ML17309A648
| ML17309A648 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/25/1999 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| PROC-990125, NUDOCS 9902030343 | |
| Download: ML17309A648 (35) | |
Text
C'EGULATORY INFORMATION.DISTRIBUTION SYSTEM (RIDS)
VISSING,G.S.
t,CESSIOP'BR'99020303 3
DOC DATE'9/01/25 NOTARIZED'O DOCKET ¹
~FACIAL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION WIDAY,J.A.
Rochester Gas
& Electric Corp.
RECIP.NAME
'RECIPIENT AFFILIATION
SUBJECT:
Revised "Ginna Station Emergency Operating Procedures.
With 990125 ltr.
DISTRIBUTION CODE: A002D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:Inadecpxate Core Cooling (Item II.F.2)
GL 82-2 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) 05000244 RECIPIENT ID CODE/NAME PD1-1 PD INTERNAL E
CE ER 01 RES DE RES/DSZR/RPSB I
EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME VISSING,G.
NRR/DSSA/SRXB RES/DET/EIB NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 D
U N
NOTE TO ALL "RZDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 9
ENCL 9
<</I/7/K~ m I')7gFII7/7I/7/
((: Oi"77'/!~/r".ii7ui7i771 7/laird'l~lJlllfiuuuu.
ROCHESTER GASANDELECTRIC CORPORATION JOSEPH A. WIDAY Plant Manager Ginna Nuclear Plant
/
ZONK
- '"'L~:,u SrArr 89EASTA VENUE, ROCHESTER, N.Y. 14649%001 TELEPHONE AREA CODE 716 546-2700 January 25, 1999 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Guy S. Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
Emergency Operating Procedures.
R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Vissing:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, Josep A. Widay JAW/jdw xc:
U.S. Nuclear Regulatory Commission Region I
475 Allendale Road King of Prussia, PA 19406-1415 Ginna USNRC Senior Resident Inspector Enclosure(s):
AP Index ATT Index AP-RHR.1, Rev 13 ATT-3.0, Rev 5 ATT-3.1, Rev 3
'tt'Tt02030343 990125 PDR ADOCK 05000244 F
REPORT NO. 01 REPORT:
NPSP0200 DOC TYPE:
PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 01/25/99 PAGB:
1 PARAMETERS: DOC TYPES PRAP STATUS: EF QU 5 YEARS ONLY:
PROCEDURE NUMBER AP-CCW. 1 AP-CCW. 2 AP-CCW. 3 AP-CR. 1 AP-CVCS. 1 AP-CW. 1
, AP-ELEC.l AP-ELEC. 2 AP-ELEC. 3 AP ELEC.14/16 AP-ELEC.X7/18 AP-FW. 1 AP-IA.1 AP-PRZR. 1 AP RCC.1 AP-RCC. 2 AP-RCC.3 AP-RCP. 1 AP-RCS. 1 AP-RCS. 2 AP-RCS. 3 AP-RCS.4 AP RHR.1 AP-RHR.2 PROCBDURE TITLE LEAKAGE INTO THB COMPONENT COOLING LOOP LOSS OF CCW DURING POWER OPERATION LOSS OP CCW PLANT SHUIDOWN CONIROL ROOM INACCESSIBILITY CVCS LEAK LOSS OP A CIRC WATBR PUMP LOSS OP 12A AND/OR 12B BUSSES SAPEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY IDES OP 12A AND/OR 12B TRANSFORMER tBBLOW 350 F)
