ML17261A984
| ML17261A984 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/23/1990 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17261A978 | List: |
| References | |
| AP-RCS.1, NUDOCS 9003080334 | |
| Download: ML17261A984 (46) | |
Text
EOP:
AP-RCS.1 T!JLE:
REACTOR COOLANT LEAK REV:
6 PAGE 1 of 9 ROCHESTER GAS AND ELECTRIC CORPORATXON GINNA STATXON CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVXEW DATE T SUPERX EN ENT 443-0 EFFECTIVE DATE QA~ NON-QA REVIEWED BY:
CATEGORY 1.0 GlNNASTATlON START:
DATE TlME C~ f(jt \\ )
DATE TIME:
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AP-RCS.1 REACTOR COOLANT LEAK REV:
6 PAGE 2 of 9 A.
PURPOSE This procedure provides the instructions necessary to mitigate the consequences of a reactor coolant leak.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure is entered from:
a.
S-12.2, Operator Action in the event of indication of significant increase in leakage.
b.
AP-CVCS.1, when leak cannot be isolated.
2.
SYMPTOMS The symptoms of REACTOR COOLANT LEAK are; a.
Annunciator F-14, Charging pump speed alarm, or b.
Annunciator A-2, VCT Level 144 86, alarm or, c.
Annunciator E-16, alarm, or RMS Process Monitor High Activity>>
d.
Annunciator E-24, RMS Area Monitor High Activity, alarm, or e.
Annunciator F-4, Pressurizer Level Deviation -5 Normal
+5, alarm, or, f.
Annunciator F-10, Pressurizer Lo Press 2185 psi, alarm, or g.
Annunciator F-11, Pressurizer Lo Level 134, alarm, lit.
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AP-RCS.1 TlTLE:
REACTOR COOLANT LEAK REV:
6 PAGE 3 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
1 Check RCS Inventory:
a.
PRZR level - DECREASING Go to Step 4..
2 Establish Stable PRZR Level:
- a. Start - ADDITIONAL CHARGING PUMPS AND INCREASE SPEED AS NECESSARY
- b. Check PRZR level - STABLE OR INCREASING
- b. Close LTDN loop B cold leg to RHx AOV-427.
3 Check PRZR Level GREATER THAN 134 AND STABLE OR INCREASING IF available charging pumps are running at maximum speed with letdown secured, AND PRZR level is decreasing, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION.
EOP:
AP-RCS.1 REACTOR COOLANT LEAK REV:
6 PAGE 4 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
o An investigation should be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of detecting a
significant increase in 'leakage from the RCS (Refer to S-12.2, OPERATOR ACTION IN THE EVENT OF INDICATION OF SIGNIFICANT INCREASE IN LEAKAGE).
o IF VCT level decreases to 5X, charging pump suction will swap to the RWST.
This may require a load reduction.
4 Check VCT Level:
a.
VCT level - GREATER THAN 5X b.
VCT level - STABLE OR INCREASING
- c. Reactor makeup control-OPERATING IN AUTO
- a. Verify charging pump suction swap to RWST:
- 1) Emergency makeup RWST to charging pump LCV-112B - OPEN 2)
VCT outlet vlv LCV-112C-
. CLOSED.
- b. Check RMW system:
- 2) Perform VCT makeup manually, as required.
3)
Go to Step 5.
- c. Place reactor makeup control in AUTO.
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AP-RCS.1 T1TLE:
REACTOR COOLANT LEAK REV:
6 PAGE 5 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 5
Check CVCS Conditions:
a.
Letdown indication:
o Letdown flow - APPROXIMATELY 40 GPM
-AND-
- a. IF letdown isolated, THEN continue with Step 5b.
IF NOT
- isolated, THEN GO TO AP-CVCS.1, CVCS LEAK.
o Letdown pressure-APPROXIMATELY 250 PSIG
- b. Charging line pressure-APPROXIMATELY 2400 PSIG c.
RCP seal infection indications-SEAL INJECTION FLOV METERS GREATER THAN 5 GPM b.
Go to AP-CVCS.1, CVCS LEAK.
c.
Go to AP-CVCS.1, CVCS LEAK.
CAUTION HEALTH PHYSICS TECHNICIAN SHOULD BE CONSULTED PRIOR TO ENTERING A HIGH AIRBORNE AREA.
