ML19327B125: Difference between revisions
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. m' '. 4 , ,\ . | . m' '. 4 , ,\ . | ||
-s; , s is,c:, | -s; , s is,c:, | ||
, ,,. . , ... .; 3~ | , ,,. . , ... .; 3~ | ||
| Line 147: | Line 146: | ||
i :- : .(:- : t- | i :- : .(:- : t- | ||
'y y | 'y y | ||
. " 3 wQ. . y qf,, W. :; ~ | . " 3 wQ. . y qf,, W. :; ~ | ||
gw - , , , | gw - , , , | ||
| Line 284: | Line 282: | ||
n s _ , - . | n s _ , - . | ||
, . .-e. . '- | , . .-e. . '- | ||
#; , s | #; , s | ||
* * | * * | ||
| Line 308: | Line 305: | ||
. c f | . c f | ||
- j- ., , | - j- ., , | ||
.g .','. | .g .','. | ||
* g .' | * g .' | ||
| Line 318: | Line 314: | ||
' '' - E p - - | ' '' - E p - - | ||
, _f | , _f | ||
- . ' (, | - . ' (, | ||
, , % . . - +e - | , , % . . - +e - | ||
| Line 355: | Line 350: | ||
3 . , | 3 . , | ||
. n s, . .. , | . n s, . .. , | ||
. . . . .. a .. .. . . . . - . | . . . . .. a .. .. . . . . - . | ||
$* . - . s y. ,. | $* . - . s y. ,. | ||
a ' *- | a ' *- | ||
.s,. | .s,. | ||
. .s 5 ....p . . | . .s 5 ....p . . | ||
| Line 374: | Line 365: | ||
.;. ''n.,9 - B ...r. ., . ' ,g,r.w-..,''..."3 . ,e - | .;. ''n.,9 - B ...r. ., . ' ,g,r.w-..,''..."3 . ,e - | ||
. n . / ' '' , | . n . / ' '' , | ||
,, x y. . | ,, x y. . | ||
,g -.; . . s. p ] ' . | ,g -.; . . s. p ] ' . | ||
| Line 382: | Line 372: | ||
. . r. . . ,. . | . . r. . . ,. . | ||
y | y | ||
. ( y K , " . . , . , _ . . ej . . . | . ( y K , " . . , . , _ . . ej . . . | ||
- - -l - L .j .a | - - -l - L .j .a | ||
| Line 388: | Line 377: | ||
.s | .s | ||
", g | ", g | ||
. ,,g,.,..1 | . ,,g,.,..1 | ||
. | . | ||
* i. f | * i. f | ||
,. .- . l , ,,.,v. y,p , . - . | ,. .- . l , ,,.,v. y,p , . - . | ||
4 ., . +. . 4.., 1, ,, , .. c , ;4 .., | 4 ., . +. . 4.., 1, ,, , .. c , ;4 .., | ||
' -. .o g .f y,,g ; . c, ,, a.. , .,p ,, + , - yj.-. , jp ,',, eg | ' -. .o g .f y,,g ; . c, ,, a.. , .,p ,, + , - yj.-. , jp ,',, eg | ||
| Line 453: | Line 440: | ||
7.. | 7.. | ||
LI LI h' | LI LI h' | ||
TECilNICAL REPORT NE-734 - Rey, 0 | TECilNICAL REPORT NE-734 - Rey, 0 L | ||
t LI | |||
LI | |||
:. NORTil ANNA UNIT 1, CYCLE B STARTUP PilYSICS TEST REPORT , | :. NORTil ANNA UNIT 1, CYCLE B STARTUP PilYSICS TEST REPORT , | ||
) | ) | ||
| Line 476: | Line 461: | ||
: therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, Tile COMPANY HALES NO WARRANTY OF MERCilANTABILITY OR FITNESS FOR A PARTICULAR l . | : therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, Tile COMPANY HALES NO WARRANTY OF MERCilANTABILITY OR FITNESS FOR A PARTICULAR l . | ||
PURPOSE,- NOR SilALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR' USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report availabic, the Company does not authorize its use by others, and any such | PURPOSE,- NOR SilALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR' USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report availabic, 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 sna11 itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided | use is expressly forbidden except with the prior written approval of the Company. Any such written approval sna11 itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory 4 | ||
herein. In no event shall the Company be liable, under any legal theory 4 | |||
whatsoever (whether contract, tort, warranty, or strict or absolute | whatsoever (whether contract, tort, warranty, or strict or absolute | ||
- = | - = | ||
| Line 495: | Line 477: | ||
n TABLE OF CONTENTS f mo .; | n TABLE OF CONTENTS f mo .; | ||
i . | i . | ||
PAGE i L | PAGE i L | ||
1 t | 1 t | ||
| Line 508: | Line 489: | ||
' I, Evaluation Sheets........................ 41 7 i | ' I, Evaluation Sheets........................ 41 7 i | ||
f | f | ||
: g. , | : g. , | ||
g 1 | g 1 | ||
| Line 522: | Line 502: | ||
t g ' | t g ' | ||
x3 LIST OF TABLES . | x3 LIST OF TABLES . | ||
s | s TABLE , TITLE PAGE ! | ||
TABLE , TITLE PAGE ! | |||
s .. .; | s .. .; | ||
i 1,1 Chronology of Tests................................... 10 i N , 2.1 llot Rod Drop' Time Summary..............-............... 18- | i 1,1 Chronology of Tests................................... 10 i N , 2.1 llot Rod Drop' Time Summary..............-............... 18- | ||
| Line 543: | Line 521: | ||
s 1 | s 1 | ||
L.- . .: | L.- . .: | ||
ft 'it' LIST OF FIGURES j s | ft 'it' LIST OF FIGURES j s | ||
TITLE PAGE f g. ' | TITLE PAGE f g. ' | ||
| Line 557: | Line 534: | ||
'4.1 Boron Worth Coefficient.................................. 29 , | '4.1 Boron Worth Coefficient.................................. 29 , | ||
Assemblywise Power Distribution - 297. Power.............. 37 I .6.1 6.2 Assemblywise Power Distribution - 74% Power.............. 38 | Assemblywise Power Distribution - 297. Power.............. 37 I .6.1 6.2 Assemblywise Power Distribution - 74% Power.............. 38 | ||
.6.3 Assemblywise Power Distribution - 1007. Power............. 39 LI | .6.3 Assemblywise Power Distribution - 1007. Power............. 39 LI g | ||
g . | |||
\ | \ | ||
Pase 4 o, 5e | Pase 4 o, 5e | ||
| Line 585: | Line 561: | ||
comparison between measured and predicted test results, thus enabling a ! | comparison between measured and predicted test results, thus enabling a ! | ||
quick identification of'possible problems occuring during the test's. , | quick identification of'possible problems occuring during the test's. , | ||
f I l, I | f I l, I | ||
.s f | .s f | ||
| Line 593: | Line 568: | ||
if S . | if S . | ||
lE, a | lE, a | ||
I LI 2 | I LI 2 NE-734 NIC8 Startup Test Report Page 6 of 58 | ||
NE-734 NIC8 Startup Test Report Page 6 of 58 | |||
y, i | y, i | ||
| Line 644: | Line 617: | ||
Technical Specification 4.1.1.1.2 criterion that the overall core reactivity balance shall be within 1% Ak/k of the design G I,'- | Technical Specification 4.1.1.1.2 criterion that the overall core reactivity balance shall be within 1% Ak/k of the design G I,'- | ||
prediction. | prediction. | ||
: 4. The boron worth coef ficient measurement was within 1.9% of the design prediction, which is within the design tolerance of 10%. | : 4. The boron worth coef ficient measurement was within 1.9% of the design prediction, which is within the design tolerance of 10%. | ||
: 5. The measured isothermal temperature coefficient (ITC) for the ) | : 5. The measured isothermal temperature coefficient (ITC) for the ) | ||
| Line 682: | Line 654: | ||
Test Date Time Power Procedure flot Rod Drop - flot Full Flow 7/14/89 1930 llSD 1-PT-17.2 L ur Zero. Power. Testing Range 7/15/89 1705 llZP 1-PT-94.0 Reactivity Computer Checkout 7/15/89 1742 IlZP 1-PT-94.0 ig.. Temperature Coefficient.- ARO 7/15/09 2235 IlZP 1-PT-94.0 g- Boron-Endpoint - AF0 7/15/89 2359 ' llZP 1-PT-94.0 Bank B Worth 7/16/89 0007 Il2P 1-PT-94.0 Bank D Worth - Rod Swap 7/16/89 0342 Il2P 1-PT-94.0 I | Test Date Time Power Procedure flot Rod Drop - flot Full Flow 7/14/89 1930 llSD 1-PT-17.2 L ur Zero. Power. Testing Range 7/15/89 1705 llZP 1-PT-94.0 Reactivity Computer Checkout 7/15/89 1742 IlZP 1-PT-94.0 ig.. Temperature Coefficient.- ARO 7/15/09 2235 IlZP 1-PT-94.0 g- Boron-Endpoint - AF0 7/15/89 2359 ' llZP 1-PT-94.0 Bank B Worth 7/16/89 0007 Il2P 1-PT-94.0 Bank D Worth - Rod Swap 7/16/89 0342 Il2P 1-PT-94.0 I | ||
1-PI-94.0 Boron Endpoint - B in 7/16/89 0501- IlZP Bank C Worth - Rod Swap.- 7/16/89 0507 Il2P 1-PT-94.0 Bank A Worth - Rod Swap' 7/16/89 0550 llZP 1-PT-94.0 Bank SB Worth - Rod Swap 1-PT-94.0 | 1-PI-94.0 Boron Endpoint - B in 7/16/89 0501- IlZP Bank C Worth - Rod Swap.- 7/16/89 0507 Il2P 1-PT-94.0 Bank A Worth - Rod Swap' 7/16/89 0550 llZP 1-PT-94.0 Bank SB Worth - Rod Swap 1-PT-94.0 | ||
:I; Bank SA Worth - Rod Swap 7/16/89 7/16/89 0646 0722 ilZP I!ZP 1-PT-94.0 | :I; Bank SA Worth - Rod Swap 7/16/89 7/16/89 0646 0722 ilZP I!ZP 1-PT-94.0 Flux Hap - 29% Power . 7/17/89 1842 29% 1-PT-21.1 f Flux Map - QPTR Verification 7/19/89 0724 74% 1-PT-21.1 1 | ||
Flux Hap - 29% Power . 7/17/89 1842 29% 1-PT-21.1 f Flux Map - QPTR Verification 7/19/89 0724 74% 1-PT-21.1 1 | |||
'I, Flux Map - !!FP Flux Map - I/E Calibration 7/26/89 7/27/89 1549 0600 100% | 'I, Flux Map - !!FP Flux Map - I/E Calibration 7/26/89 7/27/89 1549 0600 100% | ||
100% | 100% | ||
| Line 732: | Line 702: | ||
1 l 108 1 | 1 l 108 1 | ||
I E50 96 ANI E75 6A F38 R04 1 l | I E50 96 ANI E75 6A F38 R04 1 l | ||
6 | 6 1 6A l IOC les , 9A 10s 9A i 10s 1 IOC 1 6A 1 < | ||
1 6A l IOC les , 9A 10s 9A i 10s 1 IOC 1 6A 1 < | |||
1 F67 l E72 ' 546 1 J34 K37 J22 1 E53 I $66 i F44 l 13 l | 1 F67 l E72 ' 546 1 J34 K37 J22 1 E53 I $66 i F44 l 13 l | ||
'I- 1 I l 4A h 9A l | 'I- 1 I l 4A h 9A l | ||
| Line 747: | Line 715: | ||
y 7.j g. ' | y 7.j g. ' | ||
!J ; | !J ; | ||
,, X Figure 1.2 , | ,, X Figure 1.2 , | ||
.; NORTil ANNA UNIT 1 CYCLE 8 i BEGINNING OF CYCLE FUEL ASSEMBLY llVRNUPS | .; NORTil ANNA UNIT 1 CYCLE 8 i BEGINNING OF CYCLE FUEL ASSEMBLY llVRNUPS | ||
| Line 1,032: | Line 999: | ||
t R0D DROP TIME TO DASilPOT ENTRY I SLOh'LST ROD FASTEST ROD AVERAGE TIME i | t R0D DROP TIME TO DASilPOT ENTRY I SLOh'LST ROD FASTEST ROD AVERAGE TIME i | ||
.I | .I | ||
, B-06 1.78 sec. C-09 1.45 sec. 1.58 sec. , | , B-06 1.78 sec. C-09 1.45 sec. 1.58 sec. , | ||
lI f . | lI f . | ||
| Line 1,124: | Line 1,090: | ||
I I | I I | ||
.I 1 | .I 1 | ||
11 | 11 l I i l I I I i 1 | ||
l I i l I I I i 1 | |||
', t 1 i i i i l I . | ', t 1 i i i i l I . | ||
I 1.55 l l 1.63 l 11 11.551 1.M I I It i i 1 ? I' l 1: 1 ''i 1 I I I i 1 l I I l.55 l 1.54 1 1 13 # | I 1.55 l l 1.63 l 11 11.551 1.M I I It i i 1 ? I' l 1: 1 ''i 1 I I I i 1 l I I l.55 l 1.54 1 1 13 # | ||
| Line 1,174: | Line 1,138: | ||
I NE-734 NIC8 Startup Test Report Page 22 of 58 | I NE-734 NIC8 Startup Test Report Page 22 of 58 | ||
{ ' | { ' | ||
I , .; - | I , .; - | ||
| Line 1,206: | Line 1,169: | ||
1,300-" . .%. . .. %~..g+ ....- . .. | 1,300-" . .%. . .. %~..g+ ....- . .. | ||
y.. , . | y.. , . | ||
"l-- ..-.. 7.. | "l-- ..-.. 7.. | ||
..l..' | ..l..' | ||
| Line 1,215: | Line 1,177: | ||
~- - -"- | ~- - -"- | ||
"+ - - - +- - | "+ - - - +- - | ||
1 | 1 | ||
~z 1,100- | ~z 1,100- | ||
# t- | # t- | ||
.. ~.. .. .. | .. ~.. .. .. | ||
i | i I | ||
I | |||
-g; ' - - - - - - - - ' - - - - - - | -g; ' - - - - - - - - ' - - - - - - | ||
W 1,000--.." . | W 1,000--.." . | ||
| Line 1,237: | Line 1,196: | ||
..o. ... . .. , = .. = . .. o ... . . | ..o. ... . .. , = .. = . .. o ... . . | ||
t .. | t .. | ||
600- ". | 600- ". | ||
g ._, . .. , . . , ... . . . ... . . . .. .., | g ._, . .. , . . , ... . . . ... . . . .. .., | ||
| Line 1,251: | Line 1,209: | ||
; .. ..... . , 1 300- - - - - - - | ; .. ..... . , 1 300- - - - - - - | ||
-} ,.. ..}.. d-) - - - - - - - | -} ,.. ..}.. d-) - - - - - - - | ||
g-" | g-" | ||
.I 2QQ. | .I 2QQ. | ||
| Line 1,404: | Line 1,361: | ||
Boron Lndpoint , | Boron Lndpoint , | ||
[N With the reactor critical at hot zero >ower, reactor coolant system ; | [N With the reactor critical at hot zero >ower, reactor coolant system ; | ||
l , | l , | ||
(RCS) boron concentrations were measured at selected rod bank i | (RCS) boron concentrations were measured at selected rod bank i configurations to enable a direct comparison of measured boron endpoints ' | ||
configurations to enable a direct comparison of measured boron endpoints ' | |||
with design predictions. For each critical boron concentration l t | with design predictions. For each critical boron concentration l t | ||
measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the acazured critical boron concentration values were modo to account for off nominal f I | measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the acazured critical boron concentration values were modo to account for off nominal f I | ||
| Line 1,416: | Line 1,370: | ||
