ML17265A409

Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr

ML17265A409
Person / Time
Site:	Ginna
Issue date:	08/24/1998
From:	WIDAY J A ROCHESTER GAS & ELECTRIC CORP.
To:	VISSING G S NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AP-SW.1, NUDOCS 9809010319
Download: ML17265A409 (20)

Text

f.;rVCATEGORY 1 REGULAT Y INFORMATION DISTRIBUTXON SYSTEM (RIDS)ACCESSION NBR:9809010319 DOC.DATE: 98/08/24 NOTARIZED:

NO DOCKET¹FACIL:50-244 Robert Emmet Ginna NuclearaPlant, Unit 1, Rochest'er G 05000244 AUTH.NAME s AUTHOR AFFILIATION WIDAY,U.A.

Rochester Gas&Electric Corp..g~~gf PC6ct/~~RECIP.NAME RECIPIENT AFFILIATION VXSSING,G.S

SUBJECT:

Rev 13 to AP-SW.1","Svc Water Leak." W/980824 ltr.DISTRIBUTION CODE: A002D COPIES RECEIVED:LTR L ENCL 1 SIZE:)TITLE: OR Submittal:Inadequate Core Cooling (Item IX.F.2)GL 82-28 NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)

.A T 05000244 RECIPIENT XD CODE/NAME PD1-1 PD INTERNAL:~EN'ES DE RES/DSXR/RPSB EXTERNAL: NOAC.COPIES LTTR ENCL 1 1 1 1 1 1 1 1 RECIPIENT XD CODE/NAME VISSING,G.

NRR/DSSA/SRXB RES/DET/EXB NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 NOTE TO ALL ERIDSE RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE.TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COP IES RECE IVED BY YOU OR YOUR ORGANI ZATION i CONTACT THE DOCUMENT CONTRO1 DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

pt~/z/I//z//z z/zz/z/z z/I////I/I//zz/zz/I/zzzz//I'lw t 1\I owns ROCHESTERGASANDEI ECTRICCORPORATIONa 89EASTAVENUE, ROCHESTER, N.Y.14649<001 JOSEPH A.WIDAY Ptont Managor Ginna Nucroar Pront August 24, 1998 TELEPHONE AREA CODE 7IS 546 2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I-1 Washington, D.C.20555

Subject:

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

Dear Mr.Vissing:

As requested, enclosed are Ginna Station Emergency Operating Procedures.

Very truly your's, se h 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-SW.1, Rev 13'tt8090i03i9

'tt80824 PDR ADOCK 05000244 P.'DR REPORT NO.01 REPORT: NPSP0200 DOC TYPE: PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 05/22/97 PAGE: 1 PARAMETERS:

DOC TYPES-PRATT PRAP PRECA PRPT STATUS: EF QU 5 YEARS ONLY: PROCEDURE MRCBER AP-.1 AP-CCW.2 AP-CCW.3 AP-CR.1 AP-CVCS.1 AP-CW.1 AP-ELEC.1 AP ELEC,2 AP-ELEC.3 AP-FW.1 AP-IA.1 AP-PRZR.1 AP-RCC.l AP RCC.2 AP-RCC.3 AP-RCP.1 AP-RCS.1 AP-RCS.2 AP-RCS.3 AP-RCS.4.AP-RHR.1 AP-RHR.2 AP-EWE AP-TURB.1 PROCEDURE TITLE LEAKAGE INTO THE COMPONENT COOLING LOOP LOSS OF CCW DURING POWER OPERATION LOSS CCW-PLANT SHUTDOWN CONTROL ROOM I ACCESSIBILITY CVCS LEAK LOSS OP A CIRC WATER PUMP LOSS OF 12A AND/OR 12B BUSSES SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUEN Y LOSS OF 12A AND/OR 12B TRANSFORMER

