AEP-NRC-2008-35, Report of Change to Emergency Response Data System Data Point Constant
| ML082620211 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/10/2008 |
| From: | Jensen J Indiana Michigan Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| AEP-NRC-2008-35 | |
| Download: ML082620211 (3) | |
Text
INDIANA MICHIGAN POWER Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106 aepcom September 10, 2008 AEP-NRC-2008-35 10 CFR Part 50, Appendix E Docket No: 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-P1-17,
Washington, D. C. 20555-0001
SUBJECT:
Donald C. Cook Nuclear Plant Unit 1 Report of Change to Emergency Response Data System Data Point Constant
Dear Sir or Madam:
Pursuant to 10 CFR Part 50, Appendix E, Paragraph VI.3.a, Indiana Michigan Power Company, the licensee for Donald C. Cook Nuclear Plant Unit 1, is submitting notification of a change to a data point identified in the Emergency Response Data System (ERDS) Data Point Library. The affected ERDS data point, U1612, indicates total reactor coolant system (RCS) flow. The data point was changedlto reflect a new constant for RCS flow rate per reactor coolant pump.
Total RCS flow data (data point U1612) is the product of a constant value for RCS flow rate per pump (data point K0200) and a variable data value for normalized RCS flow (data point U0570).
The RCS flow constant has been revised from 94,971 gpm per loop to the calculated design value of 94,862 gpm per loop. The plant process computer database has been changed to reflect the revised value.for constant point K0200..
The revised Data Point Library sheet for the Total RCS Flow data point, U1612, is provided as an enclosure to this letter.
This letter contains no new or revised commitments.
Should you have any questions, please contact John A. Zwolinski,,Manager of Regulatory Affairs, at (269) 466-2478.
y,I Joseph N.Jensen Site Support.Services Vice-President MCS/rdwe Enclosure.
'd;
U. S. Nuclear Regulatory Commission Page 2 c:
T. A. Beltz - NRC Washington, DC J. L. Caldwell - NRC Region III K. D. Curry - AEP Ft. Wayne J. T. King - MPSC MDEQ - WHMD/RPS NRC Resident Inspector AEP-NRC-2008-35
Enclosure to AEP-NRC-2008-35 Em DATE:
REACTOR UNIT:
NRC ERDS PARAMETER:
POINT ID:
PLANT SPEC POINT DESC:
GENERIC/COND DESC:
ANALOG/DIGITAL:
ENG UNITS/DIG STATES:
ENG UNITS CONVERSION:
MINIMUM INSTR RANGE:
MAXIMUM INSTR RANGE:
ZERO POINT
REFERENCE:
REFERENCE POINT NOTES:
PROC OR SENS:
NUMBER OF SENSORS:
HOW PROCESSED:
SENSOR LOCATION:
ALARM/TRIP SET POINTS:
NI DETECTOR POWER SUPPLY TURN-OFF POWER LEVEL:
NI DETECTOR POWER SUPPLY TURN-ON POWER LEVEL:
INSTRUMENT FAILURE MODE:
TEMPERATURE COMPENSATION FOR DP TRANSMITTER:
LEVEL REFERENCE LEG:
UNIQUE SYSTEM DESC:
ergency Response Data System Data Point Library September 12, 2008 CK1 N/A CORE FLOW U1612 TOTAL REACTOR COOLANT FLOW Page 1 A
GPM N/A 0.0 397760.0 N/A 94862 GPM PER LOOP P
12 AVERAGE PER LOOP, SUM OF 4 LOOPS COLD LEG SUCTION LINE TO RCP'S N/A N/A N/A N/A N
N/A NFP-210, NFP-211, NFP-212, NFP-220, NFP-221, NFP-222 NFP-230, NFP-231, NFP-232, NFP-240, NFP-241, NFP-242