ML19320A770
| ML19320A770 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/30/1980 |
| From: | Kunsitis T, Leberstien J, Lozito E VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML19320A766 | List: |
| References | |
| VEP-FRD-35, NUDOCS 8007020598 | |
| Download: ML19320A770 (110) | |
Text
.
V E P - F R DL.3 5 -
g.ng I
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Vepco I
.g-NORTH ANNA UNIT 1,070LE 2
I STARTUP PHYSICS TEST REPORT I
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-FUEL RESOURCES DEPARTMENT VIR G I N I A ELECTRIC
~AND POWER COMPANY
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VEP-FRD-35 E
Fu bu NORTH ANNA UNIT 1, CYCLE 2 STARTUP PHYSICS TEST REPORT BY T. J Kunsitis p
J. H. Leberstien L-T. K. Ross E
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[
Approved:
Nuclear Fuel Operation Group Fuel Resources Department
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Virginia Electric and Power Company
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Richmond, Virginia E. J. Lozito, Director June, 1980
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Nuclear Fuel Operation Group
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CLASSIFICATION / DISCLAIMER
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The data, techniques, information, and conclusions in this report
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have been prepared solely for use by the Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which they were specifically prepared.
The Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability.
In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techinques, information, or conclusions in it.
By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall ithlf be deemed to incorporate the stsclaimers of liability and dis-claimers of warranties provided herein.
In no event shall the Company be
[.
liable, under any legal theory whatsoever (whether contract, tort, warranty, or strict or absolute liability), for any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions
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I 1I ACKNOWLEDGEMENTS The authors would like to acktowledge the cooperation of the i
l North Anna Power Station personnel
.*n performing the tests documented in this report. Special thanks are cue Messrs. G. A. Kann, J. P. Smith, F. T. Terminella, and C. C. Kelsey. Also, the authors would like to express their gratitude to Mr. D. L. Reid, Mr. J. R. Ju, Mr. D. M.
i Kapuschinsky, and Dr. E. J. Lozito for their aid and gaidance in pre-paring this report. We would like to thank Mrs. S. L. Kulp for her i
patience and accurate typing of the text.
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F F
L TABLE OF CONTENTS b
SECTION
'iITLE PAGE NO.
F Classification / Disclaimer.
1 L
Acknowledgements..
11 List of Tables.
iv List of Figures.
V Preface.
vii 1.0 Introduction and Summary.
1 2.0 Control Rod Drop Time Measurements.
9
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3.0 Reactor Coolant System Flow Measurements.
l'4 4.0 Control Rod Bank Worth Measurements.
16 l
5.0 Baron Endpoint and Worth Measurements.
32 6.0 Temperature Coefficient Measurements.
36 1
7.0 Power Distribution Measurements.
41 8.0 References 64 I
APPENDIX Startup Physics Test Results and Evaluation Sheets.
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LIST OF TABLES TABLE TITLE PAGE NO.
1.1 Chronology of Tests.
4 2.1 Hot Rod Drop Time Summary 11 3.1 Reactor Coolant System Flow Measurement Summary.
15 4.1 Control Rod Bank Worth Summary.
18 4.2 Shutdown Margin Calculation..
19 5.1 Boron Endpoints Summary.
34 L'
6.1 Isothermal Temperature Coefficient Summary.
38 7.1 Incore Flux Map Summary.
44 7.2 Comparison of Measured Power Distribution Para-meters With Their Technical Specifications Limit.
45 f
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ll 1I L
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iv
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l LIST OF FIGURES I
1 FIGURE TITLE PAGE NO.
l.1 Core Loading Map.
5 l
- 1. 2 Assembly ID's and Incore Instrumentation locations 6
- 1. 3 Burnable Poison and Source Assembly Locations..
7 l
1.4 Control Rod Locations.
8 l
2.1 Typical Rod Drop Trace 12
- 2. 2 Rod Drop Time - Hot Full Flow Conditions.
13 t
l 4.1 Bank D Integral Rod Worth - HZP.
20 4.2 Bank D Differential Rod Worth - HZP.
21 1
- 4. 3 Bank C Integral Rod Worth - HZP.
22 1
4.4 Bank C Differential Rod Worth - HZP.
23 f
4.5 Bank B Integral Rod Worth - HZP.
24 l
4.6 Bank B Differential Rod Worth - HZP.
25
- 4. 7 Bank A Integral Rod Worth - HZP.
26 l
4.8 Bank A Differential Rod Worth - HZP.
27 4.9 Shutdown Bank B Integral Rod Worth - HZP.
28 4.10 Shutdown Bank B Differential Rod Worth - HZP.
29 l
4.11 Intergral Worth of Control Banks A through D In Overlap Mode 30 4.12 Dif ferential Worth of Control Banks A through D In Overlap Mode 31 5.1 Boron Wort.h Coefficient.
35 l
6.1 Isothermal Temperature Coefficient - HZP, ARO.
39 6.2 Isothermal Temperature Coefficient - HZP, D-Bank In 40 7.1 Assemblywise Power Distribution - HZP, ARO.
46 l
- 7. 2 Assemblywise Power Distribution - HZP, D Bank In.
47
- 7. 3 Control Rod Insertion Limits.
48 i
7.4 Assemblywise Power Distribution - HZP, ARO.
49 I
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l 1
1 LIST OF FIGURES I
FIGURE TITLE PAGE NO.
75 Assemblywise Power Distribution - HZP, D-Bank at 0 Steps and C-Bank at 118 Steps.
50 7.6 Assemblywise Power Distribution - D-Bank at 100 Steps.
51 7.7 Assemblywise Power Distribution - I/E Cal. - Flux Map..
52 7.8 Assemblywise Power Distribution - I/E Cal. - Flux Map.
53 1
7.9 Assemblywise Power Distribution - I/E Cal. - APDM Flux Map.
54 7.10 Assemblywise Power Distribution - I/E Cal. - APDM 1
Flux Map.
55 7.11 Assemblywise Power Distribution - I/E Cal. - APDM Flux Map.
56 7.12 Assemblywise Power Distribution - I/E Cal. - APDM Flux Map.
57 7.13 Assemblywise Power Distribution - I/E Cal. - APDM Flux Map.
58 7.14 Assemblywise Power Distribution - I/E Cal. - APDM Flux Map.
59 7.15 Assemblywise Power Distribution - I/E Cal. - Flux Map.
60 1
7.16 Assemblywise Power Distribution - I/E Cal. - Flux Map.
61 7.17 Assemblywise Power Distribution - HFP, "q. Xenon. 62 7.18 Percent Quadrant Power Tilt vs. Power Level.
63 1
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PREFACE I
The purpose of this report is to present the analysis and evaluation of the physics tests which were performed to verify that the l
North Anna 1, Cycle 2 core could be operated safely, and to make an initial evaluation of the expected performance of the core.
It is l
not the intent of this report to discuss the particular methods of testing or to present the detailed data taken. Standard test tech-niques and methods of data analysis were used. The test data, results l
and evaluations, together with the detailed startup procedures, are on file at the North Anna Power Station. Therefore, only a cursory l
discussion of these items is included in this report. The analyses presented includes a brief summary of each test, a comparison c.f the l
test results with design predictions, and an evaluation of the results.
The North Anna 1, Cycle 2 Startup Physics Tests Results and Evaluation Sheets have been included as an appendix to provide additional l
information on the startup test results. Each data sheet provides the following information:
- 1) test identification, 2) test conditions i
I (design),
3) test conditions (actual), 4) test results, 5) accept-ance criteria, and 6) comments concerning the test.
These sheets provide 1
a compact summary of the startup test results in a consistent format.
l The design test conditions and design values of the measured parameters were completed prior to startup physics testing. The entries for f
the design values were based on calculations performed by Vepco's Nuclear Fuel Engineering Group.
During the tes ts, the data sheets l
were used as guidelines both to verify that the proper test con-ditions were met and to facilitate the preliminary comparison between l
measured and predicted test results, thus enabling a i;uick identification l
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of possible problems occurring during the tests. The appendix to this report contains the final completed and approved version of the Startup Physics Tests Results and Evaluation Sheets.
L E
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I Sxction 1 I
INTRODUCTION AND
SUMMARY
l On September 25, 1979, Unit No. 1 of the North Anna Power Station was shutdown for its first refueling. During this shutdown, 52 of the 157 fuel assemblies in the core were replaced with fresh fuel assemblies. The second cycle core consists of four regions of fuel:
three once-burned regions from Cycle 1 (Regions lA, 2 and 3), and one fresh region (Region 4).
The core loading pattern and the design parameters for each region are shown in Figure 1.1.
The core location of each fuel assembly is identified in Figure 1.2 together with the incore instrumentation locations. Figure 1.3 identifies the location and number of burnable poison rods in the Cycle 2 core.
Figure i.4 identifies the location and number of control rods in the Cycle 2 core.
On January 15, 1980, at 1624, the second cycle core achieved initial criticality.
Following criticality, startup physics tests were performed as outlined in Table 1.1.
A summary of the results of these tests follows:
1.
The drop time of each control rod was confirmed to be within the 2.2 second limit of the Technical Specifications.2 2.
The reactor coolant system flow rate was confirmed to be greater than the minimum limit specified in the Technical Specifications.
3.
Individual control rod bank worths for control banks A through D and shutdown bank B were measured to be within 7.9% of the design predictions. The total control rod bank worth in the overlap mode was measured to be within 4.2%
I of the design prediction.
In addition, the total worth of all 1
1 1
Y control and shutdown banks less the most reactive rod (RCCA H-14) was measured to be within 1.7% of the design prediction.
These results are within the design tolerance of 15% for individual bank worths and the design tolerance of 10% for the total control bank worth and the total worth of N-1 rods.
Bl 4.
Critical boron concentrations for six basic control and shutdown bank configurations and for the all-rods-in less I
the most reactive rod condition were measured to be within 34 ppm of the design predictions.
These results are within the design tolerances and also met the accident analysis acceptance criterion.
5.
The boron worth coefficient was measured to be within 3.8%
of the design prediction, which is within the design tolerance of 10% and met the accident analysis acceptance criterion.
6.
Isothermal temperature coefficients over the range of normal operating control rod bank insertions were measured to be within 2.6 pcm/ F of the design predictions. These results 4g are within the design tolerance of 3 pcm/ F and also met the accident analysis acceptance criterion.
7.
Core power distributions for various HZP and at-power condi-tions were generally within 7% of the predicted power distri-butions.
The quadrant power tilt ratio at ARO, HZP was 1.09, decreasing to 1.01 at HFP.
This directly affected the values of the hot channel factors.
The control rod insertion limits were raised on an administrative basis, with NRC concurrence, in order to preclude potential violations of the FN Technical l
LH E
Specifications limit.
2
+
/'b In summary, all startup. physics test results were acceptable.
Detailed'results together with specific design tolerances and acceptance l.
criteria for each measurement are presented in the appropriate sections of this report.
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Table 1.1 NORTH ANNA UNIT 1 - BOL CYCLE 2 PHYSICS TESTS CHRONOLOGY OF TESTS Test Date Time Power Reference Procecure Hot Rod Drops-Hot Full Flow 1-12-80 1455 HSD 1-PT-17.2 Reactivity Computer Checkout 1-16-80 0735 HZP 1-PT-94(B) h Boron Endpoint - ARO 1-16-80 1205 HZP 1-PT-94 (C)
Temperature Coefficient - ARO 1-16-80 1434 HZP 1-PT-94 (D)
Flux Map - ARO 1-16-80 1733 HZP 1-PT-21.1 Bank D Worth 1-17-80 0924 HZP 1-PT-94(E)
Boron Endpoint - D In 1-17-80 1455 HZP 1-PT-94 (C)
Temperature Coefficient - D In 1-17-80 1655 HZP 1-PT-94(D)
Flux Map - D In 1-17-80 2027 HZP 1-PT-21.1 Bank C Worth 1-18-80 1756 HZP 1-PT-94 (E)
Boron Endpoint - C In 1-18-80 1929 HZP l-PT-94(C)
Bank B Worth 1-19-80 0400 HZP 1-PT-94(E)
Boron Endpoint - B In 1-19-80 0454 HZP 1-PT-94 (C)
Bank A Worth 1-19-80 1829 HZP l-PT-94(E)
Boron Endpoint - A In 1-19-80 1901 HZP 1-PT-94(C)
N-1 Worth 1-20-80 0215 HZP l-PT-94(H)
Boron Endpoint - N-1 1-20-80 0211 HZP 1-PT-94 (H)
Boron Endpoint - SB In 1-20-80 0403 HZP 1-PT-94(H)
Bank SB Worth 1-20-80 0603 HZP 1-PT-94(H)
Banks A+D Worth in Overlap 1-20-80 1345 HZP 1-PT-94 (F)
Flux Map - ARO 1-20-80 2014
%3%
1-PT-21.1 Flux Map - D at 0 Steps C at 118 Steps 1-21-80 0120 N3%
1-PT-21.1 Flux Map-D at 100 Steps 1-21-80 1344 N3%
1-PT-21.1 Flux Map - I/E Calibration 1-24-80 1749
%30%
1-PT-22.2 Flux Map - I/E Calibration 1-25-80 1006 N30%
1-PT-22.2 Flux Map - APDMS, I/E Calibration 1-25-80 1511
%30%
1-PT-22.2 Flux Map - APDMS, I/E l
Calibration 1-26-80 1644
%30%
1-PT-22.2 Flux Map - APDMS, I/E Calibration 1-29-80 0429
%47%
1-PT-22.2 RCS Flow Measurement 1-29-80 0545 N48%
1-PT-27 Flux Map - APDW, I/E Calibration 1-31-80 1209
%45%
1-PT-22.2 Flux Map - APDMS, I/E Calibration 2-03-80 1353 N66%
1-PT-22.2 Flux Map - APDMS, I/E Calibration 2-04-80 0144 483%
1-PT-22.2
(
RCS Flow Measurement 2-05-80 1555
%99%
1-PT-27 L
Flux Map - I/E Calibration 2-07-80 1136
%99%
1-PT-22.2 Flux Map - I/E Calibration 2-07-80 1905
%99%
1-PT-22.2 Flux Map - EFP, Eq. Xenon 2-14-80 1616 100%
1-PT-21.1 4
Figure 1.1 NCR*H ANN A t*.IIT 1 - C"JC'l2 CORE LOADUiG MAP R
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l FUEL ASSE!"BLY OESICN PVAFE*EPS Patei I
1A 2
3 4
l Initial Enrichrent (w/o t:235) 2.11 2.60 3.10 3.21 Burnup At BOC-2 (?!dOMm;)
14.300 18.077 12,166 0
Asserbly Type 17x17 17x17 17x17 17x17 No. of Asserblies 1
52 52 52 l
Fuel Pois per Asserbly 264 264 264 2A4 5
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I Figure 1.2 NOP" JJ:NA t**I" 1 - CYC:: 2 ASSEMBLY ID's AND I?l CORE INS *R"STATICN LOCATTC? S I
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+-
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Ti;ure 1.3
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S ctien 2.0 l
1 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at cold and at hot RCS conditions in order to confirm satisfactory operation and to verify that the rod drop times were less than the maximum allowed by the Technical Specifications. The hot control rod drop time measurements were run with the RCS at hot, full flow conditions (%547 F, N2235 psig) and are described below.
The rod drop time measurements were performed by first with-drawing a rod bank to its fully withdrawn position, and then removing the movable gripper coil fuse and stationary gripper coil fuse for the test rod.
This allows the rod to drop into the core as it would in a normal plant trip. The data recorded during this test are, the stationary gripper coil voltage, the IRPI (Integrated Rod Position Indicator) detector primary coil voltage and a 60Hz timing trace which are recorded via a visicorder. The rod drop time to the dashpot entry and to the bottom of the dashpo* sre determined from this data.
Figure 2.1 provides an example of the data that is recorded during a rod drop time measurement.
As'shown in Figure 2.1, the initiation of the rod drop is indicated by the decay of the stationary gripper coil voltage when the stationary gripper coil fuse is removed. A voltage is then induced in the IRPI detector primary coil aa_the rod drops. The magnitude of this voltage is a function of the rod velocity. When the rod enters the dashpot section of its guide tube, the velocity slows causing a voltage decrease in the IRPI coil. The IRPI voltage then reaches a minimum as the rod reaches the bottom of the dashpot.
Subsequent variations in the trace are caused by the rod bouncing. This procedure was repeated for each control rod.
t 9
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f.g The measured ' rop times 'for each control' rod are recorded d
L on Figure 2.2.
The slowest, fastest-and average drop times are
~
- sununarized in Table 2.1.
Technical Specification 3.1.3.4 specifies a-maximum rod drop time from loss of stationary gripper coil voltage to I-dashpot entry of_2.2 seconds with the RCS at hot, full flow conditions.
All test results met this' limit.
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Table 2.1 NoRTil AN';A UNIT 1 - CYCLE 2 Boi PHYSICS TESTS l
nor noo DROP TrxE S mirav 1
ROD DROP TI!!E TO DASHPOT ENTRY
^"
Slowe.t Rod Fa.te.t Rod T
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- Rod Drop Time to Dashpot Entry (sec.)
l
+
- Rod Drop Time to Bottom of Dashpot (sec.)
I
+
I 13 i
I
1 Section 3 REACTOR COOLANT SYSTDI FLOW MEASUREMENT The reactor coolant flow rate is measured in order to verify that the minimum flow rate requirement is satisfied. The RCS l
flow rate is determined using the calorimetric measurement technique.
I Precision calorimetric data (i.e., feedwater temperature, feedwater flow, and steam pressure) are obtained in order to accurately determine the j
secondary-side heat rate. The primary-side enthalpy rise is determined from the RCS pressure and the temperature increase associated with l
each RCS loop.
The flow for each RCS loop is determined by establish-ing a primary-side to secondary-side heat balance.
blowdown heat loss, system heat losses,and the power produced by the reactor coolant pumps are taken into account in the heat balance.
l Reactor coolant flow measurements were performed during power ascension 3
l at 50% power and 100% powe'. These data were analyzed using the RXFLOW computer code. A summary of the results for these tests is given in Table 3.1.
As shown by this table, the test results were consistent and I
aemonstrated that the RCS flow limit was met.
1 I
1 5
1 I
I 1
3 1
I l
14 I
Table 3.1 l
NORTil ANNA UNIT 1 - CYCLE 2 BOL PlfYSICS TESTS REACTOR COOLANT SYSTDi FLOW MEASURDIENT SUFMARY l
I Percent Loop A Loop B toop C T tal riow
}finimum Flow Power Flow (gpm)
Flow (gpm)
Flow (gpm)
(gpm)
Limit * (gpm) 50%
97,882 98,412 106,244 302,538 278,400 100%
101,999 103,228 105,341 310,568 278,400 C
- North Anna Power Station Technical Specifications
Section 4
[
CONTROL ROD BANK WORTH MEASUREMENTS Differential and integral control bank worths were obtained by monitoring reactivity changes associated with boron /RCCA exchanges.