LOSS OF SAFEGUARDS BUS 14/16 LOSS OP SAFEGUMUK BUS 1'7/18 PARTIAL OR COMPLETE LOSS OP MAIN PEEDWATER LOSS OP INSTRUMENT AIR ABNORMAL PRBSSURIZBR PRESSURE CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION RCC/RPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCTION REACTOR COOLANT LEAK LOSS OP REACTOR COOLANT PLOW
'HIGH REACTOR COOLANT ACTIVITY SHUTDOWN LOCA LOSS OF RHR LOSS OF RHR WHILB OPERATING AT RCS REDUCED INVENTORY CONDITIONS EFFECT DATE IAST REVIEW 013 10/30/98 05/01/98 05/01/03 EP 012 02/24/96 08/30I94 08I30/99 EF 010 03/29/96 08/30/94 08/30/99 EF 015 01/26/98 11/17/94 11/17/99 EF 012 OS/01/98 05/01/98 05/01/03 EF 010 07/16/98 05/01/98 05/01/03 EF 016 05/01/98 05/01/98 05/01/03 EF 008 01/26/98 02/11/94 02/11/99 EF 005 05/01/98 05/01/98 05/01/03 EF 000 06/09/97 06/09/97 06/09/02 EF 001 02/27/98 06/09/9'l 06/09/02 EP 011 02/27/98 02/27/98 02/27/03 EF 015 05/01/98 05/01/98 05/01/03 EP 009 06/03/96 09/29/94 09/29/99 EF 006 02/24/96 05/14/98 05/14/03 EF 008 11/16/98 02/06/97 02/06/02 EF 004 11/16/98 02/27/98 02/27/03 EF 012 05/01/98 05/01/98 05/01/03 EP 013 05/01/98 05/01/98 05/01/03 EF 010 12/14/98 05/01/98 05/01/03 EF 007 08/05/97 08/05/97 08/05/02 EP 009 05/01/98 05/01/98 05/01/03 EF 013 01/25/99 05/01/98 05/01/03 BF 007 05/15/97 03/21/95 03/21/00 EF
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 01/25/99 PAGE:
2 PARAMETERS:
DOC TYPES - PRAP STATUS:
EP QU 5 YEARS ONLY:
PROCEDURE NUMBER AP SW.l AP-TURB. 1 AP TURB.2 AP-TURB.3 AP-TURB. 5 PROCEDURE TITLE SERVICE NATER LEAK TURBINE TRIP NITHOUI'XTRIP REQUIRED TURBINE LOAD REJECTION TURBINE VIBRATION LOSS OP CONDENSER VACUUM RAPID LOAD REDUCTION EFFECT DATE NEXT REVIEW ST 014 01/14/99 06/03/98 06/03/03 EP 009 10/10/97 10/10/97 10/10/02 EF 016 02/27/98 05/13/98 05/13/03 EF 008 12/04/96 02/10/98 02/10/03 EF 014 05/01/98 05/01/98 05/01/03 EF 003 02/27/98 07/10/95 07/10/00 EF TOTAL FOR PRAP 30
REPORT NO.
01 REPORT:
NPSP0200 DOC TYPE:
PRATT i
PARAMETERS:
DOC TYPES - PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX EOP ATTACHMENTS STATUS:
EP QU 5 YEARS ONLY:
01/25/99 PAGB:
3 PROCEDURE NUMBER ATT-l.0 ATT-2. 1 AIT-2.2 ATI-2.3 ATT-3.0 ATI'-3.1 ATT-4.0 ATI'-5.0 ATI'-5.1 ATT-5.2 ATT 6.0 ATT 7.0 ATT-8.0 ATT 8.1 ATT-8.2 ATT-8.3 ATT-8.4 ATT-9.0 ATT-9.1 ATT-10.0 ATT-11.0 ATT-11.1 ATT-11.2 ATT-12.0 PROCEDURB TITLE ATTACHMENT AT POWER CCW ALIGNMENT ATTACHMENT MIN SW ATTACHMENT SW ISOLATION ATTACHMENT SW LOADS IN CNMI'TTACHMENT CI/CVI ATTACHMENT CNMT CLOSURE ATTACHHENT CNMT RECIRC PANS ATTACHMENT COND TO S/G ATTACHMENT SAFW ATTACHMENT PIRB WATER COOLING TO 'IDAFW PUMP ATTACHMENT COND VACUUM ATTACHMENT CR EVAC ATTACHMENT DC LOADS ATTACHMENT D/G STOP ATTACHMENT GEN DEGAS ATTACHMENI'ONVITAL