ML20133N065

Startup Test Rept,Cycle 7

ML20133N065
Person / Time
Site:	Millstone
Issue date:	10/31/1985
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20133N058	List: B11732, Forwards Startup Test Rept,Cycle 7. Criticality Achieved on 850630 & 100% Power Reached on 850711 Following end-of-Cycle 6 Refueling Outage ML20133N065
References
NUDOCS 8510280375
Download: ML20133N065 (16)

Text

. . _ _ - .

Docket No. 50-336 MILLSTONE NUCLEAR POWER STATION UNIT NO. 2 START-UP TEST REPORT CYCLE 7 i

October 1985 fh P

P

3 INDEX

1.

SUMMARY

2. INTRODUCTION

3. LOW POWER PHYSICS TESTING RESULTS 3.1 Critical Boron 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

l

1.

SUMMARY

Low Power Physics Testing and Power Ascension Testing for Millstone 2 Cycle 7 identified no unusual situations or anomalies.

All parameters measured were within their acceptance criteria and Technical Specification limits. One parameter is notewortny of mention.

The most positive measured MTC at zero power was +0.553 x 10'4

~4 AK/K/ F, while the Technical Specification limit is +0.50 x 10 AK/K/*F. While the measured value was in excess of the MTC limit, this condition was permitted by a Special Test Exception which allows the limit to be suspended in order to perform the MTC measurement. Administrative restrictions were established on CEA withdrawal and RCS average temperature 'n order to ensure that the MTC would be within the Technical Specification limits. This is a typical situation at initial startup conditions, given the large 4

boron concentrations required following refueling.

! 2. INTRODUCTION The Millstone 2, Cycle 7 fuel loading was completed on June 1,1985.

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

Subsequent operation / testing milestones were completed as follows:

i Initial Criticality June 30, 1985 I

Low Power Physics Testing Completed July 2, 1985 Main Turbine On-Line July 4, 1985 50% Power Testing Completed July 7, 1985 96% Power Testing Completed July 11, 1985 100% Power Testing Completed July 26, 1985 Cycle 7 operation is with 213 Westinghouse manufactured fuel assemblies and 4 Combustion Engineering manufactured fuel assemblies. The Safety Analysis is supplied by Westinghouse.

l J

t

3. LOW POWER PHYSICS TESTING RESULTS Low Power Physics Testing was performed at a power level of

-2

< 5 x 10 % 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 i and Excore Detector locations.

I The Critical Boron Concentration (CBC) measured with CEA Group 7 at 145 steps was 1297 ppm. Adjusted to All Rods Out, the CBC is 1304 ppm. Therefore, Measured CBC @ BOL-HZP-ARO = 1304 ppm Boron Predicted CBC @ BOL-HZP-ARO = 1331 ppm A= 27 ppm The Acceptance Critaria is 1 85 ppm.

Acceptance Criteria n et? Yes The Critical Boron Concentration (CBC) measured with CEA Groups 7 through 3 inserted and Group 2 0 18 steps was 927 ppm.

Adjusted to CEA Groups 7-2 inserted, the CBC is 918 ppm.

Therefore, 4

Measured CBC @ BOL-HZP 2-7 CEA = 918 ppm Baron Predicted CBC @ BOL-HZP 2-7 CEA = 922 ppm a= 4 ppm The Acceptance Criteria is t 85 ppm Acceptance Criteria met? Yes

T 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 ' rom either a core misloading, 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 (C) Corrected Deviation (C)

Group 1 CEA's 0.99C 0.56C Group 3 CEA's 1.11C 0.83C Group A CEA's 0.93C 0.43C Group B CEA's 0.61C 0.47C The Acceptance Criteria is i 2.5C.

Acceptance Criteria met? Yes NOTE - peff = 0.6027% 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.

I

1 All Rods Out MTC Measurement The measured MTC value with CEA Group 7 at 145 steps, an average RCS temperature of 526.7 F, and an RCS boron

~4 concentration of 1297 ppm was +0.532 x 10 AK/K/*F.