Following the establishment of a constant RCS boron dilution /boration
{
rate, the controlling RCCA bank was periodically inserted /wichdrawn in order to provide reactivity compensation for the changing RCS boron concentration. The reactivity changes resulting from the control bank movements were recorded continuously by the reactivity computer.
The differential reactivity worth is defined as the ratio of the change in reactivity to the corresponding change in bank position about an average bank position, and the integral worth was obtained by summing the individual
{
reactivity changes between r.easurement endpoints.
A summary of the results for these tests is given in Table 4.1.
As shown by this table and the Startup Physics Test Results and Evaluation Sheets gives in the Appendix, the individual measured bank worths for C
l control banks D, C, B, and A and shutdown bank B were within the design tolerance of 15%. The total bank worth (non-overlap mode) for control banks A through D was measured to be within 2.0% of the design pre-diction. This is well within the design tolerance of 10% for total control bank worth.
In addition, a second measurement of total worth of the control banks (in overlap mode) was performed. This measured value was within 4. 2% of the design prediction. The total worth of N-1 rods h
was measured to be within 1.7% of the design prediction. This is well within the design tolert..tce of 10% for the worth -of N-1 rods.
E
(
16 1
~
C h
the integral and differential reactivity worths for control rod banks D through A (non-overlap mode) and shutdown bank B are shown in Figures 4.1'through Figure 4.10, respectively. The design predictions and the measured data (non-overlap mode) are plotted together in order to illustrate their agreement. The rod worth measurements are quite exact in defining th'e shape of the individual differential rod worth curves, as illustrated by the distinct depressions occurring at the assembly grid locations.. The integral and differential worths for control banks A through D operating in the overlap mode are shown in Figures 4.11 and 4.12, respectively.
The worth of N-1 rods was used in the shutdown margin calculation shown in Table 4.2.
As indicated in this table, the cal-
{
culated shutdown margin verifies that the shutdown margin requirements are met and that an excess shutdown peactivity of 464 pcm is also
[.
available.
In summary, all measured rod worth values were satisfactory.
[
(
C c
[
E:
17
o-Tcble 4.1 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TESTS CONTROL ROD BANK WORTH SCOfARY i
FfEASURED PREDICTED PERCENT DIFFERENCE
('[-P) x 100 HANE WORTH WORTH (PCI)
(PC4) s D
1069 1095
-2.4 C-Bank D In 908 873
+4.0 B-Banks C+D In 1321 1434
-7.9 A-Eanks E+C+D In 1651 1649 M.1 SB-Banks A+B+C+D In 933 907
+2.9 IA+D 4949 5051
-2.0 A + D In Overlap 4838 5051
-4.2 Mode Total Worth 5942 6044
-1.7 N-1 Rods-l[
E r
L F
l
{
18 F-i L
I Table 4.2 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST SHUTDOWN MARGIN CALCULATION l I Meas ured A.
Control Rod Worth Data (pcm)
Total Rod Worth Less 5942 RCCA B-8 (N-1 Rod Worth)
Measurement Uncertainty (4%)
238 N-1 Rod Worth Less Uncertainty 5704(a)
Most Limiting B.
Reactivity Worth Rer4uirements Design Data *(pcm)
Reactivity Defects (Combined Doppler, 2970 Tavg, Void and Red:'.stribution Effects)
Rod Insertion Allosance 500 Total Reactivity Worth Requirement 3470(b) l C.
Shutdown Margin Calculated Shutdown Margin (a)-(b) 2234 Required Shutdown Margin 1770 Excess Sh.,tdown Reactivity 464 I
I I
- These reactivity worth requirements are the most limiting of the BOL and EOL design values.3 I
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0 40 8O 120 160 200 228 BANK D POSITION (STEPS) 21 t
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Section 5
[
BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant
[-
system boron concentrations were measured at selected rod bank con-figurations to enable a direct comparison of measured boron endpoints with design predictions. For each measurement, the RCS conditions were
{
r abilized with the control bank at or very near a selected endpoint position. The critical boron concentration was then measured. If necessary, an adjustment to the measured critical boron concentration value was made to account for off-nominal core conditions, i.e.,
for rod position and
[
moderator temperature.
The results of these measurements are given in Table 5.1.
As shown in this table and in the Startup Physics Test Results and Evaluation
(
Sheets given in the Appendix, all measured critical boron endpoint values were within their respective design tolerances. All measured values met the
[.
accident analysis acceptance criterion.
In summary, all results were satisfactory.
Boron Vorth Coefficient The measured boron endpoint values provide stable statepoint data from which the. boron worth coefficient was determined. A plot of the
-boron concentration as a function of integrated reactivity can be con-
{
-structed by relating each boron endpoint concentration to the integrated rod worth present in the core at the time of the endpoint measurement.
C 32
h..
9 3
h The value of the boron worth coefficient, over the range of boron endpoint concentrations, is obtained directly from this plot.
The boron worth plot is shown in Figure 5.1.. As indicated in this figure and in the Appendix, the boron worth coefficient of re-activity was measured to be -8.88 pcm/ ppm. The measured boron worth co-(
efficient'is within 3.8% of the predicted value of -9.23 pcm/ ppm and is well within the design tolerance of 10%. The measurement result also met the accident analysis acceptance criterion.
In summary, this result was satisfactory.
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rL Table 5.1 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST 3
)
Control Rod Measured Predicted Difference Configuration Endpoint Endpoint M-P (ppm)
(ppm) *
(ppm)
ARO 1353 1319
+34 D Bank In 1243 1233
+10 D+C Banks In 1138 1147
-9 D+C+B B4utka In 988 984
+4 D+C+B+A Banks In 812 811
+1 MC+B+A+SB Banks In 697 715
-18 All Rods In Except 681 691
-10 RCCA H-14
- Predicted endpoints have beca adjusted for the difference between the measured and predicted values of the previous endpoint as shown in the boron endpoint Startup Physics Test Results and Evaluation Sheets in the Appendix, 1
P 34 L
FIGURE Sol NORTH RNNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST BORON WORTH COEFFICIENT 5 ENDPOINT FEASUREftENTS I
l
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Section 6 TEMPERATURE COEFFICIENT _ MEASUREMENTS The isothermal temperature coefficient measurements were
[
accomplished by controlling the RCS heat gains / losses with the steam dump valves to the condenser, establishing a constant and uniform heatup/
cooldown rate, and then monitoring the resulting reactivity changes on the reactivity computer. These measurements were performed at very low power levels in order to minimize the effects of non-uniform nuclear heating, thus, the moderator and fuel were approximately at the same temperature (between 543-549 F) during these measurements. To climinate
[
the boron reactivity effect of outflow from the pressurizer, the pressurizer level was maintained constant or slightly increasing during these measurements.
l Isothermal temperature coefficient measurements were performed at various control rod configurations. For each rod configuration, re-1 activity measurements were taken during both RCS heatup and cooldown I
ramps during which S RCS temperature varied approximately 6 F.
Re-activity was determined using the reactivity computer and was plotted j
against the RCO temperature on an x-y recorder. The temperature co-efficient was then determined from the slope of the plotted lines. The I
i x-y recorder plots of reactivity change vs. RCS temperature for each measurement are shown in Figures 6.1 and 6.2.
l The predicted and measured isothermal temperature coefficient I
values are compared in Table 6.1.
As can be seen from this summary and from the Startup Physics Test Results and Evaluation Sheets given in the L
36
~
)
r L
IL
~
l Appendix, all measured isothermal temperature coefficient values were L
within the design tolerance of 23 pcm/ F and met the accident analysis I
acceptance criterion.
In summary, all measured results were satisfactory.
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Fl T U Tabic 6.1 NORTil ANNA UNIT 1 - CYCLE 2 BOL PilYSICS TESTS IS011IERMAL TEMPERATURE COEFFICIENT SLW ARY ISOTIIERMAL TEPPERATURE COEFFICIENT BANK POSITION TEMPERATURE BORON (PCM/*F)
(STEPS)
RANGE CONCENTRATION
(*F)
(PPM)
IIEATUP C00LDOWN AVERACE PREDICTED DIFFERENCE C
D (M-p) 228 216/
543-549 1351
-2.57
-2.15
-2.36
-3.49
+1.13 215 u
oo 228 15 543-549 1234
-3.47
-3.92
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l 4
Figure 6.1 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST ISOTHERMAL TEMPERATURE COEFFICIENT HZP, ARO
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F L ligure 6.2 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST ISOTHERMAL TDiPERATURE COEFFICIDIT HZP, D-BANK IN B ESEI EGEEE11II l9 5EHiH13t . IliEIMET M'if iniL 1h: I ~ EUfEdia M n: iE5! !LT.td !$##:$i!N .EE EM M 41]!(. @Ih '!!i t - m_ _dh. %. ;.~ -t. H $. d E I!i,.! m, H! LE$i:: m:-+ = w .u_a e .+ .m$ tint:mtr i m. v now n = +~ + _ _ Jam m i.i.e filifE:.Jihg,1l[ll11ilil MiWi!E ME F t"""" c .l FD EEMNEEMMY ~ 8 w 3 mn.- N"IM MMNhn..i@ UI!!!! !IELiIIISN (bWq":b ij g M %MWZU3igEGl iDilie !!!i E illilill lii! ilR lii! !ii'~ gr-%:gi;g3ffE][Illfill g li: lit ~' t3 lll llll riill!!I jii! illi
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Section 7 ll l POWER DISTRIBUTION MEASUREMENTS l The core power distributions were measured using the incore movable detector flux mapping system. This system consists of five I fission detectors which traverse fuel assembly instrumentation thimbles in 50 core locations (see Figure 1.2). For each traverse, the detector output is continuously monitored on a strip chart recorder. The output is also scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power distributions are then determined by analyzing this data using the Westinghouse computer program, I INCORE. INCORE couples the measured flux map data with predetermined analytic power-to-flux ratios in order to determine tne power distribution for the whole core. A list of all the flux maps taken during the test program together with a list of the measured values of the important power dis-I tribution parameters is given in Table 7.1. The measured power dis-tribution parameter values are compared with their Technical Specifications limits in Table 7.2. Flux maps 1 and 2 were taken at zero power. These flux maps serve as base case design checks. Figures 7.1 and 7.2 show the resulting radial power distributions associated with these flux maps. These maps identified the presence of a large quadrant power tilt (N9% and N6% for the ARO and D bank in maps, respectively) and also I N indicated that the nuclear enthalpy rise hot channel factcr, FAH' " potentially exceed its design bacis value, with the control rods at their insertion limits. Flux map 3 was taken at N3% power (ARO) in order to re-confirm the results of the previous maps. Flux map 4 was taken at N3% power with the control rods at the HZP insertion limit. The N exceeded its design basis value reeults of this map verified that F3 l 41 E
N at that core configuration. In order to preclude violating the FAH design basis during normal plant operation, the control rod insertion limits were revised (see Figure 7.3) based on additional design cal-culations and the flux map results. Flux cap 6 was taken at %3% power with the control 7ds at the revised HZP insertion limit. The results N of this map verified that F was below its design basis value at that g AH core configuration. Figures 7.4 through 7.6 show the radial power dis-tributions associated with flux maps 3, 4, and 6. A safety evaluation was performed to assess the impact of the core tilt and the revised control rod insertion limits on the conclusions stated in the FSAR re-garding core safety. This evaluation concluded that the presence of the observed and predicted core tilt did not invalidate the conclusions presented in the FSAR. On this basis, the revised control rod insertion limits were administrative 1y implemented, with NRC concurrence, and the power ascension phase of the testing program was begun. Flux maps 7 through 18 were taken over a wide range of power l levels and control rod configurations. These flux maps were taken to check the at power design predictions, to measure core power distributions, and to verify that the hot channel factor limits would be met during normal operation in accordance with the revised control rod insertion limits. These maps also provide incore/excore calibration data for the nuclear instrumentation system as well a base data for axial power dis-tribution surveillance. The radial power distributions for these maps are given in Figures 7.7 through 7.17. These figures show that the measured relative assembly power values are generally within 5% of the predicted values. Figure 7.18 shows a plot of quadrant power tilt versus power level. I I 42 I
..o In. conclusion, 'with the establishment of the revised control. i rod insertion limits, all power distribution measurement results were considered to be acceptable with -respect to the accident analysis acceptance criteria and the' Technical Specification limits. It-is -therefore anticipated that the core will continue to operate safely throughout Cycle 2. E E, s [ ~ [ k 43 p t
l l l Table 7.1 l gRTM A.WA UNIT 1 - CYCLE 2 901. P"YSICS NTT* I'&*E Ftri 9P etw uY N H&T CCRE F SANK POSITION F HOT F3 g W IIUUI CRANNEL FACTOR
- CHANNE1. FACTOP**
MAX x + QPTR AX1AL .W. DESCRIPTIOM map pyg F,7
- N 40.
(1) AXIAL AX1AL C D ASST. FIN POINT F ASSY. PIN r POINT F G} l 2
- 1 *
- N P
- AA0 1
s0 228 218 P06 MD 12 3.09 P07 LG 1,64 12 1.90 1.81 1.090 +47.96 as I (1d4 NP = 0 in 2 s0 228 12 N11 IJE 13 3.64 N11 1X 1.92 11 1.88 2.14 1.063 +4 7. 30 '8 F luu Kap - ARO 3 s3 228 228 PLO MN 12 3.00 P09 LK 1.61 11 1.87 t.37 1.084 +46. 2 2 48 I Flus Np 4 s3 118 0 L13 KL 39 2.9) L13 LK 1.93 38
- 1. 35 2.15 1.034
-13.60 49 6 Inn 'up 6** s3 228 99 K14 NM 46 2.58 L13 KL 1.74 45 1.42 2.03 1.051 -t9.2 49 F li.m 9.a p - y s30 228 165 K14 NM 29 2.08 L13 IJE 1.54 28 1.25 1.67 1.024
- 0.
8 47 I 1/t e.a lib ra t io n Flus NP - 8 %30 22$ 138 810 13 45 2.20 L13 1.M 1.57 45
- 1. 30
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-14.90 48 1/L Calibration Flum Pap - APDt:5 9 % 30 228 217 J14 KL 12 2.86 P09 LK 1.47 11 1.93 1.69 1.045 +4 8. 20 48 i 1/E Calibration Flum Map = APDMS. 10 %30 228 218 K14 KM 29 1.87 K14 NM 1,48 13 1.20 1.45 1.029 + 6.2 4 48 1/F Calibration flus Pap - APDMS. 11 u? 228 218 L13 LM 20 1.90 L13 1.M 1.46 13 1.27 1.62 1.020 +11.06 46 I 1/s calibration Flus Pap - A?DMS. 12 45 228 192 L13 LM 21 1.94 'la LM 1.49 20 1.24 1.63 1.025 + 6 28 48 1/E Calibration Flum Pap - AFDMs. 13 %6 228 217 L13 LM 21/20 1.84 N11 ML 1.43 13 1.24 1.39 1.018 + 8. 90 48 I I/E Calibration k lum Map - AFDHS. 14 s80 228 228 K14 NM 29 1.75 til LM 1,41 13 1.17 1M7 1.018 + 4. 57 48 1/E Calibration flun Map - 15 $99 228 228 810 EN 45 1.76 P09 LK 1,39 20 1.11 s% 1.010 + 0.13 48 1/i; Calibration Flun up - 16 s99 228 208 B10 EN 46 1.90 L13 LM 1.40 46 1.20 1.33 1.014 - 7.27 46 1/E Calibration j Tien Map - HP'. 11 N100 228 213 810 EM 45 1.78 L13 LM 1.40 20 1.12 1.35 1.010 - 0.55 47 19 Xenon
- test ilot spot locatione are specified by givina assembly locations (e.g. F-8 is the center-of-core.nssembly location), fc13cted by the pin location (denoted by the "T" coordinate with the seventeen rows of fuel rods lettered A through Q and the "X" coordinate destgr.ated in a similar a.anner).
In the "2" direction the core is divided into 61 axial points starting f rom the top of the core.
- F includes a total c. certainty of 1.05 x 1.03.
N
- F, including a measuremnt uncertainty of 1.04
- F,7 is evaluated at the midplane of the core and includes a total acertatnty of 1.05 a 1.03.
"qPTR - Quadrant Power Tilt Ratto, Bis value is the maximum QPTR of the upper and Iner halves of tr e core.
- Map 5 vse aborted.
I
- Map 17 was a quarter core M/D fluz map.
64 I 1 l
Table 7.2
- 0RTil Ali'!A C IT 1 - CYCLE 2 3CL PHYSICS TESTS CC'! PAR!50N OF MEASURID POUER DISTRIEUTIO!! PARAMETERS WITH THEIR TECE::ICAL SPECIFICATIO!!S t.!MIT FfgHotChannelFactor*
F Hoc channel Factor F !!ap Peasured Limit Measured Limit Measured Limit 7 1.54 1.77 12.9 2.08 4.20 50.2 1.71 12 1.95 12.3 8 1.57 1.77 11.3 2.20 4.20 47.6 1.79 21 1.95 8.2 9 1.47 1.76 16.5 2.36 4.20 28.4 1.75 46 1.37 6.4 10 1.48 1.76 15.9 1.87 4.20 54.6 1.69 45 1.87 9.6 11 1.46 1.71 14.6 1.90 4.20 53.4 1.67 45 1.83 8.7 12 1.49 1.72 13.4 1.94 4.20 32.6 1.66 37 1.83 9.2 13 1.43 1.66 13.9 1.84 3.03 40.2 1.63 33 1.76 7.4 ) 14 1.41 1.60 11.9 1.75 2.52 23.6 1.60 36 1.71 6.4 15 1.39 1.55 10.3 1.76 2.12 16.3 1.59 45 1.65 3.6 16 1.40 1.55 9.7 1.90 2.12 10.3 1.59 45 1.66 4.2 18 1.40 1.55 9.7 1.78 2.10 15.6 1.59 45 1.65 3.6 lI a The neasused value for the enthsipy rise hot channel facter, F.~, includes 47. measurement uncertainty. b The Technical Specifications 14mit for the heac flux het channel factor, F, is a functica I of core height. The value for F6 listed above is the =aximum value of T' in the ccte. The Technical Specifications limit listed above is evaluated at the plane oh maxi =um F' minimummarginvalueslistedabovearetheminimumpercentdifferencebetweenthebe.The asured values of F6(2) and the Technical Specifications limit for each map. All measured F4 hot channel factors include 52 measurement uncertainty and 3* engineering uncertainty. I c.21 neasured F values include 5% ceasurement uncertainty and 3% engineering uncertainty. l 1l E i L J
~. - - - -._ F A I L Figure 7.1 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST, ASSEMBLYWISE POWER DISTRIBUTION F HZP, ARO .i ..."i. . a. o... a.s r. s. u. ".. i c s ".. a.
