ML17308A116
| ML17308A116 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/08/1990 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PROC-900208, NUDOCS 9002220730 | |
| Download: ML17308A116 (138) | |
Text
, gCCEMRATED Dl BUTION DEMONS ON SYSTEM "a
REGULATO INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:9002220730 DOC.DATE: 90/02/08 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION Rochester Gas
& Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION
+6L,. gag/Pd g
SUBJECT:
Revised emergency operating procedures, including Rev 9 to AP-CR.l,Rev 6 to AP-'CW.l 6
Rev 8 to AP-CCW.2.
R DISTRIBUTION CODE:
A045D COPIES RECEIVED:LTR ENCL SIZE:
I TlTLE: OR Submittal:
- Plans, Imp ement'g Procedures, C
D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
05000244 S
RECIPIENT ID CODE/NAME PD1-3 PD INTERNAL: AEOD/DOA/IRB NUDOCS-ABSTRACT EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1
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t (zzszrp'zsirsu sr'I ZZZ(ZZ ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, pIEW Llaw Oaf@a ROCHESTER, N.Y. 14649-0001 TELEPHONE AREA CODE TIE 546.2700 February 8,
1990 U. S. Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Allen Johnson Project Directorate I-3 Washington, D.
C.
20555
Subject:
Emergency Operating Procedures R.
E. Ginna Nuclear Power Plant Docket No. 50-244 Gentlemen:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Enclosures Robert C. Mecred Division Manager Nuclear Production xc:
USNRC, Region I,(2 copies)
Resident Inspector, Ginna Station 9002220730 900208 PDR ADOCK 05000244 PNU
0
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P-CR.1 TITLE:
CONTROL ROOM INACCESSIBILITY REV:
8 PAGE 1 of 6 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER cP~
TECHNICAL REVIEW PORC REVI W DATE P
T SU N
N NT FECTIVE D TE Y>
QA NON-QA REVIEWED BY:
CATEGORY 1.0 GINNASTATION START:
DATE TIME COMPLETED:
ATE
H
AP-CR.1 CONTROL ROOM INACCESSIBILITY REV:
8 PAGE 2 of 6 A.
PURPOSE This procedure provides the step necessary to place and maintain the plant in a Hot Shutdown Condition in the event that. a control room evacuation is necessary.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
SYMPTOMS The symptoms of CONTROL ROOM INACCESSIBILITY are; a.
Fire in the Control Room, or b.
Smoke in the Control Room, or c.
Noxious Fumes in the Control Room, or d.
Intrusion
4
EOP:
AP-CR. 1 TITLE:
CONTROL ROOM INACCESSIBILITY REV 8
PAGE 3 of 6 STEP ACTION/EXPECTED RESPONSE
. RESPONSE NOT OBTAINED NOTE:
Steps 1 and 2 are immediate action steps.
1 Verify Reactor Trip:
o Reactor trip breakers OPEN o
MRPI indicates
- ALL CONTROL AND SHUTDOWN RODS ON BOTTOM Manual trip the reactor from the control board.
IR the RX can NOT be tripped from the Control Room, THEN locally open the reactor trip breakers.
O 2
Verify Turbine Trip:
o Stop valves - CLOSED Manually trip turbine from MCB.
IR turbine can NOT be tripped at the MCB, THEN locally trip turbine at trip lever on HP turbine.
FOP:
AP-CR.1 CONTROL ROOM INACCESSIBILITY REV 8
PAGE 4 of 6 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 3 Verify That Fire HAS NOT significantly damaged the MCB Control Circuits o
MCB -
NO FIRE OR FIRE UNDER CONTROL o
Safety related controls and indications NO SIGNIFICANT LOSS OF CONTROLS/INDICATION Perform the following actions:
- a. Close both MSIVs.
- b. Trip both reactor coolant pumps.
- c. Close both PRZR relief vlv PCV-430 (431C).
- d. Proceed to the Appendix R locker, immediately outside the Control Room.
- e. Control Room Foreman and communicator proceed to TSC and refer to SC-100 for report requirements.
- f. Implement procedure SC-3.30.1 ALTERNATIVE SHUTDOWN FOR CONTROL COMPLEX FIRE.
DO NOT continue in this procedure.
4 Establish Local Operating Stations AS OUTLINED IN ATTACHMENT A 5 Establish AFW To The Steam Generators:
a.. Start,.-': BOTH MOTOR DRIVEN AFW PUMPS.>>.'-
- b. Verify - BOTH PUMPS THROTTLE TO (230 GPM
- a. Start the TDAFW pump.
Manually open TDAFW pump steam admission valves at the steam header MOV-3504A, MOV-3505A.
- b. Manually throttle AFW flow.
F,OP:
AP-CR.1 CONTROL ROOM INACCESSIBILITY REV:
8 PAGE 5 of 6 STBP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6 Establish Charging Flow:
- a. Charging pumps - AT LEAST ONE RUNNING
- b. Control charging and letdown-TO MAINTAINPRESSURIZER LEVEL
- a. Start a charging pump.
7 Establish Boration Of The RCS To The Xenon Free CSD Condition:
- a. Refer to 0-3.1 -
FOR DETERMINATION OF AMOUNT OF BORIC ACID TO BE ADDED
- b. Start - A BORIC ACID PUMP
- c. Manually open - MOV-350
- d. Stop boration -
WHEN REQUIRED BORIC ACID HAS BEEN ADDED 8 Establish Service Water:
o Verify - AT LEAST ONE SERVICE
'ATER PUMP RUNNING IN EACH LOOP Start pumps as necessary.
9 Establish Containment Cooling o
Verify.- AT LEAST TWO RECIRC FAN COOLBRS ARE RUNNING Start fans as necessary.
C
,EOP:
AP-CR.1
~.
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CONTROL ROOM INACCESSIBILITY REV:
8 PAGE 6 of 6 STBP ACTION/EXPECTED RESPONSE RESPONSB NOT OBTAINED 10 Throttle AFW as necessary TO MAINTAINS/G LEVELS BETWEEN 77%'ND 854 11 Check IF THE CONTROL ROOM IS AGAIN HABITABLE Return to Step 7.
12 Establish Normal Control Room Operations:
- a. Restore
- NORMAL OPERATION OF EQUIPMENT o
Refer to 2.2, PLANT FROM HSD TO COLD SHUTDOWN
-OR-o Refer to 0-2.4, NATURAL CIRCULATION COOLDOMN FROM HOT SHUTDOVN
-END-
J
FOP:
AP-CR 1 TLTLE:
CONTROL ROOM INACCESSIBILITY REV:
8 PAGE 1 of 1 ATTACHMENT A Duties of Personnel During a Control Room Evacuation SHIFT SUPERVISOR Will direct overall plant operations and recovery actions.
No specific duty station is assigned but the Shift Supervisor should maintain communication with the various groups working to recover from the evacuation.
CONTROL ROOM FOREMAN Will assist the Head Control Operator in transferring equipment to local control, after completion of the transfer the Control Room Foreman will direct the oper-ator's actions to recover the plant.
HEAD CONTROL OPERATOR Will go to Auxiliary Feedwater pump area taking operating procedures "0" book, official records; curve book with him and transfer equipment to local control.
CONTROL OPERATOR
Will go to the local operating station in the Charging Pump Room.
PRIMARY AUX OPERATOR Will go to the local operating stations in the Boric Acid Tank Room.
