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
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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: Emergency Preparedness Plans, Imp ement'g Procedures, C D
NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 S
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sr'I ZZZ(ZZ ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, 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, Robert C. Mecred Division Manager Nuclear Production Enclosures xc: USNRC, Region I,(2 copies)
Resident Inspector, Ginna Station 9002220730 900208 PDR ADOCK 05000244 PNU
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tp: TITLE: REV: 8 P-CR.1 CONTROL ROOM INACCESSIBILITY 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 GINNA STATION Y>
START:
QA NON-QA CATEGORY 1.0 DATE REVIEWED BY:
TIME COMPLETED:
ATE
H REV: 8 AP-CR.1 CONTROL ROOM INACCESSIBILITY 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: TITLE: REV 8 AP-CR. 1 CONTROL ROOM INACCESSIBILITY PAGE 3 of 6 STEP ACTION/EXPECTED RESPONSE . RESPONSE NOT OBTAINED NOTE: Steps 1 and 2 are immediate action steps.
1 Verify Reactor Trip: Manual trip the reactor from the control board. IR the RX can NOT o Reactor trip breakers - OPEN be tripped from the Control Room, THEN locally open the reactor trip o MRPI indicates - ALL CONTROL AND breakers.
SHUTDOWN RODS ON BOTTOM O 2 Verify Turbine Trip: Manually turbine can trip turbine from MCB. IR NOT be tripped at the THEN locally trip turbine at o Stop valves - CLOSED MCB, trip lever on HP turbine.
FOP: REV 8 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 4 of 6 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Verify That Fire HAS NOT Perform the following actions:
significantly damaged the MCB Control Circuits a. Close both MSIVs.
o MCB - NO FIRE OR FIRE UNDER b. Trip both reactor coolant pumps.
CONTROL
- c. Close both PRZR relief vlv o Safety related controls and PCV-430 (431C).
indications - NO SIGNIFICANT LOSS OF CONTROLS/INDICATION 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 a. Start the TDAFW pump. Manually PUMPS.>>.'- open TDAFW pump steam admission valves at the steam header MOV-3504A, MOV-3505A.
- b. Verify - BOTH PUMPS THROTTLE TO b. Manually throttle AFW flow.
(230 GPM
F,OP: REV: 8 AP-CR.1 CONTROL ROOM INACCESSIBILITY PAGE 5 of 6 STBP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Establish Charging Flow:
- a. Charging pumps - AT LEAST ONE a. Start a charging pump.
RUNNING
- b. Control charging and letdown-TO MAINTAIN PRESSURIZER LEVEL 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: Start pumps as necessary.
o Verify - AT LEAST ONE SERVICE
'ATER PUMP RUNNING IN EACH LOOP 9 Establish Containment Start fans as necessary.
Cooling o Verify.- AT LEAST TWO RECIRC FAN COOLBRS ARE RUNNING
- C
,EOP: REV: 8 AP-CR.1 CONTROL ROOM INACCESSIBILITY
~ . ' ~ PAGE 6 of 6 STBP ACTION/EXPECTED RESPONSE RESPONSB NOT OBTAINED 10 Throttle AFW as necessary TO MAINTAIN S/G LEVELS BETWEEN 77%'ND 854 11 Check IF THE CONTROL ROOM Return to Step 7.
IS AGAIN HABITABLE 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: TLTLE: REV: 8 AP-CR 1 CONTROL ROOM INACCESSIBILITY 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: TITLE: REV: 5 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 GINNA STATION QA NON-QA CATEGORY 1.0 START:
REVIEWED BY: DATE TIME COI'v)PLETED:
DATE
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EV: TITLE: REV: 5 AP-CCW.l LEAKAGE INTO THE COMPONENT COOLING LOOP 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: TITLE: REV: 5 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 3 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- CAUTION IF t 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 Go to Step 11.
(R-17) INCREASING 2 Check CCW Radiation Monitor Go to Step 4.
(R-17) IN ALARM 3 Verify CCW Surge Tk Vent Close CCW surge tk vent RCV-017.
RCV-017 CLOSED 4 Check RCS Leakage GREATER Go to Step 11.
