ML040710638

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R. E. Ginna Nuclear Power Plant, Emergency Operating Procedures
ML040710638
Person / Time
Site: Ginna Constellation icon.png
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


Text

Rwev Always at Your Service Joseph A. Widay 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 C3 n ;

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

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NPSP0200 Ginna Nuclear Power Plant WRIGHTJ PROCEDURE INDEX INPUT PARAMETERS: TYPE:

PRAP STATUS VALUE(S):

EF. OU PRAP ABNORMALPROCEDURE PROCEDURE NUMBER PROCEDURE TITLE AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP AP-CCW.2 LOSS OF CCW DURING POWER OPERATION AP-CCW.3 LOSS OF CCW. PLANT SHUTDOWN AP-CR.1 CONTROL ROOM INACCESSIBILITY AP-CVCS.1 CVCS LEAK AP-CVCS.3 LOSS OF ALL CHARGING FLOW AP-CW.1 LOSS OF A CIRC WATER PUMP AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREOUENCY AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F)

AP-ELEC.13/15 LOSS OF BUS 13/15 AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 AP-FW.1 ABNORMAL MAIN FEEDWATER FLOW AP-IA.1 LOSS OF INSTRUMENT AIR AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWALANSERTION AP-RCC.2 RCCIRPI MALFUNCTION AP-RCC.3 DROPPED ROD RECOVERY AP-RCP.1 RCP SEAL MALFUNCTION AP-RCS.1 REACTOR COOLANT LEAK AP-RCS.2 LOSS OF REACTOR COOLANT FLOW AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY AP-RCS.4 SHUTDOWN LOCA AP-RHR.1 LOSS OF RHR AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDmONS AP-SG.1 STEAM GENERATOR TUBE LEAK AP-SW.1.

SERVICE WATER LEAK AP-SW.2 LOSS OF SERVICE WATER AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED Wed 3/3/2004 8:38:56 am Page 1 of 2 5 YEARS ONLY:

EFFECT LAST REV DATE REVIEW 016 0110712004 06/26/2002 018 05/08/2003 06/26/2002 015 11/19/2002 06126/2002 019 02125/2003 06/26/2002 013 06/26/2002 06/03/2002 004 08/26/2003 02/27/2004 011 06/26/2002 04/1612003 026 05/30/2003 06126/2002 010 06126/2002 06/26/2002 012 05/3012003 06/26/2002 000 09124/2003 09/24/2003 007 08126/2003 06/26/2002 006 05/30/2003 06/2612002 015 05/0812003 06/26/2002 018 06/26/2002 04/16/2003 014 05/08/2003 06/26/2002 008 06/26/2002 04116/2003 010 0612612002 01/2212002 006 02/25/2003 02/25/2003 016 03103/2004 04/24/2003 016 06126/2002 04/16/2003 011 06/26/2002 04/1612003 010 06/2612002 04/01/2002 014 04/30/2003 04/30/2003 019 04/30/2003 04/30/2003 013 04/30/2003 04/30/2003 003 11/21/2002 06/26/2002 019 05/30/2003 04/21/2003 004 05/30/2003 10/31/2001 012 05/08/2003 06/26/2002 NEXT REVIEW 06/26/2007 06/26/2007 06/26/2007 06/26/2007 06/03/2007 02127/2009 04/16/2008 06/26/2007 0612612007 06/26/2007 09/24/2008 06/26/2007 06/26/2007 06/26/2007 04/1612008 06/26/2007 04/16/2008 0112212007 02125/2008 04/24/2008 04/16/2008 04/16/2008 01/22/2007 04/30/2008 04/30/2008 04/30/2008 06/26/2007 04/21/2008 10/31/2006 06/26/2007 ST EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF EF

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PRAP PRAP ABNORMAL PROCEDURE Ginna Nuclear Power Plant Wed 3/3/2004 8:38:56 am PROCEDURE INDEX Page 2 of 2 I -

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EF. OU 5 YEARS ONLY:

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-~w~co 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:

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

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

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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

  1. -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, MOV-313 - OPEN
a. Perform the following:
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 -

OPEN

  • RCP A. AOV-270A
  • RCP B. AOV-270B
b. Manually open valves.

