ML20066C811

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Rev a to IOP-3,Turbine Startup & Generator Synchronization
ML20066C811
Person / Time
Site: 05000605
Issue date: 01/09/1991
From: Torres W
GENERAL ELECTRIC CO.
To:
Shared Package
ML20066C783 List:
References
23A6169AC, 23A6169AC-RA, NUDOCS 9101110233
Download: ML20066C811 (11)
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Text

{{#Wiki_filter:. _ - l , . i GE Nuclear Energy 23A6169AC . 39 wo, 1 i* 3 Rtv A I i i REWWON STATUS SHEET i l DOCUMENT TITLE IOP-3. TURBINE STARTUP AND GENERATOR SYNCHRONIZATION 1 1 LEGEND OR DESCRIPTION OF GROUPS TYPE: OPERATING PROCEDURE l FMF: K0/7 MPL rTEM NO: A8>3020 i REVISIONS I l l A PRELIMINARY ISSUE PER gag

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REY A TABLE OF CONTENTS 1 RADA

1. SCOPE / APPLICABILITY 3
2. DISCUSSION 3
3. PRECAUTIONS AND LIMITATIONS -3 4, PREREQUISITES 4
5. PROCEDURE 5 5.1 General Procedure 5 5.2 Power increase to Rated Flow Control Line 6 4

5.3 Power increase Along Flow Control Line to Rated Power 6 5.4 Power Decrease Along Flow Control Line 6 5.5 Power Decrease By Control Rod Insertions 7

6. REFERENCES 8 ATTACHMENT 1. Generator Estimated Capability Curve.(typical)

ATTACHMENT 2. Time for Load Changes Curve (typical) ATTACHMENT 3. Power to Core Flow Map (PAE design basis) i i- 

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Arv A l 1.0 SCOPE / APPLICABILITY This procedure provides detailed instructions and limitations for varying reactor power, both increasing and decreasing, when operating above (45%) of rated thermal power. 2.0 DISCUSSION This procedure provides a means for organizing the many diversified activities associated with power plant operation for efficient reactor power ascension and power maneuvering. This procedure will normally be integrated into an overall pl ant startup. Integrated Operating Procedures 

            ' Approach to Criticality *(IOP 1), 'Heatup and Pressurization"(IOP 2), and
            ' Turbine Startup and Generator Synchronization" (IOP 3), should be initiated in such a manner so as to provide an uninterrupted succession from one procedure to another, in addition, plant shutdown from [35%)

power shall normally be conducted in accordance with ' Unit Snutdown to Unit Off-Line, Main Condenser Available"(IOP 5). 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Steady stats operating values of the following parameters shall be maintained within the limits specified:

a. MCPR 1.23(minimum)
b. LHGR later(peak)
c. Peaking Factors l

l 1. Gross later(maximum) l 2. Local later l 3. Total later

d. Generator output 1356 MW(e)
e. Total steamflow 764.37 x 104 kg/hr
f. Total Feedwater flow 762.73 x 104 kg/hr
g. Core coolant flow 58.0 x to 6 ton /hr h

1. Steam dome pressure Final feodwater temperature 72.1 kg/cm 2(g) 215.7 'O ll 3.2 Core thermal power as a function of core flow shall be maintained within the allowable operating limits as shown on the Power to Flow Operating Map.

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                  &                 GE Nuclear Energy 23A6169AD AEV    A SHPC. 4 3.0 PRECAUTIONS AND LIMITATIONS (continued) 3.3 Any control rod movements are to be performed in accordance with approved rod sequence.

3.4 Do not allow main condenser pressure to exceed 127 mm Hg absolute. Hold or reduce load as necessary to maintain condenser pressure less than 127 mm Hg absolute. 3.5 Maintain reactor water chemistry within the following limits: l Chlorides < 10 ppb Conductivity at 25 *C < 0.20 pS/cm pHat25*C 6.4 - 7.8 Dissolved Oxygen < 200 ppb Silica (SiO2) < 100 ppb Sulfate < 10 ppb TotalIron (Fe) < 10.0 ppb Copper (Cu) < 0.5 ppb - All other metals < 4.5 ppb 3.6 Maintain feedwater chemistry within the following limits: l Chlorides < O.16 ppb Conductivity at 25 *C < 0.057 pS/cm Dissolved Oxygen 20.0 - 30.0 ppb l Silica (SiO2) < lator ppb l Sulfate < 0.16 ppb l Iron, insoluble (Fe) < 1.0 ppb Iron, soluble (Fe) < 0.1 ppb Total Copper (Cu) < 0.05 ppb-l All other metals < 0.35 ppb 4.0 PREREQUISITES 4.1 Plant conditions shall be as established by IOP 3, " Turbine Startup and Generator Synchronization". 4.2 Load changes should normally be made as directed by the Power Generation Control System (PGCS), except for emergency load reductions as directed by the [ Control Room Shift Supervisor). l r 7 ------#w - m up aw-ww

i e . 2 i 0 GE Nuclear Energy 23AC169AD Ary A DH No $ 5.0 PROCEDURE 5.1 General Procedure 5.1.1 Perform the following surveillance tests at the Indicated conditions and time Intervals: a [ Core thermal rpargins, later).

b. [ Selected Reactor Trip System scram setpoints and Automatic Rod Block Monitor setpoints, later).
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c.  ; Reactor water sample and off gas sample analyses.

ater),

d. [ Neutron Monitoring System,later).

e [ Main Generator Power Load Linbalance test, later).

f. [Other required surveillance tests, later).

