B12440, Startup Test Rept Cycle 8

From kanterella
Jump to navigation Jump to search

Startup Test Rept Cycle 8
ML20207S991
Person / Time
Site: Millstone Dominion icon.png
Issue date: 03/31/1987
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20207S982 List:
References
B12440, TAC-63133, TAC-63198, NUDOCS 8703230032
Download: ML20207S991 (16)


Text

..

-. .. o.

Docket No. 50-336 B12440 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 STARTUP TEST REPORT CYCLE 8 t

l March 1987 8703230032 870316

i. PDR ADOCK 05000336 l

P PDR ,

i 4

- . - - - --2,-, .-.u.--, , . - , , ,,..,...._#mmern..,_r. , e.,- ,. ...,v.-,,,, . . . . , . . , . . - - ...-,,-,m,.~.,. , - . - - - .y..,,.--..-----,.,---

r a

INDEX

1.

SUMMARY

c?

2. INTRODUCTION
3. LOW POWER PHYSICS TESTING RESULTS 3.1 Critical Baron Concentrations 3.2 Control Element Assembly Symmetry Checks 3.3 Moderator Temperature Coefficients 3.4 Control Element Assembly Reactivity Worths 3.5 Hot Rod Drops
4. POWER ASCENSION TESTING RESULTS 4.1 Power Peaking, Linear Heat Rate and Tilt Measurements 4.2 Boron Measurements 4.3 Moderator Temperature Coefficient at 96% Power 4.4 Doppler Only Power Coefficient 4.5 RCS Flow at 100% Power 4.6 Power Distributions 4.7 Reactor Coolant System Radiochemistry
5. REFERENCES I

1 l

1 I;

)

1.

SUMMARY

Low Power Physics Testing and Power Ascension Testing for Millstone 2 Cycle 8 identified no unusual situations or anomalies. All parameters measured were within their acceptance criteria and Technical Specification limits. One item is noteworthy of mention:

Reactor Coolant System radiochemistry analyses show an increase _in the Iodine -131 activity levels, which is indicative of a small number of failed fuel pins. However, due to plant operating conditions, an equilibrium Iodine -131 value has not yet been established at the time of this writing.

2. INTRODUCTION The Millstone 2, Cycle 8 fuel loading was completed on October 20, 1986.

The attached core map (Figure 1) shows the final core configuration.

Subsequent operation / testing milestones were completed as follows:

Initial Criticality December 14, 1986 Low Power Physics Testing Completed December 17, 1986 Main Turbine On-Line December 18, 1986 50% Power Testing Completed December 26, 1986 96% Power Testing Completed January 1, 1987 100% Power Testing Completed January 12, 1987 Cycle 8 operation is with 217 Westinghouse manufactured fuel assemblies.

The Safety Analysis is supplied by Westinghouse.

.- .i

3. LOW ~ POWER PHYSICS TESTING RESULTS Low Power Physics Testing was performed at a power level of < 5 X 10 2%

power to avoid heat addition from the nuclear fuel.

3.1 Critical Boron Concentrations Critical Boron Measurements were taken at two different Control Element Assembly (CEA) configurations, at All Rods Out (AR0) and with CEA Groups.7 through 2 inserted. See Figure 2, CEA and Excore Detector locations.

The Critical Boron Concentration (CBC) measured with CEA Group 7 at 146 steps was 1217 ppm. Adjusted to All Rods Out, the CBC is 1227 ppm. Therefore, Measured CBC at BOL-HZP-ARO = 1227 ppm Boron Predicted CBC at BOL-HZP-ARO = 1207 ppm A= 20 ppm The Acceptance Criteria is i 85 ppm.

Acceptance Criteria met? Yes The Critical Boron Concentration (CBC) measured with CEA Groups 7 through 3 inserted and Group 2 at 17 steps was 817 ppm.

Adjusted to CEA Groups 7-2 inserted, the CBC is 813 ppm.

Therefore, Measured CBC @ BOL-HZP 2-7 CEA = 813 ppm Boron Predicted CBC @ BOL-HZP 2-7 CEA = 795 ppm a= 18 ppm The Acceptance Criteria is 1 85 ppm Acceptance Criteria met? Yes

os 3.2 Control Element Assembly-(CEA) Symmetry Checks Millstone 2 performs rod swaps among all CEA's in a group of' CEA's to verify that no serious . tilts are present from either a core mistoading, CEA problem, or other reactivity anomalies.

Results of the CEA symmetry checks are expressed as the largest deviation (in cents of reactivity) of any CEA from the average CEA for that CEA group.

