ML19209B643
ML19209B643 | |
Person / Time | |
---|---|
Site: | Three Mile Island |
Issue date: | 07/16/1979 |
From: | METROPOLITAN EDISON CO. |
To: | |
References | |
1102-4, NUDOCS 7910100266 | |
Download: ML19209B643 (40) | |
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- \ Revision 26 1F( I * *. , 07/16/79 THREE MILE ISLAND NUCLEAR STATION ? ORC C "ARMAl\ '
UtlIT #1 OPERATIflG PROCEDURE 1102-4 POWER OPERATION y\ '] } Table of Effective Pages Paae - Date Revision Pace Date Revision Page Date Revision 1.0 11/19/75 11 26.0 03/27/79 24 51.0 2.0 03/27/79 24 27.0 03/27/79 24 52.0 3.0 03/25/77 16 28.0 03/27/79 24 53.0 4.0 08/11/78 21 29.0 03/27/79 24 54.0 5.0 03/27/79 24 30.0 03/27/79 24 55.0 6.0 08/11/78 21 31.0 03/27/79 24 56.0 7.0 08/11/78 21 32.0 03/27/79 24 57.0 8.0 03/27/79 24 33.0 03/27/79 24 58.0 9.0 07/03/79 25 34.0 03/27/79 24 59.0 10.0 03/27/79 24 35.0 03/27/79 24 60.0 11.0 03/27/79 24 36.0 03/27/79 2a 61.0 12.0 03/27/79 24 37.0 03/27/79 P; 62.0 13.0 03/27/79 24
- 38.0 07/16/79 26 63.0 14.0 03/27/79 24 39.0 07/16/79 26 64.0 15.0 03/27/79 24 40.0 65.0 16.0 03/27/79 24 41.0 66.0 17.0 08/11/78 21 42.0 67.0 18.0 03/27/79 24 43.0 68.0 19.0 03/27/79 24 d4.0 69.0 20.0 08/11/78 21 45.0 70.0 21.0 03/27/79 24 46.0 71.0 22.0 08/11/78 21 47.0 72.0 23.0 02/11/78 21 48.0 73.0 24.0 03/27/79 24 49.0 74.0 25.0 03/27/79 24 50.0 75.0 Unit 1 Staff Recom ends Ap roval Unit 2 Staff Reco mend proval Approval / I Date Approval /\ -
Date Cognizaht Dept. flead CogrdzanbD'epl. Hekd Unit 1 PO C ,Reco m ' ends Approval Unit 2 PORC R omme ds pproval (4 Y' Date l' A ~ A - Date - V-Chairrnan of PORC Chairn[an oMfd Unit 1 p jnt dent pproval Uait 2 Superi tenden Ap vai f '24 FAN Date Q lI /$ / ' l Date w g- jj i Manager Generation Quality Assurance Approval / -- Date
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1102-4 Revisior.11 : 11/19/75 . 1
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TPREE MILE ISLAND NUCLEAR STATION ', UNIT #1 OPERATING PROCEDURE #1102-4 ' }- ,_
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Power Operation . Table of Contents 4.1 REFEPINCES 4.2 LIMITATIONS AND PPICAUTIONS 4.2.1 Equipment 4.2.2 Administrative d 4.3 PROCEDURES 4.3.1 Operation at Power 4.3.2 Periodic Operations 4.3.3 Power Operation with One Main Feed Pump 1.0 1123 !81 D
1102-4
- Revision 24 2"
03/27/79 .
