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{{#Wiki_filter:t'UML, UHAlHMAN 1202-26A''1 Revision 7-
{{#Wiki_filter:t'UML, UHAlHMAN                                                           1202-26A
'~~.L 09/18/79 THREE MILE ISLAND NUCLEAR STATION UNIT #1 EMERGE.1CY OR0CECURE 1202-2EA LOSS OF STEAM GEriERATOR PEED TO BOTH OTSG'S C0hTRO_ D C03Y Table of EHective Pages Paos Date Revision Pace Date Resisit n Pece Date R evision 1.0 06/15/79 4 26.0 51.0 2.0 09/18/79 7 27.0 52.0 3.0 08/30/79 6 28.0 53.0 4.0 29.0 54.0 5.0 30.0 55.0 6.0 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11'.0 36.0 61.0 12.0 37.0 62.0 13.0 38.0 63.0 14.0 39.0 C4.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 18.0 43.0 68.0 19.0 44.0 69.0 20.0 45.0 70.0 46.0 71.0 21.0-22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recem .~ / pyrreval Unit 2 Staff Reccenmencs/Acproval
' ''                                                            ~~
/I/ /l Appmvel/ t Date Approval _
1                                           Revision 7-
//I Date-Cogninnt 641. Hud Ccgnhant Is;(. H a' d a Unit 1 PORC Recommer:ds Approwl Unit 2 PORC Rec mmer.ds peroval Date 07 ' /'7 -7f
                                                                    .L                                           09/18/79 THREE MILE ISLAND NUCLEAR STATION UNIT #1 EMERGE.1CY OR0CECURE 1202-2EA LOSS OF STEAM GEriERATOR PEED TO BOTH OTSG'S Table of EHective Pages C0hTRO_ D C03Y Paos       Date         Revision           Pace       Date         Resisit n                     Pece   Date           R evision 1.0     06/15/79         4               26.0                                                     51.0 2.0       09/18/79         7               27.0                                                     52.0 3.0     08/30/79         6               28.0                                                     53.0 4.0                                       29.0                                                     54.0 5.0                                       30.0                                                     55.0 6.0                                       31.0                                                     56.0 7.0                                       32.0                                                     57.0 8.0                                       33.0                                                     58.0 9.0                                       34.0                                                     59.0 10.0                                       35.0                                                     60.0 11'.0                                       36.0                                                   61.0 12.0                                         37.0                                                   62.0 13.0                                         38.0                                                   63.0 14.0                                         39.0                                                   C4.0 15.0                                         40.0                                                   65.0 16.0                                         41.0                                                   66.0 17.0                                         42.0                                                   67.0 18.0                                         43.0                                                   68.0 19.0                                         44.0                                                   69.0 20.0                                         45.0                                                   70.0 21.0        -                                46.0                                                   71.0 22.0                                         47.0                                                   72.0 23.0                                         48.0                                                   73.0 24.0                                         49.0                                                   74.0 25.0                                         50.0                                                   75.0 Unit 1 Staff Recem .~ / pyrreval                                 Unit 2 Staff Reccenmencs/Acproval Appmvel
!bS! LIr% m
                                /I
/Date p Chairman of PORC Chairmah of F0FTC
                              / t       Date                       Approval _
'.Unit 2 Superintendent Approvaf Unit 1 Superintendent Appreval AN e.m.c at,.-Det, o w a Ya,= gar Ger. era: ce Cusiity Assurance App cval
                                                                                                        / /l
/D'Data TMs 55- A A v. 3 r 7 7 7910100 D 7
                                                                                                        //I         Date
-- - --_ - _ .-__ _ - _ _-
                                                                                                                                        -
Cogninnt 641. Hud                                                 Ccgnhant Is;(. H a'ad Unit 1 PORC Recommer:ds Approwl                                 Unit 2 PORC Rec mmer.ds peroval
        /    bS! LIr% m                  Date 07 ' /'7 -7f                               !                 '
Date p Chairman of PORC                                                 Chairmah of F0FTC
                                                                                                .
Unit 1 Superintendent Appreval Unit 2 Superintendent Approvaf
      .
e.m                               c at,   .-                                 o AN    w         a Det, Ya,= gar Ger. era: ce Cusiity Assurance App cval                                         /D'                 Data TMs 55- A A v. 3 r 7 7 7910100 D 7
          -
                    - - -
                                          -
_ - _ .                   _
                                                                            -
_ _ - _ _-
___ _ _ _ _ _ _. ..
___ _ _ _ _ _ _. ..
sr.s 1202-26A..Revision 4 C6/15/79 THREE MILE ISLAND NUCLEAR STATION UNIT #1 EMERGE: ICY PROCEDURE 1202-25A LOSS OF STEAM GENERATOR FEED TO BOTH OTSG'S
sr               .s
)0 U4)][f)Q l gi 26.1 SYMPTOMS g 0 [*1,,-b 1.Both OTSG(s) levels decreasing.
 