5.1.2 Attor each control rod is fully withdrawn, perform a rod coupling check. If a rod is uncoupled, stop further rod withdr::wal and core flow increase and refer to [later, procedure for rod uncoupled). 5.1.3 Monitor the Off Gas System pre treatment and post treatment activity peaks during and after power chanoos and/or rod movements. 5.1.4 Maintain ganerator loading within the limits of the Generator Capabliity Curve (Attachment 1). Verify that a power change request will not cause operation outside of the Gonerator Capability Curve. 5.1~.. Whenever possible, generator load increases and decreases should be performed within the Time for Load Changes Curve (Attachment 2). 5.1.6 Start (stop) additional condensate filter /demineralizers as neeoed to maintain [specified,later) kg/cm2 across the in service units. l t 

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                                    -                                                                                                                          1 23A6169AD         sH No. 6 Arv    A                     ;
!                                                      5.2    Power Ir. crease to Rated Flow Control Line 5.2.1 Initiate control rod withdrawal as necessary to increase reactor

, power to [45%).

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5.2.2 increase the speed of the recirculation pumpe to [40)%

5.2.3 Place the low pressure drain pumps (LPDPs) and the high pressure drain pumps (HPDPs) into service in accordance with SOP -{later). 5.2.4 Rerume control rod withdrawals to establish the rated rod pattern. 5.3 Power increase Along Flow Controi Line to Rated Power 5.3.1 Transfer the Recirculation Flow Control System to the Auto . Flow Control mode in accordance with SOP-B34/081. S.3.2 initiate power increase by increasing recirculation flow along the flow control line until the specified power level is reached. 5.3.3 When generator load is greater than [65% turbine load), with the second stage reheater in service, verify the following valves have opened: Main steam to second stage reheater control valves on both WS/Rs, L A T E R ). 5.3.4 At steady-state power generation, adjust control rod positions as necessary to compensate for xenon transients.

5.4 Power Decreases Along Flow Control Line 5.4.1 If plant shutdown is planned and Primary Containment entry is anticipated, commence de-Inerting of the primary containment, i

5.4.2 Initiate recirculation flow decrease. Observe that recirculation j flow decreases and verify that power decreases at the selected i rate, i 5.4.3 Decrease recirculation flow until the recirculation pump speed has been decrcased to [40%). . I 

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c 1 f i 5.5 Power Decrease By Control Rod insertions 5.5.1 Transfer the Recirculation Flow Control System to the Manual l Flow Control Mode in accordance with  ! SOP-834/C81. 5.5.2 initiate power decrease to the specified level [50)% by i inserting control rods in the selected sequence. 5.5.3 When generator load has been reduced below [65%) turbine i i load, verify that the following valves are closed: l i Main steam to second stage reheater control valves on both MS/Rs, L A T E R ). , 4 I 5.5.4 At [50%) power, reduce the speed of the recirculation pumps to [30]% 5.5.5 Stop the HPDPs and LPDPs in accordance with SOP-{ tater). 5.5.6 Continue control rod insertions until reactor power has been decreased to [45)%. During the power decrease, perform step 5.5.6. 5.5.7 Continus power reductions in acoordance with IOP-5, " Unit Shutdown to Unit Off-Line, Main Condenser Available", if desired. 1 i

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  • 23A6169AD SH M. 8 REV A

6.0 REFERENCES

6.1 Starting and Loading instructions for Nuclear Unit Steam Turbines . (later), 6.2 Large Steam Turbine Driven Generators (later). 6.3 Reactor System Heat Balance,23A4562, Revision 1, 6.4 GETAB Operating Limits,38 FHA 981, Revision B. 6.5 Water Quality Specification,22A8479, Revision 2, PAE No.~ 1.A.9. l i f i I l l 

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    ,                                                                                   23A6169AD    sH No. 9 Arv    A LATER L-ATTACHMENT 1. Generator Estimated Capability Curve (typical) l l

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nu n LATER-- i ATTACHMENT 2. Ime for Load Changes Curve (typleal) _m.m.-..m

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  ,                                                           23A01$9AD     SH W 11 tirv   A LATEF1 ATTACHMENT 3. Power to Core Flow Map (PAE design basis)
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