THAN NORMAL NOTE: RCPs may be safely operated without CCW to the thermal barrier if seal injection flov is maintained.
5 Check RCP Thermal Barrier IF either pump has indication of a Indications: thermal barrier leak, THEN:
o Labyrinth seal D/Ps - NORMAL a. Verify seal in]ection flov o RCP gl seal leak off flovs- b. Close CCW from lA (1B) thermal NORMAL' barrier MOV-754A (754B).
AR-A-7/15 RCP 1A/1B CCW RETURN c. Go to Step 19.
HI TEMP OR LO FLOW 165 GPM 125'F ALARM - EXTINGUISHED
EOP: TtTLE: REV: 5 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 a. IP excess letdown inservice, THEN go to Step 10.
- b. Letdown indications b. Isolate letdown as follovs:
Letdown line flov - NORMAL 1) Close letdown loop B cold leg to RHx AOV-427.
o Lov press LTDN pressure-NORMAL 2) Close LTDN orifices AOVs 200A, 200B, and 202.
o NRHX CCV outlet (local TI-600) - LESS THAN 190'R 3) Place low press LTDN press PI-135 PCV-135 in manual AND close.
- 4) Reduce charging as necessary.
- 5) Go to Step 7.
- c. Go to Step 11 7 Check Stopped:
If CCW Inleakage Has Restore normal letdown and Step 11.
g'o to P.
o CCW surge tank level - STABLE
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EoI': REV: 5 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 a. Reduce charging as necessary to REFERENCE LEVBL control PRZR level.
- b. Go to Step 18 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- c. IF CCW surge tank level STABLE continues to increase, THBN restore excess letdown to service and go to Step 11.
- d. Go to Step 18
ll EOP: TITLE:
REV: 5 AP-CCW.1 'EAKAGE INTO THE COMPONENT COOLING LOOP S PAGE 6 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ll Check RMW to CCW Surge Tank: IF RMW to CCW surge tank MOV-823 open OR RMW pump running, THEN:
o MOV-823 - CLOSED
- a. Close RMW to CCW surge tank o . RMW pump(s) - NOT RUNNING 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 Determine which sample Hx CCW Nuclear Sample Room: outlet temperature is high, THEN:
o Sample Hx (TI-602) common CCW a. Isolate the affected HX.
return temperature from sample Hxs - NORMAL b. Check if inleakage has stopped to CCW surge tank. If inleakage o Sample Hx (PI-603) common CCW has stopped, go to Step 18. IF return flow from sample Hxs- inleakage continues, go to NORMAL 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.
ltt EOP: T!TLE: REV: 5 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP" 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
- b. Idle RHR pump and Hx - ISOLATED 15 Check Stopped:
If CCW Inleakage Has
- a. CCV surge tank level - STABLE a. IF CCV inleakage continues, THEN:
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.
- b. Go to Step 18 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 IF no SI or CS pumps running, THEN Spray Pumps RUNNING go to Step 19.
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EOP: TITLE: REV: 5 AP-CCW.l LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 8 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Stop Then Isolate One SI or IF in leakage cannot be located, CS Pump At A Time And Check THEN, go to Step 19.
CCW Surge Tank Level STABLE 18 Place The Affected Component IN AN ISOLATED AND HELD CONDITION 19 Verify THAT PLANT OPERATION IF plant shutdown is required, THEN CAN CONTINUE refer to 0-2.1, NORHAL SHUTDOWN TO HOT SHUTDOWN.
20 Complete NOTIFICATION TO HIGHER SUPERVISION
-END-
1 EOP: TITLE: REV: 5 AP-'CCW. 1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 1 of 1 AUTOMATIC ACTIONS
~ CCW surge tank vent RCV-017 closes on CCW radiation monitor (R-17) alarm.
EOP: REV: 7 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 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 REVIEWED BY:
CATEGORY 1.0 8INNA STATION START'ATE TIME COMPLETED:
DATE
R' EOP! TlTLE: REV: 7 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION I B <<B.P '.
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
- 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.
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EOP: TITLE: REV: 7 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 3 of 8 STBP ACTION/EXPECTED RBSPONSE RBSPONSE NOT OBTAINED
NOTE: Step 1 is an IMMEDIATE ACTION step.
