ML18039A577: Difference between revisions

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| issue date = 10/13/1998
| issue date = 10/13/1998
| title = Notifies NRC of Revs to BFN Unit 3 Emergency Response Data Sys (ERDS) Data Point Library IAW 10CFR50,App E,Section VI.3.a.Revs Were Implemented on 980921 & Require NRC Notification within 30 Days
| title = Notifies NRC of Revs to BFN Unit 3 Emergency Response Data Sys (ERDS) Data Point Library IAW 10CFR50,App E,Section VI.3.a.Revs Were Implemented on 980921 & Require NRC Notification within 30 Days
| author name = ABNEY T E
| author name = Abney T
| author affiliation = TENNESSEE VALLEY AUTHORITY
| author affiliation = TENNESSEE VALLEY AUTHORITY
| addressee name =  
| addressee name =  

Revision as of 00:11, 18 June 2019

Notifies NRC of Revs to BFN Unit 3 Emergency Response Data Sys (ERDS) Data Point Library IAW 10CFR50,App E,Section VI.3.a.Revs Were Implemented on 980921 & Require NRC Notification within 30 Days
ML18039A577
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 10/13/1998
From: Abney T
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9810210075
Download: ML18039A577 (12)


Text

~CATEGORY 1 0 REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)ACCESSION NBR:9810210075 DOC.DATE: 98/10/13 NOTARIZED:

NO DOCKET FACXL:50-296 Browns Ferry Nuclear Power Station', Unit 3, Tennessee 05000296 AUTH.NAYE AUTHOR AFFXLIATION ABNEY,T.E.

Tennessee Valley Authority RECXP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Notifies NRC of revs to BFN Unit 3 Emergency Response Data Sys (ERDS)Data Point Library.Revs to ERDS,encl.

DISTRIBUTION CODE: A026D COPIES RECEIVED:LTR l ENCL l SIZE: TITLE: Emergency Response Data System (ERDS)NOTES: RECXP IENT XD CODE/NAME AEOD/XRB 01 INTERNAL: ACRS AEOD/DOA/IRB RGN2 ERC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME DEAGAZIO,A AEOD RGN2 FILE COP1ES LTTR ENCL 1 1.1 1 1 1 1 1 EXTERNAL: NRC PDR 1 1 D 0 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083.TOTAL NUMBER OF COP1ES REQUIRED: LTTR 9 ENCL 9 il t Tennessee Valley Authority.

Post Office Box 2000.Decatur.Alabama 35609 October 13, 1998 10 CFR 50, Appendix E U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:

In the Matter of)Tennessee Valley Authority)Docket No.50-296 BROWNS FERRY NUCLEAR PLANT (BFN)-UNIT 3-REVISIONS TO EMERGENCY RESPONSE DATA SYSTEM (ERDS)DATA POINT LIBRARY In accordance with 10 CFR 50, Appendix E, Section VI.3.a,"Emergency Response Data System," TVA is providing notification of revisions to the BFN Unit 3 ERDS Data Point Library..These revisions were implemented on September 21;1998, and require NRC notification within 30 days.The enclosure to this letter provides the revisions to the Unit 3 ERDS Data Point Library.There.are no new commitments contained in this letter.If you have any questions, please contact me at (256)729-2636.I S ncerel T.E.Abney Manager of L'sin and Indus ry Affai s Enclosure cc: See page 2'tt810220075 98iOiS PDR ADQCK 050002'stb F PDR II C I U.S.Nuclear Regulatory Commission Page 2'ctober 13, 1998 Enclosure cc (Enclosure),:

Mr.H.0.Christensen, Branch U.S..Nuclear Regulatory Commission Region II 61 Forsyth Street, S.W.Suite 23T85 Atlanta, Georgia 30303 NRC Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611 Mr.A.W.De Agazio, Senior Project Manager U.S.Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 0 t ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)UNIT 3 EMERGENCY RESPONSE DATA SYSTEM (ERDS)REVISION TO DATA POINT LIBRARY (SEE ATTACHED) ik[~',l EROS Point Number: 5 FD FLOW CALC040 vater Flow into the Reactor Date: Reactor Unit: Data Feeder: NRC ERDS Parameter:

Point ID: Plant Spec Point Desc: GenericCondDesc:

9/21/98 MAIN FD FLOW CALC040 RFW FLOW TO REACTOR Feedwater Flow into the Reactor Analog/Digital:

'ngr Units/Dig States: Engr Units Conv Minimum Instr Range: Maximum Instr Range: Zero Point

Reference:

Reference Point Notes: N/A 0.0'6.0 N/A N/A PROC or SENS Number of Sensors: How Processed:

Se'nsor Locations:

Alarm/I'rip Set Points: P Sum of RFW LINE A and RFW LINE B (ADD)N/A Run: HIHI=14.8 HI=14.7 NID Power Cutoff Level: NID Power Cut Instrument Failure Mode: N/A N/A N/A Temperature Compensation:

N Level Reerence Leg: Unique System Desc: N/A Sum of feedflow instruments, uncompensated lg g(

ERDSPointNumber:

7 CS PRESSURE SPDS0008 R or Coolant System Prcssure Date: Reactor Unit: Data Feeder: NRC ERDS Parameter:.

Point ID: Plant Spec Point Desc: GenericCond Desc: 9/21/98 BF3 RCS PRESSURE SPDS0008'RX PRESSURE-COMPOSED Reactor Coolant System Pressure Analog/Digital:

Engr Units/Dig States: Engr Units Conv Minimum Instr Range: Maximum Instr Range: Zero Point

Reference:

Reference Point Notes: A PSIG N/A 1500 N/A N/A PROC or SENS Number of Sensors: How Processed:

Sensor Locations:

Alarm/I'rip Set Points: Weighted Average w/Fault Detect (PSVA)N/A See Below NID Power Cutoff Level: NID Power Cut Instrument Failure Mode: N/A N/A N/A Temperature Compensation:

Y Level Reerence Leg: Unique System'Desc:

N/A Instruments are, calibrated for rated operating conditions.

Alarm:-Run: HIHI=1073 HI=1070 LO=918 LOLO=915 Startup: HIHI=1073 HI=1070 LO=918 LOLO=915 Shutdown: HIHI=1073 HI=1070 Refuel: HIHI=1073 HI=1070 0 0 11 ij'(