{BELOW 350 F)PARTIAL OR COMPLETE LOSS OP MAIN FEEDWATER LOSS OP INSTRUMENT AIR ABNORMAL PRESSURIZER PRESSURE CONTINUOUS CONTROL ROD WITHDRAWAL/INSER ON RCC/RPI MALFUNCTION DROPPED ROD RECOVERY RCP SEAL MALFUNCI'ION REACTOR COOLANT LEAK LOSS OF REACTOR COOLANT FLOW HIGH REACTOR COOLANT ACTIVITY SHUTDOWN LOCA LOSS OP RHR LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS SERVICE WATER LEAK TURBINE TRIP WITHOUT RX TRIP REQUIRED EFFECT REV DATE LAST REVIEW NEXT REVIEW ST 011 02/24/96 04/20/95 04/20/00 EF 012 02/24/96 08/30/94 08/30/99 EF 010 03/29/96 08/30/94 08/30/9 EF 014 12/18/96 11/17/9 11/17/99 EF 011 06/03/9~6/20/95 007~11/96 04/21/93 01 06/03/96 03/21/95 04/20/00 EP 04/21/98 EF 03/21/00 EF 007 02/11/94 02/11/94 02/11/99 EF 003 05/22/97 03/06/93 03/06/98 EF 010 06/03/96 04/21/93 04/21/98 EF 013 04/07/97 09/09/94 09/09/99 EF 009 06/03/96 09/29/94 09/29/99 EF 006 02 96 06/04/93 06/04/98 EF 007 02/06/97 4/23/93 04/23/98 EF 002 06/03/96 04/23 3 04/23/98 EF 010 05/31/96 04/20/95 011 06/03/96 04/20/95 4+20/00 EF 04/20 EF 008 06/03/96 10/08/93 10/08/98 E 006 04/23/93 04/23/93 04/23/98 EF 006 11/08/96 04/20/95 04/20/00 EF 010 03/29/96 03/06/93 03/06/98 EF 007 05/15/97 03/21/95 03/21/00 EF 010 02/24/96 07/29/93 07/29/98 EF 008 06/03/96 05/07/93 05/07/98 EF REPORT NO.01 REPORT: NPSP0200 DOC TYPE: PRAP GINNA NUCLEAR POWER PLANT PROCEDURES INDEX ABNORMAL PROCEDURE 05/22/97 PAGE: 2 PARAMETERS:

DOC TYPES-PRATT PRAP PRECA PRPT STATUS: EF QU 5 YEARS ONLY: PROCEDURE NUMBER AP-TURB.2 AP-TURB.3 AP TURB.4 AP-TURB.5 PROCEDURE TITLE TURBINE LOAD REJECTION TURBINE VIBRATION LOSS OF CONDENSER VACUA RAPID LOAD REDUCTION REV Ef FECT DATE LAST REVIEW NEXT REVIEW ST 015 06/03/96 06/04/93 06/04/98 EF 008 12/04/96 03/26/93 03/26/98 EF 011 06/03/96 03/26/93 03/26/98 EF 002 06/03/96 07/10/95 07/10/00 EF TOTAL FOR PRAP 28 EOPt AP-SW.1 TITLE!SERVICE WATER LEAK REV: 9 PAGE 1 of 10 ROCHESTER GAS AND ELECTRIC CORPORATION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVIEW PORC REVIEW DATE 7~F/B PLANT SUPERINTENDENT

'EFFECTIVE DATE CATEGORY 1.0 REVIEWED BY:

EOP: AP-SW.1 SERVICE WATER LEAK REV: 9 PAGE 2 of 10 A.PURPOSE-This procedure provides the necessary instructions to respond to a service water system leak.B.ENTRY CONDITIONS/SYMPTOMS 1.SYMPTOMS-The symptoms of SERVICE WATER LEAK are: a.Service water header pressure low alarms on computer, or b.Sump pump activity increases in containment, the AUX BLDG, or INT BLDG, OR c.Unexplained increase in the waste hold-up tank, or d.Visual observation of a SW leak, or e.Annunciator C-2, CONTAINMENT RECIRC CLRS WATER OUTLET HI TEMP 217'F, lit, or f.Annunciator C-10, CONTAINMENT RECIRC CLRS WATER OUTLET LO FLOW 920 GPM, lit, or g.Annunciator E-31, CONTAINMENT RECIRC FAN CONDENSATE HI-HI LEVEL alarm, exhibits an unexplained increase in frequency, or h.Annunciator H-6, CCW SERVICE WATER LO FLOW 1000 GPM, lit.

