ML20148H158

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Core 13 Startup Rept
ML20148H158
Person / Time
Site: Yankee Rowe
Issue date: 11/30/1977
From: Ebert M, Moody T, Stlaurant N
YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20148H155 List:
References
NUDOCS 8011170313
Download: ML20148H158 (20)
v • d • e


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YAllKEE-ROWE CORE XIII STARTUP REPORT fl0VEMBER 1977 Prepared by /j[cM Id. b Plant Reactor Engineer ,

Reviewed and Approved by: [

02 l CchWUN hi //iffluno

_ Plant Superintendent  !

? . ut Manager ofOpcttMifns z

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_ TABLE OF CONTENTS Introduction -----------------------1 Control Rod Operability -----------------5 Control Rod Drop Time ------------------5 Just Critical Boron Concentration - - - - - - - - - - - - - 6 Control Rod Differential and Integral Worths -------7 Ejected Control Rod Worth --------------- 11 Dropped Control Rod Worth --------------- 11 Moderator Temperature Coefficient - - - - - - - - - - - - 12 Xenon and Power Defects ---------------- 12 Flux Map Results -------------------- 14 Doppl e r Coe f fi cient - - - - - - - - - - - - - - - - - - -

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ItiTRODUCTIO!1 This repo,rt conveys a summary of the results obtained during the startup testing of Core XIII. It is divided into ten sections which parallel the sections specified in the Core XIII Performance Analysis Startup. Program (Proposed Change to the Technical Specification 145, Supplement 4). All testing results included in this report were obtained under the guidance of operating procedures OP-1701 (Rev.1), " Core XIII BOL Zero Po.ler Physics Test" and OP-1702 (Rev. 3), " Core XIII Zero to Full Power Physics Test Procedure".

Many of the results obtained during Core XIII startup testing were done with the use of a reactivity computer. The computer is a Westing-house model fiBSU 8094 analog computer. Programming is unique for each set delayed neutron fractions. Verification of proper programming is completed by feeding the computer an exponential signal and measuring the reactivity response of the computer. The computer is properly pro-grar:ned if it yields correct values of reactivity for a given startup rate. When the computer is connected to the excore detector both the computer and the delayed neutron fractions used in programming it are checked, this time using a real neutron response to reactivity input from )

control rod withdrawal.

The delayed neutron fractions which were used during the physics ,

esting are tabulated belcw. j FPACTIO:! EFFECTIVE LAMBDA l 30.r? BETA BAR FRACTIO!1 (SEC)-1 l 1 .00018770 .00018588 .01252 2 .00133860 .00132866 .03055 3 .00122062 .00121025 .11512 4 .00249749 .00247441 .30932 5 .00085575 .00084951 1.16220 6 .00030523 .00030300 3.04024 Beta Effective = .006352 .

Beta Bar = .006405 I Bar = .9916 Prompt lieutron Lifetime = 18.60 microseconds

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V Core XIII is loaded with 36 new Exxon fuel assemblies. The fuel is 4% enriched in U-235 with Zircaloy cladding. The new assemblies are loaded around the perimeter with 40 once burnt arsemblies in the interior. I A figure depicting the fuel arrangement follows.

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Yankee-Rowe has 24 cruciform shaped control rods arranged as shown in the following figure.

Following refueling,and prior to vessel reassembly each as loaded fuel assembly was verified to be properly positioned. This was done with  ;

an underwater television on July 7, 1977. An attempt was made to video I tape the verification but the recorder failed,

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YANKEE ROWZ CONTROL ROD GROUPS

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O REA CTOR CORE .0 FUEL L OCA TIONS COTC XIII A B C D E y F G H J ,

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1. Prior. to the initial criticality the operability of each of the This was done by exer-four control rod groups was demonstrated.

cising each group in turn from fully inserted to fully withdrawn and return to fully inserted. The control rod position lights were used to verify proper rod movement. Each control rod and control rod group responded correctly. In addition each control rod was individ-ually withdrawn nine inches to verify proper identification. As before, the rod position lights were used to verify rod movement.

