ML043350359

Notification of Data Point Library Changes for the Emergency Response Data System (ERDS)

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

-

www.exeloncorp.corm AmnerGen SM At;ierGen Energy Company, LLC An Exelon Company Oyster Creek US Route 9 South, P.O. Box 388 Forked River, NJ 08731-0388 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 11/16/2004, respectively.

The FIVE data point revisions addressed in this change notification are as follows:

NRC ERDS Parameter Point ID Change Implemented NL HBMWTH October 28,2004 Main FD Flow HB_FWFLO October 28,2004 RCIC Flow HB_RCFLO October 28,2004 Stab Class DT150A October 28,2004 NI Power Rng APRMPWR 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: 11/16/04 REACTOR UNIT: OYl DATA FEEDER: N/A NRC ERDS PARAMETER: NI Power Rng POINT ID: APRMPWR PLANT SPEC POINT DESC.: Average APRM Power GENERIC/COND DESC.: Nuclear Instruments, Power Range ANALOG/DIGITAL: A ENGR UNITS/DIG STATES:  % Power ENGR UNITS CONVERSION: Calculated MINIMUM INSTR RANGE: 0 MAXIMUM INSTR RANGE: 150 ZERO POINT

REFERENCE:

N/A REFERENCE POINT NOTES: N/A PROC OR SENS: P NUMBER OF SENSORS: 8 HOW PROCESSED: Average of 8 APRM signals SENSOR LOCATIONS: Rx Core (2 per quadrant of reactor core)

ALARM/TRIP SET POINTS: (1.47 X 104) W + 20.8 for recirculation flow

< 48% rated I (0.95 X 104) W + 60.0 for recirculation flow 2 48% rated

= 117.95 for recirculation flow 2 100%

UNIQUE SYSTEM DESC.:

JW= CORE FLOW IN LBM/HR PCI 150.116

PAGE: 13 OF 44 DATA POINT LIBRARY REFERENCE FILE DATE: 10/28/04 REACTOR UNIT: OYI DATA FEEDER: N/A NRC ERDS PARAMETER: NL POINT ID: HBMWTH I

PLANT SPEC POINT DESC.: Core Thermal Power GENERIC/COND DESC.: Core Thermal Power ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: MWT ENGR UNITS CONVERSION: Calculated MINIMUM INSTR RANGE: N/A MAXIMUM INSTR RANGE: N/A ZERO POINT

REFERENCE:

N/A REFERENCE POINT NOTES: N/A PROC OR SENS: N/A NUMBER OF SENSORS: 11 HOW PROCESSED: Calculated SENSOR LOCATIONS: N/A ALARM/TRIP SET POINTS: N/A UNIQUE SYSTEM DESC.: Calculation of steady state thermal power based primarily on feedwater flow.

PCI 150.116

PAGE: 14 OF 44 DATA POINT LIBRARY REFERENCE FILE DATE: 10/28/04 REACTOR UNIT: OYI DATA FEEDER: N/A NRC ERDS PARAMETER: Main FD Flow POINT ID: HBFWFLO I PLANT SPEC POINT DESC.: Total Feedwater Element Flow Smoothed GENERIC/COND DESC.: Feedwater Flow into the Reactor System ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: LBM/HR I ENGR UNITS CONVERSION: Square Root MINIMUM INSTR RANGE: 0 MAXIMUM INSTR RANGE: 8,000,000. LBMIHR I

ZERO POINT

REFERENCE:

N/A REFERENCE POINT NOTES: N/A PROC OR SENS: S NUMBER OF SENSORS: I HOW PROCESSED: 60 second average SENSOR LOCATIONS: Downstream of the feedwater strings header and upstream of the reactor ALARM/TRIP SET POINTS: None UNIQUE SYSTEM DESC.: This signal is independent of the feedwater control system.

PCI 150.116

PAGE: 15 OF 44 DATA POINT LIBRARY REFERENCE FILE DATE: 10/28/04 REACTOR UNIT: OYI DATA FEEDER: N/A NRC ERDS PARAMETER: RCIC Flow POINT ID: HBRCFLO I

PLANT SPEC POINT DESC.: Total Recirc Flow (calculated)

GENERIC/COND DESC.: Reactor Core Isolation Cooling Flow ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: GPM ENGR UNITS CONVERSION: Linear MINIMUM INSTR RANGE: 0 MAXIMUM INSTR RANGE: 200000.0 ZERO POINT

REFERENCE:

N/A REFERENCE POINT NOTES: N/A PROC OR SENS: P NUMBER OF SENSORS: 5 HOW PROCESSED: Add SENSOR LOCATIONS: Downstream of recirc loop discharge valves ALARM/TRIP SET POINTS: N/A UNIQUE SYSTEM DESC.: Total recirc flow signal is also provided to the APRM flow bias unit in the neutron monitoring system.

PCI 150.116

PAGE: 42 OF 44 DATA POINT LIBRARY REFERENCE FILE DATE: 10/28/04 REACTOR UNIT: OYI DATA FEEDER: N/A NRC ERDS PARAMETER: Stab Class POINT ID: DT150A I PLANT SPEC POINT DESC: (150'L33) 15-Min Avg Delta T A GENERIC/COND DESC: Air Stability at the Reactor Site ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: Degrees Fahrenheit/l 17' ENGR UNITS CONVERSION: Volts to Degrees/I 17' MINIMUM INSTR RANGE: 0 Volts MAXIMUM INSTR RANGE: 5 Volts ZERO POINT

REFERENCE:

N/A REFERENCE POINT NOTES: N/A PROC OR SENS: S NUMBER OF SENSORS: 1 HOW PROCESSED: N/A SENSOR LOCATIONS: Forked River Meteorological Tower ALARM/TRIP SET POINTS: N/A UNIQUE SYSTEM DESC.: Forked River Meteorological Tower - DT1 50 PC1150.116