ML20066C813

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Rev a to IOP-4,Power Ascension & Power Changes
ML20066C813
Person / Time
Site: 05000605
Issue date: 01/09/1991
From: Torres W
GENERAL ELECTRIC CO.
To:
Shared Package
ML20066C783 List:
References
23A6169AD, 23A6169AD-RA, NUDOCS 9101110234
Download: ML20066C813 (11)
v • d • e


Text

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i DOCUMENT TITLE LOP-4, POWER ASCENSION & POWER CHANGES LEGEND OR DESCRIPTION OF GROUPS TYPE: OPERATING PROCEDURE

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& GE Nucleer Energy RW A t TABLE OF CONTENTS DACR

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 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) 1

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1.0 SCOPE / APPLICABILITY This procedure provides detailed instructions and limitations for varying reactor Sower, both increasing and decreasing, when operating above

[45%) o' rated thermal power.

2.0 DISCUSSION This procedure provides a means fo" 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 plant startup, integrated Operating Procedures

' Approach to Criticality *(IOP- 1), 'Heatup and Pressurization *(IOP 2), and -

" Turbine Startup and Generator Synchronization" (LOP 3), should be initiated in such a mannor so as to provide an uninterrupted succession from one procedure to another. In addition, plant shutdown from (35%)

Sower shall normally be conducted in accordance with ' Unit Shutdown to Jnit Off-Line, Main Condenser Available"(IOP 5).

j 3.0 PRECAUTIONS AND LIMITATIONS '

3.1 Steady state operating values of tha following parameters shall be ,

maintained within the limits specified;

a. MCPR 1.23(minimum)
b. LHGR later(peak)
c. Peaking Factors 1
1. Gross later(maximum) .
2. Local later
3. Total later l d. Generator output 1356 MW(e)
e. Total steamflow 764.37 x 104 kg/hr i
f. Total Feedwater flow 762.73 x 104 kg/hr ,
g. Core coolant flow 58.0 x 108 ton /hr h Steam dome pressure 72.1 kg/cm 2(g) l l.
l. . Final feedwater temperature 215.7 *C 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 1 Operating Map.  ;

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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 a!Iow 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 'O < 0.20 pS/cm pHat25'O 6.4 - 7.8 Dissolved Oxygen < 200 ppb ,

Silica (SIO2) < 100 ppb '

Sulfate < 10 ppb Total tron (Fe) < 10.0 ppb Copper (Cu) < 0.5 ppb .l All other metals < 4.5 ppb 3.6 Maintain feedwater chemistry within the following limits: l 9

Chlorides < 0.16 ppb Conductivity at 25 'C < 0.057 pS/cm Dissolved Oxygen . 20.0 - 30.0 ppb Silica (SiO2) < later ppb Sulfate < 0.16 ppb Iron, insoluble (Fe) < 1.0 ppb Iron soluble (Fe) < 0.1 ppb.

Total Copper (Cu) < 0.05 ppb 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).

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r O GE Nuclear Energy 23A6169AD SHNo. 5

- A Arv 5.0 PROCEDURE 5.1 General Procedure 5.1.1 Perform the following surveillance tests ut the indichied conditions and time intervals:

a (Core thermal margins,later).

b. [ Selected Reactor Trip System scram setpoints and Automatic Rod Block Monitor setpoints, later).
c. LReactor water sample and off-gas sample analyses, ater).
d. [ Neutron Monitoring System, later).

e [ Main Generator Power Load Unbalance test, later),

f. [Other required surveillance tests, later).

5.1.2 After each control rod is fully withdrawn, perform a rod coupling check.11 a rod is uncoupled, stop further rod withdrawal and core flow increase and refer to [later, procedere for rod uncoupled).

5.1.3 Monitor the Off Gas System pre treatment and post treatment activity peaks during and after power changes and/or rod movements.

5.1.4 Maintain generator loading within the limits of the Generator  !

Capability Curve (Attachment 1). Ver19 that a power change request will not cause operation outside of the Generator Capability Curve.

5.1.5 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 /demineralizere is needed to maintain [specified,later) kg/cm2 across the in service units.

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& GE Nuclear Energy 23As19AD pry A s4 NO. 6 5.2 Power increase to Rated Flow Control Line 5.2.1 initiate control rod withdrawal as necessary to increase reactor power to [45%).

5.2.2 inc,rease the speed of the recirculation pumps 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 Resume control rod withdrawals to establish the rated rod pattern.

5.3 Power increase Along Flow Control Line to Rated Power 5.3.1 Transfer the Recirculation Flow Control System to the Auto 4 Flow Control mode in accordance with SOP-B34/C81.

5.3.2 Initiate power increase by increasing recirculailon flow along the flow control line until the specified power levelis reached.

5.3.3 When gen'erator Ioad 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 G'Rs L A T E R].

i 5.3.4 At steady-state power generation, adjust control rod positions as necessary to compensate for xenon trans!ents.

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 j containment.

5.4.2 initiate recirculation flow decrease, Observe that recirculation flow decreases and verify that power decreases at the selected rate.

i 5.4.3 Decrease recirculation flow until the recirculation pump speed has been decreased to [40%).

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! 5.5 Power Decrease By Control Rod insertions -

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! 9.5.1 Transfer the Recirculation Flow Control System to the Manual Flow Control Mode in accordance with SOP-B34/C81. -

! 5.5.2 initiate power decrease to the specified level [50)% by . [

,! inserting control rods in the selected sequence. '

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) 5.5.3 When generator load has been reduced below [65%) turbine  !

j' load, verify that the following valves are closed:

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Main steam to second stage reheater control valves on both -i US/Rs, L A T E R ).  ;

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5.5.4 At [50%) power, reduce the speed of the recirculation pumps to l

[30]%. i

5.5.5 Stop the HPDPs and LPDPs in accordance with SOP-[later).

5.5.6 Continue control rod insertions until reactor power has been  ;

decreased to (45)%. During the p0wer decrease, perform step

,l 5.6.6.  !

J 5.5.7 Continue power' reductions in accordance with IOP-5, " Unit Shutdown to Valt Off-Line, Main Condenser Available*, if desired. '

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& GE Nucient Energy AFV A 6.0 REFERENCEtt 6.1 Starting and Leading Iristructions for Nuclear Unit Steam Turbines (later),

i 6.2 Large Steam Turbine Driven Generators [later).

6.3 Reactor System Heat Balar.ce,23A4562, Revision 1.

6.4- GETAB Operating Limits,386HA981, Revision B.

6.5 Water Quality Specification,22 A8479, Revision 2, PAE No.1.A.9. l q

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i-i ATTACHMENT 1. Generator Estimated Capability Curve (typical) i

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23A6169AD SH No. 10 .

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ATTACHMENT 2. Time for Load Changes Curve (typical)

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ATTACHMENT 3. Power to Core Flow Map (PAE design basis)

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