ML20217M295

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Forwards Rev to ERDS Data Point Library for Calvert Cliffs Nuclear Power Plant
ML20217M295
Person / Time
Site: Calvert Cliffs 
Issue date: 08/19/1997
From: Lemons J
BALTIMORE GAS & ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9708220116
Download: ML20217M295 (3)


Text

J AMe n R. l.snons Italtimore cias arul1:lectric Comiumy

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Afanager Cuh rrt Clyls Nuclear l'on er l*lant t

Nuclear Sulynort Smices afi$a Calvert Clyls l'araway Imhy. Alaryland 2tt%57 4to $ f> 22tus I.'At 3(m) local 8

410 titt-J(m) llaltimore August 19,1997 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

Document Control Desk SUlWECT:

Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318 Emcigency Resnonse Data System The attached revision to the Emergency Response Data System (ERDS) Data Point Library for the Calven 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:

Point Unit Description Old Range New Range Identifier F131 A 2

RCS Total Flow Channel A 54.157:153.064 % Flow

-51.70:146.2 % 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.

Very truly yours, t

,YO

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JRL/FWG/bjd l h k,k !(

Attachment:

As Stated cc:

R. S. Fleishman, Esquire

11. J. Miller, NRC J. E. Silberg, Esquire Resident inspector, NRC Director, Project Directorate 1 1, NRC R.1. McLean, DNR A. W. Dromerick, NRC J.11. Walter, PSC J. R. Jolicoeur, NRC 9700220116 970819

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PDR ADOCK 05000318 F

PM

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PWR DATA POINT LIBRARY kEFERENCd F!1.5 kFV DATES 07/23/97 PAGE

's 6-4 LATE:

07/23/91 9thCTOR UN11e CC2 DATA FEEDERi CC21 NRC ERDS PARAMETE'tt CORE FLOW PO!FT ID:

F111A 11 ANT SPEC POINT DESC. 8 RCS TOTAL F14W CH A QENERIC/COND Disc.s TOTAL REACTOR C001 ANT F1hW ANA140/D10!iALs A

ENGR UNITS /D10 STATES:

4 FLOW

-.kNGR UNITS CONVERSION:

100v RX C001 ANT FI4W = 310,000 OIN MIN 1WJM INSTR RANGE:

+61.70

' MAX 1WJH INSTR RANGE 146.20 EERO POINT RElERENCE:

N/A

'REFERENO POINT NOTEss N/A PROC OR SENS S

WUMSER OF SENSORS:

1 HOW PROCESSEDs N/A-SENSOR LOCATIONS -

N/A AIARM/ TRIP SET POINTS:. N/A N1 DETECTOR POWER SUPPLY CUT-OFF POWER LEVI N/A NI DETECTOR POWER SUPPLY TURN-ON POWER LEVs N/A INS 11ttNENT FAILURE MODES N/A TEMPERATURE COMPENSATION FOK DP TRANSMITTERS:'

N LEVEL REFERENCE LEG N/A UN!QUE SYSTEM DESC,i REACTOR COOLANT FIDW IS DETFRMINED M THE D/P ACROSS THE STEAM OENERATORS. WHERE TOTAL PLOW IS TKT itM OF SOTH 140P F14WS.

t a

IWR DATA (CINT LlbRARY RSFERENG FILE krV DATEf et/34/96 PAO:

s 4

(ATse 04/14/96 PEACTVR UNIT CC3 LATA FEEDER:

CC21 FRC 8tRDS l'AAAMETERI COKE FIDW Polscr ids F13tA P! ANT SPI:C POINT DESC.

RCS TOTAL F14W Of A GENERIC /COND DESC.

TOTAL REACTOR C001Afff F14W ANA!4G/D10lTALs A

_ ENGR UNITS /DIO STATES:

4 FicW ENGR 14f178 CONVERSION:

100% ful CODIANT FIDf e at0,000 CPM MINIMUM INSTR RAHott

.$4,1$7 MAXIMLM INSTR RANGE 4 163,064 EERO PolNT

REFERENCE:

N/A REFERENCE POINT NOTES:

N/A PROC OR SENS:

HUMBER OF SENS0kSi 1

HOW PROCECSED:

N/A 4ENSOR 14 CAT!DNSs N/A A!ARH/ TRIP SET POINTS:

N/A HI ' DETECTOR POWR SUPPLY CtJT.0FF s'0WER LEVs N/A N1 DETCCTOR PO*ER SUPPLY TUPJ8 Of POWEI4 LEVs N/A 1NSTRtHElfr FAILURE MODEi N/A TEMPERAWRE COMPENSATION FOR DP 11LANSM11TERS:

H LEVEL REFF.RENCE LEG:

N/A 14fiQUE SYSTEM DESC.

RIACTOR COOLANT Flat IS DETERMINED BY THE D/P ACROSS THE STEAM OENERA1DRS. WHERE TOTAL FIDW IS THE SUM OF DOTH th0P FI4WS, i.

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