Two sets of values are given, raw values and corrected values.

The corrected values take into account the slight design tilt,

since the core is not exactly 1/8 core symmetric. The raw values assume the core is 1/8 core symmetric.

The results were:

Maximum Value of Maximum Value of Raw Deviation (4) Corrected Deviation ($)

Group 1 CEA's 1.60 1.04 Group 3 CEA's 1.38 0.93 Group A CEA's 1.34 1.08 Group B CEA's 0.81 0.76 The Acceptance Criteria is i 2.5&.

Acceptance Criteria met? Yes NOTE - peff = 0.5883% AK/K 3.3 Moderator Temperature Coefficients The Moderator Temperature Coefficients (MTC) were measured at two different CEA configurations, at All Rods Out and with CEA Groups 7 through 2 inserted.

T 4

g

-; a e

All Rods Out MTC Measurement The measured MTC value with CEA Group 7 at 132 steps, an average RCS temperature of 528.3*F, and an RCS boron concentration of 1222 ppm was +0.356 X 10~4 AK/K/*F.

Comparing the adjusted MTC value to the predicted value yields:

Adjusted, measured MTC @

532*F, 1207 ppm, BOL, ARO = +0.380 X 10 ~4 AK/K/*F Predicted MTC @ 532*F, 1207 ppm, BOL, ARO = +0.350 X 104 AK/K/*F

~4 A= 0.030 X 10 AK/K/ F The Acceptance Criteria is 1 0.3 X 10 -4 AK/K/ F.

Acceptance Criteria met? Yes CEA Groups 7-2 Inserted MTC Measurement The measured MTC value with CEA Groups 7 through 3 inserted and CEA Group 2 at 13 steps, at an average RCS temperature of 530.4 F, and an RCS boron concentration of 817 ppm was

-0.594 X 10 ~4 AK/K/ F.

Adjusting this measured value to the prediction conditions of 532 F and 795 ppm yields an MTC value of -0.573 X 10 ~4 AK/K/ F.

Comparing the adjusted MTC value to the predicted value yields:

Adjusted, measured MTC at

-4 532 F, 795 ppm, BOL, CEA 7-2 Inserted = -0.573 X 10 AK/K/ F Predicted MTC at 532*F, 922 ppm, BOL, CEA 7-2 Inserted = -0.620 X 10 -4 AK/K/*F A= 0.047 X 10'4 AK/K/ F The Acceptance Criteria is 1 0.3 X 10 ~4 AK/K/*F.

Acceptance Criteria met? Yes

r-.

t 3.4 Control Element Assembly Reactivity Worths Reactivity worth measurements were performed twice on CEA Groups 7 through 2. The first measurement involved measuring the reactivity worth of each CEA group individually. The second measurement involved measuring the reactivity worth of CEA Groups 2 and 3 individually, and CEA Groups 4 through 7 in their normal overlap mode of operation.

The results of the measurements were:

Individual CEA Group Measurements (by dilution)

CEA Measured Predicted Delta  % Difference Group Worths (%AK/K) Worths (%AK/K) (M-P) [(M-P)/P]

7 0.837 0.832 0.005 0.6%

6 0.440 0.427 0.013 3.0%

5 0.239 0.232 0.007 3.0%

4 1.068 1.101 -0.033 -3.0%

3 0.531 0.560 -0.009 -1.6%

2 1.241 1.173 0.068 5.8%

Total 4.376 4.325 0.051 1.2%

CEA Overlap Measurements (by boration)

CEA Measured Predicted Delta  % Difference Group Worths (%AK/K) Worths (%AK/K) (M-P) [(M-P)/P]

2 1.236 1.173 0.063 5.4%

3 0.541 0.560 -0.019 -3.4%

4-7 2.542 2.592 0.050 -1.9%

Total 4.319 4.325 0.006 -0.1%

The Acceptance Criteria for the Total Worth of CEA Groups 7 through 2 inserted is i 10%.

Acceptance Criteria met? Yes )

l

, .s The Acceptance Criteria for any individual CEA Group is either 11 0.1% AK/K or i 15% difference.

Acceptance Criteria met on all CEA Groups? Yes 3.5 Hot Rod Drops Hot Rod Drops were performed on all 61 CEA drive mechanisms.

The drop times from 0 to 100% insertion ranged from 2.20 to 2.48 seconds.

The Acceptance Criteria, per Millstone 2 Technical Specifications, is that all CEA's must drop from 0 to 90% insertion in less than 2.75 seconds.