6 Check CNMT AND AUX BLDG Radiation Monitors 'ORMAL (Normal reading found on Radiation Monitoring Charts)
IF RCS leakage is to CNMT atmosphere and can NOT,be isolated
- remotely, THEN, go to Step
- 13. If leakage is indicated in Aux Bldg, THEN, direct AO to investigate AND go to Step 7.
7 Check CCW Surge Tank Level APPROXIMATELY 504 AND NOT INCREASING Go to AP-CCV.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.
l
AP-RCS.1 REACTOR COOLANT LEAK REV 6
PAGE 6 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 8
Check PRT Conditions:
o PRT level - STABLE Go to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.
o PRT pressure
- APPROXIMATELY 1.5 PSIG AND STABLE o
PRZR relief tk liquid temp - AT CNMT AMBIENT TEMPERATURE AND STABLE o
PRZR valve leakoff temperatures
- NORMAL (Normal readings found on Pressurizer Valve Leak-Off Temperature Record Log
AP-RCS.1 TITLE:
REACTOR COOLANT LEAK REV 6
PAGE 7 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION STEAM GENERATOR TUBE LEAKAGE IN ONE S/G SHALL NOT EXCEED O.l GPM WHEN AVERAGED OVER 24 HOURS.
9 Check S/Gs For Leakage:
o Air effector radiation monitors (R-15, R-15A) - NORMAL (Normal readings found on Radiation Monitoring Charts) o S/G blowdown radiation monitor (R-19) - NORMAL (Normal readings found on Radiation Monitoring Charts) o Steamline radiation monitors (R-31, R-32) - NORMAL (Normal readings found on Radiation Monitoring Charts) o S/G sample activity - NORMAL (Check with HP Department for normal)
IF S/G tube leak indicated, THEN refer to 0-6.10, PLANT OPERATION WITH A S/G TUBE LEAK INDICATION.
10 Check Accumulator Levels:
o Accumulator levels - STABLE To calculate in leakage to accumulators, refer to S-16.11, MONITORING INLEAKAGE TO SI ACCUMULATORS.
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AP-RCS.1 REACTOR COOLANT LEAK REV 6
PAGE 8 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED ll Check RCDT Level:
a.
RCDT leak rate - NOT INCREASING a.
Check sources of inleakage to RCDT:
- 1) IF RV flange leakoff temperature has increased, THEN close Rx vess flange seal leakoff vlv AOV-521.
- 2) Verify proper operation of RCP seals.
IF RCP seal malfunction, THEN go to AP-RCP.1, RCP SEAL MALFUNCTION.
- 3) Verify excess letdown isolated.
- 4) IF source of leakage is NOT 1,
2 or 3 above, THEN suspect loop drains.
12 Check Valve Leakoff Temperatures NORMAL (Normal readings found on Pressurizer Valve Leak-Off Temperature Record Log)
IF any valve leakoff temperature are abnormally high, THEN, perform further investigation of that leakage path.
13 Check CNMT Radiati'on Monitors
- NORMAL (Normal readings found on Radiation Monitoring Charts)
IF leakage is indicated in CNMT, THEN:
a.
Have HP sample for CNMT entry.
- b. Investigate CNMT for leakage.
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AP-RCS.1 REACTOR COOLANT LEAK REV*
6 PAGE 9 of 9 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 14 Verify Tech Spec Leakage Limits SATISFIED PER TECH SPEC SECTION 3.1.5 Perform actions as directed by Tech Specs.
15 Establish MONITORING OF RCS LEAK RATE AND EVALUATE PLANT CONDITIONS FOR LONG TERM ACTIONS 16 Check Conditions For Offsite Reporting:
o Refer to - SC-100, GINNA STATION EVENT EVALUATION AND CLASSIFICATION o
Refer to 9.3, NRC IMMEDIATE NOTIFICATION
-END-
EOP AP-TURB.2 TITLE:
AUTOMATIC TURBINE RUNBACK REV:
9 PAGE 1 of 12 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE
,PLANT SUPERXN ENDENT EFFEC IV DATE CATEGORY 1.0 REVIEWED BY:
I ti
AP-TURB-2 AUTOMATIC TURBINE RUNBACK REV:
9 PAGE 2 of 12 A.
PURPOSE This procedure provides the steps necessary to control the plant during an automatic turbine runback or unexplained load rejection.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
SYMPTOMS The symptoms of AUTOMATIC TURBINE RUNBACK are; a.
