ML20198S514
ML20198S514 | |
Person / Time | |
---|---|
Site: | Oconee ![]() |
Issue date: | 05/29/1986 |
From: | Repko R DUKE POWER CO. |
To: | Harold Denton, Stolz J Office of Nuclear Reactor Regulation |
References | |
NUDOCS 8606100451 | |
Download: ML20198S514 (19) | |
Text
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3 I
4 DUKE POWER COMPANY OCONEE NUCLEAR STATION i
OCONEE 3, CYCLE 9 l
STARTUP TESTING REPORT Part I Zero Power Physics Test i
1 Part II Power Escalation Test i
i 1
Prepared By: Regis T. Repko i
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8606100451 860529 PDR ADOCK 05000269 l
P PDR IEAG i
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OCONEE 3 CYCLE 9 Startup Testing Report Table of Contents Part I Zero Power Physics Test Section Page 1.0 Introduction and Summary.
1 2.0 Approach to Critical.
1 3.0 Pre-Physics Measurements 2
4.0 Physics Testing 2
Part II Power Escalation Test Section Page 1.0 Introduction and Summary.
3 2.0 NSS Heat Balance /RC Flow Verification 4
3.0 Core Power Distribution 4
4.0 Power Imbalance Detector Correlation.
5 5.0 Reactivity Coefficients at Power 6
Enclosures 1.0 All Rods Out and Differential Boron Worth Results 2.0 Integral Group Rod Worth Measurements 3.0 Radial Peaking Factor Comparison at 58% FP 3.1 Total Peaking Factor Comparison at 58% FP 3.2 Radial Peaking Factor Comparison at 100% FP 3.3 Total Peaking Factor Comparison at 100% FP 4.0 Core Power Distribution Data Summary at 58% and 100% FP 5.0 Reactivity Coefficients 6.0 NSS Heat Balance /RC Flow Verification l
.. _ - -. _.. _ _,. _ _ _ - -. - - _ _ _ - _ _ _ _ -. _ _ _.. _. _, ~, _ _ _. _ - -. - _ - - ~ _ - -, _ _ _ -. - -..
OCONEE 3 CYCLE 9 START'JP TESTING REPORT PART I ZERO POWER PHYSICS TEST 1.0 Introduction and Summary The Oconee 3 Cycle 9 Zero Power Physics Test (ZPPT) program was conducted on 10/6/85 - 10/7/85 per Station Procedure TT/3/A/0711/09 (Oconee 3 Cycle 9 Zero Power Physics Test). The purpose of this testing was to verify the nuclear parameters upon which the Oconee 3 Cycle 9 safety analysis and Technical Specifications are based.
The ZPPT measurements were made with reactor power controlled between 2.0 x 10-10 amps and 2.8 x 10-8 amps on the intermediate range instrumentation; reactivity insertions were maintained < t 1400 pp.
RCS pressure and temperature were maintained at - 2155 PSIG and ~ 532 F, respectively.
The following nuclear parameters were measured per the ZPPT:
(a) All rods out boron concentration (See Enclosure 1.0)
(b)
Integral rod worth for CRA groups 5, 6, and 7 (See Enclosure 2.0)
(c) Differential boron worth (See Enclosure 1.0)
(d) Temperature and moderator coefficients of reactivity (See Enclosure 5.0)
The plant computer was used to record RC pressure, RC temperature, inter-mediate range NI power levels, and control rod positions.
Reactivity was calculated by the plant computer and output to a chart recorder.
On 10/ /85 at 1020, ZPPT was declared co plete. All acceptance criteria were met.
2.0 Approach to Critical l
The initial RCS heatup following the refueling outage began on 10/5/85.
Ilot shutdown was reached on 10/5/85 at 1020. Source range count rates were recorded and 1/M (inverse multiplication) vs RC temperature plots were generated throughout heatup.
Rod withdrawal for the Control Rod Drive Trip Time Test began at 2340 on 10/6/85.