ATTACHMENT SI/UV ATTACHMENT LETDOWN ATTACHMENT EXCESS L/D ATTACHMENT FAULTED S/G ATTACHMENT Ih CONCERNS ATTACHMENT IA SUPPLY ATTACHMENT DIESEL AIR COMPRESSOR ATTACHMENT N2 PORVS EFFECT REV DATB 001 07/26/94 02/10/98 02/10/03 BF 004 06/26/98 02/10/98 02/10/03 EF 005 10/30/98 08/11/98 08/11/03 EP 003 01/25/95 01/25/95 01/25/00 EP 005 01/25/99 01/06/99 01/06/04 EF 003 01/25/99 02/11/94 02/11/99 EP 003 07/26/94 05/13/98 05/13/03 EP 004 01/25/95 01/25/95 01/25/00 EF 006 07/07/98 11/08/94 11/08/99 EF 003 01/14/99 01/14/99 01/14/04 EF 003 12/18/96 02/10/98 02/10/03 EF 004 05/04/98 02/10/98 02/10/03. EP 005 01/14/99 01/14/99 01/14/04 EP 004 11/03/95 02/10/98 02/10/03 EF 005 07/26/94 02/11/94 02/11/99 EP 003 07/26/94 02/10/98, 02/10/03 EP 004 04/24/97 02/10/98 02/10/03 BF 006 04/07/97 01/06/99 01/06/04 EF 002 07/26/94 02/10/98 02/10/03 EP 005 10/03/96 05/13/98 05/13/03 EF 002 04/07/97 08/11/98 08/11/03 EF 002 04/07/97 08/11/98 08/11/03 EF 000 04/03/98 04/03/98 04/03/03 EP 003 03/24/97 02/10/98 02/10/03 EF
REPORT NO. 01 REPORT:
NPSP0200 DOC TYPE:
PRATT "GINNA~
POWER PLANT PROCEDURES INDEX EOP ATTACHMENTS 01/25/99 PAGE:
4 PARAMETERS:
DOC TYPES -
PRAP STATUS:
EP QU 5 YEARS ONLY:
PROCEDURE NUMBER ATT 13.0 ATI'4.0 ATI'-l4.1 ATT-14.2 ATT-li. 3 ATI'4.4 ATT 14 ~ 5 ATT-14.6 ATT-15.0 ATT-15.1 ATT-15.2 ATT-16.0 ATT 17.0 ATT 17.1 ATT-18.0 ATT-20.0 ATT 21.0 ATT-22.0 PROCEDURE TITLE ATTACHMENT NC ATTACHMENT NORMAL RHR COOLING ATTACHMENT RHR COOL ATTACHMENT RHR ISOL ATTACHMENT RHR NPSH ATTACHMENT RHR SAMPLE ATTACHMENT RHR SYSTEM ATTACHMENT RHR PRESS REDUCTION ATTACHMENT RCP START ATTACHMENT RCP DIAGNOSTICS ATTACHMENI'EALCOOLING ATTACHMENT RUPTURED S/G ATTACHMENT SD-1 ATTACHMENT SD-2 ATTACHMENT SFP - RWST ATTACHMENT VENT TIME ATTACHMENI'CS ISOLATION ATTACHMENT RESTORING PEED PLOW EFFECT DATE 002 07/26/94 02/10/98 02/10/03 EF 002 04/07/97 10/19/94 10/19/99 EP 004 05/01/98 05/01/98 05/01/03 EP 001 07/26/94 02/10/98 02/10/03 EP 002 08/01/97 01/06/99 01/06/04 EF 001'7/26/94 01/06/99 01/06/04 EF 002 07/26/94 02/10/98 001 01/14/99 01/14/99 02/10/03 EF 01/14/04 EF 005 05/22/97 04/20/95 04/20/00 EF 003 04/24/97 02/10/98 02/10/03 EP 003 05/22/97 02/10/98 02/10/03 EF 008 03/17/98 11/08/94 11/08/99 EF 006 11/03/95 02/03/95 02/03/00 EP 005 09/26/96 01/26/94 01/26/99 EP 004 10/08/97 02/10/98 02/10/03 EF 003 07/26/94 02/10/98 02/10/03 EF 001 07/26/94 02/10/98 02/10/03 EF 000 03/24/97 03/24/97 03/24/02 EF TOTAL FOR PRATI'2
EOP:
AP-RHR.1 T1TLE:
~ LOSS OF RHR REV:
13 PAGE 1 of 13 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER tg RESPONSIBLE'GER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:
EOP:
AP-RHR.1 TITLE:
LOSS OF RHR REV:'13 PAGE 2 of 13 A.
