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J' SAXTON PRE-OPERATIONAL TEST 8
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305 1 Initial Core Londirg,
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305 2 control Rod Drive and Plant scram Test 305 3 Initial criticality-305.h control Rod, Boron, and Void Worth Determination at Ambient Temperature e.'
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305 5 Temperature and Pressure coefficients at Shutdown Boron Concentration M
305 6 control' Rod Worth, Boron and Flow Worth at. Operating Tesqperature t
o 305 7 Temperature and Pressure coetricient Determination at-Low Boroa Concentration
-305.6 Instrumentation Response at Low Power t
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PRE-OPERATIONAL TEST 305 1 TITLE: Initial Core Loadin6
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t PRE-OPERATIONAL TEST 305 2 TITLE:
Control Rod Drive and Plant Scram Test
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I PRE-OFERATIONAL 305 3 TI'I2 : Initial Critice.11ty l
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TRE OFERATIONAL TEST 305 4 TITLE: Control Bod, Boron, and Void Worth Determination at Ambient Temperature 5
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PRE-OPERATIONAL TEST 305.4 CONTROL ROD BORON. AND VOID WORTH DETERMINATION AT AMBIENT TEMPFRAWRE I.
Objective: To deterttine at ambient temperature, the worth of bania4 control rods, worth of boron in the reactor coolant, and the void vorth.
II.
Conditions:
1.
This test procedure has been thoroughly discussed with and under-stood by operating perconnel.
2.
Satisfact9ry completion of Pre-Operational Test 305 3 3
Special nuclear instrumentation, section IV-a belov, is installed and checked out.
k.
Main coolant system is filled with primary plant grade water contain-ing the loading boron concentration and has been checked by analysis.
5 Main coolant pressure and temperature are essentially at ambient with head off for the determination of the void worth. For the rod f_
and boron vorth measurements, the head v*.ll be attached, the primary pump operating, and the main coolant pressure and tempera %re main-l tained as near ambient as possible.
6.
Pertinent auxiliary systems for the void worth measurement are the same as in Test 305 3 7
Pertinent auxiliary systems for the rod and boron worth measurements I
are in the following status:
SYSTEM STATLS l
l Pressure Control and Relief Ready for startup 0.I. 410 Charging and Volume Control Ready for startup
- 0. I. kil Reactor Control heady for startup n m d conhol 0.I. 412 1-2-62
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305.4: 2 S_tatus System Nuclear Ins +,rumentation Nomal Operation 0.I. 413 Radiation Monitoring Normal Operation O.I. 414 Boric Acid Adittion In operation as required 0.I. 417 Boric Acid Removal In operation as required I
0.I. 418 Chemical Addition Isc. lated 0.I. 419 Purification Isolated 0.I. 420 Sampling In Operation as required 0.I. 421 Camponent Cooling In operation as required 0.I. 422 l
l Shutdown Cooling In operation as required 0.I. 423 l
l Service Water In operation as required i
O.I. 424 Vapor Container, Heating and Nomal Operation Ventilation 0.I. 425 l
Electrical (Systems)
Normal Operation 0.I. 427, h28, 429 i
i Facte Disposal Capacity available to receive 0.I. 430 liquid vaste Safety Injection Operation Isolated N.I. 610 III. Pmcautions:
1.
Criticality should be anticipated at any time when control rods are being withdrava.
g 2.
Any plant changes which would produce a sudden change of reactor
305.h: 3 coolant temperature (of the order of 10*F) must be avoided while the reactor is approaching crR:cality or is critical.
3 Startup rates greater than 1 decade per minute should be avoided.
4.
Available shutdown reactivity must not be redu ed belov 3% ak with all rods in or 1% vith one rod stuck as determined by anabsis and this experiment. That is, the boron concentration in the system must not be reduc 0d below the value required to give a k of 0 97 ff or O.99 for the core under the above mentioned conditions.
5 During reactivity measurements, limit maximum flux level to 6 decades above source level or 10'I amps on CIC detector, whichever is lover.
During flux vire irradiations, limit the maximum flur. level e.s indicated by a CIC detector to 2 x 10 amps ( 100 kv).
6.
After boron addition or dilution, allow the main coolant system to become thoroughly homogenized.
IV.
Instructions A.
Special Instrumentation Requirements 1.
Extra sensitive (better than 10 amp full scale) amplifier
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for a compensated ion chamber channel.
Strip chart recorder connected to this amp?ifier output.
2.
A resistance bridge for one main cool.nt system resistance temperature detector.
3 A Heise gauge located in the sample room will be used to read the system pressure.
4.
The flux vire system if operable, vill be operated as indicated.
5 Scalers for the p3 ant BP channels.
3 B.
Performance Sequence:
i I.
Void Worth Measurements 1.
Perfom reactor startup utilizing rod program described in section II-B-2 (nominal rod program) of_the Control Rod and Boron Worth Determination portion of this procedure.
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obtain the just critical bank and startup rates of 0.2, 0 5, i
I and0.8 decades / minute.
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Insert all the rods except rods 2 and S which are cocked at 10 inches to safetien.
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semove the central 3 x 3 cunassembly (position D-3) with the appropriate fuel loading tool using the slovest s} red. Utice i
the subassembly in steps of 8 inchen and perfom a 1/M cal.
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culation. Analysis indicates that a Li of about 0.2% is l
added and the core should thus remain substantially sub.
critical. HovcVer, should the 1/M plot predict an impending criticality, the situation vill be evaluated in the sanner described in Test 3051, Initial Core Loading.
h.
After the subacaembly le removed frcan the core and safely stored, repeat step 1.
If possible, obtain a startup rate with rods at just critical position of step 1.
5 Relent step 2.
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Insert in steps of 8 inches an empty me+=114e box, having the-dame external tiimensions of a subassembly, into position D-3.
Perfom the 1/M calculation. Analysis indicates that the in-sertion of such a void vil.1 decrease the k,ff of he core. -
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Mien the empty metallic box is fully inserted it the core, repeat step 1.
i 8.