1/M vs. withdrawn rod worth plots were maintained. The RCS boron concentration had been adjusted to approximately the all-rods-out critical concentration to achieve criticality near the all-rods-out conditions.
At 2130 initial criticality was established with Group 7 at 65% wd, Group 8 at 25% wd and the RCS at 532 F.
Boron was adjusted to achieve ARO conditions.
CR Groups 1-7 were then tripped into the core to complete the trip time test.
Criticality was reestablished on 10/7/85 at 0045.
2-3.0 Pre-Physics Measurements After establishing steady conditions with the reactor critical, the NI overlap and sensible heat determination measurements were performed. From the sensible heat determination, the upper limit on the intermediate range NIs (as indicated on the Control Room Chart) was established for ZPPT.
An on-line reactimeter checkout
- was then performed by making reactivity insertions of about i 500 and 1200 pp and measuring the associated doubling times. These doubling times were input to an off-line reactivity calculation and the results were then compared to the on-line reactivity values.
- NOTE:
An "off-line" reactimeter checkout was performed during RCS heatup. This checkout verified correct calculational and chart recorder response to three test cases in which simulated power ramps were input via floppy discs.
4.0 Physics Testing A.
All Rods Out Boron Concentration Measurement The RCS equilibrium boron concentration was measured with the CR Groups within 1200 pp of the all-rods-out configuration. The control rods were moved to their all-rods-out position and the associated reactivity change was converted to ppmB.
Boron con-centration was then calculated.
B.
Reactivity Coefficient Measurements The temperature coefficient measurement was made with the CR Groups within 1 1200 pp of the all-rods-out configuration while maintaining equilibrium boron concentration in the RCS.
This measurement was made by increasing RCS temperature about 10 F and observing the assoc-iated reactivity change. The change in reactivity was divided by the change in RCS temperature to calcul; ate the temperature coefficient.
The measured temperature coef ficient was corrected for the difference in RCS average test temperature and reference temperature (532 F).
The moderator coef ficient was calculated by subtracting the isothermal doppler coefficient from the measured temperature coefficient.
C.
Control Rod Group Integral Worths and Differential Boron Worth Measurement The worths of Groups 5, 6, and 7 were measured by steadily deborating the RCS and compensating for the resulting positive reactivity ramp by inserting (in discrete steps of ~ - 800 pp) the control rods from 100% wd on Group 7 to 0% wd on Group 5 (with no rod overlap).
The reactivity changes resulting from the discrete control rod insertions were summed for each group to obtain the group integral worth.
The differential boron worth was calculated by dividing the total rod worth inserted during the rod worth measurements by the corresponding change in RCS boron concentration. The initial value for the boron concentration was recorded at critical equilibrium conditions.
The final values of boron concentration and reactivity were recorded as they were approaching steady-state at a rate of less than 1 ppmB/ minute.
PART II POWER ESCALATION TEST 4
1.0 Introduction and Summary The Oconee 3 Cycle 9 Power Escalation Test was performed between 10/8/85 and 12/16/85 per Station Procedure TT/3/A/0811/09. Testing was performed 4
at 12%, 58% and 100% Full Power (FP) to verify the nuclear parameters upon which the Oconee 3 Cycle 9 safety analysis and Technical Specifications are based. The following tests and verifications were performed:
(A) Initial Core Symmetry Check @ 12% FP (B) NSS lieat Balance (including RCS flow measurement at 100% FP) @ 12%
FP, 58% FP, and 100% FP (See Enclosure 6.0)
(C)
Incore Detector Checkout @ 58% FP and 100% FP (D) Core Power Distribution @ 58% FP and 100% FP (See Enclosure 3.0-3.3 and 4.0)
(E) Reactivity Coefficients @ 100% FP (See Enclosure 5.0) l (F) All Rods Out Critical Boron Concentration @ 100% FP The Unit reached 12% FP at 0500 on 10/8/85. Testing at this power level was completed by 1645 that same day.
