ML20042C120
| ML20042C120 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/08/1982 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20042C116 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-TM D.14, TAC-45202, NUDOCS 8203300227 | |
| Download: ML20042C120 (7) | |
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3-8-82 Rev. 16 /
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D.14 LOSS OF STEAM GENERATOR FEED 1.0 PURPOSE Provides actions to be taken following the loss of feedwater flow
.1 to one or both steam generators.
2.0 DESCRIPTION
This procedure covers two conditions for loss of feedwater flow, l5
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3.0 SY)IPTO)1S
.1 Loss of main feedwater pump (s)
.1 Reactor trip (loss of both main feedwatcr pumps)
.2 Feedwater pump (s) tripped annunciator
.3 OTSG(s) low level annunciators and/or decreasing 1cvels(s) indicated 5
.4 Reduced indicated feedwater flow
.5' ICS Runback or Limit annunciator
.6 Feedwater pump A/B discharge pressure low annunciator
.7 Increase in T and pressurizer Icvel ave
. 8' Auxiliary feedwater pumps running
.2 Loss of Feedwater Control' (one or both OTSG's)
.1 Steam generator low level annunciator (s), and/or increasing /
decreasing level indicated.
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.2 Feedwater flow indication indicates loss of or excess of i
feedwater flor (s).
.3 Feedwater flow control valves indicate closed or open more l
than plant conditions require.
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.4 Reactor coolant Tc temperature dif ference high indication l
and/or annunciated.
.5 Feedwater header pressure High annunciator.
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'D.14-1 Rev. 5 9203300227 820317 f
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4.0 AUTO.'!ATIC ACTIONS
.1 Loss of ?!ain Feedwater Pump (s)
.1 ICS Runback at 50%/ min (loss of one IHP) to 75% power.
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.2 Reactor trip and auto start of both Auxiliary Feedwater Pumps (loss of both FWP's).
.2 Loss of Feedwater Control (one or both OTSG's)
.1 Reactor coolant AT controller adjust flow to unef fected generator to hold AT limits.
.2 Decreasing steam generator pressure causing reduced turbine load.
.3 Reactor trip on high RCS pressure on loss of feedwater to i
both OTSG's.
5.0 I!DIEDIATE OPERATOR ACTIONS
.1 Loss of !!ain Feedwater Pump (s)
.1 Verify reactor and turbine trip (loss of both main INP's).
Perform Emergency procedure D.21in conjunction with the remainder of this procedure.
.2 Verify auto start of both auxiliary feedwater pumps and operation of the auxiliary feedwater valves, for loss of both main feedwater pumps.
(Bailey controlled valves or by tuodulating SFAS Bypass valves.)
.3 Verify auxiliary feedwater flow indicated on FI-31801 and FI-31901 located on ll2PSA to both OTSG's and IcVels maintained at > 24 inches on the Startup' Range (410% on the Operate Range).
.4 Verify power runback to <75% on loss of a singic main feed-15 water pump.
.5 If OTSG Icvels cannot be maintained (OTSG's steam dry), initiate llP1 (SFAS Channels 1A and B) at maximum flow to provide the core with cooling flow until feedwater can be established (HPI ptop runout at 500 gpm).
NOTE:
With IIPI providing core cooling:
liigh pressure injection may be controlled to maintain the reactor coolant system in the subcooled region ~ (>50*F) by varying the flow or pump operation if the RCS has another cooling medium, i.e. normal feedwater or aux-iliary feedwater. Auxiliary feedwater may be adjusted to control RCS cooldown rate if the RCS is being main-tained in a subcooled region (>50*F). Safety features D.14-2 Rev.
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i 5.0 PROCEDURE (Continued) equipment may be controlled by operator as long as the cf feet does not hinder operation of the RC system in the subcooled region and RCS presnure/ temperature limits for this condition are not exceeded.
.2 Loss of Feedwater control (one or both OTSG's)
.1 Verify reactor coolant ATc controller adjusts feedwater flow to uneffected steam generator to hold AT to <10*F.
.2
!!anually trip the reactor and turbine on loss of feed-uater to both steam generators or a confirmed low icvel in both OTSG's.
Verify reactor and turbine trip (loss of both main WP's). Perform Emergency procedure D.2 in con-junction with the remainder of this procedure.
NOTE:
A confirmed low level is based on Reactor Power
>22% with both Operate Range indications <10% and both steam generators on Lou Level LimLt.
.3 Close the main feedwater block valve and place the auxiliary feedwater system in service to the ef fected OTSC. Verify auxiliary feedwater flow as indicated on FI-31801 or FI-31901 on the ll2PSA. Control at minimum level of 24" on the Startup Range (%10% on the Operate Range).
.4 Put Auxiliary feedwater pumps in service and trip main feed-water pumps if both OTSG's are effected. Verify auxiliary feedwater flow as indicated on FI-31801 and F1-31901' on the ll2PSA. Control at minimum icvel of 24" on the Startup Range (%10% on the Operate Range).
.5 If OTSG 1evels cannot' be' maintained * (OTSG's steam dry),
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initiate'llPI (SFAS Channels lA and B) at maximum flow to 32 provide the core with cooling flow until feedwater can be l
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established (IIPI pump runout at 530 gpm).