Repeat step 2.-
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9 Remove slowly the empty metallic box.
- 10. Insert slowly in the core 3 x 3 subassembly into position l
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305.k :
5 II.
Control Roi and Boron Worth Determination A.
The designations of the control rods arti as follove:
Bod No.
Hod Position 1
CD-12 2
DE 23 3
12'- 34 4
BC-23 5
CD-34 6
DF h5 B.
The programed withdrawals durs ng this test are the following:
- 1) Withdraval of all rods (banked rods)
- 2) Withdravs1 c' rodn 3 and k, followed by rods 1 and 6 and then by rodo P and 5 (ncsinal rod program)
- 3) Withdrawal of rods 1, 3, h, and 6
- 4) Witndrawal of rods P, 4, and 6
- 5) Withdrawal of rods 2 and 5 C.
Procedur_e :
- 1) Establish criticality at about 3 decades above source level utilizing rod program B-1 (banked rods)
- 2) Charge boron acid at rate sufficiently slov to allow the control rods to follow and maintain criticality.
Maintain main coolant pressure by bleeding to low pressure surge tank.
Promote mixing of boric acid solution between coolant system and pressurizer.
Measure the time from boror. injaction to Br
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- 3) stop boration when banked rods are at approximately 37 inches. Obtain boron cample.
I 1-2-62 1
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4 305.k: 6 k) Obtain appropriate axial flux traces.
- 5) withdraw all-the rods to establish a stcrtup rate of about 0.8 decade per minute or to LO inches whichever is reached first.
If the rod bank is less than 40 inches, then add boron in increments of about 10 ppm until the sttertup rate is between 0 5 and 1 decade per minute with all rods at 40 inches. Allow su ficient e
time for the boron concentration to become uniform in i
the primary system and then measure the startup rate and take a boron sample.
- 6) Return the barked rode to the just critical position.
- 7) Establish criticality with rod program B-2.
- Actually, this rod program vill be run in reverse since the measure.
I ments vill begin with all rods out, i.e., rode 1, 3, 4, and 6 vill be completely withdrawn and rods 2 and 5 vill be banked to obtain criticality.
When rods 2 and 5 are completely inserted, then rods 1 and 6 vill be banked to l
obtain criticality with rode 3 and 4 completely withdrawn.
l Finally, rods 3 and k vill be banked to obtain criticality l
utter rode 1 and 6 have been completely inserted. -
- 8) Adjust position of rods 2 and 5 to establish rates of 0.2,05,and0.8 decade / minute.
Utilize rod 3 to limit:
the muimum flux level.
- 9) Return rods 2 and 5 to the just critical position.
Do an all mdt drop from a power level about 6 decaden above source level. Obtain as many nuclear detector traces as possible.
- 10) Establish criticality utilizing rod program B-1 (banked rods).
- 11) In the temperature coefficient measurement outlined im-mediately below, it is assumed that the temperature.coef-ficient is positive as predicted by analysis.
If during 1-2-62
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305.k: 7 the first step of this measurecent, it is round that the coefficient is negative, tien the procedure should be altered to begin with the startup obtained with all rods at 40 inches; then nr. ?.cmperature is increated, the corresponding decreases in startup rate should be measured.
When it becomes necessary to reduce pover level during the per:ormance of this operation, outlined here, do co by running in ordy control rod 3, and then running it tack out to the identical position it had prior to the level adjustment.
a) With the reactor just critical at about 3 decades above source level, increase the primary coolant temperature until a startup rate of about 0.2 decade per minute is attained.
Measure stable startup rate, temperature, and boron concentration.
b) Pepeat step (a) for startup rates of about 0 5 decade per minute and about 0.8 decade per minute, c) Run in rod 3 to lover power level to 3 decades above source and then adjust its position to just critical at that level. -Slowly lever the temperature of the primary coolant maintaining criticality by adjustin6 the position of rod 5.
When this rod reaches the position it had at the start of step (a) above, adjust the temperature to attain as nearly as possible a just critical condition, measure startup rate, if any, temperature and boron concentration.
- 12) Dilute the boron concentration 10 ppm and maintain criti-cality with banked rods, af ter mixing, obtain a boron sample.
- 13) Measure the stable rate with all the rods at the just critical position prior to the last dilution.
- 14) Adjust banked rods to establish startup rates of 0.2, 0 5, and0.8 decade / minute.
- 15) Return the banked rods to the just critical position.
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- 16) Establish criticality with rod program B.E.
- 17) Measure the etable startup rate with the control rods at the just critical position prior to the last dilution.
- 18) Adjust the position of the controlling rois (the n>ds that are partially inserted) to establish startup ratesof0.2,05,and0.8 decade / minute.
- 19) Return the controlling rods to the just critical position
- 20) Establish just critical with program B-1 (banked rods).
- 21) Bepeat in sequence steps 12, 13, 14, 15, 16, l'I, 18, 19, and 20 until the boron concentration is such ( 1380 ppm) that rods 2 and 5 in program B-2 are completely inserted.
- 22) At thic boron concentration, make the temperature coef-ficient measurements in the manner described in step 11.
Note that the rod bank position for just critical is now that obtained at the end of step 21. Analycis predicts that the temperature coefficient will change from positive to negative as the boron ccncentration is reduced and thus the temperature coefficient measure-e nt will eventually begin with the rods banked to give a startup rate of about 0.8 decade per minute.
Repeat this step when the boron concentration is about 800 ppm and at the minimum value.
- 23) Establish criticality.acconting to rod program B-3 24 ) Adjuet boron concentration, repeating in sequence steps 12,13,14,15,16,17,18,19, and 20 until criticaid ty t
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is obtais.ed with rods 1, 3, 4, and 6 at approximately 36 l
inches.
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- 25) Obtain approxitate axini flux traces.
