ML19224B177
| ML19224B177 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/05/1979 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2102-1.2, TM-0013, TM-13, NUDOCS 7906140166 | |
| Download: ML19224B177 (15) | |
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TMI DOCJMjE 'T_S "O/ b DOCUMENT NO:
h 2h 0F DOCUMENT PROVIDED BY COPY MADE ON j
i METROPOLITAN EDISON COMPMIY.
/h Wilda R. Mullinix,.NRC 7906140166
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Revisica 6 02/05/79 APR 2 3 7379 THREE MILE ISLAND NUCLEAF. STATION UNIT #2 OPERATING PROCEDURE 2102-1.2 APPROACH TO CRITICALITY Table of Effective Pages Paoe Date Revision Pace Date Revision Pa2a Date R evision 1.0 09/27/78 5
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Date 2-9 Date Chairrnan of PORC V'< Chairman cf PORC I
Un't-2 Superintendent Approval Unit 1 Superintendent Approval N6tft<_.
Date Date f/
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Manager Generation Quality Assurance Approval
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THREE MILE ISLAND huCLEAR STATION UNIT #2 OPERATING PROCEDURE 2102-1.2 APPROACH TO CRITICALITY TABLE OF CONTENTS SECTION PAGE
1.0 REFERENCES
2.0 1.1 Drawings Applicable for Operation 2.0 1.2 Operating Procedures Applicable for Operation 2.0 1.3 Manufacturers' Instruction Manuals 2.0 1.4 Applicable System Descriptions 2.0 1.5 Curves, Tables, etc.
2.0 2.0 LIMITS AND PRECAUTIONS 2.0 3.0 PREREOUISITES, 4.0 4.0 PROCEDURE 50 APPENDIX TITLE No.
Method to Determine Subcritical Neutron Multiplication A
1/M vs. Rod Position Plot B
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THREE MILE ISLAND NUCLEAR STATION
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UI9 UNIT #2 GPERATING PROCEDURE 2102-1.2 APPR0ACH TO CRITICALITY
1.0 REFERENCES
1.1 Drawings Applicable for Operation None 1.2 Operating Procedures Applicable for Operation i.2.1 2105-1.9, Control Rod Drives 1.2.2 2103-1.2, Soluble Poison Concentration Control 1.2.3 2103-1.9, Reactivity Balance 1.2.4 2102-1, Unit Startup Procedures 1.2.5 2105-1.4, Integrated Control System 1.2.6 2101-1, Limits & Precautions 1.3 Manufacturers' Instruction Manuals 1.3.1 Control Rod Drive Control System (B&W) 1.4 Applicable System Descriptions 1.4.1 Control Rod Drive Centrol System 1.4.2 T.M.I. Unit 2 Technical Specifications 1.5 Curves and Tables Nor.e 2.0 LIMITS AND PRECAUTIONS 2.1 If any conditions occur which physically or administratively delays criticality, the reactor will be maintained at least 1% AK/K subcritical while the conditior are being corrected.
If such delay causes the time requirements of surveillance requirements
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4.1.1.1.l(c) and 4.1.3.6(a) to be exceeded. These surveillance requirements must be reverified.
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2.2 All borating and deborating cycles will be perforned
.n accordance with 2103-1.2, Soluble Poison Control.
2.3 Do not exceed a stable startup rate of 1 DPM.
2.4 During rod withdrawal closely monitor the nuclear instrumentation to insure correct response as core reactivity changes.
2.5 Verify that sufficient overlap exists, at least one (1) decade between source an intermediate range nuclear instrumentation.
2.6 If the reactor goes critical with less thac the minimum predicted positive reactivity insertion, i.e.
(prior to rods reaching 0.5%
aK/K below the estimated critical position), insert rods to achieve a 1% A7./K shutdown position. Following rod insertion, recalculate the estimated critical position to determine the cause for error.
2.7 If the reactor is not critical with the allowable maximum predicted positive reactivity insertion, i.e. (when the rods ara at 0.5% aK/K above the esti=ated ' critical position), insert the rods to 0.5%
aK/K below estimated critical position.
Following rod insertion recalculate the estimated critical position to determine c.e cause for error.