O 1 Check CCW Pump A-17, Motor Off Status:
CCP-Perform the following:
- a. Verify auto start of standby CCV o RCP EXTINGUISHED pump or start manually.
o Both CCV pump breaker white b. IP A-22, CCV pump discharge lo~
disagreement lights- press 60 psi energized, THEN, EXTINGUISHED check closed CCV to RHR HXs (MOV-738A and MOV>>738B).
it 1 EOP: REV: 7 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 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- a. Open RMW to CCV surge tank APPROXIMATELY 50X AND STABLE (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.
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EOP: TlTLE: REV: 7 AP-CCW. 2 LOSS OF CCW DURING POWER OPERATION PAGE 5 of 8 STEP 'CTION/EXPECTED RBSPONSE RBSPONSE NOT OBTAINED
o REACTOR POVER MUST BE LBSS THAN SX FOR SINGLE LOOP OPERATION.
3 Check CCW To Both RCPs: IF CCV lost to RCP(s), THEN:
o A-7 (A-15), RCP lA (1B) CCV a. Trip the Rx.
return Hi temp or low flow 165 gpm 125'F alarm - EXTINGUISHBD b. Trip affected RCP(s).
o RCP motor bearings temperature c. Go to E-O, REACTOR TRIP or (PPCS address GD-RCPS OR RCP SAFETY INJECTION.
temperature monitor RK-30A recorder) - g 200'F 4 Check CCW Valve Alignment Align CCV valves as necessary.
NORMAL
Jt EOP: REV: 7 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 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:
- 2) Prepare to make CNMT entry,to check for CCV leak.
- 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: REV: 7 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 7 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Check For CCW Leakage In AUX IF no leakage indicated in Aux BLDG: Bldg, THEN:
o Aux Bldg sump pump - INCREASED a. Direct HP Tech to sample CCV HX START FREQUENCY SV outlet for chromates.
-OR- b. Go to step 10.
o Vaste holdup tank level-UNEXPLAINED INCREASE
-OR-o Aux Bldg - VISUAL LEAKAGE IDENTIFIED 7 Establish THE SOURCE OF THE CCW LEAKAGE AND ISOLATE 8 Verify CCW Surge Tank Level IF CCV surge tank level NOT Normal: approximately 50%, THEN open RMV to CCV surge tank, MOV-823 and start a o CCV surge tank level- RMV pump to fill CCV surge tank to APPROXIMATELY 50% approximately 50%.
9 Check CCW System For IF CCV system chromates Chromates: concentration lov, THEN add chromates to CCV system as directed o CCV system chromates by HP.
concentration - NORMAL 10 Verify'CONDITIONS PERMIT IF shutdovn required, THEN refer to CONTINUED POWER OPERATION, 0-2.1, NORMAL SHUTDOVN TO HOT (Refer to Technical SHUTDOVN Specification Section 3.3.3)
EOP: REV: 7 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 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 a. IR problem NOT corrected or leakage NOT found or isolated, THEN return to Step 4.
- b. Return to - APPROPRIATE NORMAL OPERATING PROCEDURE
-END-
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REV: 7 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 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: REV: 6 AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN 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 gy 4++
J 6INNA STATION 1
y>>'f f START:
DATE QA NON-QA CATEGORY 1.0 TIME REVIEWED BY:
COMPLETED:
DATE
tl EOP: TITLE: REV: 6 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN 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
- 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 7J (A 15) g RCP lA ( 1B) CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F alarm. flow alarm.
EOP! T!TLE! REV 6 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN 4F PAGE 3 of 6 i
STEP ACTION/EXPECTED RBSPONSE RBSPONSE NOT OBTAINED 1 Check CCW Pump Status: IF 2 pumps were previously running and one has tripped, THEN reset and o Neither pump breaker white attempt to restart the tripped disagreement light - IS LIT pump, if required for cooling.
Alarm A-17, Motor Off, CCP- IF one was previously running it pump o RCP EXTINGUISHBD and tripped, THEN ensure auto start of the standby pump or start pump manually.