in this table and in the Startup Physics Tests Results and Evaluation l Sheets given in the Appendix, the sensured critical boron endpoint values , | in this table and in the Startup Physics Tests Results and Evaluation l Sheets given in the Appendix, the sensured critical boron endpoint values , | ||
i were within their respective design tolerances and met the requirements ; | i were within their respective design tolerances and met the requirements ; | ||
of Technical Specification 4.1.4.1.2 regarding core reartivity balance. I | of Technical Specification 4.1.4.1.2 regarding core reartivity balance. I In summary, the boron endpoint results were satisfactory. | ||
In summary, the boron endpoint results were satisfactory. | |||
l i | l i | ||
Boron Worth Coefficient [ | Boron Worth Coefficient [ | ||
| Line 1,429: | Line 1,381: | ||
, n s....,,, ,,,e ...s.r os nor.. ..,t,, coe m.,en, w.s sa t ,s f.c o,, . | , n s....,,, ,,,e ...s.r os nor.. ..,t,, coe m.,en, w.s sa t ,s f.c o,, . | ||
g l i | g l i | ||
l I . | l I . | ||
I . | I . | ||
| Line 1,438: | Line 1,389: | ||
g : | g : | ||
i I | i I | ||
Table 4.1 l NORTH ANNA UNIT 1 CYC1.E 8 STARTUP PHYSICS TESTS BORON ENDPOINTS | Table 4.1 l NORTH ANNA UNIT 1 CYC1.E 8 STARTUP PHYSICS TESTS BORON ENDPOINTS | ||
| Line 1,459: | Line 1,409: | ||
9 I , | 9 I , | ||
g xE. m x,Ce Sta,t.,1cs, ,ep., Pa,e e of se | g xE. m x,Ce Sta,t.,1cs, ,ep., Pa,e e of se | ||
1 | 1 | ||
| Line 1,469: | Line 1,418: | ||
tI l | tI l | ||
l l> | l l> | ||
lg Measured DBW = -7.01 pcm/ ppm | lg Measured DBW = -7.01 pcm/ ppm 1,5oo - . | ||
1,5oo - . | |||
- - - - - , - ~ ~ - - - - - - - --- -- -, ! | - - - - - , - ~ ~ - - - - - - - --- -- -, ! | ||
t | t | ||
| Line 1,488: | Line 1,435: | ||
.!.. ... . l | .!.. ... . l | ||
.... .l -1 .I. I. .I... . .... i I | .... .l -1 .I. I. .I... . .... i I | ||
i | i | ||
,3,000 _.i,........i ... ....i.... ...;+.. .. ;1 I I I i | ,3,000 _.i,........i ... ....i.... ...;+.. .. ;1 I I I i | ||
_: ......................................I......I.,i...,I_. | _: ......................................I......I.,i...,I_. | ||
. . . . . . , . ... .. . ..s ..... .I...... | . . . . . . , . ... .. . ..s ..... .I...... | ||
l | l M goo.........................$.....-i I | ||
M goo.........................$.....-i I | |||
.- ...,............f......... .!.. ... | .- ...,............f......... .!.. ... | ||
j lI | j lI | ||
| Line 1,512: | Line 1,456: | ||
! W r t- - - | ! W r t- - - | ||
j r t- r -- | j r t- r -- | ||
W 500- l r t4- !- 7 5-4; ! - -]- - 'j-ll - | W 500- l r t4- !- 7 5-4; ! - -]- - 'j-ll - | ||
r - -"-'- ' i l 4oo. j......L... 4.. ...j.. | r - -"-'- ' i l 4oo. j......L... 4.. ...j.. | ||
| Line 1,523: | Line 1,466: | ||
-I -+ | -I -+ | ||
200 - - - -- -I + +l l | 200 - - - -- -I + +l l | ||
-I --r -- --- - - - --- - - - +l J i ----- | -I --r -- --- - - - --- - - - +l J i ----- | ||
I | I | ||
, oo. . ....+.....z.I .... .... i ...i .. 1 .. . | , oo. . ....+.....z.I .... .... i ...i .. 1 .. . | ||
.-......... l | .-......... l | ||
| Line 1,534: | Line 1,475: | ||
,' m 1940 1D00 1900 2000 2020 2040 2000 2000 . | ,' m 1940 1D00 1900 2000 2020 2040 2000 2000 . | ||
2100 2120 2140 2160 g BORON CONCENTRATloN (PPW) | 2100 2120 2140 2160 g BORON CONCENTRATloN (PPW) | ||
'I d | 'I d | ||
4 4 | 4 4 | ||
8 . | 8 . | ||
I : | I : | ||
L 4 bk | L 4 bk | ||
| Line 1,547: | Line 1,486: | ||
1 L TEMPERATURE COEITICIENT MEASUREMENT LI i The isot hern.a1 t emperature coefficient (lTC) at the all-rods-out condition is measured by controllitig the reactor coolant system (RCS) l temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer. Typically, this test sequence i | 1 L TEMPERATURE COEITICIENT MEASUREMENT LI i The isot hern.a1 t emperature coefficient (lTC) at the all-rods-out condition is measured by controllitig the reactor coolant system (RCS) l temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer. Typically, this test sequence i | ||
'I includes a cooldown followed by a heatup; however, due to high heat reinoval by steam generator blowdown, it was not possible after the i | 'I includes a cooldown followed by a heatup; however, due to high heat reinoval by steam generator blowdown, it was not possible after the i | ||
I cooldown to heat up only on reactor coolant pump heat input. Therefore, j i | I cooldown to heat up only on reactor coolant pump heat input. Therefore, j i | ||
nuclear heating was used to raise temperature to approximately 547'r, and i flux was re established within the zero power testing range. A second couldown was done to remeasure the ITC. | nuclear heating was used to raise temperature to approximately 547'r, and i flux was re established within the zero power testing range. A second couldown was done to remeasure the ITC. | ||
| Line 1,558: | Line 1,496: | ||
.- . - . . _ - ~ . . -. - . - - - - . -. | .- . - . . _ - ~ . . -. - . - - - - . -. | ||
I | I | ||
't | 't | ||
| Line 1,572: | Line 1,509: | ||
: 'I i r ! | : 'I i r ! | ||
l lE. | l lE. | ||
LE | LE NE-734 NIC8 Startup Test Report ! | ||
NE-734 NIC8 Startup Test Report ! | |||
Page 31 of 58 | Page 31 of 58 | ||
| Line 1,590: | Line 1,525: | ||
2145 +0.80 +0.47 0.64 0.94 -0.30 L I | 2145 +0.80 +0.47 0.64 0.94 -0.30 L I | ||
I : | I : | ||
I l I | I l I | ||
I ! | I ! | ||
| Line 1,654: | Line 1,588: | ||
'5 NORTil ANNA UNIT 1 CYCLE 8 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS | '5 NORTil ANNA UNIT 1 CYCLE 8 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS | ||
{' | {' | ||
WITH THEIR TECHNICAL SPECIF~i CATION LIMITS i | WITH THEIR TECHNICAL SPECIF~i CATION LIMITS i t-l F-Q(T) Il0T F-Dil(M) HOT | ||
t-l F-Q(T) Il0T F-Dil(M) HOT | |||
!g CilANNEL FACT 0f.* CllANNEL FACT 0lt | !g CilANNEL FACT 0f.* CllANNEL FACT 0lt | ||
'3 MAP l NO. MEAS LIMIT MARGIN MEAS LIMIT MARGIN ! | '3 MAP l NO. MEAS LIMIT MARGIN MEAS LIMIT MARGIN ! | ||
| Line 1,663: | Line 1,595: | ||
I | I | ||
* The Technical Specification's limit for the heat flux hot channel | * The Technical Specification's limit for the heat flux hot channel | ||
'I factor, F-Q(T), is a function of core height. The value for F-Q(T) listed above is the maximum value of F-Q(T) in the core. | 'I factor, F-Q(T), is a function of core height. The value for F-Q(T) listed above is the maximum value of F-Q(T) in the core. | ||
The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(T). | The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(T). | ||
| Line 1,826: | Line 1,757: | ||
. *.tt *22 r .* .t,*r t9. *.te 109 .* e.er C9 | . *.tt *22 r .* .t,*r t9. *.te 109 .* e.er C9 | ||
* 0 tv 09 .* | * 0 tv 09 .* | ||
* ew | * ew | ||
* t'e# | * t'e# | ||
| Line 1,976: | Line 1,906: | ||
* e *'99t *p t ** 41 t9 | * e *'99t *p t ** 41 t9 | ||
. .e *9 e* w .t' et w * * .t' e r,e* '*.2sv't2 * | . .e *9 e* w .t' et w * * .t' e r,e* '*.2sv't2 * | ||
* styNoce * | * styNoce * | ||
* ert ' er1 | * ert ' er1 | ||
| Line 1,994: | Line 1,923: | ||
3ONIM01 400 J0SIAION$I J.8 lit s 2* tis 6 41148 | 3ONIM01 400 J0SIAION$I J.8 lit s 2* tis 6 41148 | ||
~ ' | ~ ' | ||
G GYNl) VA 191 S13JS J.GH)W( a t'fe2 NM t'006 M3 I*001 JlZ( m 1*t19 SM e*666 l S3 8*661 | G GYNl) VA 191 S13JS J.GH)W( a t'fe2 NM t'006 M3 I*001 JlZ( m 1*t19 SM e*666 l S3 8*661 M5Mnd e 19 WMG/W1A V*0* e -2*tt6% | ||
M5Mnd e 19 WMG/W1A V*0* e -2*tt6% | |||
N3-LCV Nt09 S1911nd 10S1 godolL deSO (f oJ gg ' | N3-LCV Nt09 S1911nd 10S1 godolL deSO (f oJ gg ' | ||
| Line 2,006: | Line 1,933: | ||
ASSEMBl.YWISE POWER DISTRIBUTION [ | ASSEMBl.YWISE POWER DISTRIBUTION [ | ||
74% POWER I | 74% POWER I | ||
6 P W M 6 J H C- 6 i | 6 P W M 6 J H C- 6 i | ||
i t L D C 8 | i t L D C 8 | ||
| Line 2,130: | Line 2,056: | ||
. 1.T9.1.03.1.51.119.3.t9.3.16.1.03.0.F4. | . 1.T9.1.03.1.51.119.3.t9.3.16.1.03.0.F4. | ||
3.0 . 3.i . i. . l.7 . .) . .i.9 . . .3 . .l.i . 0.7 . | 3.0 . 3.i . i. . l.7 . .) . .i.9 . . .3 . .l.i . 0.7 . | ||
7 i | 7 i 0.50 . 0.44 . 1.27 . 1.17 . 1.F3 . 1.75 . 1.76 . 1.14 3. 25 . 1.th . 1. F5 . 4. 3 F . 3. tF . 0. 8% . 4.14 . | ||
0.50 . 0.44 . 1.27 . 1.17 . 1.F3 . 1.75 . 1.76 . 1.14 3. 25 . 1.th . 1. F5 . 4. 3 F . 3. tF . 0. 8% . 4.14 . | |||
I 9.50 . 0.64 . | I 9.50 . 0.64 . | ||
: 1. 26 . 3.16 . 3. tb . 1. t8 . l .50 . 1.18 . 1.76 . 1. F6 . l . 72 . 3.14 . 3. th . 0. 85 . 0.51 . 4 0 | : 1. 26 . 3.16 . 3. tb . 1. t8 . l .50 . 1.18 . 1.76 . 1. F6 . l . 72 . 3.14 . 3. th . 0. 85 . 0.51 . 4 0 | ||
| Line 2,209: | Line 2,133: | ||
i I : | i I : | ||
i i | i i | ||
i I i | i I i P | ||
P | |||
,I ; | ,I ; | ||
il | il | ||
'I l I | 'I l I | ||
| Line 2,337: | Line 2,258: | ||
5 "*'*r'ac* v'P r"o 36^ i Design Tolerance is not : | 5 "*'*r'ac* v'P r"o 36^ i Design Tolerance is not : | ||
# YES NO VI Acceptance Criteria is met : 2YES__,NO l I Comments | # YES NO VI Acceptance Criteria is met : 2YES__,NO l I Comments | ||
* l l . | * l l . | ||
l Prepared By: -_ | l Prepared By: -_ | ||
| Line 2,353: | Line 2,273: | ||
Critical Boron Concentration B Bank In i Reference Proc No /Section: 1 PT 94.0 Sequence Step Not l I II Bank Positions (Steps) RCS Temperature ('F): 547 ! | Critical Boron Concentration B Bank In i Reference Proc No /Section: 1 PT 94.0 Sequence Step Not l I II Bank Positions (Steps) RCS Temperature ('F): 547 ! | ||
Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): l I (Design) CB: 0 CC: 228 CD: 228 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature ('F): 'W S' 1 i I Test SDA: 228 SDB: 228 CA: 228 Power Level (t F.P.): 0 Other (Specify): | Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): l I (Design) CB: 0 CC: 228 CD: 228 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature ('F): 'W S' 1 i I Test SDA: 228 SDB: 228 CA: 228 Power Level (t F.P.): 0 Other (Specify): | ||
Conditions l (Actual) CB: 0 CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Perfo,tmed: ,y [ | Conditions l (Actual) CB: 0 CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Perfo,tmed: ,y [ | ||
7tv.y g - l ; 71-os- n . | 7tv.y g - l ; 71-os- n . | ||
| Line 2,367: | Line 2,286: | ||
L NE-734 N1C8 Startup Test Report Page 46 of 58 I. - - - | L NE-734 N1C8 Startup Test Report Page 46 of 58 I. - - - | ||
I | I h | ||
LI , | |||
,%A L | ,%A L | ||
, NORTH ANNA POWER STATION UNIT 1 CYCLE 8 L STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET , | , NORTH ANNA POWER STATION UNIT 1 CYCLE 8 L STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET , | ||
| Line 2,379: | Line 2,296: | ||
; Reference Proc No /Section: 1-PT 94.0 Sequence Step No i | ; Reference Proc No /Section: 1-PT 94.0 Sequence Step No i | ||
[ | [ | ||
II Bank Positions (Steps) RCS Temperature ('P): 547 I Test Power Level (% F.P.): 0 | II Bank Positions (Steps) RCS Temperature ('P): 547 I Test Power Level (% F.P.): 0 | ||
,g Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): | ,g Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): | ||
!3 (Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating i | !3 (Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating i | ||
f a 11I Bank Positions (Steps) RCS Temperature ('P): 51(3 2. l | f a 11I Bank Positions (Steps) RCS Temperature ('P): 51(3 2. l | ||
| Line 2,395: | Line 2,309: | ||
Design Value (Actual Conditions) aCB = -7.14 1 0.71 pcm/ ppm Des agn Value (Design Conditions) aCB = -7.14 1 0. 71 pcm/ppe , | Design Value (Actual Conditions) aCB = -7.14 1 0.71 pcm/ ppm Des agn Value (Design Conditions) aCB = -7.14 1 0. 71 pcm/ppe , | ||
Reference Technical Report NE 710 Rev. 0 . | Reference Technical Report NE 710 Rev. 0 . | ||
I | I 1 | ||
I V Acceptance FSAR/ Tech Spec Not Applicable t | |||
+ | + | ||
Criteria Reference Not Applicable Design Tolerance is met : YES NO I VI Comments Acceptance Criteria is met : ._/__YE S NO . | Criteria Reference Not Applicable Design Tolerance is met : YES NO I VI Comments Acceptance Criteria is met : ._/__YE S NO . | ||
| Line 2,427: | Line 2,340: | ||
= % 3.) ;t h, Meas. ositionCrit. | = % 3.) ;t h, Meas. ositionCrit. | ||
