ML023360081

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Emergency Operating Procedures for R. E. Ginna
ML023360081
Person / Time
Site: Ginna Constellation icon.png
Issue date: 11/19/2002
From: Widay J
Rochester Gas & Electric Corp
To: Clark R
Document Control Desk, NRC/NRR/DLPM/LPD1
References
Download: ML023360081 (32)
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Text

RiN A Subsidiaryof RGS Energy Group, Inc ROCHESTER GAS AND ELECTRIC CORPORATION

  • 89 EASTAVENUE, ROCHESTER, N Y 14649-0001 ° 716-771-3250 www rge corn JOSEPH A. WIDAY ViCE PRESIDENT &PLANT MANAGER GINNA STATION November 19, 2002 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Robert Clark Project Directorate I Washington, D.C. 20555

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Clark:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, seDA. *W~iday 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 ATT-11.2, Rev 4 AP-CCW.2, Rev 17 .

AP-CCW.3, Rev 15

REPORT NO. 01 REPORT: NPSP0200 GINNA NUCLEAR POWER PLANT PROCEDURES INDEX C 11/19/02 PAGE- 1 C

2 DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRAP PRER PRPT ST*ATUS- EF QU 5 )YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-CCW. 1 LEAKAGE INTO THE COMPONENT COOLING LOOP 015 06/26/02 06/26/02 06/26/07 EF AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 017 11/19/02 06/26/02 06/26/07 EF AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN 015 11/19/02 06/26/02 06/26/07 EF AP-CR.1 CONTROL ROOM INACCESSIBILITY 018 06/26/02 06/26/02 06/26/07 EF AP-CVCS. 1 CVCS LEAK 013 06/26/02 06/03/02 06/03/07 EF AP-CVCS. 3 LOSS OF ALL CHARGING FLOW 003 06/26/02 02/26/99 02/26/04 EF AP-CW 1 LOSS OF A CIRC WATER PUMP 011 06/26/02 05/01/98 05/01/03 EF AP-ELEC. 1 LOSS OF 12A AND/OR 12B BUSSES 023 06/26/02 06/26/02 06/26/07 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 010 06/26/02 06/26/02 06/26/07 EF AP-ELEC. 3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 011 06/26/02 06/26/02 06/26/07 EF AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 004 06/26/02 06/26/02 06/26/07 EF AP-ELEC. 17/18 LOSS OF SAFEGUARDS BUS 17/18 004 06/26/02 06/26/02 06/26/07 EF AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW 014 07/25/02 06/26/02 06/26/07 EF AP-IA.1 LOSS OF INSTRUMENT AIR 018 06/26/02 05/01/98 05/01/03 EF AP-PRZR. 1 ABNORMAL PRESSURIZER PRESSURE 013 06/26/02 06/26/02 06/26/07 EF AP-RCC. 1 CONTINUOUS CONTROL ROD WITHDRAWAL/INSERTION 008 06/26/02 05/14/98 05/14/03 EF AP-RCC. 2 RCC/RPI MALFUNCTION 010 06/26/02 01/22/02 01/22/07 EF AP-RCC. 3 DROPPED ROD RECOVERY 005 06/26/02 02/27/98 02/27/03 EF AP-RCP 1 RCP SEAL MALFUNCTION 014 06/26/02 05/01/98 05/01/03 EF AP-RCS.1 REACTOR COOLANT LEAK 016 06/26/02 05/01/98 05/01/03 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 011 06/26/02 05/01/98 05/01/03 EF AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 010 06/26/02 04/01/02 01/22/07 EF AP-RCS.4 SHUTDOWN LOCA 012 06/26/02 05/01/98 05/01/03 EF AP-RHR. 1 LOSS OF RHR 018 07/25/02 05/01/98 05/01/03 EF

REPORT NO. 01 REPORT. NPSP0200 GINNA NUCLEAR POWER PLANT (7 11/19/02 PAGE- 2 C -7 ,-.;

PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRAP PRER PRPT STATUS- EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDU)RE TITLE REV DATE REVIEW REVIEW ST AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 012 05/30/02 03/31/00 03/31/05 EF AP-SG.1 STEAM GCENERATOR TUBE LEAK 002 06/26/02 06/26/02 06/26/07 EF AP-SW.1 SERVICE WATER LEAK 017 06/26/02 06/03/98 06/03/03 EF AP-SW.2 LOSS OF SERVICE WATER 002 06/26/02 10/31/01 10/31/06 EF AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 011 06/26/02 06/26/02 06/26/07 EF AP-TURB.2 TURBINE LOAD REJECTION 018 06/26/02 06/26/02 06/26/07 EF AP-TURB.3 TURBINE VIBRATION 011 06/26/02 06/26/02 06/26/07 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 016 07/25/02 05/01/98 05/01/03 EF AP-TURB.5 RAPID L(3AD REDUCTION 006 06/26/02 06/26/02 06/26/07 EF TOTAL FOR PRAP 33