PURPOSE This procedure provides guidance in the event of a loss of RHR cooling at or above normal loop levels.
(i.e.
RCS loop levels of 64 inches or greater)
B.
ENTRY CONDITIONS/SYMPTOMS 1.
ENTRY CONDITIONS This procedure is entered from; a.
FR-C.3,
RESPONSE
TO SATURATED CORE COOLING, or b.
AP-ELEC.3, LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350'F),
when RHR flow can NOT be restored, or c.
AP-CCW.3, LOSS OF CCW PLANT SHUTDOWN when CCW is inadequate for RHR cooling 2.
SYMPTOMS The fo11owing are symptoms of LOSS OF RHR; a.
No RHR pumps running, or b.
Annunciator A-20, RESIDUAL HEAT REMOVAL LOOP LO FLOW 2900 GPM (Set at 400 GPM per 0-2.2 in RHR Cooling mode), lit, or c.
Unexpected increase in temperature while on RHR cooling, or d.
Erratic or no flow on FI-626, RHR Loop Flow, or e.
Annunciator J-9, SAFEGUARD BREAKER TRIP, lit.
EOP:
I AP-RHR.1 TITLE:
LOSS OF RHR REV:
13 PAGE 3 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
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CAUTION DO NOT START ANOTHER RHR PUMP UNTIL THE CAUSE OF THE ABNORMAL RHR INDICATIONS HAS BEEN DETERMINED.
IF A RUNNING PUMP HAS TRIPPED FOR REASONS OTHER THAN LOSS OF SUCTION FLOW, THEN REDUNDANT PUMP MAY BE STARTED.
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NOTE:
Conditions should be evaluated for site contingency reporting (Refer to EPIP-1.0, GINNA STATION EVENT EVALUATION AND CLASSIFICATION).
1 Check PRZR Wide Range Level GREATER THAN 0 INCHES IF RCS loop level indicator in service and loop level less than 64 inches, THEN go to AP-RHR.2.
LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.
EGP:
AP-RHR.1 TITLE:
LOSS OF RHR REV:
13 PAGE 4 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 2 Check If RHR Pump(s)
Should Be Stopped:
a.
RHR pump ANY RUNNING b.
Check RHR pump flow - LESS THAN 1500 GPM PER PUMP c.
RHR pumps cavitating:
o RHR pump flow - OSCILLATING
-OR-a.
Go to Step 3.
- b. Decrease RHR flow as necessary.
IF RHR flow can NOT be controlled.
THEN perform the following:
- 1) Stop running RHR pump.
- 2) Dispatch an AO with a locked valve key to locally throttle RHR Hx outlet manual valves to approximately half open.
~ V-715.
B RHR Hx
~ V-717, A RHR Hx
- 3) Start an RHR pump.
c.
Go to Step 17.
- APPROXIMATELY ZERO (PPCS group GD NPSH)
- d. Stop RHR pumps
EOP:
AP-RHR.l TITLE:
LOSS OF RHR REV.:
13 PAGE 5 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED
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CAUTION o
DO NOT INITIATE ANY ACTIONS WHICH MAY ADD POSITIVE REACTIVITY TO THE CORE.
o NOTIFY S/G OFFICE THAT CNMT BREATHING AIR MAY BE LOST.
h o
IF REFUELING IN PROGRESS, SRO).
THEN STOP REFUELING OPERATIONS (NOTIFY REFUELING
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NOTE:
Personnel remaining in CNMT to assist in event mitigation should consult Health Physics for changes in radiological concerns.
3 Initiate Actions To Protect Personnel In CNMT:
- a. Evacuate 'non-essential personnel from CNMT
- b. Verify all available CNMT RECIRC fan(s)
- RUNNING
- c. Initiate monitoring of CNMT area and process radiation monitors
- b. Manually start available CNMT RECIRC fans.
- c. Refer to appropriate alarm response procedures for required actions.
- d. Verify CNMT penetrations with direct access to outside atmosphere CLOSED (Refer to Attachment CNMT CLOSURE)
- d. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
close all CNMT penetrations to outside atmosphere.
EOP:f AP-RHR. 1 TITLE:
LOSS OF RHR REV:
13 PAGE 6 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 4 Check RHR Cooling Valve Alignment NORMAL (Refer to Attachment NORMAL RHR COOLING)
Manually or locally align valves as necessary.