SHIFT TECHNICAL ADVISOR Will assist the Head Control Operator while remaining cognizant of plant conditions.
OTHER PERSONNEL Will assume fire fighting or other duties as directed by the Shift Supervisor or Control Room Foreman.
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EOP:
AP-CCW.1 TITLE:
LEAKAGE INTO THE COMPONENT COOLING LOOP REV:
5 PAGE 1 of 8 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE 0 //
P T SUPERINTE DENT lo-Ao -I EFFECTIVE DATE QA NON-QA REVIEWED BY:
CATEGORY 1.0 GINNASTATION START:
DATE TIME COI'v)PLETED:
DATE
I i)
EV:
AP-CCW.l TITLE:
LEAKAGE INTO THE COMPONENT COOLING LOOP REV:
5 PAGE 2 of 8 A.
PURPOSE - This procedure provides the actions required to identify and isolate leakage into the CCW system and to control the plant during the course of the event.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
SYMPTOMS The symptoms of LEAKAGE INTO THE COMPONENT COOLING LOOP are; a.
A-5, COMP COOLING SURGE TANK HI LEVEL 58.84, or b.
CCW radiation monitor (R-17) alarm, or c ~
A 7
( 15) g RCP lA ( 1B)
CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F, or d.
Erratic RCP labyrinth seal D/P.
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E8:
AP-CCW.1 TITLE:
LEAKAGE INTO THE COMPONENT COOLING LOOP REV:
5 PAGE 3 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IFt AT ANY TIME DURING THIS PROCEDURE g A REACTOR TRIP OR SI OCCURS t E 0, REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.
NOTE:
Letdovn diversion to CVCS HUT may cause R-17 increase or alarm.
1 Check CCW Radiation Monitor (R-17)
INCREASING Go to Step 11.
2 Check CCW Radiation Monitor (R-17)
IN ALARM Go to Step 4.
3 Verify CCW Surge Tk Vent RCV-017 CLOSED Close CCW surge tk vent RCV-017.
4 Check RCS Leakage GREATER THAN NORMAL Go to Step 11.
NOTE:
RCPs may be safely operated without CCW to the thermal barrier if seal injection flov is maintained.
5 Check RCP Thermal Barrier Indications:
o Labyrinth seal D/Ps - NORMAL o
RCP gl seal leak off flovs-NORMAL' AR-A-7/15 RCP 1A/1B CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F ALARM - EXTINGUISHED IF either pump has indication of a thermal barrier leak, THEN:
- a. Verify seal in]ection flov
- b. Close CCW from lA (1B) thermal barrier MOV-754A (754B).
c.
Go to Step 19.
EOP:
AP-CCW.1 TtTLE:
LEAKAGE INTO THE COMPONENT COOLING LOOP REV:
5 PAGE 4 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION CLOSELY MONITOR PRZR LEVEL WHILE LETDOWN IS ISOLATED.
6 Check NRHX For Leakage:
- a. Normal letdown - INSERVICE
- b. Letdown indications Letdown line flov - NORMAL o
Lov press LTDN pressure-NORMAL o
NRHX CCV outlet (local TI-600) - LESS THAN 190'R
- a. IP excess letdown inservice, THEN go to Step 10.
- b. Isolate letdown as follovs:
- 1) Close letdown loop B cold leg to RHx AOV-427.
- 2) Close LTDN orifices AOVs 200A, 200B, and 202.
- 3) Place low press LTDN press PI-135 PCV-135 in manual AND close.
c.
Go to Step 11
- 4) Reduce charging as necessary.
5)
Go to Step 7.
7 Check If CCW Inleakage Has Stopped:
P.
o CCW surge tank level - STABLE Restore normal letdown and g'o to Step 11.
P
~
4
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EoI':
AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV:
5 PAGE 5 of 8 STBP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINBD 8 Establish Excess Letdown:
- a. Place excess LTDN Hx divert to seal Hx or drn tk AOV-312 in'the
- NORMAL POSITION
- b. Verify seal or excess LTDN return isol vlv MOV-313 - OPEN
- c. Verify CCV from ex LTDN Hx isol vlv AOV-745 - 0&EN
- d. Place AOV-310 inlet to excess letdown Hx to - OPEN POSITION
- e. Throttle flow using - HCV-123, OUTLET FROM EXCESS LETDOWN HX 9
Check PRZR Level:
a.
PRZR level - TRENDING TO REFERENCE LEVBL b.
Go to Step 18 a.
Reduce charging as necessary to control PRZR level.
10 Establish Excess Letdown Isolation:
- a. Excess LTDN loop A cold to Hx AOV-310 - CLOSED
- b. Excess LTDN (TI-122) HCV-123-CLOSED
- c. Check CCW surge tank level-STABLE d.
Go to Step 18
- c. IF CCW surge tank level continues to increase, THBN restore excess letdown to service and go to Step 11.
ll
EOP:
AP-CCW.1 TITLE:
'EAKAGE INTO THE COMPONENT COOLING LOOP S
REV:
5 PAGE 6 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED ll Check RMW to CCW Surge Tank:
o MOV-823 -
CLOSED o
. RMW pump(s)
- NOT RUNNING IF RMW to CCW surge tank MOV-823 open OR RMW pump running, THEN:
- a. Close RMW to CCW surge tank MOV-823.
- b. Shut off running RMW pumps.
- c. IP CCW inleakage stops, THEN go to Step 19.
- d. IF CCW inleakage continues, go to Step 12.
12 Check For Sample Hx Leaks In Nuclear Sample Room:
o Sample Hx (TI-602) common CCW return temperature from sample Hxs - NORMAL o
Sample Hx (PI-603) common CCW return flow from sample Hxs-NORMAL Determine which sample Hx CCW outlet temperature is high, THEN:
- a. Isolate the affected HX.
- b. Check if inleakage has stopped to CCW surge tank. If inleakage has stopped, go to Step 18.
IF inleakage continues, go to Step 13.
CAUTION IP AN RHR PUMP OR HX IS REMOVED FROM SERVICE, REFER TO TECH SPEC SECTIONS 3.1.1.1 AND 3.3.1 POR LCO.
ONE RHR TRAIN SHOULD BE OPERABLE AT ALL TIMES.
13 Check RHR System IN SERVICE Go to Step 16.
Observe caution prior to Step 16.
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EOP:
AP-CCW.1 T!TLE:
LEAKAGE INTO THE COMPONENT COOLING LOOP" REV:
5 PAGE 7 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 14 Place 1 RHR Loop Out Of Service And Isolate The Idle Pump And Hx:
a.
RHR loop - REMOVED FROM SERVICE
a.
CCV surge tank level - STABLE
- a. IF CCV inleakage continues, THEN:
b.
Go to Step 18 o
Restore isolated RHR loop to service and repeat Steps 14:"
and 15 for the other RHR loop.
o IF leakage is not from either RHR loop, THEN restore both loops to operable and go to Step 16.
CAUTION IF AN SI OR CS PUMP IS REMOVED FROM SERVICE, REFER TO TECH SPEC SECTION 3.3.1 OR 3.3.2 FOR THE LCO.
16 Check Any SI Or Containment Spray Pumps RUNNING IF no SI or CS pumps running, THEN go to Step 19.
f&
EOP:
AP-CCW.l TITLE:
LEAKAGE INTO THE COMPONENT COOLING LOOP REV:
5 PAGE 8 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 17 Stop Then Isolate One SI or CS Pump At A Time And Check CCW Surge Tank Level STABLE IF in leakage cannot be located, THEN, go to Step 19.
