ML040710638
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) | |
Text
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
(. ( f f. - - I NPSP0200 Ginna Nuclear Power Plant Wed 3/3/2004 8:38:56 am WRIGHTJ PROCEDURE INDEX Page 2 of 2 "I' $ '_.<
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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
- 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
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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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
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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
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.
- 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 />.
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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)