ML17263A265

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Rev 7 to EOP ES-3.1, Post-SGTR Cooldown Using Backfill
ML17263A265
Person / Time
Site: Ginna Constellation icon.png
Issue date: 04/21/1993
From: Marlow T
ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17263A255 List:
References
ES-3.1, NUDOCS 9305140030
Download: ML17263A265 (28)


Text

EOP:

ES-3 '

TITLE:

POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 1 of 9 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

93053,4'0030 930505 PQR

  • DOCK 00000244 F

PDR

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EOP:

ES-3.1 T1TLE:

POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 2 of 9 A.

PURPOSE This procedure provides actions to cool down and depressurize the plant to cold shutdown conditions following a SGTR.

This recovery method depressurizes the ruptured S/G by draining it through the ruptured S/G tubes into the RCS.

B.

ENTRY CONDITIONS/SYMPTOMS 1.

ENTRY CONDITIONS This procedure is entered from:

a.

E-3 STEAM GENERATOR TUBE RUPTURE, if plant staff selects backfill method.

ES 3 ~ 2 g POST SGTR COOLDOWN USING BLOWDOWNg when blowdown is not available and plant staff selects backfill method.

EOP:

ES-3.1 TITLE:

POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 3 of 9 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED CAUTION INADVERTANT CRITICALITYMAY OCCUR FOLLOWING NATURAL CIRCULATION COOLDOWN IF THE RCP IN THE RUPTURED LOOP IS STARTED FIRST.

NOTE:

o FOLDOUT page should be open AND monitored periodically.

o Adverse CNMT values should be used whenever CNMT pressure is greater than 4 psig or CNMT radiation is greater than 10+O5 R/hr.

1 Energize PRZR Heaters As Necessary To Saturate PRZR Water At Ruptured S/G Pressure

EOP I ES-3.1 TITLE:

POST-SGTR COOLDOWN USING BACKFILL REV!

7 PAGE 4 of 9 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 2

Check If SI ACCUMs Should Be Isolated:

a.

Check the following:

o RCS subcooling based on core exit T/Cs

- GREATER THAN O' USING FIGURE MIN SUBCOOLING a.

Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -

SUBCOOLED RECOVERY DESIRED, Step 1.

o PRZR level -

GREATER THAN 5%

[30$ adverse CNMT]

b. Dispatch AO 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

~ ACCUM A, MOV-841

~ ACCUM B, MOV-865

c. Vent any unisolated ACCUMs:
1) Open vent valves for unisolated SI ACCUMs.
d. Locally reopen breakers for MOV-841 and MOV-865

~ ACCUM A, AOV-834A

~ ACCUM B, AOV-834B

2) Open HCV-945.

EOP:

ES-3.1 TITLE:

POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 5 of 9 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED NOTE:

Leakage from ruptured S/G into RCS will dilute RCS boron concentration.

3 Verify Adequate Shutdown Margin

a. Dirept HP to sample RCS and ruptured S/G for boron concentration
b. Verify boron concentration-GREATER THAN REQUIREMENTS OF FIGURE SDM
b. Borate as necessary.

CAUTION IF CST LEVEL DECREASES TO LESS THAN 5 FEET, THEN ALTERNATE WATER SOURCES FOR AFW PUMPS WILL BE NECESSARY (REFER TO ER-AFW.1, ALTERNATE WATER SUPPLY TO AFW PUMPS).

NOTE:

TDAFW pump flow control valves fail open on loss of IA.

  • 4 Monitor Intact S/G Level:
a. Narrow range level GREATER THAN 5%

[25% adverse CNMT]

b. Control feed flow to maintain narrow range level between 17%

[25% adverse CNMT] and 50%

a. Maintain total feed flow greater than 200 gpm until narrow range level greater than 5%

[25%

adverse CNMT] in the intact S/G.

b. IF narrow range level in the intact S/G continues to increase in an uncontrolled manner, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT -

SUBCOOLED RECOVERY DESIRED, Step l.

I

EOP:

ES-3.1 TITLE:

POST-SGTR COOLDOWN USING BACKFILL REVE 7

PAGE 6 of 9 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED NOTE:

Since ruptured S/G 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 Cold Shutdown:

a. Establish and maintain cooldown rate in RCS cold legs

- LESS THAN 100'F/HR b.

Use RHR system if in service c.

Dump steam to condenser from intact S/G

c. Manually or locally dump steam using intact S/G ARV.

IF no intact S/G available and RHR system NOT in service, THEN perform the following:

o Use faulted S/G.

-OR-o Go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.

  • 6 Monitor Ruptured S/G Narrow Range Level LEVEL GREATER THAN 174 (25% adverse CNMT]

Refill ruptured S/G to 678

[55%

adverse CNMT] using feed flow.

IF either of the following conditions occurs, THEN stop feed flow to ruptured S/G:

o Ruptured S/G pressure decreases in an uncontrolled manner.

-OR-o Ruptured S/G pressure increases to 1020 psig.

EOP:

ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 7 of 9 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED

  • 7 Control RCS Makeup Flow And Letdown To Maintain PRZR Level:

a.

