ML20066C809

Rev a to IOP-2,Heatup & Pressurization

ML20066C809
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
23A6169AB, 23A6169AB-RA, NUDOCS 9101110230
Download: ML20066C809 (11)

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8 REV A REYlSION STATUS SHEET DOCUMENT TITLE LOP-2, HEATUP AND PRESSURtZATION TYPE: OPERATING PROCEDURE LEGEND OR DESCRIPTION OF GROUPS FMF: K6/7 MPL ITEM NO: A80-3020 REVISIONS 1 i A PRELIMINARY ISSUE PER OAB ERM - DMH-3234 ., 1 765 PRINTS TO l MADE BY APPROVALS DEPT LOCATION , W B TORRES C K TANO ' OE NUCLEAR ENEROY SAN JOSE CHKD BY ISSUED O A BAYLIS - F E WILHEMI l Fbk Ak&$s 0500060.m A 910109 PDF'

O GE Nuclear Energy 23A6169AB SH No. 2 REV A TABLE OF CONTENTS RAGk

1. SCOPE / APPLICABILITY 3

2. DISCUSSION 3

3. PRECAUTIONS AND LIMITATIONS 3-

4. PREREQUISITES 4

5. PROCEDURE =5 5.1 Establishing Main Condenser Vacuum 5 5.2 Preparation for Reactor Heatup and Pressurization 5 5.3 Establishing Heatup 5 5.4 Heatup to [6 kg/cm2) 6 5.5 Heatup to ( 10 kg/cm2) 7 5.6 Heatup to [20 kg/cm2] 8 5.7 Heatup to (40 kg/cm2) 8 5.8 Heatup to (66.5 kg/cm2] g 5.9 Transfer to the RUN Mode 10

6. REFERENCES 11

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    .. a O                GE Nuclear Energy

, REV A i 1.0 SCOPE / APPLICABILITY ( t This procedure provides detailed instructions for performing the operations required to heatup and pressurize the reactor following criticality, and to increase reactor power to a level sufficient for main turbine loading. 2.0 DISCUSSION This procedure involves the startup of turbine generator support systems, warming of the turbine generator, heatup and pressurizing the reactor to normal operating pressure and temperature, and increase reactor power to a level to allow turbine loading. Reactor heatup and pressurization will normally be integrated into an overall plant startup. Integrated Operating Procedures

                 " Approach to Criticality" (!OP-1), "Heatup and Pressurization" (IOP-2), .
                 " Turbine Startup and Generator Synchronization" (IOP-3), and " Power -

Asconsion and Power Changes "(IOP-4) should be initiated in such a manner as to provide an uninterrupted succession from one procedure to another, 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Reactor coolant system temperature [G33 TE 100) and pressure shall be determined to be within the applicable limits of Technical Specification Figure [ later ] at least once per 30 minutes during heatup and pressurization. l 3.2 Maintain drywell pressure [B11 PIS 606 A,0,C,D]Iess than I [0.06 kg/cm2) in order to prevent Inadvertent containment isolation and ECCS Initiation. 3.3 Maintain drywell average temperature less than [ 57 'C). 3.4 Reactor vessel level (C31 LT N004A,B,C,D)should be maintained between +[425.5 cm) and +(448.5 cm) throughout plant heatup by rejecting water using the Low Flow Control Mode in the Feedwater. Control System and the dump valve in the CUW System until a reactor feedpump has been placed into service. During drywell inspection,- use the CUW dump valve to control RPV water level, as necessary. The rejection rate should be limited so that the CUW filter demineralizer inlet temxrature does not exceed [54 *C). 3.5 Perform a rod coupling check when a rod is fully withdrawn. If a rod uncoupling annunciator is received, refer to (procedure for control rod uncoupled).

a . = . . . , sa a.as .. .. .. -~ -.a-. a.._ ,n a , .a.--.. .. - . . . , . . ---- -. - O GE Nuclear Energy \ P.t$169AB SH E 4 l pgv A i 3.0 PRECAUTIONS AND LIMITATIONS (continued) 3.6 Do not operate the mechanical vacuum pumps [ identity, later) at reactor powers greater than [5] %. 3.7 Maintain the temperature differential between the core exit coolant TE-later) and bottom head drain coolant (TE-later) less than L37 'O }. 3.8 Do not increase reactor power or recirculation flow if temperature i differentia: between steam dome (later) and bottom head drain (TE-later) exceeds (37 'C). 4.0 PREREQUISITES 4.1 Reactor power is at heating power level, at or above (later), per IOP 1,

                                                           " Approach to Criticality

• l 4.2 Prior to rolling the reactor feed pump turbine above turning gear speed, it must have been rotating on the turning gear for a minimum of (2) hours. Refer to SCP-[later),' Condensate and Feedwater.