--,r e, -4 REPORT NO. 01 C GINNA NUCLEAR POWER PLANT C 11/18/02 PAGE:

C REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE- PRATT EOP ATTACHMENTS PARAMETERS: DOC TYPES - PROPS PRATT PRER PRPT STATUS- EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ATT-1. 0 ATTACHMENT AT POWER CCW ALIGNMENT 002 05/02/02 02/10/98 02/10/03 ATT-1. 1 ATTACHMENT NORMAL CCW FLOW 000 05/18/00 05/18/00 05/18/05 ATT-2.1 ATTACHMENT MIN SW 005 02/01/01 02/10/98 02/10/03 ATT-2.2 ATTACHMENT SW ISOLATION 008 03/06/02 08/11/98 08/11/03 ATT-2.3 ATTACHMENT SW LOADS IN CNMT 004 03/06/02 12/31/99 12/31/04 ATT-2.4 ATTACHMENT NO SW PUMPS 001 01/08/02 10/31/01 10/31/06 ATT-2.5 ATTACHMENT SPLIT SW HEADERS 000 06/26/02 06/26/02 06/26/07 ATT-3.0 ATTACHMENT CI/CVI 006 03/06/02 01/06/99 01/06/04 ATT-3.1 ATTACHMENT CNMT CLOSURE 004 03/06/02 01/25/99 01/25/04 ATT-4.0 ATTACHMENT CNMT RECIRC FANS 003 07/26/94 05/13/98 05/13/03 ATT-5.0 ATTACHMENT COND TO S/G 005 03/06/02 12/31/99 12/31/04 ATT-5.1 ATTACHMENT SAFW 008 05/30/02 12/31/99 12/31/04 ATT-5.2 ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP 003 01/14/99 01/14/99 01/14/04 ATT-6.0 ATTACHMENT COND VACUUM 003 12/18/96 02/10/98 02/10/03 ATT-7.0 ATTACHMENT CR EVAC 006 03/06/02 02/10/98 02/10/03 ATT-8.0 ATTACHMENT DC LOADS 006 03/22/99 01/14/99 01/14/04 ATT-8.1 ATTACHMENT D/G STOP 005 03/06/02 02/10/98 02/10/03 ATT-8 2 ATTACHMENT GEN DEGAS 008 06/20/02 08/17/99 08/17/04 ATT-8.3 ATTACHMENT NONVITAL 004 03/06/02 02/10/98 02/10/03 ATT-8.4 ATTACHMENT SI/UV 005 03/06/02 02/10/98 02/10/03 ATT-8.5 ATTACHMENT LOSS OF OFFSITE POWER 000 05/02/02 05/02/02 05/02/07 ATT-9.0 ATTACHMENT LETDOWN 008 03/06/02 03/06/02 03/06/07 ATT- 9. 1 ATTACHMENT EXCESS L/D 005 03/06/02 10/31/01 10/31/06 ATT- 10.0 ATTACHMENT FAULTED S/G 006 03/06/02 05/13/98 05/13/03

