ML13317A665
| ML13317A665 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/09/1981 |
| From: | Brunet R, Curran J Southern California Edison Co |
| To: | |
| Shared Package | |
| ML13317A663 | List: |
| References | |
| SO1-4-9, NUDOCS 8109100397 | |
| Download: ML13317A665 (6) | |
Text
SAN ONOFRE NUCLEAR ERATING STATION OPERATING INSTRUCTION #S01-4-9 UNITi10 REVISION 0 PAGE I PLACING THE RESIDUAL HEAT REMOVAL SYSTEN IN SERVICE 1.0 OBJECTIVE 1.1 To place the Residual Heat Removal loop into service during plant cooldown.
REFERENCES CElvED 2.1 Unit 1 Technical Specifications 2
2.2 P&ID 568766, 568767, 568768 3.0 PREREQUISITES 3.1 Component Cooling Water system has the following ready for operation.
3.1.1 Two component cooling water heat exchangers.
3.1.2 Three component cooling water pumps.
3.2 Standby saltwater cooling pump is ready to be placed into service.
3.3 Before aligning the RHR loop, the RCS is at 400 psig and 400aF or less; steam dump pressure control is at 250 psig or less.
3.4 When the RCS is solid the following valves must be open.
3.4.1 MOV-813 and MOV-814.
3.4.2 LCV-1112.
3.4.3 CV-202, CV-203 and CV-204.
3.5 Before placing the RHR loop in service, the hot leg recirculation valve around the east RHR pump must be closed. An evaluation of the sphere environment and a Radiation Exposure Permit is required prior to containment entry.
4.0 PRECAUTIONS AND LIMITATIONS 4.1 Tests and maintenance activities that might affect reactor coolant system pressure shall not be performed during solid system operation.
P P000206 POR
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION #SO1-4-9 UNIT 1 MR 0 o91 REVISION 0 PAGE 2 PLACING THE RESIDUAL HEAT REMOVAL SYSTEM IN SERVICE 4.0 PRECAUTIONS AND LIMITATIONS (Cont'd) 4.2 During cold shutdown conditions, either two (2) RHR pumps and heat exchangers shall be operable or in service or one (1) RHR pump and heat exchanger shall be in service and a minimum of one (1) steam generator shall be available for decay heat removal. (Ref. 2.1, 3.1.2.G, Proposed Change 96) 4.3 With the refueling cavity flooded, one (1) RHR pump and heat exchanger may be removed from service only if an alternate means of decay heat removal is provided.
The alternate means of decay heat removal will be a refueling water pump and the recirculation Hx available for service. For system alignment refer to Emergency Operating Instruction 501-1.2-11, "Loss of Residual Heat Removal" Step 4.3. (Ref. 2.1, 3.8.A, Proposed Change 96) 4.4 When the RSC is filled and solid the OMS must be operational, or an operator will be assigned to monitor the RCS pressure to minimize the possibility of RCS overpressurization.
5.0 CHECK-OFF LISTS 5.1 Not Applicable.
6.0 INSTRUCTIONS 6.1 Preliminary Alignment of the RHR Loop.
6.1.1 Start the standby saltwater cooling water pump.
6.1.2 Verify open MOV-720 A and B, component cooling water heat exchanger isolation valve.
6.1.3 Start a second component cooling water pump.
6.1.4 Align component cooling water to the RHR heat exchangers.
.1 Place in manual, TCV-601A and TCV-601B, RHR heat exchangers temperature controllers, and set to approximately 30% open.
NOTE:
This will allow a smooth temperature transition when placing RCS flow through the heat exchangers.
.2 Open MOV-822A and MOV-822B, RHR heat exchanger inlet valves.
SAN ONOFRE NUCLEAR GENERATING STATION-OPERATING INSTRUCTION #SOl-4-9 UNIT 1 MAR 0 9 181
-REVION-O PAGE 3 PLACING THE RESIDUAL HEAT REMOVAL SYSTEM IN SERVICE 6.0 INSTRUCTIONS (Cont'd) 6.1.5 Place PCV-1105, letdown pressure controller, to manual.
NOTE:
Changed to prevent cycling pressure during the warmup phase and placing the RHR system in service.
6.1.6 Open MOV-813 and MOV-814, RHR inlet isolation valves.
6.1.7 Readjust PCV-1105, if required, to maintain desired RCS pressure.
NOTE:
Letdown has changed from the normal letdown through the orifice to the RHR loop.
6.1.8 Close the hot leg recirculation bypass valve around the east RHR pump.
NOTE:
This may be done any time prior to starting RHR pumps.