The Unit reached 58% FP at 1230 on 10/9/85. Testing at this power level was completed by 1140 on 10/10/85. The radial / total peaking factor data met the 100% FP acceptance criteria.
Intermediate Power Testing (70-85% FP) was, therefore, not required according to the Oconee Generic Startup Physics Test Program.
The Unit reached 97% FP at 0930 on 10/11/85.
Incore Detector Checkout
]
data were recorded while power was held at this level to investigate a possible condenser tube leak.
i l
The Unit reached 100% FP at 1440 on 10/11/85, but was shutdown on 10/14/85 l
to investigate RCS leakage.
100% FP was again reached at 1120 on 10/26/85.
Core Power Distribution and Reactivity Coefficient data were recorded on i
}
10/29/85 and 10/31/85, respectively. The acquisition of acceptable NSS
]
Ileat Balance data was delayed by two outages (11/7/85 - 11/16/85 and 11/24/85 - 12/14/85) to investigate high temperature on Main Turbine Bearing
- 1.
These data were obtained on 12/16/85.
f 4
i I
1 l
.. - -. -,.. - -. _ -, _.. -. ~
2.0 NSS Heat Balance /RC Flow Verification Off-line secondary and primary heat balances were perfccmed at 12% (primary j
only), 58% and 100% FP.
These tests verified the accuracy of CTPA, the on-line plant computer program which performs primary and secondary heat balances. The plant computer was used to average heat balance data (flows, temperatures, pressures, etc.) for 15 minutes. This data was input into j
the off-line heat balance programs and the results were compared to CTPA averages for the same period.
At full power, an off-line program was used to calculate RC flow based on a secondary heat balance and measured primary loop enthalpy changes. This i
demonstrated that the RC flow rate was above that assumed in the core design (106.5% design flow) and below that which would cause core lift at 375 F (114.5% design flow).
After establishing the primary flow rate at full power, the plant computer flow constant (used to calculate flow from the primary AP instrumentation) was normalized. Slope and reference flow constants for the AT power indication 4
were then normalized, based on secondary heat balance.
I 3.0 Core Power Distribution i
Core Power Distribution tests were conducted at 58% and 100% FP.
These tests verified that reactor power imbalance, quadrant power tilt, minimum DNBR, maximum LHR and radial / total power peaks did not exceed their respective specified limits. An initial Core Symmetry Check was performed at 12% FP.
However, due to the low power, only reactor power imbalance and quadrant power tilt were verified to be within limits.
Specific checks were made as follows:
Incore imbalance was compared to the error adjusted imbalar.ce LOCA 1
limit curve and was verified to be within specified limits (based on Tech. Spec. 3.5.2.7).
The maximum positive quadrant power tilt was verified to be less than the error adjusted LOCA limit (based on Tech. Spec. 3.5.2.4).
The maximum LKR was verified to be within the LOCA limit maximum allowable heat rate (per Reload Report DPC-RD-2005).
The worst case minimum DNBR and maximum LIIR, when extrapolated to the overpower trip, were verified to be within the fuel melt limits (per Technical Specification 2.1).
This was required for Low Power Testing only.
l Prior to performing the radial and total peaking factor comparisons,
{
PT/0/B/0302/06 (Review and Control of Incore Neutron Detector Signals) was performed to identify bad SPND signals. This test was performed at 58% FP and 100% FP as directed in the Incore Detector Checkout.
l e
m-w y--www --e,-yw m e
e--+-e--v--w---
w---mg
-e-y~n--ny
m.-
- ~
q
,~m.