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c.- .r. ...,-.....i. a.i. as, e . ire. ii....",.. . v e r n i... -... r e... i.-. =*.. MAP NO: N1-2-1 l'A: 1/16/80 POWER = 0% FfH' CONTROL ROD POSITIONS: D BANK AT 218 STEPS FT = 3.090 NW - 0.996 Q C BANK AT 228 STEPS -F = 1.896 NE - 0.908 l e A.O. = +47.960 SW - 1.090 BURNUP = 0 MWD /MTU SE 1.006 iL 46 r I I i
Figsarti 7.2 t l NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST ASSEMBLWISE POWER DISTRIBUTION l l HZP. D-BANK IN 1 1 i I a I
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6c r rit e s s-wcr. is a.~. a.s.. o.*3. rr is t i. n .../ s.a. i... poi =>.r I MAP NO: N1-2-2 DATE: 1/17/80 POWER = 0% CONTROL ROD POSITIONS: F{H 1.917 QPTR: I = D BANK AT 12 STEPS FT = 3.636 NW - 0.983 Q I 1.875 NE - 0.943 C BANK AT 228 STEPS F = z A.O. = +47.308 SW - 1.063 BURNUP = 0 MWD /MTU SE - 1.011 47 I
l l l f Figure 7.3 l NORTH AmlA UNIT 1 - CYCLE 2 i I CONTROL RCD INSERTIOT LIMITS I l 228 220 /,, I 200 A / 180 .f - ~ ~. - s' ~ = DBM p 5 160 0 / h 3 f: f,,' l 140 M / i h 120 J' f' j 5 -I' D BANK h
- /
8 / 80 E M a m 60 E 40
PREVIOUS INSERTICN LIMITS E
f' REVISED INSERTIQI LIMITS 20 E -l. I E O 10 20 30 40 50 60 70 80 90 100 I PCWER LEVEL (% FULL POWER) I I 48 ,3g eses e - em----
l ..~.--- - ~. -. - Figure 7.4 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION l g H m ARo w w a t B. P J P P H f 4 4 I weg o l t Fr n . g.Fn. c.on, p.Fa. s=s t. I(1 s n er&%CWrn e i g.Fl. u.e4 i 7) wdA%he.4 .PC7 nir as of Nrr. ~.pf f p t f r* =8
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- 13
= s.. F.* .i. i MAP NO: N1-2-3 DK"E: 1/20/80 POWER = 3% CONTROL ROD POSITIONS: F = 1.611 QPTR: LH I T NW - 0.988 D BANK AT 228 STEPS FQ = 3.000 C BANK AT 228 STEPS 1.866 NE - 0.916 F I = 3 A.O. = +46.721 SW - 1.084 i i BURNUP = 0 MWD /MTU SE - 1.012 I 49 ) I
Figure 7.5 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST 1 ASSEMBLYWISE POWER DISTRIBUTION HZP D-BANK AT 0 STEPS AND C-BANK AT 118. STEPS a t a u e a
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8 l.?s. l.74 . n.sf 1.1= . 1.n) 4.1. 't. F. 1.a 17 7.7. a.* 4./ I s av s4< n.74 4.** e rav..9 p.%= .-c i mis s t s. hts. 8% n. 7 en. p.F3. 4.pn. ' 6 d l a t a >=.. 3.F 3.. e.%. MAP NO: N1-2-4 DATE: 1/20/80 POWER = 3% N F' 8 1.930 QPTR: CONTROL ROD POSITIONS: = 4 I D BANK AT 0 STEPS FT = 2.946 NW - 0.990 Q I 1.353 NE - 0.968 l C BANK AT 118 STEPS F = l z A.O. =-13.600 SW - 1.034 BURNUP = 0 MWD /MTU SE - 1.008 50 I
l Figur.2 7,6 -. s l NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION l HZP. D-BANK AT 100 STEPS a P to e L m J n u e t u 0 1 a 0.71. PeEDICTED 0 71 0.86 ShEDICTED "EA*VhED . 0 73. 0.A3 0.69.
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l l y y Figura 7.9 !L NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I/E CALIBRATION - APDM FLUX MAP ~ l L ....ni. .si...... v.ri - ir i =.. ( ..~,.a.~ .:. i.. - e.~. i1 ...i....., .-. a.r . i. : . i.i-....... i.>a i.n..
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Figure 7.10 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST I ASSEMBLYWISE POWER DISTRIBUTION 4 I/E CALIBRATION - APDM FLUX MAP 1 s i.u. nic r e n . o...........se ..a r n n.. ~..~.e i - s o.. . n. r,. o. n. a.is. .s. .~ri a s u. a. i... . r i.n..,... r.. ..s. ~.> i.s>. i.ni. a.r>. -- -. a o r, i.n3. i.se. o.a.. i.>i.i.or...r .,.r . i.n.. i.>~ a.n. ..i. -<. -i.3. -i.i. i.a...i ..i. i. n..,. i t ..... i. i.. n. <.. n. % . a. n. i. n. a. 4-I <. r i. i. r u. e..... a..<? . i. o r. e... :..i... i.i......i.. 1 s. ~.- - s... - n. n. -s... -~...... o. - n. - i.e 3., i.c, . i.ia i.a-.a.r.a.n. . a.n ,t.r i. r., , i.o.. i.a. ....e-
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Figure 7.13 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST ASSEMP.LYWISE POWER DISTRIBUTION I/E CALIBRATION - APDM FLUX MAP I g L r. J n e J ( e = 4
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Figura 7.15~ NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST ASSEMBL WISE POWER DISTRIBUTION I/E CALIBRATION - FLUX MAP = e a 6 6 a n 4 I PREDICito . 0 71 0 88. 0.71. PA401C750 5 1 "Easuato . 0.73 0.90. 0.73. mt&16A80 27. 27. 2.7. .FC7 O!FFEA&NGE. .PC7 O!P8tRthCE. ....eeee........ 120.101 0.71. 0.71 1 01. 1.20 0.99 2l 0.76. 1.01. 1.88. 0.97. 1 19. 1.04 0.74 2.7. 4.4. 3.6. -0. 6. - L. 5. -1. 6. -0.4 . 0.71 1.15. 0.94. 0.95. 1.13. 0.95 0.94 1.15. 0.71 3j . 0.76. 1.18 . 0.72 1 17. 0.94. 0.92. 1.09 0 93 0.95 0.1. 2.2. 6.2. . -2.4.
- 1. 7. -0. 6. -3.5. -3 8 1.9.
1.10. 1.06. 0.78. 0.71. . 0.71. 0.78 1.04. 1.10. 1.08. 0.97. 1.08. 1 01. 0.40. 0.76 4 1 10S . 0.72. 0.79 I'.06. 1 09. 10S.094. 1 04 3.6 0.8 1.9 1.9 1.2. 1 3. -0. 2. -3.0. -3.1 -4. 2. -1. 4. 1.20. 0.96 1.06. 1.15. 0.71. 1.26. 0.98. 1.12. 0.98 0.71 1.15 1.04. 0.96. G.75. 5! 1.18. 0.95 1 06 1 17 1.19. 0.95. 1.09 0 95. 1.06. 0.96. 0 71 . 1 16 5.2. -2.2. - 1.6. -0. 2 2.6 0.2 0.2. =0.2. -0.3 -0.6. -2.6. -2.7. -3.3. 1.01 1 10 0 14 1 20 . 1.06 1.18. 1.02. 1.18. 1 04 1.10. 1.20 . 1.01 0.94 'I 1.0*. 6 i 1.02 1 17. 1.08. 0.96. 1.10. 1.19. 1.03. 1.16 1.00. 1 14 . 1.03 0.96 0.0. 25. i -2.2 -1.6. . -2.5. -0.8. al.7. -2.1. -3.4 0.4 -0.6 1.4. 1.4 0.71 i . 0.99 1.18 0.98. 1.08 0.99 1.20 1.19 1.18. 0.99 1.08 0.98. 1.20. 0.99 0.71 0.96. 1.16. 0.98. 1 16 0.97. 1 15 0.95 1.w-0.#2. 1.17. 0.71 7 1.08. . 0 73 e 121 0.96 -29. -6 1 -2.8. -1.9 -0. 3 -2 7. -25 2.1. 1.3. 1.0. -0.5. -2. 0. -1 6. - 1 9. -2 4. I 1 0.38. 0.89 1.11. 0.97. 1.12 1.02. 1.19. 0.92 1 19 1.02 1.12. 0.97 1.13. 0.49. 0 48 -2.9 O.*. 2.8 __. S 0.93. 1.01 1.18 0.91 1 17. 1. 00. 1.09 0.93 1.13. 3.9) 0.97 1.12 0.90. 1.00. 1.14
- 0. 2.
-0. 5. -0. 6. -0. 9.. -1. 6. -2.1 -2.0 -29 -. 1. 2.1. 13. 0.8 1.2J. 0.71 1.18 3.98. 1.08. 0.95. . 0.99. .I . 1 08. 0 98. 118 099 1 19 1 20. 0.95 0.71. 9-1.21 0 74 1 06. 0.d4. 1 16 0 96 . 1.09. 0.98. 1.1F. 0.98 1.18. 0.98 0.73. 1.21. 0.96 3.7 -1.7. -2.1 -1.1 11 -0. 8. - 1. 7. -1. 2. -1. 8. -1.9 2.1. 1.6. 1.1. 0.6 -3.2 1.01 1.20 1.10. 0.96. 1.06 1.01. 0.94 1 10. 1.20. 1.04. 1.18. 1.02 1 18 1.05. 0.97 1.12 1.22 1.05. 1.1S. 1.00. 1.15. 1.J2 1.18 1.10. c.15 1.05 10 ~ 32. -1.6 0.5 J.* 31 31 2.2. 17.
- 0. 6. - 2. 2. ~ -1. 8.
-2. 7. - 1. 6 1.23. 0.96 1.06 1.15 0.71 l 1.40. 0.98. 1.12. 0.98 1.04. 0.96 0.71. 1.15 . 0.73. 11 1.18 1 06 110.0.95 119 . 0.96. . 1.19 0.96 1.07. 0.98 C. 74 1.19 3.3. 33. 2.9 2 1. -0. 2. a l. 9. -1. 9. -2.9. -0. 8. -0. 5. 2.1 2.1. 31 ) . 0.71 0.78. 1.04 1.10. 1.08 0.97. 1.08. 1.10. 1.06 0.78 0.71 1.10 1.05. 0.61. 0.75. 12 0.81 106. 1 10. 1 05. 0.94 5 06 0.76. S.3. 35 0.4. -2.9 -3.1 -2.2 0.2. 0.3 3.5. 2.8 2.1. 0.71. 1.15. 0.94. 0.95. 1.13. 0.95. 0.74 1 15 0.71. 0.95. 1 18. 0.75. 13 0.95. 0.92. 1.10. 0.94 1.19. 0 76 2.0. S.3. 3.3. 1.1. -3.2. -2. 7. -1. 5. 0.5. 3.4. 0 71. 1 20. 1 01. 1 01 1 20 0.99 . 0.71. 1.02. 0.73. .16 1 18 . 0.74 1.0$. 1 19. 0.98. 2.0 -1.5. 0.4. 3.3.
- 3. 9.
-0. 2. -0. 4 n .......e........ .....................e............................ STA6taa0 . 0.71. 0.84. 0.71. AvfdAGE i . 0.74 0.89 0.70. . PCT O!FFEntNCE. 15 Otv1.TICN 2.0 4.S. 1 7. -1 3 1.a49 MAP NO: N1 '.-15 DATE: 2/7/80 POWER = 99% N 1.387 QPTR: CONTROL RCD POSITIONS: F = 1 AH I D BANK AT 228 STEPS FT = 1.762 NW - 1.001 Q 1.113 NE o,994 C BANK AT 228 STEPS F = z A.O. = +0.127 SW - 1.010 i BURNUP = 300 MWD /MTU SE - 0.995 60 tI l
Figturo 7.16 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST ASSEMBLYWISE POWER DISTRIBUTION I/E CALIBRATION - FLUX MAP A P = m 4 a J H G F 1 0 C 8 4 Pet 01CTED PREQtC7ED . 0.71 0.87. 0.71. 1 . 0.73. 0.90. 0.73. eta $URED . measunto. .P;7 OIPPEA9hC8. 3.8. 3.8. 3.6. .PC7 OIP8tRthCE. f I . 0.72. 1.02. 1.19. 0.9 7. 1.19 1.02. 0.72. 0.75. 2 l . 0 75 1 02 e 1 18. 0 96. 1.19. 1 05 0.2. 3.0 45. 4.2. 0.3. -0. 8. -0. 9 ............................................... a............... 0.72. 1.16. 0.95. 0.95. 1.13. 0.9%. 0.99. 1 16. 0.72. .___._..3 I* 0 92. 1.09. 0.93. 0.93. 1.19. 0.76. 0.73. l.18. 0.95. 22. 6.3. 2.1. 1.9. =0.0. -3.2. -3.5. -2.o. 0.0. . 0.72. 0.79 1.05. 1.10. 1 08. 0.97. 1 08. 1 10 1 05 0 79. 0.72. 1.06 0.81. 0.74 4 . 0.80. 1.06. 1 10. 1.05. 0.94. 1.0*. 1.08 1 74 -1.5 0.7. 2.0. 3.7. -2.9. -3.0. -6. 4. 2.5. 1.2. 1.2. -0.4 0.72. 0.98. 1.12. 0.93 1.19. 0.97. 1.01 1.16 . 0.72. 1.16. 1.05. 0.97. 1.19. _ S 1 17. 0.95 1.05 1.19 0.76 0.9%. . 0.72. 1.17. 1.04 0.96. 1.18. 0.95. 1.09 -0 5. =0 9. -1 2. -3 0. -3 1. -3.6. -2.2. -1.6 -0.2. 2.4 S.* 10. 10 1.10. 0.95 1.02. . 1 02 0.95 1.10. 1.19 1 02 1 17. 1.02. 1.17. 1.02 1.19 1.06. 0.95 1.05 6 1.17 . 1.0*. 0.97. 1.10. 1.18. 1.0".. 1.14. 0.99. 1.13. 0 99 -1.5. -1.8. -2 5. -2.4. -3.9 -3.0. -2.1 -1.6. 0.2. 3.3. 1.9. 1.9 0.2. 1.08. 0.95 1.19. 0.71 1 17. 0.93 1.19 0.99. . 0.98. 1.17. 0.99 1.08 . 0 71. 1 19. 0.95. 1.08. 0.95. 1.15. 0 97. 1 16. 0 94. 1 13. 0.94. 1 04. 0 93. 1 17. 0.71 7 1.21. 0.96 . 0.73. .I -3.9 -*.3 . -4.1 . -2.5 -1.6 J.e. 1.3. -0.1 -2.8. -2.2. -2.6. -1.0. -3.9 3.6 2.0 C.97. 0.87 1.G2. 1.19. 0.93. 1.if 1.02. 1.12. 0.97. 1.13. . 0.87. 0.97. 1.13 0.97 1.12 0.98. 0.90 8 1.10. 1.07. 0.93 1.16. 0.98. 1.13. 1.01. 1.17. 0.90. 1.15 0.98 . 0.90. 0.99 . -4.5 -*.1 -4.6 1.2. 3.8
- 4. 3. -0.6. -1.5. -2.3. -3.4
. -3.4 1.0. 0.8 3.6 2.0. 1 19. 0.71. 0 95. 1.17 0.99 1.19. 0.9) 1.17 0.98 1 08 . 0.71. 1.19. 0.95. 1.04 . 0.98. 1.13. 0.95. 1.0a. 0.94 1.21. 0.76 91 . 0.73. 1 22. ,.96 . 1.tc. 0.98 1.17 0.99 1.18. 0.96 2.1. l.* 1.0.
- 0. 3.
-0. 3. -0. 8.
- 1. 3. -3.1.
-3. 4 -1.1 -2.! . -1.1. 1.7. 4.4. 3.6 1.02. 0.85. 1.10 1.19 1.02 1.17. 1.02. 1.17. 1.02 1.17 1.10. 0.95 1.f2. . 1.C6 12 . 1.17 1.10. J.95 1.21. 102 11S. 1.00. 1.14 1.00 1 12 1.C S. 0 9 8 e -2 1. -0 3. 03. 39 3.2. 3.2. 1.9. 1.1. 0.2. -1.9. -1 9. -3 3. -2 6 ...............e............................................................................ 0.72. . 1.89. 0.97. 1.05. 1.16 . 0.72. 1.16 1.0$. 0.97. 1.19. 0.98. 1.12. 0.95 0.74 ?.1 1.18 0.95. 1.37. 1.19. 1 19. 0.96. 1.10. 0.95. 1.20. 1.08 0.99. 0.74 21. 3.6 3.3. 3.3. 2.9. 2.0. -0.1. -1. 8. - 1. 9. -3.2. -1.* . -1.1 1.6 1 05 0.79. 0.72. 1 05. 1 10 e 1 08. 0 97. 1 08 1 10. 0.72 0 79 12 1.10 1.05 0.32 0.76 . 0.74 0.81. 1.07. 1 10. 1.05. 0.94 s.06 -3.0. -3.2. -2.4 -0.2 -0.2. 3.3. 56. 35. 2.8. 2.1.' O.2 j 1.16 0.72. 0.72. 1.16. 0.95. 0.95. 1.13. 0.95 0.95. 0.95. 1.18. 0.76 13 0.74 1 21. 0.96. 0.92. 1.10. 0.94 1.3. -3 2. -2.5. -1.2. 0.7. 1.7. S. 4 36. 39 1.02. 4.72. 0.72. 1.02 1.19. 0.97. 1.19 0.73. 1 0.75. 1.06 1 20. 0.97. 1.18 1.02. 3.9. 4.7.
- 0. 5.
0.2. -1 1. 0.6 1.7.
- I 17aN0aa0 0.71. 0.87. 0.71.
AVERAGE 15 GEVIATION . 0.76. 0.89. C.70. . PCT 017Ft AE ACE. S.6. 2.8 -0. 3. 26 1.398 MAP NO: N1-2-16 DATE: 2/7/80 POWER = 99% N 1.403 QPTR: I CONTROL ROD POSITIONS: F = AH Ff=1.902 NW - 0.997 D BANK AT 208 STEPS I 1.201 NE - 0.992 C BANK AT 228 STEPS F = 2 A. O. = -7.267 SW - 1.014 BURNUP = 349 MWD /MTU SE - 0.997 61
i E1Lgtura 7.17 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS TEST I ASSEMBLYWISE POWER DISTRIBUTION HFP, EO. XENON .a - d 6. A w a w t w s a .I -dtblC tr a 0.78 0 4T. c.14
- tulCftb
- F.%vwE9 1
. 0.7.. v.F . 0 91 =tatuvtJ +.a. *.*. e.J. .*Cf clF8t ENCE. .vCf UlFFL-U.Ct. o.71 . 1 19. I.ul. 0.71 1.08. 1.tv. v.es 2 0.75 1 60. l.le. u.17. I.de. 1.0% 0.1.. 4.). -v.7. *w.e. -9.4 10. J.7 5.5. . 1.ws. G.ws. 8 14 U.#1 9.ws. o.ws. 1.11 . 0.11. l.8% I .- ~ 3-1.19. d.77. 0.13. 1.li. 0.w . v.wd. 1.09. f.wJ. 0.vg J.0. F.= -d.3. 0.1 . d e o.. let. =0.d . -J.4. -J.% e............................................................e..... l.0w. l.10. l.6%. G.te. 0.11 l 1.tv. l.Jw. e.we 0.78 0.7w. 3.bg j . l.um. c.nl. 0 1%. . I.uw. l. os. v. -.s 34. 1.nw . g.7s. v.no. l.we -Jee. -J.I -J.e. -l.o. l.4. d.1. e.e e i ds. 14. 1.* -o.O. l c.rl. . 0.we. 1.l?. 6.9e. l.89 n.,F. 1 43. 3.15 . l.ub. d.w?. 1.19 1 13 . 0.11. I 1 19 . u.in. 0.99. 1 87 G.93 1.us 0.72. 1 14. 1.d4. 0.94. I.16. v.ws. 1.09. 1.0 3.% -J.e. -d.d.