REPORT NO. 01 C GINNA NUCLEAR POWER PLANT 11/18/02 PAGE: 2

(

REPORT" NPSP0200 PROCEDURES INDEX DOC TYPE: PRATT EOP ATTACHMENTS PARAMETERS, DOC TYPESS - PROPS PRATT PRER PRPT STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST ATT-11.0 ATTACHMENT IA CONCERNS 002 04/07/97 08/11/98 08/11/03 EF ATT-11.1 ATTACHMENT IA SUPPLY 003 03/06/02 08/11/98 08/11/03 EF ATT-11.2 ATTACHMENT DIESEL AIR COMPRESSOR 004 11/18/02 04/03/98 04/03/03 EF ATT-12.0 ATTACHMENT N2 PORVS 004 03/06/02 02/10/98 02/10/03 EF ATT-13.0 ATTACHMENT NC 002 07/26/94 02/10/98 02/10/03 EF ATT- 14 .0 ATTACHMENT NORMAL RHR COOLING 003 03/06/02 09/23/99 09/23/04 EF ATT-14.1 ATTACHMENT RHR COOL 005 01/08/02 01/08/02 01/08/07 EF ATT-14.2 ATTACHMENT RHR ISOL 002 03/06/02 02/10/98 02/10/03 EF ATT-14.3 ATTACHMENT RHR NPSH 003 03/06/02 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 002 03/06/02 01/14/99 01/14/04 EF ATT-15 .0 ATTACHMENT RCP START 009 03/06/02 03/17/00 03/17/05 EF ATT-15.1 ATTACHMENT RCP DIAGNOSTICS 003 04/24/97 02/10/98 02/10/03 EF ATT-15 2 ATTACHMENT SEAL COOLING 005 03/06/02 02/10/98 02/10/03 EF ATT-16 0 ATTACHMENT RUPTURED S/G 011 07/18/01 01/11/00 01/11/05 EF ATT-16.1 ATTACHMENT SGTL 002 03/06/02 09/08/00 09/08/05 EF ATT-16.2 ATTACHMENT RCS BORON FOR SGTL 002 04/09/02 09/08/00 09/08/05 EF ATT- 17.0 ATTACHMENT SD-i 014 06/20/02 02/29/00 02/28/os EF ATT- 17.1 ATTACHMENT SD-2 006 03/06/02 01/30/01 01/30/06 EF ATT- 18.0 ATTACHMENT SFP - RWST 005 03/06/02 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 ATTACHMENT RCS ISOLATION 002 03/06/02 02/10/98 02/10/03 EF ATT-22 .0 ATTACHMENT RESTORING FEED FLOW 003 05/02/02 01/22/02 01/22/07 EF ATT-23 .0 ATTACHMENT TRANSFER 4160V LOADS 000 02/26/99 02/26/99 02/26/04 EF

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 11/18/02 PAGE 3 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRATT EOP ATTACHMENTS PARAMETERS: DOC TYPES - PROPS PRATT PRER PRPT STATUS: EF QU 5 YEARS ONLY-PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURI TITLE REV DATE REVIEW REVIEW ST ATT-24.0 ATTACNMEf IT TRANSFER BATTERY TO TSC 000 09/08/00 09/08/00 09/08/05 EF ATT-26.0 ATTACHME? IT RETURN TO NORMAL OPERATIONS 000 10/31/01 10/31/01 10/31/06 EF TOTAL FOR PRATT 50

EOP: TITLE:

REV: 4 "ATT-I1.2 ATTACHMENT DIESEL AIR COMPRESSOR PAGE 1 of 2 Responsible Manager rim% Date /-]6Q 6 To supply Instrument Air System using the Diesel Air Compressor perform the following:

1. Verify hose installed between Diesel Compressor discharge (located on compressor) and service air connection (at V-7203C) by Turbine Building overhead door #10.
2. Start the portable Diesel Driven Air Compressor using instructions mounted locally on the compressor.

NOTE: Blowdown portable Diesel Air Compressor Discharge Filter hourly after initial system start until oil and water are sufficiently removed from header, THEN blowdown the Discharge Filter once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3. Blowdown portable Diesel Air Compressor Discharge Filter by cycling open and closed Service Air Yard inlet drain/trap drain valve V-7203B until only air escapes. (Next to Door #10, Column A-7 Turbine Building Basement North)
4. Check closed Breathing Air Compressor discharge isolation valve V-14007Y (next to Door #10, Column A-7 Turbine Building Basement North).
5. Check closed Backup Air Compressor discharge drain valve V-14007X (next to Door #10, Column A-7 Turbine Building Basement North).
6. Open Service Air isolation valve to Turbine Building from Yard, V-7203. (Next to Door #10, Column A-7 Turbine Building Basement North)
7. Blowdown residue in line by throttling open Backup Air Compressor discharge drain valve V-14007X until residue is removed, THEN close drain valve V-14007X.
8. Open Back-up Air Compressors discharge inner isolation valve to Service Air header, V-7195A. (Next to Door #10, Column A-7 Turbine Building Basement Northwest).
9. Slowly open V-7002D (at TSA02 Service Air Compressor Wet Tank).

EOP: TITLE:

REV: 4 ATT-1I.2 ATTACHMENT DIESEL AIR COMPRESSOR PAGE 2 of 2

10. Open V-7000A, IA/SA cross connect valve (above B IA receiver, 8 ft. above floor).

NOTE: Power to SAC dryer is desired, but not required, during this procedure.