a HRef Bank T, steps) | a HRef Bank T, steps) | ||
L Design Value In = 942 1 141 pcm (Critical Ref Bank (Design Cond) Position = 151 steps) | L Design Value In = 942 1 141 pcm (Critical Ref Bank (Design Cond) Position = 151 steps) | ||
Reference Technical Report NE-710 Rev. 0, VEP-FRD-36A I V FSAR/ Tech Spec If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis. SNSOC may specify that i | Reference Technical Report NE-710 Rev. 0, VEP-FRD-36A I V FSAR/ Tech Spec If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis. SNSOC may specify that i | ||
| Line 2,544: | Line 2,456: | ||
.( up IV Test Measured Value RS I SA = C 1 | .( up IV Test Measured Value RS I SA = C 1 | ||
2 .3 (Adj. Meas. Crit. Ref Bank Position = H Y step ) ' | 2 .3 (Adj. Meas. Crit. Ref Bank Position = H Y step ) ' | ||
g Results Design Value RS (Adj. Meas. Crit. Ref Bank ,, | g Results Design Value RS (Adj. Meas. Crit. Ref Bank ,, | ||
(Actual Cond) ISA = 9ll $ I C Position = H5' steps) | (Actual Cond) ISA = 9ll $ I C Position = H5' steps) | ||
| Line 2,552: | Line 2,463: | ||
;I V FSAR/ Tech Spec shall evaluate impact of test res:1+ un safety analysis. SNSOC may specify that Acceptance additional testing be performed. | ;I V FSAR/ Tech Spec shall evaluate impact of test res:1+ un safety analysis. SNSOC may specify that Acceptance additional testing be performed. | ||
I' Criteria Reference VEP-FRD-36A | I' Criteria Reference VEP-FRD-36A | ||
'~~ | '~~ | ||
Design Tolerance is met : / YES _ NO VI Acceptance Criteria is met : 2YES NO Comments II Prepared By: b b UMu Reviewed By: . | Design Tolerance is met : / YES _ NO VI Acceptance Criteria is met : 2YES NO Comments II Prepared By: b b UMu Reviewed By: . | ||
| Line 2,558: | Line 2,468: | ||
Il , | Il , | ||
NORTH ANNA POWER STATION UkiT 1 CYCLE 8 l STARTilP PHYSICS TEST RESULTS ANb EVALUATION SHEET ! | NORTH ANNA POWER STATION UkiT 1 CYCLE 8 l STARTilP PHYSICS TEST RESULTS ANb EVALUATION SHEET ! | ||
iI~ 'I Test | iI~ 'I Test | ||
| Line 2,588: | Line 2,497: | ||
1B-l NE-734 N1C8 Startup Test Report Page 53 of 58 I t | 1B-l NE-734 N1C8 Startup Test Report Page 53 of 58 I t | ||
j g ;,z , | j g ;,z , | ||
'I . | 'I . | ||
| Line 2,626: | Line 2,533: | ||
_NO VI Consents | _NO VI Consents | ||
* As Required n nn Prepared By* x Reviewed By: | * As Required n nn Prepared By* x Reviewed By: | ||
tjM ''N% i lo | tjM ''N% i lo NE-734 NIC8 Startup Test Report Page 54 of 58 LI- .-- | ||
NE-734 NIC8 Startup Test Report Page 54 of 58 LI- .-- | |||
f 3 i 6 | f 3 i 6 | ||
| Line 2,668: | Line 2,573: | ||
'E5 V Acceptance FSAR/ Tech Spec NONE NA | 'E5 V Acceptance FSAR/ Tech Spec NONE NA | ||
'l ' | 'l ' | ||
Criteria | Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met : [YES NO l Acceptance Criteria is met : .f.,YES NO- | ||
Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met : [YES NO l Acceptance Criteria is met : .f.,YES NO- | |||
;I.- VI Comments | ;I.- VI Comments | ||
* As Required ezdb / | * As Required ezdb / | ||
| Line 2,684: | Line 2,587: | ||
Conditions: SDA: 228 SDB: 228 CA: 228 Other (specify): Eq. Xe. - | Conditions: SDA: 228 SDB: 228 CA: 228 Other (specify): Eq. Xe. - | ||
.. (Design) l CB : 228 CC : 228 CD: | .. (Design) l CB : 228 CC : 228 CD: | ||
* Must have k 38 thimblera l l | * Must have k 38 thimblera l l III Bank Positions (Steps) RCS Temperature ('F): "T~gsp Test Power Level (% F.P.): / cog | ||
III Bank Positions (Steps) RCS Temperature ('F): "T~gsp Test Power Level (% F.P.): / cog | |||
, Conditions, SDA: 228 SDB: 228 CA: 228 Other (Specify): i (Actual) CB : 228 CC : 228 CD: 2.26 g g %/g M f Date/ Time Test: ~7/26,/b'7 Perforesa: iggo l | , Conditions, SDA: 228 SDB: 228 CA: 228 Other (Specify): i (Actual) CB : 228 CC : 228 CD: 2.26 g g %/g M f Date/ Time Test: ~7/26,/b'7 Perforesa: iggo l | ||
MAX. REL NUC ENTRAL TOTAL HEAT QUADRANT * | MAX. REL NUC ENTRAL TOTAL HEAT QUADRANT * | ||
| Line 2,708: | Line 2,609: | ||
( NE-734 NIC8 Startup Test Report Page 56 of 58 1 | ( NE-734 NIC8 Startup Test Report Page 56 of 58 1 | ||
r' j 9/ ,l | r' j 9/ ,l I | ||
i I .. , | |||
I .. , | |||
NORTH ANNA POWER STATION UNIT 1 CYCLE 8 | NORTH ANNA POWER STATION UNIT 1 CYCLE 8 | ||
,'IL ' | ,'IL ' | ||
| Line 2,732: | Line 2,631: | ||
(ri-P) / t- F-dH(N) F-Q(T) QPTR 3.5 7. s. ,- | (ri-P) / t- F-dH(N) F-Q(T) QPTR 3.5 7. s. ,- | ||
) | ) | ||
Measured Value- Ph c.%for a4 | Measured Value- Ph c.%for a4 | ||
-2 3*1. for NA NA NA ., | -2 3*1. for NA NA NA ., | ||
Resu ts ^ #* | Resu ts ^ #* | ||
Design Value ' lE lI f ! !:; | Design Value ' lE lI f ! !:; | ||
Revision as of 17:07, 18 February 2020
| ML19327B125 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 10/31/1989 |
| From: | Dziadosz D, Main A, Trace D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML19327B124 | List: |
| References | |
| NE-734, NE-734-R, NE-734-R00, NUDOCS 8910250243 | |
| Download: ML19327B125 (60) | |
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7.. LI LI h' TECilNICAL REPORT NE-734 - Rey, 0 L t LI
- . NORTil ANNA UNIT 1, CYCLE B STARTUP PilYSICS TEST REPORT ,
)
ol NUCLEAR ANALYSIS AND FUEL Ll i5 POWER ENGINEERING SERVICES. VIRGINIA POWER l OCTOBER 1989 F i
'l PREPARED BY: /d/f/5ty A. P. Main Date REVIEWED BY: bd 10/4/1f4 D. A. Trace Date REVIEWED BY: //[2#hb # MMd7
? R. H. 'Garvert/ Date APPROVED BY. W -
/o/h/ ,
D. Dzifdosz d Ddte' Q l g QA Category: Nuclear Safety Related Keywords: N1C8, Startup i
, ... - -... . -.., , - . . . - , . . ~ . . -,. ...,-,,.,.:,----.,-......,--.---.-..~~--.-. - . - . . . . . . . , . . - - , . . ,
1
l
- l. .
If CLASSIFICATION / DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those t'or which they .have been specifically prepared. The Company
- therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, Tile COMPANY HALES NO WARRANTY OF MERCilANTABILITY OR FITNESS FOR A PARTICULAR l .
PURPOSE,- NOR SilALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR' USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report availabic, 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 sna11 itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory 4 whatsoever (whether contract, tort, warranty, or strict or absolute
- =
liability), for any property damage, mental or physical injury or death, i 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 in it. I I I I NE-734 NIC8 Startup Test Report Page 1 of 58
.c, , : ).
' v.; '
h' 1 i.. n TABLE OF CONTENTS f mo .; i . PAGE i L 1 t
,I Classification / Disclaimer...............................
Table of Contents........................................ 2 + 3. List of Tables..................................... .... 3
.j List of F1gures......................................... 4 i 4 / Preface................................................. 5 Section 1 Introduction and Summary................... 7 <
th-= Section 2 Control Rod Drop Time Measurements......... 16 : c Section 3-Control Rod Bank Worth Measurements........ 21 Section 4 Boron Endpoint and Worth Measurements...... 26' ) Section S Temperature Coefficient Measurement........ 30 Section 6 Power Distribution Measurements............ 33 'I i- Section.7 References................................. 40 APPENDIX Startup Physics Tests Results and
' I, Evaluation Sheets........................ 41 7 i
f
- g. ,
g 1 I l l 4
;I Pa e 2 of se g e . m s1ce Startu , T.st oc ,o m
n, , , e ' 1
'#^
l f, i.. t g ' x3 LIST OF TABLES . s TABLE , TITLE PAGE ! s .. .; i 1,1 Chronology of Tests................................... 10 i N , 2.1 llot Rod Drop' Time Summary..............-............... 18-
.3.1 Control Rod Bank Worth Summary. ...................... 23 l
4.1 Boron-Endpoints Summary...................... ........ 28 3 > l 5.1 Isothermal Temperature Coefficient Summary............ 32 6.1 Incore Flux Map Summary............................... 35
., 6.2 Comparison of Measured Power Distribution Parameters With Their Technical Specifications Limits............ 36 i
.g.
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y,,- , w p L, N E s 1 L.- . .: ft 'it' LIST OF FIGURES j s TITLE PAGE f g. ' FIGURE 1 JB , l'[ Core Loading Map.......................................... 11 1.1 , 1.2 Beginning of Cycle Fuel Assembly Burnups................. 12 Incore Instrumentation Locations......................... 13 1.3 Burnable Poison and Source Assembly Locations............ 14 i 1.4 , 1.5 Control Rod Locations.................................... 15 ; 19 l 2.1 LTypical Rod Drop ~ Trace................................... 2.2 Rod' Drop Time - Hot Full Flow Conditions................. 20 { 3' .1 Bank B Integral Rod Worth - IlZP.......................... 24 l 3.2 Bank B Differential Rod Worth - IlZP...................... 25
'4.1 Boron Worth Coefficient.................................. 29 ,
Assemblywise Power Distribution - 297. Power.............. 37 I .6.1 6.2 Assemblywise Power Distribution - 74% Power.............. 38
.6.3 Assemblywise Power Distribution - 1007. Power............. 39 LI g
g .
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Pase 4 o, 5e
- 3. ss-734 m ce sta,t., 1est eePort
!: t , b l 1 PREFACE 3 o'
.This report presents the analysis and evaluation of the physics tests which were performed to verify that the North Anna 1, Cycle 8 core could I be operated safely, and makes an initial evaluation of the performance l
t of the core. It is not the intent of this report to discuss the particular I >' , methods of testing or to present the detailed ' data taken. Stcndard test [
,' techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on ;
file at the North Anna Power Station. Therefore, only a cursory , discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison of the test results with design p'redictions, and an evaluation of the results. The North Anna 1, Cycle 8 Startup Physics Tests Results and Evaluation Sheets are included as an appendix to provide additional information on the startup test results. Each data sheet provides the following information: 1) test identification, 2) test conditiona (design), 3) test conditions (actual), 4) test results, s) acceptance criteria, and 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values of the measured parameters were , completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group *, During the tests, the data sheets were used as guidelines both to verify that
'. the proper test conditions were met and to facilitate the preliminary rag.
g NE-m N1ce Stamup rest eopom s of se
4
. y; i
. ; J'.
?
comparison between measured and predicted test results, thus enabling a ! quick identification of'possible problems occuring during the test's. , f I l, I .s f l , .l-. l 1 if S . lE, a I LI 2 NE-734 NIC8 Startup Test Report Page 6 of 58
y, i L' f
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g 3 e si SECTION 1
!g.E'
4
- p. .
gi INTRODUCTION AND
SUMMARY
L On February 25, 1989 Unit No. 1 of the North Anna Power Station shutdown for its seventh refueling. During this shutdown, 92 of the' 157
. fuel essemblics in the core were replaced with 64 fresh fuel assemblies, ' I .,
25 twice burned fuel assemblies, and 3 thrice burned fuel assemblies. l Tho' eighth cycle core consists of 12 sub-batches of fuel: two once-burned e batches, two from Cycle 7 (batches 9A and 9B); four twice burned batches,
. g. ,
- W- one from North Anna 2 Cycles 2 and 3 (batch N2/4A), one from North Anna h
L 2 Cycles 3 and 4 (batch N2/5A), one from Cycles 2 and 3 (batch 4A), and
)
F- one from Cycles 4 and 5 (batch 6A); two thrice burned batches, one from Nortn Anna 2 Cycle 3, 4, and 5 (batch N2/SA) and one from Cycles 5, 6, and 7 (batch 7A); and four fresh batches (batches 10A, 10B, IOC, and
~I- N2/9B). The core loading pattern and the design parameters for each batch are shown in Figure 1.1. Fuel assembly burnups are given in Figure 1.2.
