ML20151P075
| ML20151P075 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 04/30/1988 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20151P063 | List: |
| References | |
| PROC-880430, NUDOCS 8804260082 | |
| Download: ML20151P075 (12) | |
Text
7 t
Duke Power Company McGuire Nuclear Station Catawba Nuclear Station Startup Physics Test Program April 1988 l
8804260082 880414 PDR ADOCK 05000369 P
Startup Physics Test Program I.
Overview This document defines the minimum reload physics test program to be performed on each Duke Power Westinghouse unit.
The purpose of the test program is to provide assurance that the reactor core is loaded correctly and can be operated as designed.
The testing covered in this document nvolves core physics measurements only--mechanical or electrical tests i
such as the control rod trip time test, the initial calibration of instru-mentation, etc. are not addressed.
The startup physics test program is comprised of the following tests (measurements and/or calculations):
1.
Zero Power Test Phase a.
All Rods Out Critical 9eron Concentration b.
Isothermal Temperature Coefficient c.
Control Rod Bank Worth 2.
Power Ascension Test Phase a.
Flux Symmetry Check (Low Power) b.
Core Power Distribution (Intermediate Power) l c.
Core Power Distribution (High Power) l d,
All Rods Out Critical Boron Concentration (High Power) i
, l l
These tests will be performed during each initial startup after refueling.
Additional testing may be done as conditions warrant.
Routine surveil-lance monitoring after successfully completing startup testing is not addressed in this document.
The initial test conditions, test method, and P
acceptance criteria for each test are provided.
II.
Definitions The following terms are defined for the purposes of this document:
RTP.
Rated Thermal Power.
NC.
ARO.
All Rods Out.
ITC.
Isothermal Temperature Coefficient.
The reactivity change per unit temperature change in the fuel / moderator, with the fuel and moderator at the same temperature.
~5 AK/K.
PCM.
Percent Milli-Rho; 10 N
FAH.
The ratio of a particular fuel assembly power to the core average fuel assembly power.
Reactivity Computer.
A digital or analog device that calculates core reactivity by using an external signal which is proportional to the core neutron flux.
N
[ I (aX )2/N]b
- Where, RMS error.
4 i=1 4 = predicted-measured FfH ( r normalized reaction rates) for ith AX operable instrumented location, and N = number of operable instrumented locations, i
f L
2-
III. Zero Power Test Phase '
If any acceptance criterion is exceeded, the test results will be reviewed with regard to the impact on applicable safety analyses and subsequent plant operation.
This review will be performed by cognizant engineers from the Station Reactor Unit or the General Office Nuclear Engineering Section.
A.
All Rods Out Critical Boron Concentration 1.
Initial Test Conditions
- Mode 2, below sensible heat
- NC average temperature 557 2F
- *!C pressure 2235 150 psig
- equilibrium NC boron concentration 2.
Test Method The equilibrium NC boron concentration is measured with control bank 0 near fully withdrawn and core reactivity essentially zero.
Bank D is then fully withdrawn and the re:ulting re-activity is calculated by a reactivity computer.
The calculated reactivity from the withdrawal is converted to an equivalent boron concentration and is then added to the equilibrium NC concentration to obtain the ARO Boron Concentration.
3.
Acceptance Criterion Predicted 150 PPM Boron B.
Isothermal Temperature Coefficient 1.
Initial Test Conditions f
- Mode 2, below sensible heat l
- NC average tenparature 557 12 F
- NC pressure 2235 150 psig
- equilibrium NC boron concentration 2.
Test Method Starting with an equilibrium NC boron concentration, NC tem-perature is changed at least 3 F, at a rate $10 F/hr.
Core reactivity is calculated concurrently using the reactivity computer.
The ITC is determined from the slope of reactivity as a function of temperature, making allowances for rod motion as necessary.
The measurement is repeated with an NC temperature change in the opposite direction and the resulting ITCs are averaged.
3.
Acceptance Criterion Predicted 12 PCM/ F _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
C.
Control Rod Bank Worth 1.
Initial Test Conditions
- Mode 2, below sensible heat
- NC average temperature 157 12 F
- NC pressure 2235 150 psig
- equilibrium NC boron concentration 2.
Test Methods The "rod swap" technique is used to determine the individual bank worths.
Initially, the reference bank is inserted into the core using NC boron dilution, with all other banks withdrawn.
The bank's insertion is made in discrete movements, with the associated reactivity changes calcLlated concurrently using the reactivity computer.
The reference bank integral worth is determined by summing the reactivity changes from each insertion until the bank was fully inserted.