11. Energize SAC dryer by placing power switch on SAC control panel to "Diesel Air Compressor" position and check "Power ON" light is lit.
12. Notify Control/Shift Supervisor that Diesel Air Compressor is lined up and supplying all air systems.
13. Notify Maintenance to maintain proper fuel oil level in portable Diesel Driven Air Compressor.

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER RESPONSFTIE MANAGER EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 17 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 2 of 10 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. ENTRY CONDITIONS - This procedure is entered from:
a. AP-CCW.I, LEAKAGE INTO THE COMPONENT COOLING SYSTEM, when CCW surge tank level decrease indicated at power.
2. SYMPTOMS - The symptoms of LOSS OF CCW DURING POWER OPERATION are;
a. Annunciator A-13, CCW SURGE TANK LO LEVEL 41.2%,

lit, or

b. Annunciator A-22, .CCW PUMP DISCHARGE LO PRESS 60 PSI, lit, or
c. Annunciator A-17, MOTOR OFF RCP CCWP, lit, or
d. Annunciator A-9, RHR PUMP COOLING WATER OUTLET LO FLOW 15 GPM, lit or
e. Annunciator A-6, CONT SPRAY PUMP COOLING WATER OUT LOW FLOW 15 GPM, lit or
f. Annunciator A-14, SAFETY INJ PUMPS COOLING WATER OUT LO FLOW 25 GPM, lit or
g. Annunciator A-7 (A-15), RCP A (B) CCW RETURN HI TEMP OR LO FLOW 165 GPM 125°F, lit or
h. Annunciator A-24 (A-32), RCP A (B) OIL LEVEL + 1.25, lit or,
i. Annunciator A-12, NON-REGEN HX LETDOWN OUT HI TEMP 1450F lit or,
j. Annunciator A-18, VCT HI TEMP 1450.

..** ..* O.* *..*..*.....*..

CAUTION a*.... *O*0....

O*A **

"o IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 2000F. THEN TRIP THE AFFECTED RCP.

"o IF CCW IS LOST. THEN SEAL INJECTION SHOULD BE MAINTAINED TO THE RCP(S)

UNTIL RCS TEMPERATURE IS LESS THAN 150 0 F, OR UNTIL CCW IS RESTORED.

1 Check CCW Pump Status: Perform the following:

"o Both CCW pump breaker white a. Ensure standby CCW pump running.

lights - EXTINGUISHED IF no CCW pump can be operated.

"o Annunciator A-17. MOTOR OFF RCP THEN perform the following:

CCWP - EXTINGUISHED

1) Trip the reactor.
2) Trip BOTH RCPs.
3) CLose letdown isol, AOV-427.
4) Close excess letdown. HCV-123.
5) Go to E-0, REACTOR TRIP OR SAFETY INJECTION.
b. IF annunciator A-22. CCW PUMP DISCHARGE LO PRESS 60 PSI, lit.

THEN check closed CCW to RHR HXs (MOV-738A and MOV-738B).

EOP: TITLE: REV: 17 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 4 of 10 NOTE: MCB CCW surge tank level indication should be verified locally in the AUX BLDG, if possible.

  • 2 Monitor CCW Surge Tank Level Perform the following:

- APPROXIMATELY 50% AND STABLE

a. Open RMW to CCW surge tank.

MOV-823.

b. Start RMW pump(s).
c. IF surge tank level stable or increasing, THEN control level at approximately 50% while continuing with Step 3.

IF CCW surge tank level can NOT be maintained greater than 10%,

THEN perform the following:

1) Close letdown isol, AOV-427.
2) Close excess letdown, HCV-123.
3) Trip the reactor.
4) Trip BOTH RCPs.
5) Place both CCW pumps in pull stop.
6) Go to E-0, REACTOR TRIP OR SAFETY INJECTION.

STP ACTION/EXPECTED RSPONSEi RESPONSE NOT OBTAINEDl 3 Check CCW To Both RCPs: IF CCW lost to RCP(s). THEN perform the following:

"o Annunciator A-7 (A-15). RCP 1A (iB) CCW return Hi temp or low a. Trip the reactor.

flow 165 gpm 125°F alarm EXTINGUISHED b. Trip affected RCP(s).