System." 4.3 The feedwater chert.lstry limits are within the following: l Chlorides < 0.16 ppb Conductivity at 25 'O < 0.057 pS/cm Dissolved Oxygen 20.0 - 30.0 ppb I m.po r - - -- v,ea gy- ,. - , ,r -

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l e , i 0 GE Nuclear Energy 23A6169AB REV A SH NO. $ 5.0 PROCEDURE Subsection 5.1.

• Establishing Main Condenser Vacuum," may be conducted concurrently with subsection 5.2,
• Preparation for Heatup and Pressurization." The remaining subsections of this procedure are to be conducted in sequence.

5.1 Establish Maln Condenser Vacuum by executing subsection 5.1 of IOP-1, if necessary. If vacuum is already established, go to subsection 5.2. 5.2 Preparation for Reactor Heatup and Pressurization l 5.2.1 initiate recording of reactor heetup rate. 5.2.2 Verify that the stetpoint on the Steam Bypass and Pressure Centrol System is set at (10 kg/cmr] for startup. 5.3 Establishing Heatup 5.3.1 Verify that the Feedwater Control System is operating in the water via the CUW system and the(reactor water lev l maintained in the range of 425.5 cm to 448.5 cm on the Narrow Range water level instruments. 5.3.2 Continue to withdraw control rods as necessary to establish and maintain a reactor heatup rate not to exceed [55 ) OC per hour averaged over any one hour period. 5.3.3 Prior to reactor water temperature (TE-later) reaching [ 90 'O ), secure the condensate long-cycle cleanup mode and establish the Low Flow Control Mode in the Feedwater Control System in accordance with SOP-C31, with one low pressure condensate (LPCP) and one high pressure condensate l ' (HPCP) in operation, per SOP-{later), " Condensate and Feedwater System".- I

                 &             GE Nuclear Energy 23A6160AD Rrv     A SH WJ . 6 5.3 Establishing Heatup(continued) 5.3.4 Prior to exceeding a reactor temperature of [80 'C) as Indicated by TE-[later), verify reactor water dissolved oxygen concentration !& less than [200 ppb) as indicated by (later) or by a chemistry sample. Otherwise, stop further heatup and verify i                                  that the main steam drain valves are lined up in accordance                        .

with SOP-B21. Resume heatup when the reactor water oxygen concentration is < (200 ppb). 5.3.5 Throughout reactor heatup, vent the wetwell and drywell, via  ! the Atmospheric C,xtrol System, per SOP-[later), as necessanj to maintain drywell prceaure (B11 PIS 606A,B,C,D)less than (0.06 kg/cm2). 5.3.6 To minimize the feedwater nozzle thermal duty due to cyclings of cold feedwater, slowly increase CUW reject flow to establish [later, m3/hr) reject flow. 5.4 Heatup to [6 kg/cm2). 5.4.1 Continue to withdraw control rods to maintain reactor heatup rate. 5.4.2 At a reactor pressure of 1.3.5 kg/cm2), commence warmup of the RCIC System steam pip ng, and place the RCIC System in Standby Readiness per SOP E51, sections 3.0 and 4.0, l Reactor Core isolation Cooling System. 5.4.3 At a reactor pressure of (6 /cm2), commence warming of the main SJAEs per SOP-(later .-

• Condenser Evacuation System".

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O b GE Nuclear Energy 23A6109AB WINO 7 rirv A 5.5 Heatup to [10 kg/cm2). 5.5.1 Continue to withdraw control rods to increase reactor pressure and maintain the heatup rate, r CAUTION While shell warming per the following step, avoid a sudden change in shell pressure as it could result in a reactor scram (A pressure spike could make it appear as if the thermal power is greater than 40% and the turbine stop valves are less than 90% open. L 5.5.2 At 7 kg/cm2, startup the gland seal evaporator and shift sealing steam from the auxillary steam to the gland seal evaporator in accordance with SOP-{ tater),' Turbine Sealing Steam System.' 5.5.3 At a reactor pressure of (7 kg/cm2), commence main turbine shell' and chest warming per SOP-[later),

• Main Turbine.'

5.5.4 Verify the operability of the Steam Bypass and Pressure Control System by der. easing its regulator setpoint to below the reactor pressure unti' bypass valve No,1 starts to open. 5.5.5 Close bypass valve No.1 by raising the pressure regulator setpoint above the reactor pressure [ to a setpoint of 10 kg/cme), 5.5.6 At [10 kWcm2), increase reactor power until the No.1 bypass valve opens to [ x % " } position. When RPV pressure control is stab 1112ed, perform the RCIC surveillance test, if required, in accordance with [ specified surveillance test procedure ). 5.5.7 At ths conclusion of the RCIC test, resume beatup by ralcing the pressure regulator setpoint to slowly close bypass valve NO.1. maintalning a heatup rate at less than 55.5 'O per hour, insert control rods 11 necessary. The necessity for turbine shell warming will be detemined later.

