ML19224B270
| ML19224B270 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/17/1978 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2102-3.3, TM-0405, TM-405, NUDOCS 7906140332 | |
| Download: ML19224B270 (15) | |
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04/17/78 THREE MILE ISLAND NUCLE AR STATION UNIT #2 OPERATIIG PROCEDURE 2102-3.3 DECAY HEAT REMOVAL VIA GifG Table of Effective P. ges Pace Date Revision Pao.
Octe Revisio n Pace Date R evision_
l.0 06/16/77 0
2.0 06/16/77 0
2.0 04/17/78 6
4.0 09/08/77 1
5.0 21/17/78 6
5.1 04/17/78 6
6.0 05/16/77 0
7.0 06/16/77 0
8.0 03/01/78 4
9.0 11/15/77 3
9.1 11/01/77 2
10.0 06/16/77 0
11.0 03/17/78 5
12.0 03/17/78 5
13.0 14.0 15.0 16.0 17.0 18.0 19.0 20.0 21.0 22.0 23.0 24.0 Unit 1 Staff Rxommends Approwl Unit 2 Staff Recommends Approval Approval
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Date Approval A/
Date Cagnizant Ospt. Hsad Ccgnizant Dept. Head Unit 1 FORC Recommends Approval Unit 2 PORC Recommends Approval iib Date 0_
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Date l
Chairrmn of FORC
[f,/C)airdan of PORC
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i 2102-3.3 Revision 0 06/16/77 THREE MILE ISLAND NUCLEAR STATION UNIT #2 OPERATING PROCEDURE 2102-3.3 DECAY HEAT REMOVAL VIA OTSG Table of Contents SECTION PAGE 1.C REFERENCES 2.0 1.1 Drawings Applicable for Operation 2.0 1.2 Operating Procedures 1
1.3 Manufacturers' Instruction Manuals 2.0 1.4 System Descriptions 2.0 1.5 Curves, Tables, etc.
2.0 2.0 LIMITS AND PRECAUTIONS 3.0 2.1 Equipment 3.0 2.2 Administrative 4.0 3.0 PREREQUISITES 4.0 4.0 PROCEDURE 4.0
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THREE MILE ISLAND NUCLEAR STATION UNIT #2 OPERATING PROCEDURE 2102-3.3 DECAY HEAT REMOVAL VIA OTSG
1.0 REFERENCES
1.1 Drawings Applicable for Operation.
1.1.1 Main and Reheat Steam - B&R 2002.
1.1.2 Feedwater and Condensate - B&R 2005.
1.1.3 Reactor Coolant Makeup and Purification - B&R 2024.
1.1.4 Spent Fuel Cooling and Decay Heat Removal - B&R 2026.
1.1.5 Circulating and Secondary Services Water - B&R 2023.
1.2 Operating Procedures.
1.2.1 2102-3.1, Unit Shutdown.
1.2.2 2102-3.2, Unit Cooldown.
1.2.3 2104-1.3, Decay Heat Removal.
1.2.4 2105-1.4, Integrated Control System.
1.3 Manufacturers' Instruction Manuals.
1.3.1 Not Applicable.
1.4 System Descriptions.
1.4.1 Decay Heat Removal (.Index 20)'.
1.4.2 Main,_and Reheat Steam (.Inde: 1).
l.4.3 Feedwater and Ccndensate (Index 4A).
1.4.4 Condenser Air Extraction (Index 8).
1.4.5 Circulating '.later (Index 15).
1.5 Curves, Tables, etc.
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1.5.1 Turbine Header Fressure Serpoint vs Reactor Coolant System Temperature.
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c4oc-;.3 Revisien 6 04/17/78 1.5.2 Reactor Coolant System Cooldown Limitations.
l.5.3 Reactor Coolant System Cooldown Limitations (<500 psig).
