ML20065K079
| ML20065K079 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/30/1994 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17263A585 | List:
|
| References | |
| ES-3.3, NUDOCS 9404190149 | |
| Download: ML20065K079 (17) | |
Text
4 EOP:
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ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 12 p
V ROCHESTER GAS AND ELECTRIC CORI'SRATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE
~30~ /k f3 o
n '.< / / / x
/,-
PLANT SUPERINTENDENT Ll ')
fj 1f EFFECTIVE'DATE CATEGORY 1.0 REVIEWED BY:
O 9404190149 940414 PDR ADOCK 05000244
.P PDR
s EOP:
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REV: 9 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 2 of 12 j
9 k_/
A.
PURPOSE - This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR.
This recovery methed depressurizes the ruptured S/G by dumping steam.
)
B.
ENTRY CONDITIONS / SYMPTOMS l
l 1.
ENTRY CONDITIONS - This procedure is entered from:
a.
E-3 STEAM GENERATOR TUBE RUPTURE, if plant staff selects steam dump method.
b.
ES-3.2, POST-SGTR COOLDOWN USING BLOWDOWN, when blowdown is not available and plant staff selects steam dump method.
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g ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 1
PAGE 3 of 12
(.
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED f
i CAUTION 1
STEAM SHGULD NOT BE RELEASED FROM ANY RUPTURED S/G IF WATER MAY EXIST IN o
ITS STEAMLINE.
AN OFFSITE DOSE EVALUATION SHOULD BE COMPLETED PRIOR TO USING THIS o
PROCEDURE.
NOTE:
o FOLDOUT page snould be open AND monitored periodically, Adverse CNMT values should be used whenever CNMT pressure is o
greater than.4 psig or CNMT radiation is greater than 10+05 R/hr.
,t
-1 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure s
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REV: 9 1
ES>3.3_
POST-SGTR COOLDOWN USING STEAM DUMP I
PAGE 4 of 12
~
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED f
2 Check If SI ACCUMs should Be Isolated:
a.
Check the following:
- a. Go to ECA-3.1, SGTR WITH LOSS OF l
REACTOR COOLANT - SUBC00 LED L
o RCS subcooling based on core RECOVERY DESIRED, Step 1.
exit T/Cs CREATER THAN 0*F USING FI..'AE MIN SUBC00 LING 1
I o PRZR level - GREATER THAN 51 l
[30% adverse CNMT]
- b. Dispatch A0 with locked valve key to locally close breakers.
for SI ACCUM discharge valves
- MOV-841, MCC C position 12F
- MOV-865, MCC D position 12C
- c. Close SI ACCUM outlet valves
- c. Vent any unisolated ACCUMs:
1
- ACCUM A, MOV-841
- 1) Open vent valves for l
- ACCUM B, MOV-865 unisolated SI ACCUMs.
- ACCUM A, A0V-834A
- ACCUM B, A0V-834B
- 2) Open HCV-945, d.
Locally reopen breakers for MOV-841 and MOV 865 9 -
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TITLE:
ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE S of 12 i
O
'Q STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i
NOTE:
Leakage from ruptured S/G into RCS will dilute RCS baron concentration.
3 Verify Adequate Shutdown Margin
- b. Verify boron concentration -
- b. Borate as necessary.
CREATER TRAN REQUIREMENTS OF FICURE SDM
u)
NOTE:
TDAFW pump flow control valves fail open on loss of IA.
- 4 Monitor Intact S/G Level:
- a. Narrow range level - CREATER a.
Maintain total feed flow greater THAN 51 (25% adverse CNMT]
than 200 gpm.atil narrow range level greater than 5% [25%
adverse CNMT] in intact S/G,
- b. Control feed flow to maintain
- b. JJ narrow range level in the narrow range level between 17%
intact S/G continues to increase
[25% adverse CNMT] and 50%
in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, Step 1.
V
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REV: 9 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP
[
PAGE.6-of 12 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP NOTE:
Since ruptured S/C may continue to depressurize to less than the minimum RCS pressure necessary for continued RCP operation, cooldown to cold shutdown should not be delayed.
5 Initiate RCS Cooldown To 350*F:
- a. Establish and maintain cooldown rate in RCS cold legs - LESS THAN 100*F/HR
- b. Dump steam to condenser from
- b. Manually or locally dump steam-intact S/G from intact S/G using S/G ARV.
JZ no intact S/G available, THEN perform the following:
Use faulted S/G.
o
-OR-o Go.to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBC00 LED RECOVERY DESIRED, Step 1.
