ML20212G104
| ML20212G104 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/06/1987 |
| From: | Hastings P, Tucker H DUKE POWER CO. |
| To: | Harold Denton, Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8701120272 | |
| Download: ML20212G104 (18) | |
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DUKE POWER COMPANY OCONEE NUCLEAR STATION OCONEE 2, CYCLE 9 STARTUP TESTING REPORT ,
Part I Zero Power Physics Test Part II Power Escalation Test Prepared By: Peter S. Hastings 8701120272 870106 PDR ADOCK 05000270 P PDR
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OCONEE 2 CYCLE 9 Startup Testing Report Table of Contents Part I Zero Power Physics Test Section Py 1.0 Introduction and Summary . . . . . . . . . . .. . . . . . . . I 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 IMPT 3.1 Total Peaking Factor Comparison at IMPT 3.2 Radial Peaking Factor Comparison at FPT 3.3 Total Peaking Factor Comparison at FPT 4.0 Core Power Distribution Data Summary at IMPT and FPT 5.0 Reactivity Coefficients 6.0 NSS Heat Balance /RC Flow Verification
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OCONEE 2 CYCLE 9 STARTUP TESTING REPORT PART I ZERO POWER PHYSICS TEST
- 1.0 Introduction and Summary The Oconee 2 Cycle 9 Zero Power Physics Test (ZPPT) was conducted on 10/17/86 per Station Procedure TT/2/A/0711/09. The purpose of this testing was to verify the nuclear parameters upon which the Oconee 2 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 2.1 x 10-7 amps on the intermediate range instrumentation; '
reactivity insertions were maintained < i 1800 pp. RCS pressure and temperature were maintained at ~ 2155 psig and ~ 532 F, respectively.
The following nuclear parameters were measured:
(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 10/17/86 at 1855, ZPPT was declared complete. All acceptance criteria were met.
2.0 Approach to Critical The initial RCS heatup following the refueling outage began on 10/10/86.
Hot shutdown was reached on 10/16/86 at 1241. 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 2045 on 10/16/86. 1/M vs. withdrawn rod worth plots were maintained. The RCS boron concentration had been adjusted to approximately the all-rods-out critical concentration, but CR Group 7 reached 100% ud without criticality being achieved. Groups 1-7 were tripped at 2340 to complete this test.
The trip time test was preformed at 531.3"F and 2152 psig, and the maximum rod trip time was 1.379 seconds.
2-Based on the 1/M plots generated during the initial rod pull, a boron adjustment was calculated and made to allow for criticality at all-rods-out.
CR Groups 1-7 were withdrawn again beginning at 2350 on 10/16/86. Criti-cality was established on 10/17/86 at 0345 with Group 7 at 84% wd and Group 8 at 25% wd.
3.0 Pre-Physics Measurements After establishing steady conditions with the reactor critical, NI_ overlap was observed and recorded, and the point of adding sensible heat was determined. From the sensible heat determination, the upper testing limit on the intermediate range NIs (as indicated on the Control Room Chart) was established for ZPPT.
An on-line OAC reactimeter checkout
- was then performed by making teac-tivity insertions of about i 500, i 1200, and i 1800 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 OAC 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 1775 pp of CR Group 7 inserted (80% wd) and with CR Group 8 at 25% wd. The 4
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 while maintaining equilibrium boron concentration in the RCS, with CR Group 7 with-drawn to 82% wd (about 1600 pp inserted worth) and with CR Group 8 at 25% wd. This measurement was made by varying RCS temperature by about 10*F and observing the associated reactivity change. The change in reactivity was divided by the change in RCS temperature to calculate the temperature coefficient. The measured temperature coefficient was corrected for the difference in RCS' average test temperature and reference temperature (532'F). The moderator coefficient was calculated by subtracting the calculated isothermal Doppler coefficient from the measured temperature coefficient.
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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 80 pp/ minute.
