ML20195F803
| ML20195F803 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/11/1999 |
| From: | Woodard J SOUTHERN NUCLEAR OPERATING CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LCV-1362, NUDOCS 9906150099 | |
| Download: ML20195F803 (6) | |
Text
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J. D.Woodard Southern Nuclear Executive Vice President Operating Company,Inc.
40 invemess Center Parkway Post Offico Box 1295 Birmingham, Alabama 35201 Tel 205.992.5088 k
SOUTHERN h COMPANY Energy to Serve nurWorM*
June 11,1999 LCV-1362 Docket No.
50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Ladies and Gentlemen:
VOGTLE ELECTRIC GENERATING PLANT EMERGENCY RESPONSE DATA SYSTEM (ERDS)
DATA POINT LIBRARY MODIFICATION In accordance with the requirements of 10 CFR 50, Appendix E, Section VI, Item 3a, -
' Southern Nuclear Operating Company is submitting changes to the Vogtle Electric Generating Plant Unit 1 Emergency Response Data System (ERDS) data point library.
The changes were completed on March 8,1999, while Unit I was shut down for a j
refueling outage. Submittal of the changes within the required 30 days was inadvertently
'//
overlooked.
The data points UV0031 and UV0035 (validated source range neutron flux and validated intermediate range neutron flux respectively) were revised to reflect the replacement of the Westinghouse source and intermediate range nuclear instrumentation with the Gamma-Metrics neutron flux monitoring system. Marked up and printed copies of the changes are attached.
If you have any questions, please contact this office.
Sincerely, J. D.
oodard
[
Attachments (4): Marked up and printed changes to the Unit 1 ERDS data point library.
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U. S. Nuclear Regulatory Commission Page 2 l-JDW/RJF Southern Nuclear Operating Company xc:
Mr. J. T. Gasser -
Mr. M. Sheibani SNC Document Management U. S. Nuclear Regulatory Commission Mr. L. A. Reyes, Regional Administrator Mr. R. R. Assa, Licensing Project Manger, NRR Mr. J. Zeiler, Senior Resident Inspector, Vogtle i
l 1-LCV-1362 I'
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Emergency R::ponss D;t2 Systrm (ERDS)
Pcga 2 D ta Point Librcry-VEGP Unit 1 S[d[ff Dmie
^'"^5.T.
Reactor Un'lt
- VOI Data Feeder
- N/A NRC ERDS Parameter
- NIINTER RNG Point ID
- UV0035 Plant Spec. Point
- VALIDATED NEUTRON FLUX INTERMEDIATE RNG Generic /Cond.
- NUCLEAR INSTRUMENTS, INT RANGE Analog / Digital
- A
[
Engr. Units / Dig
- " " ^0 Engr. Units
- :.0 :: ; :.00-0; / :.: :;
f.578~/O Io 4Of**I Minimum Instr.
- :.0E- : 4.6fE-/0 Maximum Instr.
- : ^^: :.2,Of+A Zero Point
- N/A Reference Point
- N/A Proc or Sens.
- P Number of Sensors
- 2 How Processed
- VALIDATED AVERAGE Sensor Locations
- ADJACENT TO OUTSIDE OF REACTOR VESSEL
- Alarm /frip Setpoints
- NONE NI Power Cut Off
- N/A NI Power Turn On
- N/A l
Instrument Fal!ure
- N/A Temp. Comp.
- N l
Level Reference
- N/A
. Unique System This point represents the validated average of the intermediate range Ni detectors. Only valid inputs are used in the calculation, invalid inputs are discarded prior to performance of the calcu'ation. If no valid inputs are present, this point is marked invalid. The intermediate range detectors are located externally to the reactor vessel.
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c Em::rgency R:spOnse D:ta System (ERDS)
P g3 3 l
D t2 Point Libr:;ry-VEGP Unit 1 l
l 45/f/W Date
- 97 2 ""
Reactor Unit
- VOI l
Data Feeder
- N/A l
NRC ERDS Parameter
- NI SOURC RNG Point ID
- UV0031 Plant Spec. Point
- VALIDATED NEUTRON FLUX SOURCE RANGE Generic /Cond.