Acceptance Criteria met? Yes

4. POWER ASCENSION TESTING RESULTS 4.1 Power Peaking, Linear Heat Rate and Tilt Measurements The measurements of these parameters were:

T T Power Level Fxy Fr Max. Linear Heat Rate Incore Tilt 50% 1.478 1.400 6.47 KW/ft 0.010 96% 1.437 1.376 11.919 KW/ft 0.005 100% 1.417 1.372 12.110 KW/ft 0.004 The corresponding Technical Specification limits are:

T T Power Level Fxy Fr Max. Linear Heat Rate Incore Tilt 50% 1.836 1.675 15.6 KW/ft 0.02 96% 1.719 1.542 15.6 KW/ft 0.02 100% 1.719 1.537 15.6 KW/ft 0.02 Technical Specification limits met? Yes

. 3.

o- .

4.2 Boron Measurements At 50% power, 90 MWD /MTU, ARO and Equilibrium Xenon, the measu' red boron concentration was 959 ppm.

Measured boron concentration 50% power, 90 MWD /MTU, AR0, Eq. Xenon = 959 ppm Predicted boron' concentration 50% power, 50 MWD /MTU, ARD, EQ. Xenon = 946 ppm A= 13 ppm The Acceptance Criteria is i 85 ppm Boron.

Acceptance Criteria met? Yes At 100% power, 445 MWD /MTV, CEA Group 7 at 173 steps and Equilibrium Xenon, the measured boron concentration was 835 ppm.

Adjusted, Measured boron concentration 100% power 445 MWD /MTU, AR0, Eq. Xenon = 837 ppm Predicted boron concentration 100% power 445 MWD /MTU, AR0, Eq. Xenon = 803 ppm A= 34 pr'.n The Acceptance Criteria is t 85 ppm Boron.

Acceptance Criteria met? Yes

o .

4.3 Moderator Temperature Coefficient at 96% Power The measured MTC value at 96% power, with CEA Group 7 at 150 steps, at an average RCS temperature of 566.75*F, and an RCS boron concentration of 841 ppm was -0.558 X 10 ~4 AK/K/*F.

Adjusting this measured value to the prediction conditions of 96%, 567.2*F and 848 ppm yields an MTC value of -0.554 X 10 -4 AK/K/*F.

Comparing the adjusted MTC value to the predicted value yields:

Adjusted, measured MTC at 96%,

~4 848 ppm boron, and T,y, = 567.2*F = -0.554 X 10 AK/K/*F Predicted MTC 9 96%,

-5 848 ppm boron, and T,y, = 567.2*F = -0.445 X 10 AK/K/*F

~4 A= 0.109 X 10 AK/K/*F The Acceptance Criteria is 1 0.3 x 10 ~4 AK/K/*F.

Acceptance Criteria met? Yes 4.4 Doppler Only Power Coefficient The measured Doppler only power coefficient (00PC) at 94.25%

power, an average RCS temperature of 570.5*F, and an RCS boron

~4 concentration of 841 ppm was -1.100 X 10 AK/K/% power.

Adjusting this measured value to the prediction conditions yields a Doppler only power coefficient value of -1.096 X

~4 10 AK/K/% power.

Comparing the adjusted value to the predicted value yields:

Adjusted, measured 00PC at

~4 93% power, 841 ppm and 572 F = -1.096 X 10 AK/K/% Power Predicted 00PC at 93% power

~4 841 ppm and 572 f = -0.917 X 10 AK/K/% Power

~4 a= 0.179 X 10 AK/K/% Power

.. s.

The Acceptance Criteria is 1 0.3 x 10~4 AK/K/% Power.

Acceptance criteria met? Yes 4.5 RCS Flow at 100% Power The measured RCS flow at 100% power was 370,200 GPM.

The Acceptance Criteria is >340,000 GPM.

Acceptance Criteria met? Yes 4.6 Power Distributions Power Distribution Maps are shown for 50% and 100% power conditions in Figures 3 and 4. The agreement between the measurements and the predictions is good.

The Acceptance Criteria is that all locations are within i 10% of the predicted values.

Acceptance Criteria met? Yes 4.7 Reactor Coolant System Radiochemistry Reactor Coolant System (RCS) radiochemistry analyses during power ascension testing and subsequent power operation showed low activity levels in the RCS with Iodine-131 values of about 4 X 10 3 pCi/ml. After approximately 12 days of 100% power

. steady-state operation, the RCS Iodine-131 and total activity levels were seen to be slowly increasing. This increase in RCS activity levels is indicative of a small number of failed fuel pins. No known failed fuel pins were put into the Cycle 8 core. Due to plant operating conditions, an equilibrium Iodine-131 value has not yet been established as of this writing.