3 r--
-m mm--
l.*
l The radial and total peaking factors were measured and compared to the predicted values. The following acceptance criteria were applied:
(a) % Deviation = (Predicted - Measured) x 100 < 1 20%
Measured Radial Total ggp, gpp (b) x 100 $ 8.0%
12.0% @ 60% FP Lgp 5.0%
7.5% @ 100% FP Where:
LMP is the largest measured peaking factor LPP is the largest predicted peaking factor (C) The full core root mean square radial peaking factor deviation (RMS) for all core locations with operable incore detector strings was limited as follows:
N
\\
< 0.100 @ 60% FP i =1 0.075 @ 100% FP Where:
PP = Predicted radial peaking factor MP = Measured radial peaking factor N = Total number of operable incore detector strings (Strings 8, 33 and 41 were inoperable for both 58%
and 100% FP)
According to the "Oconee Generic Startup Test Program", the following criteria were verified at 58% FP to allow deletion of the Intermediate Power (70% to 85% FP) Testing:
- '^
LMP - LPP a) x 100 < 5. 0%
7.5%
gp b)
< 0.075 4
4.0 Power Imbalance Detector Correlation 3
The Power Imbalance Detector Correlation Test was performed at 58% FP.
The purpose of this test was to measure the outcore to full incore power imbalance correlation slopes for N1 Channels 5, 6, 7, and 8; and to verify these slopes to be equal to or greater than 0.95.
The incore/outcore imbalance correlation slope for each NI Channel (5-8)
I was determined by a least squares fit of outcore to incore imbalance l
indications. A total of 80 incore imbalance points which ranged between
- 13.94% and + 12.29% were used.
All the slopes were verified to be greater than 0.95.
The correlation slopes for NI Channels (5-8) were calculated to be 0.974, i
1.005, 1.001 and 0.988 respectively. The differential amp gain settings for l
NI Channels (5-8) were 3.60, 3.85, 3.35, and 3.60 respectively.
m
+--++ - - -
r-.
w-9
,wr-9---yy
g
--s i,my--
e--m.-m--------
.m---
a-w
-,---i-,----y-wy--
grw-we py, w..,w+=
--ee.
,me.-,ey,.--,m.-pr%-
-,---ws-5.0 Reactivity Coefficients at Power Data for calculating the doppler and temperature coefficients was taken at ~ 95% FP.
This test verified that the measured and extrapolated reactivity coefficients were conservative relative to the specified values in the FSAR.
The temperature coef ficient of reactivity was determined by varying the average RC temperature (thermal power was held as steady as possible) and measuring the resulting change in Group 7 position. The power doppler coef ficient of reactivity was determined by varying reactor power level (average RC temperature was held as steady as possible) and measuring the resulting change in Group 7 position.
Predicted rod worth data was used with the temperature change and power changes to calculate the temperature and the power doppler coefficients, respectively. Corrections for xenon and temperature / power variations were also made.
OCONEE 3 CYCLE 9
~
STARTUP REPORT ENCLOSURE 1.0 ARO AND DIFFERENTIAL BORON WORTII RESULTS MEASURED PREDICTED ACCEPTANCE PARAMETER CONDITIONS VALUE VALUE DEVIATION CRITERIA All Rods Out Gp 7 @ 100% wd Predicted Boron Conc.