"o RCP motor bearings temperature c. Go to E-0. REACTOR TRIP OR (PPCS Group Display-RCPS OR RCP SAFETY INJECTION.

temperature monitor RK-30A recorder) -

  • 200°F
  • 4 Monitor If Letdown Should Be Isolated:
a. Check annunciator A-12, a. Isolate Normal Letdown:

Non-Regen Hx Letdown Out Hi Temp 1450 - EXTINGUISHED 1) Close letdown isolation, AOV-427.

2) Close letdown orifice valves (AOV-200A, AOV-200B, and AOV-202).
3) Close letdown isolation, AOV-371.
4) Close charging flow control valve. HCV-142 WHILE adjusting charging pump speed to maintain:

"* RCP labyrinth seal D/P between 15 inches and 80 iniches

"* PRZR level at program

b. Check excess letdown temperature b. Isolate Excess Letdown:

- LESS THAN 195 F 0

1) Close excess letdown flow control valve. HCV-123.
2) Close excess letdown isolation valve. AOV-310.

EOP: TITLE: REV: 17 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 6 of 10 5 Check CCW Valve Alignment NORMAL

a. Check MCB CCW valves (Refer to a. Align CCW valves as necessary.

ATT-1.0. ATTACHMENT AT POWER CCW ALIGNMENT)

b. Direct AO to check local flow indications per ATT-I.I, ATTACHMENT NORMAL CCW FLOW NOTE: o IF Seal Water Hx will be bypassed. THEN an increase in VCT temperature is expected.

o IF Seal Water Hx will be isolated, THEN seal return and excess letdown (if in service) will be to the PRT through RV-314.

6 Check Seal Water Hx For Tube IF a tube leak is indicated, THEN Leak: bypass and isolate Seal Water Hx and, if desired, isolate Seal "o Locally check Seal Water Hx CCW Return.

outlet flow - NORMAL (FI-605. a. To bypass and isolate Hx perform refer to AO log) the following:

"o Locally check Seal Water Hx CCW outlet temperature - NORMAL 1) Open seal bypass V-394 (TI-604, refer to AO log)

2) Close seal inlet V-265 "o VCT level - NO UNEXPLAINED INCREASE 3) CLose seal outlet V-321
4) Close CCW inlet V-763
5) Close CCW outlet V-767
b. IF desired to isolate seal return line, THEN close MOV-313.
c. Notify RP to sample RCS for chromates.

EOP: TITLE: REV: 17 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 7 of 10 STP ACTION/EXPECTED RESPONSEI RESPONSE NOT OBTAINEDI NOTE: Operation may continue with the reactor support coolers isolated. If this occurs, notify higher supervision.

7 Check For CCW Leakage In CNMT:

a. Check CNMT sump A level: a. IF abnormal increase in CNMT sump level, THEN perform the o Level - STABLE following:

o Sump A pumps - OFF 1) Direct RP Tech to sample sump A for chromates.

2) Prepare to make CNMT entry to check for CCW leak.
b. RCP oil levels - STABLE b. IF any RCP oil level increasing uncontrollably, THEN perform the following:
1) Trip the reactor.
2) Trip affected RCP(s).
3) Close CCW supply and return for affected RCP(s).

e RCP A. MOV-749A and MOV-759A e RCP B, MOV-749B and MOV-759B

4) Go to E-0, REACTOR TRIP OR SAFETY INJECTION.

EOP: TITLE:

REV: 17 AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 8 of 10 STP ACTION/EXPECTE RESPONSEI RESPONSE NO OTAINEDI 8 Check for CCW Leakage In AUX Dispatch AO to investigate AUX BLDG BLDG: for CCW leakage.

"o Start frequency of AUX BLDG sump pump(s) - NORMAL (Refer to RCS daily leakage log)

"o Waste holdup tank level - STABLE OR INCREASING AS EXPECTED 9 Verify CCW System Leak IDENTIFIED

a. Leak identified a. Perform the following:
1) Direct RP Tech to sample CCW HX SW outlet for chromates.
2) Return to Step 2.
b. Isolate leak if possible
c. Refer to IP-ENV-3. RESPONSE TO A I SPILL OF HAZARDOUS MATERIAL/WASTEI 10 Check Normal Or Excess IF normal letdown desired. THEN Letdown - IN SERVICE establish normal letdown (refer to ATT-9.0. ATTACHMENT LETDOWN).

IF normal letdown NOT available.

THEN establish excess letdown if desired. (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D),

EOP: TITLE: REV17 AP-CCW.2 LOSS OF CCW DURING POWER OPERATIONPAGE 9 of 0 11 Check CCW System Leak Isolated

a. Surge tank level - APPROXIMATELY a. IF level less than 50%. THEN 50% continue filling.