18 Place The Affected Component IN AN ISOLATED AND HELD CONDITION 19 Verify THAT PLANT OPERATION CAN CONTINUE IF plant shutdown is required, THEN refer to 0-2.1, NORHAL SHUTDOWN TO HOT SHUTDOWN.
20 Complete NOTIFICATION TO HIGHER SUPERVISION
-END-
1
EOP:
AP-'CCW. 1 TITLE:
LEAKAGE INTO THE COMPONENT COOLING LOOP REV:
5 PAGE 1 of 1 AUTOMATIC ACTIONS
~
CCW surge tank vent RCV-017 closes on CCW radiation monitor (R-17) alarm.
EOP:
AP-CCW.2 LOSS OF CCW DURING POWER OPERATION REV:
7 PAGE 1 of 8 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE P
T SUPERINT ND T
9-e-EFFECTIVE DATE CA~ NON-QA CATEGORY 1.0 REVIEWED BY:
8INNASTATION START'ATE TIME COMPLETED:
DATE
R'
EOP!
AP-CCW.2 I B TlTLE:
<<B.P LOSS OF CCW DURING POWER OPERATION REV:
7 PAGE 2 of 8 A.
PURPOSE -'This procedure provides the steps necessary to respond to a loss of CCW while the plant is at power.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
SYMPTOMS The symptoms of LOSS OF CCW DURING POWER OPERATION are; a.
A-13 COMP COOLING SURGE TANK LO LEVEL 41.24, alarm, or b.
A-22 CCW PUMP DISCHARGE LO PRESS 60 PSI, alarm, or c.
A-31, CCW SYSTEM LO FLOW 1800 GPM, or d.
A-17, MOTOR OFF,
A-9, RHR PUMP COOLING WATER OUTLET LO FLOW 15 GPM alarm, or f.
A-6, CONT SPRAY PUMP COOLING WATER OUT LOW FLOW 15 GPM GPM alarm, or g.
A-14, SAFETY INJ PUMPS COOLING WATER OUT LO FLOW 25 GPM alarm, or h
A 7 (A 15) 1 RCP 1A
( 1B)
CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F, alarm.
i.
A-24 (A-32),
RCP 1A (1B) OIL LEVEL + 1.25, alarm.
'C
. tl,
EOP:
AP-CCW.2 TITLE:
LOSS OF CCW DURING POWER OPERATION REV:
7 PAGE 3 of 8 STBP ACTION/EXPECTED RBSPONSE RBSPONSE NOT OBTAINED CAUTION IP CCV FLOV TO A RCP IS INTERRUPTBD FOR GREATER THAN 2 MINUTBS OR IP EITHER RCP MOTOR BEARING TEMPERATUE EXCEEDS 200'F, THEN CCV SHOULD BE CONSIDERED LOST TO THAT RCP, REFER TO STEP 3.
NOTE:
Step 1 is an IMMEDIATE ACTION step.
O 1
Check CCW Pump Status:
o A-17, Motor Off RCP CCP-EXTINGUISHED o
Both CCV pump breaker white disagreement lights-EXTINGUISHED Perform the following:
- a. Verify auto start of standby CCV pump or start manually.
- b. IP A-22, CCV pump discharge lo~
press 60 psi energized,
it 1
EOP:
AP-CCW.2 LOSS OF CCW DURING POWER OPERATION REV:
7 PAGE 4 of 8 STEP ACTION/EXPECTED RESPONSB RBSPONSE NOT OBTAINED NOTE:
CCV surge tank level should be verified locally in the Aux Bldg, if possible.
2 Verify CCW Surge Tank Level Normal:
a.
CCV surge tank level-APPROXIMATELY 50X AND STABLE a.
Open RMW to CCV surge tank (MOV-823) and start a RMV pump and perform the folloving:
IF surge tank level is stable or increasing, THEN go to Step 3.
IF surge tank level can NOT be>j.
maintained greater than
- 10K, THEN:
- 1) Trip the Rx.
- 2) Trip the RCPs.
- 3) Place both CCW pumps in pull stop.
4)
Go to E-O, REACTOR TRIP or SAFETY INJECTION.
I
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EOP:
AP-CCW. 2 TlTLE:
LOSS OF CCW DURING POWER OPERATION REV:
7 PAGE 5 of 8 STEP
'CTION/EXPECTED RBSPONSE RBSPONSE NOT OBTAINED CAUTION o
IF AN RCP(S) IS TRIPPED DUE TO A LOSS OF CCV, SEAL INJECTION SHOULD BE MAINTAINBDTO THE IDLE RCP(S)
UNTIL RCS TBMPERATURB IS LBSS THAN 200'F, OR UNTIL CCV IS RESTORED.
o REACTOR POVER MUST BE LBSS THAN SX FOR SINGLE LOOP OPERATION.
o A-7 (A-15),
RCP lA (1B) CCV return Hi temp or low flow 165 gpm 125'F alarm - EXTINGUISHBD o
RCP motor bearings temperature (PPCS address GD-RCPS OR RCP temperature monitor RK-30A recorder)
- g 200'F IF CCV lost to RCP(s),
THEN:
- a. Trip the Rx.
- b. Trip affected RCP(s).
c.
Go to E-O, REACTOR TRIP or SAFETY INJECTION.
4 Check CCW Valve Alignment NORMAL Align CCV valves as necessary.
Jt
EOP:
AP-CCW.2 LOSS OF CCW DURING POWER OPERATION REV:
7 PAGE 6 of 8 STBP ACTION/EXPECTED RBSPONSE RBSPONSE NOT OBTAINED NOTE:
o An evaluation must be made to determine if operation may continue while investigating a
CCW leak in containment.
o Operation may continue with the reactor support coolers isolated.
If this occurs, notify higher supervision.
5 Check For CCW Leakage In CNMT:
a.
RCP oil levels - NOT INCREASING
- 2) Prepare to make CNMT entry,to check for CCV leak.
- b. IF any RCP oil level increasing uncontrollably, THEN:
- 1) Close CCV to and from affected RCP(s),
(MOVs 749A and 759A for "A" RCP; MOVs 749B and 759B for "B" RCP).
- 2) Trip Rx.
- 3) Trip affected RCP(s).
- 4) Go to E-O, REACTOR TRIP or SAFETY INJECTION.
EOP:
AP-CCW.2 LOSS OF CCW DURING POWER OPERATION REV:
7 PAGE 7 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 6
Check For CCW Leakage In AUX BLDG:
o Aux Bldg sump pump - INCREASED START FREQUENCY
-OR-o Vaste holdup tank level-UNEXPLAINED INCREASE
-OR-IF no leakage indicated in Aux Bldg, THEN:
b.
Go to step 10.
o Aux Bldg - VISUAL LEAKAGE IDENTIFIED 7
Establish THE SOURCE OF THE CCW LEAKAGE AND ISOLATE 8 Verify CCW Surge Tank Level Normal:
o CCV surge tank level-APPROXIMATELY 50%
IF CCV surge tank level NOT approximately 50%,
THEN open RMV to CCV surge tank, MOV-823 and start a
RMV pump to fillCCV surge tank to approximately 50%.