2.8 Prior to any rod withdrawal or boric acid dilution the source range nuclear instru=entation should be greater than 2 cps.
2.9 Tne Nuclear Instrumentation will be continously monitored during any reactivity addition. Subcritical source multiplication will be confirmed according to Appendix A or terminate the ctartup until an appropriate evaluation is made.
2.10 Safety rod groups shall te verified fully withdrawn within 15 min.
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prior to withdrawal of any regulating rod during the approach to criticality (Tech Spec 3.1.3.6) except as required by Physics Tests (Tech Spec 3.10.1 & 3.10.2).
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2.11 Reactor power shall not exceed 1 percent of rated power unless normal operating temperature pressure and rod configurations are established.
2.12 Axial power shaping rods may not normally be used for any purpcse except axial power control.
2.13 If..aring rod withdrawal, the count rate increase sharply stop rod withdrawal until the count rate stabilizes.
2.14 Two Intermediate Range Neutron Flux and Rate Channels shall be OPERABLE prior to entry into tiode 2 and during reactor criticality, in accordance with Tech. Spec.
- 3. 3.1.1, Tabl e 3. 3-1.10.
NOTE:
For Physics Testing an Intermediate Range detector can be connected to the reactimeter after Reactor Criticality.
3.0 PREREQUISITES 3.1 Reactor coolant system temperature (Tavg) shall be > 525 F within 15 minutes prior to achieving criticality (Tech Spec 3.1.1.4).
_3. 2 All precritical and prestartup checks a: e completed in accordance with Unit Startup Procedure 2102-l.3.
3.3 Source range nuclear instrumentation indicating a minimum countrateoftwo(2)C.P.S.
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Reactivity balance calculation (2103-1.9) has been completed and a critical rod position (0.5% aK/K above and below critical position) determined.
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___ _3. 5 Source range (CPS) and intermediate range (amps) indication is availabic on strip chart recorder, if required, as determined by the Shift Supervisor.
3.6 Two or more reactor coolant pumps are operating (Tech Spec 3.4.1).
3.7 The Reac, tor Protection Instrumentation Channels have had their trip setpoints verified per SP2311-6.
(Tech Spec 4.4.lb).
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Reactor coolant chemistry within limits per Tech Spec 3.4.7.
4.0 PROCEDURE Plis procedure defines the major steps involved in taking the reactor from a hat standby (Mede 3) condition to a startup condition (Mode 2).
The procedure is epplicable when no physical manipulation of core geometry (fuel changes, CRA swaps, etc) has occured since the previous shut down. Criticality will be attained by CRA group withdrawal following adjustment of soluble baron content.
The prescribed critical CRA configuration will be dependent upon future operating expectations, xenon effects and soluble poison economies.
A one over M (1/M) plot will be made during rod withdrawal.
CAUTION: Ouring any evolution that can change core reactivity the operator will assume that criticality may be achieved and will monitor the Nuclear Instrumentation.
4.1 Verify shutdown margin within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of achieving criticality, by verifying that the predicted.ritical control rod position is within the 5HUTDOWN MARGIN limits of Figure 1.
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Signa ture Date/ Time NOTE:
Plot 1/M during rod withdrawal.
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4.2 Withdraw CRA safety groups 1-4 to the upper limit in sequence if not already withdrawn. Confirm subcritical source multiplication according to Appendix A as each safety group is withdrawn.
NOTE:
Refer to 2105-1.9 fcr operation of the CRD system.
___ 4. 3 Verify each safety rod is fully withdrawn within 15 minutes prior to withdrawal of the regulating reds.
(Tech Spec 4.1.3.6a)
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Signature Da* Viime 4.4 Announce over the paging system that a reactor startup has commenced.
NOTE:
Plot 1/M during rod withdrawal.
Refer to Appendix B.
4.5 Manually withdrav CRA Group 5 to 75% WD.
4.6 Position CRA group 8 (APSR) at approximately 32% WD or to a position determined by the Nuclear Engineer.
4.7 Verify that the "ECP" has been completed per 2103-1.9.
4.8 Adjust reactor coolant system boron concentr tton to th~e concentration calculated in 2103-1.9 for critical petition.