IF ; 50%. THEN perform the following:

1) Stop RMW pump(s).
2) Close MOV-823.
b. Surge tank level - STABLE b. Return to Step 2.

12 Direct RP To Sample CCW System For Chromates 13 Evaluate MCB Annunciator Status (Refer to AR Procedures) 14 Evaluate Plant Conditions:

a. CCW system malfunction a. Return to Step 1.

IDENTIFIED AND CORRECTED

b. CCW system status adequate for b. IF shutdown required. THEN refer power operation (Refer to ITS to 0-2.1. NORMAL SHUTDOWN TO HOT Section 3.7.7). SHUTDOWN.

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

15 Notify Higher Supervision 16 Return To Procedure Or Guidance In Effect

-END-

- EOP: TITLE: REV: 17 r AP-CCW.2 LOSS OF CCW DURING POWER OPERATION PAGE 1 of 1 AP-CCW.2 APPENDIX LIST TITLE

1) ATTACHMENT AT POWER CCW ALIGNMENT (ATT- 1.0)
2) ATTACHMENT EXCESS L/D (ATT- 9. 1)
3) ATTACHMENT NORMAL CCW FLOW (ATT-1.1)
4) ATTACHMENT LETDOWN (ATT-9.0)

ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER__

  • N_~ANAGER RESPONS IBLOiAGE

/ E-CT EF D6A EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: ITITLE: REV 15 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 2 of 12 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. ENTRY CONDITIONS - This procedure is entered from:
a. AP-CCW.l, LEAKAGE INTO THE COMPONENT COOLING LOOP, or
b. AP-ELEC.3, LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350'F), or
c. AP-RHR.1, LOSS OF RHR, or
d. AP-RHR.2, LOSS OF RHR WHILE OPERATING AT REDUCED RCS INVENTORY CONDITIONS, when CCW malfunction indicated.
2. SYMPTOMS - The symptoms of LOSS OF CCW - PLANT SHUTDOWN are:
a. Annunciator A-6, CONT SPRAY PUMP COOLING WATER OUT LO FLOW 15 GPM, lit, or
b. Annunciator A-7, (A-15), RCP A (B) CCW RETURN HI TEMP OR LO FLOW 165 GPM 1250F, lit, or
c. Annunciator A-9, RHR PUMP COOLING WATER OUTLET LO FLOW 15 GPM, lit, or
d. Annunciator A-13, CCW SURGE TANK LO LEVEL 41.2%,

lit, or

e. Annunciator A-14, SAFETY INJ PUMPS COOLING WATER OUT LO FLOW 25 GPM, lit, or
f. Annunciator A-17, MOTOR OFF RCP CCWP, lit, or
g. Annunciator A-22, CCW PUMP DISCHARGE LO PRESS 60 PSI, lit, or
h. Annunciator A-24, (A-32), RCP A (B) OIL LEVEL

+/- 1.25, lit, or

i. Annunciator A-31, CCW SYSTEM LO FLOW 1800 GPM, lit or
j. Annunciator A-12, NON-REGEN HX LETDOWN OUT HI TEMP 145°F lit, or
k. Annunciator A-18, VCT Hi Temp 1450F.

EOP: TITLE: REV: 15 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 3 of 12 SP ** AI *.*..*.*..*.**.*.

.. EE D SOE RSOE NOT OBTAINED...

CAUTION o IF CCW FLOW TO A RCP IS INTERRUPTED FOR GREATER THAN 2 MINUTES OR IF EITHER RCP MOTOR BEARING TEMPERATURE EXCEEDS 2000F. THEN TRIP THE AFFECTED RCP.

o IF CCW IS LOST. THEN SEAL INJECTION SHOULD BE MAINTAINED TO THE RCP(S)

UNTIL RCS TEMPERATURE IS LESS THAN 1500F. OR UNTIL CCW IS RESTORED.

NOTE: IF CCW is lost to operating CS. ]RHR, or SI pumps, they may be left running for brief periods while isolating a CCW leak.

IF a CCW pump has tripped, THEN 1 Check CCW Pump Status:

perform the following:

"o Both CCW pump breaker white lights - EXTINGUISHED a. Ensure standby CCW pump running.

"o Annunciator A-17, MOTOR OFF, RCP b. Attempt to reset and start the CCWP - EXTINGUISHED affected CCW pump if required for cooling.

c. IF no CCW pumps available, THEN trip BOTH RCPs.