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- 26) Withdraw rods 1, 3, L, and 6 to establish a startup rate of about 0.8 decade per rinute or to 40 inches whichever is reuched first.
If these rois bank at less than 40 inches, ndd boron in it4cre nents of about 10 p}nn until the ctartup rate is between 0 5 and 1 decade }er minute with codo 1 and 6 at 40 inches. Allow sufficient time for tre boror concentration te becote mif em it the primary system and then measure the startup rate and take a boron sample.
- 27) Return rode 1, 3, 4, and 6 to the just c itical position.
- 28) Do rod drop froo a power level atout 6 Lecades above source lesel. Obtain as many nuclear detector traces as possible.
- 29) Begent steps 12, 13, 14, 15, 16, 17, 18, 19, and 20.
- 30) Establish criticality according to the programed rod vithdrawal B-3
- 31) Meat,ure the stable startup ratt with rods 1, 3, 4, and 6 at just critieni position prior to the last dilution.
- 32) Withdraw rods 1, 3, k, and 6 to establish startup rates of 0.2, 0 5, and 0.8 decade per minute.
- 33) Peturn rods 1, 3, 4, and 6 to just critical position.
- 34) Establish just critical position with banked rods.
- 35) Repeat steps 12, 13, 14, 15, 16, 17, 18, 19, and 20,
- 36) Repeat steps 30, 31, 32, 33, and 34.
- 37) Repeat in eequence steps 35 and 36 until the boron con-centration is approximately 1280 ppm.
- 38) Establish criticality according to the programed rod 1
vithdraval B-4.
1-2-62
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- 26) Withdruv rods 1, 3, l., and 6 to establish a startup rate of about 0.8 decade per rinute or to 40 inches whicheve: is reached first.
If these rods bar.k at less than 40 inches, add boron in incremente of kboat 10 p;n until the startup rata is between 0 5 and 1 decade per minute with rods 1 and 6 at 40 inches. A11ov su ticient c
time for tre boron concentration te beco:re ur.iicrm it.
the primary system and then measure the startup rate and take a borcu sample.
- 27) Return rodo 1, 3, 4, and 6 to the just entical position.
- 28) Do rod drop from a power level about 6 decades above source lesel. Obtain as many nucicar detector traces as possible.
- 29) Repeat steps 12, 13, 14, 15, 16, 17, 18, 19, and 20,
- 30) Establish critienlity according to the programed rod withdrawal B-3
- 31) Measure the stable startup rate with rods 1, 3, 4, and 6 at just critical position prior to the last dilution.
- 32) Withdrav rods 1, 3, 4, and 6 to establish startup rates of 0.2, 0 5, and 0.8 decade per minute.
- 33) Beturn rods 1, 3, 4, and 6 to just critical pooltion.
- 34) Establish just critical position with banked rods.
- 35) Repeat steps 12, 13, 14, 15, 16, 17, 18, 19, and 20,
- 36) Repeat steps 30, 31, 32, 33, and 34,
- 37) Repeat in sequence steps 35 and 36 u.til the bo xn con-centration is approximately 1280 ppm.
- 38) Establish criticality according to the programed rod withdrawal-b 4.
1-2-62
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- 39) If necescary, adjust the boron concentration repeating in sequence stepa 35 and 36 until cri ticality is obtained with rods 2, 4, and 6 at approximstely 36 inches.
- 40) Ottnin appropriate axial flux traces.
- 41) Withdraw rods 2, h, and 6 to establish a startup rate of about 0.8 decade per minute or to 40 inches which-ever is reached first.
If these rods bank at less than 40 inches, add boron in increments of about 10 ppm until the startup rate is between 0 5 and 1 decade per minute with rods 2, 4, and 6 at 40 inches. Allow su'-
ficient time for the boron concentration to become uniform in the primary system and then measure the startup rate and take a boron sample, k2) Return rods 2, 4, and 6 to the just critical position.
- 43) Do rod drop from a power level about 6 decades above source level.
Obtain as many nuclear detector traces as possible.
- 44) Establish criticality according to the programed zod withdrawal B-5 I
- 45) If necessary, adjust the boron concentration until criticality is obtained with rods 2 and 5 at approxi-mately 36 inches.
- 46) Obtain appropriate e.xial flux traces.
- 47) Utilizing rods 2 and 5 instead of rods 2, L, and 6, repeat step kl.
- 48) Ecturn rods 2 and 5 to the just critical position.
- 49) Do rod drops from a power level about 6 decades above source level.
Obtain as many nuclear d<stecto.? traces as possible.
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305.41 11 NOTE: During the process of dilution, care must be exercised that the minimum shutdown restriction of 35 ok with all rods in or 1% ok with one rod stuck is met, whichever occurs first.
Rod drop measurements vill be made for the various rod patterns during the dilution process to assure the 3% shutdown is met.
Subsequent roi drops for rode 2 and 5 vill be made when the boron concentration j
is such that rods 2 and 5 bank at 27 and 20 inches. Using this in-formation and the attached integral rod worth curve, Pig. 1, as a guide, extrapolate to the height at which rode 2 and 5 would bank and still contain 5% Ak of shutdown.
This val.e of shutdown is based on the analytical prediction that one of the rode contains a maximum of 0.8 of the vorth of two rods. Verify that the reactor is shutdown by 1% by dropping one of the two center rods.
Do not dilute beyond the point where the measured shutdown is 3% vith all f
rods in or 1% vith on rod stuck.
- 50) Repeat steps 10, 12, 13, 14, and 15 l
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- 51) Repeat steps 16, 17, 18, and 19, 1
- 52) Repeat steps 30, 31, 32, and 33
- 53) Establish criticality according to rod program B-4.
54 ) Heasure the stable startup rate with rods 2, 4, and 6 at the just critical position prior to the last dilution.
- 55) Withdraw rods 2, 4, and 6 to establish startup rates of 0.2, 0 5, and 0.8 decade per minute.
- 56) Return rods 2, 4, and 6 to the just critical position.