4.1 REFERENCES
4.1.1 OP 1101-1 Plant Limitations and Precautions . , 4.1.2 Unit 1 Technical Specifications
- 4.1.3 OP 1105-4 Integrated Control System 4.1.4 OP 1105-3 Feed System ,-
4.1.5 OP 1103-4 Soluble Poison Concentration Control - 4.1.6 OP 1104-2 Makeup and Purification System ,' 4.1.7
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OP 1105-9 Control Rod Drive System 4.1.8 OP 1103-15 Reactivity Balance 4.2 LIMITATIONS AND PRECAUTIONS 4.2.1 Equipment 4.2.1.1 During normal power operation maintain imbalance withir. the permissible operating region of Figure 4 (depending on core age). NOTE: The power-imbalance envelope defined in Figure 4 is based on LOCA analysis which have defined the .. maximum linear heat rate such that the maximum clad temperature will not exceed the Final Acceptance 0 Criteria (2200 F). Operaticn within the limits of Figure 4 assures that if the control rods are at the withdrawal / insertion limits as defined by Figures l A,1B, 2, 3A or 3B and if a +3.52% incore quadrant power tilt exists, we will not exceed the Final Acceptance Criteria. Additional conservatism is introduced by application of: - Nuclear Uncertainty Factors Thermal Calibration Uncertainty Fuel Densification Effects Hot Rod Manufacturing Tolerance Factors j]{j 182
1102-4
- f. , ..'
Revision 16 03/25/77 . 4.2.1.2 During normal operation with 4 reactor coolant ;, umps running maintain ATc less than SUF. ~ 4.2.1.3 During transients near rated power do not exceed a ATc of -,1 greater than 10 F. '. 4.2.1.4 Do not exceed 40% power unless both feed pumps and two condensate. . booster pump pairs are in operation. -
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NOTE: Prior to exceeding 40% power with 2 RC pumps (one :1
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per loop) running the Minimum Incore System must be .', operable. 4.2.1.5 Do not exceed 49% power unless at least 3 reactor coolant pumps are in operation. NOTE: Prior to exceeding 60% power with 3 reactor coolant pumps operating the Minimum Incore System must be operable. 4.2.1.6 Do not exceed 75% power unless 4 reactor coolant pumps are in operation. NOTE: Prior to exceeding 80% power with 4 reactor coolant pumps operating the Minimum Incore System must be operable. 4.2.1.7 If the total reactor coolant leakage rate exceeds 10 gpm the reactor shall be placed in hot shutdown within 24 hours of detection. (T.S. 3.1.6.1). 4.2.1.8 If unidentified reactor coolant leakage exceeds 1 gpm or if any reactor coolant leakage is evaluated as unsafe, the reactor - shall be placed in hot shutdown within 24 hours of detection. (T.S. 3.1.6.2). 3.0 1123 183
1102-4 - Revision 21 - 5. 08/l1/78 . .. 4.2.1.9 If any reactor coolant leakage exists through a non-isolable fault in a RCS strength boundary (such as the reactor vessel, piping, etc, except the S/G tubes) the reactor shall be shutdown, - - and cooldown to the cold shutdown condition shall be initiated '- -[ within 24 hours of detection. ('T.S. 3.1.6.3). 4.2.1.10 When the reactor is critical and above 2". power, 2 reactor ~ coolant leak detection systems of different operating principles : shall Se in operation for the Reactor Building with one of the - two ',ystems sensitive to radioactivity. (T.S. 3.1.6.7). 4.0 1123 !84
1102-4
~ Revision 24 :
03/27/79 ;- 4.2.1.11 The key operated shutdown bypass switch associated with each ~ reactor protection channel shall not be used during reactor . power operation. (T.S. 3.5.1.4) '. 4.2.1.12 If the computer is declared inoperable use 1203-7 " Hand Calculations 'I for Quadrant Power Tilt and Core Power Imbalance" to ensure -
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that tilt and imbalance are within their limits. - - - When reactor power is less than 15%FP, do not request a print I-out of the following computer groups: Gp. # Description
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20 Worst Case Thermal Conditions 31 Fluid Conditions 38 Core Average Thermal Conditions 39 Core Map Thermal Conditions 40 All Thermal Outputs 54 Selected Assembly Thermal Conditions 4.2.2 Administrative 4.2.2.1 Axial power shaping rods should not be used for any purpose except axial power control. 4.2.2.2 Minimum pressurizer level is 200 inches at power. 4.2.2.3 Maximum pressurizer level is 385 inches. 4.2.2.4 Boron concentration will be maintained such that the reactor will be at least 1% shutdown with the most reactive rod stuck out. (T.S. 3.5.2.1 )
~4.2.2.5 Do not attempt to start reactor coolant pumps when power is .
greater than 30%. 1-4.2.2.6 ionitoring of core power dist-ibution with in-core detectors and the online computer should be maintained as follows (T.S. 3.5.4): 0.0 1123 185
,' '.I 1102-4 . Revision 21 :. 08/11/78 .