The incore instrumentation locations are identified in Figure 1.3. Figure - l 1.4 identifies the location and number of burnable poison rods and source l 1 assemblies for Cycle 8, and Figure 1.5 identifies the location and number i of control rods in the Cycle 8 core. 1 1
-: On July 15, 1989 at 1532, the eighth cycle core achieved initial I l criticality. Following criticality, startup physics tests were performed l
as outlined in Table 1.1. A summary of the results of these tests i l follows: I "8- = "1oe 8t <t e ' ' " r r'
" 8-
' 88
. 1
(');(q.{ [ . - I The measured drop time of each control rod was within the 2.2 [ ,, 1.. 3 second limit of Technical Specification.3.1.3.4.
'2 . Individual control rod bank worths wori measured using the rod swap technique 8 and the results were within 7.2% of the des'ign I predictions. The sum of the individual measured control rod, bank worths was within 1.0% of the design prediction. These results-are within the design tolerance of 115% for. individual bank worths-(110% for the rod swap reference bank worth) and the design tolerance of t10% for'the sum of the individual control' rod bank
- worths. ,
l (
- 3. Measured critical boron concentrations for two control bank :
configurations were within 13 ppm of the design predictions. These results were within the design to1erances and also mot the '
~
Technical Specification 4.1.1.1.2 criterion that the overall core reactivity balance shall be within 1% Ak/k of the design G I,'- prediction.
- 4. The boron worth coef ficient measurement was within 1.9% of the design prediction, which is within the design tolerance of 10%.
- 5. The measured isothermal temperature coefficient (ITC) for the )
all-rods-out configuration was within 0.3 pcm/'F of the design 5 prediction. This result is within the design tolerance of 13 pcm/'F. The measured ITC of 0.64 pcm/'F meets the Technical Specification 3.1.1.4 criterion that the moderator temperature
- l' coefficient (MTC) be less than or equal to +6.0 pcm/'F. When the f
g --m h.1ceStamupree ,epos eag. e of 5e 1
o %~ s a .
' I
's% Doppler temperature coefficient and a 0.5 pcm/'F uncertainty are ,
. accounted for in the MTC limit, the MTC requirement is satisfied as long as the ITC is.less than or equal to +3.77 pcm/'F. .
8 ,
- 6. . Mode 1 (See' Reference 4) core power distributions were within I -
established design tolerances. Generally, the measured core q power distribution was within 3.5% of the design predictions. The heat flux hot channel factors, F-Q(T), and enthalpy rise hot 5 channel factors, F-DH(M), were within the limits of Technical 1 Specifications 3.2.2 and 3.2.3, respectively. In summary, all startup physics test results were acceptable. Detailed results, specific design tolerances and acceptance criteria for each measurement are presented in the following sections of this report. i I I I I , S.
- I 1
I l
~ 's . . m m ce start., 1est eeport ease , of Se
( J . 1 h Table 1.1 . I: NORTil ANNA 1 - CYCL,E 8 STARTUP PilYSICS TESTS CilRON01,0GY OF TESTS i I ; .l u Referer.co . Test Date Time Power Procedure flot Rod Drop - flot Full Flow 7/14/89 1930 llSD 1-PT-17.2 L ur Zero. Power. Testing Range 7/15/89 1705 llZP 1-PT-94.0 Reactivity Computer Checkout 7/15/89 1742 IlZP 1-PT-94.0 ig.. Temperature Coefficient.- ARO 7/15/09 2235 IlZP 1-PT-94.0 g- Boron-Endpoint - AF0 7/15/89 2359 ' llZP 1-PT-94.0 Bank B Worth 7/16/89 0007 Il2P 1-PT-94.0 Bank D Worth - Rod Swap 7/16/89 0342 Il2P 1-PT-94.0 I 1-PI-94.0 Boron Endpoint - B in 7/16/89 0501- IlZP Bank C Worth - Rod Swap.- 7/16/89 0507 Il2P 1-PT-94.0 Bank A Worth - Rod Swap' 7/16/89 0550 llZP 1-PT-94.0 Bank SB Worth - Rod Swap 1-PT-94.0
- I; Bank SA Worth - Rod Swap 7/16/89 7/16/89 0646 0722 ilZP I!ZP 1-PT-94.0 Flux Hap - 29% Power . 7/17/89 1842 29% 1-PT-21.1 f Flux Map - QPTR Verification 7/19/89 0724 74% 1-PT-21.1 1
'I, Flux Map - !!FP Flux Map - I/E Calibration 7/26/89 7/27/89 1549 0600 100%
100% 1-PT-21.1 1-PT-22.2 - Flux Map - I/E Calibration 7/27/89 1715 100% 1-PT-22.2
- g-I .
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y 7.j g. '
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.; NORTil ANNA UNIT 1 CYCLE 8 i BEGINNING OF CYCLE FUEL ASSEMBLY llVRNUPS
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'. l l--> ASSEM8tV SUPNUP l' l l l LI l 1 [. l L I ! = 1 NE-734 NIC8 Startup Test Report , Page 12 of 58 y - - - - s y;; L .g. ,
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.Y Figure _1.3 I,
~
NORTil ANNA UNIT 1 - CYCLE 8 l
- INCORE INSTRUMENTATION LOCATIONS
;I' 1
P P N M t t J H C F E D C 5 A I MD 1 I i TC l ' l. TC i TC li MD 2 I 11 MD , MD I 1 l ND 1 I i 1C 1 TC i TC l ' TC I TC 1 5
~~
1 i, I 1 1 l 1 TC MD li MD l' MD TC 1 I I 4 l l l l i i i i l MD 1 MD l MD 1 MD ' 1C 1 MD TC TC . MD TC 1 1C & 5
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I I i x l TC 1 l l MD 1 TC i 14 l 1.,,,,,,,,, l 1 1 MD - Movable Detector l l
.I. ' TC - Thermocouple MD 1 1C i .1C l l I-15 i i I
- g ,
I . I I _. - -
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)
~
! Figure 1.4 U .
f N NORTil ANNA UNIT 1 - CYCLE 8 BURNABLE POISON AND SOURCE ASSEMBLY LOCATIONS
- r. -
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- l. S$nn - StCONDARY SOUkTE LI I:'
L
. (.
h l ;
e .; Figure 1.5 ; l NORTil ANNA UNIT 1 - CYCLE 8 CONTROL ROD LOCATIONS R P N N L K J N G F E D c B A I Loop c
'r Loop B l l l l 1 outlet 1 I l~l Inlet l N-41 Nl l 1 l * -l
- l. I SA I l*l l*l I SA l l sP l V l N 45 '
5 I I I I I I I I I I ; E i ic 1- Ia 1 I 1 Ia l .Ic l l 4 r
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i 1 1 se I I I i se l-I I I sr I I 'I i l-l 1 i se i 1 1 l I I l- 5 i I I l i I l' I I I 'l l I I I i
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Inlet i l l sA I I I I se I i sa I i sr I i sA I l 7
\l I I I I I I i l l- 1 I I I i l/outle+
1 90*- 41 1o i I i ic 1 1 I Ic i l i lo l 1 - 270' a I I I 1 I 1 I IA I
'l I
l sA l I I Ia l I l sP I I I I Io l 1 l s8 1 I 1 1 lc l 1 1 1 I sB l 1 l0 l I l I I I I ls l I l SA I I I l_l I A 'l I i l 1 i
'9 10 I
I I l l I I I i 1 1 I I I I
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l I I 1 l I Ic I I l so l l I l IB l i l I 1 l I l 1 l se 1 I 1 1 I 1e i 1 I se 1 I I I Ic I I I sr l I I I i I l I 11 12-I I sP l. I SA i 1 sA l l l l 15 l- I- N-44 l l 1 1 l iA i 1 l 1 l lo 1 1 l 1 1 iA I 1. l l l i I l N-42 14
/ 1 1 1 1 \Loop 15 I. Absorber Material Loop outlet A 1 l I
o' l l Inlet A Ag In-Cd ) ! l l
>W Function Number of Clusters l
control Bank D 8 I Control Bank C 8 I a Control Bank B 8 i Control Bank A 8 l shutdown Bank s8 8 ' '. 5, shutdown Bank SA 8 ) sP (spare Rod Locations) 6 l l d .. l
;I "c- - " > ce -- - - ~ u - 8e l
y. p i SECTION 2 CONTROL ROD DROP TIME HEASUREMENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot was less than or equal to the maximum allowed by Technical Specification
.3.1.3.4. The control rod drop times were measured in Mode 3' with RCS
, Tavg above 500'F and all reactor coolant pumps operating.
' The rod drop times were measured by withdrawing a rod bank to its fully withdrawn position, and removing the movable gripper coil fuse and stationary gripper coil fuse for the particular rod of the bank to be I ~ dropped. This allowed the rod to drop into the core as it would during a plant trip. The stationacy grippe'r coil voltage and the Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded to determine the the red drop time. This procedure was repeated for each I
1
.. control rod.
e W As shown on the sample rod drop trace in Figure 2.1, the initiation i of the rod drop is indicated by the decay of the stationary gripper coil I- voltage when the stationary gripper coil fuse is removed. As the rod yl
- drops, a voltage is induced in the IRPI primary coil. The magnitude of {
1 this voltage is a function of control rod velocity. As the rod enters l 5 the dashpot region of the guide tube, its velocity slows causing a voltage decrease in the IRPI coil. This voltage reaches a minimum when the rod reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing. I ""~"'""'""""'"'""" " """
- i
[ , ., , o so . pt The measured drop times for each control' rod are recorded on Figure ! 2.2. The r, lowest,' fastest, and average drop times are summarized in Table
' c 2.1. Technical Specificat'fon 3.1.3.4 specifies a maximum rod drop. time 1 a
I from. loss of stationary gripper coil voltage to dashpot entry of ' 2.2
} .
seconds with the RCS at hot, full flow conditions. These test results
, satisfied this' limit. l I :
LIL g I l 'I . I
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IL I I NE-734 NIC8 Startup Test Report page 17 of 58
w . _ . - _ _ . I . l
' Table 2.1 ;
NORTil ANNA UNIT.1 - CYCLE 8 STARTUP PliYSICS TESTS Il0T ROD DROP TIME
SUMMARY
I ! t R0D DROP TIME TO DASilPOT ENTRY I SLOh'LST ROD FASTEST ROD AVERAGE TIME i
.I
, B-06 1.78 sec. C-09 1.45 sec. 1.58 sec. , lI f . LI I i' lI :
'I
' I' I ! I NE-734 NIC8 Startup Test Report Page 18 of 58 ; o _ _ _ _ _ _ _ _ - . . _ . . . . . . . _ _ . . _ . _ . . . . _ . _ . _ . . _ _ . , _ _ . , . . _ . , . _ . _ , , , _ . _ . . . _ _ _ _ . , . . . . _ _ . . . . . . , , _ , _ . , , _ . . . . _ . . .
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. ,W se % O O > '
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*t " STATIONARY GPIPPER "o 2 COIL VOLTAGE TRACE NN O
Se c r O"g
- ROD DROP TIME Q O 8'
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. . . . . ~ . _ , . . . , ..
~
pi' y, l t
.l ' Figure 2.2 i NORTil ANNA UNIT I - CYCI.E 8 STARTUP PHYSICS TESTS .
R0D DROP TIME - Il0T FULL FLOW CONDITIONS I; f
'R- P .M M L E J H G F f 9 C 5 A. a t I .
I I st 1 l l I l l 1.h 1 1.48 1.57 2 l l l I 1 i l i l I i i 1 l l 1.55 I 1.55 I i 3 . I l 1 1 1 ' I i 1 1 1 1 1. i I i i l1%l - l 1.53 l lI I 1.58 I 1.% 4 i 1 1 l I L _I I I I l I i ;
'I.
I 1 l i l 'i 1.63 1 1 I I 1.58 1 5 I l I ! I i l l i l i
!^ 1.51 1 11.621 1.57 I I 1. % '
3.59 . I !.60 . 1.76 ' -6
, l '
t 1 I I
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. I 1.60 1 ' l 1: . 1 60 1 1 1.59 1.72 '
4
. I l 1 I I I 1 i i i l
- I l i 1 1 l l 8 i 1.h i 1 1.53 1 1.% 1 i 1.45 l l 9 '
1 1 1 1 i 1 i ' ! I I I I I l 1 1 L l l i 1
'I 1.57 1 1 1.5r '
I 1.55 l 1. 1.58 1 1.61 i 1.% i 1.74 16 a' i 1 1 I I I - 1
, ' I- l I
l i ' 3.69 i 1 i I I l I 1 I l.60 / I I
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', t 1 i i i i l I .
I 1.55 l l 1.63 l 11 11.551 1.M I I It i i 1 ? I' l 1: 1 i 1 I I I i 1 l I I l.55 l 1.54 1 1 13 # 1 l i l i 1 t 1 I I l l l 1 i 1 1.73 11.591 1.59 4 l 14 I
'Ii '
l I i 1 I l l 1 I 1 i 1 I l l 15 I l I l l M.MM l--> ROD DROP 11ME 10 DA5HP0f (MIRY (EECA i l i I j l t : Lg I' 4 l
- g. xE m xice S_, T.m ,,_ Pe . 2e e se
n.
., ~ ,
[g< [ SECTION 3 ll I CONTROL ROD BANK WORTil MEASUREMENTS
. Control rod bank worths were measured for the control and shutdown banks using the rod swap technique 8. The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity.
changes resulting from the reference bank movements were recorded continuously by the reactivity computer and were used 'to determine the differential and integral worth of the reference bank. For Cycle 8, Control Bank B was used as the reference bank. After the completion of the reference bank reactivity worth. measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor just critical and the reference bank near full insertion. Initial statepoint data for the rod swap maneuver were obtained by enving the reference bank to its fully ; l
- I.- inserted position and recording the core reactivity and modcrator temperature. From this point, a rod swap maneuver was performed by withdrawing the reference bank several steps and then one of the other control rod banks (i.e., a test bank) was inserted to balance the reactivity of the reference bank withdrawal. This sequence was repeated I. until the test bank was fully inserted and the reference bank was I
positioned such that the core was just critical. This measured critical l position (MCP) of the reference bank with the test bank fully inserted was used to determine the integral reactivity worth of the test bank. 1
. l NE-734 NIC8 Startup Test Report Page 21 of 58 1
I: The core reactivity, moderator temperature,. and the diffcontial worth
-of the reference bank were recorded with the reference bank at the MCP.