- 57) Establish criticality accortling to rod program B-5
- 58) Measure the stable startup rate with rods 2 and 5 at the just critical position prior to the last dilution.
- 59) Withdrav rode 2 and 5 to ertablish startup rates of 0.2, 0.5, and 0.8 decade per minute.
- 60) Return rods 2 and 5 to the just' critical position.
g 1-2-62
305.4: 12
- 61) Repeat steps 10, 12, 13, 14, and 15
- 62) Repeat steps 16, 17, 18, and 19
- 63) Repeat stepo 30, 31, 32, and 33 64 ) Repeat steps 53, 54, 55, and $6.
- 65) Reieat steps 57, 58, 59, and 60.
- 66) Repeat in sequence steps 61 thru 65 until the boron concentration is such that the shutdown reactivity is 3% Ak with all rode in or 1% 6k with one rod stuck.
See note after step 49 During the sequence of steps, obtain appropriate flux traces aad rod drops when rods 2 and 5 are completely inserted and rods 1, 3, 4, and 6 withdrawn and when rods 2, 5, 3, and 4 are in.
serted and rods 1 and 6 are withdrawn.
- 67) ctop dilution.
- 68) Leave the reactor and system in the condition sIecified by the person in charge.
D.
Data Analysis Convert all startup lates to reactisdties.
1.
Void coefficient - calculate the chan6es in core reactivity for the case when 1) the fuel subassembly is removed and 2) the hollow can is inserted into the core.
The reactivity change of "2" divided by the amount of void involved (fraction of total core) yields the void coefficient.
2.
Rod group vorths - utilising data taken with boron constant, l
divide each incremental reactivity change as determined by startup rate measurements, by the corresponding incremental group movement, and average the results. Plot these averages as a function of group height.
The group height varies with boron concentration.
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Doron vorth. utilizing data obtained from startup rate and just critical measurements with the control rod group at a constant height, divide the incremental reactivity change by the change in boron concentration as the moderator is diluted.
Plot this incremental boron worth as a function of boron concentration, 4.
Emperature coefficient - utilizing data obtained from startup rate and just critical measurements with the rod position and boron concentrations fixed, divide the in-cremental reactivity change by the change in temperature.
5 Using the rod drop data and analytical rod drop information, obtain the shutdown vorths.
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c ( PRE-OPERATIONAL TEST 305.$ TITLE: Tenerature and Pressure Coefficients at Shutdown Boron Concentration A Approvals Procedure Date 11-15-61 P Technical Approval E d f jg-nde
- 4 Accepted for Saxton I
No. Date g Experimental Program 4 ff;,'} h. ENEC Approval N , q.v: r o $ t '43:'y . 3
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I J\\ FJC 0rERATIONA1. TEST 305 6 T3?LL: Control flod, Boron and Void Worth Detert:.ination at 0; crating Ternperature ,s .sa 4 ~ ) Arrrovnic ProcedureDate1k-6b Technical Approval /- Addenda legy. ~J Accepted for Saxton A/ No. Date Experimental Proernn
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SNEC AIproyal ? "/N My. 947 ( 'Q ,,lmNhs l - {. l . s n.tgC;h
FRE-OPERATIONAL TEST 305.6 CONTROL ROD W3RTH. BORON AND FIDW WORTH AT OPERATING TEMPERATURE I. Objective: To determina, at operating temperature and pressure, the vorth of banked and progracr.ed rods, boron vorth, coolant flow worth, and the temparature e. efficient as a function of borun concentration. II. Conditions: 1. This test procedure has been thoroughly discussed with and under-stood by operating personnel. 2. Satisfactory completion of Pre-operational Test 305 5 3 Special nuclear instrumentation, section IV-a belov, is installed and checked out 4. }hin coolant system is at amoient pressure and temperature and contains sufficient boron for 5% shutdown with rods inserted. 5 Pertinent auxiliary systems are in the following status: SYSTEM STATUS i Pressure Control and Relief Ready for startup 0.I. 410 Charging and Volume Control Ready for startup 0.1. 411 Reactor Control Ready for startup 0.I. 412 Nuclear Instrumentation Normal Operation 1 0.I. 413 Badiation Monitoring ?lormal Operation 0.I. 414 Boric Acid Addition In operation as required 0.I. 4 17 Boric Acid Removal In operation as required 0.I. 418 ( l 4.62
i. { L i 3 TIM k"JRTH AT OPERATING TDTERATURE Ane, at operating temperature and pressure, the banked and programed rode, boron vorth, coolant
- h, and the temperature coefficient as a function concentration.
ture has been thoroughly discussed with and under-ing personnel. 3rpletion of Pre-operatioral Test 305 5 t instrumentation,.section IV-a below, is inctalled t yotem 10 at ambient pressure and temperature and Leient boron for 5% shutdown with roots inserted. 111ary eystems are in the following status: ID4 STATUS
- .rol and Relief Ready for stsrtup
. Volume. Control Ready for startup t rol' '
Ready for startup itre. mentation Normal Operation Monitorin6 Normal Operation d Addition In operation as required id Removal In operation as required 3
.11y roda 3 and L vill be banktsd to obtain criticality (if peasibic) l after rods 1, 2. 5, and 6 Lavo 'been completely inserted.
l 17 (No entry) i l
- 18. Adfas+ perition of rods O and 5 to establish startup rates or 0.2, 0 5, and 0.8 d M e/ minute.
