ML20066C823

Rev a to IOP-9,Maintaining Hot Standby or Hot Shutdown

ML20066C823
Person / Time
Site:	05000605
Issue date:	01/09/1991
From:	Torres W GENERAL ELECTRIC CO.
To:
Shared Package
ML20066C783	List: ML20066C781 ML20066C799 ML20066C803 ML20066C806 ML20066C809 ML20066C811 ML20066C813 ML20066C815 ML20066C817 ML20066C818 ML20066C820 ML20066C823 ML20066C826
References
23A616AJ, 23A616AJ-RA, NUDOCS 9101110245
Download: ML20066C823 (8)

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GE Nuclent Energy ,,u, ,w , , , mry A REYlllON ETATUS SHEET DOCUMENT TITLE IOP-9. MAINTAINING HOT STANDBY OR HOT SHlJTDOWN LEGEND OR DESCRIPTION OF GROUPS TYPE: OPERATING PROCEDURE FMF: KS/7 MPL fiEM NO: A8ta-3020 i i REVlBIONS l A PRELIMINARY ISSUE PER GAB ERM - DMH-3234 765 i i i PRINTS TO i MADE BY APPROVALS DEPT LOCATION W B TORRES C K TANO ' GE NUCLEAR ENERGY SAN JOSE CHKD BY ISSUED SHEET 2-F E WILHEMI O A BAYLIS 3 l

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t i I ' i TABLE OF CONTENTS ', i i i a 4 QEut i i

1. SCOPE / APPLICABILITY 3 l

i. ! 2. DISCUSSION 3 t

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! 3. PRECAUTIONS AND LIMITATIONS 4  !

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4. PREREQUISITES S-

S. PROCEDURE

6 - 1 5.1 Maintaining Hot Standby 6 I i 5.2 Maintaining Hot Shutdown 7 ,

6. REFERENCES 8 1

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Q GE Nuclear Energy AEV A 1.0 SCOPE / APPLICABILITY This procedure provides the detailed instructions for maintaining the reactor in either the Hot Standby or the Hot Shutdown condition, using the main condenser or the suppression pool as the primary heat sink. 2.0 DISCUSSION lt is assumed that the desired reactor temperature and pressure conditions I have been established prior to entering this procedure by completion of IOP 8, " Unit Off.Une to Hot Standby or Hot Shutdown". The plant conditions of Hot Standby and Hot Chutdown are defined as follows: Condition Mode Switch Position Avernoe Reactor CootantTemoerature Hot Standby STARTUP/ HOT STANDBY Any temperature Hot Shutdown SHUTDOWN > 93 'O In the Hot Standby condition, the reactor is critical with the MSIVs open. In the Hot Shutdown condition, all control rods are fully inserted and the MSIVs may be either open or closed. The steps in this procedure are intended to be operation guidelines for maintaining the reactor in either state. As such, the steps need not be performed in the sequence listed.

GE Nuclear Energy , 23A6169AJ sH Mo 4 AEV A 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Operation in a Hot Standby or Hot Shutdown condition with reactor pressure greater than 28 kg/cm2 should be minimized to prevent excessive thermal stresses due to high differential temperature between feedwater and saturation temperature of the reactor coolant. 3.2 While operating in the Hot Standby condition with the reactor critical, closely monitor the neutron instruments for indicated changes in reactivity or power due to xenon transients, insert control rods as necessary to prevent Inadvertent power increases. 3.3 Operation of the reactor in the Hot Shutdown or in Hot Standby with reactor coolant tem >erature greater than 93 'O should be with the reactor maintained n a vented condition via steam flow through the turbine bypass valves. This will prevent non condensible gas buildup in the reactor coolant. 3.4 Operation of the reactor in the Hot Standby condition should be performed with a minimum amount of steam flow through the turb!ne bypass valves. This willlimit the amount of cold feedwater flow to the , reactor vessel for makeup. 3.5 Maintain reactor water chemistry within the following limits: l Chlorides < 10 ppb Conductivity at 25 *C < 0.20 S/cm 4 pH at 25 '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 All other metals < 4.5 ppb t

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3.0 PRECAUTIONS AND LIMITATIONS (continued) 3.6 Maintain feedwater chemictry within the following limits: l Chloridas < 0,16 ppb l Conductivity at 25 *C < 0.057 pS/cm l Dissolved Oxygen 20.0 - 30.0 ppb  ; Silica (SiO2) < later ppb ' Sulfate < G,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 PR EREQUISITES - The reactor is operating in the Hot Standby condition as established per IOP 8, " Unit Off Line to Hot Standby or Hot Shutdown", i L i 4

