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Rev. 21 06/06/85 (HKC 08/29/86) w, =. - . . - . .
Document Section l- N P O R .'.i A T ! O N O N L
_ C. R. Nuclear 52K4MttsurgguEN-OPERATING PROCEDURE OP-210 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 REACTOR STARTUP THIS PROCEDURE ADDRESSES SAFETY RELATED COMPONENTS t
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APPROVE 0 BY: Responsible Section Superintendent /
l Supervisor QA4 $0 Date &//SllP5~
INTERPRETATION CONTACT: Nuclear Operations Supt.
8703160147 870305 PDR ADOCK 05000302 p PDR
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HKC 08/29/86 1
1.0 PURPOSE 1.1 To provide the steps necessary to take the reactor from a 1 It A k/k shutdown condition (Operational Mode 3 - HOT STANDBY) to a critical condition at approximately 10-8 amps on the intermediate range nuclear instrumentation (Operational Mode 2
- STARTUP).
OPERATION SECTION Criticality on Control Rods 6.2 Criticality by Deboration 6.3 ECP/ECB Calculations 7.0
2.0 DESCRIPTION
2.1 RECOMMENDED CRA CONFIGURATION FOR CRITICALITY 2.1.1 The control rod assembly (CRA) configuration shall be within the limits of Standard Technical Specifications (STS) 3.1.3.5 and 3.1.3.6 while allowing sufficient rod worth to overcome the effects of Xenon and Doppler transients.
3.0 REFERENCES
3.1 OP-304, Soluble Poison Concentration Control 3.2 OP-502, Control Rod Drive System 3.3 OP-402, Makeup and Purification Sys*em 3.4 Technical Specifications 3.5 OP-103A, Operating Curves 3.6 OP-103C, Reactivity Worth Curves OP-210 Page 1 Rev.h b 1
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HKC 11/19/85 I 4.0 LIMITS AND PRECAUTIONS 4.1 If any condition exists which physically or administratively delays criticality, the reactor will be maintained shut down by at least 1\6 k/k while the condition is being corrected.
4.2 To ensure that the rod group withdrawal limits are not ex- ,
ceeded, the reactor coolant system (RCS) boron concentration shall not be reduced to a concentration that would cause the reactor to be critical with the control rods withdrawn a lesser
. amount than permitted by these limits. This condition could exist due to Xenon burnout during an increase in power under high Xenon conditions.
4.3 The axial power shaping rods (ASpR's) will normally remain at the position from the previous shutdown.
4.4 the maximum stable startup rate is 1 dpm.
4.5 The RCS lowest loop temperature (Tavg) shall be > 525'F any time the reactor is critical.
4.6 The maximum and minimum pressurizer level any time the reactor is critical is shown by Curve 5 of Op-103A, Operating Curves.
Immediately increase sakeup flow if pressurirer level falls be-low minimum level.
4.7 If it is desired to bring the reactor critical by deboration, the control rods shall be positioned per Step 2.1 of this p' toc- .
edure prior to any reduction in the baron concentration of the RCS.
OP-210 Page 2 Rev. 21
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' 4.8 There must be at least three (3) RC pumps (RCP's) in operation during operations in Modes 1 and/or 2.
4.9 Manually trip the reactor if:
- a. Two (2) or more main steam isolation valves (MSIV's) are closed,
- b. Pressurizer level goes above 290-in.
4.10 The calculated estimated critical rod position (ECP) i 1.05 Ak/k shall be within the limits of Technical Specification 3.1.3.6 4.11 It is very important that the algebraic signs and units of all reactivity component values be maintained correctly.
4.12 An ECP or estimated critical boron (ECB) should be calculated before each approach to criticality.
4.13 In the event there is a discrepancy in the calculation or acq-uisition of core physics data (i.e., Xenon, Samarium, core re-activity, etc.) the Reactor Specialist shall be requested to provide the necessary information 'needed to produce an accurate ECP or ECB.
5.0 SET POINTS 5.1 SOURCE RANCE INSTRUMENTATION 5.1.1 Hi Startup Rate Rod Withdrawal Limit: 2.0 dpm Reset: 1.0 dpm 5.2 INTERMEDIATE RANGE INSTRUMENTATION 5.2.1 Hi Startup Rate Rod Withdrawal Limit: 3.0 dpa Reset: 1.0 dpa OP-210 Page 3 Rev. $1
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HKC 05/22/86 I 5.2.2 Hi Startup Rate Bypass: 10-9 amps Reset: 5 x 10-10 amps 5.2.3 Source Range Hi Voltage Cut-Off: 10-9 amps Reset: 5 x 10-10 amps 6.0 REACTOR START'JP Initials 6.1 INITIAL CONDITIONS 6.1.1 All conditions are satisfied to enter Operational Mode 2 (STARTUP) per SP-440, Unit Startup Surveil-lance Plan.