The rod swap maneuver then was repeated in reverse such that the reference bank again was near full insertion with the test bank fully withdrawn from the' core. This-rod swap process was then repeated for each of the other ; control and shutdown banks. A summary of the test results is given in Tabic 3.1. As shown in this table and. the Startup Physics Tests Results and Evaluation Sheets J given in the Appendix, the' individual measured bank worths for the control s 1 and shutdown banks were within the design tolerance (110% for the I. reference bank, 15% for each test bank worth greater than 600 pcm, and 1100 pcm for each test bank worth of less than 600 pcm). The sum of the , individual measured rod bank worths was within .1.0% of the design prediction. This is well within the design tolerance of 110% for the sum of the individual control rod bank worths. The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively. The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod worth values were satisfactory. I i I NE-734 NIC8 Startup Test Report Page 22 of 58
{ ' I , .; - I. Table 3.1 NORTil ANNA UNIT 1 - CYCLE 8 STARTUP PilYSICS TESTS CONTROL ROD BANK WORTil SUMMAki.- . T
}
MEASURED PREDICTED. PERCENT DIFFERENCE , WORTli' WORTil (%) BANK (PCM) (PCM) (M-P)/P X 100 B-R.f.r.nc.' Bank -1318.5 1313.0 0.42 D 948.8 943.2 0.59 861.6 849.3 ' C 1.45 A 293.9 274.2 7.18 * ,
? SB 1025.7 1035.1 -0.91 t SA' 928.8 911.3 1.92 Total Worth 5377.3 5326.1 0.96 3 I
.g-
. o m ., _ . 1 1... t,.. le0 P...
I ' I l l I-g sE-,3. s1ce Sta,1 , 1.., .P , Pa . 23 o, Se
t L r ' t Figure 3.1 i NORTil ANNA UNIT 1 CYCLE 8 STARTUP PilYSICS TESTS l BANK B INTEGRAL ROD WORTil Il2P ! ALL OTilER RODS WITilDRAWN I
-I l
.r i
1 ,5 0 0 --
..... "..g.. .. .,
L"""J.. . . .. . . .. . . ., , ... .. .. . , . . .. .. . .. .. I 1,400- ". +
.. .. . ._ . , . . , , , .1- ... ... ... . .. . . .. . , . . . . . .
..l ..
l- l- -r-9.. - - ; 1,300-" . .%. . .. %~..g+ ....- . .. y.. , .
"l-- ..-.. 7..
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I 1,200- .-...
+- -
+-
. .._ .+. . .
~- - -"-
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1
~z 1,100-
# t-
.. ~.. .. ..
i I
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W 1,000--.." . l v .. . . . . .", = QQQ . .. . . _,,. .i .. . ..
"*" Pred eted 4
(o. BOO- - ".
= ..,
- 700 = . ... .. .
4.., . .
- meosured I
..o. ... . .. , = .. = . .. o ... . .
t .. 600- ". g ._, . .. , . . , ... . . . ... . . . .. .., L 500- " . -T.., . . .
..L
- - = -
~...
I
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4- --c - - 400-
" - = - - -
; .. ..... . , 1 300- - - - - - -
-} ,.. ..}.. d-) - - - - - - -
g-"
.I 2QQ.
.o. .. .,
.g ..
..... o.
k.% . l
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=L - -
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I
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,l ,i , , , . . ri - t 0 8 18 24 32 40 44 M 64 72 to 08 N 108 120 132 144 1M 1H ISO 192 204 218 228 BANK POSITION (STEPS)
I L
'l l
NE-734 NIC8 Startup Test Report , Page 24 of 58 . l l 1
i
'l I .
l Figure 3,2 NORTH ANNA UNIT 1 CYCLE 8 STARTUP PHYSICS TESTS I
*tANO B DIITERENTIAL ROD WORTH HZP
, ALL OTHER RODS WITHDRAWN ) i i i
. \
12,00 - - - - --- ~ ~ ~--~, r
- 1111111---l..,!....1.1...o. . i .. --~~[ I-
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11i I bk i li i iil iil I.i li i ii ii .i i 2 00--i - iil+ii ii
- ----- -~ ~ ~- - + - +4-- -- - - - - - + - ----
i it - - - , , - -..i . i ii
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. i i . i ..i. +e i ..y i .i i ..>..i .. i..,. .. .. -
i..u.. .. i .,i - . + . + . . , ii i ! !. : 1- 1! I ii iii ! . I 1*00--+I.i i - !> - +- +- + + - ++- -- + + - + - * - - - --' < r 1
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.....1.t it -
i
' 'l
- till
't l' *l i ,""i illi i il!
l l'"*i " T*le TV s a iilli!!! lilii!!ililili lii! l 1 1 **i l' l' +i i i ! 0 i '1'8'I4'it'io 4'S'St'i4'it'$0'it'it' 'lii '120 '1i2"144' '15i 150 'lii iii '254 '218 IS BANK POSITION (STEPS) ! , ) I ;
}
g : t I h NE-734 NIC8 Startup Test Report 25. of 58 Page
[:' 5 . ower, reactor coolant system ; l , (RCS) boron concentrations were measured at selected rod bank i configurations to enable a direct comparison of measured boron endpoints ' with design predictions. For each critical boron concentration l t measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the acazured critical boron concentration values were modo to account for off nominal f I control rod position and moderator temperature, if necessar>. t The results of these measurements are given in Table 4.1. As shown { in this table and in the Startup Physics Tests Results and Evaluation l Sheets given in the Appendix, the sensured critical boron endpoint values , i were within their respective design tolerances and met the requirements ; of Technical Specification 4.1.4.1.2 regarding core reartivity balance. I In summary, the boron endpoint results were satisfactory. l i Boron Worth Coefficient [ The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) , was determined. By relating each endpoint concentration to the integrated rM worth present in the core at the tihe of the endpoint measurement, the value of the DBW over the range of boron endpoint concentrations was obtained. ; NE-734 NIC8 Startup Test Report Page 26 of 53
J'4-y. .l is i
. I' A plot of the boron concentration versus inserted control rod worth l is shown in T!gure 4.1. As indicated in this figure and in the Appendix, the DBW measured was 7.01 pcm/ ppm. This is within 1.9% of the predicted value of +>.14 pcm/ ppm and is well within the design tolerance of 110%. j
, n s....,,, ,,,e ...s.r os nor.. ..,t,, coe m.,en, w.s sa t ,s f.c o,, .
g l i l I . I . I I I I-I i
-I g st. m m ce st.,t.,1es, ee,o,t e... 2, o, se
_ . - _ _ _ _ e
g : i I Table 4.1 l NORTH ANNA UNIT 1 CYC1.E 8 STARTUP PHYSICS TESTS BORON ENDPOINTS
SUMMARY
l 5 l l I Measured Predicted Difference l
'l, Control Rod Endpoint Endpoint I Configuration (ppm) (ppm)
M-P (ppm) ! ARO 214e 2135 +13 D Bank In 1960 1964* -4 ; p i
- The predicted endpoint for the B Bank In configuration was l I adjusted for the dif ference between the measured and predicted '
values of the endpoint taken at the ARO configuration as shown
- in the boron endpcint Startup Physics Test Results and Evaluation I Sheets in the Appendix.
i l 5 ! I l I ; i Ip h 9 I , g xE. m x,Ce Sta,t.,1cs, ,ep., Pa,e e of se
1
, \
rigure 4.1 ! i
- l NORTil ANNA UNIT 1 CYC1.E 8 STARTUP PHYSICS TESTS i
BORON WORTH COEFFICIENT I i tI l l l> lg Measured DBW = -7.01 pcm/ ppm 1,5oo - .
- - - - - , - ~ ~ - - - - - - - --- -- -, !
t
-i I
- I ---
-- -;- a -- 1 i i 1,400- ' --+-- - - - -i - -l - - - - . - . . .I - - t
-+-----l--4--l- --l -
4 1 i '
- - + -l - l - 1 1'300 - - - - +I - l 1 1,200- - I - - .i l
1 l
. I :;-- -I I i ---- -
i i - -.l - -...--- - i I II - 3,300 . .......! ........I .......+.I....... I 4
... ....i.....4-I....I.......I...,....I........,....4.....
.!.. ... . l
.... .l -1 .I. I. .I... . .... i I
i
,3,000 _.i,........i ... ....i.... ...;+.. .. ;1 I I I i
_: ......................................I......I.,i...,I_.
. . . . . . , . ... .. . ..s ..... .I......
l M goo.........................$.....-i I
.- ...,............f......... .!.. ...
j lI
....,......m..
i 1 4 i ....I.......... .. e 800 -t j- -4 i l
-)-
j- -- 7-j- - ; 5 700 = 4 J -- ---e-, I
- , -t - - - - -- !
soo i , j-,- ! W r t- - - j r t- r -- W 500- l r t4- !- 7 5-4; ! - -]- - 'j-ll - r - -"-'- ' i l 4oo. j......L... 4.. ...j..
! .. { .!'....
.. .. ... ..!..2--" -l. _.!..
. . . .. . l . . . . . , ______ j 300- Ii!
-~~ -
i l r- -:-+-"-- -+--- I I
-I -+
200 - - - -- -I + +l l
-I --r -- --- - - - --- - - - +l J i -----
I
, oo. . ....+.....z.I .... .... i ...i .. 1 .. .
.-......... l
. - .. . . - . . . .... . .. +l . . . . . -
l
' I o .
,' m 1940 1D00 1900 2000 2020 2040 2000 2000 .
2100 2120 2140 2160 g BORON CONCENTRATloN (PPW) 'I d 4 4 8 . I : L 4 bk
I
'I ;
Ig i SECTION $ ( 1 L TEMPERATURE COEITICIENT MEASUREMENT LI i The isot hern.a1 t emperature coefficient (lTC) at the all-rods-out condition is measured by controllitig the reactor coolant system (RCS) l temperature with the steam dump valves to the condenser, establishing a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer. Typically, this test sequence i
'I includes a cooldown followed by a heatup; however, due to high heat reinoval by steam generator blowdown, it was not possible after the i
I cooldown to heat up only on reactor coolant pump heat input. Therefore, j i nuclear heating was used to raise temperature to approximately 547'r, and i flux was re established within the zero power testing range. A second couldown was done to remeasure the ITC. II Reactivity was measured during both RCS cooldowns of approximately ! 3.2'r. Reactivity and temperature data was taken from the reactivity ; computer and strip chart recorders. Using the statepoint method', the temperature coefficient was determinad by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which plotted reactivity versus temperature, confirmed the statepoint method ! in calculating the measured ITC. I The predicted and measured isothermal temperature coefficient values 1 are compared in Table 5.1. As can be scen from this summary and f rom the Startup physics Test Results and Evaluation Sheet given in the Appendix, Lg xe.,3. x1Ce Sta,t , 1est , ego,t rage x - SS .
.- . - . . _ - ~ . . -. - . - - - - . -.
I
't
- g. the measured isothermal temperature coefficient value was within the i
design tolerance ' of 13 pcm/'T and met the requirements of Technical . Specification 3.1.1.4. In summary, the measured result was satisfactory, ; I l 1 l 1 I i l i I ! 1 0 1 5 l t
.I !
l l l
- 'I i r !
l lE. LE NE-734 NIC8 Startup Test Report ! Page 31 of 58
{>. t l Table 5.1 ; NORT}l ANNA UNIT 1 CYCLE 8 STARTUP PilYSICS TESTS ' ISOTilERNAL TEMPERATURE COEFFICIENT
SUMMARY
'j I i I :
ISOTilERMAL TEMPERATURE COETTICIENT ( BANK l POSITION TEMPERATURE RANGE BORON CONCENTRATION (PCH/'F) ! ('F) (ppm) C/D C/D AVE. DirrER. (
#1 #2 MEAS. PRED. (M P) i 543.5 j I. D/217 to 546.,
2145 +0.80 +0.47 0.64 0.94 -0.30 L I I : I l I I ! I : I i I l I 4 5 : xE.23A xico St.,,, Ten Report Page 32 w 58 3
I I SECTION 6 I POWER DISTRIBUTION HEASUREMENTS E The core power distributions were measured using the movable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbios in 47 core locations (see Figure 1.3). For each traverse, the detector voltage output is continuously monitored on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Fol) core, three-dimensional power distributions are determined f rom this dat.a using the Westinghouse computer program, INCORE8 . INCORE couples the measured voltages with predetermined analytic power to-flux ratios in order to determine the power distribution for the whole core. A list of the full-core flux maps taken during the startup test prohtu and the measured values of the important power distribution parameters is given in Table 6.1. A comparison of these measured values with their Technical Specification limits is given in Table 6.2. Flux Map I was taken at 29% power to verify the radial power distribution (RPD) predictions at low power. Figure 6.1 shows the measured RPDs from this I flux map. Flux maps 2 and 3 were taken at. 74% and 100% power levels with different control rod configurations. These flux maps were taken to check at power design predictions and to measure core power distributions at. various operating conditions. The radial power distributions for these maps are given in Figures 6.2 and 6.3. These figures show that the ,I measured relative assembly power values were generally within 3.5% of the predicted values. Further, the measured F-Q(T) and F-DH(M) peaking factor sE. m slCe Sta,tu, 1est ,epo,t rage u of se g .
i l l ll values for the at power flux maps were within the limits of Technical i r Specifications 3.2.2 and 3.2.3, respectively. In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the ! g accident analysis acceptance criteria, and the Technical Specification ; g l limits. It is therefore anticipated that the core will continue to ; h I i I l I l E l 5 : l8 . 1
~
l E I : I . 1 I I " " >' "2*"""""""""" "- "' '
r- ] l I l TABLE 6.1 NORTH ANNA UNIT 1 - CYCLE 8 STARTUP PHYSICS TESTS ! INCORE FLUX MAP
SUMMARY
j I : l I 1 4 i i I I 6Lsta
. I 1
i i f Ott) HOT 1 1 l F DHtMI HOT 4 l COPi F(fl
-1 i
t i MAP t HAP- UP . 16ANK 1 Chase (( F ACION i C6ML. FACTOR l Maa OPIR AilAL, NO. N SCRIPIl0N lMO. DAtt lewd /IPeePl D l i I . OF F OF ' I I i I MIU l(231$f! PSI AstylPINI Axl All i l 1 1 I AS$vlPINtf-DmMal Astat i fits) Nas ILOCl IPolNilF-et i) l l l lPOINil l l l SE1 1THIM (Il {$l(& l L ~ 4 ~i R ..A9L 1.lr9l1.,lwlw!30 ' ,.il. 'wlwl 1.,0, h,-icmia.,lwl -,. ,lr' l r F,.89-A9 I 101PR VLRIFICA180N 12 IHOT f ull P0wik 1 13 1_1 F t6 49 47 l Fel 197 l N 68 NDI F9 FSF (1901 fit I Clll Iml F9 lI I_l l 1.959 8.4% N 64 M01 3.625 1 29 11.F7318.0091 teW1 -0.671 64 Lill NN1 1.398 1 30 ll.intil.0051 tsN1 *l.35l 45 lI I I l Il 1, I I' NOI(.$ 3 Hof $P01 LOCAT10stS ARE EPICIFl(D SV CIVING A$$(M$tY LOCaf10NS (l.C. H 8 !$ THE CINI[p OF-CONC A$$ENtLV), f ot LOWED $Y THf PIN LOCA110N (DENOTED SV THL *V" C00RDINAf t b11H TH[ $(V(NittN 90ets or f utt RODS L(ITERf D A THRouGH R AND 184 *K" C00RDlh&ff D[$1Gesaf(D IN & $lh!L AR hAsest[R). IN 164 *E* DIREC180N 164 CORE 15 DIVIDt0 INTO 68 AtlAL PolNi$ ST ARTING FROM THE TOP OF THE Cont.