2.Normal Feedwater flow to both OTSG's decreasing.
. .
3.Feed pump turbine speed decreasing or both normal feed valves
1202-26A Revision 4 C6/15/79 THREE MILE ISLAND NUCLEAR STATION UNIT #1 EMERGE: ICY PROCEDURE 1202-25A LOSS OF STEAM GENERATOR FEED TO BOTH OTSG'S 26.1 SYMPTOMS
~(FW-Vl7A/3) closing.
[f)Q       l gi 1.
4.Both feed pump turbine trip alarms.
                              -
5.Reactor and turbine trip if both feed pumps trip.
Both OTSG(s) levels decreasing.
6.Reactor / turbine runback.
                                                                )0 U4)]            b g
7.Increasing reactor coolant pressure and temperature.
0 [*1,,
26.2 IT'MEDI ATE ACTION A.Automatic Action 1.Reactor trip due to high RCS pressure, or due to trip of both feed pumps.
: 2. Normal Feedwater flow to both OTSG's decreasing.
2.Emergency feed pumps EF-P1, EF-P2A, and EF-?23 start on loss of both main feed pumps and maintain GTSG level at 30" NOTE: An asterisk (*) indicates reverification of the
: 3. Feed pump turbine speed decreasing or both normal feed valves
-parameter value - is required as part of Step 1 of follow-up action.
                                                                            ~
B.Manual Action 1.Trip t' e reactor and perform imediate anual actions per E? 1202-04 2.Trip the turbine and verify stcp valvss and ::mbined intercept valvss closed.
(FW-Vl7A/3) closing.
Verify genera:cr creakers c;en.
: 4. Both feed pump turbine trip alarms.
1.0 m.%9  
: 5. Reactor and turbine trip if both feed pumps trip.
.1202-26A Revision 7 09/18/79 3.Verify turbine driven e .ergency feed pump (EF-?l) and motor driven pumps (EF-P2A/23) start as evidenced by pump discharge pressure P!-55, PI-71, and PI-72 greater than 1010 psig.
: 6. Reactor / turbine runback.
4 Verify EFV-30A/B are in automatic.
: 7. Increasing reactor coolant pressure and temperature.
5.Verify emergency feed flow by ficw indication en control room console as needed to control level to 3C" on start-up range * (50*,' en operating range
26.2 IT'MEDI ATE ACTION A. Automatic Action
: 1. Reactor trip due to high RCS pressure, or due to trip of both feed pumps.
: 2. Emergency feed pumps EF-P1, EF-P2A, and EF-?23 start on loss of both main feed pumps and maintain GTSG level at 30" An asterisk (*) indicates reverification of the
      -
NOTE:
parameter value - is required as part of Step 1 of follow-up action.
B. Manual Action
: 1. Trip t' e reactor and perform imediate anual actions per E? 1202-04
: 2. Trip the turbine and verify stcp valvss and ::mbined intercept valvss closed. Verify genera:cr creakers c;en.
1.0 m.
                                                                                %9
 
.
1202-26A Revision 7 09/18/79
: 3. Verify turbine driven e .ergency feed pump (EF-?l) and motor driven pumps (EF-P2A/23) start as evidenced by pump discharge pressure P!-55, PI-71, and PI-72 greater than 1010 psig.
4     Verify EFV-30A/B are in automatic.
: 5. Verify emergency feed flow by ficw indication en control room console as needed to control level to 3C" on start-up range * (50*,' en operating range
* for less of RC pumps).
* for less of RC pumps).
NOTE: When filling both S.G.'s from a loss of F.W.
NOTE:     When filling both S.G.'s from a loss of F.W.
conditien, limit flow rate to each OT5G to approximately 350 GPM.(This will tend to reduce thermal shock to OTSG and avoid sericus drop in RCS pressure and temperature).
conditien, limit flow rate to each OT5G to approximately 350 GPM.     (This will tend to reduce thermal shock to OTSG and avoid sericus drop in RCS pressure and temperature).
6.Verify tha- RC locp pressure is returning to approximately
: 6. Verify tha- RC locp pressure is returning to approximately
'2155 psis* and that TH is decreasing to approximately 0 550 F*.If RC pressure continues to decrease below 2155 psig, an RCS leak or a steam system leak should be suspected.
  '
25.3 FOLLOW-Up ACTION The objective of the loss of feed precedure is to verify that the auxiliary feed system starts and maintains steam generator level to remove decay he t frcm the RCS.
2155 psis* and that TH is decreasing to approximately 0
Steam generator level is increased on loss of RC pumps to provide the thermal driving head for natural circulation to remove decay heat.
550 F*. If RC pressure continues to decrease below 2155 psig, an RCS leak or a steam system leak should be suspected.
1.On completien of necessary imediate manual action steps, reverify the key carameter readings that are marked with an as terisk (",' .Us e al ternate instrurer. chir.r,eis ..here available.
25.3 FOLLOW-Up ACTION The objective of the loss of feed precedure is to verify that the auxiliary feed system starts and maintains steam generator level to remove decay he t frcm the RCS.       Steam generator level is increased on loss of RC pumps to provide the thermal driving head for natural circulation to remove decay heat.
i tol>1  
: 1. On completien of necessary imediate manual action steps, reverify the key carameter readings that are marked with an as terisk (",' . Us e al ternate instrurer. chir.r,eis ..here available.
.1202-25A'Revision 5 08/30/79 2.Investigate cause of loss of feedwater and restore nomal feed to OTSG.3.On loss of both main feedwater pumps, if plant cooldown is required, conduct cooldown using emergency feed system.
i tol                                                 >1
Refer to OP #1102-13 Decay Heat Removal by OTSG.
 
