ML20205A906

From kanterella
Jump to navigation Jump to search
Rev 2 to Emergency Operating Procedure EOP 3504, Cooldown Outside Control Room
ML20205A906
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 11/05/1985
From: Moore D
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-3504, NUDOCS 8810260127
Download: ML20205A906 (11)
v • d • e


Text

. .

E. J. Mr ka -

2-1-85 Form Approved by Station Superintendent ffective Date STATION PROCEDURE COVER SHEET i )

> A. IDENTIFICATION Number E0P 3504 Rev. 2 Title C00LDOWN OUTSIDE CONTROL ROOM Prepared By D. R. MOORE B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEA0 [ o Am ug uhh5 C. UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATICN REQUIRED:

(Significant change in procedure method or scope YES [ ] NO (%

as described in FSAR) ,

(If yes, document in PORC/50RC meeting minutes)

(V ENVIRONMENTALIMPA',J (Adverse environmental impact) YES [ ] NO ()d (If yes, document in PORC/50RC meeting minutes)

D. INTEGRATED SAFFTY DEVIEV REQUIRED (Affects response of Sr.fety Systems, performance YES [ ] NO [)d of safety-related control syst2ms or performance of control syt,tems which may indirectly af fect safety systen response.)

(If yes, decumant in PORC/50RC meeting minutes. )

E. 30CFOUREREQUIRES JCRC REVIE YES [N NQ [ ]

F. @ SORC APPk R41 SORC Meeting Number 3 2 lk ,

G. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:

Y @ )

~

Station / service / Unit Superintenpent M

Effective Date J

v

)

SF 301 Rev. 7 s010260127 001007 P39' l 'I I PDR ADOCK 05000213 p PDR

.__ - . . == _ = _ _ _ . . .-._ ___. _ -. _- - _ - ._-. -

. t'

,)

1 E0P 3504 Page 1 l Rev. 2 !l

l 9 C00LO0t'i OUTSIDE CONTROL ROOM l:

Page No. Eff. Rev. If 1-10 2 i!

i j

l

1. l I r t

5 I

l i

t 4 f a j t

!9 ,

t is t

t, t t

I

(

f i

i 9 -

l I

i

+

l

a

-" ,COOLDOWN OUTSIDE CONTROL ROOM E0P 3504 Page 2 -

Rev. 2 j- ,

t

'l A. PURPOSE

1. The purpose of this procedure is to place the plant in a safe j stable condition following a Control Room Evacuation. i i
2. To establish RCS and steam generator conditions that would take the plant from a Hot Standby condition and to place it in a cold shutdown condition from outside the Control Room.
3. To borate the RCS, to establish and maintain reactos shutdown margin.
4. To prevent or limit inadvertent actuation of the Engineered Safeguards System.

B. ENTRY CONDITIONS

1. Conditions which may result in Shift Supervisor decision to evacuate the control room.
a. Smoke and/or fire in the Control Room, or Instrument Rack Room.
b. Fire in the Cable Spreading Room.

c Toxic gas present in the Control Room.

d. Radiatior, or radioactivity levels cutside safe limits.
2. Entry into this procedure asarme7 that control is established at the All par E0P 3503, S:lUTD0VN OUTSIDE THE CONTROL RLOM.
3. Thir, procedure it; appiscable from Modes 3, 4, and 5. Using this procedu e when not in (Sese mode-a re uires a step by step evaluation to determine if tha required action is still applicable to current plant conditions.

84 4

C00LDOWN OUTSIDE CONTROL ROOM E0P 350l. Page 3 Rev. 2 7

h

\m,/

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBT?.INED CAUTION

1. Reactor Coolant System voiding is possible during the course of this procedure if RCPs are not running. Voiding can be rerognized by
a. An unexplained increase in pressurizer level while trying to depressurize the Reactor Coolant System by pressurizer spray, power operated relief operation, or other means.

-0R-

b. An unexplained difficulty in reducing system pressure while operating with solid plant conditions in the Reactor Coolant System.

-OR-

,_ c. Indication of loop temperature readings equal to or greater than saturation temperature for a given

(\-) reactor coolant pressure.

Voiding can be overcome by

a. Increasing Reactor Coolant System pressure by means of pressurizer hestr rs er charging to a pressure greater than saturation for a given Recctor Coolant Syster, temperature.

-OR-

b. Decreasing desctor Coolant S fstem temperate r by feeding and steiming steam generitors, operation of core ecclirg equipment, or by adjustir g l

residual heat removal flow (if resfoual heat removal is in service; to a temperature below saturation for a given Reattot Coolant Sys s eca pressure.