PRZR level GREATER THAN 13%

[40% adverse CNMT) b.

PRZR level - LESS THAN 75%

[65%

adverse CNMT]

a.

Increase RCS makeup flow as necessary and go to Step 8.

b, Decrease RCS makeup flow to decrease level and go to Step 10.

NOTE:

The upper head region may void during RCS depressurization if RCPs are not running.

This may result in a rapidly increasing PRZR level.

  • 8 Depressurize RCS To Backfill From Ruptured S/G:
a. Depressurize using normal PRZR spray
a. IF letdown is in service, THEN depressurize using auxiliary spray valve (AOV-296). IF NOT, THEN use one PRZR PORV.
b. Maintain PRZR level -

BETWEEN 13%

AND 75%

[BETWEEN 40%

AND 65%

adverse CNMT]

c.

Check ruptured S/G level-GREATER THAN 5%

[25% adverse CNMT]

c. Stop RCS depressurization.
d. Energize PRZR heaters as necessary
e. Maintain RCS subcooling based on core exit T/Cs

- GREATER THAN O'F USING FIGURE MIN SUBCOOLING

EOP:

ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 8 of 9 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 9 Establish Required RCS Hydrogen Concentration (Refer to S-3.3C, H2 Or 02 REMOVAL FROM PRIMARY SYSTEM BY BURPING VCT) 10 Check If RHR Normal Cooling Can Be Established:

a.

RCS cold leg temperature

- LESS THAN 350'F a.

Go to Step 11 RCS pressure

- LESS THAN 400 psig (300 psig adverse CNMT]

c. Place RCS overpressure protection system in service (Refer to 0-7, ALIGNMENT AND OPERATION OF THE REACTOR VESSEL OVERPRESSURE PROTECTION SYSTEM)
d. Establish RHR normal cooling (Refer to Attachment RHR COOL) b.

Go to Step 11.

c. IF RCS overpressure protection system can NOT be placed in
service, THEN notify TSC of potential Tech Spec violation if RHR system is placed in service.
  • ll Monitor RCP Operation:

a.

RCPs

- ANY RUNNING b.

Check the following:

o RCP ¹1 seal D/P -

LESS THAN 220 PSID a.

Go to Step 12.

b.

Go to Step 12.

-OR-o Check RCP seal leakage

- LESS THAN 0.25 GPM

c. Stop affected RCP(s)

EOP:

ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV 7

PAGE 9 of 9 STEP ACTION/EXPECTED RESPONSE

RESPONSE

NOT OBTAINED 12 Check Core Exit T/Cs LESS THAN 200'F Return to Step 3.

13 Evaluate Long Term Plant Status:

a. Maintain cold shutdown conditions (Refer to 0-2.3, PLANT AT COLD OR REFUELING SHUTDOWN)
b. Consult TSC

-END-

l S

EOP:

ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 1 of 1 ES-3.1 APPENDIX LIST TITLE 1)

RED PATH

SUMMARY

2)

FIGURE MIN SUBCOOLING 3)

FIGURE SDM 4)

ATTACHMENT RHR COOL 5)

FOLDOUT PAGES

ES-3.1 POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 1 of 1 RED PATH

SUMMARY

a.

SUBCRITICALITY Nuclear power greater than 54 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 434 t'464 adverse CNMT]

c.

HEAT SINK Narrow range level in all S/Gs less than 54

[254 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

E>

EOP:

ES-3 '

TITLE:

POST-SGTR COOLDOWN USING BACKFILL REV:

7 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 O' USING REQUIREMENTS OF FIGURE MIN SUBCOOLING.

OR 2 ~

o PRZR level CHARGING CAN NOT CONTROL LEVEL GREATER THAN 54

[304 adverse CNMT].

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 4.

5.

IF RWST level decreases to less than 284, THEN go to ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1.

AFW SUPPLY SWITCHOVER CRITERION IF 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).

MULTIPLE S G TUBE RUPTURE CRITERIA IF any intact S/G level increases in in an uncontrolled manner OR IF any intact S/G has abnormal radiation, THEN go to ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 1.

(

EOP:

ES-3.1 TITLE:

POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 1 of 1 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 (PPH) 1800 1600 BORON INCREMENTS 20 PPH 1400 1200 1000 ADEQUATE SDM 100 PPH CONSERVATISH INCLUDED 800 600 400 BO TE 200 BURNUP INCREMENTS 100 HWD/HTU 0

1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 11000 CYCLE 23 BURNUP (HWD/HTU)

EOP:

ES-3. 1 TITLE:

POST-SGTR COOLDOWN USING BACKFILL REV:

7 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE:

Subcooling Margin = Saturation Temperature From Figure Belov (-] Core Exit T/C Indication S

PRESSURE (PSIG)

RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1500 1400 1300 1200 1100 1000 900 800 700 600 500 400 300 200 100 0

20 RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION INADEQUATE SUBCOOL ING REGION DVERSE CNMT TEMPERATURE INCREMENTS 10 F

NORMAL CNMT 0

250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)

I