IF valves can NOT be opened. THEN verify IA aligned to CNMT and go to Step 3.

1

EOP:

TITLE:

REV: 16 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 6 of 11 STE ACTION/EXPECTED RESPONSE llRESPONSE 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b. Each RCP Total I 1 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

EOP:

TITLE:

REV: 16 AP-RCP.1 RCP SEAL MALFUNCTION PAGE 8 of 11 SP ACTION/EXPECTED RESPONSE llRESPONSE NOT OBTAINED I NOTE:

ATT-15.1. ATTACHMENT RCP DIAGNOSTICS may be used to aid in diagnosis.

5 Check RCP Cooling:

o Annunciator A-7. RCP A CCW RETURN HIGH TEMP OR LOW FLOW -

EXTINGUISHED o Annunciator A-15. RCP B CCW RETURN HIGH TEMP OR LOW FLOW -

EXTINGUISHED Perform the following:

a. Verify RCP CCW supply and return valves open.

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

  • RCP B. MOV-749B and MOV-759B
b. Ensure open CCW outlet valves from RCP thermal barriers.
  • RCP A. AOV-754A

. RCP B. AOV-754B 6 Check RCP #2 Seal Indications:

o Annunciator B-3. RCP A STANDPIPE HI LEVEL 41 FT - EXTINGUISHED o Annunciator B-4. RCP B STANDPIPE HI LEVEL +1 FT - EXTINGUISHED IF affected RCP #1 seal leakoff flow decreasing. THEN failure of #2 seal may be indicated.

Check RCP #2 seal leak rate to RCDT (PPCS Point ID L1003. 3.2 gal/% in 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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 GREATER WATER Labyrinth Seal D/Ps THAN 15 INCHES OF Perform the following:

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:

o Annunciator B-li. RCP A STAND PIPE LO LEVEL -4FT - EXTINGUISHED o Annunciator B-12. RCP B STAND PIPE LO LEVEL -4FT - EXTINGUISHED Check CNMT radiation monitors normal.

  • R-11
  • R-12 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.

STEP ACTION/EXPECTED RESPONSE lRESPONSE NOT OBTAINED NOTE Intheabsnceof thersea falur inicaions aneleate #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 RCP o Total #1 seal flow - LESS THAN 6.0 GPM o Total #1 seal flow - GREATER THAN 0.8 GPM
b. RCP #1 Seal Leakoff Flow -

WITHIN THE NORMAL OPERATING RANGE OF FIG-4.0, FIGURE RCP SEAL LEAKOFF

a. IF affected RCP running, THEN return to Step 1. IF NOT. THEN perform the following:
1) Monitor affected RCP (Refer to ATT-15.1, ATTACHMENT RCP DIAGNOSTICS).
2) Consult Plant Staff to determine if cooldown required.
b. Perform the following:

o Ensure seal injection flow 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

- LESS THAN 2150 AND STABLE

d. RCS leakage - NORMAL (Refer to leakage surveillance sheet)
c. IF pump bearing damage is suspected. THEN notify plant staff and expedite shutdown of the affected RCP.

IF NOT, THEN return to Step 1.

d. Perform the following:
1) Calculate RCS leakrate.
2) Refer to ITS section 3.4.13.

0

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TITLE:

REV: 16 AP-RCP.1 RCP SEAL MALFUNCTION l

PAGE 11 of 11 SP ACTION/EXPECTED RESPONSE llRESPONSE 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-

EOP:

TITLE:

AP-RCP. 1

-1 RCP SEAL MALFUNCTION REV: 16 PAGE 1 of 1 AP-RCP.1 APPENDIX LIST 1) 2)

TITLE FIGURE RCP SEAL LEAKOFF (FIG-4.0)

ATTACHMENT RCP DIAGNOSTICS (ATT-15.1)

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