Text

R. E. Ginna Nuclear Power Plant, Emergency Operating Procedures
	ML040710638
Person / Time
Site:	Ginna
Issue date:	03/03/2004
From:	Widay J; Rochester Gas & Electric Corp
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML040710638 (15)
	v • d • e

Joseph A. Widay Rwev Always at Your Service Vice President and Plant Manager March 3, 2004 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Emergency Operating Procedures R.E. Ginna Nuclear Power Plant Docket No. 50-244 As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly yours, JL ph A. Wida 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 AP-RCP. 1, Rev 16 An equal opportunity employer C3 n ;

89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com An Energy East Company

6 ( (. s-li.

NPSP0200 Ginna Nuclear Power Plant Wed 3/3/2004 8:38:56 am WRIGHTJ PROCEDURE INDEX Page 1 of 2 INPUT PARAMETERS: TYPE: PRAP STATUS VALUE(S): EF. OU 5 YEARS ONLY:

PRAP . ABNORMALPROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 016 0110712004 06/26/2002 06/26/2007 EF AP-CCW.2 LOSS OF CCW DURING POWER OPERATION 018 05/08/2003 06/26/2002 06/26/2007 EF AP-CCW.3 LOSS OF CCW. PLANT SHUTDOWN 015 11/19/2002 06126/2002 06/26/2007 EF AP-CR.1 CONTROL ROOM INACCESSIBILITY 019 02125/2003 06/26/2002 06/26/2007 EF AP-CVCS.1 CVCS LEAK 013 06/26/2002 06/03/2002 06/03/2007 EF AP-CVCS.3 LOSS OF ALL CHARGING FLOW 004 08/26/2003 02/27/2004 02127/2009 EF AP-CW.1 LOSS OF A CIRC WATER PUMP 011 06/26/2002 04/1612003 04/16/2008 EF AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 026 05/30/2003 06126/2002 06/26/2007 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREOUENCY 010 06126/2002 06/26/2002 0612612007 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 012 05/3012003 06/26/2002 06/26/2007 EF AP-ELEC.13/15 LOSS OF BUS 13/15 000 09124/2003 09/24/2003 09/24/2008 EF AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 007 08126/2003 06/26/2002 06/26/2007 EF AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 006 05/30/2003 06/2612002 06/26/2007 EF AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW 015 05/0812003 06/26/2002 06/26/2007 EF AP-IA.1 LOSS OF INSTRUMENT AIR 018 06/26/2002 04/16/2003 04/1612008 EF AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 014 05/08/2003 06/26/2002 06/26/2007 EF AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWALANSERTION 008 06/26/2002 04116/2003 04/16/2008 EF AP-RCC.2 RCCIRPI MALFUNCTION 010 0612612002 01/2212002 0112212007 EF AP-RCC.3 DROPPED ROD RECOVERY 006 02/25/2003 02/25/2003 02125/2008 EF AP-RCP.1 RCP SEAL MALFUNCTION 016 03103/2004 04/24/2003 04/24/2008 EF AP-RCS.1 REACTOR COOLANT LEAK 016 06126/2002 04/16/2003 04/16/2008 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 011 06/26/2002 04/1612003 04/16/2008 EF AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 010 06/2612002 04/01/2002 01/22/2007 EF AP-RCS.4 SHUTDOWN LOCA 014 04/30/2003 04/30/2003 04/30/2008 EF AP-RHR.1 LOSS OF RHR 019 04/30/2003 04/30/2003 04/30/2008 EF AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDmONS 013 04/30/2003 04/30/2003 04/30/2008 EF AP-SG.1 STEAM GENERATOR TUBE LEAK 003 11/21/2002 06/26/2002 06/26/2007 EF AP-SW.1. SERVICE WATER LEAK 019 05/30/2003 04/21/2003 04/21/2008 EF AP-SW.2 LOSS OF SERVICE WATER 004 05/30/2003 10/31/2001 10/31/2006 EF AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 012 05/08/2003 06/26/2002 06/26/2007 EF

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INPUT PARAMETERS: TYPE: ' PRAP STATUS VALUE(S): EF. OU 5 YEARS ONLY:

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w - -~w~co PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP-TURB.2 TURBINE LOAD REJECTION 018 06/2612002 06/2612002 06/26/2007 EF AP-TURB.3 TURBINE VIBRATION 011 06/2612002 06/2612002 06/26/2007 EF AP-TURB.4 LOSS OF CONDENSER VACUUM 017 04/30/2003 04/30/2003 04/30/2008 EF AP-TURB.5 RAPID LOAD REDUCTION 006 06/26/2002 06/26/2002 06/26/2007 EF PRAP TOTAL 34 GRAND TOTAL: 34

EOP: TITLE:

REV: 16 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 1 of 11

.5 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER __2_

0 n ,

RESPONSIBLEt ANAGER 3 cooLIf EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: TITLE:

REV: 1 6 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 2 of 11 A. PURPOSE - This procedure provides the instructions necessary to diagnose and to respond to a reactor coolant pump seal malfunction.

B. ENTRY CONDITIONS/SYMPTOMS

1. ENTRY CONDITIONS - This procedure is entered from:

a. E-3, STEAM GENERATOR TUBE RUPTURE, or

b. ES-1.1, SI TERMINATION, or

c. ES-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, or

d. ECA-O.1, LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED, or

e. ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS, or

f. ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, or

g. ECA-3.2, SGTR WITH LOSS OF REACTOR COOLANT-SATURATED RECOVERY DESIRED, or

h. ECA-3.3, SGTR WITHOUT PRESSURIZER PRESSURE CONTROL, or

i. FR-I.1, RESPONSE TO HIGH PRESSURIZER LEVEL, when RCP seal malfunction is indicated.

2. SYMPTOMS - The symptoms of RCP SEAL MALFUNCTION are;

a. Annunciator B-17(18), RCP A(B) No.1 SEAL HI-LO FLOW 5.0 GPM 1.0 , lit, or

b. Annunciator B-9(10), RCP A(B) LABYR SEAL LO DIFF PRESS 15" H20, lit, or

c. Annunciator B-3(4), RCP A(B) STAND PIPE HI LEVEL + 1 FT, lit, or Continued on next page

EOP: TITLE:

REV: 16 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 3 of 11

2. SYMPTOMS (cont)

d. Annunciator B-11(12), RCP A(B) STAND PIPE LO LEVEL -4 FT, lit, or

e. Annunciator B-25(26), RCP A(B) No. 1 SEAL LO DIFF PRESS 220 PSID, lit, or

f. Annunciator B-1(2), RCP A(B) No. 1 SEAL OUT HI TEMP 2000F, lit, or,

g. Annunciator A-7(15), RCP A(B) CCW RETURN HIGH TEMP OR LOW FLOW, lit.

STP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED

* * * * * * * *

a * - . . - -

aa* - - -a * - - -* * * - - - *

a * * - - -

CAUTION IF ANY RCP IS SECURED BECAUSE OF A SEAL MALFUNCTION. IT SHOULD NOT BE RESTARTED UNTIL THE CAUSE OF THE MALFUNCTION HAS BEEN DETERMINED AND CORRECTED.

. . * . . * * - - - - * . . - -

a* - - - .* . . - * - * * * * * * * * - -

NOTE: o If a Reactor trip is initiated while performing Step 1. transition to E-0 should occur while completing subsequent actions of the step.

o #2 Seal leak rate is total RCDT leak rate minus any known in-leakage to RCDT from another source.

o Total #1 Seal Flow is defined for each RCP as the sum of indicated

-1Seal Leakoff Flow and #2 seal leak rate to RCDT (PPCS Point ID L1003, 3.2 gal/% in the normal operating range).

1 Check Total #1 Seal Flow -IF a #1 Seal Failure is verified by LESS THAN 8.0 GPM FOR EACH RCP a decrease in Labyr Seal Diff Pressure OR increasing Seal Inlet/Outilet temps. THEN perform the following:

a. IF reactor trip breakers closed.

THEN trip the reactor.

b. WHEN all E-0 Immediate Actions done. THEN trip the affected RCP(s).

c. Allow 4 minutes for pump coast down. THEN close affected RCP(s) seal disch valve.

. RCP A. AOV-270A

. RCP B. AOV-270B

d. IF reactor trip was NOT required. THEN perform the following:

1) Initiate SDM verification per 0-3.1.

2) Go to step 4.

II STP ACTION/EXPECTED RESPONSE 1 RESPONSE NOT OBTAINED 2 Check RCP Seal Return Valve Alignment:

a. RCP seal return isolation valve, a. Perform the following:

MOV-313 - OPEN

1) Ensure CI reset.

