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{{#Wiki_filter:~CATEGORY 1 0 REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)ACCESSION NBR:9810210075 DOC.DATE: 98/10/13 NOTARIZED:
{{#Wiki_filter:~         CATEGORY 1               0 REGULATORY INFORMATION DISTRXBUTION SYSTEM (RIDS)
NO DOCKET FACXL:50-296 Browns Ferry Nuclear Power Station', Unit 3, Tennessee 05000296 AUTH.NAYE AUTHOR AFFXLIATION ABNEY,T.E.
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)
Tennessee Valley Authority RECXP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Notifies NRC of revs to BFN Unit 3 Emergency Response Data Sys (ERDS)Data Point Library.Revs to ERDS,encl.
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:
DISTRIBUTION CODE: A026D         COPIES RECEIVED:LTR l ENCL l             SIZE:
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.
TITLE: Emergency Response         Data System     (ERDS)
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:
NOTES:
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),:
RECXP IENT           COPIES              RECIPIENT            COP1ES XD CODE/NAME           LTTR ENCL          ID CODE/NAME          LTTR ENCL AEOD/XRB         01       1      1      DEAGAZIO,A                1      1.
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:
INTERNAL: ACRS                         1      1      AEOD                      1      1 AEOD/DOA/IRB             1     1                                 1     1 RGN2    ERC              1     1       RGN2     FILE             1     1 EXTERNAL: NRC PDR                     1     1 D
Point ID: Plant Spec Point Desc: GenericCondDesc:
0 NOTE TO ALL "RIDS" RECIPIENTS:
9/21/98 MAIN FD FLOW CALC040 RFW FLOW TO REACTOR Feedwater Flow into the Reactor Analog/Digital:
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
'ngr Units/Dig States: Engr Units Conv Minimum Instr Range: Maximum Instr Range: Zero Point  
  .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                                               )               Docket No. 50-296 Tennessee          Valley Authority                            )
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 have any questions, please contact me in this letter. If you I
at (256) 729-2636.
S ncerel T. E. Abney Manager of           L'sin     Affai and Indus           ry                 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   [~
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EROS Point Number:     5           FD FLOW           CALC040           vater Flow into the Reactor Date:                     9/21/98 Reactor Unit:
Data Feeder:
NRC ERDS Parameter:       MAINFD FLOW Point ID:                 CALC040 Plant Spec Point Desc:     RFW FLOW TO REACTOR GenericCondDesc:          Feedwater Flow into the Reactor Analog/Digital:
'ngr Units/Dig States:
Engr Units Conv           N/A Minimum Instr Range:
0.0'6.0 Maximum Instr Range:
Zero Point  


==Reference:==
==Reference:==
N/A Reference Point Notes:    N/A PROC or SENS              P Number of Sensors:
How Processed:            Sum    of RFW LINE A and RFW LINE B (ADD)
Se'nsor Locations:        N/A Alarm/I'rip Set Points:    Run: HIHI=14.8 HI=14.7 NID Power Cutoff Level:    N/A NID Power Cut              N/A Instrument Failure Mode:  N/A Temperature Compensation:  N Level Reerence Leg:        N/A Unique System Desc:        Sum    of feedflow instruments, uncompensated
lg g(


Reference Point Notes: N/A 0.0'6.0 N/A N/A PROC or SENS Number of Sensors: How Processed:
ERDSPointNumber:       7   CS PRESSURE             SPDS0008           R   or Coolant System Prcssure Date:                     9/21/98 Reactor Unit:             BF3 Data Feeder:
Se'nsor Locations:
NRC ERDS Parameter:.       RCS PRESSURE Point ID:                   SPDS0008 Plant Spec Point Desc:     'RX PRESSURE - COMPOSED GenericCond Desc:          Reactor Coolant System Pressure Analog/Digital:             A Engr Units/Dig States:     PSIG Engr Units Conv           N/A Minimum Instr Range:
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:
Maximum Instr Range:       1500 Zero Point  
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:==
N/A Reference Point Notes:    N/A PROC or SENS Number of Sensors:
How Processed:            Weighted Average w/Fault Detect (PSVA)
Sensor Locations:          N/A Alarm/I'rip Set Points:    See  Below NID Power Cutoff Level:    N/A NID Power Cut              N/A Instrument Failure Mode:  N/A Temperature Compensation:  Y Level Reerence Leg:        N/A Unique System'Desc:        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


Reference Point Notes: A PSIG N/A 1500 N/A N/A PROC or SENS Number of Sensors: How Processed:
0 0 11 ij
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'(}}

Latest revision as of 15:35, 3 February 2020

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 COPIES RECIPIENT COP1ES XD CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL AEOD/XRB 01 1 1 DEAGAZIO,A 1 1.

INTERNAL: ACRS 1 1 AEOD 1 1 AEOD/DOA/IRB 1 1 1 1 RGN2 ERC 1 1 RGN2 FILE 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 ) Docket No. 50-296 Tennessee Valley Authority )

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 have any questions, please contact me in this letter. If you I

at (256) 729-2636.

S ncerel T. E. Abney Manager of L'sin Affai and Indus ry 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: 9/21/98 Reactor Unit:

Data Feeder:

NRC ERDS Parameter: MAINFD FLOW Point ID: CALC040 Plant Spec Point Desc: RFW FLOW TO REACTOR GenericCondDesc: Feedwater Flow into the Reactor Analog/Digital:

'ngr Units/Dig States:

Engr Units Conv N/A Minimum Instr Range:

0.0'6.0 Maximum Instr Range:

Zero Point

Reference:

N/A Reference Point Notes: N/A PROC or SENS P Number of Sensors:

How Processed: Sum of RFW LINE A and RFW LINE B (ADD)

Se'nsor Locations: N/A Alarm/I'rip Set Points: Run: HIHI=14.8 HI=14.7 NID Power Cutoff Level: N/A NID Power Cut N/A Instrument Failure Mode: N/A Temperature Compensation: N Level Reerence Leg: N/A Unique System Desc: Sum of feedflow instruments, uncompensated

lg g(

ERDSPointNumber: 7 CS PRESSURE SPDS0008 R or Coolant System Prcssure Date: 9/21/98 Reactor Unit: BF3 Data Feeder:

NRC ERDS Parameter:. RCS PRESSURE Point ID: SPDS0008 Plant Spec Point Desc: 'RX PRESSURE - COMPOSED GenericCond Desc: Reactor Coolant System Pressure Analog/Digital: A Engr Units/Dig States: PSIG Engr Units Conv N/A Minimum Instr Range:

Maximum Instr Range: 1500 Zero Point

Reference:

N/A Reference Point Notes: N/A PROC or SENS Number of Sensors:

How Processed: Weighted Average w/Fault Detect (PSVA)

Sensor Locations: N/A Alarm/I'rip Set Points: See Below NID Power Cutoff Level: N/A NID Power Cut N/A Instrument Failure Mode: N/A Temperature Compensation: Y Level Reerence Leg: N/A Unique System'Desc: 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

'(