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PART II POWER ESCALATION TEST 1.0 Introduction and Summary The Oconee 2 Cycle 9 Power Escalation Test was performed between 10/17/86 and 10/31/86 per Station Procedure TT/2/A/0811/09. Testing was performed at 14%, 72% and 92% Full Power * (FP) to verify the nuclear parameters upon which the Oconee 2 Cycle 9 safety analysis and Technical Specifications are based. The following tests and verifications were performed:
(A) Initial Core Symmetry Check @ 14% FP (B) NSS IIeat Balance (including RCS flow measurement at 93% FP) @ 14%
FP, 72% FP, and 92% FP (See Enclosure 6.0)
(C) Incore Detector Checkout @ 72% FP and 92% FP (D) Power Imbalance Detector Correlation Slope Measurement @ 72% FP (E) Core Power Distribution @ 72% FP and 92% FP (See Enclosures 3.0-3.3 and 4.0)
(F) All Rods Out Critical Boron Concentration @ 92% FP The unit reached 14% FP at 0305 on 10/18/86. Testing at this power level
) was completed by 0605 that same day.
I The unit reached 72% FP at 1050 on 10/20/86. Testing at this power level was completed by 1430 on 10/21/86.
The unit tripped as a result of liigh Steam Generator Levels on 10/23/86, and recovered to 93% FP at ~1900 on 10/24/86*. The All Rods Out Boron Comparison at Power (PT/2/A/0800/03) was performed on 10/28/86. The Incore Detector Checkout was completed on 10/29/86. The NSS IIeat Balance, including verification of RC Flow Constants (PT/0/A/0275/03), was completed on 10/30/86. The Core Power Distribution Test was completed on 10/31/86.
2.0 NSS Ileat Balance /RC Flow Verification Off-line secondary and primary heat balances were performed at 14% (primary only), 72% and 92% 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 the off-line heat balance programs and the results were compared to CTPA averages for the same period.
- NOTE: The unit remains limited to ~ 43% FP by liigh Steam Generator f.evels.
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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 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 390*F (116.5% 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' were then normalized, based on secondary heat balance.
3.0 Core Power Distribution Core Power Distribution tests were conducted at 72% and 92% 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 14% FP.
Specific checks were made'as follows:
Incore imbalance was compared to the error adjusted imbalance LOCA 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 LHR was verified to be within the LOCA limit maximum allowable heat rate (per Reload Report DPC-RD-2007).
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 extrapolation was not required for Low Power Testing.
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 14% FP as part of Core Symmetry Verification, and at 72% FP and 92% FP as directed in the Incore Detector Checkout.
The radial and total peaking factors were measured and compared to the predicted values at 72% and 92% FP. The following acceptance criteria were applied:
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(a) % Deviation = # " '" ,#
.leasured x 100 3 t 15% for radf al peaking factors i 20% for total peaking tactors (recommended maximum deviation -
not an acceptance criterton)
(b) Largest Peak % deviation = b" p x 100 1 + 5.0% for radial peaking factors
+ 7.5% for total peaking factors j 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:
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) n l RMS = I [(PPg - HPg )2] 5 7.5%
i=1 ,3 i
Where: PP = Predicted radial peaking factor i
MP = Heasured radial peaking factor ,
n = Total number of operable incore detector strings (Strings 33, 39 and 48 were inoperable for both 72%
f and 92% FP) 4.0 Power Imbalance Detector Correlation The Power Imbalance Detector Correlation Test was performed at 71% FP.
The purpose of this test was to measure the outcore to full incore power imbalance correlation slopes for NI 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) 4 was determined by a least squares fit of outcore to incore imbalance i indications. A total of 22 incore imbalance points which ranged between l
- 9.95% and + 7.40% 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 1.060, i 1.058, 1.056, and 1.091 respectively. The differential amp gain settings for NI Channels (5-8) were 3.85, 4.00, 3.77 and 3.79 respectively.
5.0 Reactivity Coefficients at Powei Per the Oconee Generic Startup Physics Test Program (May 1986 reissue), ;
testing for measurement of reactivity coefficients at power is no longer required.