Annunciator E-28, POWER RANGE ROD DROP STOP -5%/5 sec, lit or b.
Annunciator C-14, ROD BOTTOM ROD STOP, lit or c.
MRPI Indicates control rod(s) on bottom d.
Annunciator F-30, OPaT TURBINE RUNBACK, lit or e.
Annunciator F-31, OTaT TURBINE RUNBACK, lit or f.
Unexplained turbine load rejection.
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AP-TURB.2 TlTLE:
r AUTOMATIC TURBINE RUNBACK REV:
9 PAGE 3 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OCCURS, E-O)
REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
NOTE:
o Step 1 is an IMMEDIATE ACTION step.
o Any runback signal will block auto out motion of rod control system.
O 1
Check Rod Control:
o Rod control bank selector switch in AUTO Place rod control bank selector switch in manual and drive rods in as necessary to control Tavg.
o Control rods stepping in as required
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AP-TURB - 2 AUTOMATIC TURBINE RUNBACK REV:
9 PAGE 4 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 2
Check Control Rod Status:
o Annunciator E-28, POWER RANGE ROD DROP ROD STOP 5%/5 SECONDS-EXTINGUISHED Go to Step 12.
o Annunciator C-14, ROD BOTTOM ROD STOP - EXTINGUISHED 3 Verify Annunciator F-15, RCS TAVG DEVI EXTINGUISHED Place steam dump mode selector switch to MANUAL.
4 Verify the following a.
Any aT runback signal -
PRESENT b.
aT runback occurring as required a.
Go to Step 5.
- b. Perform the following:
- 1) Place EH in MANUAL.
- 2) Reduce turbine load as necessary.
5 Verify Tavg TRENDING TO TREF Manually operate control rods as necessary to control Tavg.
IF steam dump required and NOT operating, THEN perform the following:
- a. Place steam dump mode selector to MANUAL.
- b. Place steam dump pressure controller, HCV-484, to MANUAL.
c.
Open steam dump valves as necessary to control Tavg.
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AP-TURB.2 TITLE:
AUTOMATIC TURBINE RUNBACK REV 9
PAGE 5 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6 Verify All AI Indications Approximately Equal Check NIS PR upper and lower detector currents to determine if any detector has failed.
IF NIS PR upper or lower detector has failed, THEN perform the following:
- a. Allow runback to reduce reactor power to 75X.
- b. Place EH in manual to terminate runback.
- c. Defeat failed PR channel.
(Refer to ER-NIS.3, PR
.MALFUNCTION.)
7 Check Delta T Channel Indications:
o All 4 delta T channels indicate approximately the same value o All 4 delta T channel setpoint indications approximately equal o All 4 delta T channels responding to the turbine runbacks Perform the following:
a.
Check for instrument failure:
o Any delta T channel indicating significantly different than the other 3.
o Any PRZR pressure or Tavg channel malfunction.
- b. IF 1 channel is failed, THEN perform the following:
- 1) Allow runback to reduce reactor power to 75X or until condition clears.
2)
VHEN power less than 75X, THEN place EH in manual to terminate runback if necessary.
3)
Go to Step 9.
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AP-TURB.2 AUTOMATIC TURBINE RUNBACK REV 9'AGE 6 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 8
Turbine Runback Signal CLEARED WHEN turbine runback signal clears, THEN go to Step 9.
EOP:
AP-TURB.2 AUTOMATIC TURBINE RUNBACK REV:
9 PAGE 7 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF STEAM DUMP CONTINUES FOR A SIGNIFICANT LENGTH OF TIME, CONDENSATE.
TEMPERATURE AND CONDENSER BACK PRESSURE SHOULD BE MONITORED.
NOTE:
Tavg will indicate high or low for some instrument failures affecting steam dump control, rod control, and PRZR level control.
9 Establish Stable Plant Conditions:
a.
Tavg - TRENDING TO TREF b.
PRZR pressure
- TRENDING TO 2235 PSIG c.
PRZR level - TRENDING TO PROGRAM d.
Rod insertion limit alarms-EXTINGUISHED e.
Steam dump valves -
CLOSED
- a. Insert control rods or, if necessary decrease turbine load'o match Tavg to Tref.