4.9 When deboration is completed and the Reactor coolant letdown and the pressurizer baron concentration are within 100 ppm 8 of the Makeup tank bcron concentration proceed to step 4.10.
4.10 Prior to step 4.14 verify that the shutdown margin calculated n
in step 4.1 is still valid, if not re-verify.
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4.11 Verify the reactor coolant system temperature (Tav) is > 525 F within 15 minutes of achieving criticality (Tech Spec 4.1.1.4.a).
Signature Date/ Time 4.12 Verify each safety rod is fully withdrawn within 15 minutes prior to withdrawal of the regulating rods (Tech Spec 4.1.3.6a)
Signature Date/ Time 4.13 Obtain SP2311-2 and commence procedure after criticality if U
the RC Tave is less than 530 F.
NOTE:
Plot 1/M during rod withdrawal.
Refer to Appendix B.
4.14 Continue to manually withdraw Group 5 control rods.
CAUTION:
If the reactor goes critical with less than the minimum predicted positive reactivity insertions, i.e. (prior to rods reacing 0.5% ak/k below the estimated critical position), insert rods to achieve a 1% ak/k shutdown position.
Following rod insertion, recalculate the estimated critical position to determine the cause for error.
CAUTION:
If the reactor is not critical with the allowable maximum predicted positive reactivity insertion, i.e. (when the rods are at the 0.5% ak/k valve above the estimated critical position), insert the rods to the 0.5% ak/k below estimated critical position.
Following rod insertion recalculate the estimated
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critical position to determine the cause for error.
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i APR 2g 4.15 Verify that as Group 5 passes the 75% withdrawn position group U/9 6/7 moves out with Group 5.
4.16 Verify Group 5 stops when it reaches out limit and Group 6/7 continues to withdrawn.
4 17 Slowly raise the reactor power to 10-8 amps on the intermediate range channels.
4.18 Verify that the source range channels are de-energized at 10-9 amp indication on both intermediate range channels.
4.19 When the reactor is stable at 10-8 amps with zero startup rate, record critical data, boron ppm, RCS temperature and rod position and time /date.
4.20 Depending on planned operation, continue operation in accordance with the appropriate operating procedures.
4.21 Attach completed 1/M calculations to procedure.
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APPENDIX A Method to Determine Subcritical Neutron Multiplication Calculate M = SDMI (100 - SDM2)
SDM2 (100 - SCM))
Where M - Multiplication Factor SDM1 = Shutdown Margin prior to reactivity change (% ak/k)
SDM2 = Shutdown Margin after reactivity change (% ak/k)
Note: SDM1 and SDM2 are negative values.
Calculate 2 = M(CR ) where CR2 = new count rate CR g
CRj = initial count rate Examole:
Condition: The reactor is 10% subcritical.
5.3% reactiv;ty is added by withdrawing safety rods. The initial count rate is 10 cps. The reactor is now 4.7% subcritical.
Calculaticn:
SDM1 = -10%:
SDM2 = -4.7%
M = 10 (100 + 4.7) = 10 (104.7) = 2.025 4.7 (100 + 10) 4.7 (110)
CR2 = 2.025 (10) = 20.25 cps.
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APPENDIX B 1/M vs. Rod Position Plot M - Subcritical Multiplication C, - Initial Count Rate C - Count Rate Cp - Final Count Rate Used to Predict Criticality.
Criticality is achieved when Keff = 0, M = - c.
h = 0.
Plot 1/M vs. Rod Position Record C (from NI 1 or 2). Withdraw Rods at given interval ( 5%,10% or g
25%).
Stop rod withdraw and wait for count rate to stabilize.
Record CalculatehbydividingC by C and record on Data final count rate.
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Sheet.
Note Rod Position ard plot 1/M vs. Rod position on Data Sheet.
Using a straight edge connect point 0 to point 1 and extend line to intersect rod position axis ( if it will). The rod position at this intersection is the predicted Critical position. Withdraw rods another increment and repeat the above procedure to locate subsequent points and continue the plot.
Compare predicted Critical positions to ECP. Refer to L & P 2.6 and 2.7.
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