Utilir.* l rod 3 to limit the raximw2 fluc le'cel. l l 1.1. 62 1 l j L__
1 305 6: 7 l l 19 Return rods 2 and 5 to tha just critical position. 20. Do an all rods drop from a power icvel about 6 decades atsove source level. Obtain as many nacier traces as possibic. 21. Estatlish criticality according with rod program A-1. l 22. In the temperature coefficient measurement outlined l 1 immediately below, it is assumed that the temperature i coefficient is negative as predicted by analysis. If during the first step of this neasurement, it is found that the coefficient is positive, then the procedure i should be altered to begin with the startup rate obtained vith all rods at LO inches; then as temperature is de-creased, the corresponding decreases in startup rate should be censured. When it becomes necessary to reduce l power level during the performance of the operation out-lined here, do so by running in only control rod 3, and then running it back out to the identical position it had prior to the level adjustment. l a) With the reactor just critical at about 3 decades abova source level, decrease the prinary coolant' temperature until a startup rate of about 0.2 decade per minute is attained. Measure stable startup rate, te.aperature, and boron concentration, b) Repeat step (a) for startup ratec of about 0 5 decade per minute and about 0.8 decade per minute. c) Run in rod 3 to 3over power level to 3' decades above source and then adjust its pocition to just critical at that level. Slowly raise-the temperature of the prinary coolant maintair.ing criticality by adjusting the position of rod 3 When this rod reaches the-( 1 L-62 l l l 1 ~.--.,-n.- -.---._~.-.--e,--,-..--- ...nn-,---, ,,,-,-w, --,n -e,.---,.- -,---m.n,e n,, m,,,, ,,-a..m.-r,, ,w,-,, n., ,.wr,.,,n.w-.--
305.6 8 position it had at the start of step (a) above, adjuct the temperstnre to attain no nearly an possible a just critical condition, meacare rtartup rate, if any, temIersture, ar.d boron concentration, d) Fepeat the ter}erature coe:ficient measurement when the toron concentration is 800 ppm. 23 Dilute the boron concentration 10 ppm and maintain criti. cality vith bant.ed rods, af ter mixing, obtain a boron sample. 24. Measure the stable startup rate with all the rods at the just critical position prior tc the last dilation. 25 Adjust roda to establich startup ra+en od - 0.2, 0 5, and 0.8 decade /minu+e. 26. Return the rode to the J.ct critical pcsition. 27 Establich criticality with rod program A-2. 28. Meneum the startup rate with the controlling rods (tre rods that are partially ir.eerted) at the just critical position prior to the last dilution. 29 Adjust the position of the controllias rods to establish startup rates of 0.2, 0 5, and 0.8 decade / minute.
- 30. - Return the controllinC rode to the just critical position.
31. Fepeat in sequence steps 21, 23, Ch, 25, 26, 27, 28, 29, and 30 until the boron concentration is such f=590 ppm) that rods 2 and 5 in program A-2 are completely inserted. 32. Fepeat step 21. 33 At this boron concentration, make the temperature coer. ficient trasurements in the manner described in step 22. Note that the rod bank position for jtst critical is now that obtained at the end of step 32. Pepeat this step v5en the boron concentration is at the minimum value. l 1 L-62 s i
305.6: 9 i 34. Establish criticality according to the progro;ned rod withdraval A-3 35 If necessary, adjust boron concentration, repeating in sequence steps 21, P3 *hru 30, and 34 until criticality is obtained with rode 1, 3, h, ant. 6 at approximately 36 inches, and rods 2 and 5 inserted. 36. Obtain appropriate axial flux t races. 3'i. Withdrav rods 1, 3, 4., and 6 '.o entablish a startup rate of about 0.8 decade per minute or to 40 inches whichever is renched first. If these rods bank at lens than 40 inches, add bsron in increments of about 10 ppm until the startup rate is between 0 5 and 1 decade per minute with rods 1,3.h,6 at 40 inches. Allow sufficient time for the boron concentration to become uniform in the primary system and then measure the startup rate and take a boron sample. 38. Return rods 1, 3, h, and 6 to the just critical position. 39 Do rod drop from a power level and 6 decades above source level. Obtain as many nuclear detector traces as possibic. 40. Repeat steps 21 and 23 thru 30, 41. Establish criticality according to the progracmed rod withdrawal A-3 i
- 42. Measure the stable startup rate with rode 1, 3, 4, and 6 at just critieni position prior to the last dilution.
43 Withdraw rods 1, 3, 4, and 6 to establish startup rates of 0.2, 0.5. % d 0.8 decade / minute. 44. Return rods-1., 3, 4, and 6 to the just critical position. 45 Repeat steps 21,and 23 thru 30. ( 1.h.62
l 305.6: 10 l h6. Repeat steps 41 thru hh. t 47 Repeat in sequence steps 45 and 46 until the boron concentration is approximately 500 ppm. l 48. Establish cri' according to the programmed rod l vithdraval A 1 l l 49 If necessary, 3.. ; , the boron concentration repeating in sequtince steps h5 and 46 until criticality is obtained i l vith rods 2, 4, and 6 at approximately 36 inches. l
- 50. obtain approprjate axial flux traces.
- 51. Utilizing rods 2, 4, and 6 instead or rods 1, 3, 4 and 6, repeat step 37
- 52. Return rodo 2, k, and 6 to the just critical pocition.
53 Do rod drop from a power level about 6 decades abcve source level. Obtain as many nuclear detector traces as possible. 54. Establish criticalit." according to the progracaned rod withdrawal A-5 1 l 55 If necessary, adjust the boron concentration until criti-cality is obtained with rode 2 and 5 at approximately 36 inches.
- 56. Obtain u.ppropriate axial flux traces.