- b. Verify proper operation of PRZR heaters and spray or take manual control of PRZR press controller 431K.
IF PRZR pressure can NOT be controlled, THEN refer to AP-PRZR.1, ABNORMAL PRESSURIZER PRESSURE.
- c. Verify proper operation of charging pump speed controllers OR take manual control of speed controllers to control PRZR level.
- d. Failure of a aT channel will affect rod insertion limit indication.
Determine actual RIL from Tech Spec figure 3.10-1.
IF necessary, THEN refer to AP-CVCS.2, IMMEDIATE BORATION and continue with Step Se.
e.
Ensure proper operation of steam dump control system.
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AP-TURB.2 TITLE:
AUTOMATIC TURBINE RUNBACK REV 9
PAGE 8 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 10 Check REGEN Hx Letdown Indications:
o Annunciator A-4, REGEN HX LETDOWN OUT HI TEMP 395'F-EXTINGUISHED o
REGEN Hx letdown outlet temperature
- STABLE OR DECREASING Adjust charging flow and HCV-142 as necessary to control REGEN Hx letdown outlet temperature.
IF REGEN Hx letdown outlet tempeiature can NOT be controlled, THEN perform the following:
a.
Close all letdown orifice valves (AOV-200A, AOV-200B and AOV-202).
- b. Close loop B to REGEN Hx isolation valve (AOV-427).
ll Evaluate Cause Of Turbine Runback:
- a. Verify power to Instrument busses o All red Instrument bus annunciators
- EXTINGUISHED a.
Go to Step 15.
o Busses 12A and B - ENERGIZED
- b. Failed instrument channel-IDENTIFIED
- b. Perform the following:
- 1) Attempt to determine and correct conditions requiring turbine runback.
c.
Go to ER-INST.l, REACTOR PROTECTION BISTABLE DEFEAT AFTER INSTRUMENTATION LOOP FAILURE 2)
Go to Step 20.
12 Verify Turbine Load Reduction AT LEAST 20~o Place EH in manual and reduce turbine load by 20X.
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AP-TURB.2 AUTOMATIC TURBINE RUNBACK REV 9
PAGE 9 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 13 Check Main'Generator Load:
o Gross load - GREATER THAN 15 MV o
Load -
STABLE Trip turbine and go to AP-TURB.1, TURBINE TRIP WITHOUT RX TRIP REQUIRED, Step l.
14 Verify Proper Steam Dump Operation:
o Annunciator G-15, STEAM DUMP ARMED - LIT o
Steam dump operating to control Tavg within 6'F of Tref Perform the following:
a.
Place steam dump mode selector to MANUAL.
- b. Place steam dump controller, HCV-484, to MANUAL.
c.
Open steam dump valves as required to stabilize Tavg.
15 Verify Bus 12A And Bus 12B Energized:
o Bus 12A normal or alternate feed breaker CLOSED o
Bus 12B normal or alternate feed breaker
-" CLOSED Go to AP-ELEC.1, LOSS OF 12A AND/OR 12B TRANSFORMER.
o Bus 12A and 12B voltage-GREATER THAN 4KV
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AP-TURB.2 TITLE:
AUTOMATIC TURBINE RUNBACK REV 9
PAGE 10 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 16 Establish Stable Plant Conditions:
a.
Tavg - TRENDING TO TREF b.
PRZR pressure
- TRENDING TO 2235 PSIG c.
PRZR level - TRENDING TO PROGRAM
- a. Insert control rods or, if necessary, decrease turbine load to match Tavg to Tref.
- b. Verify proper operation of PRZR heaters and spray or take manual control of PRZR press controller 431K.
IF PRZR pressure can NOT be controlled, THEN refer to AP-PRZR.l, ABNORMAL PRESSURIZER PRESSURE.
- c. Verify proper operation of recharging pump speed controllers or take manual control of speed controllers to control PRZR level.
17 Check REGEN Hx Letdown Indications:
o Annunciator A-4, REGEN HX LETDOWN OUT HI TEMP 395'F-EXTINGUISHED o
REGEN Hx letdown outlet temperature
- STABLE OR DECREASING
- Adjust charging flow and HCV-142 as necessary to control REGEN Hx letdown outlet temperature.
IF REGEN Hx letdown outlet temperature can NOT be controlled, THEN perform the following:
a.
Close all letdown orifice valves (AOV-200A, AOV-200B and AOV-202).