Cp 8 @ 25% wd*
1641 ppm 1607 ppm
+ 34 ppm i 50 ppm Differential 1438 ppm Average
- 0.889 AK/K
- 0.882% AK/K 0.8%**
Measured <-1.33%
Boron Worth During Measurement per 100 ppm per 100 ppm AK/K per 100 ppm and i 15% Deviation luitial:
Cp 7 @ 80.0, Gp 8 @ 25.0 1629 ppm Final:
Cp 4 9 87, Cp 5 @ 0.0, Cp 8 @ 25.0 1241 ppm
- Actual Equilibrium Conditions:
Cp 7 @ 83.0% wil, Gp 8 @ 25.0% wd, B o @ 1631 ppm i
f M Desiation = Predicted - measure <! x 100 measured
OCONEE 3 CYCLE 9 STARTUP REPORT ENCLOSURE 2.0 INTEGRAL GROUP ROD WORTil MEASUREMENTS MEASURED PREDICTED ACCEPTANCE PARAMETER VALUE VALUE DEVIATION
- CRITERION
(% AK/K)
(% AK/K)
(%)
Gp 7 Integral Worth
- 1.145
- 1.165 1.75 1 15% Deviation Gp 6 Integral Worth
- 0.8995
- 0.944 4.95 1 15% Deviation Gp 5 Integral Worth
- 1.4105
- 1.469 4.11 1 15% Deviation Gp 5-7 Integral Worth
- 3.455
- 3.578 3.6 1 10% Deviation
- % Deviation = Predicted - measured x 100 measured
z.y OCONEE 3 CYCLE 9 STARTUP REPORT ENCLOSURE 3.0 Radial Peaking Factors 0 58 % FP 8
9 10 11 12 13 14 15 0.78 1.00 0.92 1.23 1.26 1.27 1.06 0.55 H
0.81 0.99 0.90 1.19 1.23 1.31 1.03 0.52
-3.2
+0.9
+2.6
+3.3
+2.1
-3.0
+3.3
+5.2 0.88 1.06 1.08 1.25 1.09 1.21 0.53 K
0.85 1.06 1.09 1.29 1.14 1.13 0.53
+3.4
+0.1
-0.9
-2.4
-4.4
+6.7
+0.1 0.98 1.18 0.99 1.26 0.97 0.40
[
0.99 1.25 1.04 1.25 0.96 0.40
-0.6
-5.3
-4.5
+0.9
+0.7
+0.6 1.07 1.24 1.15 0.94 M
1.10 1.27 1.17 0.91
-3.0
-2.1
-1.6
+3.1 1.18 1.14 0.54 N
1.08 0.55
+5.1
-1.0 0.57 : Predicted Peak Q
0.58 : Measured Peak
-2.2
- % Deviation NOTE: All values on 1/8th core map have been rounded to two significant digits.,
(Pred.-Meas.\\x100 Meas.
/
Core Conditions for Predicted Core Conditions for Measured Peaking Factors:
Peaking Factors:
Group 5 0 100.0 % WD Group 5 0 99.5 % WD Group 6 0 100.0 % WD Group 6 0 98.9 % WD Group 7 0 92
% WD Group 7 0 93.0 % WD Group 8 0 35
% WD Group 8 0 34.6 % RD Imbalance 0 -4.04 % FP Imbalance 0+5.11 % FP Core Burnup 0 2 EFPD Core Burnup 0 0.9 EFPD Power @ 60 % FP Power 0 58 % FP RMS Radial Peaking Factor Boron Concentration 01259 PPM Deviation = 3.32 %
Incore Tilt: WX XY YZ ZW
-0.26
+0.14 40.33
-0.21 liighest % Deviation = 6.7 % in 1/8th core location K-14.
liighest Measured Radial Peak = 1.31 7. in 1/8th core location 11-13.
LMP-LP P x 100 = +3.0 %
ll!P
- Inoperable Detector
OCONEE 3 CYCLE 9
)
1*
STARTUP REPORT 7
ENCLOSURE 3.1 Total Peaking Factors 0 58% FP 8
9 10 11 12 13 14 15 0.90 1.17 1.07 1.49 1.55 1.60 1.35 0.68 i
H 1.00 1.22 1.09 1.47 1.56 1.62 1.28 0.65
-10.4
-4.1
-1.6
+1.1
-0.5
-1.5
+5.2
+4.2 1
1.01 1.23 1.28 1.55 1.36 1.52 0.67 K
1.04 1.30 1.32 1.55 1.40 1.43 0.66 j
-2.5
-5.1
-2.9
-0.3
-2.7
+6.4
+1.2 i
i 1.14 1.42 1.24 1.58 1.20 0.51 L
1.20 t.53 1.21 1.55-1.20 0.50
-4.7
-6.9
+2.2
+2.2
+0.4
+1.6 1
1.29 1.56 1.47 1.19 i
M 1.33 1.57 1.45 1.15 l
-3.4
-0.7
+1.0
+3.4
't l
1.52 1.45 0.69 i
N 1.37 0.69
+6.1
-0.6 l
l 0.71 : Predicted Peak 1
0 0.72 : Measured reak i
-0.9
- % Deviation 4
NOTE: All values in 1/8th core map have been
[ Pred.-Meas. )x 100 tounded to two significant digits.