4.If EF-V30A/S do not respond to maintain appropriate OTSG level indication, take manual control of EF-V30A/B hand / auto station to maintain proper level .
                                  .
If EF-V30A/3 still do not respond, station an operator in communication with the control room to take local manual control in accordande with OP 1105-6.
'
5.If unable t,o establish main or emergency feedwater, initiate HPI cooling as follows:
1202-25A Revision 5 08/30/79
a)Initiate High Pressure Injection.
: 2. Investigate cause of loss of feedwater and restore nomal feed to OTSG.
CAUTION: Do not throttle HPI until steam generator lcooling is re-established and RCS is at least
: 3. On loss of both main feedwater pumps, if plant cooldown is required, conduct cooldown using emergency feed system.         Refer to OP #1102-13 Decay Heat Removal by OTSG.
., 50 F subcooled by both cold and hot leg temperature
: 4. If EF-V30A/S do not respond to maintain appropriate OTSG level indication, take manual control of EF-V30A/B hand / auto station to maintain proper level . If EF-V30A/3 still do not respond, station an operator in communication with the control room to take local manual control in accordande with OP 1105-6.
;I indications and hot leg temperature is not more i , than 50 F higher than secondary side saturation f temperature.
: 5. If unable t,o establish main or emergency feedwater, initiate HPI cooling as follows:
'i b)Open RC-V2 and allow RCRV2 to cycle until feed water flow is regained.
a)   Initiate High Pressure Injection.
77'l ~ i 4 3.0lJu--.}}
CAUTION: Do not throttle HPI until steam generator l
  .,                        cooling is re-established and RCS is at least 50 F subcooled by both cold and hot leg temperature   ;
I indications and hot leg temperature is not more       i
          ,
than 50 F higher than secondary side saturation f
temperature.                                         '
i b)   Open RC-V2 and allow RCRV2 to cycle until feed water flow is regained.
3.0 4
l 'l Ju
                                                                    ~i   77
                                                                        --
    .}}

Revision as of 14:44, 19 October 2019

Emergency Procedure 1202-26A,Revision 7, Loss of Steam Generator Feed to Both Once-Through Steam Generators.
ML19209B653
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 09/18/1979
From:
METROPOLITAN EDISON CO.
To:
References
1202-26A, NUDOCS 7910100278
Download: ML19209B653 (4)
v • d • e


Text

t'UML, UHAlHMAN 1202-26A

' ~~

1 Revision 7-

.L 09/18/79 THREE MILE ISLAND NUCLEAR STATION UNIT #1 EMERGE.1CY OR0CECURE 1202-2EA LOSS OF STEAM GEriERATOR PEED TO BOTH OTSG'S Table of EHective Pages C0hTRO_ D C03Y Paos Date Revision Pace Date Resisit n Pece Date R evision 1.0 06/15/79 4 26.0 51.0 2.0 09/18/79 7 27.0 52.0 3.0 08/30/79 6 28.0 53.0 4.0 29.0 54.0 5.0 30.0 55.0 6.0 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11'.0 36.0 61.0 12.0 37.0 62.0 13.0 38.0 63.0 14.0 39.0 C4.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 18.0 43.0 68.0 19.0 44.0 69.0 20.0 45.0 70.0 21.0 - 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 Staff Recem .~ / pyrreval Unit 2 Staff Reccenmencs/Acproval Appmvel

/I

/ t Date Approval _

/ /l

//I Date

-

Cogninnt 641. Hud Ccgnhant Is;(. H a'ad Unit 1 PORC Recommer:ds Approwl Unit 2 PORC Rec mmer.ds peroval

/ bS! LIr% m Date 07 ' /'7 -7f  ! '

Date p Chairman of PORC Chairmah of F0FTC

.

