3F1204-03, Emergency Response Data System Data Point Library Changes
| ML043500317 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/02/2004 |
| From: | Powell S Progress Energy Florida |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3F1204-03 | |
| Download: ML043500317 (7) | |
Text
Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50, Appendix E December 2, 2004 3F1 204-03 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Subject Crystal River Unit 3 - Emergency Response Data System Data Point Library Changes
References:
- 1. Letter to NRC, "Submittal of ERDS Implementation Program," dated October 28, 1991
- 2. Letter to NRC, "Emergency Response Data System," dated February 14, 1994 Dear Sir.
The purpose of this letter Is to correct Information provided in the above referenced letters and to provide new data points for the Crystal River Unit 3 (CR-3) Emergency Response Data System (ERDS) Data Point Library. In Reference 1, Florida Power Corporation, now doing business as Progress Energy Florida, Inc. (PEF), stated, in part, that the ERDS data point for "Air Stability at Reactor Site" would be implemented during the second phase of the ERDS project in February 1993 and that the ERDS data point for "Saturation Temperature - Highest CET" would be implemented in the final phase of the ERDS project, no later than March 31, 1994.
In Reference 2, PEF provided Pressurized Water Reactor (PWR) Data Point Library Reference Files necessary to complete the ERDS Data Point Library for CR-3. However, PWR Data Point Library Reference Files for "Air Stability at Reactor Site" and 'Saturation Temperature - Highest CET" were not included In that submittal. A comparison of the above referenced documents found no other anomalies within the ERDS Data Point Library. The omission is documented in the Progress Energy Corrective Action Program as Nuclear Condition Report 122174.
Upon further investigation, PEF determined that the "Saturation Temperature - Highest CET" parameter is not currently available as a data point in the Plant Process Computer System (PPCS) and will not be added to the CR-3 ERDS Data Point Library at this time. The parameter "Highest Temperature at Core Exit" does currently exist in the CR-3 ERDS Data Point Library.
To enhance that data, two new data points were added to the PPCS and the CR-3 Data Point Library for the "Highest Temperature at Core Exit" on November 23, 2004.
The "Air Stability at Reactor Site" parameter has also been added to the PPCS database. Two new data points for this parameter were added to the CR-3 ERDS Data Point Library on November 23, 2004.
Progress Energy Florida, Inc.
Crystal RiverNuclear Plant 15760 W. Powerline Street Crystal River, FL 34428
U.S. Nuclear Regulatory Commission Page 2 of 2 3F1204-03 The four new PWR Data Point Library Reference File data sheets for CR-3 are included as an attachment to this submittal. This information is provided in accordance with 10 CFR 50, Appendix E, Section VI.3.a, which states that data point changes must be submitted to the NRC within 30 days after the changes are completed.
No new regulatory commitments are made in this letter.
If you have any questions regarding this submittal, please contact me at (352) 563-4883.
Sincerely, Sid C. Powell Supervisor, Li nsing & Regulatory Programs Crystal River Nuclear Plant SCP/dwh Attachment Data Point Library Reference Files xc:
NRR Project Manager Regional Administrator, Region 11 Senior Resident Inspector
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT DATA POINT LIBRARY REFERENCE FILES
U.S. Nuclear Regulatory Commission 3F1204-03 Attachment Page 1 of 4 PWR Data Point Library Reference File Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point
Description:
Generic/Cond
Description:
AnafoglDigital:
Engineering Units/Digital State:
Engineering Units Conversion:
Minimum Instrument Range:
Maximum Instrument Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Setpoints:
NI Detector Power Supply Cut-off Power Level:
NI Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation for DP Transmitters:
Level Reference Leg:
Unique System
Description:
November 23, 2004 CR Crystal River Unit 3 N/A STAB CLASS W702 Air Stability Class (Delta-T)
Air Stability at the Reactor Site A
NA N/A 1
7 N/A N/A P
1 Compare delta-T to values in table Primary Met. Tower - 175733' N/A N/A N/A N/A N/A N/A This uses the Delta-T instrument, which displays the delta between the 175' and 33' readings on the primary Met. Tower.
U.S. Nuclear Regulatory Commission 3F1204-03 Attachment Page 2 of 4 PWR Data Point Library Reference File Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point
Description:
Generic/Cond
Description:
Analog/Digital:
Engineering UnitslDigital State:
Engineering Units Conversion:
Minimum Instrument Range:
Maximum Instrument Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Setpoints:
Ni Detector Power Supply Cut-off Power Level:
Ni Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation for DP Transmitters:
Level Reference Leg:
Unique System
Description:
November 23, 2004 CR Crystal River Unit 3 N/A STAB CLASS W707 Air Stability Class (Sigma-Theta)
Air Stability at the Reactor Site A
N/A N/A 1
7 N/A N/A P
1 Compare Sigma-Theta to values in table Primary Met. Tower N/A N/A N/A N/A N/A N/A This uses the Sigma-Theta on the primary Met.
Tower.
U.S. Nuclear Regulatory Commission 3F1 204-03 Attachment Page 3 of 4 PWR Data Point Library Reference File Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point
Description:
Generic/Cond
Description:
Analog/Digital:
Engineering Units/Digital State:
Engineering Units Conversion:
Minimum Instrument Range:
Maximum Instrument Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
Iow Processed:
Sensor Locations:
Alarm/Trip Setpoints:
Ni Detector Power Supply Cut-off Power Level:
Ni Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation for DP Transmitters:
Level Reference Leg:
Unique System
Description:
November 23, 2004 CR Crystal River Unit 3 N/A TEMP CORE EX RECL-423 T-lncore Maximum Temp A Train Highest Temperature at the Core Exit A
DEGF None 0
2500 N/A N/A IP 8
Selects highest of the 8 inputs In core N/A N/A N/A N/A N/A N/A Highest of the 8 EQ A Train Incore Temperatures.
U.S. Nuclear Regulatory Commission 3F1 204-03 Attachment Page 4 of 4 PWR Data Point Library Reference File Date:
Reactor Unit:
Data Feeder:
NRC ERDS Parameter:
Point ID:
Plant Specific Point
Description:
GenericlCond
Description:
Analog/Digital:
Engineering Units/Digital State:
Engineering Units Conversion:
Minimum Instrument Range:
Maximum Instrument Range:
Zero Point
Reference:
Reference Point Notes:
PROC or SENS:
Number of Sensors:
How Processed:
Sensor Locations:
Alarm/Trip Setpoints:
NI Detector Power Supply Cut-off Power Level:
Ni Detector Power Supply Turn-on Power Level:
Instrument Failure Mode:
Temperature Compensation for DP Transmitters:
Level Reference Leg:
Unique System
Description:
November 23, 2004 CR Crystal River Unit 3 N/A TEMP CORE EX RECL-424 T-incore Maximum Temp B Train Highest Temperature at the Core Exit A
DEGF None 0
2500 N/A N/A P
8 Selects highest of the 8 inputs In core N/A N/A N/A N/A N/A N/A Highest of the 8 EQ B Train Incore Temperatures