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] OCol6EE 2 CYCLE 9 '
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STARTUP 1:EPol:T ENCLOSURE 1.0 i
i ARO AND DIFFERENTIAL LORON WORTil RESULTS i
i i 11EASURED PREDICTED ACCEPTANCE PARAf1ETER CONDITIONS VALUE VALUE DEVIATION CRITERIA j! All Ro,Is out Gp 7 @ 100% wd Predicted i horon Conc. Cp 8 @ 25% wd2 1535 ppmil 1555 ppmB - 20 ppmB 1 50 ppmB -
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, Differential 1326 ppmB Average - 1.004% Ak/k - 0.887% Ak/k - 11.65% Measured more posi-q I;oron Worth During Heasurement per 100 pparB per 100 ppmB tive than -1.33% Ak/k i
per 100 ppmB and Initial: 1 15% deviation from i Gp 7 @ 82% wd, Cp 8 @ 25% wd predicted j e516 ppm 4
i Final:
! Cp 4 @ 68% wd, Gp 5 @ 0% wd, l Cp 8 @ 25% wd j 1136 ppm j ___ _ ___
- Actual ?!easured Conditions: Gp 7 @ 80% ud, Gp 8 @ 25.0% wd, 1515 ppmB
] MC Devistion = Predicted - measured x 100 measured 1
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OCONEE 2 CYCLE 9 , )
1 STARTUP REPORT l i
ENCLOSURE 2.0 !
l' INTEGRAL GROUP ROD WORTH !!EASUREMENTS MEASURED PREDICTED ACCEPTANCE PARAMETER VALUE VALUE DEVIATION
- CRITERION
(% Ak/k) (% Ak/k) (%)
Gp 7 Integral Vorth - 1.011 - 0.966 - 4.5 i 15% Deviation ]
l Gp 6 Integral Worth - 1.125 - 1.156 + 2.8 i 15% Deviation l Cp 5 Integral Worth - 1.436 - 1.544 + 7.5 1 15% Deviation Gp 5-7 Integral Worth - 3.572 - 3.666 + 2.6 i 10% Deviation
- Deviation _ predicted - measured x 100 measured
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OCONEE 2 CYCLE 9 STARTUP REPORT .
ENCLOSURE 3.0 Radial Peaking Factors at 70% FP 8 9 10 11 12 13 14 15 1.01 1.21 1.05 0.99 1.15 1.19 1.00 0.47 H 0.96 1.21 1.04 0.94 1.14 1.17 1.04 0.52
-5.0% 0.0% -1.0% -5.1% -0.9% -1.7% 4.0% 10.6%
1.12 1.25 1.07 1.28 1.24 1.11 0.48 K 1.09 1.27 1.05 1.25 1.21 1.23 0.47
-2.7% 2.0% -1.4% -2.3% -2.4% 11.3% -2.1%
1.24 1.34 1.04 1.27 0.92 0.34 L 1.27 1.25 0.96 1.29 0.97 0.34 2.4% -6.7% -7.7% 1.3% 6.0% 0.0%
1.15 1.28 1.14 0.68 M 1.08 1.24 1.13 0.68
-6.1% -3.1% -0.9% 0.0%
1.16 **** 0.44 Prod.
Meas. N 1.15 1.10 0.44 -
-0.9% **** 0.0%
% Dev.
0.54
- - inoperable 0 0.55 detector 1.9%
core Conditions Predicted Measured Power 75.0 %FP Power 70.25 %FP Group 5 100 %wd Group 5 100 %wd Group 6 100 %wd Group 6 100 %wd Group 7 92 %wd Group 7 89 %wd Group 8 35 %wd Group 8 35 %wd Imbalance -2.97 %FP Imbalance -3.09 %FP Burnup 3 EFPD Burnup 1.38 EFPD RCS Boron 1120 ppmB RCS Born 1070 ppmB Incore tilt WX: -1.75 XY: +1.05 YZ: +1.29 ZW: -0.59 The highest % Deviation is 11.3 % at location K-14.
The highest measured radial peak is 1.34 at location L-11.
The Largest Peak % Deviation is 3.7 %.
The full core RMS % Deviation is 4.64 % with 49 operable detectors.
OCONEE 2 CYCLE 9 -
STARTUP REPORT ENr:LOSURE 3.1 Total Peaking Factors at 70% FP 8 9 10 11 12 13 14 15 1.13 1.46 1.20 1.12 1.35 1.39 1.18 0.55 H 1.12 1.44 1.20 1.09 1.34 1.36 1.22 0.60
-0.9% -1.7% 0.4% -2.9% -0.8% -1.9% 3.6% 9.7%
1.31 1.46 1.23 1.50 1.49 1.34 0.56 K 1.30 1.51 1.23 1.48 1.41 1.46 0.55
-0.8% 3.9% 0.0% -1.2% -4.9% 9.2% -1.0%
1.44 1.59 1.22 1.50 1.07 0.40 L 1.49 1.48 1.15 1.52 1.14 0.40 3.1% -6.9% -5.8% 1.6% 6.3% 1.2%
1.33 1.52 1.34 0.80 M 1.25 1.46 1.31 0.79
-6.0% -3.6% -1.6% -1.1%
- 0.53 Pred. 1.39 "
Meas. N 1.37 1.32 0.52
-1.2% **** -2.0%
% Dev.