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GE Nuclear Energy 23A6169AJ SH NO . 6 Rrv A 5.0 PROCEDURE The steps in this procedure are intended as guidelines and need not be - performed in the sequence listed. 5.1 Maintaining Hot Standby It is desired to raalntain the reactor pressure at approximately 28 kg/cm2 to minirnize the temperature differential between the feedwater and the reactor, to provide steam to auxiliary systems, and to maintain the HPCP feed capability. 5.1.1 Maintain the Reactor Recirculation Pumps at minimum speed [ 30%). 1 5.1.2 Maintain the reactor water levelin the normal operating range of 425.5 cm to 44c.5 cm on the Narrow Range water level  ; instruments. Verify that reactor water levelis being controlled 1 with one LPCP and one HPCP in the Low Flow Control Mode per SOP-C31 and SOP-{later). 5.1.3 To minimize the effect of feedwater cyclings on the feedwater nozzle, perform the following steps: 5.1.3.1 Establish a CUW reject flow of [later, mNhour) to the main condenser, and , 5.1.3.2 Set the setpoint of the Pressure Regulator at the desired pressure and uslag the manual Jack, open ' bypass valve No.1 to [20-30 % ) position. 5.1.4 Adjust control rod poshion as necessary to maintain the reactor critical on [ SRNMS heating range ). 5.1.5 If directed, proceed to IOP-10," Unit On-Line from Hot Standby or Hot Shutdown *, or to IOP-6, 'Cooldown to Cold Shutdown, Main Condenser Available*, _ -- __i___.m_ _ . _ - _ _ _ . _ _

4 , 4 GE Nuclear Energy 23A6169AJ sH No. 7 Arv A 1 5.2 Maintaining Hot Shutdown 5.2.1 Maintain the Reactor Recirculation Pumps at minimum speed [ 30%). 5.2.2 When reactor pressure falls below [40 kg/cm? and decreasing, control reactor water level in the Startup Leve' Control mode with one LPCP and onc HPCP. Refer to SOP-C31 and SOP-(later). , 5.2.3 Maintain reactor pressure at the desired pressure by performing the foll0 wing steps: 5.2.3.1 To minimize the effect of feedwater cyclings on the feedwater nozzle, perform the following steps:

                                                      -      Establish a CUW reject flow of [later, m3/ hour) to Radwaste, and
                                                      -      if the main condenser is available, set the setpoint of the Pressure Regulator at the desired pressure and using the manual Jack, open bypass valves No.1 to l20-30 % )

position. 5.2.3.2 If the main condenser is NOT available, maintain pressure by performing the following steps: Operate the RCIC System in the Test Mode per SOP E51," Reactor Core Isolation Cooling System", Supplement pressure control by using the Reactor Safety Rollet valves if necessary; open the SRVs in the following sequ6nce, as required: [later) Control suppression pool temperature to below [ limit,later) by operating the RHR System in the Suppression Pool Cooling Mode per SOP E11,

• Residual Heat Removal-System *.

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1 s , e Os (d \ GE Nuclear Energy nA6169AJ sH m 6 nry A 5.2 Maintaining Hot Shutdown (oonunued) 5.2.4 If the MSIVs are open and if the decay heat load decreases such that reactor pressure can not be maintained at the desired pressure, perform the following: Close main steam drain valves B21-F152 and F211. ll Shltt the turbine gland sealing steam from the Steam Seal Evaporator to the Auxiliary Boller. CAUTION Do not start the Mechanical Vacuum Pumps until both of the turbine-driven reactor feedpumps have been cecured and all turbine steam bypass valves

are closed.

If pressure continues to decrease

• If a Steam Jet Air Ejector is stillin service, shift to the startup Steam Jet Air Ejectors per SOP-(tater),

                                                                ' Condenser Evacuation System",

• Close the turbine bypass valves and manipulate the bypass valve Jack to control pressure as noosssary, 5.2.5 11 directed, proceed to IOP-10. " Unit On-Line from Hot Standby or Hot Shutdown *, IOP-6, *Cooldown to Cold Shutdown, Main Condenser Available", or IOP-7, 'Cooldown to Cold Shutdown, Main Condenser Not Available", as appropriate.

6.0 REFERENCES

6.1 General Electric Service information Letter SIL-208, ' Minimizing Feedwater Nozzle Thermal Duty *, Revision 1. October,1978. 6.2 Water Quality Specification,22A8479, Revision 2, PAE No.1.A.9. l

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