ML031750328

From kanterella
Revision as of 05:41, 22 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Emergency Operating Procedures
ML031750328
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/30/2003
From: Widay J
Rochester Gas & Electric Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML031750328 (9)
v • d • e


Text

{{#Wiki_filter:Rl ~4 A Subsidiary of RGS Energy Group, Inc. ROCHESTER GAS AND ELECTRIC CORPORATION

  • 89 EASTAVENUE, ROCHESTER, N.Y. 14649-0001
  • 716-771-3250 www.rge.com JOSEPH A. WIDAY VICE PRESIDENT &PLANT MANAGER GINNA STATION May 30, 2003 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, sept A.W id 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 E-2, Rev 11 ECA-0.2, Rev 15 FR-H.2, Rev 5 ATI Index E-3, Rev 34 ECA-1.1, Rev 22 FR-H.3, Rev 6 E, ECA, ES Index ES-0., Rev 21 ECA-1.2, Rev 5 FR-H.4, Rev 5 FR Index ES-0.2, Rev 13 ECA-2. 1, Rev 26 FR-H.5, Rev 9 A1T-2.4, Rev 2 ES-0.3, Rev 9 ECA-3.1, Rev 26 FR-P.1, Rev 26 AP-ELEC.1, Rev 26 ES-1.1, Rev 25 ECA-3.2, Rev 27 FR-P.2, Rev 8 AP-ELEC.3, Rev 12 ES-1.2, Rev 26 ECA-3.3, Rev 29 FR-Z.1, Rev 7 AP-ELEC.14116, Rev 6 ES-1.3, Rev 36 FR-S.1, Rev 15 FR-Z.2, Rev 5 AP-ELEC.17/18, Rev 6 ES-3.1, Rev 15 FR-S.2, Rev 9 FR-Z.3, Rev 5 D(9;--- AP-SW.1, Rev 19 AP-SW.2, Rev 4 E-0, Rev 34 ES-3.2, Rev 16 ES-3.3, Rev 16 ECA-0.0, Rev 25 FR-C.1, Rev 20 FR-C.2, Rev 17 FR-C.3, Rev 9 FR-I.1, Rev 16 FR-I.2, Rev 11 FR-I.3, Rev 18 A E-1, Rev 28 ECA-0. 1, Rev 22 FR-H.1, Rev 29 

    !                                                                    (                                                            (

NPSP0200 Ginna Nuclear Power Plant Thu 5/29/2003 3:37:07 pm WRIGHTJ PROCEDURE INDEX Page 1 of 7 INPUT PARAMETERS: TYPE: PRAP, PRATT, PRE STATUS VALUE(S): EF, QI 5 YEARS ONLY: PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE RIEIEW 0EVEW ST AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 015 06/26/2002 06/26/2002 06/26/2007 EF AP-CCW.2 LOSS OF CCW DURING POWER OPERATON 018 05108/2003 06/26/2002 06/26/2007 EF AP-CCW.3 LOSS OF CCW -PLANT SHUTDOWN 015 11/19/2002 06/26/2002 06/26/2007 EF AP-CR.1 CONTROL ROOM INACCESSIBILrTY 019 02/25/2003 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 003 06/26/2002 02/26/1999 02/26/2004 EF AP-CW.1 LOSS OF A CIRC WATER PUMP 011 06/26/2002 04/16/2003 04/16/2008 EF AP-ELEC.1 LOSS OF 12A AND/OR 128 BUSSES 026 05/30/2003 06/26/2002 06/26/2007 EF AP-ELEC.2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUENCY 010 06/26/2002 06/26/2002 06/26/2007 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER (BELOW 350 F) 012 05/30/2003 06/26/2002 06/26/2007 EF AP-ELEC.14/16 LOSS OF SAFEGUARDS BUS 14/16 006 05/30/2003 06/26/2002 06/26/2007 EF AP-ELEC.17/18 LOSS OF SAFEGUARDS BUS 17/18 006 05/30/2003 06/26/2002 06/26/2007 EF AP-FW.A ABNORMAL MAIN FEEDWATER FLOW 015 05/08/2003 06/26/2002 06/26/2007 EF AP-IA.1 LOSS OF INSTRUMENT AIR 018 06/26/2002 04/16/2003 04/16/2008 EF AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 014 05/08/2003 06/26/2002 06/26/2007 EF AP-RCC.1 CONTINUOUS CONTROL ROD WITHDRAWAL/lNSERTION 008 06/26/2002 04/16/2003 04/16/2008 EF AP-RCC.2 RCCIRM MALFUNCTION 010 06/26/2002 01/22/2002 01/22/2007 EF AP-RCC.3 DROPPED ROD RECOVERY 006 02/25/2003 02/25/2003 02/25/2008 EF AP-RCP.1 RCP SEAL MALFUNCTION 015 05/08/2003 04/24/2003 04/24/2008 EF AP-RCS.1 REACTOR COOLANT LEAK 016 06/26/2002 04/16/2003 04/16/2008 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 011 06/26/2002 04/16/2003 04/16/2008 EF AP-RCS.3 HIGH REACTOR COOLANT ACTMTY 010 06/26/2002 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 VITHOUT RX TRIP REQUIRED 012 05/08/2003 06/26/2002 06/26/2007 EF AP-TURB.2 TURBINE LOAD REJECTION 018 06/26/2002 06/26/2002 06/26/2007 EF xcJ