6.1.2 OP-202, Plant Heatup, has been completed.
6.1.3 A minimum of two (2) licensed Operators are available and in the Control Center during reactor .startup.
6.1.4 Approval has been granted to take the reactor crit-ical by the operations Superintendant or Man-on-Call.
6.1.4 1 For a reactor startup following a reactor trip, AI-704, Enclosure (1) has been completed and authorizes a reactor startup.
6.1.5 Reactor startup authorized by shift Supervisor.
6.1.6 Record the startup time and number on Enclosure 3 (for ECP) or Enclosure 4 (for ECB).
6.2 PROCEDURE CRITICALITY ON CONTROL RODS 6.2.1 Perform two (2) ECP calculations per section 7.0 of
+ this procedure. These calculations shall be perform-ed by two (2) different persons independently.
i, OP-210 Page 4 Rev. b b
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Initials 6.2.1.1 Both ECP's shall be in agreement (10.1% Yk/k) prior to proceeding with the startup. Transpose results to Enclosure 3, Table 1.
6.2.1.2 Ensure the critical rod positions are within the limits of Section 2.1 of this procedure.
6.2.1.3 Attach a copy of any computer calculation utilized to determine Xenon or Samarium reactivities to Enclosure 1 or 2.
6.2.2 If not already accomplished, withdraw the safety groups to their upper limits per OP-502, control Rod Drive System, Section 9.1.
6.2.3 Reset Post-Trip Review Summary by having the computer print it out.
6.2.4 Verify lowest loop T(ave) is > 525'T a minimum of 15 \
min. Prior, to achieving criticality. Record on SP-390. ,
6.2.5 Deborate the RCS to- the desired precritical concen-tration by performing the following:
- a. Determine the volume of desineralized water re-quired per OP-304, Soluble Poison concentration Control, Section 6.3, Page 7. ,
NOTE: Criticality will be anticipated during the bleed and feed operation.
OP-210 Page 5 Rev. 21
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HKC 02/24/86 l -
Initials
- b. Perfora a bleed and feed operation per OP-402, Makeup and Purification System, Section 11.
6.2.5.1 Announce over the PA system that ' REACTOR STARTUP IS IN PROGRESS
- NOTE: Criticality will be anticipated at all times during rod withdrawal. The Rod position at which criticality is achieved shall be within the limits of the i 1.05.dk/k rod positions of Enclosure 3 (Table 1).
6.2.5.2 Withdraw the regulating rods, in sequence per OP-502, Control Rod Drive System, Section 9.2, until criticality is achieved.
6.2.5.3 While withdrawing the regulating rods, verify the following:
- a. The intermediate range instrumentation is on scale and indicating prior to the source range instrumentation indicating > 105 cps, j b. The regulating rod group overlap between Sequen-tial Groups 5 and 6 and 6 and 7 is 25 5 $. . .
6.2.5.4 If the reactor is critical proceed to Step 6.2.5.6 of i this procedure.
OP-210 Page 6 Rev. 2M- -
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- Initials 6.2.5.5 If reactor is not critical or critical prior to the limits of the ECP, perform the following
- a. Insert regulating rod groups and ensure > 17. ak/k ,
- b. Verify the boron concentration.
- c. Recalculate tne ECP per Section 7.1 of tnis pro-cedure.
NOTE: This calculation should be performed by anotner individual. /
- d. If an error in tne ECP was found, record tne applicable data on Enclosure 3. Repeat Steps 6.2.5.1 through 6.2.5.4
- e. If no error can be found in the ECP, notify tne Reactor Specialist for appropriate action to con-tinue the startup.
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i j NOTE: Any further action taken to achieve criti-cality beyond the scope of this procedure snall have concurrence by tn'e Reactor Special-
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l ist, Shift Supervisor, and Operations Superin-1 tendent (or the man-on-call).
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6.2.5.6 Increase reactor power to 10 8 amps on the intermed-iate range instrumentation. Establish steady state conditions at 10 8 amps and record the following:
NOTE: This step should be performed as expeditiously as possible (without exceeding i dpm) in order to minimize the error induced by transient Xenon between these control rod positions and actual critical rod, positions.
- a. Rod Positions: Groups 1-4 100 .
Group 5 .
Grou p 6 %
Group 7 .
Grou p 8 .