NOTE: MCB surge tank level indication should be verified locally in the Aux Bldg. if possible.

2 Check CCW Surge Tank Level IF CCW surge tank level is APPROXIMATELY 50% AND STABLE decreasing, THEN perform the following:

a. Open RMW to CCW surge tank, MOV-823.
b. Start RMW pump(s).
c. Dispatch AO to AUX BLDG to investigate for CCW leak
d. Control CCW surge tank level at approximately 50% while continuing with Step 3.

EOP: TITLE:

REV: 15 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 4 of 12 3 Check CCW Cooling To RCPs:

a. RCPs - BOTH RUNNING a. Perform the following:
1) Verify SDM requirements met.

(Refer to 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)

2) IF no RCPs running, THEN verify natural circulation (refer to ATT-13.0, ATTACHMENT NC) AND go to Step 4.
b. Check RCP indications: b. IF CCW lost to RCP(s). THEN perform the following:

" Annunciator A-7 (A-15), RCP A (B) CCW RETURN HI TEMP OR LOW 1) Stop the affected RCP(s).

FLOW 165 GPM 125 0 F EXTINGUISHED 2) IF no RCPs running. THEN verify natural circulation

" Verify RCP motor bearing (Refer to ATT-13.0.

temperatures (PPCS Group ATTACHMENT NC).

Display - RCPS or RK-30A recorder) - LESS THAN 200°F 3) Verify SDM requirements met.

(Refer to 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)

EOP: TITLE: REV: 15 AP-CCW.3 \ LOSS OF CCW - PLANT SHUTDOWN PAGE 5 of 12

  • 4 Monitor If Letdown Should Be Isolated:
a. Check annunciator A-12. a. Isolate Normal Letdown:

Non-Regen Hx Letdown Out Hi Temp 1450 EXTINGUISHED 1) Close letdown isolation, AOV-427.

2) Close letdown orifice valves (AOV-200A. AOV-200B. and AOV-202).
3) Close letdown isolation, AOV-371.
4) IF PRZR solid, THEN perform the following:

a) Stop all charging pumps.

b) IF CCW lost to RCP thermal barrier Hx, THEN close seal injection V-300A and V-300B.

c) Start and stop charging pump to maintain RCS at desired pressure.

d) Go to Step 4b.

5) Close charging flow control valve, HCV-142, WHILE adjusting charging pump speed to control:

"o RCP labyrinth seal D/P between 15 inches and 80 inches "o PRZR level at desired level

6) Establish excess letdown, if desired (Refer to ATT-9.1.

ATTACHMENT EXCESS L/D).

b. Check excess letdown temperature b. Isolate Excess Letdown:

LESS THAN 195 0 F.

1) Close excess letdown flow control valve. HCV-123.
2) Close excess letdown isolation valve, AOV-310.

5 Check CCW Pump Discharge Pressure

a. At least one CCW pump - RUNNING a. Go to Step 6.
b. Verify Annunciator A-22. CCW b. Dispatch AO to the AUX BLDG to PUMP DISCHARGE LO PRESS 60 PSIG perform the following:

- EXTINGUISHED

1) Throttle CCW to RHR Hxs as necessary to restore CCW pump discharge pressure.

"*MOV-738A

"*MOV-738B

2) Investigate for CCW leaks.

6 Check RCS Temperature IF RHR cooling available, THEN STABLE OR DECREASING adjust RHR cooling to stabilize RCS temperature AND go to Step 7.

IF S/G cooling available. THEN control S/G ARVs to stabilize RCS temperature. IF S/G ARVs do NOT provide adequate cooling, THEN perform the following:

a. Stop all but one RCP.
b. Initiate S/G blowdown from both S/Gs. (Refer to T-14 series)
c. Maintain both S/G levels stable by controlling AFW flow.
  • 7 Monitor CCW Surge Tank Level Perform the following:

- GREATER THAN 10%

a. Stop any running RCP.
b. Close letdown isolation, AOV-427.
c. IF RHR pump(s) running in shutdown cooling mode, THEN stop both RHR pumps AND refer to AP-RHR.l. LOSS OF RHR or AP-RHR.2, LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.
d. Pull stop both CCW pumps.
e. Verify natural circulation (Refer to ATT-13.0, ATTACHMENT NC).