( ( ( NPSP0200 Ginna Nuclear Power Plant Thu 5/29/2003 3:37:07 pm WRIGtlTJ PROCEDURE INDEX Page 2 of 7 INPUT PARAMETERS: TYPE: PRAP, PRATT, PRE STATUSVALUE(S): EF,QU 5YEARS ONLY: sv . < swe~*os.*..e)se c . PRAP ABNORMAL PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TTLE REV DATE REVIEW REVIEW ST AP-TURB.3 TURBINE VIBRATION 011 06/26/2002 06/26/2002 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: 33

( ( NPSP0200 Ginna Nuclear Power Plant Thu 5/29/2003 3:37:07 pm WRIGHTJ PROCEDURE INDE) Page 3 of 7 !ff* 6 aS'- -*,§,: T:J.tY}8-.*" , elf:¢4:, A-, ,TJVALUE(S:-r. i- . i1-- J IIerII d _' 1. - - - O-L 'Y -Y . -' '  ! INPUT PARAMETERS: TYPE: PRAP, FFRATT,PRE STATUSVALUE(S): EF,QU 5 YEARtS ONLY: 'Ia_*2Ww'0.7a14P 1W94twn t ,4*'eflrrw- fla'*W,a _ ___t Gt.tltS SsivAll'IG t';^.zu-{r-.-l.*11.1'.-f*. Lr.w> -. .X;. ds¢*N-17:',Ie - w K 11 ~ ~ ~ 1-1 ---- I~I. . - -- 11^Cs1^S " - /t .r PRATT EOP ATTACHMENTS PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVEW ST ATT-1.0 ATTACHMENT AT POWER CCW ALIGNMENT 003 02/12/2003 02/12/2003 02/12/2008 EF ATT-1.1 ATTACHMENT NORMAL CCW FLOW 000 05/18/2000 05/18/2000 05/18/2005 EF ATT-2.1 ATTACHMENT MIN SW 005 02/01/2001 02/03/2003 02/03/2008 EF ATT-2.2 ATTACHMENT SW ISOLATION 008 03/06/2002 03/27/2003 03/27/2008 EF ATT-2.3 ATTACHMENT SW LOADS INCNMT 004 03/06/2002 12/31/1999 12/31/2004 EF ATT-2.4 ATTACHMENT NO SW PUMPS 002 05/30/2003 1013112001 10/31/2006 EF ATT-2.5 ATTACHMENT SPLIT SW HEADERS 000 06/26/2002 06/26/2002 06/26/2007 EF ATT-3.0 ATTACHMENTC/CVI 006 03/06/2002 01/06/1999 01/06/2004 EF ATT-3.1 ATTACHMENT CNMT CLOSURE 004 03/06/2002 01/25/1999 01/25/2004 EF ATT-4.0 ATTACHMENT CNMT RECIRC FANS 003 07/26/1994 03/27/2003 03/27/2008 EF ATT-5.0 ATTACHMENT COND TO S/G 005 03/06/2002 12/3111999 12/31/2004 EF ATT-5.1 ATTACHMENT SAFW 008 05/30/2002 12/31/1999 12/31/2004 EF ATT-5.2 ATTACHMENT FIRE WATER COOLING TO TDAFW PUMP 003 01/14/1999 01/14/1999 01/14/2004 EF ATT-6.0 ATTACHMENT COND VACWM 003 12/18/1996 02/03/2003 02/03/2008 EF ATT-7.0 ATTACHMENT CR EVAC 006 03/06/2002 02/03/2003 02/03/2008 EF ATT-8.0 ATTACHMENT DC LOADS 006 03/22/1999 01/14/1999 01/14/2004 EF ATT-8.1 ATTACHMENT DIG STOP 005 03/06/2002 02/03/2003 02/03/2008 EF ATT-8.2 ATTACHMENT GEN DEGAS 008 06/20/2002 08/17/1999 08/17/2004 EF ATT-8.3 ATTACHMENT NONVITAL 004 03/06/2002 02/03/2003 02/03/2008 EF ATT-8.4 ATTACHMENT SWV 005 03/06/2002 02/03/2003 02/03/2008 EF ATT-8.5 ATTACHMENT LOSS OF OFFSITE POWER 000 05/02/2002 05/02/2002 05/02/2007 EF ATT-9.0 ATTACHMENT LETDOWN 008 03/06/2002 03/06/2002 03/06/2007 EF ATT-9. 1 ATTACHMENT EXCESS LID 005 03/06/2002 10/3112001 10/31/2006 EF ATT-10.0 ATTACHMENT FAULTED S/G 006 03/06/2002 03/27/2003 03/27/2008 EF ATT-11.0 ATTACHMENT IACONCERNS 002 04/07/1997 03/27/2003 03/27/2008 EF ATT-11.1 ATTACHMENT IASUPPLY 003 03/06/2002 03/27/2003 03/27/2008 EF ATT-11.2 ATTACHMENT DIESEL AIR COMPRESSOR 004 11/18/2002 03/10/2003 03/10/2008 EF ATT-12.0 ATTACHMENT N2 PORVS 005 02/12/2003 02/12/2003 02/12/2008 EF ATT-13.0 ATTACHMENT NC 003 02/12/2003 02/12/2003 02/12/2008 EF ATT-14.0 ATTACHMENT NORMAL RHR COOLING 003 03/06/2002 09/23/1999 09/23/2004 EF