- l.)
o.J. - -. 64. 99. *Wed. =0 6. -l.9. -d.w. -J.4 i 1.ul 1.uJ. 1 1/. 102 111 . 1.dJ l.19. l.50. w..* . 1.0L. D.w%. 1 34. 1.19 I 0..%
- l. %
. 4.u). 0..e. 8.!!. 1.le. 1.*d. 1 13. u.4e. I.lJ. 1.00 1.lF b 4.pn -s.* =c.) . -d.4 -=.4 -J.d. */.J n.a. J.w. -l.. v.o. =0.7 1.s 19
- 0. 5. 1.19. s.11.
l.00. 3.11. 4.46. l.ww l.10 . 1 19. 4.w4. a.ww. c.we. l.11. l.Jv. weil . l.tr 0.74 7
- o. 3 1.42. 0.wJ l.J.
0.64 . c.ve, l.de. 0.44. 1.lb. 0.97 1 15 0.F2. 1.21 =6 1. -+.6
==.M -..J ./.6 . -l./. J.8. -d.* . -c.w. -J.A 2.5. 15. 10 -4.e. -2.7 l i 0.ef . u..e. tenJ. u.wd. 0.93. I.lw. 1.dd . 1.le seef. G.9e. leal e Gews. 1 1d . 1.ud. 1.tv. . U.ww 0.wl l ai. 0.d. l.ld e 1.li. 0 96 . 3.13. 9 99. l.dt 1 11 6.=4 . 9.wv. 1.le . veva. .T 1.a -e.M .../. -/.6 -d.#. -J.J. -J.e =0.4. -l.3. -1.* . -l.i 4.* o.t. d.S I . 0.71 . u.ws. l.!*. J.11 1.11 1.64. 4.we. 1.11. l.de. 1 19. I.ud. l.ww 9. 'e.. 1 49. u.w%. l.77 G. t* 1.16 0.ww . 0.97 1.16. 6.dn. 1 17. 0.wl c.**. L.un 1.ww 4.74. 1.d4 9.=*
- 3.1
-t* -4.9 4.* 5.h. =l.5. -J.d d.). l.6. 41. -v.0 . -l.e. -l.a. al.4. . -J.J. 3 1e. U. *. lovl. 1.u) I.tv l.02. 1.11. 1.19 1.wJ. l.it . 1 48. 0.w%. 1.lu. . 0.v4. 1.us e aw l.lf 1.I+. 4 00 . 1 10 . 0.49. l.it. led!. l.uJ. 1 15. 1 00 4.v6 I -J.* . -d.5. *d.d. 0.4. 4.6. .4 J.I. 3.1. l.9. 1.d. -0 1. -d.. . -d.0 1.us. 1.15.. 71 1.tv. U.wm. 1 17 3.we. 1 19 0.41. 0.47. . 3.F8. less. l.9% l.dr. l.no. d.f* 11 1.!T 6.7= . l.43. 1.un. 0.Se. 1.49. 0 9e. 1.lc. 0.45 . G.we. d.* J.e. . 39. J.4. J.d. les. -c.*. -del. -d.1 . -J.e. -1.6 . al.1 d.d. I . voit 0.11. . 1.e%. 0.79 1 09. 1.10 v 79 14U 1 09. U.48. . 0.11. 1.W5 Ic 0 14 0.e2. lest. l.80. leds. 0 9e. 1.0e. 1.04. 4.w . 0.ed. J.h. 5.7 . -v.5. -0., J.J. l.5. c.d. -3 4. *J.J. -d.g 4.h. 0.9%. I.1). 4.ws. G.ws. 1 1%. 0.71 0.Fl 1.tv. 0.95 . d.le. IJ l.lf I ~ ~~ ..eee.................e..e....e.....e.............e............e l.10. o.we. 0.w4. . W.75 l.de. o.90 . U.we. 1.5.,37 l.J. -J.5. ad.5 -1.* o.d. J.9 ..d U.11 1.ul 1 01. 6.!w. v.we. 1 19. 4 . 0.71 14' 1.id. 1.pd e 0*It. 0 14 . l.De. 4 49. Weed 3.w. o.e. 0.d. 0 1. -l.d.
- o. F.
l.b. I - - - - - -. - Ot v l a l lus. ............ee.............. ........e..... 0.it. a v e. a ns 0.71 0.mF blahunau .dct DIF5t-e%Lf. le 0.73. v.wo. 0.71. d.. s.i. 30 o. i.. i .i.5 1 MAP NO: N1-2-18 DATE: 2/14/80 POWER = 100% CONTROL ROD POSITIONS: Fh=1.395 QPTR: D BANK AT 213 STEPS FT = 1.776 NW - 0.995 Q I C BANK AT 228 STEPS h = 1.124 NE - 0.994 A. O. = -0.553 SW - 1.010 BURNUP = 570 MWD /MTU SE - 1.001 62 II
1 Figure 7.18 NORTH ANNA UNIT 1 - CYCLE 2 BOL PHYSICS ESTS 1 PERCENT OUADRANT PCWER TILT vs. POWER LEVEL 1 I +10 +8 l A - SCUTHWEST QUADRANT i C - NCRTHEAST QUADRPliT +g
- 3. -
3 +4 ^ I w w m $4 I m 0 __w m e W I g -2 C a o 4 4 I 7 7 .n;. -6 -8 l '~~ -10 i 1 O 20 40 60 80 100 I 1 POWER LEVEL (% FULL POWER) l es
f S7ction 8 j H l e L E u F REFERENCES lu 1. M. C. Cheok, S. A. Ahmed, and R. T. Robins, " North Anna Unit 1, Cycle 2, Design Report," NFE Technical Report No. 127, November, 1979. y l 2. North Anna Unit 1 Technical Specifications. l 3. T. J. Kunsitis, "RXFIOW, A Computer Program to Calculate Reactor L Flow end Thermal Output," NFO-CCR-8, Vepco, December, 1979. 4. "Tecnnical Manual for Westinght.,use Solid State Reactivity Computer," Westinghouse Electric Corporation. 5. Letter froh Mr. C. M. Stallings (Vepco) to Mr. H. R. Denton (NRC) { dated November 2, 1979. 6. W. Leggett, and L. Eisenhart, "The INCORE Code," WCAP-7149, December, 1967. I 7. Letter from Mr. C. M. Stallings (Vepco) to Mr. H. R. Denton (NRC) dated March 11, 1980. I 1I lI i u 64 y
L 5 e APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS E [ i = [ F L I.
( I l l-PT-94 ATTAC: OLE:1-' 6.11 [- hi [3 [ Q [," ^ ! *1 ' "~' 12-I6-79 l
- *
- 6.
. i - s. s.>.._.* Page 2 of 35 L North A.:ns Power Station Unit l_ Cycle l Startup Startup Physics Tests Kasults cr.d Evaluati n Sheet ~ I Test
Description:
Reactirity Cc putar Checkou Refer==:e Procedure Ku her/Section: 1-PT-94/ APP.3 sequence step Number: y i II Back Positions (steps) RCS Teeperature (*T): 5479 ~J ?over Level (IT.P.): g Test Cen><-#cas 'SOA: 223 SD3: 223 CA: 228 Other (specify): (Desia) C3: 223 CC: 228 CD:
- 3elov Nuclear Heating RCCA: NA
- At the. just critical pcsition II'I 3ank Positic:s (st.c;:)
RCS Temperature (*7): ft/5 7 Power Level (%7.P.): g L Te t CA: 2.7.d$ Other (specify): Conditicus $2A: 22.'6 ED3: 2. 2. *j (Acr=si) C3: q2,g CC. ;.1 a( CD:/w/,.fj gg py,, g, jjg,,, y,gg;, r A//4 Date/Ti=s Test / - 14 "i o Perfor=ad: o q c 7,,,7 3 c 40c = Measured reactivity using the reactivitf h eured Pars tar a (description). cc puter Aor = Infe-red remettvity fren remeter ear $d. 21 . O, O 3 df ( [/g /M urf 1:easured Valua l Y r. ~ Y r_ l g O* b Test resip Yalue i Rasults (A.- % 1 Ccaditiens) [ g p, [** I. acc - der Desi p Yalne < 0.04 f (Desi p Cenditicas) Apr WCAP-7905, Rev. 1, Table 3.6 2aferesce 1 Y TSAR / Tech Spec NA Acceptacca Criteria Refercsce NA Yl/rk/n J il b Lt.dwA ds-a l Gatriv11Y kap &G = $ 6 0 j:? c t1 y Ceep1.ted By _./>_ Evalusted 3y / N.,, 4 /I, stArtup Test Ingineer / / Reccer-cruled Tor / Approvs1 sy / [ y yrc z.,,1 e, I i A.1 l
s 1]IQ I 'I T. C C' ! -I If'g[i t \\ Lv Ll L 1_p;.94 h i-ATTACIC'.E:C 6.11 12-26-79 !! orth Aans l'over Staticti Unit ~1 Cycle 2 Startup Page 12'cf 35 ~~ Startup Thysics Tests Results and Evaluation Sheet CCI! TROL DA X D UCRTH IMMURD ENT I Test Dc cription: Referencu Procedure Nurtar/Section: 1-PT-94/ APP.E sequence Step Nuador: 7 II tack Positions (stepc) RCS Teepor:ture (*T): 547-5 Power Level (:r.P.): O I Test Conditions 3rd.: 223 sts: 223 CA: 223 other (specify): l (Design) C3: 228 CC: 228 CD: !!hving Below Nuclear F. eating I P.CCA: NA E III Eank Po:ittens (steps) RCS Teeperature (' ): 54(, l Power Level (:T.P.): O I Test Conditiens 3DA "L1 9 SD3: 71% CA:128 Other.(specify): ( 66 HJ~g { (Actual) C3: 2/2.3
- :.?
CD: Mad Date/ Time Test 1-11-30 Perfor: d: c(,IO - 0 914 Hessured Para:eter I ; Integral Ucrth of Control Bank D p (description) I IV g f !!casured Value fQ69 pe,m Test Design Value 1 OM "4"" I (> 4 [& Results (Actual Co.ditions) f l l B Design value 1095 + 164 pcm l (Design Conditions) Vepco NFE Technical Report No. 127, November, g B Refercace
- yn79, If Castan Acceptance Critcrica is =Esedec.
tr.en assure ads qusta s'nutdew. =argin and/or V TSAlt/ Tech Spec e-aluate other accidents, as eccessar I Acceptsace C#1***1^ Letter from C. M. Stallings (Vepco) to E. C. E*f***"** Case (tmC) dated "av 11. 1079 (cerial W. ?m. i Qg g % }gyc,q, met, VI J Ac.cep b ec Cr. N m g-Cosencats .1 [behe$ Evalusted By f Completed 3y m se ccup I dt.'Enginect g I tecoaccisaed Toe AppNval Dr l f NTO Ingineer l l l A.2 I l l .a ..... ~,,
1-PT-94 l AT*"ACIC'.rc 6.11 P li V M p-( E.D ;... nvLi0 12-2s-79 y ..g n ! Pays 13 cf 3S North A. ins l'over Station L' nit,,l_ Cycle 2 Startup Startup Physics Tests Results and Evaluation Sheet I Test
Description:
CONTROL BM*K C b' ORTH MEASt.'RE CIT - BMit: D IN xetetenen Procedure Nu.1cr/Section: 1-?T-94/ AFP.E.Scquence Step Nur.ber: qg N II tack Posittens (steps) RCS Ter par ture (*T): 347~ l Power Level (~F.p.): 0 Tect CA: other (specify): Conditions SOA: 228 3038 228 228 (Design) C3 CC: CD: 228 m, Moving 0 Belev Nuclear Heating NA III Bank Positions (steps) RCS Te:perature (*F):. IV-f Power Level (%T.?.): o Test Conditions SDA: 2.2.8 SD3: 320 CA: 220 ether (specify): I (Actual) C3: 7. 2,8 CC: Mova*ng CD: o RCCA: yp Date/ Time Test /-/P-70 Perfer::d: / f /o - f y.s-g V.aasured Part=eter (description) I ; Integral worth of Centrol Bank C C 1 IV I licasured value pCg em Test Design Value Results (Actual Co ditio:s) h3 .j / 3 / gen; Design value 873 + 131 pcs ~ (Desi;n Conditicus) Vepco NFE Technical Report NO. 127, Nove:ber, Reference
- 1979, If tesign Acco;cance criterien is c.tceecet, V
FSAR/ Tech Spec then assure adequate shutd:. s cargin sed /or evaluate a:Ser seeidents, as necessarv. Acceptance Criteria Letter f rom C. M. Stallings (Vepco) to E. G. Reference Case (NRC) dated May ll,1978 (Serial 50. 272). VI D6G ' n Ner<vs'ce !?? C S Cosa:nts kCc ep1{Arrec. 0rifeWA MC Evaluated 3y b Y. e-d/ Completed ::y / Enginsc 5tptupTest Recem-muded For M Approval Dy / I Hr0 r.ngineer 1 A.3 i i
T-94 ATTACTE ;7 6.11 m-r.'
- ;.m 12-26-79 tP ps a
L i, s \\l 1. _ < 4 caJ Page 14 cf 35 I \\ i.V ' 1i North A. ins Powcr Staticu 1:ni: 1 Cycle 1 Startup Startup Physics Tests Results and Ivaluation Sheet CONTROL BA:"* S '.' ORTH !!E.\\SU".EENT - BANKS C,D I:1 I Test nescription: Refctencu Procedurc Nu-lar/Section: 1.PT-94/ APP.E SC9uence StcP Numbcr: q/ +0 II Eank Pesitirns (stcN) 7.C5 Temper:ture (*7): 347. ~# Test Pcver Level (%F.P.): 0 Conditions 50A: 223 S:32228 CA: 223 Other (specify): CD: (Design) C3:!'.oving Cy, o 0 Belcw Nuclear Heating ' ' " ^ L III Bank Fositicas (ste s) RCS Temperature ('T): S*N Test Power Level (%T.P.): o Conditions SDA: ~2. 2. 9 SD3: 2.? 8 CA: 2.23 Cther (specify): CC: o CD: o (Actual) C3: Movig 13eJow Aluclen-Yedi Date/ Time Test /// P-/9 / Fo Performed: e,,: o % Heasured Para:eter I ; Integral k' orth of Control Bank 3 g (description) 1:easured Value f3gj Test Design Value Results (Actual Canditicas) [ 3 .8 2 / 6~ g cny I Design Value 1434 + 215 pcs (Design Conditions) l l Vepco NFE Technical Report l'o.127, November, B Reference
- y979, li Design Ac:eptance Criterion is ex ecces, then assure adequate shutdevn =argin and/or l
y ygArt/ Tech Spec e<aluste other accidents, as necessary. l 3egepg,ne, I Criteri" Latter from C. M. Stallings (Vepco) to E.G. Case Reference (NRC) dated Unv 11,1078 (serisi No. 272), l VI D C $ia, To ler.anee m e.& Coracnts l Accepkee Cr o*fe&c. m e 6 dd_ Coopleted By kk N Evalusted By septupTestEngineer Reco. mended For -f f/ l Approval 3y I A O NTO ragineer t A.4 g l. --- - ----- a ..- ~.