As a verification, this reference bank worth is then compared to the reference bank worth calculated using the NC boron change and predicted differential boron worth.
If these two worths do not agree oy 115%, the reference bank measurement will be repeated before completion of the test.
Beginning with the reference bank at or near 0 steps withdrawn and equilibrium NC boron concentration, the bank to be measured c,
(hereaf ter the "test bank") is partially inserted into the core.
The reference bank is then withdrawn to compensate for the reactivity change.
This sequence continues until the test bank is fully inserted.
The final reference bank position is noted and the test bank is then withdrawn from the core, in similar fashion, versus the insertion of the reference bank or the next test bank.
The change in the reference bank position is used to infer the test bank's integral worth.
The above procedure is repeated until all banks, control and shutdown, are measured.
If a test bank is worth more than the reference bank, the remaining withdrawn worth of the test bank is measuted, using the re-activity computer, with the reference bank fully out.
This additional reactivity is used with the reference bank total worth to infer the test bank integral worth.
3.
Review Criteria a.
Reference bank i10% of predicted, b.
Remaining individual banks 115% or 1100 PCM of predicted (whichever is greater), and c.
Sum of all banks 5, 110% of predicted Note:
If any review criterion is missed, remedial action will be taken per the NRC Safety Evaluation Report for the Duke Power Company Rod Swap Hethodology.
6-
4.
Acceptance Criteria a.
Reference bank 115% of predi:ted b.
Remaining individual banks 130% or 1200 PCM of predicted (whichever is greater), and c.
Sum of all banks > 90% of predicted 7~
IV.
Pcwer Ascension Test Phase If any acceptance criterion is exceeded, the test results will be reviewed with regard to the impact on applicable safety analyses and subsequent plant operation.
This review will be performed by cognizant engineers from the Station Reactor Unit or the General Office Nuclear Engineering Section.
A.
- Flux, y Check - Low Power 1.
Initial Test Conditions
- reactor power between 0 t
' Y,RTP
- NC average temperature T
- 2 I ref NC pressure 2235 150 psig 2.
Test Method A full incore flux map is taken, maintaining reactor power and control bank D position stable-power changing $1%/hr, 5 steps rod motion.
The map analysis includes a comparison of predicted to measured F or normalized reaction rates for all operable q
instrumented locations.
3.
Acceptance Criteria a.
F r n rmalized reaction rates 110% of H
predicted, and b.
Root Mean Square error 50.05 C.
Core Power Distribution - Irtermediate Power 1.
Initial Test Conditions
- reactor power between 50 and 80% RTP
- NC average temperature T 12 F ref
- NC pressure 2235 150 psig 2.
Test Method A full incore flux map is taken, maintaining reactor power and control bank. O position stable-power changing $1%/hr,15 steps rod motion.
The map analysis includes a comparison of predicted to measured F r normalized reaction rates for all operable
)
H instrumented locations.
3.
Acceptance Criteria a.
F r normalized reaction rates 10% of H
predicted, and b.
Root Mean Square error 50.05 l
l
.g_
t
- C.
Core Powe'r Distribution'- High Power t
- 1,
' Initial' Test Conditions
- reactor power above 90% RTP
- NC average temperature T 12 F ref L
- NC pressure 2235 iS0.psig 3
2.
Test Method A full incore flux map is taken, maintaining reactor power and control bank D position stable--power changing 51%/hr,15' steps rod motion.
The map analysis includes a comparison of predicted N
to measured F r normalized reaction rates for all operable AH instrumented locations.
3.
Acceptance Criteria Ffg or normalized reaction rates 110% of a.
1, predicted, and b.
Root Mean Square error 50.05 t
t
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'~
n
,, +
r; 3.E
- l D.
All Rods Out Critical Boron Concentration-- fligh Power
.s
'1.-
Initial Test Conditions
- reactor power above.90% RTP
- NC-average temperature Tref.12 F L
- NC: pressure 2235 150 psig
~
- Control bank D 2200 steps withdrawn or positioned, as necessary, for axial flux difference control or.ontrol rod withdrawal limits
- equilibrium NC boron concentration 2.
Test Method The NC boron concentration is measured with control bank D near fully withdrawn.
The measured value is corrected to account for any reactivity effects due to deviations from the conditions the predicted boron concentration is based on.
It is also adjusted for the measured-to predicted difference determined at the Zero Power AR0 Critical Boron measurement.
3.
Acceptance Criterion Predicted 150 PPM Boron i.;... -
...... -...