( ( ( NPSP0200 Ginna Nudear Power Plant Thu 5/29/2003 3:37:08 pm WRIGHTJ PROCEDURE INDEX Page 4 of 7 

                                                     .          *     -, -.        -  %A-N I             i .             r         .                     I-,-

INPUT PARAMETERS: TYPE: PRAP, F'RATT, PRE STATUS VALUE(S): EF, QU 5 YEARS ONLY: wn ,.fl -r,4 ^v9mtt*-%@, 1.2..-.gi ` K5v~9-t{> -.. .!-' -- ,',-,nl --- n-PRATT EOP ATTACHMENTS PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TrrLE REV DAkTE REVIEW REVIEW ST ATT-14.1 ATTACHMENT RHR COOL 006 04/30/2003 01/08/2002 01/08/2007 ATT-14.2 ATTACHMENT RHR ISOL 003 0212/2003 02/1212003 02/12V2008 ATT-14.3 ATTACHMENT RHR NPSH 003 03/06/2002 01/06/1999 01/06/2004 E: ATT-14.5 ATTACHMENT RHR SYSTEM 003 03/20/2003 02/03/2003 02/03/2008 E: ATT-14.6 ATTACHMENT RHR PRESS REDUCTION 002 03/06/2002 01/14/1999 01/14/2004 ATT-15.0 ATTACHMENT RCP START 009 03/06/2002 03/17/2000 03/17/2005 E: ATT-15.1 ATTACHMENT RCP DIAGNOSTICS 003 04/24/1997 02/03/2003 02/03/2008 E: ATT-15.2 ATTACHMENT SEAL COOLING 005 03/06/2002 0203/2003 02/03/2008 E: ATr-16.0 ATTACHMENT RUPTURED S/G 011 07/18/2001 01/11/2000 01/11/2005 E: ATT-16.1 ATTACHMENT SGTL 002 03/06/2002 09/08/2000 09/08/2005 E: ATT-16.2 ATTACHMENT RCS BORON FOR SGTL 002 04/09/2002 09/08/2000 09/08/2005 E: ATT-17.0 ATTACHMENT SD-1 014 06/20/2002 02/29/2000 02/28/2005 E: ATT-17.1 ATTACHMENT SD-2 006 03/06/2002 01/30/200t 01/30/2006 E: ATT-18.0 ATTACHMENT SFP - RWST 005 03/06/2002 02/03/2003 0203/2008 E: ATT-20.0 ATTACHMENT VENT TME 003 07/26/1994 02/03/2003 02/03/2008 E: ATT-21.0 ATTACHMENT RCS ISOLATION 002 03/06/2002 0203/2003 02/03/2008 E: ATT-22.0 ATTACHMENT RESTORING FEED FLOW 003 05/02V2002 01/22V2002 01/22V2007 ATT-23.0 ATTACHMENT TRANSFER 4160V LOADS 000 02/26/1999 02/26/1999 02/26/2004 ATT-24.0 ATTACHMENT TRANSFER BATTERY TO TSC 000 09/08/2000 09/08/2000 09/08/2005 ATT-26.0 ATTACHMENT RETURN TO NORMAL OPERATIONS 000 10/31/2001 10/31/2001 10/31/2006 PRATT TOTAL: 50