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NOTE:
With IIPI providing core cooling:
Illgh pressure injection may be controlled to maintain the reactor coolant system in the nubcooled region (>50*F)
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by varying the flow or pump operation if the RCS has another cooling medium, i.e. normal. feedwater or aux-111ary feedwater. Auxiliary feedwater may be adjusted to control RCS cooldown rate if the RCS is being main-tained in a subcooled rer. ion (>50*F).
Safety features equipment may be controlled by operator as long as the effcet does not hinder operation of the RC system in the nubcooled region and RCS pressure / temperature limits for this condition are not exceeded.
D.14-3 Rev. 12 s
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'k 6.0 SUBSEQUENT OPERATOR ACTIONS
.1 Notify the Shif t Supervisor and System Dispatcher.
.2 On loss of a single main feedwater pump restore pump to service and resume nor:nal plant operation.
.3 On loss of both nain feedwater pumps or feedwater control, restore' feedwater flow path through the startup feed valves with one snain feedwater pump uhen OTSG Icvels are >24" on the Startup Range.
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.4 If an OTSG has gone completely dry, trip the reactor, insure any water inflow is via the auxiliary feed nozzles.
NOTE:
A dry OTSG is defined as,$8 inches indicated startup icvel.
.5 Perforn Excergency Procedure D.2, Reactor / Turbine Trip, if applicable in conjunction with the remainder of this procedure.
.6 If all feedwater is lost to both OTSG's, restore feed to at least one OTSG via any of the following nethods:
NOTE:
The following are listed in order of preference.
.1 Place auxiliary feedwater system in service in accordance with OP A.51 Section 7.5 or 7.7.
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.2 Establish feed via main FDW pu.sp and/or condensate pump through the OTSG main feed nozzles.
Manually operate / start valves / pumps if remote control is lost. Adjust steam
~8 header pressure as necessary.
.3 Establish feed via auxiliary boiler feed pumps. Flow path from condensate storage tank, gravity to auxiliary building steam condensate storage tank, to auxiliary boiler feed pumps, to downstream of 3rd point heaters via HCM-033/084, bypass inain feed pumps, to OTSG main feed noz: les.
NOTE:
Upon restoration of OTSG feed, initiate RCS cooldown; if not possible irnediately, nain-tain feed to OTSG's as required to remove core decay heat.
D.14-4 Rev. 16
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6.0 SUBSEQUENT OPERATOR ACTIONS (Continued)
.7 On total loss of all feedwater to both OTSC's (IIPI's at maximum allowed flow), if RCS pressure l 16 f nerer.ses at 2300 psig:
.1 Open the EtiOV by placing key lock selector suitch on llIRC consolc in the OPEN position.
.2 tihen RCS pressure has decreased to 1800 psig, close the EMOV by placing the key lock selector switch on !!IRC console in the llICit position. Allow RCS pressure to increase to 2300 psin.
Continue this cycle until feedwater is recovered and OTSC Icvels are being restored (in a controlled manner)
CAUTION _:
If RCS pressure decreases to 1600 psig, verify SFAS channelo IA and B, 2A and B initiated and trip all operating RCP's.
Close EMOV block valve 11V-21505.
Continue llPI flow to provide core cooling until RCS natural circulation can be verified in accordance with OPOP B.4, Section 6.
NOTE:
If Th, Tc, and/or Incore Tc's indicate super-heated conditions exist in the RCS, perform Casunity Procedure C.47 in conjunction with the remainder of this procedure.
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.3 Establish one RCP running per loop. The limitations and actions as set forth in D.12, RCP/itotor Emergencies, do not apply if ptcup combinations would be reduced below one RCP/ loop.
NOTE:
In the event RCS circulation is lost in conjunction with a loss of feedwater flow, utilize the average of the temperature readings from the incore thermo-couples listed on Enclosure 7.1.
The operator shall take action to reduce high pressure injection flow, if necessary, to avoid exceeding the allowable pressure limit given in Enclosure 7.1, for the calculated average reactor core outlet temperature.
The normal guidelines for pressure and temperature given in the Technical Specifications do not apply to thin procedure and should not be used as the basis for the termination of high pressure injection flou.
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D.14-5 3ev. 16
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g 6.0 Sur, SEQUENT OPEltATOR ACTIONS (Continued)
.8 With auxL11ary fecdwater pumps supplying the OTSG's, break condenser vacuum when the CST level reaches the Lo-Lo Icvel alarm point (29' 3").
With the Plant Cooling Water and Reservoir System in service in accordance with OP A.36, shif t auxiliary WP's suction to site supply system when the CST level reaches the Lo-Lo-Lo level alarm point (3').
P-318, Open PCW-076 - then close MCM-OS7.
P-319, Open PCW-079 - then close HCM-058.
7.0 ESCLOSURES
.1 Reactor Coolant Systen Interium Brittle Fracture Limit-No Forced Flow.
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Maintaining the reactor coolant 500F subcoolett takes precedence over the PREFERRED ALTERNATE Interin Dri t tle Fracture Curve
- 1) T-38' TW (D 1. U 74-1122501 page 6)
- 2) T-272 T-.264
- 3) T-271 T-267 D.14-7 Rev. 16 Is) T-270 T-297 S) T-298 T-296
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