9 Check CCW System For Chromates:
o CCV system chromates concentration
- NORMAL 10 Verify'CONDITIONS PERMIT CONTINUED POWER OPERATION, (Refer to Technical Specification Section 3.3.3)
IF CCV system chromates concentration lov, THEN add chromates to CCV system as directed by HP.
IF shutdovn required, THEN refer to 0-2.1, NORMAL SHUTDOVN TO HOT SHUTDOVN
EOP:
AP-CCW.2 LOSS OF CCW DURING POWER OPERATION REV:
7 PAGE 8 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Refer to 0-9.3, NRC IMMEDIATE NOTIRICATION, for reporting requirements.
11 Complete NOTIFICATION TO HIGHER SUPERVISION 12 Establish Further Guidance:
a.
Problem or leakage
- CORRECTED
- b. Return to - APPROPRIATE NORMAL OPERATING PROCEDURE
- a. IR problem NOT corrected or leakage NOT found or isolated, THEN return to Step 4.
-END-
~
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AP-CCW.2 LOSS OF CCW DURING POWER OPERATION REV:
7 PAGE 1 of 1 F,
t AUTOMATIC ACTIONS o
The standby component cooling pump starts automatically from a low pressure condition in the pump discharge header.
o Control valve TCV-130 in the cooling water return line from the non-regenerative heat exchanger may open wide because of a high temperature condition in the letdown line.
o Valve TCV-145 in the letdown line may operate to divert flow from the demineralizers directly to the volume control tank.
5
I 4J
EOP:
AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN REV:
6 PAGE 1 of 6 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE T SUPERIN EN ENT J't-EFFECTIVE DATE
>> 4++
gy J 1y>>'f f
6INNASTATION START:
QA NON-QA REVIEWED BY:
CATEGORY 1.0 DATE TIME COMPLETED:
DATE
tl
EOP:
AP-CCW.3 TITLE:
LOSS OF CCW - PLANT SHUTDOWN REV:
6 PAGE 2 of 6 A.
PURPOSE - This procedure provides the steps necessary to respond to a loss of CCW while the plant is shut down.
B-ENTRY CONDITIONS/SYMPTOMS 1.
SYMPTOMS The symptoms of Loss of CCW Plant Shutdown are:
a.
A-13, COMP COOLING SURGE TANK LO LEVEL 41.24 alarm, or b ~
A 22 g CCW PUMP DISCHARGE LO PRESS 60 PS I alarm, or c.
A-31, CCW SYSTEM LO FLOW 1800 GPM alarm or d.
A-17, MOTOR OFF RCP CCP alarm, or e.
A-9, RHR PUMP COOLING WATER OUTLET LO FLOW 15 GPM alarm, or f.
A-6, CONT SPRAY PUMP COOLING WATER OUT LO FLOW 15 GPM alarm, or g.
A-14, SAFETY INJ PUMPS COOLING WATER OUT LO FLOW 25 GPM alarm, or A 7 J (A 15) g RCP lA ( 1B)
CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F alarm.
flow alarm.
EOP!
AP-CCW.3 4F i T!TLE!
LOSS OF CCW - PLANT SHUTDOWN REV 6
PAGE 3 of 6 STEP ACTION/EXPECTED RBSPONSE RBSPONSE NOT OBTAINED 1
Check CCW Pump Status:
o Neither pump breaker white disagreement light - IS LIT o
Alarm A-17, Motor Off, RCP CCP-EXTINGUISHBD IF 2 pumps were previously running and one has tripped, THEN reset and attempt to restart the tripped pump, if required for cooling.
IF one pump was previously running and it tripped, THEN ensure auto start of the standby pump or start pump manually.
2 Check CCW Pump Discharge Lo Pressure 60 PSI ALARM A-22, EXTINGUISHED IF CCV pump discharge pressure is low, THEN:
a.
Check closed or close CCV to RHR Hx A(B) MOV-738A(B) unless onf RHR cooling.
- b. Dispatch an aux operator to the aux bldg to check discharge pressure locally and to look for leaks.
3 Check CCW To Operating RCPs:
- a. A-7 (A-15),
RCP 1A (1B)
CCV RETURN HI TEMP OR LOV FLOV 165 GPM 125'F - EXTINGUISHED
- b. Verify -
NO RCP MOTOR BEARING TEMPERATURE ALARMS IF CCV is lost to operating RCPs for GRBATER THAN 2 minutes OR IF an RCP motor bearing temperature exceeds 200'F, THEN trip the affected RCP and see Attachment A, if natural circulation is required.
EOP:
AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN REV 6
PAGE 4 of 6 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 4
Check For CCW Leak:
- a. Verify CCW Surge Tank Level Normal - A-13, COMP COOLING SURGE TANK LO LEVEL 41.2X ALARM EXTINGUISHED AND LEVEL STABLE b.
Go to step 8
- a. IF CCW surge tank level is decreasing, THEN:
- 1) Open RMW to CCV surge tank MOV-823 and start RMV pump 1A(1B) as necessary to fill the tank.
- 2) IF CCV surge tank level can NOT be restored, THEN:
a) Stop any running RCP.
b) Pull stop both CCV pumps';
c) Verify Natural Circulation as per Attachment A if required.
3)
Go to Step 5.
l
~ Q
EOP:
AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN REV:
6 PAGE 5 of 6 STEP
'CTION/EXPECTED RESPONSE RBSPONSB NOT OBTAINBD 5
Check for CCW Leakage In CNMT:
a.
RCP Oil Levels - NOT INCREASING
- 1) Direct Health Physics Tech to sample Sump A for Chromates.
- b. IF any RCP oil level increasing uncontrollably, THEN:
- 1) Stop affected RCP.
(MOV-749A and MOV-759A for A RCP; MOV-749B and MOV-759B for B RCP).
- 3) Verify Natural Circulation as per Attachment A if required.
6 Check for CCW Leakage In AUX BLDG o
Start frequency of AUX BLDG sump pump(s), - INCREASED o
Waste:-'holdup tank level-UNEXPL'AINED INCREASE IF no leakage indicated in AUX BLDG, THEN:
b.
RBTURN to step 3.
wg 4
EOP:
AP-CCW.3 TlTLE:
LOSS OF CCW PLANT SHUTDOWN REV 6
PAGE 6 of 6
\\
STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF AN RCP(S) IS TRIPPED DUE TO A LOSS OF CCV, SEAL INJECTION SHOULD BE MAINTAINEDTO THE IDLB RCP(S)
UNTIL RCS TBMPBRATURE IS LESS THAN 200'F, OR UNTIL CCV IS RESTORED.
NOTE: If CCV is lost to operating CS, RHR, or SI pumps, they may be left running for brief periods while isolating a CCV leak.
7 Establish SOURCE OF CCW LEAKAGE AND ISOLATE 8
Check CCW Valve Alignment-AS REQUIRED FOR PLANT CONDITIONS Realign valves as necessary to restore CCV to individual components.
9 Verify CCW Available TO ANY IF RHR in operation and CCV is lost OPERATING RHR HX to RHR HX, GO TO AP-RHR.1, LOSS OF RHR.
10 ComPlete HIGHER SUPERVISION NOTIFICATION NOTE:
REFER TO 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
ll Establish Further Guidance o
RETURN'-;TO '- NORMAL OPERATING PROCEDURES
-END-
~ (
(
EOP:
AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN REV:
6 PAGE 1 of 1 AUTOMATIC ACTIONS o The standby component cooling pump starts automatically from a low pressure condition in the pump discharge header.
o Control valve TCV-130 in the cooling water return line from the non-regenerative heat exchanger may open wide because of a high temperature condition in the letdown line.
o Valve TCV-145 in the letdown line may operate to divert flow from the demineralizers directly to the volume control tank.