- 1. F 041) INCLUDES A T3f al LMC(p1 AlhiY OF I.S$ R l.$3.
I 2. OP1R OuADRANT POWER flL1 RAfl0.
- 3. MAP $ 4 AND $ WCRC QUARf(R-COPC flUr naps lat(N FOR INCORt/taCOHf CALIS& ATION. (1/( CAllSRATION)
I I-I LB LI I I I I I "8- = == s' " t " - - r- >> " 'a
kly ' l. I E Table 6.2 Ll '5 NORTil ANNA UNIT 1 CYCLE 8 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS {' WITH THEIR TECHNICAL SPECIF~i CATION LIMITS i t-l F-Q(T) Il0T F-Dil(M) HOT !g CilANNEL FACT 0f.* CllANNEL FACT 0lt '3 MAP l NO. MEAS LIMIT MARGIN MEAS LIMIT MARGIN ! I
,(%) (%) i 1 ?.118 4.369 51.4 1.502 1.807 16.9 2 1.939 2.944 33.7 1.413 1.606 12.0 3 1.836 2.179 15.7 1.391 1.490 6.6 L' -
I
- The Technical Specification's limit for the heat flux hot channel
'I factor, F-Q(T), is a function of core height. The value for F-Q(T) listed above is the maximum value of F-Q(T) in the core.
The Technical Specification's limit listed above is evaluated at the plane of maximum F-Q(T). I The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(T) and the Technical Specification's limit for each map. The measuted F-Q(T) hot channel factors include 8.15% total t uncertainty. I l I : g' . I I I ""-"'""""""'"'"*""
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~ '
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t Maure 6.2 i NORTH ANNA UNIT 1 - CYCII 8 STARTUP PHYSICS TESTS ; ASSEMBl.YWISE POWER DISTRIBUTION [ 74% POWER I 6 P W M 6 J H C- 6 i i t L D C 8
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. - 1. 0 . l . t . - 3. 2 . 0.9 . 3.0 . 1.6 . -0.4 . 0.4 . -0.4 . -0.6 . -0.1 . -0.9 . -0.4 . 0.3 . 1.F . ;
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I
. 0.33 . 1.30 . 3.tF . 1.F3 . I.tt . 3.16 . 3.ft . 3.36 . l.74 . I.t3 . 1.t? . 4.30 . 4.33 .
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. 0.2 . 0.F . -0.5 . 0.6 . 0.6 . -0.0 . 8.1 . 3.1 . *0.9 . *0.4 . -0.9 . -0.5 . 0.F . j
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. 3.7 . 0. 6 .
- 0. 6 .
- 0. 7 . - 0. 7 . - 0. 7 . 1.3 . 1. 0 .
- l . 6 .
- l . 4 .
- l . 5 .
.............................................................................. }
. 0. 36 . 1.10 . 3.76 . 1.17 . 1.t? . 1.17 . 1.F6 . 1.10 . 0.36 . -
. 0.36 1.09 1.F6 . 3.1% . 1.26 . 1.16 . 1.73 . 3.07 . 0.35 . 13
. 0.5 . 0.6 . -0.7 . *l.7 . al.1 . *f.6 . -2.7 . 2.3 . al.6 .
. 4.34 0.63 . 1.04 . 0.61 . 3.04 . 0.63 . 0.34 8
E . 0.33 . 0.62 . 4.02 . 0.79 . 1.01 . 0.61 . 4.33 .
. -0.6 . -0.9 .
- t. 0 . !.4 .
- t. 6 . 2. 7 . 2.6 .
14 l I
. $f6NDARD , , 0.!F . 0.t9 . 9.t? . . AW(06Cl .
. IEVI6150N . . 0.76 . 6.t6 . 0.26 . .PCI DIt'fl M NCE. 15 *
. *0.933 . . 1.6 . t.1 . t.9 . .
- 3.8 .
I MAP NO: N1 4 02 DATE: 7/19/89 SupeMARY POWER: 74% ; , CONTROL ROD POSITIONS: r-0(T)
- 1.939 9PTR D BANIC AT 192 $f(PS F DH(M) = 1.415 NW 1.009 i NE 0.999 i
l- rtzt s 1.27s 4 sw 0.998 i st 0.994 BURNUP
- 47 MWD /MTU A.0. = 0.%7X I ~~~~
~ " ' .
l l'igura 6.3 l j l t l NORTil ANNA UNIT I CYCI.E 8 STARTUP PHYSICfi TESTS l ASSEMBLYWISE POWER DISTRIBUTION : 100% POWER i B p P W M & 8 J H & F [ D C $ & I
................ ...................... ................ i
. 84 01(150 . . 6.te . 0.St . 9.te . . PRE DICilD .
. Ml att*t D . . 0.78 . 4.58 . 4.te . . ML A$tmt p . 3 .
I .PCI Dif flNl utt .
. f.4 . f.4 . 1.8 .
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................ t l
. 034 . 0.65 . l.tb . 0.4% . 4.06 . 0.63 . 0.54 . i
. 0.S'. 0.67 . 1.0b . 0.6% . 3.0L . D.64 . D.34 . t
. l.6 . F.6 . *0.3 . +0.4 . D.4 . 1.F . 1.t .
................................................................ l
. f.56 . l . 6 6 . 4 . f t . 1.16 . 1. F F . l .16 . 1. F% . 3 . 04 . 0. 56 . n
. D.3F . 1.40.1.ft.3.16.1.F6.3.17.1.t6.l.99. 4.55. 3
. 1.6 . 3.5 . -t.3 . -0.6 . *0.9 6.9 . 0.S . 0.8 . t.1 .
- I
............................ ................................................. l
. 6.34 . 0.67 . 4.t* . 1.t3 . 4.57 . l.It . 1.37 . l.75 . l.t* . 0.87 . 0.56 . ,
. 9.16 . 0.67 . 3.t6 . 1.tn . l.57 . 1.88 . l.38 . 1.t4 l.74 . 0.68 . 0.56 . 4
. 0.0 . 9.t . 0.6 1.t . D.& . 0.5 . 0 5 . 0.4 . +0.4 . -0.9 . D.t . l
. 0.34 .
1.06 . 3.tt . l.it . 1.76 . 1.88 . l.it , t.14 . 1.78 . l.ft . 3.26 . 1.68 . 0.5= , t I l.24 . 8.f9 . 1.te . I.F4 . 1.70 . 4.F9 . l.ft . 3.te . 1.66 . 0.56 .
. 9.11 . 1.07 I.24 . & *
. *1.5 . *l.3 . *0.6 . *D.! . 0.6 . 1.7 . l.7 . 4.0 . 0.6 . 0.1 . 4.0 0.7 . f.6 . j
. 0.65 . 1. FE . 1.t* . 1. f 6 . 3.19 . 1. t9 . l . 74 . 1.F9 . 3.19 . 1.te . 1.f4 1.F5 . 0.65 . !
. 0.61 . 1.74 . 1.f3 . I.te . 1.fi . 1.11 . l.te . 1.12 . 3.fi . 1.76 . 1 77 . 1.F4 . 0.64 . 6
. 0.6 . 0.5 . *0.4 . *0.3 . 1.4 . F.6 . F.6 . f.9 . 1. 6 . - 0. 6 .
- l . 0 . - 0. 4 . 0.4 .
r
.......................................................................................................... i
. 6.ft . 1.e4 . 1.16 . 1.52 . 3.39 . 1.F9 . 1.01 . 3.76 I.el . 3.19 . 1.19 . 1.52 . 1.16 . 1,64 . 9.te . i I .
6 to . l.D4 . 1.16 . 3 12 . 1.19 . l.57 . l.94 0.4 . 0.5 . -0.5 . .i . 0.7 . i. .
. 1.T9.1.03.1.51.119.3.t9.3.16.1.03.0.F4.
3.0 . 3.i . i. . l.7 . .) . .i.9 . . .3 . .l.i . 0.7 . 7 i 0.50 . 0.44 . 1.27 . 1.17 . 1.F3 . 1.75 . 1.76 . 1.14 3. 25 . 1.th . 1. F5 . 4. 3 F . 3. tF . 0. 8% . 4.14 . I 9.50 . 0.64 .
- 1. 26 . 3.16 . 3. tb . 1. t8 . l .50 . 1.18 . 1.76 . 1. F6 . l . 72 . 3.14 . 3. th . 0. 85 . 0.51 . 4 0
. +1.5 . 0.6 . -0.6 . 0.0 . f.S . f.7 . 4.0 . 1.6 . 0.8 . 0.7 . - 0.7 -f.0 . l.t . 0.5 . l.6 . [
.9.t6.3.04.1.36.3.17.1.19.1.F4.1.01.1.F6.168.1.F9.3.19.3.12.1.56.1.04.0.76.
.0.77.167 314 . 3.12 . 1.F3 . 1.11 . l.08 . 1.F6 . 1.01 . 3.f4 . 3.14 . 3 30 . 1.86 . 8.06 . 9.F6 . 9
. *F.6 . 2.0 . *t.0 . 9.1 . 2.1 . 3.3 . - 0. 2 .
- 0.7 . 0.6 .
- 0.7 . -0.4 . *l.6 . -0.1 . 1.5 . f.6 .
I . 0.65 . 1.75 . 1.74 . 1.F4 . 1.19 . 1.F9 . 1.24 . 1.79 . 1.19 . 1.F8 . 1.f4 . 3.tb
. 0.6% . 4.ft . 3.t3 . 1.50 . I.ft . 1 50 . 3.F6 . 1.F9 . 1.18 . 4.t? . 4.t3 . 3.16 . 0.65 .
. -f 6 . -F.S . -0.7 . 1.0 . 0.6 . 9.2 . 4.5 . 0.5 . *l.t . -0.7 . 0.t . 1.4 .
0.65 .
$.4 .
10 7
- . 0.54 1.08 . l.7% . 1.22 . 3.te . 3.16 . I.tf . 1.lt . I.th . 8.rt . I.tb . I 68 . 9.14 . ;
. 0.54 . 1. 66 . l .16 . 1. FF . 1. 2 7 . 3 .18 . l . it . 1.19 . 1. 2 7 . 1. tl . 3 . tn . 4. 0 9 . 0. 54 Il !
. 9.t . 6.7 . 0.1 . 0.1 . - 0. 7 .
- 0. 4 . - 0. 5 . 0.8 . *0.5 . 0.6 . 0.8 . 0.7 . 2.0 . t
.l\
- 11 .. 0.36,. l.75 . 1.17 . 3.18 . 1.3 0.4 i 0.> . 4.42 1. F3 . 1.F4, 1.f4 .. 3.f 4 . 3. tf . i . 30 . i . i6 . 1. 2,2 ..i.F .. 0. ?.
7 . 0..a. 56 . I
- 0. i.f it ;
. 3.0 . l . 5 . 0.1 .
- 0.9 . - 1. 5 . a l . 6 . 2. 0 .
- l .3 . a l . 6 .
- 0.1 . 0.3 . ,
. D. h . 1.06 . 1.75 . 1.16 . I.t? . 3.16 . 1.F6 . 1.68 . 9.16 .
. 0.57 . l.Il . 1.75 . 1.15 . 3.f= . l.15 . l.it . 1.06 . 6.&6 . 13
. f.6 . f.5 . 4.4 . *t.6 . t.& . -f.9 . 2.6 . **.3 . 4.2 . f
................................................................ t
. 0. 54 . 0.61 . I 0L . 0.6% . 4.06 . 0.63 . 0.34 >
I ................
. 0.35-. 0.65 . 4.0; . 0.85 . 1.07 . 0.62 . 0.51 .
.26. 2.5 . 3.6 . F.4 . *t.4 . 2.6 . 3.F .
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. . l$
. *0.964 . . 2.6 . -2.0 . *f.0 . .
= 1.3 . f
................ ....... .............. ................ i SUPlMARY ,
MAP N05 N1 8 05 DAT[3 7/26/89 POWERI 100% CONTROL POD POSITIDetSI F-9(T) a 1.856 OPTR j D BANK AT 228 STEPS F DH(M) s 1.591 NW 1.00$ NE 1.005 FlZ) s 1.218 SW e.999 i SC 0.995 j buRNUP e 257 MWD /MTU A.0. s 1.546% ( t
P l, I- SECTION 7 l RETERENCES { I 1. A. Abbasi and A. H. Nicholson, " North Anna Unit 1 Cycle 8 l Design Report," Technical Report NE-710, Revision 0, Virginia ; Electric and Power Company, June, 1989,
- 2. T. K. Ross, W. C. Beck, " Control Rod Reactivity Worth Determination .
By The Rod Swap Technique " VEP TRD-36A, December, 1980. e l
- 3. W. Leggett and L. Eisenhart, "The INCORE Code," WCAP-7149, !
December, 1967. I- .4. North Anna Unit 1 Technical Specifications, Sections 1.18, 3.1.3.4. 3.2.2, 3.2.3, 3.1.1.4 and 4.1.1.1.2. , I ! I ! LI , I l
.I !
I . LE : I
.E l B. xt-734 81ce St-, Te t R t ease a - se
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APPENDIX )I l STARTUP PilYSICS TESTS PESULTS AND EVALUATION SilEETS [ t il I J l l I . i I : i i i I i P ,I ; il 'I l I
"t - "' ">c8 s - ~ T - -
- 41 - se
s. L l l ' [ NORTH ANNA POWER STATION UNIT 1 CYCLE 8 ' STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Reactivity Computer Checkout l Reference Proc No /Section: 1 PT 94.0 Sequence Step No: II Bank Positions (Steps) RCS Temperature ('F): 547 ! l- Test Power Level (% F.P.): 0 ;
'l Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):
W (Design) CB: 228 CC: 228 CD:
- Below Nuclear Heating ;
III Bank Positions (Steps) RCS Temperature ('F): Sys Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): ' (Actual) CB: 228 CC: 228 CD:mp'hy Below Nuclear Heating Date/ Time Test Performed: ! l vnt 2 ,listto ; Measured Parameter pc = Meas. Reactivty using p-computer : IV (Description) pg = Inferred React from react period pc = ' 39.0
- /40.0 l Heasured Value pg= - 39.~2 E40./ , l 8
Test %D = . /.P f . o. 2 'd l Results t 5 Design Value (Actual Conditions) %D n ((pc pg )/pt) x 100% 5 4.0% Design Value f (Design Conditions) 1D = ((pe pt)/p )g x 100% 5 4.0% Reference WCAP 7905, Rev.1 Table 3.6 V FSAR/ Tech Spec Not Applicable ,
.g Acceptance l 5 or2**
Reference Not Applicable l Design Tolerance is met : 1 YES N0 1 'I VI Acceptance Criteria is met : )C.,YES NO I Comments !