- b. Baron Concentration: ppm 8
- c. RC Average Temperature: 'F
- d. Time Criticality Conditions Established:
6.2.5.7 Send a xerox copy of this completed procedure to the 19 Reactor Specialist. 19 6.2.5.8 Depending on planned operation, i .e. , trai ni ng, phy- 19 sics tes ti ng , shutdown, or startup into the power 19 range, continue in accordance with the appropri ate 19 Operating Procedures. 19 Shift Supervisor Date OP-210 Page 8 Rey! 21
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HKC 02/24/86 I
Initials 6.3 CRITIritITY BY DEBORATION 6.3.1 Perform two (2) ECB calculations per Section 7.0 of this procedure. These calculations shall be per-formed by two (2) different persons independently.
ECB #1 ECB #2 NOTE 1: Both ECB's shall be in agreement (1 0.1\)
prior to proceeding with the startup.
Transpose results to Enclosure 4, Table 1.
NOTE 2: Ensure the critical rod positions are within the limits of Section 2.1 of this procedure.
6.3.2 If not already accomplished, withdraw the safety groups to their upper limits.per 0p-502, Control Rod Drive System, Section 9.1.
6.3.3 Reset post-Trip Review Summary by having the computer print it out.
, 6.3.3.1 Verify lowest loop T(ave) is > 525'F a minimum of 15 min, prior to achieving criticality. Record on Sp- ,
390.
l NOTE: Criticality will be anticipated at all times during rod withdrawal.
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l Op-210 Page 9 Rev. 2,1 I
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HKC 02/24/86 i Initials 6.3.4 withdraw the regulating rods, in sequence per OP-502, Control Rod Drive System, Section 9.2, until the desired critical rod position is achieved (i.e., the rod position recorded on Enclosure 4.
6.3.5 Commence deborating the RCS to the ECB concentration recorded on Enclosure 4 by performing the following:
- a. Determine the volume of demineralized water required per OP-304, Soluble Poison concentration Control, Section 6.3, Page 7.
NOTE: The RCS boron concentration should be sampled and verified every 30 min. during deboration.
- b. Commence a feed and bleed or batch operation as desired per OP-402, Makeup and Purification System, Section 11, to dilute the RCS to criticality.
6.3.6 While deborating the RCS, verify the following:
- a. The intermediate range instrumentation is on scale and indicating prior to the source range instrumentation indicating > 105 cps. .
6.3.7 If the reactor is critical within the RCS boron limits of the ECB, proceed to Step 6. 3.10 of this procedure.
OP-210 Page 10 Rev. 2, l.
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Initials 6.3.8 If reactor is not critical or critical prior to the limits of tne EC8, perform the following:
- a. Insert regulating rod groups to ensure > ,
1*. ok/k shutdown margin.
- b. Verify t7le baron concentration.
- c. Recalculate the ECB per Section 7.2 of tnis procedure.
NOTE: This calculation should be performed by anotner individual.
- d. If an error was found in the ECB, perform one (1) of the following actions:
- 1. Calculate an ECP for the present RCS baron concentration, record the applicable data c'n Enclosure 3 and recommence the startup at Step 6.2.5.1 by withdrawing control rods. OR
- 2. Recommence the startup with boron dilution per i
instructions of Reactor Specialist, record the l applicable data on Enclosure 4 and then continue with Step 6.3.3.1.
- e. If no error can be found in ene ECB, noti fy the Reactor Specialist for appropriate action to continue the startup.
OP-210 Page 11 Rev. M1
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Initials
. NOTE: Any further action taken to achieve criticality beyond the scope of this procedure shall have concurrence by the Reactor S pecial i st, Shi f t Su pervisor, and Operations Superintendant (or the man-on-call) .
6.3.9 Increase reactor power to 10-8 amps on the intermed-iate range instrumentation. Establish steady state conditions at 10-8 amps and record the following:
NOTE: This step should be performed as expeditiously as possible (without exceeding 1 dpm) in order to minimize the error induced by transient Xenon between these control rod positions and actual critical rod positions.
- a. Rod Positions: Groups 1-4 100 %
5 %
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7 %
8 %
- b. Baron Concentration: ppm 8 .
- c. RC Average Temperature: _
OF
- d. Time Criticality Conditions Established:
j OP-210 Page 12 Rev.