- 1. During steady-state operating, a 3-D Power Map (Group 34) -
7 and a worst case Thermal Condition (Group 20) data dump . . should be taken every EFPD. The reactor power level, i boron concentration, and core burnup should als: be ,, recorded. This data should be collected each day at -; midnight along with the Station Daily Log Sheet, Heat
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Balance (Group 32), Reactivity Balance (Group 22) and Periodic Typewriter Log Daily Summary for delivery to the .. Station Nuclear Engineer.
- 2. Following a significant one-step load change (>10% rated power) above 50% rated power or significant control rod motion (>10% insertion or withdrawal) a Worst Case Thermal Condition should be taken within one hour after the change and then every 4 to 8 hours for a period of 24 to 36 hours, or longer if evidence of a power distribution '
transient exists. A 3-D Power Map should be taken about - 1 hour after reaching steady-state conditions. These data printouts are not necessary on the way up to full power if the Mechanical Maneuvering Recommendations are followed. However, the data from Groups 20 and 34 should be calltd out one hour after power level cutoff 1; reached. The recommended measurement frequency will allow transient power peaking to be traced and the minimum margin to ECCS limits to be evaluated witn relatively - high accuracy.
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- 3. A 3-D power map and worst case thermal printout should -
also be obtained whenever a large imbalance or any other core flux abnormality exists. I 6.0 ! l l. <?
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h,5 1102-4 - Revision 21 : 2, 08/11/79 ., 4.2.2.7 Do not exceed 2535 MWt Core Thermal Power 4.2.2.8 If any Safety Limit (defined in Technical Specification 2.1 - " and 2.2) is exceeded, the shift supervisor shall notify the .- Station / Unit Superintendent. The reactor shall be shut down. .' The licensee shall notify the Commission, review the matter . and record the results of the review, including the cause of - the condition and the basis for corrective action taken to , I preclude reoccurrence. Operation shall not be resumed until C-authorized by the Commission. ~ 4.2.2.9 If, during operation, the automatic safety system does not function as required, the Station / Unit Superintendent shall be notified. The shift supervisor shall take appropriate action as outlined in the Tech Specs. Note that this appropriate action may include shutting down the reactor: s . Examples of " failure to function as required" are: (1)Setpoints
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exceeding liniiting safety system settings (2) failure of a protection system component in an untripped state. 4.2.2.10 When a Limiting Condition for Operation (defined in Section 3 of the Technical Specifications) is not met, the shift supervisor shall notify the Station / Unit Superintenderit. The reactor shall be shut down or remedial action taken as permitted _by_ the Technical Specifications until the condition can be met. In the event an LC0 is not met and the remedial action permitted by the Tech. Specs. does not correct the situation, the licensee shall notify the Commission, review the matter and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude reoccur-rence. i 73 11M 187
1102-4
. Revision 24 I 4.2.2.11 Observe the maneuvering rate limitations as listed in Encic ure '
1 (Mechanical Maneuvering Recommendations). 4.2.2.17 During normal operations, select NI-5 for control to the ICS. . 4.2.2.13 Power operation with one idle reactor coolant pump in each ~2' loop shall be restricted to 24 hours. If the reactor is not ; returned to an acceptable RC p>mp operating combination at the' ~ end of the 24 hour period, the reactor shall be in a hot '[-
~2 shutdown condition within the next 12 hours. (TS 3.1.1.1. b) ,, ~~
4.2.2.14 Observe the requirements of Enclosure 2 to assure adequate (
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Nuclear Instrument accuracy. 3.0 11c3 '.88
1102-4 -
'. Revision 25 [,
07l.03/79 4.3 PROCEDURES ' ' ,.. 4.e.1 Operation at Power 4.3.1.1 Prerequisites :