- At The Just Crit'ical Position I Allowable Range = 139 j
Prepared By: Reviewed By: #APO - d 5 NE-734 NIC8 Startup Test Report Page 42 of 58 LI . . _ - - _ -
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,h , ,w . .u,ty 4 FNAw NORTH ANNA POWER STATION UNIT 1 CYCLE 4
! STARTUP PilYSICS TEST RESULTS AND EVALUATION SHEET l lI I Test
Description:
Critical Boron Concentration ARO , Reference Proc No /Section: 1-PT-94.0 Sequence Step No: !
!! Bank Positions (Steps) RCS Temperature ('F): 547 f Test Power Level (% F.P.): 0 I Conditions (Design)
SDA: 228 SDB: 228 CA: 228 CB: 228 CC: 228 CD: 228 Other (specify): Below Nuclear Heating 1 III Bank Positions (Steps) RCS Tesaperature ('P): 984 0 ' Test Power Level (% F.P.): 0 i Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB: 228 CC: 228 CD: 228 Below Nuclear Heating I Date/ Time Test Performed. , 1ler/rt 25d ' Meas Parameter g IV (Description) (CB ) AR0; Critical Boron Conc - ARO I Test Measured Value M (Cg) ARO " I' d .M l I Results Design Value i
.I (Actual Cond) Cg= ?.iM i W g .w '
Design Value I (Design Cond) Reference Cg =2135 1 50 ppe Technical Report NE-710 Rev. O I iI V TSAR / Tech Spec D aCBxCB s 1000 pcm I l I Acceptance Criteria Reference Technical Specification 4.1.1.1.2 Design Tolerance.is met [
- DYES NO l Acceptance Criteria is met : _f YES NO ;
VI Comments aCB " *7 14 Pes /ppe for preliminary analysis i I CB D M
= l(CB) ARO - CB j; Cg is design value at actual conditions.
I 4Q3 4 . ), o g / \*y,s.% M 5 .W,. ;b h%i 5 PC CctM WU r oJ FeWos s ceseen are . Jea a.J2 ' e E Prepared By: W Reviewed By: V I NE-734 NIC8 Startup Test Report Page 43 of 58 ; I i
l NORTH ANNA POWER STATION UNIT 1 CYCLE 8 STARTUP PHYSICS TEST RESUI.TS AND EVALUATION SHEET f p i I Test
Description:
Isothermal Temperature Coefficient ARO l Weference Proc No /Section: 1-PT*94.0 Sequence Step Not [ 11 Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (7, F.P.): O r il Conditions SDA: 228 SDB: 228 CA: 228 Other (specify)1 1 5 (Design) CB: 228 CC: 228 CD: 228 Below Nuclear Heating ; III Bank Positions (Steps) RCS Temperature ('T): GF. l ' Test Power Level (7, F.P.): 0 ; Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB: 228 CC: 228 CD: g,7 < Below Nuclear Heating i Date/ Time Test Performod 1b @d 2nf i Mnas Parameter ISO IV (Description) (a T )ARO Isothermal Temp Coeff - ARO [ ISO ' Test Measured Value (a T )ARO = w , M pcs/ F (C3 a llWppm) ; Results i Design Value ISO - (Actual Cond) (a T )ARO = 90 pce/'T (CB "I W PP") l (8 )ARO = 0.84 1 3,0 pcm/'T y (Design Cond) (CB = 2135 ppe) ! Reference Technical Report NE 710 Rev. O FSAR/ Tech Spec a 5 3.77* pen /'r a = -1.73 pen /'F
+
ISO Acceptance l Criteria I Reference TS 3.1.1.4, Technical Report NE-710 Rev. 0 1 L I Design Tolerance is met : ' YES ,,_,NO VI Acceptance Criter,fa is set : / YES ,,_,_NO Comments
- Uncertainty on aTMOD = 0.5 pcm/*F (
Reference:
memorandum I from C. T. Snow to E. J. Lozito dr.ted June 27, 1980).
,g rixt v,co %o cot tbou-4 Prepared By: (NW ' W Reviewed By: d bW NE-734 NIC8 Startup Test Report Page 44 of 58 I
I I I NORTH ANNA POWER STATION UNIT 1 CYCLE 8 l STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Cntl Bank B Worth Meas.. Rod Swap Ref. Bank Reference Proc No /Section: 1-PT-94.0 Sequence Step No:
' I II Bank Positions (Steps) RCS Temperature ('F): 547
; Test Power Level (% T.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify):
(Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating
!!! Bane Positions (Steps) RCS Temperature ('T): 54.1 I Test -
Power Level (% F.P.): 0-Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB: Moving CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Performed: 1 l# t,.hri CCC'? REF Measured Parameter I Integral Worth of Cntl Bank B. B ; All Other Rods Out I (Description) IV REF ' Test Measured Value IB " 333%* Pc m Results I Design Value pgp 1313
- f 3 J pm ,,,
(Actual Conditions) IB
- b .,f,c,[e Design Value REF (Design Conditions) I B
- 1313 i 131 pcm Reference Technical Report NE-710 Rev. 0 l
If Design Tolerance is exceeded, SNSOC i shall evaluate impact of test result - Y FSAR/ Tech Spec on safety analysis. SNSOC may specify ; Acceptance that additional testing be performed, j
- g. Criteria .
5 "*'*r'ac* v'P r"o 36^ i Design Tolerance is not :
# YES NO VI Acceptance Criteria is met : 2YES__,NO l I Comments
- l l .
l Prepared By: -_ Reviewed By: b Nv l NE-734 NIC8 Startup Test Report Page 45 of 58 ' 1 5-1 'I . - . - -
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t LI l t i F w A L. NORTH ANNA POWER STATION UNIT 1 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET 1 Test
Description:
Critical Boron Concentration B Bank In i Reference Proc No /Section: 1 PT 94.0 Sequence Step Not l I II Bank Positions (Steps) RCS Temperature ('F): 547 ! Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): l I (Design) CB: 0 CC: 228 CD: 228 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature ('F): 'W S' 1 i I Test SDA: 228 SDB: 228 CA: 228 Power Level (t F.P.): 0 Other (Specify): Conditions l (Actual) CB: 0 CC: 228 CD: 228 Below Nuclear Heating Date/ Time Test Perfo,tmed: ,y [ 7tv.y g - l ; 71-os- n . Meas Parameter IV (Description) (C )gB B; Critical Boron Cone - B Bank In Measured Value (CBB=
)M l T6 O p fe r - '
Test Results Design Value (Actual Cond) CB" %N 29 P P a' I Design Value (Design Cond) CB = 1951 + ACB Prey 1 (10 + 131.3/laC3 l)ppe j Reference Technical Report NE 710 Rev. O D ; V FSAR/ Tech Spec aCBxCB s 1000 pcm I Acceptance Criteria Reference Technical Specification 4.1.1.1.2 l Design Tolerance is met : /YES ,___NO Acceptance Criteria is met i d ES ,_ NO 'I l l v1 Comments oC3 = -7.14 pcm/ ppm for preliminary analysis AC
= (CB)A 0,- 2135 l
C = l(CB ) - CBl; CB is design value at actual conditione-1 k',y* -i.O\ .m M 5~% .A *%% s5 Prepared By: % Reviewed By: 'I / L NE-734 N1C8 Startup Test Report Page 46 of 58 I. - - -
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, NORTH ANNA POWER STATION UNIT 1 CYCLE 8 L STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET ,
I Test
Description:
HZP Boron Vorth Coefficent Measurement
; Reference Proc No /Section: 1-PT 94.0 Sequence Step No i
[ II Bank Positions (Steps) RCS Temperature ('P): 547 I Test Power Level (% F.P.): 0
,g Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): !3 (Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating i
f a 11I Bank Positions (Steps) RCS Temperature ('P): 51(3 2. l {g Test Power Level (1 T.P.): 0 i Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CBtMoving CC: 228 CD: 228 Berlow Nuclear Heating ! lI Date/ Time Test Performed:
' )IC.\%4 OTc i i
Measured Parameter IV (Description) 30 3 Poron Vorth Coefficient : I Test Measured Value aCB" - 7. O l f c ~ /gf m < ! I Results ' Design Value (Actual Conditions) aCB = -7.14 1 0.71 pcm/ ppm Des agn Value (Design Conditions) aCB = -7.14 1 0. 71 pcm/ppe , Reference Technical Report NE 710 Rev. 0 . I 1 I V Acceptance FSAR/ Tech Spec Not Applicable t
+
Criteria Reference Not Applicable Design Tolerance is met : YES NO I VI Comments Acceptance Criteria is met : ._/__YE S NO . I - Prepared By: % Reviewed By: ' l NE-734 NIC8 Startup Test Report Page 47 of 58 !I - _-- _
I ; l 'E WORTH ANNA POWER STATION UNIT 1 CYCLE 8 l STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Cntl Bank D Worth Measurement-Rod Swap ! Reference Proc No /Section: 1-PT-94.0 Sequence Step Not I II Test Bank Positions (Steps) RCS Temperature ('F): 547 Power Level (% F.P.): 0 i i Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): ; I (Design) CB: Moving CC: 228 CD: Moving Below Nuclear Heating ! III Bank Positions (Steps) RCS Temperature ('F): M H.S ! I Test Power Level (% F.P.): 0 Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify): (Actual) CB: Moving CC: 228 CD: Moving Below Nuclear Heating i I Date/ Time Test Performed: , 7/lkltet o34 A ! Meas Parameter RS (Description) 19 ; Int Worth of Cnti Bank D-Rod Swap ! , IV- pg Test Measured Value In = 949.7( Adj. Position Meas. Crit.
= HTRef Bank steps) ,
Results I Design Value (Actual Cond)
*RS p
(Adj.
= % 3.) ;t h, Meas. ositionCrit.
a HRef Bank T, steps) L Design Value In = 942 1 141 pcm (Critical Ref Bank (Design Cond) Position = 151 steps) Reference Technical Report NE-710 Rev. 0, VEP-FRD-36A I V FSAR/ Tech Spec If Design Tolerance is exceeded, SNSOC shall evaluate impact of test result on safety analysis. SNSOC may specify that i Acceptance additional testing be performed. Criteria I Reference VEP-FRD-36A t I VI Comments Design Tolerance is met Acceptance Criteria is met
/
[ YES _NO YES __,NO , I . I e 4 >>= M " * " - *- * >>> 'A* NE-734 NIC8 Startup Test Report Page 48 of 58 I
I i i NORTH ANNA POWER STATION UNIT 1 CYCLE 8 , STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET > I Test
Description:
Cnt! Bank 0 Worth Heasurement Rod Swap I ! Reference Proc No /Section: 1 PT 94.0 Sequence Step Not II Bank Positions (Steps) RCS Temperature ('F): 547 j Test Power Level (% F.P.): 0 ; Conditions SDA: 228 SDB: 228 CA: 228 Other (specify): lg3 (Design) CB: Moving CC: Moving CD: 228 Below Nuclear Heating i t Bank Positions (Steps) RCS Temperature ('T): 545.1 I III Test Conditions SDA: 228 SD3: 228 CA: 228 Power Level (% F.P.): O Other (Specify): Below Nuclear Heating (Actual) CB Moving CC: Moving CD: 228 Date/ Time Test Performed: 7 htefe:Cl 0 5 0 '~7 l Mcas Parameter g3 (Description) IC ; Int Worth of Cntl Bank C Rod Swap I IV Test Results Measured Value RS IC = S (c l (p (Adj. Meas. Crit. Ref Bank Position = 555 5teps) I Design Value (Actual Cond) RS IC ( Adj. Meas. Crit. Ref Bank
- MM t o 1 Position = ISS steps)
Design Value I = 851 i 127 pcm (Critical Ref Bank (Desit,n Cond) Position = 138 steps) , Reference Technical Report NE-710 Rev. O, VEP FRD-36A I If Design Tolerance is exceeded SNSOC ! r shall evaluate impact of test result on , V FSAR/ Tech Spec safety analysis. SNSOC may specify that ; Acceptance additional testing be performed. I Criteria Reference VEP FRD 36A
/ YES I VI Comments Design Tolerance is met Acceptance Criteria is met
- 2 YES NO N0
- I I- "" ' >>> ""-
NE-734 NIC8 Startup Test Report
"- - * >>= NN Page 49 of $8 I . . .
ll I ~ l NORTH ANNA POWER STATION UNIT 1 CYCLE 8 ; p STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l g I Test
Description:
Cntl Bank A Worth Measurement Rod Swap Reference Proc No /Section: 1-PT 94.0 Sequence Step No !W II Bank Positions (Steps) RCS Temperature ('F): $47 [ Test Power Level (% F.P.): 0 I .g Conditions SDA: 228 SDBi 228 CA: Moving Other (specify): l lg (Design) CB: Moving CC: 228 CD: 228 Delow Nuclear Heating Bank Positions (Steps) RCS Temperature ('F): 545.5 I III Test Power Level (% F.P.): 0 1 Conditions SDA: 228 SDB: 228 CA: Moving Other (Specify): ; i , (Actual) CB: Moving CC: 228 CD: 228 Below Nucl' ear Heating Date/ Time Test Performed:
,Im m osso ,
Meas Parameter RS (Description) 13 ; Int Worth of Cntl Bank A - Rod Swap [ I IV g3 (Adj. Meas. Crit. Ref Bank [ Test Measured Value I4 = 293.9 Position = 7c> steps) ; Results -
- I Design Value (Actual Cond) IA RS (Adj. Meas. Crit. Ref Bank
- 2"7 4. 31 iCC Position = *to steps)
{ ( I RS Design Value IA = 273 1 100 pcm (Critical Ref Bank , (Design Cond) Position = 73 steps) Reference Technical Report NE-710 Rev. O, VEP-FRD-36A If Design Tolerance is exceeded, SNSOC I V FSAR/ Tech Spec shall evaluate impact of test result on safety analysis. SNSOC may specify that [ Acceg ance additional testing be performed.
,I Criteria Reference VEP FRD 36A !
I Design Tolerance is met : I YES __ NO VI Acceptance Criteria is met : J YES __,_NO Comments , t . Prepared By: bb %, Reviewed By: 4 M 4 i NE-734 NIC8 Startup Test Report l' Page 50 of 58 !