F.OP s AP-SW.1 T1TLE: SERVICE WATER LEAK REV: 9 PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION 0 IF>AT ANY TIME DURING THI S PROCEDURE y A REACTOR TRI P OR S I OCCURS y E 0 y REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED' IF EITHER D/G RUNNING WITHOUT SW COOLING AVAILABLE, THEN STOP THE AFFECTED D/G TO PREVENT OVERHEATING.

1 Verify 480V AC Emergency Busses 17 and 18-ENERGIZED Ensure associated D/G(s)running and attempt to manually load busses 17 and/or 18 onto the D/G(s)if necessary.

2 Verify At Least One SW Pump Running In Each Loop:~A or B pump in loop A~C or D pump in loop B IF a SW pump has tripped, THEN ensure other pump in the affected loop is running.

EOP s AP-SW.1 SERVICE WATER LEAK REV: 9 PAGE 4 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: Abnormally low pressure in either SW loop may indicate that the idle pump check valve is open.This may be corrected by restarting or isolating the idle pump.3 Check SW System Status: a.Check SW loop header pressures; o Pressure in both loops APPROXIMATELY EQUAL o PPCS SW low pressure alarm status-NOT LOW o Pressure in both loops STABLE OR INCREASING b.Check SW loop header pressures GREATER THAN 55 PSIG a.IF three SW pumps operating and either loop pressure less than 40 psig, THEN trip the reactor and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

IF only two SW pumps operating and either loop pressure less than 45 psig, THEN start one additional SW pump (258 kw each pump)b.IF either SW loop pressure is less than 55 PSIG with three SW pumps running AND cause can NOT be corrected, THEN initiate a controlled shutdown while continuing with this procedure (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN).

~I EOP: AP-SW.1 SERVICE WATER LEAK REV: 9 PAGE 5 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED , NOTE: o If SW is lost to any safeguards equipment, the affected component should be declared inoperable and appropriate actions taken as required by Tech Specs, Section 3.o CNMT sump A level of 10 feet is approximately 6 feet 6 inches below the bottom of the reactor vessel.4 Check For SW Leakage In CNMT: a.Check Sump A indication o Sump A level-INCREASING a.IF the SW leak is NOT in the CNMT, THEN go to Step 6.-OR-o Sump A pump start frequency-INCREASING (Refer to RCS Daily Leakage Log)b.Evaluate Sump A conditions:

1)Verify Leakage within capacity of one Sump A pump (50 gpm)2)Check Sump A level-LESS THAN 10 FEET b.Plant shutdown should be considered, consult plant staff.c.Direct HP to establish conditions for CNMT entry l~~

EOP: AP-SW.1 T1TLE: SERVICE WATER LEAK REV: 9 PAGE 6 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*****************************************CAUTION BEFORE ISOLATING SW TO CNMT RECIRC FANS, REFER TO TECH SPEC SECTION 3.3.2 FOR OPERABILITY REQUIREMENTS.

NOTE: o One Reactor Compartment cooling fan should be running whenever RCS temperature is greater than 135'F.o CNMT recirc fan condensate collector level indicators may be helpful in identifying a leaking fan cooler.5 Check CNMT recirc fan indications:

o CNMT recirc fan collector dump frequency-NORMAL (Refer to RCS Daily Leakage Log)o CNMT recirc fan SW flows APPROXIMATELY EQUAL (INTER BLDG basement by IBELIP)Dispatch AO to perform Attachment SW LOADS IN CNMT as necessary.

WHEN CNMT SW leak location identified, THEN go to Step 9.