6.2 Placing the RHR Loop In Service.
NOTE:
RCS shall be at 350 psig, and 350OF or less. Pressurizer liquid temperature should be at 430OF or less. Steam dump controller should be fully open and RCS temperature beginning to level off.
6.2.1 Open MOV-833 and MOV-834, RHR outlet isolation valves.
6.2.2 Verify PCV-1105, letdown pressure controller, is in the manual position.
6.2.3 Start an RHR pump.
NOTE:
PI-1105 will indicate the shutoff discharge pressure of the RHR pump, approximately 430 psig with 350 psig in the RCS.
6.2.4 Open HCV-602, RHR flow control valve, to obtain 100 gpm for approximately 5 minutes to warm the RHR loop.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION #SO-4-9 UNIT 1 MAR 0 9 191 REVISION 0 PAGE 4 PLACING THE RESIDUAL HEAT REMOVAL SYSTEM IN SERVICE 6.0 INSTRUCTIONS (Cont'd) 6.2.5 Observe the following instrumentation to verify proper operation.
.1 FI-602, RHR flow indicator.
.2 FI-1112, Charging flow indicator.
.3 PI-1105, Letdown pressure indicator.
.4 RHR pump motor amps.
6.2.6 Open HCV-602 to obtain the desired cooldown rate.
.1 Adjust FCV-1112, RC charging controller, as necessary to maintain volume control tank level constant.
.2 Adjust PCV-1105, letdown pressure controller, to maintain desired RCS pressure.
6.2.7 Start the second RHR pump when HCV-602 has been fully opened.
6.2.8 Initially adjust TCV-601A and TCV-601B to maintain a return RHR temperature of approximately 182oF.
NOTE:
Do not exceed the maximum capability of the Component Cooling Water System.
6.2.9 Readjust HCV-602 to maintain the desired cooldown rate.
NOTE:
Monitor RCS temperature on TR-402.
6.2.10 Place PCV-1105 to automatic control to maintain RCS pressure at 350 psig.
6.2.11 Adjust FCV-1112, as required, to match letdown flow.
6.2.12 When the desired RCS temperature is obtained, TCV-601A and B may be returned to autom.tic and set at their normal setpoint of 115 0F.,
NOTE:
After the RCS temperature is 1400F, the pumps and heat exchangers of the component cooling water and RHR loops pay be taken out of service and the cooling wate flow reduced.
SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION #SO-4-9 UNIT I MAR 09181 REVISION 0 PAGE5 PLACING THE RESIDUAL HEAT REMOVAL SYSTEM IN SERVICE 7.0 RECORDS 7.1 Not Applicable.
8.0 ATTACHMENTS 8.1 Not Applicable.
R.R. BRUNET SUPERINTENDENT, UNIT 1 APPROVED:
J.M. CURRAN PLANT MANAGER NUS/er
Ilee SAN ONOFRE NUCLEAR GENERATING STATION OPERATING INSTRUCTION S-3-5.34 Revision 0 February 1, 1980 EMERGENCY LOSS OF SALT WATER COOLING TO THE COMPONENT COOLING SYSTEM 1.0 SYMPTOMS 1.1 Reactor Plant Annunciator Alarm.
1.1.1 Component Cooling heat exchanger high temperature (970F).
1.2 Auxiliary Board Annunciator Alarms:
1.2.1 Salt water cooling pump low flow (<50" or '<2500 gpm).
1.2.2 Salt water cooling pump low discharge pressure (<20 psig).
2.0 AUTOMATIC ACTION NONE 3.0 IMMEDIATE OPERATOR ACTION 3.1 If both the salt water cooling pumps become inoperable, place the auxiliary salt water cooling pump into operation. Refer to Operating Instruction S-2-7, "Salt Water Cooling Pump and Backup Operation."
NOTE:
Normally, the auxiliary salt water pump is aligned to the bottom component cooling heat exchanger.
3.2 If the auxiliary salt water cooling pump provides adequate cooling proceed to shutdown the unit. Refer to the following Operating Instructions:
S-3-1.4 Unit 1 Shutdown to Hot Standby Condition S-3-1.13 Reactor Shutdown From Hot Standby To Hot Shutdown.
3.3 If the auxiliary salt water cooling pump cooling is inadequate, trip the unit.
Refer to Emergency Operating Instruction S-3-5.1, "Emergency Shutdown."
4.0 SUBSEQUENT OPERATOR ACTION 4.1 If the top component cooling heat exchager is in service, the auxiliary salt cooling pump discharge should be re-aligned by:
4.1.1 Change the component cooling side of the heat exchanger to the bottom.
4.1.2 Verify the component cooling MOV-720A is closed and MOV-720B is open.