ML16343A071
| ML16343A071 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 10/24/2016 |
| From: | Indiana Michigan Power Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16336A263 | List:
|
| References | |
| AEP-NRC-2016-42 | |
| Download: ML16343A071 (3) | |
Text
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
16.1 Table:
13.3-1 Page:
1 of 3 POST CRITICALITY TESTING
SUMMARY
TEST CONDITIONS OBJECTIVES Control Rod Assembly Drop Tests (a)
Cold Shutdown (b)
Hot Shutdown To measure the drop time of control rod assemblies under full flow and no flow conditions Nuclear Design Check Tests Normal control group configurations at hot, zero power To Verify that nuclear design predictions for endpoint boron concentrations, and isothermal temperature coefficient are valid Control Group Calibration All control rod assembly groups at power To verify that nuclear design predictions for control rod assembly group differential worths are valid Power Coefficient Measurement Performed at various per levels To verify that nuclear design predictions for differential power coefficients are valid Automatic Control Systems Checkout Approximately 20 percent of rated power To verify control system response characteristics for the:
(a)
Steam generator level (b)
Control rod assembly automatic control system (c)
Turbine control system
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
16.1 Table:
13.3-1 Page:
2 of 3 POST CRITICALITY TESTING
SUMMARY
TEST CONDITIONS OBJECTIVES Power Range/RTD Instrumentation Calibration During static and/or transient conditions at the following percentages of rated power:
30 percent 50 percent 75 percent 90 percent 100 percent To verify all power range instrumentation consisting of power range nuclear channels, and reactor coolant RTD's were responsive to change in reactor power to intercalibrate these systems Load Swing Test 10 percent step load decrease at 50 and 100 percent power To verify control systems performance as evidenced by plant parameter variations Turbine Trip Turbine trip from power To verify ability of plant to sustain plant trip and bring plant to an orderly hot shutdown Pressurizer Effectiveness Test Hot, shutdown To verify that pressurizer pressure is reduced at the required rate by pressurizer spray actuation Minimum Shutdown Verification Hot, zero power To measure the minimum shutdown boron concentration with one "stuck" control rod assembly Static Control Rod Assembly Drop Test 50 percent of rated power To verify that a single control rod assembly inserted fully or part way below the control bank results in hot channel factors below design values Load Reduction Reduction from 100 percent to 50 percent of rated power at a ramp rate of 5 percent per minute To verify control systems performance as evidenced by plant parameter variations
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
16.1 Table:
13.3-1 Page:
3 of 3 POST CRITICALITY TESTING
SUMMARY
TEST CONDITIONS OBJECTIVES Incore Power Distribution Measurements 50 percent 75 percent 100 percent To verify that nuclear design predicted power distributions are valid for normal control rod patterns and configurations Dynamic Control Rod Assembly DropTest 50 percent of rated power To verify automatic detection of dropped control rod assembly, and subsequent automatic rod withdrawal stop and turbine cutback