RA-18-0261, Response to Request for Additional Information Regarding License Amendment Request on Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints
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Letter Sequence Response to RAI | |
|---|---|
EPID:L-2018-LLA-0203, TSTF-493 (Approved, Closed) | |
Initiation Administration | |
MONTHYEARRA-18-0072, License Amendment Request to Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints2018-07-30030 July 2018
[Table View]License Amendment Request to Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints Project stage: Request RA-18-0171, Supplemental Information for License Amendment Request Regarding Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints2018-09-24024 September 2018 Supplemental Information for License Amendment Request Regarding Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints Project stage: Supplement ML18270A1292018-10-0404 October 2018 Acceptance of Requested Licensing Action Project stage: Acceptance Review RA-18-0261, Response to Request for Additional Information Regarding License Amendment Request on Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints2018-12-27027 December 2018 Response to Request for Additional Information Regarding License Amendment Request on Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints Project stage: Response to RAI ML19225C0692019-09-19019 September 2019 Issuance of Amendment No. 175 Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints Project stage: Approval 2018-07-30 |
| ML18362A415 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 12/27/2018 |
| From: | Hamilton T M Duke Energy Progress |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RA-18-0261 | |
| Download: ML18362A415 (25) | |
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Category:Letter type:RA
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Text
1.Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
2.Does the proposed change create the possibility of a new or different accident from any accident previously evaluated?
3.Does the proposed change involve a significant reduction in a margin of safety?
SHEARON HARRIS - UNIT 1 3/4 3-11 Amendment No. 154 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS FUNCTIONAL UNIT CHANNEL CHECK CHANNEL CALIBRATION ANALOG CHANNEL OPERATIONAL TEST TRIP ACTUATING DEVICE OPERATIONAL TEST ACTUATION LOGIC TEST MODES FOR WHICH SURVEILLANCE IS REQUIRED 1. Manual Reactor Trip N.A. N.A. N.A. SFCP(12) N.A. 1, 2, 3*, 4*, 5* 2. Power Range, Neutron Flux
SFCP (4,6),
SFCP (4,5) SFCP N.A. N.A. 1, 2 b. Low Setpoint SFCP SFCP (4) S/U(1) N.A. N.A. 1***, 2 3. Power Range, Neutron Flux, High Positive Rate N.A. SFCP (4) SFCP N.A. N.A. 1, 2 4. Power Range, Neutron Flux, High Negative Rate N.A. SFCP (4) SFCP N.A. N.A. 1, 2 5. Intermediate Range, Neutron Flux SFCP SFCP (4,5) S/U(1) N.A. N.A. 1***, 2 6. Source Range, Neutron Flux SFCP SFCP (4,5) S/U(1), SFCP(8) N.A. N.A. 2**, 3, 4, 5 7. Overtemperature T SFCP SFCP (11) SFCP N.A. N.A. 1, 2 8. Overpower T SFCP SFCP SFCP N.A. N.A. 1, 2 9. Pressurizer Pressure -- Low SFCP SFCP SFCP N.A. N.A. 1 (16) 10. Pressurizer Pressure -- High SFCP SFCP SFCP N.A. N.A. 1, 2