ML043350359
| ML043350359 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/23/2004 |
| From: | Swenson C AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2130-04-20287 | |
| Download: ML043350359 (7) | |
Text
AmnerGen SM At;ierGen Energy Company, LLC Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ 08731-0388 www.exeloncorp.corm An Exelon Company 10 CFR 50, Appendix E, Sec V1.3.a November 23, 2004 2130-04-20287 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 - 0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219
Subject:
Notification of Data Point Library Changes for the Emergency Response Data System (ERDS)
Pursuant to 10 CFR 50, Appendix E, Sec VI.3.a., this letter is to notify you of changes to our Emergency Response Data System (ERDS) data point library made on October 28, 2004 and November 16,2004. Enclosed are copies of revised pages of the Oyster Creek Data Point Library Reference File annotated by revision bars to indicate changes dated 10/28/2004 AND 1 1/16/2004, respectively.
The FIVE data point revisions addressed in this change notification are as follows:
NRC ERDS Parameter Point ID Change Implemented NL Main FD Flow RCIC Flow Stab Class NI Power Rng HBMWTH HB_FWFLO HB_RCFLO DT150A APRMPWR October 28,2004 October 28,2004 October 28,2004 October 28,2004 November 16, 2004 As part of the installation of a new Plant Computer System, the System Requirements Specification for Oyster Creek ERDS, OC-PPC-SRS-001 4 was created to control future changes to the ERDS Data Point Library. During its development it was recognized that several Alarm/Trip setpoints have been revised in the past, but not updated in the ERDS Data Point Library. A revised copy of OC-PPC-SRS-0014 in its entirety will be forwarded to the NRC to replace the existing document, VM-PC-1 150, Appendix 1-16.
If any further information or assistance is needed, please contact David Fawcett at 609-971-4284.
KI-0
2130-04-20287 Page 2 Sincere C. N. Swenson Vice President, Oyster Creek Generating Station CNS/DIF
Enclosure:
cc:
S. J. Collins, Administrator, USNRC Region I P. S. Tam, USNRC Project Manager, Oyster Creek R. J. Summers, USNRC Senior Resident Inspector, Oyster Creek K. Tosch, Chief NJDEP Bureau of Nuclear Engineering File No. 04012
PAGE: 9 OF 44 DATA POINT LIBRARY REFERENCE FILE DATE:
REACTOR UNIT:
DATA FEEDER:
NRC ERDS PARAMETER:
POINT ID:
PLANT SPEC POINT DESC.:
GENERIC/COND DESC.:
ANALOG/DIGITAL:
ENGR UNITS/DIG STATES:
ENGR UNITS CONVERSION:
MINIMUM INSTR RANGE:
MAXIMUM INSTR RANGE:
ZERO POINT
REFERENCE:
REFERENCE POINT NOTES:
PROC OR SENS:
NUMBER OF SENSORS:
HOW PROCESSED:
SENSOR LOCATIONS:
ALARM/TRIP SET POINTS:
1 1/16/04 OYl N/A NI Power Rng APRMPWR Average APRM Power Nuclear Instruments, Power Range A
% Power Calculated 0
150 N/A N/A P
8 Average of 8 APRM signals Rx Core (2 per quadrant of reactor core)
(1.47 X 104) W + 20.8 for recirculation flow
< 48% rated (0.95 X 104) W + 60.0 for recirculation flow 2 48% rated
= 117.95 for recirculation flow 2 100%
I UNIQUE SYSTEM DESC.:
JW= CORE FLOW IN LBM/HR PCI 150.116
PAGE: 13 OF 44 DATA POINT LIBRARY REFERENCE FILE DATE:
REACTOR UNIT:
DATA FEEDER:
NRC ERDS PARAMETER:
POINT ID:
PLANT SPEC POINT DESC.:
GENERIC/COND DESC.:
ANALOG/DIGITAL:
ENGR UNITS/DIG STATES:
ENGR UNITS CONVERSION:
MINIMUM INSTR RANGE:
MAXIMUM INSTR RANGE:
ZERO POINT
REFERENCE:
REFERENCE POINT NOTES:
PROC OR SENS:
NUMBER OF SENSORS:
HOW PROCESSED:
SENSOR LOCATIONS:
ALARM/TRIP SET POINTS:
UNIQUE SYSTEM DESC.:
10/28/04 OYI N/A NL HBMWTH Core Thermal Power Core Thermal Power A
MWT Calculated N/A N/A N/A N/A N/A 11 Calculated N/A N/A Calculation of steady state thermal power based primarily on feedwater flow.