\\
Meas.
/
Core Conditions for Predicted Core Conditions for Measured Peaking Factors:
Peaking Factors:
Group 5 0 100.0 % WD Group 5 0 99.5 % WD r
Group 6 0 100.0 % RD Group 6 0 98.9 % WD i
Group 7 0 92
% WD Group 7 0 93.0 % WD Group 8 0 35
% WD Group 8 0 34.6 % WD l
l Imbalance 0 -4.04 % FP Imbalance 0 +5.11 % FP j
Core Burnup G 2 EFPD Core Burnup G 0.9 EFPD j
Power 0 60 % FP Power 0 58 % FP 1
Boron Concentration 0 1259 PPM j
Incore Tilt: WX XY YZ ZW
-0.26
+0.14
+0.33
-0.21 liighest % Deviation = 10.4 % in 1/8th core location 11-8.
]
liighest Measured Total Peak = 1.62 % in 1/8th core location it-13.
LMP-i.PP 4
x 100 = +1.5,.
j ggp t
- Inoperable Detector i
NA.ie --.
OCONEE 3 CYCLE 9 STARTUP REPORI j.
ENCLOSURE 3.2 Radial Peaking Factors @ 100 % FP 1
i 8
9 10 11 12 13 14 15 0.80 1.01 0.93 1.23 1.25 1.26 1.06 0.55 H
0.84 1.02 0.93 1.19 1.17 1.28 1.03 0.54
-4.8
-0.8
+0.4
+3.2
+6.6
-1.4
+3.0
+2.7 4
4 0.89 1.07 1.08 1.25 1.09 1.20 0.54 K
0.88 1.08 1.10 1.26 1.12 1.14 0.54
+1.3
-1.2
-1.4
-0.5
-3.2
+5.6
-0.3 1
1 0.99 1.18 1.00 1.26 0.97 0.41 L
1.02 1.23 1.04 1.25 0.95 0.41
-2.8
-4.6
-4.2
+0.8
+1.2 0.0 j
l 1.07 1.24 1.14 0.94 M
1.10 1.26 1.16 0.91
-2.9
-2.0
-1.4
+3.1 1.17 1.13 0.55 N
1.07 0.55
+5.4 0.0 i
0.57 :
Predicted Peak j
0 0.58 : Measurea Peak
-1.5
- % Deviation
)
NOTE: All values on 1/8th core map have been
.(Pred.-Meas.}x100 rounded to two significant digits.
. Meas.
i l
Core Conditions for Predicted Core Conditions for Measured l
Peaking Factors:
Peaking Factors:
Group 5 @ 100.0 % WD Group 5 @ 99.5 % WD Group 6 @ 100.0 % WD Group 6 0 98.9 % WD Group 7 0 92
% WD Group 7 @ 91.0 % WD i
Group 8 0 35
% WD Group 8 0 30.1 % WD l
Imbalance 0 -10.31 % FP Imbalance @ -5.27 % FP I
Core Burnup @ 4 EFPD Core Burnup @ 9.4 EFPD l
Power @ 100 % FP Power G 100 % FP l
RMS Radial Peaking Factor Baron Concentration @ 1097 PPM Deviation = 2.97 %
Incore Tilt: WX XY YZ ZW j
-0.37
+0.41
+0.17
-0.21 liighest % Deviation = 6.6 % in 1/8th core location 11-12.
)
liighest Measured Radial Peak = 1.28 in 1/8th core location 11-13.
i LMP-LPP x 100 = +1.4 %
LT
- Inoperable Detector
$ E4a
,e, 4,,..
OCONEE 3 CYCLE 9 STARTUP REPORT
].