1-PT-94 b*jhI/\\[e I N /". L. IIL.U U L.I d 12-26-79 I. T ~."- l * ~ ~O ATTACIC'.r:T 6.11 Page 15 of 35 llorth.una Power Station 1 nic _1_, cycle 1 Senetup startup Physics Tests Results and Evaluation Sheet I Test Der:cription:CCN~~10L BL'K A WORTd !!EASURC1ENT-BA!:KS B,C,D IN. Keference Procedure : ura,cr/Section: 1-PT-94/AFP,E Sequence Step n = der:,p g -H) i II Each Posittens (=teps) RCS Tc Te.rature (*7): 347 -3 Power level (::F.P.): 0 Test Conditions SOA: 223 SD3: 228 CA: Moving ccher (specify): (Desi:n) C3: O CC: O CD: o nelou Nucicar Heating F.CCA: NA I III Eank Pocicions (secos) RCS Te=perature (*F): 346 Power Level (!;7.P.): O Test l Conditions SDA: 418 SD3: 2~ M CA:PWIW#n Other (specify): (Actual) C3: o CC: O CD: O I RCCA: Wh 8,ELO W N h C.L.6 h E. N 6 h'I W h. l Date/ Ties Test I"I9"EO Perforted: 132,5 1%'29 l'.casured Para =eter IA; Integral Worth of Centrol Bank A (description) l IV I !!easured value l%[ fC.Tn-I Test Design Value g48O 7 hN. F Results (Actual Conditions) Design Value 1649 + 247 pcm I ~ (Design Conditions) l I Vepco NFE Technical Report No. 127, Novenber, Refarcuce
- gg79, B
11 Design Acceptance Criteri:n is exceecec, th:n assure adequate sr.utde.m ::rgin and/er l V FSAR/ Tech Spec evaleste other seeide.:s, as neemsserv. Acceptance I. Criteria Letter from C. M. Stallings (Vepco) to E. G. Reference ' Case (NRC) dated May 11, 1973 (Serial No. 272). t l g c,j'oe, E s14 w rob E R. Pet 9 d. E. A G. T. A C.c.EPTivNC.C CR.tTER)er ME!T-Ceepleted By W Evaluated By /k. stfecup re:sc T.nsincer Ecconcended Tor M f/ Approval SY // l t L A.5 r (. -.... _
^ 1-Pt-94 A':'"'ACn!'.I:.'"' 6.11 [_..BiA.\\{ I n 's. r 1 -(1 .m g I l \\1s/ g-(i v t./ ; ; 3 12-2o.,9 . i Page 35 of 35 !! orth A.m l'o or Station L' nit 1 Cy:1e 1 Startup [. Ctartup Physics Tests Results and Ev.Uustion Sh t n I Test Deceription: SHUTDC*41 EMIK 3 WCRTH MEA 50?M!I:iT,CCNTROL EN*KS I': neference Procedurc Nu.Lcr/Section: 1.PT-94/ APP. H tequence Step ::un.:,ce: g II Eank Positions (step ) RCS Tc: prar cure (*r): 54[ $ Test payer teyet (.;p,p,) 0 Conditions Sta: 228 SD3: Moving CA tC Cther (specify): (Design) C3: O CC:0 CD: 0 RCCA: N/A 2elow Nuclear Heating j i III Bank Positions (steps) RCS To:perature (*T): 6% Test Power Level (%7.P.): 0 Cenditions SM: RA[y Sug: Moviwc CA: O . Other (specify): q (Actual) C3: o CC: O CD: o RCCA: Wh f*> 6-l-O W N\\JC.t GhC HENTINC, Date/Tf:.c Test g-Ao-20 Perfor: ad: c4. g,3 - 0 6 0 S Keasured Pera ster I (description) ISDB ; Integral Worth of Shutdevn Bank 3 17 I 9 3 3 > c vn-1:aasured Value Test 04s!(,n Value () O 7 "-t-13 6 *Cm - Rescits (Actual Ccaditio.s) Design Value 907 t 136 pcm (Design Conditions) Menorandum frem M. L. S=ith to E. J. Lo:ito. Reference dated Decenber 7,1979 If Design Acceptance Cr?.terien is exceeded. V P!AT*/ Tech Spec then assure adequsta shutdevu =arp,in and/or 3,g q ggg, evaluate other accidents. as ascessary. Criteria Letter fres C. M. Stallings (Vepec) to 3. C. Rusche Ecference .(N2C). dated May 14.1975 (Sartal No. 017/042373). VI T E. si Giw 10c cs.#r+Jc.C MET L Ca.-ant: Acc.G PTArtJc.C. CRITERi A P4G T. [ IM. tvaJuated ny 8 bM Cn;iletea cy 7., ns. :.. ;. u n nee: nece =.en. tea r3..r.. r ai.e t.,v.il. x m re-in.,: . A. 6 s ~ ~ -~~ ~ ~ ~~ ~ ~~ ~~ ~ .. - --- - -. ~ -- + - ~ ~
f I l 1-FT-94 l AT"'ACICC:.7 6.1; I l7. e r p,, L., c -. ; i.,~.-s 12-26-79 l%[ I\\L v L',sL. : d. Page 16 of 35 .- w - llorth A.snt l'cuer Station tr.it i Cycle 1 Startup l Startup Physics Tests Results and Evaluation Sheet In Overla Test
Description:
Rod 'a' orth !!essurement - D.C.B,9' tep !.wne:p.jg 1 Sequence l Proccdure 1:wtber/Section: 1_pI_94/ App,y xcference I +0 II Back Posittens (steps) RCS Te: rar:ture (*T):5!.7,3 Power Levcl (%T.P.): O Test Conditions SOA: 22S SD3: 228 CA: Moving other (specify): CD: Moving Below Nuc1 car Heating (Design) C3: Moving CC:1!oving Ib NA l III Bank Pocitions (semos) RCS Tc=perature ('T): d6 5 Power Level (%7.P.): O Test Conditions SDA: '17.9 SD3:0.'tS CA: Mom other (specify): (Actual) C3:Mov, CO. Ne e CD:Nov k Datc/Ti=c Tese ! ~2.0-% f Perforced: 0604 - IWF "] 'd
- *[ *
- IDC3A; Inte;;ral Worth of Control Bank D C,3, A g
In Overlao f IV Measured Value 493% Pc " Desi n Value OC466 W Test C I P Results (Actual Cenditi x.s) A at 0 steps Design Value 3o3,' ~+ SOS Pcm (to D at 228 steps) X (Design Coaditions) Vepco NFE Technical Report No.127, Nove=be Keference 19794 I If Design leccitance Criter.:n is exc:esec, then assura adequate shutd -e. =argin and/cr V TSAR / Tech Spec evaluzte ethe-accidents, as -ecesserv. Acceptance II Criteris 1.etter frcra C. M. St:llings (Vepco) to E. c. Reference Case (NEC) dated W v 11, 1973 (sert 31 go, 37c3, Ab.ss' ~ Tolcrec4. mei.p % e. G. % a m e~r. Da VI l C*'"=*c' Compi.:ced Dy Evalusted Dy .M. Khrtup To:sc Engineer d Recomcieniled For y I Approvsl Dr / M i NTO Engineer l I ( A.7 i 1
I 1-TT-94
- ! !} p ATTACICCIT G.11 9 r-(C U L,. i s.)
1 l bC 12-26-79 ~ y Page 32 of 35 !! orth A. ins 1 evc Station Unit._1. Cycle.2, startup Startup Physics Tests Results and Evsluaticn Sheet I Test Dec.cription: TOTAL WORTH OF N-1 RODS Reference Procedurc !*urt.or/Section: 1-PT-94/A??. H Sequence Step Nundier: g 1 II Eank Positions (etcp:) RCS Terper:ture (*T): 547+O _3 Powcr Level (::P.P.): O Con ions SDA: O SD3: O CA: o other (specify): CD: (Design) C3: O CC: O 0 Wik 2f/WPo M.0/ a t 228 Eelev Nuclear Heating RCCA: H III Bank Po:itier.s (steps) RCS Te=persture (':-): Sylo 1 Power Level (::P.P.): O Test Conditiens SDA: O SD3: o CA:.0 . other (specify): (Actual) C3: o CC: O CD: O g gg,j RCCA: H -8 54 of 118 Date/~ica Tesc Perfor:rd: 1-s? i/1o/80 g Total Integral Worth of All Centrol gj)[j,,3 Heasured Part=eter (description) L I J-l and Shutecwn 3an,ts Less RCCA.iMI N-/S Measured value $'9 8-ll. pc. Test Design Value' loo'I'l i loo'l Dc.m f Results (Actual Ccaditions) I Design Value (Design Conditions) 6044 1 604 p Vepco N7E Technical Report No. 127, Refercuce November, 1979 ( "#8"# =" " CO 2 y TSAR / Tech Spec i-l
- $[*$
WCAP 9594, Table 6.3 and memorandu= fr== C. T. , e Reference Sncv to E. J. Lo:ito dated December 17, 1979 VI De,si ~ Tele,,mnta me_..t 1 C" " Ac.c9+ecc. CeMed **-
- 1"##
I Cosipleted By sc ttup Te::t f.n C sne e r (/ uconecuaed ror y Appe.sv.11 Dy /\\ MFO tagineer A.8
1_p;_94 Tp ATTACE!E2:T 6.11 I.~. j f.j. f*i t._ Itj h (~'O ' }* I {1 : Q ( !._ i O 12-26-79 l I sJ Page 3 of 35 hrth A.:ns Power Station 1: sit l_ Cycle 1 Startup I Startup Physics Tests Results and Evaluation Sheet l I Test Descrip_1on: CRITICAL SORON CONCIS~RATICM - ARO Refercsce Precedurs Nu:bar/Section: 1-PT-94/ APP.C Sequcace Step Number: f II Za=k Posittens (steps) RCS Te=prirsture (*?): 547 ) -M ~ Test Powcr Level (27.P.); O Conditions S?J.: 228 SD3r 228 CA: 228 Cther (specify): (D*81D) C3: 228 CC: 228 C3: 228 Below Nuclear Ecating r 15 ECCA: NA J { ECS Te perature (*F): 6"9 5~ 4 III Eask Positis:s (steps) Test Power Level (*.T.P.): o Conditiens SDA: 2.27. SD3: 2.28 CA:2.E F other (specify): (Actual) C3: agg CCt R2 & CD: 2E8 3cCA:ta Below IJoedcac Hessis Data /Ti=a Tase /-/6-80 Perfor=ad: 120 5~ M (C )ARO; Critic $1 Boron Concentration - ARO Measured Para =ater 3 (description) IV y.easured T..1cs C3= /353 PPS Test Design value 3I f 60 ppm Kasu1cs hr*- d Co dttions) Desi p value CB = 1319 + 50 ppm (Design Conditions) Vepco N'F. Technical ReporC No. 127, November I 1979 Y IsA2/ Tech sp d '. ( C=) x C3 f,,24,000 pcm Aciceptance FSAR Section 15.2.4 Esference Dseiy rbler m mec. }}e e.epw cr-;ter-ia. mes. gg Co m nes Use " "9*23.2#*/29* f # P#"1iM #7 *"#l *i** I C3 fed pm -for~ hinAl Mta. lysis. f = ~8.88 f 7E b Completed 3y n* */ Evaluated 3y spetupIcscEnt,2.ncer Eccometemted For /f / //. MAL Approvs1 3y L ! NTO Ingiseer A.9 f..
l-PT-94 ATTACIC:E::T 6.11 '~ 1 i'. l g i rv*o8 't " m .12-26-79 . b $ 3 N e['l!EMUb1. f b Page 4 of 35 ' Forth A.irm Po.eer Statica L'ai L Cycle 2,,,_ Startup { Startup Pt.ysics Tests Results and Evaluation Sheet l I Test nescription: CRITICAL BORON CONCE';T2ATION - 3/JK D IN. Reference Procedurc !!ucher/Section: 1-PT-94/ APP.C Scquence Step Mce: cf II E nk Positi ns (ctep=) RCS Te. per:ture (*i): 547 +0 Test. ?over Level (:;7.P.): 0 ~ Condi:1ons StA: 228 SD3: 228 CA: 228 other (specify): (Desia) Cs 228 Cc: 223 CD: [ gceg: gg -15 0_o -Belev Nuclear Heating j III 3ank Focitions (steps) RCS Te=perature (*7): Sf-S" 7-Test Poser Level (27.?.): c) Conditices SDA: 228 SD3: 228 CA: 228 Other (specify): (Act=al) Cs: 228 CC: aa8 CD: o acca:nA 6 claw JUoU ste l^lschin.s Date/Tima Tast 1-/ 7 - &O Perfor:ad: /AS"4" M Measured Fara:ater (C )D; Critical Baron Concentration - Bank D In B (descripties) IV {^ unasured vs.lus C3= /S.M ppm Tc Desica vain. c" n, suit, cato t c - mes,) B 12.33 f 22. ppm -1 19]i{l(H-109.5/j( A/3C)0 Desi p valce CB = 1199 + [(CB ARD B (Des @ conditions) Vepco NFE Technical Report No. 127, Nove=ber, 1979. (Me ). x C,5,,.24;000 pc=. Y FIAR/ Tech Spec 3 6Cg Acceptance Criteria saference FSAR Section 15.2.4 Desiss 'TMst m snet. Act.epto t.e. C. rite ria. met. gg Use = -9.23 pcm/ ppm for praid-4 -=7 analysda Q = -8.88 pe.m/ ppm for final a na.l sis y Coogleted 3y /M Evaluated By 7M bDD partupTest En;;incer Recommended Tor / jf 'jf/ e Approval By i /. # /G.p d 4 -ts [ lNTO znqineer i I A.10 ~ w. e ::< -. -..~. .a.. -- :=... _. .u w a. . : _.;. -. ;;. -. -,;;_ _ _.; ;. 3 _
v _ j ( 1-FT-94 ATTAC1EE:IT 6.11 f p e,g3. A l g.. v;.g. m IsL.V v,1 :stV 5* 2-2 6~'# 9 .t e. as,*h Page 5 of 35 North A.ma Power Station Unit 1 Cycle 1 Startup Startup Physics Tests Results and Evaluation Sheet I Test,r,cscription: CRITICAL 3CRON CONCE2;TJ*ATINT - BA2:1,"SgN#8n IN. 1-PT-94/ APP.C
- 9"**** 8'*P Kcierence Procedure h'u:ter/Section:
,~tC II Eanh Positiens (steps) RCS Te: perature (*r): 547 +0 / Test Pcs er Level (*:P.P.): 0 22S Sc3: 228 H3 CA: 228 other (specity): Conditions SDI:228,g CC: 0 CD: 0 (Design) C3: 3 4 Below Nuclear Resting RCCA: MA III Bank focitions (steps) RCS Te:perature ('F): 594./ Test Power Level (%T..P.): O Conditicas SDA: 2.2.8. SD3: EES CA:228 - Oth :r (specify): (Actual) C3: 2.E F CO: O CD: O Be ow Jear Heabis ^ Date/ Time Tese f-/8-80 Perfor=ad: 192.9 "'**y,lh# (C )C,D; Critical Boren Concentration-Banks B ) C, D In IV Heasured value C3= //38 ppm ( f Test Design value C3 g pg Ib = I Results (Actual Conditions) ( \\ 3 = 1103 +t(C ff - 1199]+[10t37.3/l(3#/3C)D Design value C B 3 (Design Conditions) l i Vepco NFE Technical Report No.127, Nove=ber, g, g,,,,, 1979 V TSAR / Tech Spec ( )xC3124,000 pc:n Acceptance f Criteria Reference FSAR Section 15.2.5 i D4 5), rg Telar M yngg. AcAgrea^ce C,r-ider-ia. rwec. g Co unents Use = -9.23 pcm/ppti for preliminary analysis. 6CB ~ 8.83 p c. / ppm fot* EInA.I C' N ySIS* = Completed By Wi Evalusted 3y 7M M byttupfcscEngineer i Reconcen led For /j s2/ Approval 3r, /. p. /we.[/d [ NTO T.ngineer 6 L A.ll ~ M . ~ _ _.
l-PT-94 1- . ATTACIO.' ::T 6.11
- r..,
3 n ; s i .n I" ' a.! /.i.! !.-f' v , l'. A - i s'1 12-26-79 i l t s Page 6 of 35 !! orth A. ins !*ower Station Unit 1,, Cy cl e,2__ S ta r t u p Startup Physics Tests Results and Etaluation Sheet I Test Dec.cription: CRITICAL 30n0N CCNCC.""?J.TICN - BANKS 3,C,D IN. Reference Procedure Nu Lor /Section: 1-PT-94/A?F.C sequence scep Nu=.her: pg I II Back Posittens ( teps) RCS Tc=per:ture (*T): 547 -5 Power Level (:7.P.): 0 Test g Conditions $0/.: 228 SD3: 22S CA: 228 Other (specify): 15 CC: O CL- 0 -15 0+0 Below Nuclear Heating (Design) CL: RCCA: NA III Bank Positions (stops) RCS Te=perature (*r): 5* V6. 6 Test Power Level ( T.P.): O Conditions SDA: '2.'2. S SD3: 2."2. S CA:"J '2. $ . Cther (specify): (Actua1) C3: O CO: o CD:O I SCt.od hlUcLCAt Henvs-RCCA: g Date/ Tine Test l - /'f-5 0 Perfor:sd: OWy (C ),C,D; 3 ca rn oncentratien-Banh ( cr. i ) B,C,D In 1 IV !!casured value C3= 9$$ l Test Design Value C3= '7 $ d/ "'f* 10 88F1 B Results (Actual Conditions) F 3 = 949 +[(C f -1103}+[10+143.4/j(30/3C)p l DesiCa value C 3 C'D 3 3 (DesiC: Conditions) Reference Vepco N ?. Technical Report No. 127, November, 1979. V FSAR/ Tech Spec 3}
- 31
/ E" 1 Acceptance Criteria Re ference FSAR Section 15.2.4 M3/ow Tocc4 Aves Mn A ccetrawcz C RrTEfth H K7'. l VI Cosaents Use m FhW aWsh.. BC3 $ u --s, gg pen /ffn yog psyks-AVAL YSIS, a Cp I Completed 3y Sf/ Evaluated 3y h dactup Tesc Engineer I Recomcmnited For [ Approval DT./. M [ NFO Engineer i ~ A.12 y_ . 7.-
1-PT-94 ATTAC:-CENT 6.11
- r. t
- r. r.^. ' f 1 TO 12-26-79
!". k !4.l b $U d i-. I U Pa9e 7 of 35 North A. ins l'over Statica 1: nit L Cycle L Startup Startup Physics Tests Results and Ivsluation Sheet CRITICALBORONCCNCENT'!ATION-BA';KSA.3,C, DIN.] Test
Description:
Rcterence Procedurc NucLar/Section: 1-PT-94/ APP.C 8*9"*"** 8C*P 5""3C': 7.3 l II tank Positions (etes:) RCS Tet:per-ture (*T): 547 +0 -5 Power Level GT.P.): 0 Tccc 0+13 - other (specify): i 228+g Conditions 5:A: 223 S 3: CA: CD: (Ccsign) C3 g CC: O 0 Below Muclear Heating RCCA: gg III Eank Positicas (steps) RCS Te:perature (*T): 5M.O ) Test Power Level (**T.P.) : O Conditions SDA: 2.E 9 503: 2.? 8 CA: O other (specify): (Actual) C3: O CC: O CD: O scCA:NA gelow hjoclear hasy Date/Ti=c Test I 90 Performed: 19 0/ M (C )
- 1
= 3 ,B,C,D'
- C{h ri n
zy P.easured Value l Cg= 8/d ppm Test Design value C3= $ //' 4-2 cf ppm Rasults (Actual Conditiene M B = 772 + [(C )3 C*n-9'91+[10+164.9/K3p/3C )l] I resign value C 3 3 (Design Conditions) 8 Vepco NFE Technical Report No.127, Nove=ber, gg,, 1979. 7 TSAR / Tech Spec. (- )xCB 1 24,000 pcm I Acceptance FSAR Section 15.2.4 Reference besisn ~T~c,le.t A+Le M tt.. A t.Lef cL ne.c k/tttiA. t%tb a t y1 tise f# -9.23 pc=/pp r preliminary analysis. Coenents C B _ - 3. 2 2 g /g,. ro,- soa oagis. .uEs h b.; Evaluated By 7M Completed 3y cartup fest litsincer Reconecitiled For / Approval By J. 4[ .s.d / NTO Engineer .A.13 r t....
