ML17309A648

Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr

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) 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 VISSING,G.S.

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 COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-1 PD 1 VISSING,G. 1 1 INTERNAL E CE ER 01 1 1 NRR/DSSA/SRXB 1 1 RES DE 1 1 RES/DET/EIB 1 1 RES/DSZR/RPSB 1 1 I

EXTERNAL: NOAC NRC PDR 1 1 D

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WASTETH NOTE TO ALL "RZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE 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

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ROCHESTER GAS AND ELECTRIC CORPORATION  % 89EASTA VENUE, ROCHESTER, N.Y. 14649%001 JOSEPH A. WIDAY TELEPHONE Plant Manager AREA CODE 716 546-2700 Ginna Nuclear Plant 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 PDR

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 01/25/99 PAGB: 1 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES PRAP STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EFFECT IAST NUMBER PROCBDURE TITLE DATE REVIEW AP-CCW. 1 LEAKAGE INTO THB COMPONENT COOLING LOOP 013 10/30/98 05/01/98 05/01/03 EP AP-CCW. 2 LOSS OF CCW DURING POWER OPERATION 012 02/24/96 08/30I94 08I30/99 EF AP-CCW. 3 LOSS OP CCW PLANT SHUIDOWN 010 03/29/96 08/30/94 08/30/99 EF AP-CR. 1 CONIROL ROOM INACCESSIBILITY 015 01/26/98 11/17/94 11/17/99 EF AP-CVCS. 1 CVCS LEAK 012 OS/01/98 05/01/98 05/01/03 EF AP-CW. 1 LOSS OP A CIRC WATBR PUMP 010 07/16/98 05/01/98 05/01/03 EF

, AP-ELEC.l LOSS OP 12A AND/OR 12B BUSSES 016 05/01/98 05/01/98 05/01/03 EF AP-ELEC. 2 SAPEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 008 01/26/98 02/11/94 02/11/99 EF AP-ELEC. 3 IDES OP 12A AND/OR 12B TRANSFORMER tBBLOW 350 F) 005 05/01/98 05/01/98 05/01/03 EF AP ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 000 06/09/97 06/09/97 06/09/02 EF AP-ELEC.X7/18 LOSS OP SAFEGUMUK BUS 1'7/18 001 02/27/98 06/09/9'l 06/09/02 EP AP-FW. 1 PARTIAL OR COMPLETE LOSS OP MAIN PEEDWATER 011 02/27/98 02/27/98 02/27/03 EF AP-IA. 1 LOSS OP INSTRUMENT AIR 015 05/01/98 05/01/98 05/01/03 EP AP- PRZR. 1 ABNORMAL PRBSSURIZBR PRESSURE 009 06/03/96 09/29/94 09/29/99 EF AP RCC.1 CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION 006 02/24/96 05/14/98 05/14/03 EF AP-RCC. 2 RCC/RPI MALFUNCTION 008 11/16/98 02/06/97 02/06/02 EF AP-RCC.3 DROPPED ROD RECOVERY 004 11/16/98 02/27/98 02/27/03 EF AP-RCP. 1 RCP SEAL MALFUNCTION 012 05/01/98 05/01/98 05/01/03 EP AP-RCS. 1 REACTOR COOLANT LEAK 013 05/01/98 05/01/98 05/01/03 EF AP-RCS. 2 LOSS OP REACTOR COOLANT PLOW 010 12/14/98 05/01/98 05/01/03 EF AP-RCS. 3 'HIGH REACTOR COOLANT ACTIVITY 007 08/05/97 08/05/97 08/05/02 EP AP-RCS.4 SHUTDOWN LOCA 009 05/01/98 05/01/98 05/01/03 EF AP RHR.1 LOSS OF RHR 013 01/25/99 05/01/98 05/01/03 BF AP-RHR.2 LOSS OF RHR WHILB OPERATING AT RCS REDUCED INVENTORY CONDITIONS 007 05/15/97 03/21/95 03/21/00 EF

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 01/25/99 PAGE: 2 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRAP STATUS: EP QU 5 YEARS ONLY:

PROCEDURE EFFECT NEXT NUMBER PROCEDURE TITLE DATE REVIEW ST AP SW.l SERVICE NATER LEAK 014 01/14/99 06/03/98 06/03/03 EP AP- TURB. 1 TURBINE TRIP NITHOUI'X TRIP REQUIRED 009 10/10/97 10/10/97 10/10/02 EF AP TURB.2 TURBINE LOAD REJECTION 016 02/27/98 05/13/98 05/13/03 EF AP-TURB.3 TURBINE VIBRATION 008 12/04/96 02/10/98 02/10/03 EF LOSS OP CONDENSER VACUUM 014 05/01/98 05/01/98 05/01/03 EF AP-TURB. 5 RAPID LOAD REDUCTION 003 02/27/98 07/10/95 07/10/00 EF TOTAL FOR PRAP 30

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 01/25/99 PAGB: 3 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRATT EOP ATTACHMENTS i

PARAMETERS: DOC TYPES - PRAP STATUS: EP QU 5 YEARS ONLY:

PROCEDURE EFFECT NUMBER PROCEDURB TITLE REV DATB ATT-l.0 ATTACHMENT AT POWER CCW ALIGNMENT 001 07/26/94 02/10/98 02/10/03 BF ATT-2. 1 ATTACHMENT MIN SW 004 06/26/98 02/10/98 02/10/03 EF AIT-2.2 ATTACHMENT SW ISOLATION 005 10/30/98 08/11/98 08/11/03 EP ATI-2.3 ATTACHMENT SW LOADS IN 003 01/25/95 01/25/95 01/25/00 EP CNMI'TTACHMENT ATT-3. 0 CI/CVI 005 01/25/99 01/06/99 01/06/04 EF ATI'-3. 1 ATTACHMENT CNMT CLOSURE 003 01/25/99 02/11/94 02/11/99 EP ATT-4. 0 ATTACHHENT CNMT RECIRC PANS 003 07/26/94 05/13/98 05/13/03 EP ATI'-5. 0 ATTACHMENT COND TO S/G 004 01/25/95 01/25/95 01/25/00 EF ATI'-5. 1 ATTACHMENT SAFW 006 07/07/98 11/08/94 11/08/99 EF ATT-5. 2 ATTACHMENT PIRB WATER COOLING TO 'IDAFW PUMP 003 01/14/99 01/14/99 01/14/04 EF ATT 6.0 ATTACHMENT COND VACUUM 003 12/18/96 02/10/98 02/10/03 EF ATT 7.0 ATTACHMENT CR EVAC 004 05/04/98 02/10/98 02/10/03 . EP ATT-8. 0 ATTACHMENT DC LOADS 005 01/14/99 01/14/99 01/14/04 EP ATT 8.1 ATTACHMENT D/G STOP 004 11/03/95 02/10/98 02/10/03 EF ATT-8. 2 ATTACHMENT GEN DEGAS 005 07/26/94 02/11/94 02/11/99 EP ATT-8.3 ATTACHMENI'ONVITAL 003 07/26/94 02/10/98, 02/10/03 EP ATT-8.4 ATTACHMENT SI/UV 004 04/24/97 02/10/98 02/10/03 BF ATT-9. 0 ATTACHMENT LETDOWN 006 04/07/97 01/06/99 01/06/04 EF ATT-9. 1 ATTACHMENT EXCESS L/D 002 07/26/94 02/10/98 02/10/03 EP ATT-10.0 ATTACHMENT FAULTED S/G 005 10/03/96 05/13/98 05/13/03 EF ATT-11.0 ATTACHMENT Ih CONCERNS 002 04/07/97 08/11/98 08/11/03 EF ATT-11.1 ATTACHMENT IA SUPPLY 002 04/07/97 08/11/98 08/11/03 EF ATT-11.2 ATTACHMENT DIESEL AIR COMPRESSOR 000 04/03/98 04/03/98 04/03/03 EP ATT-12.0 ATTACHMENT N2 PORVS 003 03/24/97 02/10/98 02/10/03 EF

REPORT NO. 01 REPORT: NPSP0200 DOC TYPE: PRATT "GINNA ~ POWER PLANT PROCEDURES EOP ATTACHMENTS INDEX 01/25/99 PAGE: 4 PARAMETERS: DOC TYPES - PRAP STATUS: EP QU 5 YEARS ONLY:

PROCEDURE EFFECT NUMBER PROCEDURE TITLE DATE ATT 13.0 ATTACHMENT NC 002 07/26/94 02/10/98 02/10/03 EF ATI'4.0 ATTACHMENT NORMAL RHR COOLING 002 04/07/97 10/19/94 10/19/99 EP ATI'-l4.1 ATTACHMENT RHR COOL 004 05/01/98 05/01/98 05/01/03 EP ATT-14.2 ATTACHMENT RHR ISOL 001 07/26/94 02/10/98 02/10/03 EP ATT-li. 3 ATTACHMENT RHR NPSH 002 08/01/97 01/06/99 01/06/04 EF ATI'4.4 ATTACHMENT RHR SAMPLE 001'7/26/94 01/06/99 01/06/04 EF ATT 14 ~ 5 ATTACHMENT RHR SYSTEM 002 07/26/94 02/10/98 02/10/03 EF ATT-14.6 ATTACHMENT RHR PRESS REDUCTION 001 01/14/99 01/14/99 01/14/04 EF ATT-15.0 ATTACHMENT RCP START 005 05/22/97 04/20/95 04/20/00 EF ATT-15.1 ATTACHMENT RCP DIAGNOSTICS 003 04/24/97 02/10/98 02/10/03 EP ATT-15.2 ATTACHMENI'EALCOOLING 003 05/22/97 02/10/98 02/10/03 EF ATT-16.0 ATTACHMENT RUPTURED S/G 008 03/17/98 11/08/94 11/08/99 EF ATT 17.0 ATTACHMENT SD-1 006 11/03/95 02/03/95 02/03/00 EP ATT 17.1 ATTACHMENT SD-2 005 09/26/96 01/26/94 01/26/99 EP ATT-18. 0 ATTACHMENT SFP - RWST 004 10/08/97 02/10/98 02/10/03 EF ATT-20.0 ATTACHMENT VENT TIME 003 07/26/94 02/10/98 02/10/03 EF ATT 21.0 ATTACHMENI'CS ISOLATION 001 07/26/94 02/10/98 02/10/03 EF ATT-22.0 ATTACHMENT RESTORING PEED PLOW 000 03/24/97 03/24/97 03/24/02 EF TOTAL FOR PRATI'2

EOP: T1TLE:

REV: 13 AP-RHR.1 ~

LOSS OF RHR 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:  ! TITLE:

REV:'13 AP-RHR.1 LOSS OF RHR 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 TITLE:

REV: 13 AP-RHR.1 LOSS OF RHR PAGE 3 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

~ I ~ ~ ~ I I ~ ~ ~ ~ I I I ~ I ~ ~ ~ ~ ~ I I ~ ~ I ~ ~ I ~ I I I ~ ~ 0 I I ~ I ~

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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• I I ~ I I

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• I I ~ I ~ I ~ ~ I ~ I ~ ~ ~ ~ ~ ~ ~ ~ I ~

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 IF RCS loop level indicator in GREATER THAN 0 INCHES 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:  ! TITLE:

REV: 13 AP-RHR.1 LOSS OF RHR PAGE 4 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 Check Be If RHR Stopped:

Pump(s) Should

a. RHR pump - ANY RUNNING a. Go to Step 3.

b. Check RHR pump flow - LESS THAN b. Decrease RHR flow as necessary.

1500 GPM PER PUMP 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.

4) Direct AO to locally adjust RHR flow to less than 1500 gpm.

c. RHR pumps cavitating: c. Go to Step 17.

o RHR pump flow - OSCILLATING

-OR-o RHR pump NPSH - APPROXIMATELY ZERO (PPCS group GD NPSH)

d. Stop RHR pumps

EOP:  ! TITLE:

REV.: 13 AP-RHR.l LOSS OF RHR PAGE 5 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

/ t

~ ~ ~ ~ ~ ~ 4 ~ 1 I ~ ~ 0 ~ ~ 1 ~ ~ ~ ~ ~ ~

• 1 ~ 4 4 ~ ~ ~ 1 4 ~ ~ ~ 0 ~ ~ ~ ~

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, THEN STOP REFUELING OPERATIONS (NOTIFY REFUELING SRO).

~ i 1 ~ 0 ~ ~ ~ 1 0 t ~ ~ ~ ~ ~ ~ 0 1 ~ 1 ~ 1 1 ~ 0 ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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 b. Manually start available CNMT fan(s) RUNNING RECIRC fans.

c. Initiate monitoring of CNMT area c. Refer to appropriate alarm and process radiation monitors . response procedures for required actions.

d. Verify CNMT penetrations with 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 direct access to outside penetrations to outside atmosphere - CLOSED (Refer to atmosphere.