57 Utilizing rods 2 and 5 instead or rode 1, 3, 4, and 6 repeat step 37 j 58. Return rods 2 and 5 to the just critical position. l 59 Do rad drops from a power level about 6 decades above l source level. l Obtain as many nuclear detector traces as possible. 1-4-62 t
- _ _ - -.-._.-.-.-~~_.- - 305.6: 11 NOTE: During the process of dilution, care must be exercised that the minimum chutdown restriction of 1% Ak with one rod stuck is met. Subsequent rod drops for rods 2 and 5 vill be cade when the boron concentration is such that rodo 2 and 5 bank at 25, 20, and 15 inches. Using this information and the attached integral rod worth curve, Fig.1, as a guide, extrepolate to the height at which rods 2 and 5 would bank and still contain 5% Ak of shutdown. This value of shutdown is based upon the analytical predicition that the nnximum worth of one central rod is equal to OA the worth of the two centN1 rods. Do not dilute beyond the concentration which would have rods 2 and 5 bank at tho extrrpolated position, but go to step 26 directly from there. 60. Repeat steps 21 and 23 thru 30. 61. Bepeat steps 21, 42, 43, and 44. ( 62. Establish criticality according to the programmed rod withdrawal A 4. 63 Mensure the stable startup rate with rods 2, 4, and 6 at the just critical position prior to the last dilution. 64. Withdrav rods-2, 4, and 6 to establish startup rates of 0.2, 0.5, and 0.8 decade / minute. l l l 65 Return rods 2, 4, and 6 to the just critical position. 66. Establish criticality according to the programmed rod withdrawal A-5 67 Measure the stable startup rate with rods 2 and 5 at the l just critical position prior to the last dilution.
- 68. Withdraw rods 2 and 5 to establish startup rates of 0.2, -
0 5, and 0.8 decade / minute. 69 Return rods 2 and 5 to the just critical position. ( l l 4-62
305.6: 12 NOTT: During the sequence of stepq obtain, if possible, appropriate flux traces when the :ontrolling rods for each of the rod programs e.re about half way inserted. Obtain banked red (program A-1) drop measurements when the boron concentration is about 600 and 400 ppm. 70. Repeat ste;r 21, 23, 24, 25, and 26, ~ 71. Repeat steps 37, 28, 29, and 30. 72. Repeat steps 41, 42, 43, and 44. 73, nepeat steps 62, 63, 6h, and 65 74. Repeat steps 66, 67, 68, and 69 75 Repeat sequence steps 70 thrv 74 until the boron conet 9-tration.is at lowest practical value or such that the note after step 59 is just satisfied, i NOTE: The following steps 76 thru 87 vill be utilized to determine in a safe experimental manner the maximum withdrawal of one of the center rods which can be made and still have the shutdown re-quirements met with that rod stuck at that position and all the other rods fully inserted. The con-ditions for a 2% shu+down limit will be detercined e for use in setting rod withdrawal limits during the early phases of power operation. Then, by extrapolation, the conditions for a 1% shutdown vill be determined for setting rod'vithdrawal limits during the remainder of the hot, zero power 4 experiments with low boron concentrations. { 1.h-62 ---ww__--_-_-____
305.6: 13
- 76. Attain criticality with rod program A 1 (ban).ed rode and with boror, concentration obtained at the end ot step 75 or an earlier step if necesser.r to meet the re.
quirements of the note after s.ep 50 Ievel the reactor ot 3 decades above source level. 77 Withdraw control rod 5 an are nt suiticient to gire a startup rate and record it together with all cont rol rod positions. Level t!e reactor at atoct fi decades above source level by ranning in rod 5 and record the data listed in section 3Y-B.
- 78. Drop all rods except No. 5 and obtain recorder traces or the outputs of as.nany nuclcar detectors as poor 1ble.
From these recorder traces, obtain a best value tot-the shutdown. 79 If the shutdown obtained in step 78 is 3% or greater, proceed directly to step 80. If the shutdown is less than i 3%, then add sufficient boror to secure 3% or more shut-down. To do this, obtal" a preliminary value of the ^ toron vorth using data from step 70, or its most recent repetition in step 75, and the data analysis procedure given in section E 3 below. Tren calculate the ame z.t of bcron necessary to increase the sh.tdce to 31 Add this quantity of boron to the primary coolant eye *cr, - bring the reactor to critical with all rods banked and at a level of about 3 decades above source le-el. Nput steps 77 and 78. If the shutdovn is stil_1 less 1her 3%, repeat the boron addition and stutdovn check ur.til that amount of shutdown is attained. 80, Determine the amount by v51eh contrcl rod 5 ste ad te withdrawn from its position in step 77 or 701r orde-to Antroduce an amount of additional reacti'-ity equal to ore q arter of the difference between the shutdovo reactiuty obtaired in step 78 or 79 and 2%. In making this deterzi-( nation, use Fig.1 as an apprcximate integral rod voM,h curie and assume that the total verth of rod 5 is 6%. 1 L 62 w
=_ 305.6: 1h 81. Withdraw rod 5 the amount determined in step 80. Bring the reactor critical by banking the remaining rods and level off at about 3 decades above source level. Repeat steps 77 and 78.
- 82. Using the data obtained in steps 77 or 79, and 61, obtain incremental vorths for rod 5 according to the procedure given in csetion E-2 below, plot these as a function of the position of rod 5 and graphically integrate the plot to obtain the reactivity addition represented by the with-dravul of No. 5 in step 81.