2.0 LIMITS AND PRECAUTIONS 2.1 Equipment.
2.1.1 Reactor coolant temperature, pressure, and cooldown rates shall be e.aintained within the limits specified in Figure 3.4.2 of T.S. 3.4.9.1 (Refer to Figure 1.5.2 attached).
2.1.2 Except when drying an OTSG for shutdown, the minimum water level is (24") on startup range indicators SP-1A-LT4 and 5 and SP-18-LT4 and 5 on Panel 4.
2.1.3 The pressurizer maximum allcuable cooldown rat. -hall be 0
0 limited to 100 F/hr, 75 F step change, or 60 F in ar.v 1/2 hour period.
(T.S. 3.4.9.2).
2.1.4 For the Emergency Feedwater header /, ozzle fatigue limits, see Table 5-7.1 of Tech Specs.
2.1.5 During cooldown by natural circulation, the RCS shall be protected against thermal stress. caused by cold injection water accumulating in pockets at the point of injection and lower elevations by maintaining the cooldown rate so that the maximum AT between RC temperature, Tc, (as indicated by RC-5A-TI-1.or 2 on Panel 4) and S.G. upper downccmer temperature (as indicated on Computer points 487, 483, 489 & 490) is less than 0
or equal to 25 F.
2.1.6 If Decay Heat Removal by natural circulation is due to a blackout condition, then once p'_wer is restored, place the Turbine Bypass Valves in " Manual" prior to resetting Control Rod Drive breakers.
This will prevent excessive cooldown when Turbine Header Pressure control reverts to setpoint.
2102-3.3 Revision 1 09/03/77 2.1.7 During Decay Heat Removal by natural circulation, maintain Th (as indicated by RC-4A/4B-TIl or TI2) 30 F below the saturation temperature corresponding to pressurizer pressure in order t) prevent boiling in the hot legs.
- 2.2 Administrative.
Not Applicable.
3.0 PREREQUISITES I
3.1 The reactor is at Hot Shutdown (Mode 3) in accordance with 2102-3.1, Unit Shutdown, with safety rod groups 1-4 fully withdrawn and group 8 in its operating position.
3.2 Feedwater flow is via the Startup Feedwate Valves (FW-V25A &
B) and 0TSG level is being maintained at 97-995 on the operating rar.ge level instruments (SG-1A/lB-LT2 or LT3) with the Startup Feedwater Valves FU-V25A & B in " Manual".
3.3 Decay Heat is being removed via the Turbine Bypass Valves (MS-V25A and B and MS-V26A and B) with Turbine Header Pressure setpoint at 855 psig (47.2% on Turbine Header Pressure ICS Station) maintaining Reactor Coolant System Temperature (ic)
U at 532 F as indicated by RC-5A-TI-l or 2 on Panel 4.
4.0 PROCEDURE;_
4.1 Normal System Startup.
4.1.1 To maintain reactor coolant system temperature above 0
480 F (as indicated by RC-5A-TI-l or 2 on Panel 4) adjust the Turoine Header Pressure Setpoint to maintain the turbine header pressure corresponding to the desired Reactor Coolant System tcmperature as per Figure 1.5.1.
4' 195 310 l
21 U2-3. 3 Revision 6
-1 04/17/78
_4.1.2 To decrease Reactor Coolant System ter,mrature adjust the Turbine Header Pressure Setpoint downward, thereby, increasing steam flow from the OTSG's and decreasing the Reactor Coolant System temperature, Tc (as indicated by RC-5A-TI-l or 2 on Panel 4) Correlate Reactor Coolant System temperature and Turbine Header Pressure Setpoint by using Figure 1.5.1.
Cooldown must be limited to 0
100 F/hr, 75 F step change, or 500F in any 1/2 hour period, and the cooldown limitations of Figure 1.5.2 must be met.
Maintain this method of cooldown until Reactor Coolant System temperature Tc (as indicated by RC-5A-TI-l 0
or 2 on Panel 4) is below 500 F.