Unit 1 Superintendent Appreval Unit 2 Superintendent Approvaf

.

e.m c at, .- o AN w a Det, Ya,= gar Ger. era: ce Cusiity Assurance App cval /D' Data TMs 55- A A v. 3 r 7 7 7910100 D 7

-

- - -

-

_ - _ . _

-

_ _ - _ _-

___ _ _ _ _ _ _. ..

sr .s

. .

1202-26A Revision 4 C6/15/79 THREE MILE ISLAND NUCLEAR STATION UNIT #1 EMERGE: ICY PROCEDURE 1202-25A LOSS OF STEAM GENERATOR FEED TO BOTH OTSG'S 26.1 SYMPTOMS

[f)Q l gi 1.

-

Both OTSG(s) levels decreasing.

)0 U4)] b g

0 [*1,,

2. Normal Feedwater flow to both OTSG's decreasing.
3. Feed pump turbine speed decreasing or both normal feed valves

~

(FW-Vl7A/3) closing.

4. Both feed pump turbine trip alarms.
5. Reactor and turbine trip if both feed pumps trip.
6. Reactor / turbine runback.
7. Increasing reactor coolant pressure and temperature.

26.2 IT'MEDI ATE ACTION A. Automatic Action

1. Reactor trip due to high RCS pressure, or due to trip of both feed pumps.
2. Emergency feed pumps EF-P1, EF-P2A, and EF-?23 start on loss of both main feed pumps and maintain GTSG level at 30" An asterisk (*) indicates reverification of the

-

NOTE:

parameter value - is required as part of Step 1 of follow-up action.

B. Manual Action

1. Trip t' e reactor and perform imediate anual actions per E? 1202-04
2. Trip the turbine and verify stcp valvss and ::mbined intercept valvss closed. Verify genera:cr creakers c;en.

1.0 m.

%9

.

1202-26A Revision 7 09/18/79

3. Verify turbine driven e .ergency feed pump (EF-?l) and motor driven pumps (EF-P2A/23) start as evidenced by pump discharge pressure P!-55, PI-71, and PI-72 greater than 1010 psig.

4 Verify EFV-30A/B are in automatic.

5. Verify emergency feed flow by ficw indication en control room console as needed to control level to 3C" on start-up range * (50*,' en operating range
  • for less of RC pumps).

NOTE: When filling both S.G.'s from a loss of F.W.

conditien, limit flow rate to each OT5G to approximately 350 GPM. (This will tend to reduce thermal shock to OTSG and avoid sericus drop in RCS pressure and temperature).

6. Verify tha- RC locp pressure is returning to approximately

'

2155 psis* and that TH is decreasing to approximately 0

550 F*. If RC pressure continues to decrease below 2155 psig, an RCS leak or a steam system leak should be suspected.

25.3 FOLLOW-Up ACTION The objective of the loss of feed precedure is to verify that the auxiliary feed system starts and maintains steam generator level to remove decay he t frcm the RCS. Steam generator level is increased on loss of RC pumps to provide the thermal driving head for natural circulation to remove decay heat.

1. On completien of necessary imediate manual action steps, reverify the key carameter readings that are marked with an as terisk (",' . Us e al ternate instrurer. chir.r,eis ..here available.

i tol >1

.

'

1202-25A Revision 5 08/30/79

2. Investigate cause of loss of feedwater and restore nomal feed to OTSG.
3. On loss of both main feedwater pumps, if plant cooldown is required, conduct cooldown using emergency feed system. Refer to OP #1102-13 Decay Heat Removal by OTSG.
4. If EF-V30A/S do not respond to maintain appropriate OTSG level indication, take manual control of EF-V30A/B hand / auto station to maintain proper level . If EF-V30A/3 still do not respond, station an operator in communication with the control room to take local manual control in accordande with OP 1105-6.
5. If unable t,o establish main or emergency feedwater, initiate HPI cooling as follows:

a) Initiate High Pressure Injection.

CAUTION: Do not throttle HPI until steam generator l

., cooling is re-established and RCS is at least 50 F subcooled by both cold and hot leg temperature  ;

I indications and hot leg temperature is not more i

,

than 50 F higher than secondary side saturation f

temperature. '

i b) Open RC-V2 and allow RCRV2 to cycle until feed water flow is regained.

3.0 4

l 'l Ju

~i 77

--

.

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