0.64
- - inoperable 0 0.65 detector 2.3%
Core Conditions Predicted Measured Power 75.0 %FP Power 70.25 %FP Group 5 100 %wd Group 5 100 twd Group 6 100 %wd Group 6 100 %wd Group 7 92 %wd Group 7 89 %wd Group 8 35 %wd Group 8 35 %wd Imbalance -2.97 %FP Imbalance -3.09 %FP Burnup 3 EFPD Burnup 1.38 EFPD RCS Born 1070 ppmB RCS Boron 1120 ppmB Incore tilt WX: -1.75 XY: +1.05 YZ: +1.29 ZW: -0.59 The highest % Deviation is 9.7 % at location H-15.
The highest measured radial peak is 1.59 at location L-11.
The Largest Peak % Deviation is 3.8 %.
The full core RMS % Deviation is 5.20 % with 49 operabic detectors.
OCONEE 2 CYCLE 9 .
STARTUP REPORT ENCLOSURE 3.2 Radial Peaking Factors at 92% FP 8 9 10 11 12 13 14 15 1.01 1.19 1.04 1.00 1.19 1.19 1.00 0.48 H 0.97 1.21 1.04 0.95 1.14 1.17 1.04 0.53
-4.2% 1.3% -0.2% -5.1% -4.1% -1.9% 4.2% 9.6%
1.10 1.23 1.06 1.27 1.23 1.12 0.48 K 1.10 1.27 1.05 1.25 1.21 1.23 0.48
-0.5% 3.7% -1.1% -2.1% -1.5% 9.1% -0.8%
1.23 1.33 1.03 1.26 0.92 0.35 L 1.27 1.25 0.96 1.29 0.97 0.35 3.0% -5.9% -6.4% 2.1% 5.9% 0.0%
1.13 1.27 1.14 0.69 M 1.08 1.24 1.12 0.69
-4.1% -2.8% -1.3% -0.6%
Pred. 1.19 **** 0.44 -
Meas. N 1.15 1.10 0.45
% Dev. -3.4% **** 1.1%
0.54
- - inoperable 0 0.56 detector 3.0%
Core Conditions Predicted Measured Power 100.0 %FP Power 91.71 %FP Group 5 100 %wd Group 5 100 %wd Group 6 100 %wd Group 6 100 %wd Group 7 92 %wd Group 7 95 %wd Group 8 35 %wd Group 8 36 %wd Imbalance -6.63 %FP Imbalance +3.65 SFP Burnup 4 EFPD Burnup 8.48 EFPD RCS Born 1011 ppmB RCS Boron 1032 ppmB Incore tilt WX: -1.86 XY: +0.41 YZ: +1.64 ZW: -0.19 The highest % Deviation is 9.6 % at location H-15.
The highest measured radial peak is 1.33 at location L-11.
The Largest Peak % Deviation is 3.2 %.
The full core RMS % Deviation is 4.21 % with 49 operable detectors.