2 Check CCW Pump Discharge Lo IF CCV pump discharge pressure is Pressure 60 PSI ALARM A-22, low, THEN:
EXTINGUISHED
f
- 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: IF CCV is lost to operating RCPs for GRBATER THAN 2 minutes OR IF an
- a. A-7 (A-15), RCP 1A (1B) CCV RCP motor bearing temperature RETURN HI TEMP OR LOV FLOV 165 exceeds 200'F, THEN trip the GPM 125'F - EXTINGUISHED affected RCP and see Attachment A, if natural circulation is required.
- b. Verify - NO RCP MOTOR BEARING TEMPERATURE ALARMS
EOP: REV 6 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 4 of 6 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check For CCW Leak:
- a. Verify CCW Surge Tank Level a. IF CCW surge tank level is Normal - A-13, COMP COOLING decreasing, THEN:
SURGE TANK LO LEVEL 41.2X ALARM EXTINGUISHED AND LEVEL STABLE 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.
- b. Go to step 8
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EOP: REV: 6 AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN PAGE 5 of 6 STEP 'CTION/EXPECTED RESPONSE RBSPONSB NOT OBTAINBD 5 Check for CCW Leakage In CNMT:
- 1) Direct Health Physics Tech to sample Sump A for Chromates.
- 1) Stop affected RCP.
- 2) Close CCW supply and return for affected RCP(s) (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 IF no leakage indicated in AUX BLDG BLDG, THEN:
o Start frequency of AUX BLDG sump a. Direct HP Tech to sample CCW HX pump(s), - INCREASED SW outlet for chromates.
o Waste:-'holdup tank level- b. RBTURN to step 3.
UNEXPL'AINED INCREASE
wg 4 EOP: TlTLE: REV 6 AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN PAGE 6 of 6
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STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
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- Realign valves as necessary to AS REQUIRED FOR PLANT restore CCV to individual CONDITIONS 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-
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EOP: REV: 6 AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN 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: REV: 6 AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN 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 (ADMINISTRATIVE LIMIT 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: TITI.Et REV: 6 AP-CCW.3 LOSS OF CCW PLANT SHUTDOWN 1
hf PAGE 1 of 1 FIGURE MIN SUBCOOLING NOTE: Subcooling Margin = Saturation Temperature From Figure Below [-] Core Exit T/C Indication RC S PRESSURE (PSIG) 2500 2400 RCS PRESSURE 2300 INCREMENTS 20 PSIG 2200 2100 2000 1900 1800 1700 1600 1400 SUBCOOLED 1300 REGION 1200 1100 1000 900 800 INADEQUATE 700 SUBCOOLING 600 REGION
'500 400 300 200 NORMAL CNMT TEMPERATURE INCREMENTS 10'F 100 0
20 0 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE ('F)
REV 4 AP-CVCS.1 CVCS LEAK 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 8INNA STATION QA ~:-'NON-QA CATEGORY 1. 0 START:
REVIEWED BY:
DATE TIME COMPLETED:
DATE
V EOP: TITLE: REV 4 AP-CVCS. 1 CVCS LEAK 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;
- b. Charging line pressure low, or
- c. F-14, CHARGING PUMP SPEED ALARM, or d A 4 g REGEN HX LETDOWN OUT H I TEMP 3 9 5 F ALARM'/ or
- e. Letdown line low pressure and low flow, or
- f. Charging Pump Room AREA MONITOR R-4 ALARM
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EOP: TITLE: REV: 4 AP-CVCS. 1 CVCS LEAK 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 IF PRZR level is stable, THEN go to Step 4.
o PRZR level - DECREASING 2 Increase PRZR Level:
- a. Start - ADDITIONAL CHARGING PUMPS AND INCREASE SPEED AS NECESSARY 3 Check PRZR Level: IF available charging pumps are running at maximum speed with o PRZR level - GREATER THAN 13X letdown isolated, AND PRZR level is AND STABLE OR INCREASING 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 IF CCW leak indicated, THEN go to System Leak: AP-CCW.1, LEAKAGE INTO THE COMPONENT COOLING LOOP.
o CCW radiation monitor (R-17)-
NORMAL" o CCW surge'ank level - NORMAL
4 l4, S
EOP: REV 4 AP-CVCS. 1 CVCS LEAK PAGE 4 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check For Letdown Line Leak: IP abnormal letdown flow or pressure exist, THEN close LTDN o Letdown line flow- loop B cold leg to RHx AOV-427, AND APPROXIMATELY 40 GPM IP RCS leakage returns to normal, o Low press LTDN pressure- THEN go to Step 8, OR APPROXIMATELY 250 PSIG IR RCS leakage does not return to normal, THEN go to Step 6.