.__d E.. i 1-PT-94 l ATTACH?I:;T 6.11 dr-,se I !,* * [d., {~gjl.')b::,,,:,y -m e 12-26-79 d i t i g Page 34 cf 25 llorth A.ina l'over Static.ti t'ni: _J, Cycle _2,,Startup Initial Startup l'hysic:, Tur.ts P.ccults snd Evsluatinis 1 CRITICAL E0r0:1 COUCCITRATION-BANKS A,3,C.D & $33 I:* I Test Der.cription: Kcierencu Procedurc Nuc.:.ar/Screion: 1-?T-94/AFF. H 3C9"C"CC S**? U"4 C ' 53 tank Positions (ser.p ) RCS Terpetr:ture (*T): 547$ II Power Level (;.'T.P.): g Conditions S::A: 223 SD3: O CA:0 Other (specify): Test I (Desis;n) C3: O CC: 0 CD: 0 N/A Below Muelear Heatin: RCS Temperature (*r):.5 f6. 2. 3ank Poci: ions (sccps) III Power Level (*:7.P.): O Tc:t SOA:dd8 SDs: O CA: O - other (specify): Conditions (Actual) C3: O CC: O CD: O " ' ' ^ *
- 8eb meJeae Neats j-20-90 Date/ Time Test Perfor ed:
04-0 3 Critical Beren Ccacentre. tion-(C )MB A,3,C,D,SD3 ' A,3,C,D, Shutdown Bank 3 In heasured Pera ater (descripcion) d97 ppm Hessured Value Test Design Value 7g .f. 2O ppm Results (Actual Condition:) C =675 + ((C ) A'3'C'D-772] t[10+90.7/ l(3# /3C3)'. Desirn Value 3 3 (Design Conditions) Memorandum frem M. L. S=ith to E. J. Lozito, 8 Reference dated Decem'cer 7, 1979 / C ) :t C 1 24,000 pcm V FSA:t/ Tech Spec ( 33 3 I Accept:nce Critcria FSAR Section 15.2.4 Reference a use lac - -9.23 pcm/ ppm for preliminary analysis. 2:l:s Q =3 -8.se pem/erm for Findl & y. sis. Co: besign T;;Ier en. met.. Aeeepwe. C.riteria. met. l YM b3 b. r4*/ Evaluated ny Ceepleted 5f ~ S ep'. tute,L::.t Laginect I Reconcended For [ j ef/ , p, Art.wval Dy d, //. & w / h A / [NTO Engir.ce r A.14 i-- -__ __
I 1-FT-94 f n..nCH:iE 7 6.11 I ' ~gr i .,.., C. ! ' ~._J ', j l V.' ? 12-26-79 i '. ~ ;, 4 e s, e i e it -, v t_. Page 33 of 35 !! orth tun.s l*s Sentitn !! nit _1, Cycle 1 startup Initial Startup P:iysics Tc:ts T.csul. and Ivsluation Test Der.cription: CRITICAL OCEC i CC::CE' T3(TIC:* '\\LL ?.003 "i'[t "50I"'~ I 5~r P. CST REACi I fcquence Secp ::o.ber: g Kcierence Procedure ::u-Scr/5cetion: 1 p7_g4/ gyp, g II Each Por.Leiens (sters) RCS Tc pe.rsture (*T):547 Power Level (**T.P. ) : O I Tesc Conditions SOA: 0 S::3: O CA: o other (specify): (Design) C3: O CC: o C3: o gg,fCA: at 223 Below Nuclear Heating 1 III Bank Pocitions (steps) RCS Te=;c ::ure ('T) :.5'f 6.f I Test Fever Level (~:7.P.): O Conditions SDA: O SDB: O CA: O other (specify): (Actual) C3: O Cc: O CD:O RCCA:y-J.j. d 2gy Q g[o w & cjg y lfe d Date/Tice Test I - 2.0 - 8 0 i l Per forr.ed: op// (C )M3 ARI-MRR. Critical Boron Ccncentration- ]/ / Y.casured Para eter (descriptica) ' All Rods In Except RCCA.? -r/N@ IV I 'fi=acured Value [$/ m l Test Cesicn Talue g9f4. g ppg I Rescits (Actual Cc=diciens) Design Value (C }33 ARO ~ 1319.50 ppm I C" (Desitn Ce ditions) B 1 VePc NFE Tect.nical Report No.127, Reference I ,ove=ber, 19fy J ( /3C)xC3 1 24,000 pcm l V FSA*t/ Tech Spec 3 Acceptance I Criteria FSAR Section 15.2.4 Reference l l US* / = -9.23 pcm/ ppm f r preli=rinary analysis. 3C & =s - 8.'8 8 pew / Pff\\ ~fo t~$5n 0 Yl: I 55S. Co es P f Desi n Tolcrwe met. Acrephee C.t-iderio_, web. 3 I 7k b Coepleted By ~7 hvalusted Ly S.v: cup Ta:6L f..:7. Ane c t Recenmen.ted For / APPtVval fir t / vm / !!*FO t.,yincer lL A.15 I L
I l-FT-94 ATTAC*C'.E:T! 6.11 Q d. I fta 2 9.'1l p T""O ! ! ] 7O 12-26-79 I1[ dU !
- V 7
Page 10 cf 35 Ilorth A.ms l'over Station Unit.l.,, Cycic 2_ Startup Initial Startup l'hy=ics Tests P.c:ults and Ivsluation I Test
Description:
Boron Worth Measurement Kcierence Procedure Wr.bcr/Section: 1-PT-94/ APP.E. Scquence Step hmber: L i II Rank Posittens (strpc) RCS Tc-pnr:ture (*P):547+ 0 Atevi A.Wng Po'.cr Level ( :F.P.) : H:'P-5 Test 7g SrJ.: p,,W g" B R-3 g CA:,,;;Hr other (specify): Conditi. j 22$ SO3: /g C3: Moving CC: Moving CD: Moving 3 (Design) P.CCA: pg III Bank Positions (steps) RCS Te:perature (*r): 6~/f Test Power Level (%T.P.): O Conditions SDA: MOVIH3 SCS:McVlMj CA:AleVi,a3 - Other (specify): B (Actual) C3:Movin3 CC: A& oving CD:#.ovinj RCCA:y/, he./cw Milcle.u-Meah'h3 f[fg Date/ Time Test g, I Perforr.ed: Measured Fara:cter [ 30 g (description) \\ ag /, Differential Beren Worth I IV Hessured Value ( ) = - F.&s pe.m/ ppm )= g,ypggPg/ Test Design Value ppm Results (Actual Conditiens) B I ( BC )=-9.23+0.92 pcm/ppet Design Va.'un (Design Co,'diciens) ~ B Veece hF Technical Repcrt No. 127, Nove:ier, l Reference
- 1979, Y
75A?JTech Spec ( B B 8 Acceptance Criteria Reference FSAR Sectien 15.2.4 i V1 begjy Kjerm mef, A gg C.1-il:e rio me.t. 'sb Ev41usted Dy 7k h3 Coinpleted By 7t ~ ScfetupTescEnginece I Reconcended For / <7/ j IMM Approval 3r _/ o )dO Engineer 6 I r A.16 1 B
f l-FT-94 C][.IAl, O C O !l} [L' l a 41l'h i \\ .i ' e ATTACH". INT 6.11 12 26-79 ( L Page 11 of 35 t North A.tns Po.scr Station UnitdCycle,2,Startup Initisi Startup thysics Tc:ts fic:ults and Evs1*uation I Test D:r.cription: Boron Worth Mcasurement Keferencu Procedurc Nudar/Section: 1-PT-94/ APP.F. Sequence Step W dce: i +0 II Eank For.icions (cent ) RCS Te per:ture (*T): 547 i -5 Fover I.evel (::T.P.): H::p Test /,1.q u fa,yfg CA: g., jag Other (specify): [ Conditions y 50/.: ;g SD3: -l2.J' (Design) Y C3: 1sving CD: geying Movinc Eelow Nuclear Heating l C NA L III Sank Positions (steps) RCS Te porature (*r):.5f6 l Power Level (%T.?.): Q Test Conditicas SDA:/[0Vang SD3: /A DV8,h3 CA: /eleV[M3 Other (specify): (Actual) C3:M,vig CC: /Aov8a3 CD: /Asven3 be CLA) LlCkta f $CA hn$ f i 16 -20ho L Date/Tisc Test Perforr.ad: [ S. ), Merendal Boren Wed Heasured Para =ecer ( BC (description) 3 IV (303C,). - 9.8g gem / ppm He.sured value P"4M Re u s 1 itions) 3 ( 30 1 Design Value aC = -9.23 + 0.92 pcm/ ppm (DesiCa Conditions) B Vepco NT2 Technical Report No. 127, Neverter, Reference
- 1979, Y
FSAR/ Tech Spec (3 )x 3 :!I. 24,000 pc:a C Acceptanca Criteria FSAR Section 15.2.4 Reference D e. 5 I n % /e r d.s c h. V W 6 b. VI b Cosraents A cf.c.g b g c. b Ild.1?.J't o N b
- Evalusted 3y 7/d M Completed 5y
/ St/ttup Tc:6e Enginecr Recomr..cnded Tor / l Approval ny , / I m 13 l !NFO Enc;ineer L-A.17 i P ~ ~ - - - - { m t..
5 l-PT-94 ATTACIO*.E!T:' 6.11 [ FINAL RESULTS %;2';" u !! orth A. ins Power Station L' nit,1,,_ Cycle 1 startup Startup Physics Iests Results and Evaluatica Sheet I Test Der.cription: Isothermal Te=perature Coefficient - ARO d
- E '"
Reference Procedurc !!u.-Scr/Se: tion: 1-?T-94/ APP.D II Eank Posittens (steps) RCS Tc=pe.r:ture (*T): 547 9 ~# Tcat Power Level (::T.P.): 0 Conditions 50/.: 228 SOS: 228 CA: 228 Other (specify): (Design) C3: 228 CC: 28 CD: 0 Below Nuclear Ucating 228,+g [ RCCA: A III Bank Positions (steps) RCS Te=p"erature (*F):Sf 3 -5+7 Test Power Level (:*T.7.): O Conditions SDA:22P SD3: 8.88 CA:dd8 Other (specify): (Actual) C3: 228 CC 28,8 CD:214/2/S" h e) 0to b d c.fca r 0 4 a d N,3 Date/Tisc Test l -/(, - 90 Ferfor ad: /SSO-/43Y Hessured Parameter go Iso (description) (IT}AR0; Is thermal Te=perature Coefficient-ARO IV (22.) AROI50 - 2. 36 pc.m/*F Measured Value eT Test Desita value (12.yISO -3.97 3.o Pcm/*F Reruits (Actus1 Conditions) 3T ARO (C6 13 5/ ppm) Design value ( ) = -3.87 t-3.0 pcm/'F 0 (Design Conditions) (D/228, 1320 pps, 547.0*F) Reference Vepco NFE Technical Report No. 127, Novem'cer,1979 i C v rsAR/ Tech spec ( ) < -1.98 pcm/0F [ DOFF 1.ER( )= -1.98pe=/ F) Acceptance Criteria Reference FSAR Table 4.3-2, VEP-?RD-NFE-127 n nes, rw wa. e Cosssents M O C 8p8 CLAW.t O,.f-ikIO. M6b. 1 O_ 8 M z 1uoted 37 7xpa Ceepleted By SprtupTcut Engineer Recommended For / Approval 3y .). I M s [NTO ragineer A.18 ...:----- :x ... _.., z_.
- ~;---. _;;-.-._
~
n . ~. 1-pT-94 A~~rAChN. E:Tr 6.11 ';NTi; ( h! (I I t 12-26-79 4 Page 9 cf 35 L [ North A.:ns Power Station Unit _l, Cycle 1 Startup L. Startup Physics Tests Results and Evaluatica Sheet F I Test neceription: Isother=al Temperature Coefficient - Bank D In Reference Procedure Nua.bor/Section: 1-PT-94/ APP.D Scquence Step *: umber: p 547* 3 II tack Positions (ctepc) RCS Tc.perature (*F): 5 Tect Power Level ( F.P.): 0 223 15 other (specity): Conditions ' S:t.: 228 st3: 228 CA: 0*0 Belew Nuclear Heating, (Design) Cs: 228 CC: 223 CD: RCCA: NA-15 III Bank Positions (ste s) RCS Tc=perature ('r):5f3-Sf7 Test Power Level (%F.F.): O Conditions SDA: 2,28. SDB:228 CA:238 Other (specify): (Actual) C3: 2.28 CC: 228 CD: /S" RCCA:NA &/m Aloclee //m49 Date/Tisc Tes I~ l7 ~ 80 Perfor:cd: /5ff ~ /4f.S~ (h)D1SO; Isother'=al Temperature Coefficient-3ank l P.easured Para:acer (description) o* D In I IV (h " -3.70 pg.m /* F l 1:casured value (30.)D1S0,-6.39
- 3. o p ed* F l
Test Desica value 3T (. Ce = /23'/ pp) Rasults (Actual Co:ditions) l Design value ( ) = -6.87 + 3.0 pcm/CF l (Desica Conditions) (D/0, C/228, 1199 ppe, 547.00F) l Vepco NFE Technical ReporC No.127, Nove:bar, B Reference 1979. j <-1.98 pe=/ F (DCP?LIR (h)~1.98 pc:/CF' V F:An/ Tech sped - ( ) Ac'ceptance Criteria FSAR Table 4.3-2, VEP-FRD-NFE-127 i l Reference VI k 5' n ~J~o~ /a f M m ed.". Cocc:ents 1 Ac.cmw ee C. rim. m et. I ~ Completed By e Evalusted 3y 7/d b Segetup Tc:at Enginect Ecconectated For / Approval By ,/ ew'< [NFO Incineer A.19 ? -- i
1-PT-94 [ l l\\)[.C d L, '_') t e-p.: i! */ n ACACF.:iC.7 6.11 L 12-26-79 s,f Page 17 of 35 !! orth Anna Power Station Unit,,1.,,, Cycle 1 Startup Startup Physics Tests Results and Evaluation Sheet I Test Descriptions !!/D TIUX MAP. ARO reference Procedure fiumber/ faction: 1-PT-21.1 sequcaca step :tucher: 7 11 tank Positions (steps)' 2C5 Tenperature ('T): 547 +5 Test Pever Levci (!?.P.): 4 - Conditions SDM 223 sca: 223 CA: 223 Oth*' (8P"*1'Y)* (D'*1t") ~23 CD: 21f C3: 228' C: 1 1 ACCA: NA Must have > 33 thimbles III 34ak Positions (steps) RCS Tc=perature (CF): 5'4 C Test Power Leval ( Y.P.): O Coneftions CA: 2.23 Other (specif y): 50A: ll.)'d SOS: '.2.~2.Tr (Actual). g3g g,g gg 2.2[d CD:"1.I'd RCCA: M 4kTkm. f,3 1 Date/ Time Tese I-l l=~ 80 l Perfor=ed lS55. ;733 l MAX. "!IL.
- T MEASURID PAJtx^M A$5T. P.'R.
F'lg, :.JCLIAR F, TOTAL XuT CUADRAT q
- 'E d.T41ALPYRISIECT TLL'I !!OT C*dA:::.T.,
PC'r'ER TILT I CHAh".*ZL TAC":R FACTOR RATIO (QPTR) y l 3.090 4 + ~f l~7.17o
- 1. Q 1.090 l
x.,sured Value I IS7o) bO,9 Test-Desi:n Value ~ l.%O LL -~ f. 2. OO Z-l.O').O 2. I Rasults (Actual Conditions 1 ~~ -+ 10: for P 10.9 i ,r.. s. u.u, .e.s 11.55x(1+.2(1-9)) 1 1.02 Design Value + 13 for P <0.9 g F "'#**"*?" l (De sign Conditions: (P = Assy pve) B Reference 'JCAP-7905 m m5 T3 3.2.3 TS 3.2.2 REV.1 RIV.1 l I V TSAR / Tech Spec
- A NA gg g
Acceptance l Criteria g l Reference n is 3.2.3 Ts 3.2.2 TS 3.2.4 F mq;n. 2.s '7e, o.4 o. $c~e. hegk+ of ci.% f'ech TLe. min /-om q yr Cowe.ts B l Completed 3y Evaluated Sy 41 ..o# / ud Recoenended Tor M Approvs1 sy / - NF0 tugir.cer Tke test resolb o ec. o cccptolle.. 4 Af erences : 1. MoctL Ann ( L ER to-on /o t T-0. 2.. Le.&c nom C.N. S+a.ll M s CV o) -t o H.R. Denb F -........ O s1 A C.) ci d e d f % c c,[ l I, I 90.. sr k I tJo. 11c,. - [ A,20 i
B 1 I 1-rT-94 i ATTACE:tE:" 6.11 p '\\l f l p~ r q
- p a ai Lt
.iv Lld 12-:'6-79 j Psge }7 o' 35 J l l ~7 4. 1 trorth Ann.3 P.awer Statien :: nit _],_ Cycle 1 Startup Startup Physics Tests Resuits and Evaluation Sheet I Test Descriptioot If/D FLt:X P.rP-M Peference Procedure I;uaber/Section 1-PT-21.1 Sequenco sece u ber: l I 7 II tank Positions (stern) ACS Ten crsture (OT): 547 +5 Test Power Levci (27.P.): 4 ~ SDA: 223 S s: 228 CA: 223 Other (specify): Conditions 21;+1 (8 " 18"3 CD: Cs: 228 CC: 228 Must have > 33 thi:bles RCa: n III 3Jok Positions (steps) 105 Temperature (OF): DIS Test Power !.evel ( Y.P.): e3 SDA:')."1.9 SOS: ~2.'2.'!r CAI "2 '2.g Cther (specify): Conditions (Ac:ual). C3: r2.) CC:~2.': & CD: 0.*2.;r RCCA: Q 4k CS e Date/ Time Test 1-10-?,0 Perfor=ed l 9 Lj % - 20l L[ I. P.AI. RE.. F* H. :::JCI.ZAR q Ton.En? ], Ct.C u R nr.Ascr.za P.exc::IR ASST. F.3. (d"*P*i*") y_i"- c.mtA:.PT Rzer acT ru;x ::CT Cu=.n. rCtn n:.T Cux;n. FAc: R rACTCR RAMO (QPM) I l '&.0 0 O l.OS4 4 - 1 1. 4 To I. fo l I Peasured value I lo7ofizo.1 /-- I ~/- 1, sri /_ t/. '2.00 "'~.02.0 Tut Dest:n value ~ Reculta (Actual Conditions 1 I -+ 10: for P 10.9 1 ,; -.s.1s......e. / ,35x (t+,2(1.p)] g 1.02 Design V.tlue + 15 for P e.9 g AN 'e *** '8 * * 8 ' eg s (Design Conditions) (p. g3,7 y) I. VCO'ISOS Referenes ECAP-7905 TS 3.2.3 TS 3.2.- RIV.1 RIV.1 I V FSAR/ Tech Spec
- A NA MA IIA Acceptance Criteria Recennee xx TS 3.2.2 TS 3.2.2 rs 3.2.4 l
- h. rd.nimum F q 'n = 2.5"7c, o.+ A core ke.i0' kt of 9.2 Oct vr q
co cs I h,.g I d h / Evalueced 3y completed 8y / so / [ /,.,, _,, 8 /// Recosacnd.ad For Approvs1 sy / /sro cuatneer 4 The. test results art. acceptdle.. 8 Refen.,Ces : i. rdertk Am LER to-on /o rT-0. l 2.LeHer Ar C./1. 5*lhdy 6/efco) to H.R. BedodlAd l d % e d M u c.( (( 3 19eo, Suk.1 rJo. i nc. t A.21 - - - I
1-PT-94 AT**ACI:2C:3T 6.11 !.~ ' i. I li I D ~~ O I l 'l. T'.') 12-26-79 ! 5._ ; V Is
- t. 's / d page is og 33
. I ! fortis Anes Power Statloa L'nic 1 Cfcle,,,,2__ !:artup Startup thysics Te:ts Results and :saltiation $ncet I Te.st
Description:
lt/3 TLUT. P.t?- 3cr.'r. D In 1:e f e resco Procedure ::atirr/Section: y_p7_77,y 5cquece Step Ninhen 7/ 11 L.sch Positicci (stept) 2C5 Teapersture (8F1 547 +5 Test Fawcr Level ( F.P.)s*4 1 Conditicas s:A: 228
- 223.