-OR-

c. Increasing Reactor Coolant System flow rate which decreases the probability of hot spots occuring in stagnent or low flow areas of the Reactor Coolant System.

i ca.v.n , . .

C00LDOWN OUTSIDE CONTROL ROOM E0P 35U4 Page 4 Rev. 2 (vl STEP ACTHMd/ EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. Automatic control and protection systems may spuriously actuate or fail to respond due to a damaging event in the Control Room, Instrument Rack Room, or Cable Spreading Area. IF this occurs at any time, THEN complete Attachment D of E0P 3503, SHUTDOWN OUTSIDE CONTROL ROOM.
3. The occurrence of multiple high impedance faults (under some fire scenarios) may result in the inability to reenergize 120 VAC and 125 VDC busses due to repeated trips of the feeder breaker. This occurs when the faults are of insuffd.cient magnitude to trip each affected load breaker, but in total exceed the capacity of the feeder breaker. If this occurs to any panel listed in Attachment E of E0P 3503, Shutdown Outside Control Room, THEN to protect Appendix R loads, strip all loads from the affected panel and reenergize ONLY those circuits specified in Attachmeat E.

NOTES

,__s 1. Loss of indicating lights at the ASP is indicative

( ) of either

\m /

a, component not in local control, or

b. the component control power fuse has blown. .

Replacement of the control power fuse may be ,

necesstry to vperate the equipment.

I j .. There is no control of normal spra/ from the ASD. If there is no urgency for immediate depressurization, maintain stable plant ecnditions 1 and allno the PZR to cool down to depressarize.

Use aux spray only if necessary.

Cooldown by natural

1. STOP all but one RCP.

circulation.

a

2. Borate to cold shutdown conditions by one of the followirt (ASP)
a. Charging pump suction from the RWST
b. Gravity boration i

_ _3 . Verify cold shutduwn boron concentration by

( )

\d sampling the RCS.

- e. , u n

I COOLDOWN'0UTSIDE CONTROL ROOM E0P 3504 Page 5 Rev. 2

! I g/

STEP AC)hiN/ EXPECTED RESPONSE R2SPONSE NOT OBTAINED

4. IF no RCPs are running, THEN establish Reactor Vessel Head excess letdown to maintain head cooling. ,
5. Deenergize PZR heaters 3RCS*HIA ASP 3RCS*H1B 32V 4-2 (AB 24'6")

3RCS-HIC 32C 6-2 (AB 45')

3RCS-H1D 32B 7-2 (SB 4'6")

3RCS-HIE 32N 7-2 (SB 4'6")

CAUTION

1. Limit PZR cooldown to a maximum of 100*F/Hr.
2. Shif t AFW pump suction to the CST if DWST level ., ). \

decreases to (later).

NOTE Throttle seal injection as necessary with HCV 182 to maintain _8-13 gpm. During the cooldown the PE0 stationed in Aux Bldg may be required to adjust seal injection flow to each RCP.

6. Increase steaming rate of SG's to establish a cooldown rate oi ( 50*F/Hr (AFP)

Maintain SG narrow ringe level

~~7.

about 507..

Maintain PZR Icvel about 25'f.,

_ 8.

) _, ,9 . Reduce RCS pressure to Depressuri.* with Aux Spray, about 1935 psia. Observe IF Aux spray is NOT available, temperature - pressure limits piFjN depressurize with the of Technical Specifications. PZR PokVs.

(

>\

i C Pe # # . ' S 44

~~

- C00LDOWN OUTSIDE CONTROL ROOM E0P 3504 Page 6 Rev. 2

<-- l L--)

ACTION / EXPECTED RESPONSE RESFONSE NOT OBTAINED STEP f CAUTION 31ocking SI may not prevene a SIS due to the damaging event. Ensure unnecessary Train A equipment is in LOCAL and tripped. It may be necessary to deenergize 34D to prevent spurious Train B actuations.

10. Block Train A and Train B S1 actuation (ASP) a) Main Steamline SI -

Block A/B b) PZR Press SI -

Block A/B

11. Continue cooldown and depressurization.
12. Below 1000 psia restore power to SI accumulator isolation

) valves (AB 24'6") i

13. CLOSE all SI accumulator Vent any unisolated isolation valves accumulator.

3SIL*MOV8808A-D (ASP)

a. Transfet control of accumulator vent 3SIL*HCV943A to the ASP (FTSP)
b. Vent any unisolated accumulator. (ASP)

_j 4. Remove poser icom Si accumulator isolation valves 3SIL*MOV8808A 32-2R RSF (AB 24 6")

3SIL*MOV8808B 32-2W R3] (AB 24'6")

3SIL*MOV8808C 32-2R F4M (AB 24'6")

1SIL*MOV8808D 32-2W F4M (AB 24'6")

30,T E COPS will not be operable if placcil in ISOLA 1E at the 17SP.