6 Check For Charging Line Leak: IR charging line leak is indicated, THEN go to Step 7.
- a. Charging pump discharge pressure
- NORMAL
- b. REGEN Hx LTDN outlet temp TI-127
- NORMAL
- c. Charging line flow - NORMAL (PI-128 25 gpm)
- d. Go to Step 12
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EOP:
REV: 4 AP-CVCS.1 CVCS LEAK 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
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EOP: TITLE: REV: 4 AP-CVCS. 1 CVCS LEAK PAGE 6 of 8 4
STEP 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*
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EOP: TITLE: REV: 4 AP-CVCS 1 F CVCS LEAK PAGE 7 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
12 Check For RCP Seal Injection IF RCP labyrinth seal D/P is low or Leak: zero, THEN suspect leak in seal in)ection line. Dispatch AO to o RCP labyrinth seal D/P - GREATER investigate AND go to Step 14.
THAN 15 INCHES IF seal return flow or standpipe ~
o RCP fl seal return flows- alarms indicate RCP seal malfunction, THEN GO TO NORMAL AP-RCP.1,"'CP SEAL MALFUNCTION.
o RCP standpipe level alarms - OPP CAUTION THE NORMAL METHOD OP VCT DIVERSION (AOV-112A) IS NOT AVAILABLEWHILE ON EXCESS LETDOWN. VCT LEVEL MAY BE DECREASED BY MANUALLY DIVERTING 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 IF the leak can NOT be isolated, CVCS Leak And Have Personnel THEN go to AP-RCS.1, REACTOR COMPLETE MANUAL ISOLATION COOLANT LEAK, Step 6.
AS REQUIRED
EOP: TITLE: REV: 4 AP-CVCS.l CVCS LEAK PAGE 8 of 8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Allow Conditions To IF the leak can NOT be isolated, Stabilize, THEN Perform An THEN go to AP-RCS.1, REACTOR RCS Leakage Calculation TO COOLANT LEAK, Step 6.
VERIFY THAT LEAK HAS BEEN ISOLATED NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION, for reporting requirements.
16 Complete NOTIFICATION TO HIGHER SUPERVISION
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EOP TITLE:
REV 4 AP-CVCS ~ 1 CVCS LEAK 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:
REV 3 AP-IA.1 LOSS OF INSTRUMENT AIR 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 6INNA STATION QA NON-QA M CATEGORY 1.0 START:
REVIEWED BY:
DATE TIME CQMoLETED DATE
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EOP TITLE:
REV: 3 AP-IA.1 LOSS OF INSTRUMENT AIR 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
~
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 I IN TO VO DS 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 SHOCK CONDITION, TO IMMINENT PRESSURIZED THERMAL 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.
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EOP: TITLE:
REV 3 AP-IA.1 LOSS OF INSTRUMENT AIR 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 GREATER THAN 60 PSIG AND
. IF IA pressure is greater than 60 psig but decreasing, THEN start standby IA compressor.
STABLE IR IA pressure is less than 60 psig, THEN:
o Trip the reactor.
o Go to E-O, REACTOR TRIP or SAFETY INJECTION.
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EOP: TITLE:
REV: 3 AP-IA. 1 LOSS OF INSTRUMENT AIR 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 a. 'Crosstie bus 13 to 14, OR crosstie bus 15 to 16 as o Bus 15 - APPROXIMATELY 480 VOLTS 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: Perform the following:
o At least 2 compressors - RUNNING a. Start additional IA compressors.
AND IA PRESSURE STABLE OR INCREASING b. Service air compressor running OR start service air compressor.