4
EOP:
AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN REV:
6 PAGE 1 of 1 ATTACHMENT A The following conditions support or indicate natural circulation flow:
~
RCS subcooling based on core exit TCs-GREATER THAN REQUIREMENTS OF FIGURE MIN SUBCOOLING.
~
S/G pressures STABLE OR DECREASING.
~
RCS hot leg temperatures STABLE OR DECREASING (ADMINISTRATIVELIMIT FOR COOLDOWN ON NATURAL CIRCULATION IS 25'F/HR.)
~
Core exit TCs STABLE OR DECREASING.
~
RCS cold leg temperatures AT SATURATION TEMPERATURE FOR S/G PRESSURE.
p
~
Both control rod shroud fans should be running for head cooling.
NOTE:
Ensure that PRZR heaters are restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of initiation of natural circulation, REFER TO ER-PRZR.1, RESTORATION OF PRZR HEATERS DURING BLACKOUT.
i'
EOP:
AP-CCW.3 TITI.Et hf 1
LOSS OF CCW PLANT SHUTDOWN REV:
6 PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE:
Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication S
PRESSURE (PSIG)
RC 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 1400 1300 1200 1100 1000 900 800 700 600
'500 400 300 200 100 0
20 RCS PRESSURE INCREMENTS 20 PSIG SUBCOOLED REGION INADEQUATE SUBCOOLING REGION TEMPERATURE INCREMENTS 10'F NORMAL CNMT 0
250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
AP-CVCS.1 CVCS LEAK REV 4
PAGE 1 of 8 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE T SUPERI T
DENT EFFECTIVE DATE QA ~:-'NON-QA CATEGORY 1. 0 REVIEWED BY:
8INNASTATION START:
DATE TIME COMPLETED:
DATE
V
EOP:
AP-CVCS. 1 TITLE:
CVCS LEAK REV 4
PAGE 2 of 8 A.
PURPOSE,-'his. procedure provides the necessary instructions to mitigate the consecpxences of a CVCS leak.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure is entered from; a.
AP-RCS.1, REACTOR COOLANT LEAK, Step 5, when conditions indicate a
CVCS leak.
2.
SYMPTOMS The symptoms of CVCS leak are; a.
B-9/B-10 RCP LABYR SEAL LO DIFF PRESS ALARM, or b.
Charging line pressure low, or c.
F-14, CHARGING PUMP SPEED ALARM, or d
A 4 g REGEN HX LETDOWN OUT HI TEMP 3 9 5 F ALARM'/
e.
Letdown line low pressure and low flow, or f.
Charging Pump Room AREA MONITOR R-4 ALARM or
'E y1
EOP:
AP-CVCS. 1 TITLE:
CVCS LEAK REV:
4 PAGE 3 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF I AT ANY TIME DURING THIS PROCEDURE T A REACTOR TRIP OR SI OCCURS I E 0 7 REACTOR TRIP OR SAFETY INJECTION, SHOULD BE PERFORMED.
1 Check RCS Inventory o
PRZR level - DECREASING IF PRZR level is stable, THEN go to Step 4.
2 Increase PRZR Level:
- a. Start - ADDITIONALCHARGING PUMPS AND INCREASE SPEED AS NECESSARY 3
Check PRZR Level:
o PRZR level - GREATER THAN 13X AND STABLE OR INCREASING IF available charging pumps are running at maximum speed with letdown isolated, AND PRZR level is still decreasing in an uncontrolled
- manner, THEN trip the reactor and go to E-O, REACTOR TRIP or SAFETY INJECTION.
4 Check For Component Cooling System Leak:
o CCW radiation monitor (R-17)-
NORMAL" IF CCW leak indicated, THEN go to AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.
o CCW surge'ank level - NORMAL
4 l4, S
EOP:
AP-CVCS. 1 CVCS LEAK REV 4
PAGE 4 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 5
Check For Letdown Line Leak:
o Letdown line flow-APPROXIMATELY 40 GPM o
Low press LTDN pressure-APPROXIMATELY 250 PSIG IP abnormal letdown flow or pressure exist, THEN close LTDN loop B cold leg to RHx AOV-427, AND IP RCS leakage returns to normal, THEN go to Step 8, OR IR RCS leakage does not return to
- normal, THEN go to Step 6.
6 Check For Charging Line Leak:
- a. Charging pump discharge pressure
- NORMAL IR charging line leak is indicated, THEN go to Step 7.
b.
REGEN Hx LTDN outlet temp TI-127
- NORMAL
- c. Charging line flow - NORMAL (PI-128 25 gpm) d.
Go to Step 12
J~
P,
EOP:
AP-CVCS.1 CVCS LEAK REV:
4 PAGE 5 of S
STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINBD 7
Check Aux Bldg For Leak:
- a. Operation personnel
- DISPATCHED TO AUX BLDG WITH NECESSARY LOCKED AREA KEYS TO INVESTIGATE FOR LEAK b.
CVCS leak - NOT IN AUX BLDG
- b. IF charging line leak is in the Aux Bldg AND isolable, THEN go to Step 8.
IF charging line leak is in the Aux Bldg AND is not isolable, THEN:
- 1) IF leak is manageable (i.e.",
pressurizer level, seal in)ection, and makeup can be maintained),
shut the plant down as quickly as possible (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN, AND go to Step 16.
- 2) IF leak is not manageable, THEN trip the reactor AND go to E-O, REACTOR TRIP or SAFETY INJECTION.
8 Establish Isolation Of Letdown Flow to REGEN Hx:
o LTDN loop B cold leg to RHx AOV-427, - CLOSBD o
LTDN orifices valves AOV-200A, AOV-200B, and AOV-202 -
CLOSED
I t
EOP:
AP-CVCS. 1 TITLE:
CVCS LEAK REV:
4 PAGE 6 of 8 STEP 4
ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 9 Establish Isolation Of Charging Flow to REGEN Hx:
o HCV-142 - CLOSED 10 Establish Control Of Charging Pumps As Necessary To Maintain RCP Labyrinth Seal aP LESS THAN 80 INCHES ll Establish Excess Letdown:
- a. Place excess LTDN Hx divert to seal Hx or drn tk AOV-312 - IN THE NORMAL POSITION
- b. Verify seal or excess LTDN return isol vlv MOV-313 -
OPEN
- c. Verify CCV from EX LTDN Hx isol vlv AOV-745, CCV from excess letdown Hx - OPEN
- d. Place excess LTDN loop A cold to Hx AOV-310 - TO OPEN POSITION
- e. Flov from excess letdovn Hx-CONTROLLED BY EXCESS LTDN HCV-123 f.
Go to:;,-,,:STEP 13 2I P*
p X~,
iN l
EOP:
AP-CVCS F 1 TITLE:
CVCS LEAK REV:
4 PAGE 7 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION RCP OPERATION MAY CONTINUE WITHOUT SEAL INJECTION IP CCW IS BEING SUPPLIED TO THE THERMAL BARRIER.
- HOWEVER, SINCE SEAL SUPPLY WILL NOW BE UNPILTERED, RCP OPERATION WITHOUT SEAL INJECTION SHOULD BE MINIMIZED.