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OCONEE 2 CYCLE 9 STARTUP REPORT ENCLOSURE 3.3 i
Total Peaking Factors at 92% FP 8 9 10 11 12 13 14 15 1.15 1.42 1.16 1.16 1.37 1.39 1.17 0.56 H 1.13 1.44 1.21 1.10 1.35 1.37 1.22 0.61
-2.0% 1.5% 4.5% -5.6% -1.5% -1.7% 4.5% 8.9%
1.22 1.40 1.20 1.49 1.45 1.33 0.56 K 1.31 1.52 1.24 1.49 1.42 1.47 0.56 7.1% 8.2% 3.5% 0.3% -2.1% 10.9% 0.2%
1.39 1.50 1.12 1.46 1.06 0.41 L 1.49 1.49 1.18 1.54 1.15 0.41 7.4% -0.7% 5.6% 5.8% 8.1% 0.2%
1.26 1.45 1.32 0.80 M 1.26 1.48 1.33 0.80 0.4% 2.2% 0.4% -0.6%
Pred. 1.35 **** 0.52 Meas. N 1.38 1.33 0.52
% Dev. 2.5% **** 0.6%
0.63
- - inoperable 0 0.66 detector 4.6%
Core Conditions Predicted Measured Power 100.0 %FP Power 91.71 %FP Group 5 100 %wd Group 5 100 %wd Group 6 100 %wd Group 6 100 %wd Group 7 92 %wd Group 7 95 %wd Group 8 35 %wd Group 8 36 %wd Imbalanco -6.63 %FP Imbalanco +3.65 %FP Burnup 4 EFPD Burnup 8.48 EFPD RCS Born 1011 ppmB RCS Boron 1032 ppmB Incore tilt WX: -1.86 XY: +0.41 YZ: +1.64 ZW: -0.19 The highest % Deviation is 10.9 % at location K-14.
The highest measured radial peak is 1.50 at location L-11.
The Largest Peak % Deviation is -2.7 %.
The full core RMS % Deviation is 6.54 % with 49 operablo detectors.
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OCONEE 2 CYCLE 9 .
STARTUP P.EPol f ENCI.0St1RE 4.0 CORE POWER DISTRIBUTION DATA SUll!!ARY AT IIIPT AND FPT Pl.ATEAUS Extrapolated
- Incore Tilt- Ext ra pola t ed* Worst Case Power Cp6/7/8 Boron Incore WX/XY Worst Case Max. Plax . .
Level I;urnap Positions CONC Imbalance YZ/ZW flin. Min. LIIR IJIR
(% FP) (EFPD) (% sd) (ppmB) (% FP) (%) DNBR DNBR (kw/ft) (kw/fL)
-1.75/1.05 70.3 1.4 100/89/35 1120 -3.09 1.29/-0.59 5.66 3.65 7.82 11.37
-1.86/0.41 91.7 8.5 100/95/36 1032 +3.65 1.64/-0.19 3.39 2.58 9.99 11.31 l C NO'1 E : Ext rag.<,la ted t o 105.5% FP l
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OCONEE 2 CYCLE 9 ,.
STARTUP REPORT ENCLOSURE 5.0 REACTIVITY COEFFICIENTS ffEASURED PREDICTED ACCEPTANCE PARMIETER CONDITIONS VALUE VALUE CRITERION liot Zero Power T = 537'F Temper.iture C$"7982%wd -0.034 x 10-4 -0.085 x 10-4 Predicted 1 0.3 x 10-4 Coefficient Gp 8 @ 25% wd Ak/k per *F Ak/k per *F Ak/k per *F (ARO) 1516 ppmB liot Zero Power T = 537'F Predicted 1 0.3 x 10-4 Ak/k per *F
!!cdc rator C$"7@82%wd +0.126 x 10-4 +0.072 x 10-4 and Coefficient Gp 8 @ 25% wd ak/k per *F Ak/k per *F tiessured < + 0.5 x 10-4 Ak/k per *F (ARG) 1516 ppmR l
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- OCONEE 2 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 LPT 14.9 N/A 14.3 15.6 N/A 115.63% D.F.
IMPT 72.6 70.2 72.5 72.8 70.2 110.71% D.F.
FPT 94.5 91.9 94.5 94.9 91.8 110.67% D.F.
FPT (after adjusting constants) 92.8 94.0 93.0 N/A N/A 110.61% D.F.
- Calculated by the of f-line secondary heat balance program (POkT.R) l i
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DUKE POWER GOMPANY P.O. HO x IK3180 CHAMLOTTE, N.C. 28942
"#U "J.D.' Y" P* ""
January 6, 1987 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: Mr. J.F. 'Stols, Project Director PWR Project Directorate No. 6
Subject:
Oconee Nuclear Station, Unit 2 Docket Nos. 50-270
Dear Mr. Denton:
Please find attached the Startup Test Report for Oconee Unit 2, Cycle 9.
Very truly yours, N ~
Hal B. Tucker WHM/32/V3/jgm Attachment xc Dr. J. Nelson Grace, Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta St., NW, Suite 2900 Atlanta, Ca. 30323
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