ML17046A557
Text
Nuclear Design Check Tests (1)
Rod and Boron Worth Measurements during Boron Dilution and Addition (1)
RCCA Pseudo Ejection at Zero Power (1)
Minimum Shutdown Verification and Stuck Rod Worth Measurements (1)
Calibration of Steam and Feedwater Flow Instrumentation at Power Natural Circulation (Unit 2 only)
SGS-UFSAR Conditions Hot zero power Hot zero power Hot zero power Hot zero power Hot zero power and 30%, 50%,
75%, and 100%
<7%
TABLE 14.4-1 PHASE III POST CRITICALITY TESTING
SUMMARY
Objectives To verify that nuclear design predictions for endpoint boron concentration, temperature coefficient and normal flux distribution are valid.
a) To determine differential and integral worth of control banks b) To determine differential boron worth over range of control bank motion.
To determine worth of most reactive RCCA in the rod configuration assumed in the accident analysis.
To measure the minimum shutdown boron concentration with one stuck control rod assembly and measure integral worth of all rod banks.
To calibrate feedwater and steam flow instruments for proper indication.
To demonstrate natural circulation heat removal capability and provide plant response information, baseline data for specific plant characteristics, and supplemental operator training.
1 of 5 Comments SAR criteria applicable
\\
SAR criteria applicable The "just critical" boron concentration and flux distribution also obtained with the most reactive RCCA withdrawn Verify stuck control rod ~ssembly shutdown criteria Verify correct inputs to control systems Testing successfully completed between 8/23 and 8/29/80 Revision 12 July 22, 1992
Test Chemistry and Radiochemistry Tests Radiation Monitoring and Shielding Evaluation Effluent Monitoring Systems Power Coefficient and Integral Power Defect Measurement( I)
Dynamic Automatic Steam Dump Control Automatic Steam Generator Level Control Turbine Overspeed Trip SGS-UFSAR Conditions Specific analyses at low power and 30%,
SO%, 7S%, and 100% power Low power and during power escalation at 30%, 70%, 100%
As early in power operation as possible and repeated after operation at 30%,
SO%, 75%, and 100% power Various power levels up to 100% power
<10% power 30% power Approximately 10% power TABLE 14.4-1 (Cont)
Objectives To demonstrate ability to control water quality.
To measure and record radiation levels in accessible areas of the nuclear plant.
To verify calibration of effluent monitors by lab analysis of radioactive waste samples.
To verify validity of nuclear design predictions for differential power coefficient and determine the integral power defect.
To demonstrate proper operation of steam dump control and verify setpoints.
To demonstrate satisfactory performance of the automatic steam generator level control system.
To verify that turbine overspeed trip setpoint is correct.
2 of 5 Comments Ability to control water quality verified at each power level Radiation levels were verified to be within the shielding design criteria Verification of calibration of plant effluent monitors SAR criteria applicable Steam dump operation satisfies design criteria System maintained steam generator level during simulated transient Revision 6 February 1S, 1987
Test tu'ibine*.*****can-ti'ol System Checkout and Startup Adjustments of Reactor Control System Automatic Reactor Control within design requirements Steam Generator Moisture Incore/Excore Detector (l)
Nuclear and Instrumentation Calibration and Thermal Power Measurement{1}
Static RCCA and RCCA Below Bank Position Measurements(1)
SGS-UFSAR Conditions o%; 3tr%*, so%,
75%, 100%
30% power 75%,
100%
, and 75% power 30%, 50%, 75%,
90%, and 100%
power 50% power TABLE 14.4-1 {Cant}
Objectives befines turbine steairiline :i..niet.pressure.
characteristic curve. Reprograms rod control system Tavg program for designed stm press.
To*verify reactor characteristics.
To determine average total moisture steam state To determine at rod from a} To determine of power range detectors.
b) To calibrate power range channels to reflect thermal power level.
c) To obtain nuclear instrument d) To obtain data for and a) To rod worth and hot channel factors assumed in SAR of effects on DNB.
b) To demonstrate of a RCCA bank 3 of 5 Comments caiibrated cont.r*c:,:i 1
systems in accordance with design specifications Calculated steam had
'limits Calibrate instruments in accordance with SAR criteria Revision 21 December 6, 2004
RCCA Pseudo 50% power Ejection and RCCA above Bank Position Measurements(l)
Load Swing Tests Load Reduction Tests Shutdown from outside Control Room Loss of Offsite Power Generator Trip Rod and Plant Trip (2)
SGS-UFSAR Design step changes at power levels of 30%, 75,
and 100%
(50% reduction of load at 75%,
100 power) 10% power 10% power 10 0% p01-ver 50% power TABLE 14.4-1 (Cant) a) To verify ected-rod worth and hot channel factors assumed in SAR.
b) To demonstrate of a s RCCA above bank position or ejected.
Demonstrate changes.
To demonstrate changes.
response to des response to des small load large-load from outside control room, veri maintain hot shutdown conditions from outside control room.
To demonstrate response upon occurrence of a loss of offsite power.
To determine any turbine and to demonstrate plant response to a trip from 100% power.
To demonstrate plant response and control system behavior to a two-rod and subsequent plant to demonstrate the of the rate trip circuitry.
4 of 5 SAR criteria applicable Plant parameter variations are within design limits Plant variations are within limits Plant can be controlled within limits from outside control room Plant parameter variations are within design limits Plant parameter variations are within limits Plant parameter variations are within design limits Revision 25 October 26, 2010 I
NSSS Acceptance Test Conditions 100% power TABLE 14.4-1 (Cant)
Objectives To demonstrate satisfactory operation of the NSSS during a 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> full power run.
(1) These tests verified that core performance is within design Comments Plant parameter variations are within design limits (2) Salem NRC License Amendment 278-261 (Salem 1 and the removal of the Flux Rate Trip.
This function was disabled by the greater value than the Maximum SGS-UFSAR Rate expected (per change (DCP) 80094424).
The Negative Flux Rate has removed from both Unit 1 and 2 per DCPs 80097106 and 80099680.
5 of 5 Revision 26 May 21, 2012 I