I

5. REFERENCES 5.1 In-Service Test T86-15, Initial Criticality / Low Power Physics lest - Cycle 8.

l' 5.2 In-Service Test T86-16, Power Ascension Test - Cycle 8.

5.3 Westinghouse Nuclear Design Report - Cycle 8, WCAP-11267.

RB:jlm l

l

Figure 1 -

i a s a r e,anuuuu a n is i, a si l I I I I I i ll1lllll l l l l l 1 i

,_ wng acgg kst wa3 a

,_ K991w26 wir 719 'b6k794kS3 wr6463 St 80 0

,_ utf H1f 7f6 Gro H69 7 99 Mit M66 Ivf Htt r6 M 'ti 18 39 ff

  • ~ uMS 219 ki9 etl 713 Iso Her sto 791 MN tro'87g1 kat 13 it so t's in if'

,_ kH6 Hl1 ko6 G63 73o Tao Mai ylg Hg6 Tal It'1 G61 gt3 MS3 wri b 9 31 38 9 63

,_ wwf 753 Ht6 725 76o H37 koM no9 ria Neo 199 Tat H16 767 wat 10 l'1 50 51 e K24 Ntl 7 10 71% Gff 73r Hfi M94 9m6e9731 G68 721 77f M91 w31

," [ xic f tf i'l gg aif go 3 64 W

"~ 749 M61 7 41 M68 wog. H61 76% H31764 M9: N'io H6S 759 NSF T61 d S 81 11 SS ft 65* 4P18

[~

rst 833 743 16 Mob Tab Hii T

Mf3 H65 % Ii H31 Hft H08 740 Hol 2ftG61 st too aN 9

  • 91 R6o

,_ 73r Mtf 7 69 M9f xif Mf6 Xf1 H10 77t H61 kai Htt 7fs H90 762 i ,_ wii i to At 31 f1 6*f x41 W64 M16 7 16 Tai H3e 236 Mf1H34 NS6 733 Mil 3317W6 Mfl g33 l *~

$4 it 16 31 it #2 6:

,_ Wit rgi Hti 723 Til H38 Ki6 Mif r in H64 781 721 N14 76f uso e 7 16 ali 91

'~ Kf1 M13 Ko19m3 734 7 31 M49 739 HSnt Tar 73W.4st wot M11 xas i

$ 9 fl 42 9 &c ugi sin mot att;74:

,_ x61,Hei,xtr Tat Mit> uor 766 wzi i2 if I 17I I I6_ MI _

T*f C- E ii af 91 gi rl l , _ rei rti wri sti

- sk Mo 13s 7Fi N39 x31 krfl

, _ n* iwnrenri l

l i

CTCLE 8 CORE MAP ll{

y SOURCf LOCAt!0N5 Source Core Location f.utde tube 53 F.3 lb 54 5 19 5t

$5 s 11 h.

14 A 10 h1 i

i

.-.~,~---y, ,, _ , - . _ .._,,_,,,,rm.~__.,_..,,_e_. .e-. , _ _ _ , . . ..,.-,,._,,,_,mo,.,-____,_,_.. . - . , - . - ~ .

. 8 Figure 2 o'

P2, uti m2, na, NORTH 2,

f20 .30 m20 m20 L20 J20 .20 F20 (20 3-69 3-58 vi9 19 .it ni9 .it LiS Ji9 .it ,it ti9 oit A-49 4-57 7-38 4-50 A-42 w,. v,. ,,. ... ... ... L,. J,. ... ,,. E,. ... ...

7-68 A-49 1-33 1-26 A-42 7-59 4,7 w,7 V,7 f,7 .,7 4,7 Ml? L,7 Jt7 .,7 F,7 t,7 .,7 C,7 .,7 L-48 2-25 i 2-18 A-43

... w,. vi. ,,. ... ... ... L,. u. ... , , .

p,. ... ... ...

l A-48 6-17 6-14 A-43

... ... ... ... ... ... ... ... J,. ... ... ... ... ... ...

vu 6-56 2-24 B-9 5-2 B-6

2-19 4-51 I,3 w,3 v,3 f,3 .3 R,3 N,3 L,3 J,3 .,3 F,3 t,3 0,3 C,3 .,3 via 3-67 1-32 B-9 B-6 1-27 3-60W 1,, w,, vi, T,, .,, R,, N,, Ll, J,, .,, F1, E,, 0,9 C, 0,,

C 7-41 5 'a 7-1 5-3

7-39 59 w9 v0 f9 .9 R9 N9 -

L9 JS .9 F9 ES 09 CD 09 r 3-66 1-31 B-8 B-7 1-28 3-61 C R7 #7 v7 77 87 n' n7 47 J7 .7 77 E7 07 C7 .7 4 2-23 8-8 5-4 B-7 2-20 4-SE Q ..

n.

w.- 5!

w.