2) Ensure both trains of XY relays for RCP seal return isolation valve. MOV-313.

reset.

3) Open RCP seal return isolation valve. MOV-313.

IF MOV-313 can NOT be opened, THEN dispatch AO to AUX BLDG with RWST area key to check valve and breaker locally (breaker MCC C position 13J).

b. Verify RCP seal disch valves - b. Manually open valves. IF valves OPEN can NOT be opened. THEN verify IA aligned to CNMT and go to

RCP A. AOV-270A Step 3. 1

RCP B. AOV-270B

EOP: TITLE:

REV: 16 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 6 of 11 ACTION/EXPECTED RESPONSE llRESPONSE STE NOT OBTAINEDl NOTE: o If a reactor trip is initiated while performing Step 3. transition to E-0 should occur while completing subsequent actions of the step.

o The lower limit of 0.8 GPM limit for total #1 seal flow applies when the RCS is at normal operating pressure. Refer to FIG-4.0.

FIGURE RCP SEAL LEAKOFF and consult plant staff for guidance if the RCS is at reduced pressure.

3 Check RCP Seal Return Flow:

a. Total #1 Seal Flow - BETWEEN a. IF #1 Seal Inlet and Outlet 0.8 GPM AND 6.0 GPM FOR EACH RCP temperatures are increasing in an uncontrolled manner. THEN perform the following:

1) IF reactor trip breakers closed. THEN trip the reactor.

2) WHEN all E-0 Immediate Actions done. THEN trip the affected RCP(s).

3) Allow 4 minutes for pump coast down. THEN close affected RCP(s) seal disch valve.

RCP A. AOV-270A

RCP B. AOV-270B

4) IF reactor trip was NOT required. THEN initiate SDM verification per 0-3.1.

IF #1 Seal Inlet and Outlet temperatures are NOT increasing in an uncontrolled manner. THEN go to Step 4.

b. Go to Step 5.

[EOP: TITLE: REV: 16 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 7 of 11 STP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED 4 Determine RCP Shutdown Requirements:

a. Each RCP Total #1 seal flow - a. Perform the following while 2 0.8 GPM continuing with this procedure:

1) IF Seal Inlet/Outlet temperatures begin to increase in an uncontrolled manner, THEN return to Step 1.

2) Prepare for orderly pump shutdown by placing the plant in Hot Shutdown using 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN.

3) IF Total #1 seal flow increases to 2 0.8 GPM. THEN pump shutdown is NOT required. Stop the load reduction AND return to Step 1.

4) Secure the affected RCP within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

b. Each RCP Total I1 seal flow - b. Perform the following while 6.0 gpm continuing with this procedure:

1) IF total #1 Seal flow from any RCP greater than 6.0 gpm.

THEN maintain seal injection flow rate of 9.0 GPM or greater to the affected RCP.

2) IF total W1 Seal flow from any RCP exceeds 8.0 GPM OR Seal Inlet/Outlet temperatures begin to increase in an uncontrolled manner. THEN return to Step 1.

3) Prepare for orderly pump shutdown by placing the plant in Hot Shutdown using 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN.

4) Secure the affected RCP within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

EOP: TITLE:

REV: 16 AP-RCP.1 RCP SEAL MALFUNCTION

. PAGE 8 of 11 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I NOTE: ATT-15.1. ATTACHMENT RCP DIAGNOSTICS may be used to aid in diagnosis.

5 Check RCP Cooling: Perform the following:

o Annunciator A-7. RCP A CCW a. Verify RCP CCW supply and return RETURN HIGH TEMP OR LOW FLOW - valves open.

EXTINGUISHED

. RCP A. MOV-749A and MOV-759A o Annunciator A-15. RCP B CCW

RCP B. MOV-749B and MOV-759B RETURN HIGH TEMP OR LOW FLOW -

EXTINGUISHED b. Ensure open CCW outlet valves from RCP thermal barriers.

RCP A. AOV-754A

. RCP B. AOV-754B 6 Check RCP #2 Seal Indications: IF affected RCP #1 seal leakoff flow decreasing. THEN failure of #2 o Annunciator B-3. RCP A STANDPIPE seal may be indicated.