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CAUTION THE RHR HX OUTLET VALVES (HCV-624 AND HCV-625) WILL FAIL OPEN ON LOSS OF INSTRUMENT AIR PRESSURE.
5 Check IA System:
- a. Verify 2 IA compressors
- RUNNING b.
Check IA supply o
Pressure GREATER THAN 60 PSIG o
Pressure STABLE OR INCREASING
- a. Manually start IA compressors as necessary (75 kw each).
IF IA compressors can NOT be started
- manually, THEN dispatch AO to locally reset and start compressors (75 kw each).
- b. IF IA pressure can NOT be restored.
THEN perform the following:
- 1) Dispatch AO with a locked valve key to locally throttle RHR Hx outlet manual valves to approximately half open.
~ V-715.
B RHR Hx
~ V-717.
A RHR Hx 2)
WHEN conditions permit.
THEN refer to AP-IA.1, LOSS OF INSTRUMENT AIR, to restore IA.
EOP:
AP-RHR.l TITLE:
LOSS OF RHR REV:
13 PAGE 7 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED I
- 6 Monitor RCS Temperature GREATER THAN 200 F
Go to Step 8.
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CAUTION o
CHANGES IN RCS PRESSURE COULD RESULT IN INACCURACIES IN RCS LOOP LEVEL INDICATION o
UNSTABLE OR FLUCTUATING LEVEL INSTRUMENTS SHOULD NOT BE RELIED ON FOR INDICATION OF RCS INVENTORY.
7 Verify RCS Intact:
o PRZR level GREATER THAN 5'/. AND STABLE o
RCS pressure STABLE o
RCS subcooling based on core exit T/Cs GREATER THAN O' USING FIGURE MIN SUBCOOLING o
RCS vent. paths CLOSED Perform the following:
- a. Verify charging line flow control valve.
HCV-142.
open as necessary.
- b. Ensure charging line valve to loop B cold leg.
AOV-294, open.
- c. Start charging pumps as necessary.
- d. Control charging pump speed and letdown flow as necessary to stabilize RCS conditions.
~
PRZR pressure
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PRZR level
~ Loop level IF charging flow greater than 75 gpm with letdown isolated OR unable to verify RCS inventory.
THEN go to AP-RCS.4, SHUTDOWN LOCA.
EOP:
AP-RHR. 1 TITLE:
LOSS OF RHR REV:
13 PAGE 8 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 8 Establish Conditions To Start RHR Pump:
a.
RHR pump
.- AVAILABLE
CCW pumps
- AT LEAST ONE RUNNING o
CCW to RHR Hxs, MOV-738A AND MOV-738B -
OPEN AS NECESSARY
- c. Close RHR pump flow control valves (controllers at 1001.
demand)
~ HCV-624
~ HCV-625 a.
Perform the following:
- 1) Start trending core exit TCs.
- 2) IF RCS closed, THEN go to Step 10.
IF RCS open to atmosphere.
THEN. go to Step 16.
- b. Perform the following:
- 1) Ensure at least one CCW pump running.
I 2)
Open MOV-738A and MOV-738B as necessary.
IF CCW can NOT be restored.
~T EN continue with Step 9 while attempting to restore CCW (Refer to AP-CCW.3.
LOSS OF CCW -
PLANT SHUTDOWN).
- d. Place RHR Hx bypass valve, HCV-626, to MANUAL and close valve
EOP:
AP-RHR.1 TITLE:
LOSS OF RHR REV:
13 PAGE 9 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED I
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CAUTION STARTING AN RHR PUMP MAY RESULT IN AN RCS LEVEL OR PRESSURE DECREASE DUE TO SHRINK OR VOID COLLAPSE.
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9 Restore RHR Flow:
Go to Step 9e.
b.
Check RHR flow - LESS THAN 1500 GPM PER PUMP
- c. Adjust RHR Hx bypass flow control valve.
HCV-626, to desired flowrate
- b. Manually adjust RHR flow as necessary.
- d. Place RHR Hx bypass flow control
- valve, HCV-626. controller in AUTO e.
RHR flow -
RESTORED
~ HCV-624
~ HCV-625
- e. Perform the following:
- 1) Start trending core exit T/Cs.
