ML20073R495

Procedure OP/1/A/6100/05, Unit Fast Recovery

ML20073R495
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/02/1983
From:	DUKE POWER CO.
To:
Shared Package
ML20073R489	List: ML20073R486 ML20073R495 ML20073R502 ML20073R508
References
NUDOCS 8305040240
Download: ML20073R495 (9)

Text

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• t OP/1/A/6100/05 PAGE 1 0F 9 DUKE POWER COMPANY McGUIRE NUCLEAR STATION UNIT FAST RECOVERY 1.0 . Purpose The purpose of this procedure is to define the cause and/or actions resulting in a Reactor Trio and/or Shutdown. This procedure defines the corrective action taken to remedy the Reactor Trip and/or Shutdown and outlines the steps necessary to return the unit to power. This procedure may be used provided:

1) The Reactor Startup is to begin within sixteen hours after the Reactor Trip and/or shutdown occurred.

2) Cooldown has not been initiated oer controlling procedure for Unit Shutdown (OP/2/A/6100/02).

Sections included in this procedure are:

3.0 Cause of Reactor Trip and/or Shutdown AND Corrective Actions Taken.

4.0 Fast Recoverv Procedure.

2.0 Limitations and Precautions

2.1 Refer to McGuire Limitations and Precautions (OP/0/A/6100/08), as applicable.

2.2 Do not exceed a stable startup rate of 1 DPM.

2.3 Overlap between source and intermediate and between intermediate and power range shall not be less than one decade.

2.4 If reactor startup is not initiated in sixteen (16) hours, OP/1/A/6100/01 (Controlling Procedure for Unit Startup) shall be used for unit startup.

2.5 Whenever there is a thermal power change exceeding 15% of the rated thermal power within a one hour period, Primary Chemistr.y must be

, notified to take an isotopic analysis for fodine following the power 8305040240 830502 PDR ADDCK 05000369 S PDR

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. OP/1/A/6100/05

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change, and Health Physics must be notified to samole and analyze the unit vent per T.S. 4.11.2.1.2.

3.0 Cause of Trio / Shutdown and Corrective Action Taken 3.1 Initial Conditions

/ 3.1.1 AP/1/A/5500/01 (Reactor Trip) and/or applicable steps in  !

OP/1/A/6100/02 (Controlling Procedure for linit Shutdown) have been completed.

3.2 Procedure 3.2.1 Date Time of reactor trip and/or shutdown. .

3.2.2 The cause of the reactor trip and/or shutdown was an operational errnr, equipment failure, etc. Explain in detail:

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. OP/1/A/6100/05 PAGE 3 0F 9 3.2.3 The corrective a'ction taken was reoair equipment, procedure change etc. Explain in detail:

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4.0 Fast Recovery Procedure 4.1 Initial Conditions

/ 4.1.1 The reactor is to be restarted within sixteen (16) hours after the trip and/or shutdown.

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/ 4.1.2 Cooldown has not been initiated per Controlling Procedure for Unit Shutdown (OP/1/A/6100/02).

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OP/1/A/6100/05 PAGE 4 0F 9

/_ 4.1.3 The main turbine-generator is coastino down or on the turning gear.

/ 4.1.4 Two licensed Reactor Operators are in the Control Room.

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4.1.5 The Steam Dumo Control is set at 1092 osig and transferred to pressure control.

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/ 4.1.6 Tech. Spec Action Log has been reviewed for items that may effect entering Modes 2 or 1.

4.2 Procedure Date Time' Initial 4.2.1. Perform startup surveillance testing as follows:

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4.2.1.1 If MG sets are not in service then proceed to Step 4.2.1.4

/ 4.2.1.2 Insert all control rods per OP/1/A/6150/08 (Rod Control).

I, 1:

/ 4.2.1.3 Shutdown both MG sets per OP/1/A/6150/08 (Rod Control).