Attachment CNMT CLOSURE)

EOP: TITLE:

f REV: 13 AP-RHR. 1 LOSS OF RHR PAGE 6 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 Check RHR Cooling Valve Manually or locally align valves as Alignment NORMAL (Refer to necessary.

Attachment NORMAL RHR COOLING)

~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ 4 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ 1 1 1 ~ ~ 4 ~ 0 0 4 ~ ~ 1 ~

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 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. Check IA supply b. IF IA pressure can NOT be restored. THEN perform the o Pressure - GREATER THAN following:

60 PSIG

1) Dispatch AO with a locked o Pressure - STABLE OR valve key to locally throttle INCREASING 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: TITLE:

REV: 13 AP-RHR.l LOSS OF RHR PAGE 7 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I

• 6 Monitor RCS Temperature Go to Step 8.

GREATER THAN 200 F

~ ~ ~ ~ ~ ~ 0 1 ~ 0 1 0 ~ ~ 1 4 ~ ~ I ~ 4 ~ ~ ~ ~ 4 ~ ~ ~ ~ ~ ~ ~ t 0 ~ ~ ~ 0 ~

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: Perform the following:

o PRZR level - GREATER THAN 5'/. AND a. Verify charging line flow STABLE control valve. HCV-142. open as necessary.

o RCS pressure - STABLE

b. Ensure charging line valve to o RCS subcooling based on core loop B cold leg. AOV-294, open.

exit T/Cs - GREATER THAN O' USING FIGURE MIN SUBCOOLING c. Start charging pumps as necessary.

o RCS vent. paths - CLOSED

d. Control charging pump speed and letdown flow as necessary to stabilize RCS conditions.

~ PRZR pressure

~ 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: TITLE:

REV: 13 AP-RHR. 1 LOSS OF RHR PAGE 8 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Establish Conditions To Start RHR Pump:

a. RHR pump .- AVAILABLE 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. Verify CCW cooling to RHR system b. Perform the following:

in service

1) Ensure at least one CCW pump o CCW pumps - AT LEAST ONE running.

I RUNNING

2) Open MOV-738A and MOV-738B as o CCW to RHR Hxs, MOV-738A AND necessary.

MOV-738B - OPEN 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).

c. Close RHR pump flow control valves (controllers at 1001.

demand)

~ HCV-624

~ HCV-625

d. Place RHR Hx bypass valve, HCV-626, to MANUAL and close valve

EOP:  ! TITLE:

REV: 13 AP-RHR.1 LOSS OF RHR PAGE 9 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I ~ ~ I ~ 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:

a. Start one RHR pump - RHR PUMP a. Go to Step 9e.

RUNNING

b. Check RHR flow - LESS THAN b. Manually adjust RHR flow as 1500 GPM PER PUMP necessary.

c. Adjust RHR Hx bypass flow control valve. HCV-626, to desired flowrate

d. Place RHR Hx bypass flow control valve, HCV-626. controller in AUTO

e. RHR flow - RESTORED 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.

f. Open RHR Hx outlet valves'as necessary to control RCS temperature .

~ HCV-624

~ HCV-625

EOP: I TITLE:

REV: 13 AP-RHR.1 LOSS OF RHR PAGE 10 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Monitor RCS Temperature:

a. RCS temperature - STABLE OR a. IF RCS closed. THEN go to DECREASING Step ll. IF RCS open to atmosphere, -THEN go to Step 16.

b. Go to Step 19 11 Check Any S/G Level GREATER Verify at least 200 gpm AFW flow THAN 17% available. IF NOT, THEN go to Step 17.

12 Check RCS Pressure GREATER Increase RCS pressure to greater THAN 300 PSIG than 300 psig. IF RCS pressure can NOT be increased, THEN go to Step,17.

13 Check RCP Status ANY RCP Perform the followig:

RUNNING

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: TITLE:

REV: 13 AP-RHR.l LOSS OF RHR PAGE 11 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Establish Condenser Steam Dump Manual Control:

a. Verify condenser available: a. Perform the following:

o Any MSIV - OPEN 1) Place S/G ARV controller in MANUAL and open ARVs as o Annunciator G-15, STEAM DUMP necessary to stabilize RCS ARMED - LIT temperature.