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- 1. The Plant Startup in accordance with OP 1102-2 is complete ,
and the plant is in operation at between 15% and 100, load. " 4.3.1.2 Procedure ; CAUTION 1: Prior to exceeding 49% power, verify at least 3 ,,. Reactor Coolant Pumps are in operation. . CAUTION 2: Prior to exceeding 75% power, verify 4 Reactor Coolant pumps are in operation. CAUTION 3: Do not attempt to start Reactor Coolant Pumps when greater than 30% power. CAUTION 4: Do not exceed 40% power unless 2 condensate pumps and 2 condensate Booster Pumps are in operation. .. CAUTION 5: The available shutdown margin shall not be less , than 1% AK/K with the highest worth control rod fully withdrawn (T.S. 3.5.2.1). CAUTION 6: Except for physics tests or exercising control rods, the control rod insertion / withdrawal limits are specified on Figure lA (for up to 12515 EFPD), and Figure 1B (from 125 to 2651 15 EFPD), for four pump operation, and Figures - 3A or 3B for three or two pump operation. The - APSR limits are specified on Figure 2. If the ' - control rod position limits are exceeded, corrective measures shall be taken immediately 9o 1123 !89
1102-4 -
. Revision 24 :
03/27/79 _ i.- to ac.' ave an acceptable control rod posit' ion. ;~ Acceptable control rod positions shall be attained within four hours (T.S. 3.5.2.5). CAUTION 7: Monitor quadrant tilt on a minimum frequency of ' [, [ once every 2 hours when operating above 15% of ._- rated power (T.S. 3.5.2.4). *
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CAUTION 8: Except for physics test, if quadrant tilt - exceeds +3.52% as measured by the full incore detector system, power shall b'
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educed immediately , to below the power level cutoff. See Figures - 1A, 1B, 3A or 3B). Moveover, this power level cutoff value shall be reduced 2% for each 1% tilt in excess of +3.52 tilt. For less than 4 pump operat on, thermal power shall be reduced 2 percent of the thermal power allowable for -- the reactor coolant pump combination for each 1 _. percent tilt in excess of +3.52 percent (T.S. 3.5.2.4). CAUTION 9: Within a period of 4 hours, the quadrant power tilt shall be reduced to less than +3.52 percent except for physics tests, or the following - adjustments in setpoints and limits shall be made: (T.S.3.5.2.4).
- 1. The protection system reactor power / imbalance '
envelope trip setpoints shall be reduced 2 - percent in power for each 1 percent tilt. - 10.0 1123 '.90
1102-4 Revision 24 : 03/27/79 {
- 2. The control rod group withdrawal limits ",
(Figures l A,1B, 3A or 3B as applicable) ,. shall be reduced 2 percent in power for :
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each 1 percent tilt in excess of +3.52 , percent. 2
- 3. The operational imbalance limits (Figure 'I 4 as applicable) shall be reduced 2 . '.
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percent in power for each I percent tilt . in excess of +3.52 percent. CAUTION 10: If quadrant tilt is in excess of +16.80 percent, as measured by the full incore detector system, except for physics tests or diagnostic testing, the reactor will be placed in hot shutdown condition. Diagnostic testing during power operation with a quadrant power tilt is permitted ' provided the thermal power allowable for the _ reactor coolant pump combination is restricted as stated in Caution 8 above (T.S. 3.5.2.4). CAUTION 11: The mechanical draf t cooling tower shall be operated in accordance with OP 1104-37. OP 1104-37 prc.l des guidance to assure the requirements of ETS 2.1 are met.
~ CAUTION 12: Except for physics test, power shall not be increased above the power level cutoff (See ..
Figures lA, IB, 3A or 38) unless one of the ' following conditions is satisfied: ' - 1;.0 }l23 !9l
1102-4 Revision 24 5. 03/27/79
- a. Xenon reactivity never deviated ~more than -'
10 percent from the equilibrium value for ,. operation at 100 percent of rated thermal - . power.
- b. Xenon reactivity deviated more than 10 ~
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percent and is now within 10 percent of - the equilibrium value for operation at )' 100 percent of rated thermal power and - asymptotically approaching stability.