- NUCLEAR INSTRUMENTS, SOURCE RNG Analog / Digital
- A Engr. Units / Dig
- CPS -
- c,09 Engr. Units
- -M l.0E+6 CPS Minimum Instr.
- -M-0. 07 Maximum Instr.
- 1000000.0 j
Zero Point
- N/A Reference Point
- N/A Proc or Sens.
- P Number of Sensors t 2 How Processed
- VALIDATED AVERAGE Sensor Locations
- ADJACENT TO OUTSIDE OF REACTOR VESSEL Alarm / Trip Setpoints
- NONE gp NI Power Cut Off e g p:cpy,.; m ;
NI Power Turn On
- ' er t e,* up Instrument Failure
- N/A Temp. Comp.
- N Level Reference
- N/A Unique System This point consists of the validated average of the two source range signals from the excore detectors located adjacent to the outside of the vessel. If either signal is invalid the other is used. The point is marked invalid if no valid inputs are present.
Source range instrumentation can be bypassed if one intermediate range channel is greater than P6.. _
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_ _ __.; =,..;.. e,,n n nez o.. P6 represents !.0" ' O T.;: intermediate range power. ?:_x: r;: ? "
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4.0 E-5 %
EROS DPL DATAaASE.MDB I
Emergency R:sponss Dit: Syst:m (ERDS)
Pago 2 D;ta Point Library-VEGP Unit 1 Date
- 3/8/99 Reactor Unit
- 'VOI Data Feeder
- N/A NRC ERDS Parameter
- N1 INTER RNG Point ID
- UV0035 Plant Spec. Point
- VALIDATED NEUTRON FLUX INTERMEDIATE RNG Generic /Cond.
- NUCLEAR INSTRUMENTS, INT RANGE Analog / Digital
- A Engr. Units / Dig Engr. Units
- 4.69 E-10 to 2.0 E+2 %
Minimum Instr.
- 4.69 E-10
)
Maximum Instr.
- 2.0 E+2 Zero Point
- N/A
' Reference Point
- N/A Proc or Sens.
- P l
Number of Sensors
- 2 How Processed
- VALIDATED AVERAGE Sensor Locations
- ADJACENT TO OUTSIDE OF REACTOR VESSEL Alarm /frip Setpoints
- NONE 1
NI Power Cut Off
- N/A NI Power Turn On
- N/A l
Instrument Failure
- N/A l
Temp. Comp.
- N Level Reference
- N/A Unique System This point represenir the validated average of the intermediate range NI detectors. Only valid inputs are used in the calculation, invalid inputs are discarded prior to performance of the calculation. If no valid inputs are present, this point is i
marked invalid. The intermediate range detectors are located externally to the reactor vessel.
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Emergency R:spons3 D;ts Syst:m (ERDS)
Paga 3 Dito Point Library-VEGP Unit 1 y.-
Date
- 3/8/99 Reactor Unit
- VO!
Data Feeder
- N/A NRC ERDS Parameter
- NI SOURC RNG Point ID
- UV0031 Plant Spec. Point
- VALIDATED NEUTRON FLUX SOURCE RANGE Generic /Cond.
- NUCLEAR INSTRUMENTS, SOURCE RNG Analog / Digital
- A Engr. Units / Dig
- CPS Engr. Units
- 0.09 to 1.0E+6 CPS Minimum Instr.
- 0.09 Maximum Instr.
- 1000000.0 Zero Point
- N/A l
Reference Point
- N/A Proc or Sens.
- P
~ Number of Sensors
- 2 How Processed
- VALIDATED AVERAGE Sensor Locations
- ADJACENT TO OUTSIDE OF REACTOR VESSEL '
Alarm /I'rlp Setpoints
- NONE NI Power Cut Off
- N/A NI Power Turn On
- N/A Instrument Failure
- N/A Temp. Comp.
- N Level Reference
- N/A Unique System This point consists of the validated average of the two source range signals from the exeore detectors located adjacent to the outside of the vessel. If either signal is invalid the other is used. The point is marked invalid if no valid inputs are present.
Source range instrumentation can be bypassed if one intermediate range channel is greater than P6. P6 represents 2.0 E.5 %
intermediate range power.
i ERDS DPL DATABASE.MDB