Comparing the adjusted MTC value to the predicted value yields:

Adjusted, measured MTC @

-4 532*F, 1331 ppm, BOL, ARO = +0.553 x 10 AK/K/ F Predicted MTC @ 532 F, 1331 ppm, BOL, ARO = +0.544 x 104 AK/K/ F

~4 A= 0.009 x 10 AK/K/*F

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

Acceptance Criteria met? Yes In addition to comparing the measured MTC value to the predicted value, it is also required to verify that the Technical Specification MTC limits are satisfied.

The Millstone 2 Technical Specification MTC limit states that

~4 the MTC shall be less positive than +0.50 x 10 AK/K/*F whenever thermal power is less than or equal to 70% of rated thermal power.

While the measured MTC value exceeds the Technical Specification limit, this is permitted by a Special Test Exception which allows the MTC limit to be suspended in order to allow the MTC measurement to be performed.

Since the measure MTC value was in excess of the Technical Specification limit, it was necessary to establish administrative restrictions on CEA withdrawal a,d RCS average

l 4

l temperature in order to ensure that the MTC would be less l

~4 positive than +0.50 x 10 AK/K/*F. These restrictions were

, only required until the critical boron concentration was

{ reduced by fuel depletion.

j CEA Groups 7-2 Inserted MTC Measurement i The measured MTC value with CEA Groups 7 through 3 inserted and CEA Group 2 at 20 steps, at an average RCS temperature of  ;

527.4*F, and an RCS boron concentration of 927 ppm was

-0.422 x 10 ~4 AK/K/*F.

l Adjusting this measured value to the prediction conditions of ,

~4

) 532 F and 922 ppm yields an MTC value of -0.444 x 10 AK/K/*F.

l i

4 Comparing the adjusted MTC value to the predicted value yields: ,

I i

l Adjusted, measured MTC @ r

~4 532 F, 922 ppm, BOL, CEA 7-2 Inserted = -0.444 x 10 AK/K/ F Predicted MTC @ 532*F,

~4 922 ppm, B0i., CEA 7-2 Inserted = -0.256 x 10 AK/K/ F l

~4 I A= 0.188 x 10 AK/K/*F 1 l l l

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

Acceptance Criteria met? Yes i

3.4 Control Element Assembly Reactivity Worths

]

! Reactivity worth measurements were performed twice on CEA l j Groups 7 through 2. The first measurement involved measuring l l 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 i their normal overlap mode of operation, j l

1

)

i .

4 I

The results of the measurements were:

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

7 0.752 0.727 0.025 3.4%

6 0.366 0.393 -0.027 -6.9%

5 0.225 0.267 -0.042 -15.7%

4 1.217 1.189 0.028 2.3%

3 0.573 0.503 0.070 13.9%

2 1.240 1.168 0.072 6.2%

Total 4.373 4.247 0.126 3.0%

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

l 2 1.251 1.168 0.083 7.1%

3 0.569 0.503 0.066 13.1%

4-7 2.582 2.576 0.006 0.2%

Total 4.402 4.247 0.155 3.6%

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

Acceptance Criteria met? Yes The Acceptance Criteria for any individual CEA Group is either 1 0.1% AK/K or i 15% difference.

2 Acceptance Criteria r et on all CEA Groups? Yes i

l i

)

I ______ -

i

3.5 Hot Rod Drops j Hot Rod Drops were performed on all 61 CEA drive mechanisms.

! The drop times from 0 to 100% insertion ranged from 2.19 to 2.45 seconds.

l i

The Acceptance Criteria, per Millstone 2 Technical l Specifications, is that all CEA's must drop from 0 to 90%

insertion in less than 2.75 seconds.

l l Acceptance Criteria met? Yes l

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

1 i

l T T 4

Power Level Fxy & Max. Linear Heat Rate Incore Tilt

! 50% 1.570 1.473 6.91 KW/ft 0.002 l 96% 1.528 1.461 13.01 KW/ft 0.003 l 100% 1.521 1.466 13.12 KW/ft 0.003 i

i

! The corresponding Technical Specification limits are:

T T l Power Level Fxy & Max. Linear Heat Rate Incore Tilt 50% 1.836 1.705 15.6 KW/ft 0.02 f

l 96% 1.719 1.570 15.6 KW/ft O.02

{ 100% 1.719 1.565 15.6 KW/ft 0.02 i

i

. Technical Specification limits met? Yes i 4.2 Boron Measurements l At 50% power, 30 MWD /MTU, ARO and Equilibrium Xenon, the i

measured boron concentration was 1061 ppm.

l i

Measured boron concentration 50% power, 30 MWD /MTU, AR0, Eq. Xenon = 1061 ppm t Predicted boron concentration 50% power, 50 MWD /MTU, AR0, EQ. Xenon = 1071 ppm A= 10 ppm  !

