ML20092G861
| ML20092G861 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/04/1990 |
| From: | Bochhold J GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20092F288 | List:
|
| References | |
| CON-IIT05-087-90, CON-IIT5-87-90, RTR-NUREG-1410 VEGP-18020-C, NUDOCS 9202200377 | |
| Download: ML20092G861 (5) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _. _ _.. _ _ _ _ _ _ _. _ _ _ _ _ _ _
PtoC%utQ NO.
Yogtle Electric Generating Plant 18020-C NUCLEAR OPERATIONS
%. ion s3 i
3 Unit COMMON Geogia Power
"* "f o r 5 g
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D :l ' - 5 ') ]()
MiDLer stres ABNORMAL OPERATING PROCEDURE LOSS OF COMP 0NENT COOLING WMER \\g0
~
PURPOSE This procedure addresses the loss of one CCW Train with both RHR and SFPC Systems in operation.
i SYMPTOMS e
CCW TRAIN A(B) LO HDR PRESS Annunciator.
e CCW TRAIN A(B) LO FLOW Annunciator.
e CCW TRAIN A(B) SURGE TANK LO-LO LVL Annunciator.
o CCW TRAIN A(B) RHR PMP SEAL LO FLOW Annunciator, e
NSCW TRAIN A(B) LO HDR PRESS Annunciator.
l e
NSCW CCW ACCW TRAIN A(B) TEMP ALARM Annunciator.
e CCW TRAIN A(B) RHR HX HI FLOW Annunciator.
e CCW TRAIN A(B) RHR HX LO FLOW Annunciator.
er 6
(
i b
~
- 882
- 288U 3586s 6 S
PDR w oia wa
_., ~..
'PMoClDUAE NO.
Asv@oN Pt QE No.
I 1
VEGP 18020-C 3
2 of 5 B
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED, 1.
Verify two CCW pumas in the 1.
Start two CCW pumps in the f
affecte,d trhin - RJNNING.
affected train nr%rY
-l 2.
VLrify CCW train operationi b.
Stop the CCW pumps in the N
i Flow - Approximately unaffected train in service
-Jl '
affected train.
Place the e
9000 GPH.
by initiating 13715, COMPONENT COOLING WATER Pressure - Approximately SYSTEM.
g j
e 90 psig.-
IF one train of CCW can NOT 5e placed in service, THEN initiate 18019-C, LOSS UTTESIDU/.L HEAT REMOVAL
.M i
18030-C, LOSS OF SPENT FUEL l
POOL LEVEL OR COOLING.
3.
Initiate 18021-C, LOSS OF O
Total Flow Approximately NUCLEAR SERVICE COOLING 18000 Gpm As Read On WATER SYSTEM.
FI-1640B (16415).
W
' CAUTION RHR Pump seal cooling is provided by the-respective CCW vr Train.
Damage to the seal assembly may result from j
sustained operation-of the pump without CCW flow to the seal cooler.
4.
Place the non-affected RHR 4.
Initiate 18019-C, LOSS OF L[
Train in operation by RESIDUAL HEAT REMOVAL and.
initiating 13011, applicable ACTION items for:
RESIDUAL HEAT RDIOVAL
\\
SYSTEM.
^"C Tech Spec 3.4.1.4.1 e
Tech Spec 3.9.8.1 N-e Tech Spec 3 Q 1 e\\
d
PMOCEDU,- E NO LEVILION PAGE t#O.
VEGP 18020-C 3
3 of 5 t,
~}
ACTION /EXPECTEQ RESPONSE RESPONSE NOT OBTAINED 5.
Verify the CCW train A(B) 5.
Verify Demineralized Water surge tank tow level Makeup Valve LV-1850(1851)
Annunciator is - Reset Or is open.
Level Is Rising.
-OR-Manually open surge tank makeu from RMWST LV-1848 (1849.
6.
Verify the affected CCW 6.
Isolate the leak by:
train has - No Unexpected
- Leakage, e
Stop the pumps in the affected train and place the control switches in PULL-TO-LOCK.
e Isolate makeum water to the surge tani.
Clone system isolation
.r~'
valves as necessary.
-\\
r er 1
l l
l O(_)
'?D3449
P90CE DU.,f NO.
- ,gvisiod~
pagg gg VECP 18020-C 3
4 of 5
\\
(m)
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED
.</
7.
Verify the affected CCW Heat Exchanger cooling capacity - Not Impaired By:
- a. Venting the heat exchanger
- a. Continue venting until tube ara shell sides of all trapped air or gases tranped air or gases per are removed.
13715,00KPOWENTCOOLING WATER SYSTEM.
NOTE Heat exchanger plugging or fouling may be indicated by a higher than normal pressure drop, a lower than normal flowrate or a lower than normal temperature rise in the cooling water,
- b. Check the tube side
- b. Initiate 18021-C, LOSS OF pressure drop - Less NUCLEAR SERVICE COOLING
~s (v)
Than or Equal To 6 Psid.
WATER SYSTEM.
- c. Check NSCW flow through
- c. Initiate 18021-C, LOSS OF the CCW Heat Exchanger on NUCLEAR SERVICE COOLING local flow indicator WATER SYSTEM.
FIT-1720A (1721A) - Equal To Or Greater Than 9000 Gpm.
- d. Check the NSCW temperature
- d. Initiate 18021-C, b9SS OF rise across the CCW Heat NUCLEAR SERVICE COOLING Exchanger on local WATER SYSTEM.
temperature indicators -
approximately 4*F.
e TI-1712(1713) e TI-1716(1717) 13 h
F0Mel
..... ~. _ - - - -. _ ~ - - -.. - - _. _ - -. -. -... -. -. _
~
8 NEDURE NO.
LgvessoN PAOL NO.
VECF 18020-0 3
5 of 5
{}
ACTION /IIFECTED RESPONSE RESPONSE NOT OBTAINED 8.
RestoreiheaffectedCCW 8.
Implement the a plicable loop to service b Tech. Spec. ACT ON statement initiating 13715,y for the current plant COMPONENT COOLING WATER condition:
-SYSTEM.
e Tech Spec 3.4.1.4.1 Tech Spec 3.4.1.4.2 e
9.
Verify Spent Fuel Pool 9.
Place the non-affected SFPC tangerature is - Less Than Train in service by 130 F.
initiating 13719, SPENT
,l FUEL POOL COOLING AND PURIFICATION SYSTEM.
1 l
10.' Verify Fuel Handling Bldg.
10.
Start Fuel Pool Area Normal NVAC Units Recirculating Air Handling O-1541-A7-001(002) and Unit 1541-A7-003(004) by In initiating 13320 FUEL 1541-N7-001(002)
Operation.
HANDLING BUILDING HVAC SYSTEM.
11.
Return'to the UOP In effect.
or END OF PROCEDURE TEXT O
Sha$
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