( ( ( NPSP0200 Ginna Nudear Power Plant Thu 5/29(2003 3:37:08 pm WRIGHTJ PROCEDURE INDEX Page 5 of 7 4tWn., M-t, %fw.m4l .r V m, "'r^f~ .r tn<<..* rf INPUT PARAMETERS: TYPE: PRAP, PRATT, PRE STATUS VALUE(S): EF, QU 5 YEARS ONLY: 

                                                          ?_.t A, - t*n. i t  ,t   VM         *. r-.        *.&.~w r . ^ 'f,-  r   r2.

PRE EMERGENCY PROCEDURE PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST E-0 REACTOR TRIP OR SAFETY INJECTION 034 05/30/2003 03/24/2003 03/24/2008 EF E-1 LOSS OF REACTOR OR SECONDARY COOLANT 028 05/30/2003 03/24/2003 03/24/2008 EF E-2 FAULTED STEAM GENERATOR ISOLATION 011 05/30/2003 03/24/2002 03/24/2007 EF E-3 STEAM GENERATOR TUBE RUPTURE 034 05/30/2003 03/24/2003 03/24/2008 EF PRE TOTAL: 4

( ( ( NPSP0200 Ginna Nudear Power Plant Thu 5/29/2003 3:37:08 pm WRIGHTJ PROCEDURE INDEX Page 6of 7 

  *.'~Wrin.~w    'r  "-' ,k        *'.fr'                         '     w             s      M    .              . r               r       f     I :      "  i INPUT PARAMETERS: TYPE:                           PRAP, PRATT. PRE               STATUS VALUE(S):    EF, QU               5 YEARS ONLY:

n

  • rWW J 'a, rss' h 14ma.M .rcW, ta# ,, ** V f I ' Ii - F' - F' PRECA EMERGENCY CONTINGENCY ACTIONS PROC PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TrTLE REV DATE R3/V/EW ST ECA-0.0 LOSS OF ALL AC POWER 025 05/30/2003 03/24/2003 03/24/2008 EF ECA-0.1 LOSS OF ALL AC POWER RECOVERY WITHOUT SI REQUIRED 022 05/30/2003 03/24/2003 03/24/2008 EF ECA-0.2 LOSS OF ALL AC POWER RECOVERY WITH SI REQUIRED 015 05/30/2003 03/24/2003 03/24/2008 EF ECA-1.1 LOSS OF EMERGENCY COOLANT RECIRCULATION 022 05/30/2003 03/24/2003 03/24/2008 EF ECA-1.2 LOCA OUTSIDE CONTAINMENT 006 05/30/2003 03/24/2003 03/24/2008 EF ECA-2.1 UNCONTROLLED DEPRESSURIZATION OF BOTH STEAM GENERATORS 026 05/30/2003 03/2412003 03/24/2008 EF ECA-3.1 SGTR WITH LOSS OF REACTOR COOLANT SUBCOOLED RECOVERY DESIRED 026 05/30/2003 03/24/2003 03/24/2008 EF ECA-3.2 SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED 027 05/30/2003 03/24/2003 03/24/2008 EF ECA-3.3 SGTR WHOUT PRESSURIZER PRESSURE CONTROL 029 05/30/2003 03/24/2003 03/24/2008 EF PRECA TOTAL: 9

( ( ( NPSP0200 Ginna Nudear Power Plant Thu 5/29/2003 3:37:08 pm WRIGHTJ PROCEDURE INDEX Page 7 of 7 INPUT PARAMETERS: TYPE: PRAP, PRATT, PRE STATUS VALUE(S): EF, QU 5 YEARS ONLY: r..>. t.rti 

                                                                                                        ...Ud'<->.
                                                                                                                                 -,,,,y, PRES           EQUIPMENT SUB-PROCEDURE PROCEDURE                                                                                    EFFECT                    LAST                NEXT NUMBER                                                                                 REV    DATE                   RE0VEW              REVIEW    -