- 2) IF RCS closed, THEN go to Step 10.
IF RCS vented to atmosphere,
~HEN go to Step 16.
EOP:
I AP-RHR.1 TITLE:
LOSS OF RHR REV:
13 PAGE 10 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 10 Monitor RCS Temperature:
a.
RCS temperature
- STABLE OR DECREASING b.
Go to Step 19
- a. IF RCS closed.
THEN go to Step ll.
IF RCS open to atmosphere,
-THEN go to Step 16.
11 Check Any S/G Level GREATER THAN 17%
Verify at least 200 gpm AFW flow available.
IF NOT, THEN go to Step 17.
12 Check RCS Pressure GREATER THAN 300 PSIG Increase RCS pressure to greater than 300 psig.
IF RCS pressure can NOT be increased, THEN go to Step,17.
13 Check RCP Status ANY RCP RUNNING Perform the followig:
- a. Establish conditions for starting an RCP.
o Verify bus 11A or llB energized.
o Refer to Attachment RCP START.
- b. Start one RCP.
IF an RCP can NOT be started, THEN verify natural circulation.
(Refer to Attachment NC.)
IF natural circulation NOT
- verified, THEN increase dumping steam.
EOP:
AP-RHR.l TITLE:
LOSS OF RHR REV:
13 PAGE 11 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 14 Establish Condenser Steam Dump Manual Control:
- a. Verify condenser available:
o Any MSIV -
OPEN o
Annunciator G-15, STEAM DUMP ARMED - LIT a.
Perform the following:
- b. Place condenser steam dump controller HC-484 in MANUAL 2)
Go to Step 15 Place steam dump mode selector switch to MANUAL'.
Open steam dump valves as necessary to stabilize RCS temperature 1S Monitor RCS Temperature:
a.
RCS temperature STABLE OR DECREASING a
~ IF dumping steam does NOT provide adequate
- cooling, THEN.
perform the following:
- 1) Initiate S/G blowdown from both S/Gs.
- 2) Maintain both S/G levels stable by controlling AFW flow.
3)
Go to Step 17.
b.
Go to Step 18
EGP:
C AP-RHR.1 LOSS OF RHR REV:
13 PAGE 12 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED 16 Check RCS Conditions:
a.
Rx vessel head REMOVED
- b. Stop refueling operations if in progress cd Verify Refueling Cavity Level-GREATER THAN 23 FEET ABOVE VESSEL FLANGE
- d. Verify refueling cavity sweep fans RUNNING a.
Go to Step 17.
- c. Increase refueling cavity level to greater than 23 feet (Refer to 0-15.3, FILLlNG REFUELING CAWAL).
- d. Locally start refueling cavity sweep fans if available.
17 Check CCW System Operation:
o CCW pumps
- AT LEAST ONE RUNNING o
MOV-738A AND MOV-738B -
OPEN AS NECESSARY o
Annunciator A-21.
COMP COOLING HX OUT HI TEMP
- EXTINGUISHED o
Annunciator A-22.
- EXTINGUISHED o
Annunciator A-30.
- EXTINGUISHED To restore CCW cooling to RHR Hxs, perform the following:
a.
Ensure the standby CCW pump is running.
b.
Open MOV-738A and MOV-738B as necessary.
IF CCW can NOT be restored, THEN continue attempts to restore CCW (Refer to AP-CCW.3, LOSS OF CCW-PLANT SHUTDOWN).
H
EOP:
AP-RHR.1 TITLE:
LOSS OF RHR REV:
13 PAGE 13 of 13 STEP ACTION/EXPECTED RESPONSE
RESPONSE
NOT OBTAINED NOTE:
Consult with Plant Staff to determine alternatives for long term cooling.
18 Monitor RHR Cooling:
o RHR cooling RESTORED o
RCS temperature
- STABLE OR DECREASING Perform the following:
- a. Evaluate alternatives for long term cooling (Consult Plant Staff)
~ Consider establishing secondary heat sink
~ Refer to ER-RHR.1.
RCDT PUMP OPERATION FOR CORE COOLING
~ Consider RCS feed and bleed NOTE:
- c. Return to Step 3.
Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION. for reporting requirements.