C EOP!AP-SW.1 SERVICE WATER LEAK REV: 9 PAGE 7 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Dispatch AO To Screenhouse To Perform The Following:

a.Verify idle SW pump check valve closed o Idle pump shaft stopped o Idle pump discharge pressure-ZERO (unisolate and check local pressure indicator) b.Investigate for SW leak in Screenhouse

-NO EXCESSIVE LEAKAGE INDICATED a.Notify Control Room of any indication of check valve failure.b.Perform the following:

1)Identify leak location.IF increase in leakage from underground header indicated, THEN isolation of header should be considered (Refer to Attachment SW ISOLATION) 2)Notify Control Room of leak location.NOTE: Refer to Attachment SW ISOLATION for a list of the major non-safeguards loads supplied by each service water header.7 Check Indications For Leak Location: o AUX BLDG sump pump start frequency-NORMAL (Refer to RCS Daily Leakage Log)o Annunciator L-9, AUX BLDG SUMP HI LEVEL-EXTINGUISHED Dispatch AO to the specific area to investigate for leakage.o Annunciator L-17, INTER BLDG SUMP HI LEVEL-, EXTINGUISHED EN" AP-SW.1 T1TLEs SERVICE WATER LEAK REV: 9 PAGE 8 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 Dispatch AO To Locally Investigate For SW Leakage And To Monitor Operating Equipment~Turbine BLDG~SAFW pump room EOP: AP-SW.1 TITLE: SERVICE WATER LEAK REV: 9 PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED NOTE: If SW is lost to either D/G, refer to ER-D/G.2, ALTERNATE COOLING FOR EMERGENCY D/Gs, if cooling is required.J 9 Evaluate SW Leak Concerns a.Check SW pump status-AT LEAST THREE PUMPS RUNNING b.Intact SW loop header pressure GREATER THAN 45 PSIG a.IF either SW header pressure less than 45 psig, THEN start third SW pump.b.Dispatch AO to perform the following:

1)Split A and B SW headers: o Close V-4669 OR V-4760.in B D/G room.o Close V-4611 OR V-4612 in Screenhouse.

o Close V-4625 OR V-4626 in INT BLDG clean side.o Close V-4639 OR V-4756 in INT BLDG clean side.c.Verify leak location-IDENTIFIED d.Verify plant operating at power e.Leak isolation at power-ACCEPTABLE 2)IF plant at power, THEN initiate a controlled shutdown (Refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN).

3)Go to Step 10.c.Return to Step 3.d.Verify SW system conditions appropriate for plant mode (Refer to Tech Spec Section 3.3.4.1)and go to Step 10.e.IF plant shutdown required, THEN refer to 0-2.1,'NORMAL SHUTDOWN TO HOT SHUTDOWN.

EOP: AP-SW.1 TITLE: SERVICE WATER LEAK REV: 9 PAGE 10 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 Dispatch AO(s)To Locally Isolate SW Leak As Necessary 11 Verify SW Leak Isolated a.Monitor SW System Operation o SW loop header pressure-RESTORED TO PRE-EVENT VALUE Archive PPCS point ID loop A P2160 OR loop B P2161)o Both SW loop header pressures STABLE a.IF SW leak can NOT be isolated within the affected header, THEN stop SW pumps in the affected loop and go to Step 12.b.Verify at least one SW pump available from each screenhouse AC Emergency bus~Bus 17, SW pumps A or B~Bus 18, SW pumps C or D b.Refer to Tech Spec Section 3.3.4.1 for limiting conditions for operation.

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

o An A-25.1, GINNA STATION EVENT REPORT, should be submitted for a SW leak in CNMT.12 Notify Higher Supervision-END-(0 EOP: AP-SW 1 SERVICE WATER LEAK REV: 9 PAGE 1 of 1 AP-SW.1 APPENDIX LIST TITLE 1)ATTACHMENT SW ISOLATION 2)ATTACHMENT SW LOADS IN CNMT PAGES