             " TNs bypass valve position shall have a steam ibw equivalent greater than [1.10 times) that required for the RCIC test.-

( GE Nuclear Energy 23A6160AB SH No. 8 Arv A 5.6 Heatup to [20 kg/cm2). 5.6.1 Continue to withdraw control rods to malntain the heatup rate and maintain the pressure regulator setpoint [2 kg/cm2) above the reactor pressure. 5.6.2 At [17.5 kg/cm2), place the Off Gas System into normal operation in accordance with SOP-[later), *Off Gas System", and concurrently, 5.6.3 Place the main SJAEs in service and shut down the mechanical vacuum pumps and the startup SJAEs [ device, later) in accordance with SOP-[later), *taaln Condenser Evacuation System." 5.7 Heatup to [40 kg/cm2). 5.7.1 Continue to withdraw control rods to increase reactor pressure and maintain the heatup rate until reactor pressure reaches

                                                  ;40 kg/cm2). Maintain the pressure regulator setpoint [2 (g/cm2) above the reactor pressure.

I 5.7.2 At a reactor pressure 2 l40 kg/cm2), start the motor driven feedpump, and place it into service to control water level in the Low Flow Control Mode in accordance with SOP-[later),

                                                 "Feedwater Control System."

5.7.3 Stop rejecting water via the CUW System for reactor level control and transfer control from Low Flow Control Mode to Single-Element Control Mode per SOP-[later), i 5.7.4 Commence warmup of a reactor feed pump turbine, per SOP. [later), ' Condensate and Feedwater System."

j . . i. l' GE Nucirr Encrgy - 23A6169AB SH WJ. 9 REV A i 5.8 Heatup to (66.5 kg/cm2). 5.8.1 Continue to withdraw control rods to increase reactor pressure. l Maintain the setpoint of the pressure regulator at [2 kg/cm2) , above reactor pressure, until a setpoint of (66.5 kg/cm2]is reached. 5.8.2 Close the following main steam drain valves: ll

                                                                        -Inboard Drain to Condenser,                 B21-F152,
                                                                        -Main Steam Drain,                           B21-F211.

5.8.3 Check steamline drain operation per paragraph 4 or 5, as applicable, of SOP-21, " Nuclear Boller System".- 5.8.4 If lined up to vent the wetwell or drywell, coeure the venting lineup in the Atmospheric Control System. 4 5.8.5 When reactor pressure stabilizes, perform drywell inspection l according to [ procedure, later), if required, i l 1 1 ! 4 l r

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                     <                          GE Nuclear Energy 23A6169AB          SHNo, 10 RFV      A 5.9     Transfer to the RUN Mode.

5.9.1 Continue to withdraw control rods to increase reactor power until all APRM DOWNSCALE annunciators are cleared. 5.9.2 As power is increased per step 5.9.1, verify the turbine bypass valves open in sequence to maintain reactor pressure at [66.5 kg/cm2). 5.9.3 Verify the following conditions exist in preparation fur transferring the reactor mode switch to the RUN Mode:

                                                  - 5.9.3.1 Main steam pressure greater than [60 kg/cm2) and associated annunciators [A xxx, later) are cleared.

5.9.3.2 Condenser pressure less than [x em Hg absolute) and associated annunciators are cleared. 5.9.3.3 APRM DOWNSCALE annunciators are cleared. 5.9.3.4 All APRMs Indicating between (5)% and [12]% 5.9.3.5 The reactor coolant chemistry limits are within the following limits: Chlorides < 10 ppb Conductivity at 25 *C < 0.20 S/cm pH at 25 'O 6.4 - 7.8 5.9.4 Switch the reactor mode switch to the RUN Mode and reard the date and time. 5.9.5 Verify APRM rod block setpoints transfer to the flow biased setpoints. 5.9.6 Verify the four divisional MSIV CLOSURE TRIP BYPASSED annunciators [A xxx) have cleared. 5.9.7 Align CUW retum flow to both feedwater lines and open the isolated fesowater line to feed the vessel with both feedwater - lines in accordance with SOP-B21, " Nuclear Boller System"/" 5.9.9 Continue to withdraw control rods to increase reactor power until [1.5) bypass valves are open to roll the main turbine. The CUW flow algnment wlIl require further evaluation.

4 e . l 23A6169AD SH C . it i arv A 5.9 Transfer to the RUN Mode (conunve) 4 l 5.9.10 Perform the RCIC surveillance testing,if required,in accordance with [ specified surveillance test procedure ). 5.9.11 Perform turbine startup and generator synchronization in , accordance with IOP-3, ' Turbine Startup and Generator Synchronization'.- 4 6.0 REFERENCE 8 6.1 Water Quality Specification,22AB479, Revision 2, PAE No.1.A.9. l 6.2 GE Service Information Letter SIL-208,

• Minimizing Feedwater .

Nozzle Thermal Duty", Revision 1, October,1978. l 4 6.3 ' GE Service Information Letter SIL-107,' Increasing Flexibility of Reactor Startups", October 31,1974. I i l . . .

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