4.1.3 When Reactor Coolant System temperature, Tc (as indicated 0
by RC-5A-TI-l or 2 on Panel 4) is belov-SC0 0F, place the Turbine Bypass Valves in Manual in accordance with 2105-1.4, Integrated Control Systen.
Continue cooldown to the desired Reactor Coolant System temperature, Tc (as indicated by RC-5A-TI-l or 2 on Panel 4), in accordance with 2102-0 3.2, Unit Cooldown.
Cooldown must be limited to 100 F/hr, 75 F step change, or 50 F in any 1/2 hour period, and the nccoldown limitations of Figure 1.5.2 must be met.
Maintain this method of cooldown until Reactor Coolant System temperature, Tc (as indicated by RC-5A-TI-l or 2 ca Panel 0
- 4) is at 230 F, t
4.2 RCS Cooldown Operation.
U 4.2.1 The Reactor Coolant System is cooled down to 280 F (as indicated by FC-5A-TI-l or 2 on Panel 4) using the 195 311 5.0 e
ciG2-3.3 Revision 6 04/17/78 Turbine Bypass Valves to dump steam to U.c main condcnser in accordance with 2102-3.2, Unit Cooldown.
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2102-3.3 Revision 0 06/16/77 4.2.2 The Reactor Coolent System pressure (as indicated by RC-3A-PI2) has been reduced to the midpoint of the " Window" for simultaneous operaticn of the RC pumps and DH pumps in accordance with 2102-3.2, Unit Cooldown.
4.2.3 The Decay Heat Removal System is in operation per 2104-1.3, Decay Heat Removal.
NOTE:
The snutdown of Decay Heat Removal via OTSG will be correlated with 2104-1.3.
4.2.4 Secure Decay Heat Removal via OTSG when RCS temperature is less than 220 F by closing the turbine bypass valves, MS-V25A and B, and MS-V26A and B.
4.3 Heat Removal by Natural Circulation.
On loss of all four (4) RC Pumps, the Emergency Feedwater Pumps (EF-P-1, EF-P-2A, and EF-P-28) will start and the Emergency Feedwater Vi ves (EF-VilA and B). will open to supply emergency feedwater directly from the condensate storage tanks to the OTSG's through the Eme.gency Feedwater Nozzles. This introduction of cold feedwater to the upper half of the OTSG will cause a reduction in RC System temperature in the upper section of the OTSG.
This reduction in RC System temperature will induce the natural circulation required for decay heat removal.
4.3.1 All four (_4). RC Pumps are tripped, the reactor is tripped, and the turbine is tripped.
4.3.2 Steam pressure is being main' _1ned at Turbine Header setpoint (_i.e. - 855 psig during noraml operation plus 125 psig) dumping steam to the main condenser thrcugh the Turbine Bypass Valves (fis-V25A and B and MS-V26A and B) 6.0
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195 313
2102-3.3 Revision 0 06/16/77 or dumping steam to the atmosphere through the Atmospheric Dump Valves (MS-V3A and B) if a low vacuum condition of less than 24" H O exists in the main condenser or less 2
than three (.3) Circulating Water Pumps are running.
Steam safety valves and pressurizer electromtic and code safety valves are closed.
4.3.3 The Emergency Feedwater Pumps (EF-P-1, FF-P-2A, and EF-P-2B1 are running (as indicated by Panel 3 indicating lights)., supplying emergency feedwater to the OTSG's frcm the Condensate Storage Tanks, through the Emergency Feedwater Valves (EF-VilA and B) OTSG level is increasing to, or at, 21' (50% as indicated on operating range level instrumentation SG-1A/lB-LT2 or 3 on Panel 3).
NOTE:
Decay heat remcval by natural circulation will be accomplished in conjunction with 2202-2.1, Blackout.
2202-2.1 cover, two possibilities:
1.
Blackout with diesels - use step 't.3.4.
2.
Blackout without diesels - use step 4.3.5.