CA: 223 'h *' I'"* "Y) 8 I "#8") Cs: 223 C:: 213I15 CD: c+if Inst have > 33 thi:bles RCCA: NA 'D 3 /,,fL I re. 1 III Sack Positt:es (s:ers) AOS Te=pera:urc (8F): ftl,5' Test P:5.er *,4 vel (27 P.): O Condnions $7,g;.y.yy, g.;3 <2,2 } CA: '2 t.Q Other (specify): I (AC'al) Cs h3 C:: :": ' CD: ) 7. H TL.Mle.s gcCan % Date/Tt: Test l-17.20 l Perferred: 1217 - 10"1."'I l !">Z. RI:.. l CASL"7.D PA74:"TIX A35Y. 7 2. I'.*y, 27.:CLIA2 Tf,TOTALEIAT QTA::7xt: (a = =r 53"") h.355-J.&.: tn 2::: m rta m aA ::. 1:. n 1t-02:C II. TAC 0?. T.C10R RATIC (Qr R) y l n v' n*y70 i*917 *
- 3. 63(,
l'.0 63' + .:easured Value Test Design Value 1 10 ,2 0.') 6 l.%O .::s 4.1. 00 g ),o 1,0 F4sults (Actual Cenditis.gi ,) l 2.,.i.. u.u,,..> 1 -+ 10: for ? 23.9 i ,8 - s ,g.,33 x (t,,2 (1.p;.! y,1.02 Desics value
- 13 for F <0.9 N
g 7 (Design Conditto:sJ (? = Assy pvr) 'i""' i Reference WCA?-7805 TS 3.:.3 TS 3.2.2 CAP-M 5 l Rl'V.1 REY.1 l V FSAR/Tec.4 SFec NA NA KA E I Acceptance Criteria l Reference 'a
- g 3,2,3 is 3,;,2
.S 3.,.,* ~ M.dm m Fq mc.rp 1 'l cd-A C. ore _ heijk+ ef (1. i -Pec.t. 0 y. C:w n ts O @d,uff D.,1 1 f.y.mgc,x sp.leted,0, tvaim,ted 3, / U U l y p Q.wh Re:2=.emr.d rnr , j_r-,-
- .nrea t :.,
.4...., _%s..,w.Asi.mJio ~ +ta wi,e-aj i ' ~y. e h ' e, c v r o.i:_1,c:]. m u.m.e c
- 4..
A ll 1 kriN fcE.d %c H2.1)Insechon l l.w lt,q I Ge r* erant.c:. ::.idr.n :, !\\<,s.u L EQ to-o t': lc [ ; -. O. 2, L c :-h:.c pc. , C,l'i, $h!) ; n 7, ( N....et,') b fl. S. b Wi%. (IJ/.'C) I ..b. t.. ! I i. v q l!, t'; 9,.<.._. n l C j,. g ; !., A.22
1-FT-91 37'O 3 ii ~~I~ O ATT.iCIS!CI"' G.11 f~ ' f l '[*\\ l* l. h. u.. ' \\ CC !_) L.1 U 12 26 ~c) Page.1& c' 35 I b. JitL M'clD trorth kins Power stition t nit i Cycle _,2_ startup scattup thysics Tests Results and Evaluation sheet . % nl,a In test Descriptions ::/3 rtt :: P.tr.Ba.1-t)_.k. Zc.co TbV No l Ewn Umit I reference trocedure ::ucher/ sections y_p7_gy,y squence secp Mia6er: j) II 1.ar.k Positions (steps)
- tCs Te :pursturo (*rl: 547 +5
~~ Test = rowe Level (tr.P.): 4 0'h (**"Y)* Conditions s c.'.: 22S SCt: 223. CA: 228 (***8E"I Cs: 228 CC:.2.lge CD e liusC have > 38 thimbles RCCA: gjg 3g$ 10 W 3!'eI*' Sank Focitions (steps) RCs Te terature (*F)* $"t)$ III Test Power Leve1 (IF.P.): #3 s0A: '). *2. s03: 2. CA:113 Other (specify): Condniens (Actual). C3 1"). CC: 11 CD O RCCA: y,\\ QC\\ Themble.S Date/ Tine Test I f2.O * 'il.I 8D Performed: t3 30- o I':Lo 1* L RIL. J rk, t JCI.DR T. TOTAL P.T.AT Q'!ADitA;TT y.tAst1to PraxzTu Asst. ren. (cescription)
- Diff.
g h g y,f Rise EDT FL:'i E3*l' CFM IEL 7C'4*Q TILI I C:1A:CE TACTO't TACTOR MIIO (Q?Z J.,,redv.1ue 'l.27. l.cl3o#
- 2. 9 %
l.0 34* ii.s3)Pl_4.9 f-1. 951 4'/.100 4 1.010 Tese oesien v.1oe Results (Actual Candi.tonsi -+ 1C* for F 20.9 1 ,{..to e s(sites e.e.s si.5 5x (lv.2 (1-p)] 1 1.02 Design value + 15 for P <0.9 l g r U* (Design Cor.ditionsJ (P = Assy pvr) C P"7IOS I Reference k'CAF-7905 Ts 3.2.3 Ts 3.2.2 RIV.1 3:Y.1 y TSAR / Tech spec n l'A NA NA Acceptarce I Criteria Re ference KA Ts 3.2.3 Ts 3.2.2 T3 3,2,4 1 q mor3;n : lo '7 a.t a. c.oce. ha.pt o f ti. y (e e+ 4o ' mum F y, Ces==sa ts Complete ( By Evalusted By ) e / U d Recossended For y) Approval Oy 3 g/ NN t.ng)tteer
- Test res vIts confirm +ha.-t +ke. F[g lim;t is Wolcded witl Ac rCJ s a.+ +ke. E P,4sec G 1/w +s.
1 Refere.nces: 1. lJoc+L Anna. LER to -or i/o T-o.
- a.. LeMee 4'cor..C. M. Std l.h
38 th1=bles RCCA: NA '24
-to nr ?l,.im III Sank Positions (steps) KC3 Temperature (OT). 71]$ Test Power Level (:T.P.): w3 Condrticas sa:1M SOB: ng CA: 118 Other (specify): Q 1M CO: 2,3 CD 93 (Actual) g 49 Th,mele.s ECG y A, Dete/Tice Tese I 3.1-SO Performed: 3 g gg. l Mt/ !*J.X. P.II.. T.I,1.*JCI. EAR Q.TOTALF.ZAT I QUAMA3T xzAsGED PAFx:ETIR A35Y. F'A. g (description) ~ Duf. Eb!ALPYRIstEDT TLOX EDT C:!A:: net, TO'tra TILT C:Lucri, rACTea FACTes ratio (qPTM, IV
- 10. I To I.7 4 O 1.5 80 f.dSI 2:sasured value
[ 1;s7,> G eocy ~Z. l, g g l ~ y,2.co Z_J,020 /_. Test Design value "~~ ~ Results (Actual Canditionsi + 10: for ? 10.9 i 11.55x1+.2(1.p)] q*..se u.stes e.e.S g 1.02 N Desita value ! 151 for P co.9 y g 1**# "''** (Design Conditions) (P = Assy pvr) Reference VCAP-7?05 TS 3.2.3 TS 3.2.2 p -MOS arv.L a.v.1 y rsAm/ Tech spee sa sA xA xx Acceptance Criteria meterance NA Ts'3.2.3 rs 3.:.i fTS3.2.4 M.^.' mum F f:L., r 31'7c, s+ a. cor e he'gki' o-f 3.0 fe.e.t y, q Cessaants CoeS1ste( Sy t Evaluated Sy ~ .aM~/,* a*w / ~ 0 d OK.0sbh NN IJigs,tcar 4The_ tcSF resoH'.5 a.re. a.a.cphdle. { tlc _ test ec3sli3 conf.Jm tkd- -the. Fy 1:'m,t ,*5 rsot utecle) wdl +h*- red 3 a.i +Le. new oJmin6+ced.0c. im,cr+ 'a I.b it.
- 1. rJoetL Anns LER 90-or ; /o iT-0.
.t I Reference.s : 1. Leh bm C.t1. Stgil.' y N. o) to H. A. b% C^Ad da. ed t%k n, s MO. Susal tJa. Ti ts. a L s A.24 I i
1 AMACE.C."? 6.11 1-PT-94 l-. j\\ h,... h.g nd s.g, 9u. j Q 12-M-79 u, l... v P4 e 19 of 35 Itorth A.sna Pover Station Unit 1 Cycle 1 Startup Startup Phystes Tests Results and Evaluation Sheet 1 Test cesertpetent :r/o FtrX tur-AT PO'E.R,."I CALIS., P. D.iTA P./2 reference Precedure flucher/S.*ction: 1-PT-22.2 sequence Sten wer: II lar.k Positions (sters) RCS Tempera ture (OT): Tref +1 Test Conditions ~25 ~ Power Level (P.T.F.): 1 s:Aa 223 s:s:223 CA 228 Other (8Peeily): "I CD: C3: 223 C 223 AR Must have > 3S Ch hbles NA I III Earth Positions (steps) RC5 Terperature (CT): NS Test T.wer Level (*:T.P.):~ ~30 Condnions 50A: 22f.- SOS: '22f CA: 228 Cther (specify): (Actual) g3, 2,, y cc: 2zy cy: 2;j 1 RCt'.A t yf 4.P 24W6/cs Date/T! e Test / "- 2 f - M Perfor=eds /33 0 - /pf/ l'AT. REI.. I MEASURID PA?A':ET!X AS$*f. P%'t. T,,1:!CinA T, TOTAZ,EEA7 QUAcrACT d.T.LU.PT RISZ E)7 TL7 ".C CF.A*:::TL PC'.."Il !!LT CEL'C;IL TACTOP. FACTOR RATIO (CFTR) p IV e 2:easured Value /*YS7 2.883 /. 04.f Test Design Value fff,/,,p,.gg,j NA Nd
- f. /. 4 2 C I
F.esults (Actu.s1 Condt:* ens) ! 10" for P 10.9 g Desigs value
- 152 for P e0.9 g
a y,1.02 (Design Condi:1 ens: 3;g (P = Assy pvr) Reference t'CM -7905 k' CAP-7905 g a Trt.1 rzv.1 ,r.,,,,,,,y,,,,3 si.55x (1+.2(1-p)') NA y TsAPJTec.h spee n T8
- l :*.ne * * **8
- e.s Acceptance AH Criteria
'~'" I Reference x4 T3 3.2.3 T3 3.2.2 TS 3.2.4 vs M.'n ;,m. i> Fa snaryt i 2f c/e ed a ce rc he.yAt of 9.9 ful. = ~ " Fe, udcHed
- 1. wa wl,:c), exetCds de pll! 1. :t ;{ t.650
= but is less &,o d.- f.'w f. . t e.f i. E '7 /. ' Completed By 9-b Evaluated By 6#.R. k/
- Tl c lest r/
V /. i i esults are. necyta&Ic. Recomend.d ror 1 Approval 6y C.
- v..s I
Rc[crenecs : I.'A/crih An e L FR pc _ o,7 j,,7,,, e uinneer l 2 l Clice {rson
- c. M. Skl;.sp C Vqc.) t u. g..De,de,, cNRe) dafd March 11
,11Po, fer;<d /Jo. fib. 3 IJ:rik Am Tc<.t C _9... Spee;[cek .s. 2. ?.. E ~ ~ ~ ~ " ^ ' ~~~ A.25 I-
1-PT-94 ATTAC:-DLE:i? 6.11 ENAL RESULTS 12-t" Page -Yo., 3 5 l%. ~ North Anna Power Staticn Unit i Cycle 15tartup ttartup Physi:s Tests Results and Evaluation Sheet 1 Test Cescriptions :t/D rt.:;X l'AP-AT FO'ER,NI CALIS.3-DAstt-FJ M S~'#~#0 l'e f e rc oce Procedure Nucher/Section: 1-PT-22.2 sequence step t w er: 11 tar.k Positions (steps) RCs Temperature (OT) : Tref +1 ~ Test Power Level (*.T.P.): = 0 'h
- 8' '*P**1'7):
Conditiens stA: 228 CDS: 22S CA: 228
- D I C3 228 CC: 223 C3' AR Must have > 38 thi=bles
!!A III Bank Posittens (sters) RC3 Tenperature (OT): fgg, T* Tower Level (*:T.F. ) : ug Condn'E $ A: 2.2 f SDS:223 CA: 228 Cther (specify): ions I C3:228 CC:22,8 CD:/(,,g* IA*'"*1I
- NA N /.b[ m l)lc,s l-Et-Fo Date/ Time Test Ferforted
/4 2.5 - /797 l'AX. REL. .g T F, M.C E CTC NIAst: RED PARN:ETIR AS$Y. :". A. T*gg 1.T.E.M I q (description) ~ Diff. ENTi!M.JT RISZ EDT TLt'X 1:0T CHA: ;IL PC*TR TII.T D CHNCiE:. TACTCR TACTCR RATIO (Q?!3) a p Iv 8.9 '7, /,5+2. 2.078 1.0 2.+* Yassured Value I (Actusi CanJitions) t/st,', fj<o.9 pjA NA 61.020 Design Value rest Results + 10% for P 10.9 g .g Design Value + 15% for P d.9 i* g NA NA (Design Canditions) (p. Assy pvr) VCM-7905 Raference uCa-7*05 gA xx RIV.1 gzy.1 ej :r. e a usi/ri,**.3 NA r'hs1.35x(1+.2(1-?)) y rsArJTech spee x^ ,e.,,,, Acceptance I Criteria reference xA Ts 3.2.3 Ts 3.2.2 'S 3*9-*4 Minirnum Fq margin = So % e.c a. core heiah6 of 6.4 feet.. v! F Unrokas. = l.uS wha'c.k execed.s de F? limit af 1.570
- ~*"
n but is less do.n the. Fjy limit of-f.7 70.* Completed By / Evaluated 8y k / = . Recoveended Tor ([m j Approval By . /?
- M0Enginpr
- N The t.est rcsults are, megs)e.
Referc e : t. N orLh hnna.* LBR So - 0I1/oIY - O.
- 2. Leu.ct-from C.M. StaJIInss (VcFo) to H.A. Den k (AIRc) cGt. Led. March Il s l'130, Set-la l Mo. It c,.
- 3. 2.. a_.._ __,
- 3. tdorth. A sso Tee.heiset. Spetificesim
....g., . y I
1-PT-94 AT'"ACH2CT 6.11 O II 'i'9 12-20-79 %s\\. v,}d L 3 V C' %I [6, l 1 ! cl~ st Page A f of 35 l'7b Horth /nna Fever Station Unit,l,,, Cycle _,,2 Startup gg yjf,gg, ,,tartup Ptrysics Tests Pesults and Evaluation Sheet I 1 Test Descriptions :t/D Fil,~4 l'aP-AT P0hCR,NI CALI?>. ;E:".;:.'J'J::22.F: J/2J Feference Procedure Nucber/Ocction: 1-PT-22.2 sequence ste? I mber: y.,, jj, II lar.k Positions (steps) RCS Te perature (OT): Tref +1 Test Power Level (tr.P.): ~ onditica' 5 A: 228 503: 22S CA: 22S C'h*' (SP**ii )* I 7 " E'I C3: 223 C 223 CD: gg , 3g uA 1 III 2ank Positions (steps) RCS Temperature (OT): d'$' S test Power Level (*47.P.): ~ Jo SOA 22[ 5:32 '228 C.t: 278 Cther (specify): Cond :1ons (Actual) g3
- ,,7 g gcg
- 12. d CUI /38
- CCA' NA 4g.g),;,,.,jje g Date/Ti=a Test I ~ 2I~ h Performed: op3p
/opf MAX. REL. T 10:Ast ID PARN'ITIR A55't. FtR. T**1. 17CLIAR T, TOTAL EIAT GAORAJT a q I (description)
- Diff.
g{7.tALPYKIEEEDT TL::X HOT CHA:0;II. Pol.TA TILT CHA:CiZ1. TACTCF. FACTOR RA!!O (CP!K] 1!easured Value 2.2#0 Test Design value f ff,j/,, P. <<.1 /s/A ud s /. c ze 6 Fasults (Actus1 conJittens) ! 107 for P to.9 g Design Value ! 13: for P e0.9 g 1.02 g g.4 g (Design Conditionsi (P = Assy pvr) ,. Re ference W./.P-7905 k' CAP-7905 NA u g/.1 RD?.1 te p.no e u.un e e.s $1.5$x (1+.2(1-p)]l t' p. s. u. NA N y TSAR / Tech Spec NA yAH a:e.s g,,,, I criteria .,.S 3..,, Reference NA TS 3.2.3 TS 3.2.2 A l'l:ntm.on Fg marf 3. 4S *h ed a u rc heQht cf L2 ["Y
- S.g cxCceds di. Fs"Y* li :t of I '/I*
W EUS I (, y 7,4y j =. a. Nc wl:ch Ca m ats than tAs. fir sj 9.p) '?! f:. :l of I.ito hit :s fl-:A F-t r unnd.lal - s. c'7F w l.. < !, evarses .s tr - F 0 R b 1,,
- v. ( v4m I
Completed liy r..iu ted or less da. -1LlF7.it :t of 1.891.* 0 accerfdle -
- g d ror 7g j
~# Test results cut. y I Test roitifs cen[:rm dat t/ic for 1.-it ;3 r,t no w incer ute:Aest m>:4 -i,e nas,d.itw ag n, a g,,,;,,;g r,g;g ;,, e,g;, n g; ;t,. l Rc(evences : /. Ale r!!r Anna LER 20 -. c1-7 f o l i - 0. 1 L<W r from c.Fl. Stalfeqs ( Vqcs) A H.R. Den ~bn WAC)s ankd t1 orch i I , i9Po, ser:<d N. es4. -i. Me.4 Anna TcClink,J Qu:{rutten 3.2i. 1 A.27
l-P';*-94 e mxc cts::: e.11 ,,- c i n I U $h U 1 12-26-79 ~ l j Page 20 o' 35 treeth /.ua Fower Statica Unit _,1,_ Cycle ,7.,_ Startup Start =p Thysics Teets Results and Ersluation $heet [ t Test Ooscriptions :!/o rtuX mP-AT PO*i?.R,'!I CALI3. I DATA MAP Peterence Frscedure :hacher/section: 1-PT-22.2 smence s:ep ::wher: II 14r.k Fositions (steps) ECS Temperature ('T): TTef +1 l ~ Test Fwer Level (:T.F.): ~ 40
- A 228 s:s: 223 CA: 228 0'h*' (8*1'Y)8 I
C* di'18"' 228 C AR g,NA Must have y,,38 thi=bics C38228 UI Sank rositions (sters) KCS Te:rperature (97) 3~8d [ Test ?over te.el (':7.~7.): " 30 ggg 2 3,f $;3: 2 2.f CA: 22.P Other (specify): Co ictions (Actu.sl)- C3 12.g CC: 227 CD; 2/8 'N [ 4P ' -t'l.'ml/c3 ~ Date/TI:s Team Terfot=ed: 15 21 = //,44 [- 1*> L P.!L. 7 ifg. l.;m ti?.A3;;rI3 FAF.',. w._s A5ST. F'.'t. T.MM M WE q (descr1pt!.4,a)
- Diff.