ST ES-0.0 REDlAGNOSIS 010 05/01/1998 03/24/2003 03/24/2008 EF ES-0.1 REACTOR TRIP RESPONSE 021 05/30/2003 03/24/2003 03/24/2008 EF ES-0.2 NATURAL CIRCULATION COOLDOWN 013 05/30/2003 03/24/2003 03/24/2008 EF ES-0.3 NATURAL CIRCULATION COOLDOWN WITH STEAM VOID INVESSEL 009 05/30/2003 03/24/2003 03/24/2008 EF ES-1.1 Si TERMINATION 025 05/30/2003 03/24/2003 03/24/2008 EF ES-1.2 POST LOCA COOLDOWN AND DEPRESSURIZATION 026 05/30/2003 03/24/2003 03/24/2008 EF ES-1.3 TRANSFER TO COLD LEG RECIRCULATION 036 05/30/2003 03/24/2003 03/24/2008 EF ES.3.1 POST-SGTR COOLDOWN USING BACKFILL 015 05/30/2003 03/24/2003 03/24/2008 EF ES-3.2 POST-SGTR COOLDOWN USING BLOWDOWN 016 05/30/2003 03/24/2003 03/24/2008 EF ES-3.3 POST-SGTR COOLDOWN USING STEAM DUMP 016 05/30/2003 03/24/2003 03/24/2008 EF PRES TOTAL: 10 GRAND TOTAL: 106

NPSP0200 Ginna Nuclear Power Plant Wed 611812003 3:14:59 pm co WRIGHTJ PROCEDURE INDEX Page 1 of 1 INPUT PARAMETERS: TYPE: PRFR STATUSVALUE{S): EF 5 YEARS ONLY: I-I- PRFR FUNClONAL RESTORATlON GUIDELINE PROC PROCEDURE EFFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEHf REVIEWN ST FR-C.1 RESPONSE TO INADEQUATE CORE COOLING 020 05J3012003 03124f2003 03)2412008 EF FR-C.2 RESPONSE TO DEGRADED CORE COOLING 017 0513012003 03124J2003 O3242008 EF FR-C-3 RESPONSE TO SATURATED CORE COOLING 009 05130f2003 03f24J2003 0312412008 iT FR-Hil RESPONSE TO LOSS OF SECONDARY HEAT SINK 029 05130/2003 0312412003 03(2412008 EF FR-H.2 RESPONSE TO STEAM GENERATOR OVERPRESSURE 005 05F30/2003 03124)2003 0324)2008 EF FR-H.3 RESPONSE TO STEAM GENERATOR HIGH LEVEL 006 0513012003 0312412003 03124)2008 6= FR-HA RESPONSE TO LOSS OF NORMAL STEAM RELEASE CAPABILITIES 005 0530203 03J2412003 03124J2008 EF FR-H.5 RESPONSE TO STEAM GENERATOR LOW LEVEL 009 05130J2003 03)24120D3 03V2412008 EF FR4.1 RESPONSE TO HIGH PRESSURIER LEVEL 016 05J3012003 03)2412003 03124)20D8 EF FR-1 2 RESPONSE TO LOW PRESSURIZER LEVEL 011 05)3012003 03fZ4f2003 03)24f2008 EF FR-1.3 RESPONSE TO VOIDS IN REACTOR VESSEL 018 05130/2003 0312412003 0312412008 6F FR-P.1 RESPONSE TO I/INElNT PRESSURED TERMAL SHiOCK CONDfrON 026 0513012003 03(2412003 0312412008 EF FR-P2 RESPONSE TO ANTICIPATED PRESSUR0E THERM LSHOCK CONDMON 008 05130/2003 03124)2003 0312412008 F= FR-S.1 RESPONSE TO REACTOR RESTART/AWS 015 0513012003 03J24J2003 03t24/2008 EF FR-S2 RESPCNSE TO LOSS OF CORE SHUTDOWN 009 0513012003 0312412D03 03/2412008 EF FR-Z.1 RESPONSE o HIGH GONTAINMENT PRESSURE 007 0513012003 03)2412003 0312412008 E= FR-Z2 RESPONSE TO OONTAINMENT FLOOOG 005 0513012003 0312412003 0312412008 EF FR-Z.3 RESPONSE TO HIGH CONTAINMENT RADIATON LEVEL 005 05130(2003 03)24/2003 03)2412008 EF PRFR TOTAL: 18 GRAND TOTAL 18}}

Retrieved from "https://kanterella.com/w/index.php?title=ML031750328&oldid=2654530"