12 Check For RCP Seal Injection Leak:
o RCP labyrinth seal D/P - GREATER THAN 15 INCHES o
RCP fl seal return flows-NORMAL o
RCP standpipe level alarms -
OPP IF RCP labyrinth seal D/P is low or
- zero, THEN suspect leak in seal in)ection line.
Dispatch AO to investigate AND go to Step 14.
IF seal return flow or standpipe ~
alarms indicate RCP seal malfunction, THEN GO TO AP-RCP.1,"'CP SEAL MALFUNCTION.
CAUTION THE NORMAL METHOD OP VCT DIVERSION (AOV-112A) IS NOT AVAILABLEWHILE ON EXCESS LETDOWN.
VCT LEVEL MAY BE DECREASED BY MANUALLYDIVERTING EXCESS LETDOWN TO THE RCDT USING AOV-312.
13 Establish Control Of Charging And Excess Letdown Flows TO RESTORE:-.PRZR LEVEL TO NORMAL 14 Establish 'The Location Of CVCS Leak And Have Personnel COMPLETE MANUAL ISOLATION AS REQUIRED IF the leak can NOT be isolated, THEN go to AP-RCS.1, REACTOR COOLANT LEAK, Step 6.
EOP:
AP-CVCS.l TITLE:
CVCS LEAK REV:
4 PAGE 8 of 8 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 15 Allow Conditions To Stabilize, THEN Perform An RCS Leakage Calculation TO VERIFY THAT LEAK HAS BEEN ISOLATED IF the leak can NOT be isolated, THEN go to AP-RCS.1, REACTOR COOLANT LEAK, Step 6.
NOTE:
Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
16 Complete NOTIFICATION TO HIGHER SUPERVISION
p,
'J l
EOP AP-CVCS ~ 1 TITLE:
CVCS LEAK REV 4
PAGE 1 of 1 AUTOMATIC ACTIONS
~
Auto make-up.
~
Charging pump speed increase.
~
Letdown isolation PRZR level at 134
~
Charging pump suction swapover to RWST at VCT level of 54.
~
AUX BLDG sump pump auto start.
~
Plant ventilation trip.
EOP:
AP-IA.1 LOSS OF INSTRUMENT AIR REV 3
PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE P
T SUPERINT N ENT EFFECTIV DATE QA NON-QA M
CATEGORY 1.0 6INNASTATION START:
REVIEWED BY:
DATE TIME CQMoLETED DATE
q I
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~
f/1>
EOP AP-IA.1 TITLE:
LOSS OF INSTRUMENT AIR REV:
3 PAGE 2 of 10 A.
PURPOSE This procedure provides the instructions necessary in the -event of a loss of instrument air.
B.
ENTRY CONDITIONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure is entered from:
a.
E-O, REACTOR TRIP OR SAFETY INJECTION, Step 33, or b.
E-l, LOSS OF REACTOR OR SECONDARY COOLANT, Step 8,
or c.
ES-1.1, SI TERMINATION, Step 3, or d ~
ECA 2 ~ 1 g UNCONTROLLED DEPRESSURI ZATION OF BOTH STEAM GENERATORS, Step ll, or e.
E-3, STEAM GENERATOR TUBE RUPTURE, Step 11, or f
ECA 3 ~ 1 g SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED, Step 3, or g
FR I ~ 1 g
RESPONSE
TO HIGH PRESSURI ZER LEVELS Step 2, or h
FR I ~ 3 g
RESPONSE
TO VOIDS IN REACTOR VESSEL HEAD/
Step 3, or i.
FR-H.1,
RESPONSE
TO LOSS OF SECONDARY HEAT SINK, Step 14, or j.
FR-P.l,
RESPONSE
TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION, Step 5.
2.
SYMPTOMS The symptoms of LOSS OF INSTRUMENT AIR are; a.
H-8, Instrument Air Lo Press, 100 psi, alarm lit, or b.
H-16, Instrument Air Compressor, alarm lit.
<k"~
I
'K t
EOP:
AP-IA.1 TITLE:
LOSS OF INSTRUMENT AIR REV 3
PAGE 3 of 10 STEP ACTIONlEXPECTED 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, SHOULD BE PERFORMED.
NOTE:
o Step 1 is an IMMEDIATE ACTION Step.
o If this procedure is entered from any EOP, go to Step 3.
O 1
Check Instrument Air Pressure IF IA pressure is greater than 60 GREATER THAN 60 PSIG AND psig but decreasing, THEN start STABLE standby IA compressor.
IR IA pressure is less than 60
- psig, THEN:
o Trip the reactor.
o Go to E-O, REACTOR TRIP or SAFETY INJECTION.
4F, z
wt 7t t
ff
EOP:
AP-IA.1 TITLE:
LOSS OF INSTRUMENT AIR REV:
3 PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION o
OBSERVE D/G LOADING LIMITS OF 2300 KW FOR 1/2 HOUR, 2250 KW FOR 2 HOURS, AND 1950 KW FOR CONTINUOUS SERVICE.
o WHEN IA PRESSURE IS LOW, MFW REGULATING VALVES SHOULD BE MONITORED FOR PROPER OPERATION.
2 Verify Power To Bus 13 and IF IA pressure is low Bue to a loss Bus 15:
of power to bus 13 OR bus 15, THEN:
o Bus 13 - APPROXIMATELY 480 VOLTS o
Bus 15 - APPROXIMATELY 480 VOLTS
- a. 'Crosstie bus 13 to 14, OR crosstie bus 15 to 16 as required.
- b. Start IA compressors as necessary (75 kw each).
- c. IF offsite power is lost, THEN go to AP-ELEC.l, LOSS OF f12 SS TRANSFORMER.
3 Check IA Compressors:
o At least 2 compressors
- RUNNING AND IA PRESSURE STABLE OR INCREASING Perform the following:
- a. Start additional IA compressors.
- b. Service air compressor running OR start service air compressor.
~O
'h
~1; t
0 sg
%t, i
EOP:
AP-IA.1 LOSS OF INSTRUMENT AIR REV:
3 PAGE 5 of 10 STEP ACTIOHLBXPECTED RESPONSE
RESPONSE
NOT OBTAINED 4
Check IA System Major Components Locally:
- a. IA dryers:
o Dryers - NOT BLOWING AIR o
Dryers - AUTO TRANSFER OCCURRING PROPERLY
1)
A IA dryer isolation:
o Open bypass V-5276.
o Close inlet V-5277.
o Close outlet V-5275.
- b. IA dryer prefilters and after filters D/P - NORMAL ((10 psid)
- c. Running IA compressors-INDICATIONS NORMAL 2)
B IA dryer isolation:
o Open bypass V-8230.
o Close inlet V-8228.
o Close outlet V-8229.
- b. IF any filter D/P is excessive
() 10 psid),
THBN bypass the affected filter.
- c. IF any IA compressor malfunctioning, THEN:
- 1) Remove faulty IA compressor from service.
$'I
~ I lg
EOP:
AP-IA.1 TITLE:
LOSS OF INSTRUMENT AIR REV:
3 PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RBSPONSE NOT OBTAINED CAUTION AN EVALUATION OF THE CONSEQUENCES SHOULD BE PERFORMBD BEFORE A LBAKING SECTION OF THE IA SYSTEM IS ISOLATED.