O
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Titte:
REV: 9 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 7 of 12
~
t STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTIOf]
RCS AND RUPTURED S/C PRESSURES MUST BE MAINTAINED LESS THAN 1050 PSIG.
- 6 Control RCS Pressure And Makeup Flow To Minimize RCS-To-Secondary Leakage:
a.
Perform appropriate action (s) from table:
PRZR RUPTURED S/C NARROW RANCE LEVEL LEVEL i
INCREASING DECREASING OFFSCALE HICH LESS THAN 13%
o Increase RCS Increase RCS o Increase RCS (40% ADVERSE CNMT]
makeup flow makeup flow makeup flow o Depressurize o Maintain RCS RCS using and ruptured
/~h Step 6b.
S/G pressure Q
equal BETWEEN 13%
Depressurize Energize Maintain RCS
[40% ADVERSE CNMT)
RCS using PRZR and ruptured AND 50%
Step 6b.
heaters S 'G pressure e qu a.t BETWEEN 50% AND 75% o Depressurize Energize Maintain RCS
[65% ADVERSE CNMT)
RCS using PRZR and ruptured Step 6b.
heaters S C pressure fequal o Decrease RCS makeup flow CREATER THAN 75%
o Decrease RCS Energize Maintain RCS
[65% ADVERSE CNMT) makeup flow PRZR and ruptured heaters S/G pressure equal
- b. Use normal PRZR spray to obtain
- b. J,.F letdown is in service, THEN desired results for Step 6a use auxiliary spray (A0V-296).
IF NOT, THEN use one PRZR PORV.
O
e iOPt fille:
REV: 9 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP
+
PAGE 8 of 12 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 OR O2 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 8 Check If RCS Cooldown Should Be Stopped:
- a. RCS cold leg temperatures - LESS a.
Return to Step 3.
THAN 350'F
temperature - LESS THAN 350*F
- 9 Monitor Ruptured S/G Narrow Refill ruptured S/C to 67% [55%
s Range Level - LEVEL GREATER adverse CNMT) using feed flow.
THAN 17% [25% adverse CNMT)
If either of the following conditions occurs, THEN stop feed-flow to ruptured S/G:
Ruptured S/C pressure decreases o
in an uncontrolled manner.
-OR-Ruptured S/G pressure incr..ases o
to 1020 psig, O
6-EOP ilILE:
REV: 9 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 9 of 12 ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP CAUTION RUPTURED S/C PRESSURE MAY DECREASE RAPIDLY k'llEN STEAM IS RELEASED.
NOTE:
Steam release from ruptured S/G may be stopped when RHR System is-in service.
10 Initiate Cooldown Of Ruptured S/G:
a.
Verify condenser available:
- a. Manually or locally dump steam using ruptured S/G ARV and go to o
Intact S/G MSIV - OPEN Step 11.
o Annunciator G-15, STEAM DUMP AILMED - LIT b Dispatch A0 to locally open ruptured S/G MSIV bypass valve
- c. Dump steam to condenser using steam dump pressure controller
- 11 Control RCS Makeup Flow And Letdown To Maintain PRZR Level:
i a.
PRZR level GREATER THAN 13%
a.
Increase RCS makeup flow as (40% adverse CNMT]
necessary and go to Step 12,
-l b.
PRZR level - LESS TilAN 75% [65%
b Decrease RCS makeup flow to adverse CNMTJ decrease level and go to Step 13.
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i REV: 9 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 10 of 12 L
~
(v STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED NOT F,:
The upper head region may void during depressurization if RCPs are not running.
This may result in a rapidly increasing PRZR level.
- 12 Depressurize RCS To Minimize RCS-To-Secondary Leakage:
- a. Depressurize using normal PRZR a.1F letdown is in service, THEN spray associated with running RCP depressurize using auxiliary 1
spray valve (A0V-296).
IF NOT, THEN use one PRZR PORV.
- b. Energize PRZR heaters as necessary
- c. Maintain RCS pressure at ruptured S/G pressure
- d. Maintain RCS subcooling based on core exit T/Cs - GREATER THAN O
0*F USING FIGURE MIN SUBC00 LING
- 13 Monitor RCP Operation:
- a. RCPs - ANY RUNNING
- a. Go to Step 14,
- b. Check the following:
- b. Go to Step 14.
RCP #1 seal D/P - LESS THAN o
220 PSID
-OR-Check RCP seal leakage - LESS o
THAN 0.25 GPM c.