The Acceptance Criteria is t 85 ppm Boron.

i Acceptance Criteria met? Yes At 100% power, 275 MWD /MTU, ARO and Equilibrium Xenon, the measured boron concentration was 948 ppm.

Measured boron concentration 100% power 275 MWD /MTU, ARO, Eq. Xenon = 948 ppm Predicted boron concentration 100% power 275 MWD /MTU, AR0, Eq. Xenon = 951 ppm a= 3 ppm The Acceptance Criteria is 1 85 ppm Boron.  !

L i

Acceptance Criteria met? Yes 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 567.25*F, and an RCS boron concentration of 948 ppm was -0.257 x 10 ~4 AK/K/*F.

Adjusting this measured value to the prediction conditions of 96%, 567.2*F and 966 ppm yields an MTC value of -0.231 x

~4 10 AK/K/*F. i Comparing the adjusted MTC value to the predicted value yields:

I I

i

]

l l

4 Adjusted, measured MTC 9 96%,

~4 966 ppm boron, and T,y, = 567.2*F = -0.231 x 10 AK/U*F Predicted MTC 9 96%, -

, 966 ppm boron, and T, = 567.2*F = -0.215 x 10 ~4 AK/K/'F j A= 0.016 x 10 ~4 AK/K/*F

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

Acceptance Criteria met? Yes i

I 4.4 Doppler Only Power Coefficient The measured Doppler only power coefficient at 94.1% power, an average RCS temperature of 571.0*F, and an RCS boron concentration of 948 ppm was -0.943 x 10 AK/K/% power.

4 Adjusting this measured value to the prediction conditions yields a Doppler only power coefficient value of -0.947 x I ~4 10 AK/K/% power.

! Comparing the adjusted value to the predicted value yields:

Adjusted, measured value 9 93% power, 966 ppm and 572*F = -0.947 x 10 ~4 AK/K/% Power

! Predicted value 9 93% power

~4 f 966 ppm and 572*F = -0.918 x 10 AK/K/% Power

~4 A= 0.029 x 10 AK/K/% Power

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

Acceptance Criteria met? Yes

. 4.5 RCS Flow at 100% Power i

i The measured RCS flow at 100% power was 375,300 GPM.

l' The Acceptance Criteria is >350,000 GPM.

1 i

1 i

i i

f Acceptance Criteria met? Yes i

i 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.

l The Acceptance Criteria is that all locations are within 110%

f of the predicted values.

l I Acceptance Criteria met? Yes i

4.7 Reactor Coolant System Radiochemistry Reactor Coolant System (RCS) radiochemistry analyses during power ascension testing and subsequent power operation have i showed low activity levels in the RCS. The Iodine - 131 values i

are typically 2 x 10

-3 pCi/ml or less as of this writing, which I

indicates that the fuel integrity is sound. This is a factor i of

• 30 lower than the previous 2 operating fuel cycles. With l the core currently at ' 1000 s MWD /MTU burnup, no iodine spiking 4

at all has been observed, further substantiating that no fuel failures are present.

i i

j 5. REFERENCES

5.1 In-Service Test T85-18, Initial Criticality / Low Power Physics

} Test - Cycle 7.

i 1 5.2 In-Service Test T85-19, Power Ascension Test - Cycle 7. E 5.3 Westinghouse Nuclear Design Report - Cycle 7.

I  !

1 RB: dip t I

I r l I t____._..______-____. _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . .

FIGURE 1 1 2 3 4 5 6 7 8 9 10 Il 12 13 14 15 le 17 18 19 30 21 I I I I I I IIIIIIIll l l l l l l 1

,_ Iss 765 747 797 - i-x- Il3 N 873 # 'I IIO Il 3\ 40

, ,_ 75'l G23 72o H71 HL4 F5o H'71 H35 J2l Goh I?b l 19 19 71 41 ST

,_ N H49 7t? Gl3 GSt dit H31 H19 hlb Got T 37 H5Z W3 77 i8 30 39 ri 79

[ _y_ 7 70 Got T3i Gb5 H 37 H21 H52 F24 Hir H oM H&o G3s IMo G tl J75

, 6 P 29 44 9 63

~

,'_ 7 69 7 24 G li G59 G59 H41 G69 4 05'G72 H&i G41 G67 G13 72i ISI io 17 fo 59 e

,_ J48 H79 31% H li H57 Aob1 723 GHz J29 Aos r H 36 H t9 H 41 Hit TLt

,_ 774 f 63 23 34* 4f 59 61 7 52 HSD H61 glo ggy G29 J3) G 50 Gt37 G37 J34 G *70 H4f GIO H37 N7f I60 2- 9 29 3R 63 69 7 64 t_

G33 F60 H4F F2n F31 G23 GC3 F23 H32 See G ar.

,_ 757 So P 22 GW 89 l Nil49lG44 Wit 9 g3 x39 l , _ HM H25 H21 H46 G7 730 Gb4 6 03:G39 757 G 3e H29 Hio H40 H 7S-

,_ I43 I 8 28 37 57 6*l IL4

, ,_ 787 His H2L GoS Hsi Ao46 J21 G25 123 Aos7wes Hot H S: H1f 162

't i2 2t 32 43 53 (31 4

,_ 742 Ili Go3 H30 GF2 H b7 GH3 F43 G27 HS6 GT3 H11 Gq l732 '754 ^

• 7 lb 49 66!

,_ J76 Go9 726G39 H33 His HL3 F22 H b1 Hi3 Han 'G53 J33lGir T%

3 9 2o 42 p !6o

,_ 76T H53 J36 G22 R42 Ho7 H"70 Ho2 H2"7 GO7 J3% H39 INT 76 19 27 3b 4? 73 ,

c- If6 G20 739 H16 H97 F31 H5fH 8L J+4 T22lG21 j 11 2f  ?! 41 i T2 i

,_ I'4 l IffTfl Hg3 h20 Hg7 753 763 Jgz 26 37 l

,_ x,z 1,eix,e as3 I

t

)

?

CYCLE 7 l[

} CORE MAP

• CEA 34 rotated CW 90* S/M in NE web 4

5008CE 10 cat! CMS j Source Core locatton Guide tube *

~

53 F3 14

! 54 5-19 SE g 55 t-11 %d I

56 A-10 %i

FIGURE 2 1

• 2 u21 just w21 NORTH l

i T20 s20 R20 m:0 L20 J2C G20 F20 E20

\

3-69 3-58 v19 T19 519 R19 Ntp L19 Jt9 619 F19 E19 D1b

. A-49 4-57 7-38 4-50 A-4Z wie vie T18 518 R18 utO L18 J18 618 FtB 118 01E C'8 7-68 A-49 1-33 1-26 A-42 7-59.

4 117 wi7 v17 T17 S17 R17 Nt? L17 J17 617 F17 EI' 017 'C17 817 A-48 2-25 2-18 A-43 x16 m16 V16 T16 $16 R16 Nt6 L16 'J t6 616 F16 Et6 016 C16 516 A-48 6-17 6-14 A-43 X x15 wt5 : v15 Tis '515 RiS ut5 L15 J15 G15 FIS r15 015 CIS 515 ,

j

- na 4-56 2-24 B-9 5-2 B-6 2-19 4-51 ^"

113 w13 v13 T13 $13 R13 ut3 L13 J13 GIS F13 Et3 Dt3 CIS 813 j "2 3-67 1-32 B-9 B-6 1-27 3-60 '

stl wit vli T11 stl R11 mit Ltt utt sit rti ett att Cil sit vio 7-41 5-5 7-1 5-3 7-39 a'a It w9 v9 79 SS A9 N9 .