ENCLOSURE 3.3 Total Peaking Factors @ 100 % FP 8
9 10 11 12 13 14 15 i
0.92 1.19 1.10 1.50 1.56 1.60 1.36 0.69 H
0.93 1.18 1.07 1.39 1.46 1.56 1.28 0.65
-1.4
+1.1
+2.4
+8.2
+6.9
+2.9
+6.2
+6.5 1
1.04 1.26 1.31 1.56 1.38 1.53 0.68 K
1.00 1.25 1.27 1.50 1.35 1.38 0.66
+3.6
+0.6
+2.7
+3.5
+2.0
+11.0
+3.6 1.17 1.44 1.27 1.59 1.21 0.52
[
1.15 1.46 1.23 1.51 1.15 0.51
+1.5
-1.2
+3.6
+5.5
+5.6
+2.4 4
l 1.30 1.57 1.48 1.20 i
M 1.28 1.54 1.44 1.13
+1.8
+1.8
+3.0
+6.6 I
1.53 1.46 0.70 N
1.32 0.68
+10.7
+2.9 0.73 : Predicted Peak 0
0 70 : Measurca Peak 4
+3.7
- % Deviation NOTE: All values on 1/8th core map have (Pred.-Meas.)x 00 been rounded to two significant digits.
Meas.
Core Conditions for Predicted
' Core Conditions for Measured Peaking Factors:
Peaking Factors:
Group 5 0 100.0 % WD Group 5 0 99.5 % WD
[
Group 6 0 100.0 % WD Group 6 @ 98.9 % WD Group 7 0 92
% WD Group 7 0 91.0 % WD Group 8 0 35
% WD Group 8 0 30.1 % WD i
Imbalance 0 -10.31 % FP Imbalance 0 -5.27 % FP Core Burnup @ 4 EFPD Core Burnup @ 9.4 EFPD Power 0 100 % FP Power @ 100 % FP 4
Boron Concentration 01097 PPM Incore Tilt: WX XY YZ ZW
-0.37
+0.41
+0.17
-0.21
{
Highest % Deviation = 11.0 % in.1/8th core location K-14.
l Highest Measured Total Peak = 1.56 % in 1/Sth core location H-13.
~
i x 100 = -2.9%
j LMP
- Inoperable Detector
- "-9
" #M W% @,(
, g p,, g
,_n--
n.
-,,,,._,.- - -.- - _,-,--_.,,~- - - -, _,., - _,.. - -,. _. _. _. -, - - -.,, -,, -..
~ _ _... - _ _ _.. _. _ _. _ _ _ _ _ _ _ _ _ _.. _. _ _
._..__-._g.__.
r i
i OCONEE 3 CYCLE 9 l
STARTUP REPORT i
i ENCLOSURE 4.0 l
f CORE POWER DISTRIBUTION DATA
SUMMARY
AT 58% AND 100% FP TEST PLATEAUS i
r i
j Incore Ti1t Extrapolated
{
Gp6/7/8 Boron Incore WX/XY Extrapolated Worst Case
+
Power Burnup Positions CONC Imbalance YZ/ZW Worst Case MLHR MLHR Level (EFPD)
(% WD)
(PPM)
(% F.P.)
(%)
MDNBR MDNBR (KW/FT)
(KW/FT) i t
-0.26/0.14 I
58 0.90 98.9/93/34.6 1259 5.11 0.33/-0.21 6.21 3.30 6.61 12.00 t
-0.37/0.41 l
100 9.4 98.9/91/30.1 1097
-5.27 0.17/-0.21 4.01 N/A 11.97 N/A I
I k
j NOTE:
The 58% FP case was extrapolated to 105.5% FP.
The 100% FP case was not extrapolated.