- c. Except for Xenon free startup (when Tech Spec 3.5.2.5.c.2 applies) the reactor has operated within a range of 87 to 92 percent of rated thermal power for a period exceeding 2 hours in the soluble poison control mode. "
CAUTION 13: Core imbalance shall be_ monitored on a minimum _ frequency of once every two hours during power operation above 40 percent of rated power. Except for physics tests, corrective measures (reduction of imbalance by ApSR movement and/or reduction in reactor power) shall be taken to maintain operation within the envelope defined by Figures 4. If the imbalance is not within the envelope defined by these . Figures, corrective measures shall be taken to ' achieve an acceptable imbalance. If an acceptable - imbalance is not achieved within four hours, 112] '92
' 1102-4 . ' Revision 24 :
03'27/79 ;- reactor power shall be reduced until imba.ance
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limits are met (T.S. 3.5.2.5.d). CAUTION 14: Follwing any thermal power change of more than- . 15% of rated thermal power within a 1 hour 'E period, notify Health Physics / Chemistry that '.: . -
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primary coolant must be sampled and analyzed ' ' 3 for dose equivalent I-131 within 4 hours and ~f the condenser vacuum pump discharge must be
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sampled and analyzed for individual gamma - omitters within 4 hours. Primary coolant samples should be continued at 4 hour intervals until the dose equivalent I-131 drops below luci/ml. 4.3.1.2.1 Core power is controlled by movement of the control rods, and adjustment of the boron concentration. Figures 5A or 5B, core -- power vs. rod position, illustrates the recommended transient - and long-term control rod operating bands depending on core age. Control rods should be maintained, within the steady-state operating rod position band whenever steady load conditions exist for greater than 1-2 hours, or for load changes less than 0.5% per minute. This action will minimize imbalance changes. The transient rod position band is used for all transients greater than 0.5% per minute, and during the period when power changes greater than 15% are expected. The rod . position bands were developed, assuming initial conditions of - 100% core power,100% equilibrium xenon with Group 7 positioned - at 87 to 97% withdrawn. 13.0 ll23 l9
1102-4 - Pavision 24 03/27/79 -[. 4.3.1.2.2 Steady-State Operation (Transients <0.5%/ min). a) During steady-state operation with equilibrium xenon, , , control rods will slowly drift out of the core with - burnup. As rods approach the top of the control band,
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they should be deborated ba6k into the lower half of the ~,] band. The exact point at which to deborate can be at the ~i convenience of the plant operators. If 2535 MW is .- t , exceeded, immediate steps must be taken to bring core .' power equal to or less than 2535 MW
- t b) During steady-state operation with xenon oscillations due to a recent transient, xenon will push control rods out of the band first in one direction, then in the other, for several hours following the transient. This action
, is dependent on the transient performed, Fut is applicable . 'to both control rod bands. The operator should:
- l. Determine the chan9; in baron necessary to drive the rods from the top of the band from Figure 7 (Note ,
that the same change in boron will go from bottom to top cf band also).
- 2. Using the soluble poison concentration control procedure, convert the change in boron te a batch volume of de-ionized (DI) water necessary to drive rods from the top of the band to the bottom, or a volume of boric acid to go from the bottom to the _
top of the band.
- 3. As rods approach the top (bottom) of the band due to known transients, add the volume of DI water (boric acid) calculated above.
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' 1102-4 Revision 21, .-
03/27/79 .} - c) Power may be increased at rates of <0.5% FP/ min. , with.
~ 'I rods maintained in the steady-state band, by debarating ..
to maintain rods in the core as follows: p
- 1. Determine the change in boron necessary to move rods ,,
from 97% wd to 87% wd from Figure 7 , and convert I
'_-7 this to a batch volume of DI water per the soluble ~
poison concentration control procedure. 17'. As tha control rods approach 97% wd, batch in the
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volume of DI water calcul'ted above. -
- 3. Each time the rods approach 97% wd, batch in another equal volume of DI water until the transient is complete.