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- g. 6.3.10 Send a xerox copy of this completed procedure to the Reactor 19 S pecialist. 19 6.3.11 Depending on planned operation, i.e., training, physics 19 testing, shutdown, or startup into the power range, continue in 19 accordance with the appropriate Operating Procedures. 19 Snift Supervisor Date 7.0 ECP/ECB CALCULATION 7.1 ESTIMATED CRITICAL ROD POSITION (ECP) 7.1.1 The methodology for calculating the ECP consists of performing a reactivity balance to determine p(Net) = 0. The reactivity for the core is expressed by the following relationship:,
o(Net) = o(Fuel) + o(Rods) + o(B'oron) + o(Xenon) + o(Samarium)
+ o(Temperature)
By setting o(Net) = 0 and knowing the value of reac tivi ty associated with each of the components in the above reactivity balance equation, we can solve for the reactivity worth anich must be inserted by control rods to achieve criticality (Kef f =
1).
7.1.2 To calculate the ECP, complete Worksheet I (Enclosure 1) 7.1.3 Proceed to Step 6.2.2 of this procedure.
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7.2 ESTIMATED CRITICAL BORON (ECB) g 7.2.1 The methodology for calculating the ECB consists of performing a reactivity balance to determine o(Net) = 0. The reactivity for the core is expressed by the following relationship:
o(Net) = o(Fuel) + a(Rods) = p(Boron) + o(Xenon) +
o(Samarium) + o(Temperature)
By setting o(Net) = 0 and knowing the value of reac ti vi ty associated with each of the components in the above reactivity balance equation, we can solve for the reactivity worth wnich must be inserted by baration to achieve criticality (Ke rf = 1).
7.2.2 To calculate the ECP, complete Worksheet I (Enclosure 1).
7.2.3 Proceed to Step 6.3.2 of this procedure.
ENCLOSURES Enclosure 1 Worksheet I, Estimated Critical Position Enclosure 2 Worksheet 11-Estimated Critical Boron Concentration Enclosure 3 Data Sheet, Estimated Critical Position Enclosure 4 Data Sheet, Estimated Critical Boron OP-210 Page 14 Rev. $! 1
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HKC 11/19/85
-WORKSHEET I- ENCLOSURE 1 4
(Page 1 of 2)
ESTIMATED CRITICAL POSITION REFERENCE CONDITIONS: 5320F, 0% FP, No Xenon, No Control Rods, Equilibrius Samarium
- 1. Fuel Reactivity
- a. Core Burnup EFPD + \Ak/k
- b. Read Curve 1 of OP-103C, Reactivity Worth Curves.
- 2. Baron Reactivity
- a. Boron Concentration ppa
- b. Using core burnup from Step 1(a), find the inverse boron worth from Curve 4 of OP-103C, Reactivity Worth Curves: opa/\lik/k *
- c. Divide Step 2(a) by the inverse boron worth in Step 2(b). -
$21k/k
- 3. Xenon Reactivity (Use Step 3.1 or 3.2) 3.1 value calculated by SAXON I (submit printout).
(- %tlk/k) = - %dik/k OR 3.2 a. Last power level was t FP for hrs,
- b. Time' Shutdown hrs.
- c. If time at last power level was ( 40 hrs. and SAXON is unavailable, consult with Reactor Specialist.
(- \ 6k/k) = - \t k/k
- 4. Samarium Reactivity Builduo After Shutdown 4.1 Value calculated by SAXON I (submit printout) -
\fik/k
- 5. Reactivity Effect Frca Temeerature
- a. Average RC Temperature CF
- b. Reference temperature is 5320F.
- c. Temperature coefficient at ppa 8 is obtained from Curve 5 of OP-103C, Reactivity Worth Curves, to be x 10~2% 6k/k/0F.
- d. Reactivity = (T(ave)
- - 532] (Temp. Coeff.)2 l1k/k/0F)=
- e. Reactivity = ( )( x 10 \ 1 \/1k/k Calculated By Date
- 6. Axial Power Shanina Red Worth
- a. Worth of Group 8 at i WD from Curve 9 of OP-103C, Reactivity Worth Curves. -
\ 6k/k OP-210 Page 15 Rev. $$ 1
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HKJ 11/19/85 WORKSHEET I, ESTIMATED CRITICAL POSITION ENCLOSURE 1 g
(Continued) (Page 2 of 2)
- 7. Reactivity Worth of Inserted control Reds Necessary to Maintain Just Critical Conditions
- a. This equals s (sua of Steps 1-6) = - (+ ). -
Stik/k
- 8. Estimated Critical Rod Position
- a. Use the calculated worth of Step 7 and Curves 7, 8A-D, and 9 of OP-103C, Reactivity Worth Curves, to determine critical rod positions. NOTE: See instructions with Curve 8A for Groups 5-7.