2. The control rod insertion time was measured for each control rod, prior to the initial criticality of Core XIII. Determination of the drop time involved measuring the tine from the opening of the station-ary gripper power supply circuit to the insertion of the rods below the six inch indicating coil light. A Visicorder (recording oscillo-graph) was used for this measurema t.

All control rods inserted well within the required 2.5 seconds. Below is a table of the drop times from cycle XIII as well as cycle XII for comparison.

Control Drop Time (Sec) Control Drop Time (Sec)

Rod XIII XII Rod XIII XII 1 1.42 1.77 13 1.50 1.74 2 1.56 1.73 14 1.54 1.52 3 1.69 1.61 15 1.47 1.50 4 1.70 1.74 16 1.70 1.53 5 1.52 1.54 17 1.51 1.62 6 1.46 1.56 18 1.64 1,56 7 ,1.50 1.58 19 1.60 1.59 8 1.50 1.58 20 1.79 1.61 9 l'.53 1,56 21 1.54 1.84 10 1.52 1.56 22 1.52 1.68 11 1.49 1,48 23 1.54 1.86 12 1.74 1.54 24 1.56 1.60

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3. Equilibrium, just critical, main coolant boron concentrations were measured four times during startup testing. The measured results, p ?dicted results and approximate control rod confirguration are tabulated below.

Just Critical Boron Conc.

Control Pod Confiauration Measured Predicted All rods withdrawn 1990 ppm 1762 ppm Group C inserted 1805 1520 Groups C and A inserted 1608 1333 Groups C, A and B inserted 1286 949 The measured values do not meet the acceptance criteria of plus or minus ten percent of predicted. The-exact reason for the discrepancy is under investigation. To verify the validity of the measured data two hand calculations were performed.

Method number ene was to start with the critical boron concentration (1405 ppm) as calculated under hot, full power, all rods out conditions.

This normally accurate value is based on boron letdown curves from the previous two cores. This value however, must be adjusted to simu-late measured conditions. This is done by removing the xenon and doppler contributions to get zero power, no xenon conditions. When these adjustuents are done, the resulting adjusted just critical, all rods out boron is 1962 ppm which is in good agreement with the measured value of 1990 ppm.

Method number two involved the use of cycle X11 excess reactivity compared to cycle XIII excess. The difference in calculated excess is equal to 1.65% reactivity. The measured value for the just critical all rods out boron for cycle XII was 2258 ppm. As the calculated difference was 1.65% reactivity (equivalent to 249 ppm) between cycio XII and XIII, method two would predict 2009 ppm. This is also in good agreement with the measured value, 1990 ppm.

Based on these two methods the measured value was taken to be correct and the predicted number to be in error. Examination of chemistry analysis methods and boron 10 content in the boron used support this conclusion.

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Such an error in the predicted beginning of cycle, all rods out just critical boron has no effect on the accident analysis or safe operation'of the plant. Therefore cycle XIII startup was not affected.

4. The differential and integral worths.of control rod groups C, A and B were measured. This was done by introducing a constant dilution, balancing the dilution with control rod group insertion and measuring the worth of each step with a reactivity computer. The integral wo ths were obtained by summing the worth of all the steps. In each case, prior to beginning the measurerent, the boron concentration was determined to be in equilibrium. Also, while the measurerents were going on, the temperature was held as close to constant as possible.

The table below summarizes the results:

Measured S Ao Predicted *' Ao Group C ( 4 rods) 1,57 1.60 Group A ( 4 rods) 1.25 1.23 Group B ( 8 rods) 2.50 2.55 The acceptance criteria imposed on control rod group worth was that the measured value must agree within the predicted plus or minus 7 1/2%.

All measurements successfully verified the calculated number.

Graphs of the differential and integral rod worths of groups C, A and ,

D occupy the following three pages.