A-47 v.

6-16 n.

m.

L. ,. .. ,.

,6-15 A-44

t. 8. L$ J. .. F. E. O. C. ..

A-47 2-22 2-21 A-42 we v4 74 $4 ne m4 L4 J4 .4 F4 to 04 C4 7-65 A-46 1- 10 1-29 A-45 7-62 v3 13 s3 as as L3 J3 .3 83 E3 03 A-46 4-54 7-4C 4-53 A-4E T2 82 A2 m2 42 J2 .2 F2 E2 3-64 3-63 er ui ni ai I

REACTOR CORE CEA AND EXCORE DETECTOR LOCATIONS

e' . ,

l RELATIVE POWER DERSITIES l 50% Power- BOC 8 KEY ]

XXX = Predicted RPD, 50% Potter, ARO, Equilibrium Xenon, 50 !%'D/HTU YYY = INCA l'.easured RPD, 50% Power, ARO, Equilibrium Xenon, 90 MWD /MTU ,

ZZZ = % Difference [(M-P)/P] 33 34 1.08 0.67 1.097 0.683

+1.6% +1.9%

~

29 30 31 32 0.98 1.21 0.71 0.57 0.998 1.228 0.748 0.593

+1.8% +1.5% +5.4% +4.0%

2 24 25 26 l 27 28 E 1.14 1.01 0.88 1.12 0.93 5 1.127 1.009 0.908 1.110 0.954

-1.1% -0.1% +3.2% -0.9% +2.6%

18 19 20 21 22 23 0.98 1.01 1.06 1.26 1.03 1.18 0.975 1.009 1.062 1.271 1.037 1.168 17

-0.5% -0.1% +0.2% +0.9% +0.7% -1.0%

0.75 0.742 10 11 L12 -I' 13 14 15 16 1.03 0.95 1.22 1.01 1.23 1.02 1.12 1.011 0.947 1.164 1.011 1.219 0.993 1.108 3

-1.8% -0.3% -4.6% +0.1% -0.9% -2.6% -1.1%

1 0.94 0.927 1 2 3 '4 l5 '6 7 3 -1.4%

0.87 0.89 0.93 0.85 1.02 1.12 1.26 1.03 0.866 0.878 0.926 0.836 1.023 1.148 1.226 1.001

-0.5% -1.3: -0.4% -1.6% . +0.3% +2.5% -2.7% -2.8%

l l 5

i l

}' .a

! RELATIVE POWER DENSITIES . .

gy 100% Power- BOC 8 i

XXX  : Predicted RPO,100% Power, ARD, Equilibrium Xenon, 500 !MD/MTU l YYY = INCA Measured RPD, 100% Power, Group 7 at 173 steps, Equilibrium Xenon, 560 MWD /MTU ZZZ = % Difference [(M-P)/P] 33 34 1.05 0.66 1.081 0.679

+3.0% +2.9%

29 30 31 32 0.99 1.19 0.71 0.56 1.004 1.227 0.744 0.586

+1.4% +3.1% +4.8% +4.6%

n 24 25 26 '27 28 [

1.17 1.03 0.89 1.10 0.89 2 1.154 1.023 0.907 1.097 0.917 . '

-1.4% -0.7% +1.9% -0.3% +3.0%

18 19 20 21 22 23 -

1.03 1.05 1.08 1.25 1.01 1.12 1.012 1.043 1.075 1.259 1.020 1.129 17

-1.7%  ! -0.7% -0.5% +0.7% +1.0% +0.8%

0.71 1 0.712 10 11 2 +0.3%

112 13 14 15 16 1.09 0.99 1.25 1.04 1.23 1.00 1.08 1.058 0.986 1.211 1.023 1.212 0.981 1.077

-0.3% I

-2.9% -0.4% -3.1% l -1.6% -1.5% -1.9% 0.89 u  ! 0.892 1 2 3 4

+0.2%

l5 76 7 3 0.93 0.94 0.98 0.89 l 1.05 1.13 1.24 0.99 0.902 0.925 0.968 0.872 1.038 1.142 1.194 0.974

-3.0% '

-1.6% -1.2% -2.0% -1.1% +1.1% -3.7% -1.6%

.