REFER TO ATTACHMENT A FOR MAJOR EQUIPMBNT AFFECTED IN EACH SPECIFIC AREA.
5 Check For Instrument Air Leakage In The Turbine And Intermediate (Clean Side)
Buildings:
o Turbine Building -
NO LEAKAGE DETECTED o
Intermediate Building (clean side) -
NO LEAKAGE DETECTED IF the IA leak is found in the turbine or intermediate bldgs.,
THEN:
- a. Isolate the leak (Refer to
'Figure 1).
b.
Go to Step 15.
6 Establish Letdown Isolation:
o AOV-427 - CLOSED o
AOV-200A, AOV-200B, and AOV-202
- CLOSBD NOTE:
When IA is isolated
-to CNMT, PRZR spray valves vill not function.
PRZR heaters should be manually controlled.
7 Close AOV-5392. TO ISOLATE IA TO CNMT 8
Check IA Pressure
- a. Pressure STABLE OR INCREASING b.
Go to Step 12
- a. IF IA pressure continues to
C I
~ ~
EOP:
AP-IA.1 LOSS OF INSTRUMENT AIR REV:
3 PAGE 7 of 10 STEP ACTIOEXPECTED
RESPONSE
RESPONSE NOT OBTAINED NOTE:
When IA is isolated to the Aux Bldg, make-up to the VCT and from the RUST is disabled, AND charging pumps will go to minimum speed, AND HCQ-142 fails open.
9 Close V-7350 (By SFP On West Wall)
TO ISOLATE IA TO AUX BLDG 10 Check IA Pressure STABLE OR IR IA leak is NOT in Aux Bldg, INCREASING THEN:
a; Restore letdown as follows:
'1) Open IA to Aux Bldg V-7350.
IR NOT, go to Step 12.
- 3) Ensure AOV-371 and AOV-427 open.
- 4) Place PCV-135 and TCV-130 in manual at " 25X open.
- 5) Open desired orifice isolation valve.
- 6) Ad)ust PCV-135 and TCV-130 as necessary.
- 7) Restore PCV-135 and TCV-130 to auto at " 250 psig and 80'R to 120'R.
- b. Continue investigation.
c.
Go to Step 16.
'/pgi D
gL
AP-IA.1 TITLE:
LOSS OF INSTRUMENT AIR REV:
3 PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED CAUTION IF CHARGING PUMP SUCTION IS SWAPPED TO THE RWST TO INCREASE VCT LEVEL, A LOAD REDUCTION MAY BE REQUIRED TO MAINTAINTAVG AT TREF.
11 Check VCT Level GREATER THAN 204 IF VCT level is low and IA has NOT been restored, THBN open V-358 RWST to charging pump suction.
IF normal VCT makeup or normal or excess letdown can NOT be restored, THEN, plant shutdown will be
- required, (Refer to 0-2.1 Normal Shutdown to Hot Shutdown).
12 Verify CCW Is Being Supplied To The RCPs:
o Alarm A EXTINGUISHED o
Alarm A BXTINGUISHED Perform the following:
- b. IF CCW can NOT be restored to
- RCPs, THEN go to Step 14.
CAUTION MONITOR RCP SEAL INDICATIONS WHEN CHARGING PUMP IS NOT RUNNING.
13 Start And Stop Charging Pump(s)
As Necessary TO CONTROL PRZR LEVEL
)C
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CAl
EOP:
AP-IA.l TITLE:
LOSS OF INSTRUMENT AIR REV:
3 PAGE 9 of 10 STEP ACTIONLEXPECTED RESPONSE
RESPONSE
NOT OBTAINED 14 Throttle Charging Flow Locally TO MAINTAIN RCP SEAL INJECTION FLOW WHEN CHARGING PUMPS(S)
ARE RUNNING 15 Establish Isolation Of IA Leak:
- a. Investigate
- LEAKING SECTION TO BE ISOLATED
- b. Isolate - LEAK AS CLOSE TO SOURCE AS POSSIBLE IF IA leak can NOT be isolated, with plant at power, THEN:
- a. Trip the reactor.
b.
Go to E-O, REACTOR TRIP or SAFETY INJECTION.
IF IA leak occurred while performing any EOP and can NOT be
- isolated, THEN, return to.procedure and step in effect.
16 Complete RESTORATION OF UNAFFECTED PORTIONS OF THE IA SYSTEM TO SERVICE 17 Verify THAT PLANT OPERATION CAN CONTINUE NOTE:
Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
18 Complete MAINTENANCE AND HIGHER SUPERVISION NOTIFICATION
EOP:
AP-IA.1 LOSS OF INSTRUMENT AIR REV:
3 PAGE 10 of 10 STEP ACTIONLEXPECTED RESPONSE
RESPONSE
NOT OBTAINED 19 Establish Further Guidance:
o Return to -
PROCEDURE AND STEP IN ERRECT
-OR-o Return to - NORMAL PLANT OPERATIONS
-END-
EOP:
AP-IA.1 LOSS OF INSTRUMENT AIR REV:
'3 PAGE 1 of 1 AUTOMATIC ACTIONS o
Standby IA compressor may start on low IA header pressure of approximately 115 psig.
o Service air to IA automatic crosstie, AOV-5251), will open when
'lA pressure is less than 90 psig.
EOP:
AP-IA.1 TITLE:
LOSS OF INSTRUMENT AIR REV:
3 PAGE 1 of 1 FIGURE1 AVT By Ser. Air Comp.
Above
'B'ond.
Booster 9535D pump 5317 Above door 37 5315 5316 4314 5397 5392 at Pen.
310 5318 TO SERVICE and AUX.
BLDGS.
'WALL Above
~A~ A.F.W.r.
I I
PEH. 310 Bottom C. V.
FROM AIR DRYERS Air Dryer 5311 t
Above
'A'ond.
Booster Punp Overhead by South side of Fire Water stg. tk..East stanchion 5313 PI ~ 2163 5312 PI -2162 From Service Air
)IHST AIR COMP.J 6962 fAbov D/C ]
[Fuei GagesJ To Screen House
)
8 1'
EOP:
AP-IA.1 TITLE:
LOSS OF INSTRUMENT AIR REV:
3 PAGE 1 of 1 ATTACHMENT A CNMT IA LOSS AND FAILURE MODE o
Letdown AOV-427 FO AOV-200A, 200B, 202 FC o
Excess letdown AOV-310 FC o
Charging AOV-294, 392A, 392B FC o
PRZR Spray PCV-431A, 431B FC o
Aux. Spray AOV-296 FC o
PRZR PORVs FC (can be opened using overpressurization N
system) o RCP seal return AOV-270A, 270B, FO AOV-386 FC o
RCP thermal barrier CCW AOV-754A, 754B FO o
RCS and PRZR sample valves FC AUX BLDG IA LOADS AND FAILURE MODE o
Charging Pump speed control fails to minimum o
VCT makeup valves AOV-110A FO AOV-110B, 110C, ill FC o
Letdown valves AOV-371 FC TCV-145, AOV-112A, Fail to VCT o
Charging pump suction AOV-112B FC AOV-112C FO o
NaOH Tank Outlet vlvs AOV-836A, 836B FO o
RHR vlvs HCV-624, 625 FO HCV-626 FC o
RCS and PRZR sample valves FC TURBINE BLDG IA LOADS AND FAILURE MODE o
MFW regulating valves and bypass valves FC o
Steam Dump valves FC o
S/G blowdown and sample vlvs FC o
Condensate Bypass valve FO o
H~ cooler bypass valve AOV 4229 FO o
H> cooler inlet vlv AOV 4230 FO o
Condenser Makeup vlv FC o
Condensate Makeup vlv FC o
Condensate Trim valves FC o
Heater Drain Pump Recirc vlv FO (HDT pumps trip if recirc vlv full open 1 min) o Reheater 2nd pass Hi level dump vlvs to condenser FO o
Reheater 2nd pass level control vlvs to N5 heaters FC o
S/G ARVs (have backup N~ supply)
4
\\{
l
}'s
EOP:
ES-O.O T!TLE:
REDIAGNOSIS REV 5
PAGE 1 of 4 I
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA,STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE QA X NON-QA REVIEWED BY:
CATEGORY 1.0 6 INNASTATION START:
DATE TIME COMPLETED:
DATE
EOP:
ES-O.O TITLE REDIAGNOSIS REV:
5 PAGE 2 of 4 A.
PURPOSE This procedure provides a mechanism to allow the operator to determine or confirm the most appropriate post accident recovery procedure.
B.
ENTRY CONDITIONS/SYMPTOMS l.
ENTRY CONDITIONS This procedure is entered based on operator judgement.
EOP:
ES-O.O REDIAGNOSIS REV' PAGE 3 of 4 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
o FOLDOUT page should be open and monitored periodically.
o This procedure should only be used if SI is in service or is required.
1 Check If Any S/G Secondary Side Is Intact a.
Check pressures in all S/Gs-ANY S/G STABLE OR INCREASING
- a. IF a controlled cooldown is in
- progress, THEN GO TO Step 2.
IF NOT, THEN the following applies:
o IF main steamlines NOT
- isolated, THEN you should be in E-2, FAULTED STEAM GENERATOR ISOLATION.
-OR-o IF main steamlines
- isolated, THEN you should be in ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS.
2 Check If BOTH S/Gs Secondary Sides Are Intact o
NO S/G PRESSURE DECREASING IN AN A
UNCONTROLLED MANNER o
NO S/G COMPLETELY DEPRESSURIZED Verify faulted S/G isolated unless needed for RCS cooldown:
o Steamlines o
Feedlines IF NOT THEN you should be in E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1
I
EOP:
ES-O.O TITLE:
REDIAGNOSIS REV 5
PAGE 4 of 4 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 3
Check 3Xf S/G Tubes Are Ruptured:
a o
ANY S/G LEVEL INCREASING IN AN UNCONTROLLED MANNER You should be in an E-l or ECA-1 series procedure.
-OR-5 o
ANY S/G WITH HIGH RADIATION I'
4 You Should Be In An E-3 Or ECA-3 Series Procedure
-END-
EOP:
ES-O.O TITLE:
REDIAGNOSIS REV:
5 PAGE 1 of 1 FOLDOUT PAGE RCP TRIP CRITERIA 2.
IF BOTH conditions listed below occur, THEN trip both RCPs:
a.
SI pumps AT LEAST TWO RUNNING b.
RCS pressure minus maximum S/G pressure LESS THAN 175 psig
[400 psig adverse CNMT]
SI ACTUATION CRITERIA IF ANY condition listed below occurs, THEN actuate SI and go to E-O,I-.REACTOR TRIP OR SAFETY INJECTION, Step 1:
o RCS subcooling based on core exit T/Cs LESS THAN O'F USING FIGURE MIN SUBCOOLING
-OR-o PRZR level LESS THAN 54
[304 adverse CNMT]
AND RCS subcooling based on core exit T/Cs LESS THAN 20'F USING FIGURE MIN SUBCOOLING
-OR-o Any automatic SI setpoint is reached 3.
I SI PUMP AUTO SWITCHOVER CRITERION WHEN BAST 1Ievel decreases to 104, THEN ensure SI pump automatic switchover to RWST.
4.
AFW SUPPLYIiSWITCHOVER CRITERION IF CST level decreases to less than 5 feet, THEN switch to alternate XFW water supply (Refer to ER-AFW.1, ALTERNATE WATER SUPPLY TO A'FW PUMPS).
l
EOP:
F-0.3 TITLE:
HEAT SINK REV:
1 PAGE 1 Of 2 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE P
T SUPERIN ND NT EFFECTIVE DATE QA NON-QA REVIEWED BY:
CATEGORY 1.0 GINNA S ETIO"4 Q PgPP DATE TIiVIE Cr" e aPI g=TQD DATE CIME'
I'
CSFST:
F-0.3
Title:
HEAT SINK Rev:
Page 1
of 1
GO TO FR-H.1 TOTAL FEEDWATEA FlaW TO SGs GREATEA THAN 200 GPM YES NARROW AAHGE LEVEL IN AT LEAST OHE SG GAEATER TIlAN SX t25X edverse CHhA]
NO YES GO TO FRH.2 PRESSURE IN AlL SGs LESS THAN 1140 PSIG NO YES GO TO FR-H.3 HARROW RAHGE lEVEL IH AIL SGs tESS THAN 67K NO YES GO TO FR-H.2 PRESSURE IN ALL SGs LESS THAN,,
1085 PSIG NO YES GO TO FR-H.5 HARROW RANGE LEVEL IN ALL SGs GAEATEA THAM 17K f25% adverse CHhAj YES CSF SAT
EOP:
F-0.5 TITLE:
CONTAINMENT REV 1
PAGE 1 of 2 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE P
NT SUPERIN EN NT 1 xi EFFECTIVE DATE QA NON-QA
'ATEGORY 1.0 GIN~A $TATfON START:
REVIEWED BY:
C.'~';PLE, L:D.
QAT,-
CSFST:
F-0.5
Title:
CONTAINMENT Rev:
1 Page 1
of 1
GO TO FR-Z.1 CONTAINMEHT PRESSURE LEss THAN 80 psIe NO YES CONTAINMEHTPRESSURE LESS THAN 28 PSIe IIII!SWWIRWWRIRSIISIRISIRIISW 2
GO TO FR-Z.-2 I
II g
8 NO YES GO TO FR-Z.3 CONTAINMEHT SUMP 8 LP/EL LESS THAN 180 IHCHES YES P
ss H WRSIR HRRR RRR RR IS WRR HRRBRRR GO TO FR-Z.1 IIII NO CONTAIHMEHTRADIATIOH lESS THAN 10 lVhr YES CSF SAT
(
Nt
EOP:
F-0.6 INVENTORY REV:
2 PAGE 1 of 2 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE NT SUPER TE DENT EFFE TIVE DATE QA NON-QA CATEGORY 1.0 GINNAS 'TION START:
DATE REVIEWED BY:
TIME CG!
DEPLETED:
DATE
CSFST:
F-0.6
Title:
INVENTORY Rev:
2 Page 1
of i
GO TO FR-I.3 RVUS FUIID FRACTION QAEATEA THAN 97K OR VESSEL LEVEL GREATER THAN 95K NO YES PRESSURIZER IEVEL LESS THAN ST%
NO YES GO TO FR-I.i GO TO FR-I.2 PRESSURIZER LEVEL GREATEA THAN 13K NO YES GO TO FR-I.3 RVUS flUID FAACTION eREATEA THAN 9TX OR VESSEL IEVEL eREATEA THAN 95X NO YES 4