Groups 1-4 100 \ WD Group 5 % WD Group 8 \ WD Group 6 % WD (same as Step 6) Group 7 * \ WD Value From Step 7, - \ak/k & 1.0%21k/k = - \tik/k= \ WD on Gp. l19 Value From Step 7, - \ 6k/k - 1.0\lik/k = - \tsk/k= \ WD on Gp. l:9 Calculated By Date Time Reactor Startup No.
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HKC 11/19/85 p -WORKSHEET II- ENCLOSURC_2 (Page 1 of 2-)
ESTIMATED CRITICAL BORON CONCENTRATION REFERENCE CONDITIONS: 5320F, 0% FP, No Xenon, No Control Rods, Equilibrius Samarium
- 1. Fuel Reactivity
- a. Core Burnup EFPD + %dik/k
- b. Read Curve 1 of OP-103C, Reactivity Worth Curves.
- 2. Xenon Reactivity (Use Step 2.1 or 2.2) 2.1 Value calculated by SAXON I (submit printout).
(- \tik/k) = - $.21k/k OR 2.2 a. Last power level was % FP for hrs,
- b. Time Shutdown hrs.
- c. If time at last power level was < 40 hrs. and SAXON is unavailable, consult with Reactor Specialist.
(- %tlk/k) = - \41k/k
- 3. Samarina Reactivity Builduc After Shutdown 3.1 Value calculated by SAXON I (submit printout) -
S. Ilk /k
- 4. Reactivity Effect From Tencerature
- a. Average RC Temperature CF
- b. Reference temperature is 5320F.
- c. Temperature coefficient at ppaa is obtained from Curve 5 of OP-103C, Reactivity Worth Curves, to be x 10-2\tak/k/0F,
- d. Reactivity = (T(ave)
- - 532] (Temp. Coeff.)2 dik/k/0 *.
- e. Reactivity = ( )( x 10 % F)= 21k/k
- 5. Reactivity of Control Rods at Desired Insertion See Curves 7, 8A-D, and 9 of OP-103C, Reactivity Worth Curves, to determine critical worths. HQII: See i instructions with Curve 8A for Groups 5-7.
I Groups 1-4 at 100 % WD Group 5 at i WD Group 6 at t WD Group 7 at \ WD Regulating Group Worth -
\lik/k Group 8 at i WD Group 8 Worth -
%dik/k Calculated By Date OP-210 Page 17 Rev. %$ 1
HKC 11/19/85 WORKSHEET II, ESTIMATED CRITICAL BORON CONCENTRATION ENCLOSURE 2 4 (Continued) (Page 2 of 2)
- 6. Reactivity of Boron to Maintain Just critical Conditions
- a. Find sua of Steps 1 thru 5. \Zik/k
- b. Using core burnup from Step 1(a), find the inverse boron worth from Curve 4 of OP-103C, Reactivity Worth Curve: pps/*sak/k.
- c. Multiply Step 6(a)~ by the inverse boron worth in Step -
6(b).
- d. Estimated critical boron concentration is ppa 8.
Calculated By Date Time Reactor Startup No.
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,N ENCLOSURE 3 t
DATA S 2ET _
ESTIMATED. CRITICAL POSITION
- 1. From Step 6.1.6: ,
j Startup Time: -
Reactor Startup No.: ,
x .
- 2. From Step 6.2.1 and Worksheet 1: ,-
Transpose the value of ECP from Worksheet I (Section 8) to tne following Table 1.
TABLE 1:
Groups % Withdrawn
-1.0% Ak/K Just Critical +1.0% sk/k 19 1-4 100 % 100 % .100 %
5 t t i %
j' 6 % % %
7 % % %
8 % % % _
Required Boron Concentration: _
Actual Boron Concentration:
i
- 3. From Step 6.2.5.3:
! NI-1: cps NI-3: amps i i NI-2: cps NI-4: amps .
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< OP-210 Page 19 ' Rev.
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ENCLOSURE 4 DATA SHEET
-' ' , ESTIMATED CRITICAL BORON
- 1. From Step 6.1.6: .
Startup Time:
Reactor Startup No.:
J
- 2. From Step,6.2.'1 and Worksheet II:
Trar.spose- the value of ECB from Worksheet II (Section 6) to the following Table 1.
TABLE 1: - ~
. Grou ps % Withdrawn
+1.0% ak/k 19
-1.0% a k/k Just Critical 14 b0 % 100 '% 100 %
5 % % %
6 % % %
7 % % %
i 8 % % %
PP PP Required Baron Concentration: ppmb l
- 3. ' From Step 6.3.6: -
NI-1: cps NI-3: amps NI-Zi e ps N!-4: amps l'
OP-210 Page 20 (LAST PAGE) Rev. $1 e
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