2) Go to Step 15

b. Place condenser steam dump controller HC-484 in MANUAL 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 a ~ IF dumping steam does NOT DECREASING 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 REV: 13 AP-RHR.1 LOSS OF RHR PAGE 12 of 13 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check RCS Conditions:

a. Rx vessel head - REMOVED a. Go to Step 17.

b. Stop refueling operations if in progress cd Verify Refueling Cavity Level- c. Increase refueling cavity level GREATER THAN 23 FEET ABOVE to greater than 23 feet (Refer VESSEL FLANGE to 0-15.3, FILLlNG REFUELING CAWAL).

d. Verify refueling cavity sweep d. Locally start refueling cavity fans - RUNNING sweep fans if available.

17 Check CCW System Operation: To restore CCW cooling to RHR Hxs, perform the following:

o CCW pumps - AT LEAST ONE RUNNING

a. Ensure the standby CCW pump is o CCW to RHR Hxs. MOV-738A AND running.

MOV-738B - OPEN AS NECESSARY

b. Open MOV-738A and MOV-738B as o Annunciator A-21. COMP COOLING necessary.

HX OUT HI TEMP - EXTINGUISHED IF CCW can NOT be restored, THEN o Annunciator A-22. CCW PUMP continue attempts to restore CCW DISCHARGE LO PRESS - EXTINGUISHED (Refer to AP-CCW.3, LOSS OF CCW-PLANT SHUTDOWN).

o Annunciator A-30. CCW PUMP INLET HEADER HI TEMP - EXTINGUISHED

H EOP: TITLE:

REV: 13 AP-RHR.1 LOSS OF RHR 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: Perform the following:

o RHR cooling - RESTORED a. Evaluate alternatives for long term cooling (Consult Plant o RCS temperature - STABLE OR Staff)

DECREASING

~ Consider establishing secondary heat sink

~ Refer to ER-RHR.1. RCDT PUMP OPERATION FOR CORE COOLING

~ Consider RCS feed and bleed

b. Continue attempts to restore RHR to operable.

c. Return to Step 3.

NOTE: Refer to 0-9.3, NRC IMMEDIATE NOTIFICATION. for reporting requirements.

19 Notify Higher Supervision 20 Return I'END-to Procedure Or Guidance Xn Effect

EOP: TITLE:

REV: 13 AP-RHR. 1 LOSS OF RHR 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:

REV: 5 ATT-3.0 ATTACHMENT CI/CVI PAGE 1 of 3 Responsible Manager NOTE: Locked valve key may be required for local operations.

AUTO ISOL VALVE ALTERNATE ISOL ALTERNATE ISOL LOCATION AOV-200A AOV-371/133 MCB AOV-200B AOV-371/133 MCB AOV-202 AOV-371/133 MCB AOV-5392 V-5397/5410 IB BASEMENT CLEAN SIDE AOV-371 V-204A/820 NRHX ROOM (locked area)

MOV-313 V-315A/315C SWRF ROOM (reach rods)

AOV-9227 V-9225 IB BASEMENT CLEAN SIDE AOV-508 AOV-548/550A/550B MCB AOV-5738 V-5701 IB BASEMENT CLEAN SIDE AOV-5737 V-5702 IB BASEMENT CLEAN SIDE AOV-5735 V-5733 SAMPLE HOOD AOV-57 3 6 V-5734 SAMPLE HOOD SOV-921 V-928A INSIDE A H2 MON PNL (AFW PUMP AREA)(key 59)

SOV-922 V-928B INSIDE A H2 MON PNL (AFW PUMP AREA)(key 59)

SOV-923 V-929A INSIDE B H2 MON PNL (AFW PUMP AREA)(key 59)

SOV-924 V-929B INSIDE B H2 MON PNL (AFW PUMP AREA) (key 59)

AOV-539 V-546 BY SFP HX AOV-1789 V-1655 BY SFP HX AOV-1786 AOV-1787 MCB AOV-1787 AOV-1786 MCB (1) does not receive Auto closure signal on CI

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REV: 5 ATT-3.0 ATTACHMENT CI/CVI PAGE 2 of 3 AUTO ISOL VALVE ALTERNATE ISOL ALTERNATE ISOL LOCATION AOV-1721 AOV-1003A/1003B/1722 WASTE DISPOSAL PANEL/AB SUB-BASEMENT AOV-1003A AOV-1721 WASTE DISPOSAL PANEL AOV-1003B AOV-1721 WASTE DISPOSAL PANEL AOV-1597 V-1596 IB BASEMENT CLEAN SIDE AOV-1598 AOV-1599 MCB AOV-1599 AOV-1598 MCB 12)