I I NORTH ANNA POWER STATION UNIT 1 CYCLE & L STARTUP PilYSICS TEST RESULTS AND EVALUATION SHEET I I Test
Description:
Shutdown Bank B Worth Meas. Rod Swap Reference Proc No /Section: 1-PT-94.0 Sequence Step Not J Bank Positions (Steps) II RCS Temperature ('T): 547 Test = Power Level (% T.P.): 0 I Conditions (Design) SDA: 228 SDB: Moving CA: 228 CB Moving CC: 228 CD: 228 Other (specify): Below Nuclear Heating III Bank Positions (Steps) RCS Temperature ('T): 54 5.~1 I Test Conditions (Actual) SDA: 228 SDB Moving CA: 228 CB Moving CC: 228 CD: 228 Power Level (% F.P.): 0 Other (Specify): Below Nuclear lleating Date/ Time Test Performed l 7/ev /'iA O(o 4 (o Meas Parameter pg (Description) ISB; Int Worth of Shutdown Bank B Rod Swap 'l . IV gg (Adj. Meas. Crit. Ref Bank jW Test Measured Value Igg = 4 0 2.5. 7 Position,= ik,0 steps) Results l Design Value RS (Adj. Meas. Crit. Ref Bank
; (Actual Cond) 1 33 = iC'$5. t I a5g Position = l40 steps)
RS Design Value I SB = 1034 1 155 pcm (Critical Ref Bank l (Design Cond) Position = 165 steps) Reference Technical Report NE-710 Rev. O. VEP-FRD-36A If Design Tolerance is exceeded, SNSOC I V Acceptance FSAR/ Tech Spec shall evaluate impact of test result on safety analysis. SNSOC may specify that additional testing be performed. I Criteria Reference VEP-TRD 36A lg Design Tolerance is met : ig VI Acceptance Criteria is set : [] YES YES _ NO N0 l Comments , I lI Pre,a,ed B,, u 2 % Revie.ee B,, Od)07v NE-734 NIC8 Startup Test Report Page 51 of 58 I - . m
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P i NORTH ANNA POWER STATION UNIT 1 CYCLE 8 2
. STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I V :
l I Test
Description:
Shutdown Bank A Worth Meas. - Rod Swap l Reference Proc No /Section: 3-PT-94.0- Sequence Step No: II Bank Positions (Steps) RCS Temperature ('F): 547 C Test Power Level (% F.P.): 0 :
,'g Conditions SDA: Moving SDB: 228 CA: 228 Other (specify): < "g, (Design) CB: Moving CC: 228 CD: 228 Below Nuclear Heating d
g' III- ' Bank Positions (Steps) RCS Temperature ('F): 545. ] Test - Power Level (% F.P.): 0 ' kg Conditions -SDA:Movsag SDB: 228 CA: 228 Other (Specify): (Actual) . CB:Muving CC: 228. CD: 228 Below Nuclear Heating W Date/ Time Test Performed:
. ?lWliPL O'733 Meas Parameter RS ISA; Int Worth of Shutdown Bank A-Rod Swap (Description) .( up IV Test Measured Value RS I SA = C 1
2 .3 (Adj. Meas. Crit. Ref Bank Position = H Y step ) ' g Results Design Value RS (Adj. Meas. Crit. Ref Bank ,, (Actual Cond) ISA = 9ll $ I C Position = H5' steps) RS Design Value 134 = 915 1 137 pcm (Critical Ref Bank
-I (Design Cond) Position = 147 steps)
Reference Technical Report NE-710 Rev. O, VEP-FRD-36A If Design Tolerance is exceeded, S!! SOC r
;I V FSAR/ Tech Spec shall evaluate impact of test res:1+ un safety analysis. SNSOC may specify that Acceptance additional testing be performed.
I' Criteria Reference VEP-FRD-36A '~~ Design Tolerance is met : / YES _ NO VI Acceptance Criteria is met : 2YES NO Comments II Prepared By: b b UMu Reviewed By: . W NE-734 NIC8 Startup Test Report Page 52 of 58 I . - . - -
Il , NORTH ANNA POWER STATION UkiT 1 CYCLE 8 l STARTilP PHYSICS TEST RESULTS ANb EVALUATION SHEET ! iI~ 'I Test
Description:
Total Rod Worth - Rod Swap [ Reference Proc No /Section: 1-PT-94.0 Sequence Step No-
'II Bank Positions (Steps) RCS Temperature ('F): 547 Test Power Level (% F.P.): 0 1
.g Conditions SDA: Moving SDB: Moving CA: Moving Other (specify):
- g. (Design) 'CB: Moving CC: Moving CD: Moving Below Nuclear Heating !
III Bank Positions (Steps) RCS Temperature ('F): 54(c[d
- Test Power Level (% F.P.): 0 ;
'~
Conditions SDA: Moving SDB: Moving CA: Moving Other (Specify): ! (Actual) CB: Moving CC: Moving CD: Moving Below Nuclear Heating Date/ Time Test Performed:
, /wltet ocen j Meas Parameter i (Description) ITotal; Int Worth of All Banks - Rod Swap l IV W Test Measured Value ITotal
- 6 3"I 1'b F # -
Results-
-Design Value ,
I. (Actual Cond) ITotal
- 6 % 7(#*I 1 6 33 PC"
. Design Value ITotal = 5328 i 533 pcm .
(Design Cond) I Reference Technical Report NE-710 Rev. O, VEP-FRD-36A I If Design Tolerance is exceeded, SNSOC f shall evaluate impact of test result on > V FSAR/ Tech Spec safety analysis. SNSOC may sp mify that Acceptance addit. tonal testing be performed. ' Criteria j Reference VEP-FRD-36A L Design Tolerance is met : / NO l : VI Acceptance Criteria is met : 7,__.YE
. YES S NO Comments
- Prepared By: bu NNW Reviewed By:
1B-l NE-734 N1C8 Startup Test Report Page 53 of 58 I t
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NORTH AhNA POWER STATION UNIT 1 CYCLE 8 , STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET l
'I I. Test
Description:
M/D Flux Map.- At power ! Reference ' Proc No /Section: 1 PT-21.1 Sequence Step Not l
' I- II Bank' Positions (Steps) RCS Temperature ('F):T REF 11 l
Test Power Level (% F.P.): <3D1 1
' g- Conditions SDA: 2?8 SDBt 4 8 CA: 228 Other (specify)
.3 (Design) CB : 228 CC : 228 CD:
- Must have it 38 thimbles Bank Positions (Steps)
I RCS Temperature ('F): Tgee III i Test - Power Level (% F.P.): 2v.s Conditions J SDA: 228 SDB: 228 CA: 228 Other (Specify). (Actual) CB : 228 CC : 228 CD:
'g. l WL. 'Date/ Time Test: ' I'H 59 Performed: 1944.
MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT- : (Description)
% DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR 8tPhhc.4 ;
J Measured Value p.j9 g, go t 2. H 3 l,009 Results 0 * #* ' I........... e iiiiii~Va'Iue D~ ; g t (Design Conds) ;* g ;;; ;;**p;
*
- a' . .* NA NA 5 1.02 WCAP-7905 WCAP-7905 Reference REV.1 NONE NONE REY.1 r",,n .n o . . n ... .
g' V FSAR/ Tech Spec NONE NA 13 Acceptance - Criteria ,g Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 i ,g ( Design Tolerarce is est Acceptance Criteria is set
- d YES _ N0
- L YES I
_NO VI Consents
- As Required n nn Prepared By* x Reviewed By:
tjM N% i lo NE-734 NIC8 Startup Test Report Page 54 of 58 LI- .--
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- NORTH ANNA POWER STATION UNIT 1 CYCLE 8 D
STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET - LI l y I Test
Description:
M/D Flux Map-At Power [i Reference Proc No / Section: 1-PT-21.1 Sequence Step No: $ L (. II Bank Positions (Steps) RCS Temperature ('F):T 11 i
- Test . Power Level (*. F.P.): Rh$% <
Conditions !E SDA: 228 SDB: 228 CA: 228 Other (specify) g; (Design)
~
CB : 228 CC : 228' CD:
- Must have 2 38 thimbles
! l l l III Bank Positions (Steps) RCS Temperature ('F): T y Test Power Level (*. F.P. ): w y9,9 ' ! , Conditions SDA: 228 SDB: 228 CA: 228 Other (Specify):
- vsmH (Actual) CB : 228 CC : 228 CD: d 4,
~
h 44 mineh E S L q , Date/ Time Test: 'i/ A l's 9 j.' . Performed: o ra,q MAX. REL NUC ENTHAL TOTAL HEAT QUADRANT IV Meas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT I , (Description) *. DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T) QPTR l APb 2 o.4 g W Measured Value gih gqg , ,q g ),o09 Test 299 " ! Results !! Design Value l l3 ll:l ! !:; J L (Design Conds) *""'l'"' NA NA s 1.02 l, c . a' ' WCAP-7905 WCAP-7905
"*'*rence REV.1
' 5: NONE NONE REV.1 'E5 V Acceptance FSAR/ Tech Spec NONE NA 'l ' Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 Design Tolerance is met : [YES NO l Acceptance Criteria is met : .f.,YES NO-
;I.- VI Comments
- As Required ezdb /
, Prepared By: Reviewed By: s v
NE-734 NIC8 Startup Test Report Page 55 of 58
~ _._ - _ __ - _ _ _ _ _ _ _ _ _ . -
I, ! NORTH ANNA POWER STATION UNIT 1 CYCLE 8 STAKTUP PHYSICS TEST RESULTS AND EVALUATION SHET,7 I Test Descript'.on: M/D Fluz Hap - NFP. ARD, Eq. Xe ; Reference l Proc No / Section: 1-PT-21.1 Sequence Step Not l II Bank Positions (Steps) RCS Temperature ('F):T 21
. Test , Power Level (% F.P.): b !
Conditions: SDA: 228 SDB: 228 CA: 228 Other (specify): Eq. Xe. -
.. (Design) l CB : 228 CC : 228 CD:
- Must have k 38 thimblera l l III Bank Positions (Steps) RCS Temperature ('F): "T~gsp Test Power Level (% F.P.): / cog
, Conditions, SDA: 228 SDB: 228 CA: 228 Other (Specify): i (Actual) CB : 228 CC : 228 CD: 2.26 g g %/g M f Date/ Time Test: ~7/26,/b'7 Perforesa: iggo l MAX. REL NUC ENTRAL TOTAL HEAT QUADRANT * > IV Moss Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT , i (Description) ?. DIFF CHAN FACT CHAN~ FACT RATIO l (M-P)/P F-dH(N) j F-Q(T) [ QPTE'
' i/.c 2. w t Measured Value Pt o.9 {g g Test 3 *" "'
l Results 8# ! Design Value l l: I *} ! !:I ' (Design Conds) " ' * " " ' " ' NA NA 5 1.02 i WCAP-7905 WCAP-7905 Reference REY.1 NONE NONE REY.1 , L '". ii . .u . . .. . . . ,p ,, , , , , ,,, , u ,, l. V FSAR/ Tech Spec NONE NA / Acceptance Criteria Reference NONE TS 3.2.3 TS 3.2.2 TS 3.2.4 L . Design Tolerance is set : l YES _.,_NO l Acceptance Criteria is set : gfYES ,NO [ , VI l Comments
- As Required
- I t
. Prepared By: bM be ,
Reviewed By: #d& ( NE-734 NIC8 Startup Test Report Page 56 of 58 1
r' j 9/ ,l I i I .. , NORTH ANNA POWER STATION UNIT 1 CYCLE 8 ,'IL '
-STARTUP PHYSIC 3 TEST RESULTS AND EVALUATION SHEET I lTestDescr16 tion: M/D Flux Map- NI Calibration Reference l Proc No / Section: 1-PT-22.2 Sequence Step No:
II Bank Positions (Staps) RC8 Teeperature ('T):7 21 ! Test
- I
- Conditions l SDA: 228 SDB: 228 CA: 228 Power Level (% F.P.):
Other (specify):
- 1
( ,, (Design) l CI : 228 CC : 228 CD: ** ! III Bank Positions (Steps) RC8 Teeperature('F): Trap : Test Power Level (7. F.P.): t00% ' Conditions- SDA: 228 SDB: 228 CA: 228 Other (Specify): !o (Actual) CB : 228 CC : 228 CD: 206 2.1 'Thim eln uscel - M ne cw<* mY
- l. Date/ Ties Test: 7 / 2 7/fn r
Perforeen: o t.,co MAX. REL NUC ENTRAL TOTAL HEAT QUADRANT l IV Mea's Parameter ASST PWR RISE HOT FLUX HOT POWER TILT (Description) *. DIFF CHAN FACT CHAN FACT RATIO 1 (ri-P) / t- F-dH(N) F-Q(T) QPTR 3.5 7. s. ,-
)
Measured Value- Ph c.%for a4
-2 3*1. for NA NA NA .,
Resu ts ^ #* Design Value ' lE lI f ! !:; (Design Conds) "**"****' NA NA s 1.02 .,
.: WCAP-7905 WCAP-7905 Reference ,
REY.1 NONE NONE REY.1 ; r".u............ ,'" " " " "' V FSAR/ Tech Spec NONE NA- ! Acceptsace lI Criteria Reference NONE TS 3.2.3 TS 3.2.2 T8 3.2.4 Design Tolerance is met : TES NO
/ Acceptance Criteria is met : YES _ NO >
VI Comments
- Must have at least 38 thimbles for a full-core fluz map, or
' I
at least 16 thimbles for a. quarter-core flux asp.
** As Required Prepared By: bdf c' Revieted By: #28 a NE-734 NIC8 Startup Test Report Page 57 of 58
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7 I , NORTH ANNA POWER STATION UNIT 1 CYCLE 8 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET j I Test Descr16 tion: M/D Flux Map- NI Calibration j Reference Proc No / Section: 1-PT-22.2 Sequence Step Not II Bank Positions (Steps) RCS Temperature ('F):7 21 4 Test Power Level (*. F.P.): b , i Conditionsu SDA: 228 SDB: 228 CA: 228 Other (specify): * ; (Design) CB : 228 CC : 228 CD: ** 1 III Bank Positions (Steps) ECS Temperature ('F): "l~ast-l Test Power Level (% F.P.): loog :
- Conditions .SDA: 228 SDB: 228 CA: 225 Other (3pecify):
(Actual) CB : 228 CC : 228 CD: 228 ~2 i Mim bits used Date/ Ties Test: 7 /2 7 /69 N Performent j / / 5' NAX. REL NUC ENTRAL TOTAL HEAT QUADRANT IV Maas Parameter ASSY PWR RISE HOT FLUX HOT POWER TILT p (Description) % DIFF CHAN FACT CHAN FACT RATIO (M-P)/P F-dH(N) F-Q(T): QPTF gD" % 4e Measured Value O NA NA Test - 2. 6 % 4e MA Results " # Design Value ! !3 llll , (Design Conds) **"t"!!:" NA NA 5 1.02 WCAP-7905 WCAP-7905 Reference REY.1 NONE NONE REY.1 l? V FSAR/ Tech Spec: NONE
'b"""" NA l Acceptance . -E critar**
g Reference N(NIE TS 3.2.3 TS 3.2.2 TS '3.2.4 Design Tolerance is set Acceptance Criteria is set : 4YE3 JO
- M JO VI l Comments
- Must have at least 38 thimbles for a full-core fluz sap, or l
at least 16 thimbles for a. quarter-core fluz esp.
** As Required
- l Prepared By: N'M Reviewed By: #IO -?
NE-734 NIC8 Startup Test Report Page 58 of 58 I-
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