d) Power may be decreased at any time by driving in control rods. Design rates, for decrease, can be obtained with
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rods starting i. either band, if rod insertion limits will not be exceeded. Upon reduction in power, APSR's - should be used to minimize imbalance while control rods . are withdrawn with xenon buildup. If return to power will be at <0.5% FP/ min, control rods should be allowed to follow xenon antil they reach the steady-state band. 4.3.1.2.3 Transient Operation (>0.5%/ min) NOTE: /rior to changing unit load, notify the Dispatcher and inform Plant Operating Shift personnel of the impending load change. - a) During transient operation, the reactor control system ~~ will follow step or ramp load changes under automatic ' '- integrated control. 15.0 1123 !95
1102-4 ~' Revision 24 .. 03/2.7/79 --: ~-. b) The combined action of the control system and the turbine bypass system permit a 25% load rejection (10% to the ~,, system and 15% to the condenser) without safety valve - ,I ac tior.. The combined actions of the control system, the ],. turbine bypass valves, and the main steam safety valves
.f are designed to accept separation of the generator from - f,,
the transmission system without reactor trip. .. c) The following represent the typical transients likely to I-be experienced. The general guidance provided below for operating during each transient is based on B&W's recommendations for minimizing imbalance changes while maintaining control rods as high as possible. It is recognized that the Shift Supervisor / Foreman must evaluate system loao requirements and available primary and radwaste water inventories during each transient, to provide the most acceptable operation within the limits of the Tech Spec Rod Index, imbalance and power tilt.
- 1. Power increase at >0.5%FP/ min; assuming control rods were in steady-state band.
a) Determine the change in boron necessary to move the rods from the steady-state band to the transient band from Figure 8 ; and convert this to a feed and bleed volume of f DI water per the soluble poison control procedure. b) Calculate the time required to make the above change. t = Volume of DI to add , Water Volume of MU Tank F & B Flow Rate F & 8 Flow Rate 74 - 16.0 1123 !96
1102-4 Revision 21 2' _8/ll/78 Q NOTE: This amounts to the advance notice required ' prior to performing transients in excess of 15% ' - FP, at greater than 0.5% FP/ min. This time can - vary from 3 hours, for smaller transients,. at '.., , beginning of cycle to 7 hours, for long.er, 'E
. ,g transients, near end of cycle. A 15% load .-
y change at <.5% FP/ min. can be accomplished any ,,.' time without dilution, and still remain in the .-
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long-term or transient operating bands. c) Commence feed and bleed of the DI water as calculated above. When control rods reach the transient band, power may be increased Mr pulling rods manually or under ICS control.
- 2. . Power decreases at >0 5%hnin a) Starting from either the steady-state or transient bands,
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insert the control rods (manually or under ICS control) to reduce power at the desired r.tmp rate. ~ b) At the conclusion 9f the trtas5ent, borate deborate, or allow rods to follow Xenon. &s necessary to place rods in the desired band for anticipated operation. The Shift Supervisor / Foreman shall determine the desired rod index based on system load requirements and primary /radwaste water inventory considerations. Based on the Shift Supervisor / Foreman's decision, recovery can follow either the Unolanned Power Return, or Planned Power Return. 17.0 1107 1 1 L. .) 107
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. .. 1102-4 ,
Revision ' 24 03/27/.79~
- 3. Unplanned Power Return at Nominal Rates, a) Maintain rods, within the transient position band, to ,
preserve return to power capability at nominal ramp -. rates. By keeping the control rods within the transient ~~., T. position band, nominal ramp rates, 'over the entire load . . ' range, can be obtained. Maintaining rods near the top of 'f the transient band will minimize the power irrbalance, and - - . resulting loss of rod worth, thereby, maximizing the ~~ power return capability at nominal ramp rates. b) Use Figure 6 to determine if the manuever is possible. Figure 6 is a plot of minimura feed and bleed dilution rate vs. RCS boron concentration for various load changes. The load change curves indicate if the desired load
, change is possible, at that feed and bleed flow rate, and __