I PCI 150.116
PAGE: 14 OF 44 DATA POINT LIBRARY REFERENCE FILE DATE:
REACTOR UNIT:
DATA FEEDER:
NRC ERDS PARAMETER:
POINT ID:
PLANT SPEC POINT DESC.:
GENERIC/COND DESC.:
ANALOG/DIGITAL:
ENGR UNITS/DIG STATES:
ENGR UNITS CONVERSION:
MINIMUM INSTR RANGE:
MAXIMUM INSTR RANGE:
ZERO POINT
REFERENCE:
REFERENCE POINT NOTES:
PROC OR SENS:
NUMBER OF SENSORS:
HOW PROCESSED:
SENSOR LOCATIONS:
ALARM/TRIP SET POINTS:
UNIQUE SYSTEM DESC.:
10/28/04 OYI N/A Main FD Flow HBFWFLO Total Feedwater Element Flow Smoothed Feedwater Flow into the Reactor System A
LBM/HR Square Root 0
8,000,000. LBMIHR N/A N/A S
I 60 second average Downstream of the feedwater strings header and upstream of the reactor None This signal is independent of the feedwater control system.
I I
I PCI 150.116
PAGE: 15 OF 44 DATA POINT LIBRARY REFERENCE FILE DATE:
REACTOR UNIT:
DATA FEEDER:
NRC ERDS PARAMETER:
POINT ID:
PLANT SPEC POINT DESC.:
GENERIC/COND DESC.:
ANALOG/DIGITAL:
ENGR UNITS/DIG STATES:
ENGR UNITS CONVERSION:
MINIMUM INSTR RANGE:
MAXIMUM INSTR RANGE:
ZERO POINT
REFERENCE:
REFERENCE POINT NOTES:
PROC OR SENS:
NUMBER OF SENSORS:
HOW PROCESSED:
SENSOR LOCATIONS:
ALARM/TRIP SET POINTS:
UNIQUE SYSTEM DESC.:
10/28/04 OYI N/A RCIC Flow HBRCFLO Total Recirc Flow (calculated)
Reactor Core Isolation Cooling Flow A
GPM Linear 0
200000.0 N/A N/A P
5 Add Downstream of recirc loop discharge valves N/A Total recirc flow signal is also provided to the APRM flow bias unit in the neutron monitoring system.
I PCI 150.116
PAGE: 42 OF 44 DATA POINT LIBRARY REFERENCE FILE DATE:
REACTOR UNIT:
DATA FEEDER:
NRC ERDS PARAMETER:
POINT ID:
PLANT SPEC POINT DESC:
GENERIC/COND DESC:
ANALOG/DIGITAL:
ENGR UNITS/DIG STATES:
ENGR UNITS CONVERSION:
MINIMUM INSTR RANGE:
MAXIMUM INSTR RANGE:
ZERO POINT
REFERENCE:
REFERENCE POINT NOTES:
PROC OR SENS:
NUMBER OF SENSORS:
HOW PROCESSED:
SENSOR LOCATIONS:
ALARM/TRIP SET POINTS:
UNIQUE SYSTEM DESC.:
10/28/04 OYI N/A Stab Class DT150A (150'L33) 15-Min Avg Delta T A Air Stability at the Reactor Site A
Degrees Fahrenheit/l 17' Volts to Degrees/I 17' 0 Volts 5 Volts N/A N/A S
1 N/A Forked River Meteorological Tower N/A Forked River Meteorological Tower - DT1 50 I
PC1150.116