Stop affected RCP(s) l l
il l
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REV: 9 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 11 of 12 O
)
STEP ACTIC.4/ EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check If RHR Normal Cooling Can Be Established
- a. RCS cold leg temperature - LESS
- a. Return to Step 9.
THAN 350*F
- b. RCS pressure - LESS TRAN
- b. Return to Step 9, 400 psig (300 psig adverse CNMT]
- c. Place RCS overpressure
- c. JJ RCS overpressure protection protection sy.ecem in service system can _N_0_T be placed in (Refer to 0-7 ALIGNMENT AND service, THEN notify TSC of OPERATION OF THE REACTOR VESSEL potential Tech Spec violation if OVERPRESSURE PhqTECTION SYSTEM)
RHR system is placed in service.
Shutdown:
- a. Maintain cooldown rate in RCS cold legs - LESS THAN 100'F/HR
- b. Use RHR System
- c. Dump steam to condenser from
- c. Manually or locally dump steam intact S/G using intact S/C ARV JF no intact S/G available and RER system bR in service, THEN perform the following:
Use faulted S/G.
o
-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -
SUBC00 LED RECOVERY DESIRED, Step 1.
s
l EOPr ilTLE:
REV: 9 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 12 of 12 im t
ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED STEP 16 Check Core Exit T/Cs - LESS Return to Step 9 THAN 200*F l
17 Evaluate Long Term Plant Status:
a.
Maintain cold shutdown conditions ("afer to 0-2.3.
PIANT AT COLD JR REFUELING SilUTDOWN)
- b. Consult TSC
-END-oV
D iof:
~Tiia:
~
ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 m
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ES-3.3 APPENDIX LIST TITLE PAGES 1)
RED PATl!
SUMMARY
1 2)
FIGURE MIN SUBCOOLING 1
3)
FIGURE SDM 1
4)
ATTACHMENT RIIR COOL 2
5)
FOLDOUT 1
[)
m s
I gen ma,
Rgv g
ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1
.rm
(
)
~
K/-
RED PATH
SUMMARY
l a.
SUBCRITICALITY - Nuclear power greater than 5%
b.
CORE COOLING - Core exit T/Cs greater than 1200*F
-OR-Core exit T/Cs greater than 700'F AND RVLIS level (no RCPs) less than 43% [46%
adverse CNMT) c.
HEAT SINK - Narrow range level in all S/Gs less than 5%
[25% adverse CNMT] AND total feedwater flow less than 200 gpm d.
INTEGRITY - Cold leg temperatures decrease greater than 100'F in last 60 minutes AND RCS cold leg temperature less than 285'F e.
CONTAINMENT - CNMT pressure greater than 60 psig O'
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REV: 9 ES-3.3 POST-SGTR COOLDOWN USIt1G STEAM DUMP PAGE 1 of.1 1
FIGURE MIN SUBCOOLI!1G NOTE:
Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RCS PRESSURE (PSIG) 2500
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200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE (*F)
f.'
TdP ilILE:
REV:-9 ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 p
'tN FIGURE SDM NOTE:
o Curve includes allowance for one stuck rod.
Add 100 ppm for each additional stuck rod.
o To obtain core burnup, use PPCS turn on code BURNUP.
BORON CONCENTRATION (PPM) 1800 n.. r.. 9 %..&. r.u., tg tn. twg.n. tn..;, t;+.nn n t.,it t. : 13n,4 e
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(OP:
M TLE:
g ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP PAGE 1 of 1 FOLDOUT PAGE 1.
SI REINITIATION CRITERIA If either condition listed below occurs, THEN operate SI pumps manually as necessary and go.to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1:
o RCS subcooling based on core exit T/Cs -
LESS THAN 0*F USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.
9E o
PRZR level - CHARGING CAN NOT CONTROL LEVEL GREATER THAN 5% (30% adverse CNMT).
2.
SECONDARY INTEGRITY CRITERIA If any S/G pressure is decreasing in an uncontrolled manner or is completely depressurized AND has not been isolated, THEN go to E-2, FAULTED S/G ISOLATION, Step 1.
(
3.
COLD LEG RECIRCULATION SWITCHOVER CRITERION If RWST level decreases to less than 28%, THEN go to ES-1,3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.
4.
AFW SUPPLY SWITCHOVER CRITERION IE CST level decreases to less than 5 feet, THEN switch to alternate AFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).
5.
MULTIPLE S/G TUBE RUPTURE CRITERIA If any intact S/G level increases in in an uncontrolled manner 9B IE any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBCOOLED RECOVERY DESIRED, Step 1.
O
_