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EOP:
REV: 3 AP-IA.1 LOSS OF INSTRUMENT AIR PAGE 5 of 10 STEP ACTIOHLBXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check IA System Major Components Locally:
- a. IA dryers: a. IF IA dryer is bloving air OR IF dryer transfer is NOT occurring, o Dryers - NOT BLOWING AIR THEN isolate the faulty dryer:
o Dryers - AUTO TRANSFER 1) A IA dryer isolation:
OCCURRING PROPERLY o Open bypass V-5276.
o Close inlet V-5277.
o Close outlet V-5275.
- 2) B IA dryer isolation:
o Open bypass V-8230.
o Close inlet V-8228.
o Close outlet V-8229.
- b. IA dryer prefilters and after b. IF any filter D/P is excessive filters D/P - NORMAL ((10 psid) () 10 psid), THBN bypass the affected filter.
- 1) Remove faulty IA compressor from service.
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EOP: TITLE:
REV: 3 AP-IA.1 LOSS OF INSTRUMENT AIR 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 IF the IA leak is found in the Leakage In The Turbine And turbine or intermediate bldgs.,
Intermediate (Clean Side) THEN:
Buildings:
- a. Isolate the leak (Refer to o Turbine Building - NO LEAKAGE 'Figure 1).
DETECTED
- b. Go to Step 15.
o Intermediate Building (clean side) - NO LEAKAGE DETECTED 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 a. IF IA pressure continues to decrease, THEN open IA to CNMT (AOV-5392) AND go to Step 9.
- b. Go to Step 12
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EOP:
REV: 3 AP-IA. 1 LOSS OF INSTRUMENT AIR 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.
- 3) Ensure AOV-371 and AOV-427 open.
- 4) Place PCV-135 manual at " and TCV-130 in 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.
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TITLE:
REV: 3 AP-IA. 1 LOSS OF INSTRUMENT AIR 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 MAINTAIN TAVG AT TREF.
11 Check VCT Level GREATER IF VCT level is low and IA has NOT THAN 204 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 Perform the following:
To The RCPs:
o Alarm A EXTINGUISHED
- CAUTION MONITOR RCP SEAL INDICATIONS WHEN CHARGING PUMP IS NOT RUNNING.
13 Start And Stop Charging Pump(s) As Necessary TO CONTROL PRZR LEVEL
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EOP: TITLE:
REV: 3 AP-IA.l LOSS OF INSTRUMENT AIR 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 IF IA leak can NOT be isolated, Leak: with plant at power, THEN:
- a. Investigate - LEAKING SECTION TO a. Trip the reactor.
BE ISOLATED
- b. Go to E-O, REACTOR TRIP or
- b. Isolate - LEAK AS CLOSE TO SAFETY INJECTION.
SOURCE AS POSSIBLE 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:
REV: 3 AP-IA.1 LOSS OF INSTRUMENT AIR 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:
REV: '3 AP-IA.1 LOSS OF INSTRUMENT AIR 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: TITLE: REV: 3 AP-IA.1 LOSS OF INSTRUMENT AIR PAGE 1 of 1 FIGURE1 TO SERVICE and AUX.
BLDGS.
'WALL Above ~A~ A.F.W.r .
I Above door 37 I
PEH. 310 5315 Bottom Above C. V.
Booster
'B'ond.
5397 5392 9535D pump 5317 AVT at Pen. 310 By Ser. Air Comp.
5316 4314 5318 Above Booster Punp
'A'ond.