O I o N N 4.a 1 44

9 C00LDOWN OUTSIDE CONTROL R0051 E0P 3504 Page 7 Rev. 2 m

1 L,/

$?EP ACTION / EXPECTED RESPCNSE RESPONSE NOT OBTAINED

15. When RCS temperature is < 425', and RCS pressure < 700 psia, arm COPS. (ASP)
a. Arm COPS - Train A
b. Arm COPS - Train B ,
16. Reduce RCS Temp to 350'F CAUTION IF RPCCW and RHR are not available DO NOT proceed beyond this point.

_____17. Rack down both SI Pump breakers when temperature is < 350'.

k-- 18. Rack down one charging pump breaker when temperature is < 350'.

19. Transfer control of RHR ItX1 and HX2 flow to the ASP by momentarily depressing the togglit switch on the GIM #, ASP).

NOT7.

l

1. Control of RHR isolat.icns inside containment '

are provided at the ASP, All othe- valves will -

have to be manually operated. I

2. A complete flow path verification should be performed prior ta initiating RHR flow.
20. Establish RER boron concentration per OP 3310A, RESIDUAL HEAT R'_10 VAL SYSTEM ,

O

(

[

. COOLDOWN OUTSIDE CONTROL ROOM E0P 35v4 Pags 8 Rev. 2 i i

\s /

-- STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

21. Align RPCCW for plant cooldown per OP 3330A, REACTOR PLANT COMPONENT COOLING
22. Align RHR for plat.t cooldown per OP 3310A, RESIDUAL HEAT REMOVAL SYSTEM  !
23. OPEN SLOWLY A and B N B KX RPCCW outlet flow control valves 3CCP*FCV66A, FCV66B to provide maximum cooling flow available (ASP)
24. START RHR Pump A (swited ear).
25. Slowly OPEN A RER HX Bypass Valve 3RHS*FCV618 locally to obtain about 4000 gpm RHR flow, l

I

26. START RHR Pump B (switchgear).

%J

27. Slowly OPEN B RHR EX Bypass Valve 3RHS*FCv'619 locally to obtain about 4000 gpm RHR flow.
28. Ccamence letdown from RHR
a. Verify letdown in a. Place letdown in service.

service,

b. Slowly OPEN RHR Letdown Flow Control valve 3CHS-HCV128 (ASP).

. CAUTION

1. Monitor the cooldowr. rate carefully when initiating RX flow.
2. Initiate flow through the RH RX slowly.

l 1 i a - .. , . .

g-

. i i,

  • C00LDOWN OUTSIDE CONTROL ROOM E0P 35ue Page 9 I Rev. 2  ;

-- STEP ACT10P0' EXPECTED RESPONSE RESPONSE NOT CBTAINED l

29 Slowly OPEN the following flow control valves to ,

initiate cooldown (ASP)

a. A RHR HX Flow Control valve 3RHS-HCV606
b. B RHR HX Flow Control valve 3RES-HCV607
30. Throttle the bypass flow control valves 3RHS-FCV618, FCV619 as necessary to main'.ain RHR total flow about 4000 gpm.
31. Manually isolate SG blowdown per OP 3316C, STEAM GENERATOR BLOWDOWN.
32. Stop the cooldown at about 250*F.

Isolate the SG (ASP)

O, 33.

4. CLOSE the atmospheric dumps
b. CLOSE the atmospheric dr.mp bypass valves
34. Place a nitrogen blanket on the SG pet OP 3316A, MAIN STEAM.
35. Adjust SG chemistry for wet layup.
36. Place each SG in set layup.
37. Continue the cooldown to less than 200* using RHR.

Observa pressure - temperature limitations.

O CMYS 1 1 44

C00LDOWN OUTSIDE CONTROL ROO!! E0P 3504 Page 10 Rev. 2 g ~S,

()

STEP ACTION / EXPECTED RESPONSE RESFONSE NOT OBTAINED

38. When RCS temperature is

< 200'F,

a. Rack down A and B Quench Spray Pamp Breakers
b. Rack down A, B, C and D Containment Recirculation Pump Breakers
39. Consult plant management on further plant conditions.

-FINAL-

.s e

O

~

4 t

Retrieved from "https://kanterella.com/w/index.php?title=ML20205A906&oldid=3061744"