U 4
l l
1 1
i i
1 l
l L
i i
OCONEE 3 CYCLE 9 STARTUP REPORT ENCLOSURE 5.0 REACTIVITY COEFFICIENTS MEASURED PREDICTED ACCEPTANCE PARAMETER CONDITIONS VALUE VALUE CRITERION Hot Zero Power T
= 532*F Temperature Gp#7 @ 83% wd 0.003 x 10-4
-0.022 x 10-4 Predicted 1 0.3 x 10-4 Coefficient Gp 8 @ 25.0% wd AK/K per *F AK/K per *F AK/K per *F (ARO) 1631 ppm Hot Zero Power T
= 532*F Predicted 1 0.3 x 10-4 AK/K per *F Moderator Op#7 0 83% wd 0.153 x 10-4 0.172 x 10-4 and Coefficient Gp 8 0 25.0% WD AK/K per *F AK/K per *F Measured < + 0.5 x 10-4 AK/K per *F (ARO) 1631 ppm Hot Full Power BOC T
= 579*F
-1.247 x 10-4
-1.138 x 10-4 Temperature Coefficient more Temperature Coefticient AK/K per F AK/K per *F negative than -0.13 x 10-4 EFPD = 10 Extrapolated to 95% FP AK/K per *F at 95% FP Hot Full Power BOC T
= 579*F
-1.260 x 10-4
-1.151 x 10-4 N/A Temperature Coefficient AK/K Per *F AK/K per *F EFPD = 10 Extrapolated to 100% FP Hot Full Power BOC T
= 579*F
-2.671 x 10-4
-2.862 x 10-4 Temperature Coefficient more Temperature Coefficient AK/K per *F AK/K per *F positive than -3.15 x 10-4 Extrapolated to 100% FP AK/K per *F at 100% FP at EOC (400 EFPD)
Hot Full Power BOC T
= 579 F
-1.399 x 10-4
-1.027 x 10-4 Power Doppler Coef ficient more Power Doppler Coef ficient A/ per FP AK/K per %FP negative than -0.55 x 10-4 EFPD = 10 j
Extrapolated to 100% FP AK/K per %FP at 100%FP
OCONEE 3 CYCLE 9 STARTUP REPORT ENCLOSURE 6.0 NSS IIEAT BALANCE /RC FLOW VERIFICATION Plant Computer Plant Computer Plant Computer Off Line*
Off Line*
Plant Computer Test Plateau On Line Primary On Line Secondary
" Delta Temp" Calculated Calculated RC Power Level Power Level Power Level Primary Secondary Flow Power Level Power Level 12% FP 11.64 N/A 12.19 13.31 N/A 114.6% D.F.
58% FP 57.73 58.40 58.31 59.54 58.37 111.78% D.F.
1001 FP 100.97 99.84 101.73 102.18 99.86 110.82% D.F.
100% FP (after adjusting constants) 99.41 100.03 99.95 N/A N/A 110.99% D.F.
- Calculated by the off-line secondary heat balance program (SECIIT)
I l
DuxE POWEn GOMPANY l*,
P.O. HOX IMll89 CHAML& RTE. N.C. 28242 HAl, H. TUCKEN rei.arssons tws poemsonst (704) 07:>4808 StMIL pa a pasMM7(TM85 May 29, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation j
U.S. Nuclear Regulatory Cosmaission Was.Fington, D.C.
20555 ATTENTION:
Mr. J.F. Stolz. Project Director PWR Project.sirectorate No. 6 i
Subject:
Oconee Nuclear Station, Unit 2 Docket Nos. 50-269, 50-270, 50-287 i
Dear Mr. Denton l
l Please find attached the Startup Test Report for Oconee Unit 3 Cycle 9.
l I
Very truly yours, R2L/W Hal B. Tucker PJN/jgm Attachment xct Dr. J. Nelson Grace, Reg. Admin.
U.S. Nuclear Regulatory Comunission j
Region II 101 Marietta St., NW, Suite 2900 Atlanta, Ca.
30323
's-s\\\\
I
Harold R. D:nton May 29, 1986 a
Page 2 bxc: P.M. Abraham R.H. Clark J.C. Collier ONS D.S. Compton ONS G.
Davenport ONS R.M. Gribble W.A. Haller C.L. Harlin G.P. Horne M.S. Tuclaman N. A. Rutherford P.F. Guill M.A. Haghi W.H. McDowell Group File: OS-801.01 OS-318.09