- b. Close loop B to REGEN Hx isolation valve (AOV-427).
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AP-TURB. 2 TITLE:
AUTOMATIC TURBINE RUNBACK REV 9
PAGE ll of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Vith a PR lover detector failed lov, the plant could experience both a dropped rod turbine runback with continuing aT runbacks.
18 Check NIS PR Indication:
o All PR total channel indicators ON SCALE o All al indicators-APPROXIMATELY EQUAL IF a NIS PR failure is indicated, THEN perform the folloving:
- a. Verify 20X dropped rod runback has occurred.
IF tT runbacks still occurring, THEN allow runbacks to reduce pover to less than 75X and place EH in manual to terminate runbacks.
- b. Refer to ER-NIS.3, PR MALFUNCTION.
c.
Go to Step 21.
19 Verify Dropped Rod Indication:
a.
Check dropped rod indication o
MRPZ indicates rod on bottom
-OR-
- a. IF the cause of the runback has NOT been determined, THEN return to Step 2.
o Annunciator C-14, ROD BOTTOM ROD STOP - LIT b.
Go.to AP-RCC.2, RCC/RPI MALFUNCTION
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AP-TURB. 2 TITLE:
AUTOMATIC TURBINE RUNBACK REV' PAGE 12 of 12 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 20 Establish Normal Plant Conditions:
- a. Verify EH control in AUTO IMP IN
- b. Verify steam dump controller, HC-484, in AUTO at 1005 psig
- c. Verify annunciator G-15, STEAM DUMP ARMED - EXTINGUISHED
- a. IF conditions requiring runback have cleared, THEN place EH in AUTO IMP IN.
- c. IF Tavg within 6'F of Tref, THEN perform the following:
- 1) Ensure steam dump valves closed.
- d. Verify charging pump speed control in AUTO
- e. Verify Rod Control Selector Switch in AUTO
- 2) Reset steam dump.
- d. Place charging pump speed control in AUTO if desired.
- e. Place Rod Control Selector Switch in AUTO if desired.
NOTE:
Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
21 Notify Higher Supervision
-END-
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ATT EOP/AP ATTACHMENTS REV:
0 PAGE 1 of 1 ATTACHMENT AUX BLDG SW Supt.
Date~4~
1)
Dispatch AO to locally open AUX BLDG SW isolation valve breakers:
o MOV-4615, MCC C position 14J o MOV-4616, MCC C position 6F 2)
Manually open AUX BLDG SW isolation valves MOV-4734 and MOV-4735 (control board switches).
3)
Direct AO to locally open MOV-4615 and MOV-4616 slowly to approximately half open.
(middle level opposite 1G charcoal filter) 4)
Direct AO to locally close AUX BLDG SW isolation valve breakers:
o MOV-4615, MCC C position 14J o MOV-4616, MCC C position 6F 5)
Ensure AUX BLDG SW isolation valves MOV-4615 and MOV-4616 open fully.
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ATT TI1'LE:
EOP/AP ATTACHMENTS REV 1
PAGE 1 of 1 ATTACHMENT SAFW Supt
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Date / o To lace SAFW in service er rm the fo win 1.
Verify the following valves OPEN:
0 MOV 9701Ag SAFW PUMP C DISCH VALVE 0
MOV 9701Bg SAFW PUMP D DISCH VALVE o
MOV-9704A, SAFW ISOL TO S/G A o
MOV-9704B, SAFW ISOL TO S/G B
o MOV-9746, SAFW PUMP D EMERG DISCH VLV 2.
Open SAFW pump suction valves:
o MOV-9629A, SAFW PUMP C SUCTION VALVE o
MOV-9629B, SAFW PUMP D SUCTION VALVE CAUTION IF SW ISOLATION HAS OCCURRED g THEN AUX BLDG SW ISOLATION VALVES TO SAFW SHOULD BE OPENED SLOWLY LOCALLY TO PREVENT WATER HAMMER IN THE SAFW PUMP SUCTION.
3.
Ensure SW isolation valves MOV-4615 for C SAFW pump and MOV-4616 for D SAFW pump are open.
IF closed, THEN reset SI and dispatch AO to locally open valves slowly.
4.
Verify associated MDAFW pump switch in stop position.
Start either o'r both SAFW PUMPS as necessary to supply feedwater to the S/Gs.
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