MOV-813 MOV-817 MCB MOV-814 V-815A AB INT LEVEL l2)

AOV-1723 AOV-1728 WASTE DISPOSAL PANEL l2)

AOV-1728 AOV-1723 WASTE DISPOSAL PANEL AOV-951 AOV-966A MCB AOV-953 AOV-966B MCB AOV-955 AOV-966C MCB AOV-959 V-957 PRIMARY SAMPLE ROOM AOV-966A V-956F SAMPLE HOOD AOV-966B V-956E SAMPLE HOOD AOV-966C V-956D SAMPLE HOOD AOV-846 V-8629/944A BY SFP HX AOV-8418 V-5021 IB BASEMENT CLEAN SIDE AOV-7971 AOV-7970 MCB REAR AOV-7970 AOV-7971 MCB REAR (2) AC power normally off (3) Place CNMT sump pumps in pull-stop

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REV 5 ATT-3.0 ATTACHMENT CI/CVI PAGE 3 of 3 AUTO ISOL VALVE ALTERNATE ISOL ALTERNATE XSOL LOCATION AOV-7445 AOV-7478 MCB REAR AOV-7478 AOV-7445 MCB REAR PEVO-5879 N/A FLANGED PSVO-5869 N/A FLANGED l4)

SOV-1B (10214S1) V-1080A SAMPLE HOOD l4)

SOV-2B (10214 S) V-1080A SAMPLE HOOD l4)

SOV-3B (10211S1) V-1076B SAMPLE HOOD l4)

SOV-5B (10213S1) V-1084B SAMPLE HOOD l4)

SOV-1A (10215S1) V-1080A SAMPLE HOOD l4)

SOV-2A (10215S) V-1080A SAMPLE HOOD l4)

SOV-3A (10205S1) V-1076A IB BASEMENT CLEAN SIDE l4)

SOV-5A (10209S1) V-1084A IB BASEMENT CLEAN SIDE (4) Valves normally deenergized with manual isolation valve locked closed.

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REV: 3 ATT-3.1 ATTACHMENT CNMT CLOSURE 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 COLUMN 2 AUTO ISOL VALVE ALTERNATE ISOL ALTERNATE ISOL LOCATION AOV-5392 (IA) V-5397/5410 IB CLEAN BSMT AOV-371 (L/D) V-204A/820 NRHX ROOM (locked area)

MOV-313 (RCP Seal) V-315A/315C SWRF ROOM (reach rods)

AOV-9227 (Fire Sys) V-9225 IB CLEAN BSMT AOV-508 (DI Water) AOV-548/550A/550B MCB AOV-5738 (S/G B/D) V-5701 IB CLEAN BSMT AOV-5737 (S/G B/D) V-5702 IB CLEAN BSMT AOV-5735 (S/G samp) V-5733 SAMPLE HOOD AOV-5736 (S/G samp) v-5734 SAMPLE HOOD AOV-539 (PRT gas) V-54 6 BY SFP HX AOV-1789 (RCDT to V-1655 BY SFP HX gas anal)

AOV-1786 (RCDT/VH) AOV-1787 (V-1716A) BY'FP HX AOV-1721 (RCDT pumps) AOV-1003A/1003B/1722 WASTE PANEL/AB SUB-BASEMENT AOV-1597 (CNMT rad) V-1596 IB CLEAN BSMT AOV-1598 (CNMT rad) AOV-1599 MCB MOV-813 (CCW) CCW SYSTEM INTACT AUX BLDG INT (BY RWST)

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REV: 3 ATT-3.1 ATTACHMENT CNMT CLOSURE PAGE 2 of 2 COLUMN 1 COLUMN 2 AUTO ISOL VALVE ALTERNATE ISOL ALTERNATE ISOL LOC TION MOV-814 (CCW) CCW SYSTEM INTACT AUX BLDG INT (BY RWST)

AOV-1723 (CNMT sump) AOV-1728 .WASTE PANEL AOV-846 (ACCUM N2) V-8629/944A BY SFP HX AOV-8418 (DI water) V-5021 IB CLEAN BSMT AOV-7970 (Mini purge) AOV-7971 MCB REAR AOV-7445 (Mini purge) AOV-7478 MCB REAR AOV-5879 (Purge) Purge Exhaust Fan OFF AOV-5869 (Purge) Purge Supply Fan OFF 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).