19 Notify Higher Supervision 20 Return to Procedure Or Guidance Xn Effect I'END-
EOP:
AP-RHR. 1 TITLE:
LOSS OF RHR REV:
13 PAGE 1 of 1
AP-RHR.1 APPENDIX LIST TITLE 1)
FIGURE MIN SUBCOOLING (PIG-1. 0) 2)
ATTACHMENT NORMAL RHR COOLING (ATT-14.0) 3)
ATTACHMENT RCP START (ATT-15.0) 4)
ATTACHMENT NC (ATT-13.0) 5)
ATTACHMENT CNMT CLOSURE
'(ATT-3. 1)
EOP:
ATT-3.0 ATTACHMENT CI/CVI REV:
5 PAGE 1 of 3 Responsible Manager NOTE:
Locked valve key may be required for local operations.
AUTO ISOL VALVE AOV-200A AOV-200B AOV-202 AOV-5392 AOV-371 MOV-313 AOV-9227 AOV-508 AOV-5738 AOV-5737 AOV-5735 AOV-573 6 SOV-921 SOV-922 SOV-923 SOV-924 AOV-539 AOV-1789 AOV-1786 AOV-1787 ALTERNATE ISOL AOV-371/133 AOV-371/133 AOV-371/133 V-5397/5410 V-204A/820 V-315A/315C V-9225 AOV-548/550A/550B V-5701 V-5702 V-5733 V-5734 V-928A V-928B V-929A V-929B V-546 V-1655 AOV-1787 AOV-1786 ALTERNATE ISOL LOCATION MCB MCB MCB IB BASEMENT CLEAN SIDE NRHX ROOM (locked area)
SWRF ROOM (reach rods)
IB BASEMENT CLEAN SIDE MCB IB BASEMENT CLEAN SIDE IB BASEMENT CLEAN SIDE SAMPLE HOOD SAMPLE HOOD INSIDE A H2 MON PNL (AFW PUMP AREA)(key 59)
INSIDE A H2 MON PNL (AFW PUMP AREA)(key 59)
INSIDE B H2 MON PNL (AFW PUMP AREA)(key 59)
INSIDE B H2 MON PNL (AFW PUMP AREA) (key 59)
BY SFP HX BY SFP HX MCB MCB (1) does not receive Auto closure signal on CI
EOP:
ATT-3.0 TITLE:
ATTACHMENT CI/CVI REV:
5 PAGE 2 of 3 AUTO ISOL VALVE AOV-1721 AOV-1003A AOV-1003B AOV-1597 AOV-1598 AOV-1599 MOV-813 MOV-814 l2)
AOV-1723 l2)
AOV-1728 AOV-951 AOV-953 AOV-955 AOV-959 AOV-966A AOV-966B AOV-966C AOV-846 AOV-8418 AOV-7971 AOV-7970 ALTERNATE ISOL AOV-1003A/1003B/1722 AOV-1721 AOV-1721 V-1596 AOV-1599 AOV-1598 12)
MOV-817 V-815A AOV-1728 AOV-1723 AOV-966A AOV-966B AOV-966C V-957 V-956F V-956E V-956D V-8629/944A V-5021 AOV-7970 AOV-7971 ALTERNATE ISOL LOCATION WASTE DISPOSAL PANEL/AB SUB-BASEMENT WASTE DISPOSAL PANEL WASTE DISPOSAL PANEL IB BASEMENT CLEAN SIDE MCB MCB MCB AB INT LEVEL WASTE DISPOSAL PANEL WASTE DISPOSAL PANEL MCB MCB MCB PRIMARY SAMPLE ROOM SAMPLE HOOD SAMPLE HOOD SAMPLE HOOD BY SFP HX IB BASEMENT CLEAN SIDE MCB REAR MCB REAR (2)
AC power normally off (3)
Place CNMT sump pumps in pull-stop
EOP:
ATT-3.0 TITLE:
ATTACHMENT CI/CVI REV 5
PAGE 3 of 3 AUTO ISOL VALVE AOV-7445 AOV-7478 PEVO-5879 PSVO-5869 l4)
SOV-1B (10214S1) l4)
SOV-2B (10214 S) l4)
SOV-3B (10211S1) l4)
SOV-5B (10213S1) l4)
SOV-1A (10215S1) l4)
SOV-2A (10215S) l4)
SOV-3A (10205S1) l4)
SOV-5A (10209S1)
ALTERNATE ISOL AOV-7478 AOV-7445 N/A FLANGED N/A FLANGED V-1080A V-1080A V-1076B V-1084B V-1080A V-1080A V-1076A V-1084A ALTERNATE XSOL LOCATION MCB REAR MCB REAR SAMPLE HOOD SAMPLE HOOD SAMPLE HOOD SAMPLE HOOD SAMPLE HOOD SAMPLE HOOD IB BASEMENT CLEAN SIDE IB BASEMENT CLEAN SIDE (4)
Valves normally deenergized with manual isolation valve locked closed.