L9 JS 69 F9 E9 09 CS 59 3-66 1-31 B-8 B-7 1-28 3-6L 1 E7 w7 V7 77 $7 R7 h7 L7 J7 67 F7 (7 07 C7 37 i

4-55 2-23 B-8 5-4 B-7 2-20 4-52 y x6 w6 v6 T6 .6 A6 .6 L6 J6 .6 F6 e6 06 C6 .6 4-47 5-16 5-15 t -4 *e 1 -

15 wS v5 T5 SS R5 al LS J6 65 F5 ES & C5 B5 A 2-22 2-21 A-44 we v4 T4 $4 R4 N4 L4 J4 64 F4 to D4 C4 7-65 4-46 l-30 1-29 A-45 7-62 I v3 T3 $3 R3 m3 L3 J3 63 F3 g3 c3

{ A-46 4-54 7-40. 4-53 A-45 J

T2 52 R2 m2 L2 J2 62 F2 E2 3-64 3-63 Pl Mt lR$ Mt ,

i 4

h i

i i

, REACTOR CORE l

1, CEA AND EXCORE DETECTOR LOCATIONS I

i i i .

l i

5 I

I l

l l

~

~

i

~ ,1 l -

i RELATIVE POWER DENSITIES . ,

50% POWER-BOC 7  :

XXX Predicted RPD, 50% power, AR0, Equilibrium Xenon, 50 MWD /MTU \

YYY INCA Measured RPD, 50% power, AR0, Equilibrium Xenon, 50 MWD /MTU ZZZ  % Difference [(M-P)/P] 33 34 1.05 0.63 '

1.076 0.657

+2.5% +4.3%

l i

29 30 31 32 1.03 1.19 0.69 0.55 1.047 1.193 0.731 0.570  !

t

+1.6% +0.2% +5.9% +3.6% -

- 2l 24 25 26 27 28 81 0.97 0.968 1.19 1.181 0.88 0.911 1.19 1.206 0.93 0.951 5l wI

-0.2% -0.8% +3.5% +1.3% +2.3% {

18 19 20 21 22 23 0.85 1.17 1.04 1.18 1.09 1.15 17 0.843 1.142 1.033 1.191 1.100 1.163 i

-0.8% -2.4% -0.7% +0.9% +0.9% +1.1%  !

2 10 11 12 13 14 15 16 +3.2%

0.93 1.21 0.98 1.12 1.06 1.17 1.02 0.907 1.164 0.917 1.108 1.057 1.138 1.035 )

-2.5%

-3.8% -6.4% -1.1% -0.3% -2.7% +1.5% 0.90 i O.903 i 1 2 3 4 5 6 7 3

+0.3%

0.72 0.98 0.98 0.94 0.83 1.22 1.03 1.19 0.699 0.928 0.951 0.889 0.831 1.224 1.043 1.220

-2.9% -5.3% -3.0% -5.4% +0.1% +0.3% +1.3% +2.5% ,

. # i

- l I j

f

- / *

{ RELATIVE POWER DENSITIES _ ,

100% POWER-BOC 7 4 XXX Predicted RPD, 100% power, AR0, Equilibrium Xenon, 150 TWD/MTU

! s j YYY INCA Measured RPD, 100% power, AR0, Equilibrium Xenon, 500 MWD /MTU

._. . ZZZ  % Difference [(M-P)/P] 33 34 i 1.03 0.62

] 1.060 0.652 ~

I +2.9% +5.2% l i

29 30 31 32 1.03 1.18 0.68 0.54 i 1.042 1.172 0.719 0.567  !

i +1.2% -0.7% +5.7% +5.0% i r

j 1

24 0.99 25 1.19 26 0.89 27 1.17 28 0.90 hl E'

O.988 1.191 0.902 1.171 0.920 "i

• I

-0.2% 0% +1.3% 0% +2.2% i 18 19 20 21 22 23 l 0.88 1.20 1.06 1.18 1.08 1.11 j7  :'

! 0.878 1.179 1.047 1.184 1.073 1.110

-0.2% -1.7% -1.2% +0.3% -0.6% 0% 0.66  !

10 0.686 11 12 13 14 15 16 1 +3.9L i 0.96 1.24 1.01 1.14 1.07 1.16 1.00 i

'0.960 1.221 0.963 1.129 1.056 1.118 1.002 3 ,

0% -1.5% -4.6% -1.0% -1.3% -3.6% +0.2% 0.87 I 2 0.875 3 4 5 6 7 3

+0.6%

0.76 1.01 1.01 0.97 0.85 1.23 1.03 1.16 0.994 1.003 0.938 0.850 1.226 1.025 1.176 O.749

-1.4% -1.6% -0.7% -3.2% 0% -0.3% -0.5% +1.4%

i j . . i I

a