Z:i;9AI.?T LI3I ECT TLOI EOT C'.!A:::.*II. FCt.'El TILT O'-" Cn::.;c nC:Ca nCTea 2A::o (c!:?J If y.,;,,,4 y,.1,, i o.o e/, t.476 /. M /.czy Test Dest; Talow L tpef,, h e e,9 NA NA
- tI.c2c Results (Ae:c.a1 Cc-ditio _s)
+ 10: for F t0.9 g De.stss value + 15% for P 40.9 s 1.02 g g g (tesign C72ditions: gy. A,37 p.,r) . 'r VCAP-7105 2afe enen WCAP-7505 g. g nrt.L 3r?.1 'rj ::.se i st.ntes e.o.3 g:AM11.55x(1+.2(1-p)3J NA t Y TSAI/ Tech $;ec .itA tj :5.**
- Sta8 8 '? 8 Accepta ce Criteria
~E*f*** C* NA T3 3.2.3 T3 3.2.2 T3 3.2.4 [.. M:n t~ ~ Fa. una u of 2.2 ful. Fq Unrodded =. q:n = n+ << << cca InusF T { R.'- :t e f ' t. t k a bsst v1 I.L 91 wicxb creads W. ES ltsS ihan tltt (~ r 1: :t e f 1.S94. A ~ O.R L a, 1 -ted i,
- v. a. Om Completed my D
/ If O' L
- TAf. fesf nsu fs arc. ciccerf alle.
- [*"dj'*7 c j 1..;
r i AA.fA Ano. (gg ec _ oth/o,7. o, { Re{erous s 2 Ldter frsm C.F1. CL,.' ling s ( Vtfee ) L H. k. Denien (NC c.) dated Srch II, t.9Po, sert.J: Nc. t s4 3 tJera Anna Tec h. cal s ce {:catt.,,. s. 2. 2.. e ~' ' A,.28 I
1-PT-94 l
- ~
A'I'!ACP. !C.~2 6.11 Fl W** \\i RESUiTS 2 - '-" Page 21 of 35 lit,rth Anna fewer Station Unit 1 Cycle _2., Startup Startup Thysics Tests F.csults and Ev:1uation Sheet I Test Descrirtion: If/D rtxx mP-AT PO'ER.NI CALIB.E DATA MAP re fe rence Procedure 1. umber /Section: 1-PT-22.2 sequence step :n.=ber: yp 1 Test = RC3 Ter:perature (OT): T:e{ +1 11 bar.k Positions (steps) Power Level ( T.?.): ~50 - B '*"di"*aa ser:228 ses: 228 cas228 0'h*' (SP*"ift)8 (* *I "I 5 j C C"8 Cs 228 gj8 228 AR Must have > 38 th1=bles , NA III Sank Positions (steps) RCS Tee.perature (OT): 563 Test Power Laval (%Y.P.) + 4<7 scA: 22f SDB: 228 CA: 2 2./ Other (specify): Condnions (Actual) CS 21/ CC: 32P CD: 2./f RCCA: gA 46 shtmble's '~ ~ Date/Ti=e Test Perforted ev ).: $ - c 4 2 9 l ~ 6 l'.AX. REL. Ff.TOTALEIAT MEASURED PARA:CTIR Af.ST. P'."1. F. NUCLEAR. (TA*RAdf I
- IP"I*"I I:."Ti!ALPY RIST. E0-Tit".( tici CF.A:0EL FCt.TK TILT C)t.Vi.sIL FACTCP.
FACTOR RAT 10(q?TE] $*f'[e /. 9c3 /.c 2 c 3 1'.easured value Test Destg1 value t l f ofe, j', t o;] lJA fff f_ p, o 2 o Results (Actual Conditfoesi ! 10% for P 10.9 g Design Value ! 13% for P *0.9 n g 1.02 g (Design Canditions: (y. 43,7 pyg) Reference VCAP-7905 VCAP-7905 g g RIV.1 Rr/.1 rj -..ss a steste s e**.8 MA gl.53 x (t+.2 (1-p)) M N y TSAR / Tech Spec n y AE . ' l'";* * * '* 8 8 ' N Acceptance ggy 3f,,f;;. I Criteria Reference NA Ts.3.2.3 Ts 3.2.) TS 3.2.4 ,1 M:,, :,.,u,,, F1 rurf;n = h / c.t a etre he:ylt e P. 2 fed. } Fn vs roded = ' 6 72 WlA acccIs ih F?r 1'~;tc/ '* Wo ' ' ~ " ' '
- t. t t.1 hu ik,, at Fh J.. e 1 i.. par
- Complated By hed Evaluated 3y
/I. /, he v 1 / V V Recomend.ad for C dw)
- T$c Ec51 8ciul!! tt n.
necepfafle. Approval 27
- sN Eng$acer de{tre.1ces
- s. Alert 4 A,um t.cg Sc-oI?/clT-C'.
~ 2 Letter fresor C.M. Slaih Sf ( Myce} L ff A. Dinicas (NRc.) g daled Mars !. It. ityc, screc.l t/c. ill. k, Aferil. (buut Tech,r:es( Sj ec:Schla 3.2.g.. n l i
~ 1-PT-94 AT'"ACD*.Z:!T 6.11 irlNN RE'9"ILTS -2c-" I 1' Page 22 of 35 Iforth Anas Power Station Unit 1 Cycle 15tartup Startup Physics Tests Recuits an.1 Evaluation Ehtet Test Descriptions :t/D rtux t AP AT PC'.1ER,:ll CALIB,5 DATA I re f e rer.c e Procedu:e !!u.~.ber/Sectir.n: 1 PT-22.2 3ctua"c" 88'? N'*b*r8 / </ s/ 2 11 kank Posittor.s (steps)
- t:5 Teeperature (CT) : Tref +1 Test Taver Level (*:T.F.):
w 60 - 223 sD3: 22S CA: 223 ccher (specify): Condittens (D*'1;") C* Cs: 228 C8228-AR Must have,> 3S thi=bics ICCA: g I III 3ank Positions (steps) FCs Terperature (87): 3~[ 2 Test Power Level (:T.P.): ~ 4f SOA: 22[ SDB: 2 7[, CA: 22f other (specify): Condftiens (Actual) 1I 3 2g ' CC: 12/. CD: fy2 C3 NE-f f f's'odk's
- ~
Date/ Time Test Ferfor:ed f e,g / 2 e f EAx. art. rh, rJC:.tra Q, Ten:. ant atAsuzzo rn a zita Asst. rwx. cricus; lI @f-(d'iP*i "3 z..w.rT 2rst acT rt : acT Cyx su. recta n:.T C:wac. rACTea rACTCa uT:o(crx4 IV Eeasured Value
- .' I f
/* b 3
- # 2 O'
Test De' sign Value i i p[, [),.: a, f /M /M 6/.82C 1 Results (Actual Ccr.ditions) + 10% for P 10.9 g Design value + 15: for ?geo.9 g 1.02 gg g (Design Conditions; (? Assy pvr) VCA?-79c5 Enference
- JCAP-7905 yr gg RIV.1 sn.1 l rj '.r.te usu,5 P'4.5 51,33x{1+,1(1-ph S.1. t2*
N Y TSAR / Tech Spec 2tA y ir
- 2' * "O 8 ':e.s An Acceptance p
Criteria I referenen u Ts 3.:.3 Ts 3.2.2 TS 3.2.4 he:g41 of 2.c, feet. v1 14;n:>um Fa n ar ;rs = H /c at a ca re 7p Coenents Fn unnahd = 1.663 wl:els ocud' A Flr L :t cf .tsc ht.4 hss dar, de fh p,.,;g , f i. p 3 /, < 6 /' (j 7/ Enluated 87 Completed By 1 / o j i Recor:senJed For It$$ TciHIf5 alt ncCc g,yc. A proval Dy P I I .WO EnCineer Ref<rencut Uc.-il. A,wa uR 20- s q fo u r - c. i Letter [N n c.M. Sfu f;,ngs (y}pCc).t. fl.R.'Denien <yge) l 1 I c{nicd MarCA 11 r p o, scrtc.L A/c.,s4.
- 3. Ahcik 1%na Ted>.:4 Spec:Qad:en 3.2.:,
I-.........- f f e A.30 I
[ l-PT-94 ie ATTAC.9 Err 6.11 F N AL MES;ui_. ! -(.,i 12-2e->e Page 23 of 35 North Anna Power Station Unit l Cycle 1 Startup ~Startup Physics Tests Results.ind Evaluar. ion sheet I Test Desertption: n/a ritrX HAP-AT P0uF.R,NI CALI3 R DATA IfAP l'e f erence Sequence gtop ::aber: Procedure lueber/Ocetions ppp 7 ,II Lank Positions (steps)
- tC3 Temperature (Cr) : Tref +1
- 8%
~ Power Level (*.r.P.): ~ 70 Conditions s::A: 223 scs:. 228 CA: 228 other (specify): esign) '23 CC: 233 CDs 9 C3: gg aCCA: Must have,> 38 Thi:::bles E III Sack Positions (steps) RCS Temperature (Or)s 85 f Test Pouer *,evel (TY.F.): % gf l Cond tions $2A: 22.8 SD8: ,2 2 f CA: 22/ Cther (specify): { (Actual) C3: pp CC: 22] CD: q L nCCA: ',fp $$ bEMbleS. ~ Date/ Time Test terformed: l 2 / / - l 3 3-) >n. a. r xtrsvara PAu:cTza Asst. rwx. r 3, m:Ct. EAR Pf, TO AI. EEAT QUMuST L (d***'iP***") (3ijf* zi:r.ur.n xts: noT rt::x ac! Cu:ca Peura m ; C m. n rACTea rACToa uTTo (cria; [' IV 3:e su,,4 y,2,, f.1 /o /. G /. % /.o.1 Test Design Value 11$</, f; <..y gf] A/A 'f. /.o 2 0 Results (Actual Candittens) ! 10: for P 10.9 g Design Value ! 15% for P d.9 1 1*02 g NA yr (Design Conditions) (P = Assy pwr) Reference WCAF-7905 VCAP-79G5 gr g REv.1 art.1 r Ah.s1.55x(1+.(1-pd,rj.:.a. u.u,i..s y rsAx/ Tech spee sr yN 4 1*02 Acceptance ....o uo s,:e.s Criteria Reference NA T3 3.2.3 T5.~'.2.2 TS 3.2.4 iI f4.'n 'on u ns h ntttrf.'n 'fa *lo A Ct CC fC-l1C'WIi of <f* 2 fY' = Cosemer. s L Destyn Tole ranc e met. A cce dona CrNe rin *ke l. Completed ay Evaluated By 7, [ hsv L / r / l Accomended for l { Approval By b. %) hFQ kngineer A.31
L [ 1-PT-94 ACTAC3".I'r? 6.I1 ].p g l 8\\t vvi K p l-l g 12-26-79
- b' Page 24 of 35 8
I 17 North Anna Power Station Unit 1 Cycle 1 Startup Startup Physics Tests Results and Evaluation Sheet I Test DJseription: 't/D FLUX MAP-AT PO%T.R,NI CA*.I3,li D.*TA "AP reference Proctdure !* umber /Section: 1 pT 22,2 Sequence Step Humber p l II tatk Positions (steps) !CS Te=perature (*T): Tref +1 l Test Power Level (:7.r.): ~ 80 - l Conditions sgA: 228 003: 223 CA: 223 Cth*' (*P'*1'Y)*
- **'"3 C3: 228 CC: 228 CD: AR Must have > 38 th1=bles 1
RCCA: III 3ank Posttions (steps) RC3 Te=perature (CF): 5"76 l Test Pouer Level (17.P.): # g g* Ccndrtions SOA '2.'2.3 SD3: 1'LS CA: '2."2.9 Ccer (specify): (Actual) c3, 3,1g CC: ").'i.% CD: '2.'2.S RCCA: 74 As Date/71=a Test "2.-N-EO Perforced: o o I i - O i L/ L[ HAX. REL. { MEASL" RID PAM2tCITR ASSY. IV1. F7 .J C*.!.AR Fj,TOTALHT.AT QUAORA.;T i$'3 L "ItALPY RISI ECT TL;% HCT CXA:C:IL PohJ2 !!LT CaxCn!. uC Cr. nC=R uT:o (cr:R: [ IV s'.9 7. I. 4 n-I.Wl I.Oi? ,,,,,,,,,,,1, Il 57., P4 0.9 MA MA t-Test Design value " I.olo P.esults (Actu.21 Conditions 1 + lo: for P t0.9 g Design Value + 15: for F <0.9 g 1.02 g g (Design Conditions) (P = Assy pvr) Rafarence VCAP-7905 g g VCAP-7905 REV.1 RIV.1 51.55x(1+.2(1-p)J ; ~*.20 s Mel 3 .d.3 ,...:.. w.u,i.. s Fi.ut/ Tach Spec n y4
- S1.02 y
8N F ; Acceptance Criteria ESf*i'"** M T3 3.2.3 TS 3.2.2 TS 3.2.4 KiMemum Fq wp 2.9 "7, of Cu e. ore. he.ij kt of io. 2. Fee.t ,g b C**"*"*' basip To tea.nc.e. me.i. Accephce. C. '.+vi mei Co*Fleted By Evaluated By 4 A i co 1 Reconciended Tor --f Approval Ey I / tiF0 Engineer A.32 i ......_..._~...__....._...m.....
L 1-PT-94 1 RNAL RESULTS IEST" ' r I Page 25 of 35 l North Anna Povet Station Unic L Cycla,,2,, Startup j I startup Physics Tests Results and Evaluation Sheet I~ t/o FLCx >!AP-AT PC'.CR,NI CALI?.,h * * '" ~ 1 Test
Description:
Reference Proceduro Nu=ber/Section: 1-PT-22,2 Sequence Step Waber: ef' II lard Positiens (stern) ltOS Tenperature (CF): Tref +1 l Test Power Level (*.F.P.): - 90 ~ SDA: 223 s:s: 228 CA: 228 th*' (*P**1f ): I Conditions 7 "" 18" ) CD: CC.; NA C3: 223 223 AR Mus ; have > 38 thimbles g III 34nk Positions (steps) RCS Temperature (CF)i 5@ Test rever Level (*7.P.): cyC) u Condf*. ions gg,y 7, g g $g3:22C CA 7.26 Other (specify): l (Actual) C3: 2. 2,6 CC: 2. c d CD: 2.2$ M 4 & 'i~h\\bG6 Date/Tims Test 2.*7*OO Perforced: 100g -]I M 1*.AX. REL. }!EASL* RED PARA.6 ASST. PR. P, iUCLEA.R F, TOTAL EEAT QCAOFXi? (description)
- Diff.
Eb1ALPY RISE 11CT FL::I EOT CI:A:C:!L PC"~J. TILT C:4.uC;C, FACTCR FACTOR RATIO (QPTI: p a 1-l,762-1,OIO 6. 2:sssured Yalue rest Desten value .tl6'f Pgo.? NA NA < ) 02 0 I I Results (Actual Conditions) + 10% for P 10.9 g Design Value i 131 for P <0.9 n g s 1.02 g (Design Conditions] (P = Assy pvr) WCAP-7905 Reference VCAP-7905 g g tr7.1 Pn.1 r;.iae. u.im. a [AA;t,33x(1+.2(1-p)} y FSAR/ Tech Spec M 5.1.02 'l: :..:o a 6.63 i efa Acceptance Criteria Reference M T3 3.2.3 TS 3.2.2 TS 3.2.4 Mi nimum Fq mumm : 17 */o a. o. ccce. h eipt a f 3,2 feef, d vt Desican Toleto.oce met Co.ncs bCCep AOCE Cf f' $ Ct. M E +' Completed By Evaluated By D,'D Sci e r, eds is / h g Recorrmed.d For Approval By ,[ M (/. wor.ngyet 1 A.33 1
F 1-PT-94 L c ' r-Q jd L l d t! ~Q AMACE:C 6.11 g a {l, l_, I~ 12-26-79 2 Page ;5'of 35 23 st North Anna Power Station Unit,1,_ Cycle 2.,, Startup yy 3 _f p,g startup Physics Tests Results and Evaluation Sheet s I Test Descripeten :t/D rtrx HAP-AT POWR,NI CALIS 2 Dir?4-t2 Jf 7 7-8 J - A Reference Procedure hucbcr/Section: 1-PT-22.2 sequence Step h' umber: II lank Positicas (steps) 2CS Temperature ('T): Tref +1 Test Power Level (3T.P.): ~90 - Conditions 223 sDs: 228 CA: 228 Oth** ('P**if 38 7 s "" 8" ' O' C3: 228 CC: 228 AR Must have > 33 thimbles uA ( III Bank Positions (steps) XCS Temperature (0?)'s I/O Test Pswer Level ( 7.F.): ~ cf f SDA: 228 $D3: 2af CA: "228 Other (spccify): Condrtions [ (Actual) C3: r.2 p CC: 1Q. CD: 2c8 NA 46 1l,,'anble s f Date/Tise Test ~ ~ L Perfortsd l'))].- Iye f [ ux. nE:.. uzAsuarD rm:ETER ASST. P,4R. T,lCCI.ZAR T, 703:. EEAT QUAOM77 u.s.g,t1..) =. &m,, m, _ ,m.OT m._ ...,,=.T Cx.uc;E:. rACTCa rf.CTOR RA*IO (QP3] (,' 3 I.4a3
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I 1-FT-94 6 A's'"AC:e"'2e C ~ F!NAL RESULTS 1 Page 26 of 35 tiorth Anr.a Poser 5tstion Unic 1 Cycle _2 Startup Startup Physics Tests Results and Evaluation Sheet HIP, ARO,sequencu Step :h=her: Eg Xe I Test
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II tank Positions (steps) RCS Temperature (OF): Tref +1 Test Power Lcvel ( 7.P.): 9j +7 s:A: 228 ses: 228 CA: 228 Oth*? (87'*1f ): ~ T Conditic"* (##"C"3 C' C3: 228 CC: 228-AR Must have > 38 th1=bles RCCA: III Back Positions (steps) RCS Temperature (CF): 88/ Test Power Level (:T.?.): /c o g:A: 2,1[ 303: lif CA: 22f Other (specify): Condnions CC: 1,_f CD: 2/ 3 (Actual) C3: 11p RCCA: N4 I 47 d?nflkJ 2 - /4 - po Date/ Tine Test Perfor:ed: /(,c 47 - /(, / g !!AI. REL. MEAS'TRID PARM ASST. PW. F, NOCLEAR T, TOTAL *E.AT QTA*RNC
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