Compare thic value of re-activity with the difference between the shutdown values obtained in steps 78 or 79, and 81. If these differ by more than the estimated experimental uncertaintics, attempt to resolve the discrepancy before proceeding. 83 Using an extrapolation of the incremental rod worth curse obtained in step 82, determine the amount that rod 5 should be withdrawn to introduce an amount of additional reac-i tivity which is equal to one third the difference betveen the shutdown obtained in step 81 and 2%. Withdraw rod 5 by this aLount, then bring the reactor critical with all the remaining rods in a bank and icvel off at about 3 decades above source level. Repeat step 77 and 78. 84. Repeat the data analysis outlined in step 82 using the data obtained in step 83 Add this incremental rod verth to the curve and extrapolate to obtain the amount that rod 5 should be withdrawn to reduce the shutdown in the remaining rods to 2%. Withdrav rod 5 by this amount,_ bring the reactor critical with all the remaining rods in a bank and level of f at about 3 decades above source level. Repeat steps 77 and 76. 85 If the shutdown obtained in step 84 is greater than 2%, repeat the procedure indicated in that step until 2% shutdown is attained. ( 1 h-62 s )
305.6: 15 ti6. If during the perf ormance of steps 81 thru 85, control rc>d 5 reaches its upper limit and if the boron concen-tration is greater than the minimum practical value, then substitute boron dilution in place of rod $ vith-drawal as the means of reducing the shutdown of 2%. For the boron dilution, use the procedure given in steps 23 thru 26 vith the exception that rod 5 is left fully withdrawn. 87 If the 2% shutdown limit is reached before control rod 5 is fully withdrawn, use the procedure outlined in step 82 and all the data obtained in steps 77 tnru 85 to plot in-cremental and integral rod worth curves. Extrapolate these curves to obtain the position of rod 5 which will leave 1% shutdown available when the reactor is critical with rod 5 at that position and the remaining rods banked. Set the rod withdrawal limits at that position on control rods 2 and 5 during any future preoperational experiments performed at operating temperature, and low boron concentrations. 88. Bring the reactor critical by banked withdrawal of all rods except No. 5 Level off at about 6 decades above source level. Then drop all control rods obtaining recorder traces of as many detectora as-possible. 89 Leave the - reactor and its auxiliary systems in _ the con-dition specified by the person in charge. E. pata Analysis 1. Flow Worth--using the data obtained in steps D-3 thru 9 with the startup rate measurements converted to reactivities, divide each incremental reactivity change by the correspon-ding change in main coolant-flow to obtain the flow worth coefficient. Plot these results as a function of flow. 2. Control Rod Worths--for each incremental rod worth measure- { ment,' divide the incremental reactivity change by the 1 4-62 ~
305.6: 16 corresponding rod position change. Plot the results as a function of rod position using the average of the rod position at each step. Graphically integrate the re-sulting cu2 'e to obtain integral rod vorth and plot this as a function of rod position. From the data obtained during boron addition and dilution, plot boron concen-tration as a function of rod position. Using the boron worths obtained in step E-3, convert boron concentration to reactivity and plot ac a function of rod position. The data for program A-1 vere obtained in steps 10,11, 13,14, 21, 23, E4, 25, 26, 31, 35, 40, 45, 47, 49, 60, 70 and 75 The data for rod program A-2 vere obtained in steps 16, 17,. 18, 19, 27, 28, 29, 30, 31, 35, 40, 45,. 47, 49, 60, 71, and 75 The data ror rod program A-3 were obtained in steps 34, 35, 37, 38, 41, 42, 43, 44, 46, 47, 49, 61, 72, and 75 The data for rod program A-4 were obtained in sters 48, 49, 51, 52, 62, 63, 64, 65, 73, and 75 The data for rod program A-5 vere obtained in steps 54, 55, 57, 58, 66, 67, 68, 69, 74, and 75 3 Boron worth--utilizing the incremental boron vorth data were obtained in steps 11 or 13, 23, 24, 28, 31, 35, 40, 42, 45, 46, 47, 49, 51, 55, 57, 60, 61, 63, 67, 70, 71, 72, 73, and 74, divide the incremental changes in reactivity by the corresponding incremental changes in boron concentration for each rod program. Plot the corresponding incremental boron worths as a function of the average boron concen-tretion at each point. Graphically integrate the resulting curve to obtain the integral boron vorth as a function of boron concentration. 4. Temperature Coefficient--using the data obtained in steps 22 and 33, divide the incremental changes in reactivity ( by the corresponding incremental changes in temperature. Average the results obtained at each boron concentratica [ and plot these average temperature coefficients as a function of boron concentration. 1 4-62 l
305 6 17 5 Shutdown--using the rod drop data and recorder traces obtained in steps 15, 20, 29, 53, 59, 78, 79, and 83 thru 88, and the analytical rod drop information, obtain the shutdown worths for the various reactai conditions repretented. NOTE: In the data analyses outlined above, it has been assu:ned that all variables have been held constant except those involved in the corresponding measurement. In practice, this vill not always be the case. Therefore, it vill be necessary to correct for the unwanted perturbations. For example, if the temperature varies during the boron worth measurements, the change in temperature together with the corresponding tempersture coefficient must be used to correct the observed reactivity changes to obtain the proper values for use in determining the boron vorth. ,y
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( PRE-OPERATIONAL 305 7 TITLE: Tecperature and Pressure Coefficient Determination at Lov Boron Conecatration s e ( i AI l. / Approvals p Precedure Date 11-15-61 1 Ez frechnical Approval I h. Addenda- / hcceptedforSaxton 4 ? No.- 'Date (, Experimental l'rogram ~ a-s l ?>qv n SNEC Approval ' ' + ' +E
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k 4 FRE-OPERATIONAL TEST 305 6 TITLE: Instrumentation Response at Low Power s., M '., pw.+L - ~.4;.; w::s -., t. g< r 4 A !$h ^ ,o Approvals Procedure Date 1 M b2 g Technical Approval Addenda v Accepted for Saxton 4 N,,o. Date pp 27 Experimental Program 1 4 W 4* W -" ~.W g i& git y ' s%.. %;t;l:- Q.:w..t-ge q,4 %gm..- p-c.s SNEC Approval, .c. ~. g d g4 'y ~ ', 'iyj, -e 7 e 1