RCS boron concentration, with the ability to return to power at nominal ramp rates. c) Deborate and insert rods to the bottom of the control band just before the power return. Use Figure 7 and the rod position at top of transient band, to determine boron concentration change. d) When return to power is desired, determine the batch volume of boric acid required to increase RCS boron concentration by 18 ppm. e) Commence power increase by pulling rods, batch in the volume calculated above to compensate for Xenon burnout; letdown flow shoui e be at the maximum rate. Continue adding batches of the same size at an effective flow rate
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l123 !98
1102-4 . . . Revision 24 - 03/27/79 ~; c-of 10 gpm until control rods have stopped inserting.on. Xenon burnout. , f) When Xenon burnout is complete, control rods shall be . maintained in the transient band of Figure SA or 58, or
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allowed to follow Xenon to the steady-state band if . . -
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continued steady-state operation is expected. -
- 4. Planned Power Return at Nominal Rates. 'I-
'.i a) Allow Xenon to put rods in the steady-state operating {' ', -
band. Maintain rods in the steady-state band using
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Figure 7. b) Determine the change in baron necessary to move the rods from the steady-state band to the transient band from Figure 8, and convert this to a feed and bleed voluae of DI water per the soluble poison control procedure. c) Calculate the time required to make the above changes as - follows: t = V lume of DI to add , Water Volume of MU Tank F & B Flow Rate F & B Flow Rate - x4 NOTE: This amounts to the advance notice required prior to performing transients in excess of 15% FP changes at greater than 0.5% FP/ min. This time can vary from 3 hours for smaller transients - at beginning of cycle to 7 hours for longer transients near end of cycle. 19.0
. 1102-4 '
Revision 21 " 08/11/78 -: d) Commence feed and bleed of the DI water as calculated above. When control rods reach the transient band, power ._ may be increased by pulling rods.
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e) Determine the batch volume of boric acid required to .. increase RCS boron concentration by 18 ppm. (present . . .' concentration may have to be calculated based on total DI ; water added in Step 4.3.1.2.3.lb because previous additions .'.. : 2 may not be fully mixed. .The change of 18 ppm is used to 7~- - give the operator a head start on Xenon burnout. f) While increasing power at nominal ramp rates, initiate batch boration at 20 gpm intermittantly to average 10 gpm over the duration of the transient. g) Continue with successive operation of reentering the same J batch size of Step e, at 20 gpm at an average flow rate _ of 10 gpm, until control rods have initially stopped inserting on Xenon burnout. _ CAUTION: Do not allow control rods to exceed the control rod LOCA insertion limit. Correct the situation by increasing the batch effective flow rate as necessary. b) Continue to borate until minimum Xenon undershoot has occurred, i.e., rods have stopped moving in due to Xenon burnout.
- 1) Allow Xenon to put rods in the steady-state operating band and continue operation per steady state operation.
20.0 1123 200
1102-4 e Revision 2.4 .1-03/27/79 .?
- 5. Peak Xenon Recovery Capability The limiting power maneuver for the reactor system is a load ..
decrease from rated full power down to 15% power, at nominal ~~' ramp rates, followed by a return to full rated power during ,. the subsequent Xenon peak. Maneuvers of this magnitude are .. seldom seen in normal operation. Normal power changes are 'I-well below the design load changes. The peak Xenon recovery 4.- capability of the system, (at nominal ramp rates), can be determined by observing, on Figure 6 the intersection of a given flow rate with the RCS boron concentration at the appropriate load change curve. RCS boron concentrations, that lie to the left of the above intersection (greater ppm boron), indicate that the desired maneuver can be accomplished at the f.ow rate
, with the capability of returning to power at nominal ramp .
rates at peak Xenon. RCS boron concentrations, that lie to the right of the above intersection, indicate the incapability of the system to accommodate, at that flow rate, the return to power at nominal ramp rates at peak Xenon. This assumes a nominal rod position, within the transient control rod band, before the initial load reduction. Rod positions greater than . nominal will shift the curves, of Figure 6 to the left while rod positions less than nominal will shift the curves to the right. A 15% load reduction followed by a return to power at peak Xenon can be accomplished at any time without need for .- RCS boron dilution. 21.0 1.123 201
1102-4
- ~
Revision 121 08/11/78 - ,7 In summary, the peak Xenon recever capability basic guidelines a - are: ,, . , a) Use Figure 9 to determine if_the maneuver is possible. -- - i-b) Decrease power at nominal ramp rates by driving rods '.