EOP~:
ATT-3.1 ATTACHMENT CNMT CLOSURE REV:
3 PAGE 1 of 2 Responsible Manager Date
/ AS+
A)
Ensure at least one door closed in EACH CNMT airlock:
o Equipment airlock o
Personnel airlock B)
Verify valves in column 1 closed.
IF any valve NOT
- closed, THEN evaluate penetration and isolate as necessary (Refer to column 2).
NOTE:
Locked valve key may be required for local operation.
COLUMN 1 AUTO ISOL VALVE AOV-5392 (IA)
AOV-371 (L/D)
MOV-313 (RCP Seal)
AOV-9227 (Fire Sys)
AOV-508 (DI Water)
AOV-5738 (S/G B/D)
AOV-5737 (S/G B/D)
AOV-5735 (S/G samp)
AOV-5736 (S/G samp)
AOV-539 (PRT gas)
AOV-1789 (RCDT to gas anal)
COLUMN 2 ALTERNATE ISOL V-5397/5410 V-204A/820 V-315A/315C V-9225 AOV-548/550A/550B V-5701 V-5702 V-5733 v-5734 V-54 6 V-1655 ALTERNATE ISOL LOCATION IB CLEAN BSMT NRHX ROOM (locked area)
SWRF ROOM (reach rods)
IB CLEAN BSMT MCB IB CLEAN BSMT IB CLEAN BSMT SAMPLE HOOD SAMPLE HOOD BY SFP HX BY SFP HX AOV-1786 (RCDT/VH)
AOV-1721 (RCDT pumps)
AOV-1787 (V-1716A)
BY'FP HX AOV-1003A/1003B/1722 WASTE PANEL/AB SUB-BASEMENT AOV-1597 (CNMT rad)
AOV-1598 (CNMT rad)
MOV-813 (CCW)
V-1596 AOV-1599 CCW SYSTEM INTACT IB CLEAN BSMT MCB AUX BLDG INT (BY RWST)
EOP.
ATT-3.1 TITLE:
ATTACHMENT CNMT CLOSURE REV:
3 PAGE 2 of 2 COLUMN 1 AUTO ISOL VALVE COLUMN 2 ALTERNATE ISOL ALTERNATE ISOL LOC TION MOV-814 (CCW)
AOV-846 (ACCUM N2)
AOV-8418 (DI water)
AOV-7970 (Mini purge)
AOV-7445 (Mini purge)
AOV-5879 (Purge)
AOV-5869 (Purge)
CCW SYSTEM INTACT AOV-1728 V-8629/944A V-5021 AOV-7971 AOV-7478 Purge Exhaust Fan OFF Purge Supply Fan OFF AUX BLDG INT (BY RWST)
.WASTE PANEL BY SFP HX IB CLEAN BSMT MCB REAR MCB REAR C)
Verify both S/Gs intact in CNMT OR steam and feed headers isolated outside CNMT (Refer to 0-15.2, REQUIRED VALVE LINEUP FOR REACTOR HEAD REMOVAL, for specific guidance).
D)
Evaluate and isolate'ny other known openings from CNMT to the outside atmosphere.
Contact Outage Coordinator or Maintenance Manager and refer to 0-2.3.1A, CONTAINMENT CLOSURE CAPABILITY IN TWO HOURS DURING REDUCED RCS INVENTORY OPERATION, for add-itional guidance.'
E)
Verify fuel transfer flange installed or gate valve, V-650J, closed.
F)
Contact S/G office to ensure that S/G maintenance penetration is isolated (no openings to outside).