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FFI-OPERATIONAL TEST FC. 305.8 INTGUMENTATION FISP0XSE AT I_fW PMER I. Object 1*.e : To correlate data obtained during tre course of tbc other Pre-Operational Tests in order to detemir.e tbc response and penormance of the nuclear detectors under various reactor conditions as fcllows: A. BF-3 Detector - Response to source and detector positionin6s neutron multiplication and Main Coolant condition. B. Ion Chambers - Fesponse of interMie 'ange CIC's and pcver range IC's to control rod movement and progracing, detector location, flux level and changes in Main Coolant condition. C. Preliminary Power Calibration of the ion chambers to serve en a guide until a more precise power calibration is made during the initial tests at power. II. Conditions: The conditions applicable to proced' en 307:.1 t5 305 7 also apply here, since the measurements vill be made du-ing the perfomance of these procedures. III. P*ccautions: 1. See applicable procedure 'or precautions. 2. Observe nomal operating restrictione with rege.rd to use of the detectors. IV. Instructions: A. gocedural Method - Since the measurements ner.eesary to saticly the objective vill be done durin6 the pcr.%rmance of procedures 305.1 thru 305 7, the perforrance segunce, section C belov, vili refer only to the instructions in the appropn ste procedues. E. Special Instrumentation Pequirements: Tbc necessary instrumentation is listed in the appropriate procedures during which these-. messix e-ments were made. ( JAN - 4 iDL? f l I
~. 305.8; D C. Peafo. w ee Seq;cnce 1. Normal Plant E-3 Pesponse: (a) Ref er to 305.1, l'i-L, steps J R and P9 for the cM eet of soarce and bi-3 placemnt upor B -3 m ponsc. (b) During 305 3, r.-D, step 11, obtain the cotet rates as a f unction of time and comparc vith +he CIC lesel indi-cations (sectic '-a te3 W Det er:. ire if a one or two decade overlap exists between the startup and intermediate ranges and if the time rate of change of level, i.e., start-vp rate, is the same f or all detectors irrrolved. (c) From the control Eod and Boron WortF Detertina+ ion portier o 305.h, ';!-c, step 2, obtain the delay tine 1 rom ber'on injaction to B:-3 zesponse. (d) :r eder tc detemi'e the c 'fect of Nit w el ter - perstm and boron concentration 'h ral.tiw outp
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2 obta1Nd { of the BI-3 detectors, compa:e BF-3 courn in 305 3, Tc-D, step 2 (Ambimt Temper 9t' re and Fresrej Loeding Be*cn Ccncentration) wit' 3C,5 5, TJ.D, step 25 (585* :, 2100 pss, _c ding Boron Concentration., and sleo with 305 7, r. -p, stup PS (585= :, 2000 psi,..e.r Lc on Ccoct.nt raticr.). he co r t -'d .c to be ec:pn ed n* t ra equilibrius shutdcyn ccant. rates obtsine.d vith 5t11 Tcd9 in. 2. Ion Cuder ;eopenscs,: (a i Iro: 305 3, !Y-d, stcps 10 and 11, obtain the C;C responeos to control rod movement and ilux level changes. (b) From 305 3, TI-D, steps 13,16, and 17 obtsi- "
- elutsee outpute f rom the intermediate and power ra ge icn chaders for each of the indicated rod prog-am coni'igurations. In oM ei n. g +Pese data, the ultra-sens$ tive micro-microameter vill be used ar.d the outputs of the various ion chambers will N seq 2entially connected to that instrum nt.
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a 305.8-3 (c) Trom 305 3, Appendix I-3, obtain the response o# an ion chamber as a function or its radial and axial position. (d) In order to determine the efects of Main Coolsnt tem. perature and pressure, and bcron concent ra+1or on t he i relative outputs of the 1on chsabers, the resul+s f rom 1 d above vill be used together with data f rom 305 3, 1 305 5, and 305 7 Ite reactor vill be operated at a pov3r level cuch that both the BI-3 detectors ar.d inter-mediate range ion chambers are giving satisf actory duta. The BT-3 detectors vill serve as monitors. obtain the data for ambient temperature and pressure, and Icading bcron concentration f rom 305 3, IV-D, step 12; the data for 585* F, 2100 psi and loading boron concent stion f rom 305 5, IV-D, step,, and the data for 585* I, 2000 psi and low boron concentrarion f rom 305 7, IV-D, step 25 ( 3 Preliminary Power Calibration - From Appendix I-l of 305 3, obtain the gold foil activity resulting from the irradiation along with the irradiation time and nuclear instrumentation readings obtained during the irradiation of the gold foil. Also obtain the corresponding axial flux distribution mens;.:e-ments obtained with the special and normal flux vires. I D. Data Analysis 1. Using the data from step C-1-a, tabulate the BT-3 cour.t rate as l a functione detector and source-position. 2. Using the data f rom steps C-1-b and C-2-a, plot the BT-3 and ica chamber outputs as a function of time. 3 Using the data in step C-1-d, tabulate the equilibrium shut-down count-rates as a function or Main Coolant condition. ( 1 i 1 .~ ~ - -
305.8: 4 4. Using the data from step C-E-s, dete:mine the linearity of each of the ion chamber channels used. If any significant deviations from linearity are noted, correct this deficiency before using the corresponding channel to obtain subsequent data. This evaluation should be made and corrective action taken, if needed, i= mediately after the data for step C-2-a are taken. 5 Using the data from step C-2-b and the cermspondinr,experi-mental and/or analytical flux distribution determinations for the various control rod program configurations, establish the correlation between the relative outputs of the ion chambers and the power distribution within the core. If this cor-relation is good enough, the relative outputs of the ion chambers can be used to detect the presence of flux tilts in subsequent operations. 6. Using the data from step C-2-c, tabulate the ion chamber
- output as a function of axial position and as a function of radial position. These Itsults will show how the neutron flux variec in the region involved.
7 Using the data from step C-2-d, cormlate the variations in Main Coolant temperature and pressute with the relative readings from the various detectors. Use the Br-3 count rates together with the results of step 3 above to normalize the ion chamber readings at each of the temperature and prescure conditions. In a similar manner, correlate the vari-ations in Main Coolant boron concentration with the various detector readings. These correlations will be used to correct subsequent measurements, e.g., power level determinations, for such variations in Main Coolant conditions. 8. Using the data from step C-3, convert the gold foil activity .i 9
o 305.8: 5 and flux distribution measurements to the average power level. Divide the ion chamber current readings by the power level to obtain the power calibrations. These calibrations are to be used only as preliminary values. '1 rey should be corrected when different control rod patterns, boron concen-trations and/or temperatures are used. These co :t<tions can be obtained frc: "Pe resdts of steps 5 and 7 above, e l' 4 i _ __}}