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inward. , c) Refer to Paragraph 4.3.1.2.3.c.4, " Planned Power Return ~f-of Nominal Rates", for return to power. I. :- , 4.3.2 Periodic Operations 4.3.2.1 Conduct surveillance testing as listed on the surveillance
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test schedule in accordance with Administrative Procedure 1010. e M 4 e 22.0 1 1I ^j 7 9
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1102-4 .
. .' Revision 21 - ~
08/11/78 :2
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4.3.2.2 Maintain shift logs in accordance with Administrative Procedure '
#1012. I~
4.3.2.3 Make routine inspections throughout the plant in accordance . _ /I. .
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with applicable Operations Department Special Operating Proce-dures. .. 4.3.3 Power operation with one main feed pump. - 4.3.3.1 Prerequisites
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- 1. Reactor power is less than 60% FP. "[- -
- 2. Operation with one main feed pump 0 660 MWe is desirable and approval is received from Shift Supervisor.
4.3.3.2 Procedure
- 1. Set the voltage on ICS module 1-5-6, power supply number 2, to + 3.2 + 0.1 VDC (660 fMe).
- 2. Power may be increased to 660 MWe with one main feed pump.
- 3. After second feed pump is returned to service, return the main feed pump load limit setpoint to 585 MWe by the following procedure:
(1) Set the voltage on ICS module 1-5-6, power supply number 2, to + 1.7 + 0.1 VDC. 23.0 1123 203
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.- 07/16/79 ENCLOSURE I MECHANICAL MANEUVERING RECOMMENDATIONS TMI-l The following are the recommended maneuvering limits for TMI-1, Cycle 5;
- 1. The maximum rate of power increase below 20% full power shall be 10% per hour.
- 2. Above 20% power, normal operating procedures (Tech Spec Limits) will apply unless the reactor has operated at less than 20% power for more than 48 hours.
- 3. If the power level has been below 20% full power for greater than forty-eight (48) hours, the maximum rate of power increase above 20% full power shall be 30% per hour with a five (5) hour hold at 20% full power below the power level cutoff and five (5) hour hold at the power level cutoff. These holds can run concurrently with holds required by the Technical Specification.
, 4. During the initial power escalation at cycle startup or immediately following a control rod interchange, the initial escalation above the 40% full power shall be limited to 3% per hour, with a five (5) hour hold at the power level cutoff. This hold can run concurrently with Technical Specification holds where applicable.
- 5. During the initial power escalation at cycle startup and if required, immediately following a control rod interchange, a PIDC test shall be run at 40% full power. Escalation above the 75% full power shall then be limited to 5% per hour, with a five (5) hour hold at the power level cutoff.
- 6. With the exception of Items 4 and 5 above, no restrictions are placed on required physics startup tests.
38.0 l!2; 218
% 1102-4 j;
f.. Revision 25 07/16/79-Enclosure 2 Operation to Ensure Adequate Nuclear Instrument Accuracy
- 1. Safety analysis calculations assume a maximum nuclear instrument error of 4% (power calculated by heat balance minus power indicated by the nuclear instruments).
- 2. Operating experience at some plants has shown '. hat this error may exceed 4% during and following certain transients. Generaliy, the nuclear instruments tend to read low following a power increase, with the magnitude of the error proportional to the magnitude of the power change.
- 3. To assure compliance with safety analysis assumptions, the following operating requirements must be observed:
A. During Startup Perform heat balance checks (and N.I. adjustments where necessary)
, per 1302-1.1 at 15-30, 70, 90 and 100% power.
NOTE: These power levels are approximate and may vary a few percent to accommodate normal evolutions). B. During Steady-State Operation (Power maintained within a 5% band and no rod index change greater than 15% since the last heatbalancecheck). Perform a heat balance check (and N.I. adjustment where necessary) once per shift. C. During Non-Steady-State Operation (Power Increase) Perform a heat balance check (adjustment) immediately upon reaching steady state pcwer, and then at two to three hour intervals until the calibration has stabilized. 39.0 4 il '19}}