HI LEVEL 41 FT - EXTINGUISHED Check RCP #2 seal leak rate to RCDT o Annunciator B-4. RCP B STANDPIPE (PPCS Point ID L1003. 3.2 gal/% in HI LEVEL +1 FT - EXTINGUISHED the normal operating range).

a. IF RCP #2 seal leak rate to RCDT is S 1.1 gpm. THEN continue plant operation while closely monitoring RCP seal indications.

b. IF RCP #2 seal leak rate to RCDT is greater than 1.1 gpm, THEN perform the following:

1) Prepare for orderly pump shutdown by placing the plant in Hot Shutdown using 0-2.1.

NORMAL SHUTDOWN TO HOT SHUTDOWN.

2) Secure the affected RCP within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

EOP: TITLE:

REV: 1 6 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 9 of 11 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

* *

A A * * * * * * * * * * * * * * * . * * * * * * * * * * * . * * * * * *

CAUTION REDUCING CHARGING FLOW WILL RESULT IN INCREASING REGEN HX OUTLET TEMPERATURE.

* *

A * * * * * * * *

4 4

4 4

4 4 4 * * * * * * * * *

4 4 * * *

A

7 Check RCP Labyrinth Seal D/Ps Perform the following:

- GREATER THAN 15 INCHES OF WATER a. En~sure open CCW outlet valves from RCP thermal barriers.

RCP A. AOV-754A

RCP B. AOV-754B

b. Verify seal injection flow greater than 5 GPM for affected RCP.

c. Adjust HCV-142 to obtain at least 15 inches labyrinth seal AP.

d. Dispatch AO to check seal injection filter D/P.

e. Check CCW surge tank level stable. IF level increasing.

THEN go to AP-CCW.1. LEAKAGE INTO THE COMPONENT COOLING LOOP.

8 Check RCP #3 Seal Indications: Check CNMT radiation monitors normal.

o Annunciator B-li. RCP A STAND PIPE LO LEVEL -4FT - EXTINGUISHED

R-11

R-12 o Annunciator B-12. RCP B STAND PIPE LO LEVEL -4FT - EXTINGUISHED IF RCP'standpipe level low and CNMT radiation increasing. THEN # 3 seal leakage increase is probable.

Continue plant operation while closely monitoring RCP seal indications.

. I .

ACTION/EXPECTED RESPONSE lRESPONSE STEP NOT OBTAINED thersea falur inicaions aneleate NOTE Intheabsnceof #1sea NOTE: In the absence of other seal failure indications. an elevated #1 seal outlet temperature may indicate pump bearing damage.

9 Monitor RCP Seal Conditions:

a. RCP total #1 seal flow for each a. IF affected RCP running, THEN RCP return to Step 1. IF NOT. THEN perform the following:

o Total #1 seal flow - LESS THAN 6.0 GPM 1) Monitor affected RCP (Refer to ATT-15.1, ATTACHMENT RCP o Total #1 seal flow - GREATER DIAGNOSTICS).

THAN 0.8 GPM

2) Consult Plant Staff to determine if cooldown required.

b. RCP #1 Seal Leakoff Flow - b. Perform the following:

WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0, FIGURE RCP o Ensure seal injection flow SEAL LEAKOFF exceeds #1 seal leakoff flow.

o Refer to S-2.1. Reactor Coolant Pump Operation.

.. o Consult plant staff for further instructions.

c. RCP #1 seal outlet temperatures c. IF pump bearing damage is

- LESS THAN 2150 AND STABLE suspected. THEN notify plant staff and expedite shutdown of the affected RCP. IF NOT, THEN return to Step 1.

d. RCS leakage - NORMAL (Refer to d. Perform the following:

leakage surveillance sheet)

1) Calculate RCS leakrate.

2) Refer to ITS section 3.4.13.

0

EOP: TITLE: REV: 16 AP-RCP.1 RCP SEAL MALFUNCTION l PAGE 11 of 11 ACTION/EXPECTED RESPONSE llRESPONSE SP NOT OBTAINED I 10 Evaluate MCB Annunciator Status (Refer to AR Procedures)

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

11 Notify Higher Supervision

-END-

-1

. EOP: TITLE:

REV: 16 AP-RCP. 1 RCP SEAL MALFUNCTION PAGE 1 of 1 AP-RCP.1 APPENDIX LIST TITLE

1) FIGURE RCP SEAL LEAKOFF (FIG-4.0)

2) ATTACHMENT RCP DIAGNOSTICS (ATT-15.1)

ML040710638

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