5311 t Overhead by South PI ~ 2163 side of Fire Water stg. tk..East stanchion FROM AIR DRYERS Air Dryer 5313 5312 PI -2162 From Service Air
)IHST AIR COMP.J 6962 fAbov D/C ]
[Fuei GagesJ To Screen House
)
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EOP: TITLE:
REV: 3 AP-IA.1 LOSS OF INSTRUMENT AIR 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 control fails to o
o o
Charging Pump speed minimum VCT makeup valves AOV-110A FO AOV-110B, 110C, Letdown valves AOV-371 FC TCV-145, AOV-112A, Fail to ill FC 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 open 1 min)
FO (HDT pumps trip if recirc vlv full 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
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EOP: T!TLE: REV 5 ES-O.O REDIAGNOSIS PAGE 1 of 4 I
ROCHESTER GAS AND ELECTRIC CORPORATION GINNA,STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE PLANT SUPERINTENDENT EFFECTIVE DATE 6 INNA STATION START:
QA X NON-QA CATEGORY 1.0 DATE REVIEWED BY:
TIME COMPLETED:
DATE
EOP: TITLE REV: 5 ES-O.O REDIAGNOSIS 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: REV' ES-O.O REDIAGNOSIS 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 Side If Any S/G Is Intact Secondary
- a. Check pressures in all S/Gs- a. IF a controlled cooldown is in ANY S/G STABLE OR INCREASING 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 Sides If BOTH S/Gs Are Intact Secondary Verify faulted S/G isolated unless needed for RCS cooldown:
o NO S/G PRESSURE DECREASING IN AN o Steamlines A UNCONTROLLED MANNER o Feedlines o NO S/G COMPLETELY DEPRESSURIZED IF NOT THEN you should be in E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1
I EOP: TITLE: REV 5 ES-O.O REDIAGNOSIS PAGE 4 of 4 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 Check 3Xf S/G Tubes Are You should be in an E-l or ECA-1 Ruptured: series procedure.
a o ANY S/G LEVEL INCREASING IN AN UNCONTROLLED MANNER
-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: TITLE: REV: 5 ES-O.O REDIAGNOSIS PAGE 1 of 1 FOLDOUT PAGE RCP TRIP CRITERIA 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]
- 2. 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 I
- 3. 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: TITLE: REV: 1 F-0.3 HEAT SINK 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 GINNA S ETIO"4 Q PgPP QA NON-QA CATEGORY 1.0 DATE TIiVIE REVIEWED BY:
Cr" e aPI g=TQD DATE CIME'
I' CSFST:
Title:
Rev:
F-0.3 HEAT SINK 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 NO GO TO FR H.2 SG GAEATER TIlAN SX t25X edverse CHhA] YES PRESSURE IN AlL NO GO TO SGs LESS THAN 1140 PSIG YES FR-H.3 HARROW RAHGE lEVEL NO GO TO IH AIL SGs tESS THAN 67K YES FR-H.2 PRESSURE IN ALL NO GO TO SGs LESS THAN,,
1085 PSIG YES FR-H.5 HARROW RANGE LEVEL IN ALL SGs GAEATEA THAM 17K f25% adverse CHhAj YES CSF SAT
EOP: TITLE: REV 1 F-0.5 CONTAINMENT 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 GIN~A $ TATfON START:
QA NON-QA 'ATEGORY 1.0 REVIEWED BY:
C.'~';PLE, L:D.
QAT,-
CSFST:
Title:
Rev: 1 F-0.5 CONTAINMENT Page 1 of 1 GO TO FR-Z.1 NO GO TO CONTAINMEHT PRESSURE ss H W R SIR H R R R R R R R R IS W R R H R R B R R R LEss THAN 80 psIe P FR-Z.1 III YES I
CONTAINMEHT PRESSURE NO GO TO LESS THAN 28 PSIe IIII!SWWIRWWRIRSIISIRISIRIISW 2 FR-Z.-2 YES III g
8 CONTAINMEHT SUMP 8 NO GO TO LP/EL LESS THAN 180 IHCHES YES FR-Z.3 CONTAIHMEHT RADIATIOH lESS THAN 10 lVhr YES CSF SAT
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EOP:
REV: 2 F-0.6 INVENTORY 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 GINNA S 'TION DEPLETED:
START:
QA NON-QA CATEGORY 1.0 DATE REVIEWED BY: TIME CG!
DATE
CSFST:
Title:
Rev: 2 F-0.6 INVENTORY Page 1 of i GO TO FR-I.3 RVUS FUIID FRACTION QAEATEA THAN 97K OR NO VESSEL LEVEL GREATER THAN 95K YES GO TO FR-I.i PRESSURIZER NO IEVEL LESS THAN ST%
YES GO TO FR-I.2 PRESSURIZER NO GO TO LEVEL GREATEA THAN 13K YES FR-I.3 RVUS flUID FAACTION eREATEA THAN 9TX OR NO VESSEL IEVEL eREATEA THAN 95X YES CSF 4