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5. The' worth of an ejected control rod for cycle XIII was measured for two conditions. The ejected rod worth was measured with group C in-serted and all other rods fully withdrawn. This condition mocks the

" full power" case. -

The "zero power" case ejected rod was measured with groups C and A inserted and all other rods fully withdrawn.

In both the full power and zero power cases the measurement was con-ducted with more rods inserted than would be allowed by the rod re-striction curve. The ejected rod worths, as assumed in the accident analysis, were calculated based on the control rod restriction curve limitation. Hence the measurements do not directly measure the accident analysis input, bt ', verify the methods which produce that input.

Ejected rod worths were obtained by balancing a small boron dilution with insertion of the rod. The reactivity computer was used to measure ,

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the value of the ejected rods.

The results of the ejected rod worth measurements are tabulated below.

Worth Gao Meas ured Predicted Rod 16, Group C inserted 0.60 0.62

(" full power" case) r ed 16 Groups C and A inserted 0.82 0.81

("zero power" case)

Acceptance Criteria: predicted ! 15%

6. Cycle XIII dropped control rod worth was measured for the calculated most worthy rod. The measurement was performed from the all rods out condition by establishing a small steady dilution, balancing the reac-tivity addition with insertion of the dropped rod, and measuring the worth of the rod with the reactivity computer. Below is the result:

Worth % op Measured Predicted Rod 4, most wortny dropped rod 0.33 0.32 Acceptance Criteria: predicted + 15"

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7. Moderator temperature coefficient was measured as part of the startlp program. The measurement was performed by #irst attaining a stable, just critical reactor condition at equilibrium boron concentration.

Then the main coolant system temperature was varied by operating a secondary side steam dump and the reactivity change was measured with the reactivity computer.  ;

Measurements of moderator temperature coefficient were made at four different boron concentrations. Insertion of control rods allowed the boron to be reduced over the range from 2000 to 1287 ppm. Correct-ions were made in the predicted values to account for rod insertion.

The results are tabulated below and graphically represented on the following page. Acceptance Criteria: predicted 10.5E-4 AK/K/ F.

Moderator Temperature Coefficient Boron Concentration, Measured Predic ted 2000 -0.49E-46K/K/ F -0. 90E-4 AK/K/ F I 1805 -0.75E-4 -1.12E-4 1606 -1.19E-4 -1. 3 7 E- 4 1287 -1.78E-4 -1.74E-4 The measured data recoried above is the result of averaging the dat.a from a ninimum of five cianges in temperature (heatup or cooldown).

Each change in temperature was a minimum of two degrees. All measure-ments were in the range of 518 to 528 F main coolant temocrature.

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8. The combined xenon ar.d power (doppler) defects were measured from zero po.ter to equilibrium 499 MWt (1831). This was accomplished by recording all pertinent data at zero and 499 MWt. Changes in main coolant temperature and pressure, control rod position, boron, and burnup ' tere accounted for in calculating the combined defect.

Measured Predicted Power + zenon defect 3.38S AK/K 3.4S AK/K Acceptance Criteria: ilone A

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9. At approximately 7 percent power.a set of flux traces were taken to verify core symmetry. At this power level, the flux levels are so low the amplitude produced on the strip chart is less than 1.5 inches.

This small amplitude leads to inaccuracy in the measurements and analysis. Initially, a visual check of the traces was made by comparing i symmetric locations. From the visual inspection, symetric locations appeared symmetric. An analysis was later done with IliCORE and the comparison of measured and thcoretical sionals can be seen on the map which follows.

At 348 lMt (58%) another set of flux traces was taken with the moveable fission chambers. This set was analyzed with the IllCORE program, using j ti.coretical information from the PDQ program. During this set of traces, l

only one pen was operable on the recorders. The analysis showed a small but noticeable tilt. However, since only one pen was used, no cross calibration of detectors was possible. To verify what had been analyzed a second set of traces were taken with both pens operable. The condi-tions present during this second set of traces were:

Burnup 75 t0!D/MTU  !