With either of these two conditions, the follouing considerations prevail:
l.
Normal pressurizer pressure control is lost due to loss of spray capability and loss of pressurizer heaters.
2.
System pressure will decay due to heat i
losses to ambient from the pressurizer
(.100-200 psig/hr).
7.0 195 314
2102-3.3 G"3'fbflh Assuming continued efforts to reenergize the Auxiliary transformers fail, the operators must follow the pressurizer pressure decrease and maintain th9 pressure / temperature limits for cooldown in Figure 1.5.2 by following the appropriate procedure below:
4.3.4 Decay Heat Removal by Natural Circulation with Emergency Diesels.
4.3.4.1 Establish seal. injection flow by the following procedure:
4.3.4.1.1 Place MU-V32 Seal Injection Flow Control Valve in Manual and close (Panel 3).
4.3.4.1.2 Close MU-V25 or 377.
4.2.4.1.3 Start Md-PI A (Panel 3) per 2104-1. 2.
4.3.4.1.4 Open MU-V32 in Manual slowly te establish Seal Injection Flo'.. Rate of 2 GPM per RCP for two minutes.
4.3.4.1.5 Establish seal injection ' low of 6 GPM per RCP for two minutes.
4.3.4.1.6 Open seci return valves MU-V33 A, B, C, D i f closed, and open MU-\\25 or 377 closed in step 4.3.4.1.2.
4.3.4.1.7 Establish full 10 GPM seal injection per RCP.
4.3.4.1.8 Place MU-V32 in AUTO.
NOTE:
These steps are to avoid thermally shockirc the RCP seals.
4.3.4.2 Using Turbine Header Pressure setpoint, adjust OTSG pressure to maintain RCS temperature within the pressure /
temperature limitations of cooldown curve, Figure 1.5.2.
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NOTE:
With CRD breakers tripped, a 125 psig bias is added to Turbine Header Pressure setpoint to prevent excessive cocidown of the reactor.
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2102-3.3 Revision 3 11/15/77 4.3.4.3 When RC System temperature decreases to 510 F (as indicated by RC-5A-TIl/2 on Panel 4) place the Turbine Bypass Valves Hand / Auto control statior; in Manual and continue cooldown in accordance with 2102-3.2, Unit Cooldown, maintaining pressure /temperatur' relationship dictated by the cooldcwn curve, Figure 1.5.2.
NOTE:
During blackout onditions, the Turbine Bypass Valve ICS Hand / Auto station will be controlling Atmospheric Stearn Dump Valves, MS-V3A and B due to loss of all circulating water pumps.
U 4.3.4.4 When RCS temperature decreases to 250 F, the DHR system will be placed in operation in accordance with 2104-1.3, Decay Heat Removal and transfer of decay heat removal to the DH systen Will be accomplished in accordance with Section 4.2.
4.3.5 Decay Heat Removal by Natural Circulation Without Emergency Diesels.
_4.3.5.1 Stop letdown from the RC System by closing MU-V376 (Panel 3).
4.3,5.2 Prior to total loss cf Instrument Air System (60 psig) station personnel at following locations to manually control associated valves on orders from the Control Room.
(1) Atmospheric Dump valves MS-V3A and B.
~.5 (2)
EFP Steam supply valve MS-V14.
-1 (3)
Emergency FW valves EF-VllA and B.
0 4.3.5.3 Maintain Th 20 F belcw the saturation temperature corresponding to pressurizer pressure by manual operation of tha above 9-195 316
i 2102-3.3 Revision 2 11/1/77
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listed valves to prevent boiling in the hot legs and to allow minimum RC System s'rinkage until makeup is restored.
4.3.6 Discentinuing the removal of decay heat by natural circulating after an Auxiliary transformer is returned to service.
When an Auxiliary transformer is returned to service, return required system to norma', as determined by plant conditions iri,'acccrdance with appropriate procedures.
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