8 Check CCW System Leakage - Go to Step 13.

ANY LEAKAGE INDICATED

NOTE: o IF Seal Water Hx will be bypassed. THEN an increase in VCT temperature is expected.

o IF Seal Water Hx will be isolated. THEN seal return will be to the PRT through RV-314.

9 Check Seal Water Hx For Tube IF a tube leak is indicated, THEN Leak: bypass and isolate Seal Water Hx and, if desired, isolate Seal 9 Locally check Seal Water Hx CCW Return as follows.

outlet flow - NORMAL (FI-605.

refer to AO log) a. To bypass and isolate Hx perform

& Locally check Seal Water Hx CCW the following:

outlet temperature - NORMAL (TI-604. refer to AO log) 1) Open seal bypass V-394

  • VCT level - NO UNEXPLAINED INCREASE 2) Close seal inlet V-265
3) Close seal outlet V-321
4) Close CCW inlet V-763
5) Close CCW outlet V-767
b. If desired to isolate seal return line close MOV-313.
c. Notify RP to sample RCS for chromates.

EOP: TITLE: REV: 15 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 9 of 12 10 Check For CCW Leakage In CNMT:

a. Check CNMT sump A level: a. IF abnormal increase in CNMT sump level, THEN perform the "o Level - STABLE following:

"o Sump A pumps - OFF 1) Direct RP Tech to sample sump A for chromates.

2) Prepare to make CNMT entry to check for CCW leak.
b. RCP oil levels - STABLE b. IF any RCP oil level increasing uncontrollably, THEN perform the following:
1) Stop affected RCP.
2) Close CCW supply and return for affected RCP(s).

o RCP A. MOV-749A and MOV-759A o RCP B. MOV-749B and MOV-759B

3) IF no RCPs running. THEN verify natural circulation (Refer to ATT-13.0, ATTACHMENT NC).
4) Verify SDM requirements met.

(Refer to 0-3.1. BORON CONCENTRATION FOR THE XENON FREE ALL RODS IN - MOST REACTIVE ROD STUCK OUT SHUTDOWN MARGIN)

EOP: TITLE:

REV: 15 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 10 of 12 STP ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED 11 Check for CCW Leakage In AUX Dispatch AO to investigate AUX BLDG BLDG: for CCW leakage.

"o Start frequency of AUX BLDG sump pump(s) - NORMAL (Refer to RCS daily leakage log)

"o Waste holdup tank level - STABLE OR INCREASING AS EXPECTED 12 Verify CCW System Leak IDENTIFIED

a. Leak identified a. Perform the following:
1) Direct RP Tech to sample CCW HX SW outlet for chromates.
2) Return to Step 2.
b. Isolate leak if possible
c. Refer to IP-ENV-3, RESPONSE TO A SPILL OF HAZARDOUS MATERIAL/WASTEI 13 Check CCW Valve Alignment And Realign valves to restore CCW to Flow Rates - AS REQUIRED FOR individual components.

PLANT CONDITIONS (Refer to ATT-I.1, ATTACHMENT NORMAL CCW FLOW)

EOP: TIITLE:

REV: 15 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 11 of 12 14 ACTION/EXPECTED RESPONSE RESPONSE O TAINED 14 Evaluate Plant Conditions:

a. RHR normal cooling - IN SERVICE a. Adjust S/G ARVs to stabilize RCS temperature and go to Step 15.
b. Check RCS Cooling: b. Perform the foliowing:

o RCS temperature - STABLE OR 1) Increase SW from CCW Hx DECREASING 9 CCW Hx A, V-4619 o CCW system status - ADEQUATE

  • CCW Hx B, V-4620 FOR RHR NORMAL COOLING
2) Adjust CCW to RHR Hxs, MOV-738A and MOV-738B to maintain RCS temperature stable or decreasing.
3) IF > 4900 gpm CCW flow required for desired RHR cooling (FI-619). THEN notify the Shift Supervisor.
4) IF CCW inadequate for RHR normal cooling. THEN go to AP-RHR.1, LOSS OF RHR OR AP-RHR.2, LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS.

15 Evaluate MCB Annunciator Status (Refer to AR Procedures)

"EOP: TITLE:

REV: 15 AP-CCW.3 LOSS OF CCW - PLANT SHUTDOWN PAGE 1 of 1 AP-CCW.3 APPENDIX LIST

(

TITLE

1) ATTACHMENT NC (ATT-13.0)
2) ATTACHMENT EXCESS L/D (ATT -9.1)
3) ATTACHMENT NORMAL CCW FLOW (ATT-1.1)
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