Power 448 lMt (74.7%)

Boron 1513 ppm

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Tinlet 495 F l Group C 87 in.  !

1 Group A, B, D. 87 in.  ;

The comparison of measured and theoretical signals can be seen in the fi gure which follo'.is. The quadrant tilt reen in this analysis is less  ;

than 2';. This tilt is taken into accou1t in the hot channel factors Thus, the measured linear heat generation rate takes the tilt into  ;

l account.

Below is a summar,/ of the results of the It! CORE run prior to exceeding 75% power.

Paramete r Measured Limit LHGR 8.415 kw/ft 9.438 kw/ft Fq 2.454 2.76 F}g 1.609 1.80 This measured LHGR takes into account all the factors required by the Technical Spect fications.

' ' [ - - COMPARI C OF MEASURED AND THEORET v F'.L SIGNALS INCORE RUN YR-13-001 60.0 MWT. GROUP C AT 75.0 INCHES

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  • 0. NWD/MTU MEASURED SIGNAL

.703 THEORETICAL SIGNAL

.724 PERCENT DIFFERENCE -2.892

.988 1 052

~6.079 1.063 1.124

-5.472 1.024 1.100 .

1.124 1.054

-8.904 5.103 1.040 .978

.737 1.049

.727 1.058

-1 740 -6.757 1.362 s

1.131I

.) - l 1 050 6.055 l

1.095 1 114! 1.122 1.054 1.124 l 1.102 .165 l

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l 1.124 1.119 3.669 6.822 ,

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.752 1.054

.731 1.052 2.075 .234)

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AVERAGED A1(SOLUTE DIFFERENCE 3.892 PERCENT DETWEEN HEASURED A>:3 THEORETICAL n.

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COMPARIsoft OF MEASURED AND THEORETICAL SIGNALS

' - INCORE RUN YR-13-003 440.0 MWT. GROUP C AT 87.0 INCHES

75. MWD /MTU 4

MEASURED SIGt!AL . 700 THEORETICAL SIGNAL .727 PERCENT DIFFERENCE -3.688

.998 1.049

-4.892 1.090 i 1.121 l

-2.775 1.119 1.087.

1.121 1.050

.128 2.289 1

1.099 1.020

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1.062 1.000

.730 )

3.504

-2.068 1.660 I 1.090 1 062 2.60G i i I , __

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.121 1.090 3.174 --2.576 1 . 5 11 1,127 1.0?S.

1.121 1.116

.577 -1 006

.//, 1.046

.731 1.049 2.202 .316

.733

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10. Doppler coefficient was measured by recording the change for perti-nent reactiyity parameters between two equilibrium steady state power levels. Changes in main coolant boron concentrations, temperature and pressure are accounted for as are rod positions, fuel burnup and Xenon.

Twice doppler coefficient was measured, once between 60 and 70% and again between 70 and 835.

Apower Measured Predicted 60 - 70% -1.75E-5 op/ F -1.48E-5 op/ F 70 - 83% -1.47E-5 Ap/ F -1.46E-5 op/ F Acceptance criteria: predicted ! 25%

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TRUTION lSIER ISSUANCE OF EERATING LICENSE _

- u.3. NUCLEAR i,EQULATORY COMglCN OOCKET NUMIEQ

,u 195*

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.: 7 h @ .17

"""*I""

- NRC OISTRIBUTION FOR PART 50 DOCKET MATERI AL FROM: oats op DOCUMENT 0* Yankee Atomic Electric Co*

12/06/77 i S. R. C. Westborough, Mass. 3,7, ,, c ,, y , o R. H. Groce 12/12/77 PROP INPUT FORM NUM8ER OF COPIES RECEIVED zipa O NOTORIZE D '

E mc.NAL gNCurs3ipiEO C.*'~ AS/6060 ENCLCSU R E 0150TtPT:ON Yankee-Rowe - Core XIII Startup Report -

November 1977.-

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