/ 4.2.1.4 Perform PT/1/A/4600/56 (Manual Reactor Trip Functional Test) unless it has baen completed within the orevious seven days. ,

/ 4.2.1.5 Ensure IAE has completed channel functinnal tests on the following if not performed within the previous seven days:

, 1) Intermediate Range, Neutron Flux

2) Source Range, Neutron Flux

3) Reactor Trip Breaker

/ 4.2.1.6 Ensure IAE has completed channel functional tests on

OP/1/A/6100/05 PAGE 5 0F 9 the following if not performed within the orevious 92 days:

1) Intermediate Range, P6 Interlock

2) Reactor Trip, P4 Interlock

/ 4.2.1.7 One rod position indicator is ooerable per Tech. Spec.

3.1.3.3.

4.2.2 Ensure IAE has completed the following prior to entering Mode 1:

/ 4.2.2.1 Channel functional tests on the following if not completed within the previous seven davs:

1) Tur5f ne Trip, Low Fluid Oil Pressure

2) Turbine Trip, Stop Valve Closure

/ 4.2.2.2 Channel functional tests on the following if not comoleted within the orevious 92 davs:

1) Power Range, P7 Interlock *

2) Power Range, P8 Interlock

3) Power Range, P10 Interlock

/ 4.2.3 Determine the desired estimated critical rod height and corresponding boron concentration per OP/0/A/6100/06 (Reactivity Balance Calculation).

NOTE NC Systen boron concentration shall not be reduced below the value required to maintain 1.6% Delta k/k shutdown margin at xenon free hot standby conditions unless the shutdown banks are fully withdrawn. When possible, the shutdown banks should be withdrawn during any boron concentration change.

-/ 4.2.4 Adjust NC Systen boron concentration as required in Step 4.2.3 i

per OP/1/A/6150/09 (Boron Concentration Control) or OP/1/A/6200/02 (BTRS).

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OP/1/A/6100/05 PAGE 6 0F 9

/ 4.2.5 When desired, start one Feedwater Pump oer OP/1/A/6250/01 (Condensate and Feedwater System) and secure Auxiliary Feedwater per OP/1/A/6250/02 (Auxiliary Feedwater System) when desired, and align system per Enclosure 4.1 (Alignment for Standby Readiness).

NOTE If CA Pumps received an auto start signal and Train "A" and Train "B" Modulating Valve resets were placed in " Reset" when securing CA, return both Train "A" and Train "B" resets to

" Normal".

/ 4.2.6 When main feedwater is in service, match the steam generator levels and programmed level, then place feedwater bypass control valves in automatic when desired.

/ 4.2.7 After Step 4.2.1 is complete, place the MG sets in service per i

OP/1/A/6150/08 (Rod Control).

/ 4.2.8 Set the highest reading source range and intermediate range channels to record on the Nuclear Instrumentation Recorder (NR-45).

/ 4.2.9 Close or verify closed the reactor trio breakers and withdraw the shutdown banks to 100% withdrawn per OP/1/A/6150/08 (Rod Control ) .

/ 4.2.10 Defeat the " Source Range High Flux Level at Shutdown" alarn by the manual block switch on each of the source range drawers.

/ 4.2.11 Verify the " Source Range High Shutdown Flux Alarm Blocked" annunciator is illuminated.

/ 4.2.12 Comolete Enclosure 13.2 of PT/1/A/4600/08 (Precriticality Surveillance Requirements for Unit Startuo).

OP/1/A/6100/05 PAGE 7 0F 9 l l

/ 4.2.13 Announce over the paging system that a recorder startup has commenced.

/ 4.2.14 Set NR-45 Recorder Chart Speed to Hi, NOTE If criticality is attained below the control rods' low insertion limit, reinsert all control rods and refer to OP/0/A/6100/06 (Reactivity Balance Calculation).

If criticality attained above the control rods' low insertion limit, but below the estimated critical position (ECP) lower band, notify reactor personnel (within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) and continue normal operation.

If criticali~ty is not attained prior to exceeding the uoper band of ECP, stop withdrawing rods and recheck ECP calculations. If calculations are not in error, criticality must be approached using OP/0/A/6150/13 (1/M Approach to Critical).

