DATE: 07/23/97 REACTOR UNIT: CC2 l

DATA FEEDERt CC21 f

NRC ERDS PARAMETER: CORE FLOW POINT ID: F131A PLANT SPEC POINT DESC.s RCS TOTAL FLOW CH A GENERIC /COND DESC.: ; TOTAL REACTOR COOLANT FLOW ANALOG / DIGITAL A~

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ENGR UNITS / DIG STATES  % FLOW ENGR UNITS CONVERSION: 100% RX COOLANT FLOW = 370,000 GPM MINIMUM INSTR RANGE: -51.70 MAXIMUM INSTR RANGE: 146.20 I ZERO POINT

REFERENCE:

N/A REFERENCE POINT NOTES: N/A PROC OR SENS: S NUMBER OF SENSORSi- 1 p}' :

i HOW PROCESSED: N/A Q/

. SENSOR IDCATIONS: N/A  ;

I ALARM / TRIP SET POINTSr N/A NI DETECTOR POWER SUPPLY CUT-OFF POWER LEV N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEVs N/A INSTRUMENT FAILURE MODE: N/A I

TEMPERATURE COMPENSATION FOR DP TRANSMITTERS: N

' LEVEL REFERENCE LEG: N/A l

L*NIQUE SYSTEM DESC.: REACTOR CCOLANT FLOW IS DETERMINED BY THE D/P ACROSS THE STEAM GENERATORS. WHERE TOTAL FLOW IS THE SUM OF BOTH LOOP FLOWS.

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I S. \ . ' M PWR DATA' POINT LIBRARY REFERENCE FILE REV DATE: 06/01/99 PAGE  : 5 U().-

,DATE: 06/01/99 REACTOR UNIT: CC2 DATA FEEDER: CC21 NRC.ERDS' PARAMETER: CORE FLOW POINT'ID: F131A PLANT SPEC POINT DESC.-: RCS TOTAL FLOW CH A GENERIC /COND DESC.: TOTAL REACTOR COOLANT FLOW ANALOG / DIGITAL: A ENGR UNITS / DIG STATES:  % FLOW ENGR UNITS CONVERSION: 100%'RX COOLANT FLOW = 370,000 GPM MINIMUM INSTR RANGE: -53.49

. MAXIMUM INSTR. RANGE: 151.25

'ZERO POINT

REFERENCE:

N/A REFERENCE POINT NOTES: N/A PROC OR SENS: S NUMBER OF SENSORS: .1 i HOW PROCESSED: 'N/A SENSOR-LOCATIONS: N/A ALARM / TRIP SET POINTS: N/A NI DETECTOR POWER

-SUPPLY CUT-OFF. POWER LEV: N/A

.NI. DETECTOR POWER SUPPLY TURN-ON POWER LEV: N/A-INSTRUMENT-FAILURE MODE: N/A i

TEMPERATURE COMPENSATION "FOR DP. TRANSMITTERS: N LEVEL REFERENCE LEG: N/A UNIQUE SYSTEM'DESC.: REACTOR COOLANT FLOW IS DETERMINED BY THE D/P ACROSS THE STEAM GENERATORS. WHERE TOTAL FLOW THE SUM OF BOTH LOOP. FLOWS. {