/ 4.2.15 Withdraw the Control Rod Banks per OP/1/A/6150/08 (Rod Control) to attain criticalitv.

, 4.2.16 Perform the following steps while increasing reactor power to 1 x 10-8 amps.

/ 4.2.16.1 Select both IR channels to record on NR-45 when power is greater than 1 x 10-10 amos and "P-6 IR Permissive" lamos is illuminated.

/ 4.2.16.2 Block the S.R. High level trip and high voltage by placing both SR select switches to " Block".

/ 4.2.16.3 Verify the "SR Train A (8) Trip Blkd. Hi Voltage Off" pennissive lamps illuminated.

/ 4.2.17 With reactor power leveled out at 1 x 10-8 an s record the following data: Time Rod Position Tave *F

OP/1/A/6100/05 PAGE 8 0F 9 Boron Concentration opm Record the followino if OAC is operational:

Xenon Worth pcm Samarium Equil. Difference ocm.

/ 4.2.18 Verif.v H blanket 2

on NCDT per OP/0/A/6500/01 (Liquid Waste).

/ 4.2.19 Select one PR Channel to record NR-45 Recorder and return NR-45 Recorder to slow speed.

/ 4.2.20 Increase reactor power to 3%. If necessarv continue heatup to no-load Tave.

/ 4.2.21 Align and startup the MSR's per OP/1/8/6250/11 (Moisture Separator Reheater Operation) concurrent with the Turbine Generator.

NOTE Do not exceed 600 RPM until no-load Tave is attained.

/ 4.2.22 Bring the main turbine to 1800 RPM per OP/1/A/6300/01 (Turbine Generator). Do not allow Tave to decrease below 551*F.

NOTE Refer to Data Book, Section 1.3 (Fuel Maneuvering Limits) for rate at which power level can be changed.

/ 4.2.23 Increase reactor power to about 6% for a cold turbine start.

/ 4.2.24 Increase reactor oower to about 12% for a hot turbine start.

/ 4.2.25 Parallel the unit to the system per OP/1/A/6300/01 (Turbine Generator Operation).

/ 4.2.26 When the steam dump valves close, transfer the Steam Bypass Mode selector switch to Tave control.

/ 4.2.27 With reactor power greater than or equal to 10%, verify "P-10 Nuclear at Power Permissive" light illuminated, "P-13 Lo Turb.

. OP/1/A/6100/05 PAGE 9 0F 9 Impulse Press Permissive" light off, and "P-7 Lo Power Trip Block" light off.

/ 4.2.28 Block the intermediate range high level trip and rod stop by depressing both " Intermediate Range Block" oushbuttons. Verify both "I/R Trip Blocked" lights illuminated.

/ 4.2.29 Block the power range lo Setpoint trip by depressing both

" Power Range Block" pushbuttons. Verify both "P/R Lo Setpoint Trio Blocked" lights illuminated.

/ 4.2.30 At approximately 183 MWE, transfer automatic feedwater control from the bypass control valve to the main feedwater control valve for each steam generator as follows:

NOTE Transfer should be made over a period of approximately 5 minutes to reduce oscillations.

4.2.30.1 With Main Feedwater Control Valve in manual, throttle open Main Feedwater Control Valve until main feedwater bypass control valve slowl.y closes.

When main feedwater bypass control valve closes, place Man / Auto station on Bypass Control to minual.

Place Main feedwater Control Viv. in auto and verify proper operation.

/ 4.2.31 When "C-5 Lo Turb. Impulse Press Rod Blk" light is out, ad.iust Tave to within 1*F of Tref and transfer rod control to automatic if desired.

, / 4.2.32 Place the Turbine Exhaust Hood Spray Switch to "0FF".

/ 4.2.33 Notify HP to sample Unit Vent per Tech. Spec. Surveillance requirement 4.11.2.1.2.

/ 4.2.34 For further oower increase refer to OP/1/A/6100/03 l (Controlling Proc dure for Unit Operation),

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