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 ROCHESTER GAS & ELECTRIC CORP.
To:	Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
AP-SW.1, NUDOCS 9809010319
Download: ML17265A409 (20)

Text

CATEGORY 1 f .; rV REGULAT Y INFORMATION DISTRIBUTXON SYSTEM (RIDS)

ACCESSION NBR:9809010319 DOC.DATE: 98/08/24 NOTARIZED: NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna NuclearaPlant, Unit 1, Rochest'er G 05000244 AUTH.NAME s AUTHOR AFFILIATION WIDAY,U.A.

RECIP . NAME Rochester Gas & Electric RECIPIENT AFFILIATION Corp.. g~~ gf PC6ct/~~

VXSSING,G.S

SUBJECT:

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

DISTRIBUTION CODE: A002D TITLE: OR COPIES RECEIVED:LTR L ENCL Submittal:Inadequate Core Cooling (Item IX.F.2) GL 82-28 1 SIZE: ) A T

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 RECIPIENT . COPIES RECIPIENT COPIES XD CODE/NAME LTTR ENCL XD CODE/NAME LTTR ENCL PD1-1 PD 1 1 VISSING,G. 1 1 INTERNAL: ~EN'ES 1 1 NRR/DSSA/SRXB 1 1 DE 1 1 RES/DET/EXB 1 1 RES/DSXR/RPSB 1 1 EXTERNAL: NOAC NRC PDR 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 ZATIONi CONTACT THE DOCUMENT CONTRO1 DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 9 ENCL 9

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//I/I//zz ROCHESTERGASANDEI ECTRICCORPORATIONa 89EASTAVENUE, ROCHESTER, N.Y. 14649<001 JOSEPH A. WIDAY Ptont Managor t 1\I owns TELEPHONE AREA CODE 7IS 546 2700 Ginna Nucroar Pront August 24, 1998 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 05000244 PDR P

ADOCK

.'DR

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 05/22/97 PAGE: 1 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRATT PRAP PRECA PRPT STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EFFECT LAST NEXT MRCBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP- .1 LEAKAGE INTO THE COMPONENT COOLING LOOP 011 02/24/96 04/20/95 04/20/00 EF AP-CCW. 2 LOSS OF CCW DURING POWER OPERATION 012 02/24/96 08/30/94 08/30/99 EF AP-CCW. 3 LOSS CCW - PLANT SHUTDOWN 010 03/29/96 08/30/94 08/30/ 9 EF AP-CR. 1 CONTROL ROOM I ACCESSIBILITY 014 12/18/96 11/17/9 11/17/99 EF AP-CVCS. 1 CVCS LEAK 011 06/03/9~6 /20/95 04/20/00 EP AP-CW.1 LOSS OP A CIRC WATER PUMP 007 ~11 /96 04/21/93 04/21/98 EF AP-ELEC.1 LOSS OF 12A AND/OR 12B BUSSES 06/03/96 01 03/21/95 03/21/00 EF AP ELEC,2 SAFEGUARD BUSSES LOW VOLTAGE OR SYSTEM LOW FREQUEN Y 02/11/94 007 02/11/94 02/11/99 EF AP-ELEC.3 LOSS OF 12A AND/OR 12B TRANSFORMER {BELOW 350 F) 003 05/22/97 03/06/93 03/06/98 EF AP-FW. 1 PARTIAL OR COMPLETE LOSS OP MAIN FEEDWATER 010 06/03/96 04/21/93 04/21/98 EF AP- IA. 1 LOSS OP INSTRUMENT AIR 013 04/07/97 09/09/94 09/09/99 EF AP-PRZR.1 ABNORMAL PRESSURIZER PRESSURE 009 06/03/96 09/29/94 09/29/99 EF AP-RCC.l CONTINUOUS CONTROL ROD WITHDRAWAL/INSER ON 006 02 96 06/04/93 06/04/98 EF AP RCC.2 RCC/RPI MALFUNCTION 007 02/06/97 4/23/93 04/23/98 EF AP-RCC.3 DROPPED ROD RECOVERY 002 06/03/96 04/23 3 04/23/98 EF AP-RCP. 1 RCP SEAL MALFUNCI'ION 010 05/31/96 04/20/95 4+20/00 EF AP-RCS. 1 REACTOR COOLANT LEAK 011 06/03/96 04/20/95 04/20 EF AP-RCS.2 LOSS OF REACTOR COOLANT FLOW 008 06/03/96 10/08/93 10/08/98 E AP-RCS.3 HIGH REACTOR COOLANT ACTIVITY 006 04/23/93 04/23/93 04/23/98 EF AP-RCS.4 SHUTDOWN LOCA 006 11/08/96 04/20/95 04/20/00 EF

.AP-RHR.1 LOSS OP RHR 010 03/29/96 03/06/93 03/06/98 EF AP-RHR.2 LOSS OF RHR WHILE OPERATING AT RCS REDUCED INVENTORY CONDITIONS 007 05/15/97 03/21/95 03/21/00 EF AP-EWE SERVICE WATER LEAK 02/24/96 010 07/29/93 07/29/98 EF AP-TURB.1 TURBINE TRIP WITHOUT RX TRIP REQUIRED 008 06/03/96 05/07/93 05/07/98 EF

REPORT NO. 01 GINNA NUCLEAR POWER PLANT 05/22/97 PAGE: 2 REPORT: NPSP0200 PROCEDURES INDEX DOC TYPE: PRAP ABNORMAL PROCEDURE PARAMETERS: DOC TYPES - PRATT PRAP PRECA PRPT STATUS: EF QU 5 YEARS ONLY:

PROCEDURE EfFECT LAST NEXT NUMBER PROCEDURE TITLE REV DATE REVIEW REVIEW ST AP- TURB. 2 TURBINE LOAD REJECTION 015 06/03/96 06/04/93 06/04/98 EF AP-TURB. 3 TURBINE VIBRATION 008 12/04/96 03/26/93 03/26/98 EF AP TURB.4 LOSS OF CONDENSER VACUA 011 06/03/96 03/26/93 03/26/98 EF AP- TURB. 5 RAPID LOAD REDUCTION 002 06/03/96 07/10/95 07/10/00 EF TOTAL FOR PRAP 28

EOPt TITLE!

REV: 9 AP-SW.1 SERVICE WATER LEAK 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:

REV: 9 AP-SW.1 SERVICE WATER LEAK 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 T1TLE:

REV: 9 AP-SW.1 SERVICE WATER LEAK PAGE 3 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION 0 IF AT ANY TIME DURING THIS 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 Ensure associated D/G(s) running Busses 17 and 18 ENERGIZED and attempt to manually load busses 17 and/or 18 onto the D/G(s) if necessary.

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

~ A or B pump in loop A

~ C or D pump in loop B

EOP s REV: 9 AP-SW.1 SERVICE WATER LEAK 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; a. IF three SW pumps operating and either loop pressure less than o Pressure in both loops 40 psig, THEN trip the reactor APPROXIMATELY EQUAL and go to E-O, REACTOR TRIP OR SAFETY INJECTION.

o PPCS SW low pressure alarm status - NOT LOW IF only two SW pumps operating and either loop pressure less o Pressure in both loops than 45 psig, THEN start one STABLE OR INCREASING additional SW pump (258 kw each pump)

b. Check SW loop header pressures b. IF either SW loop pressure is GREATER THAN 55 PSIG 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:

REV: 9 AP-SW.1 SERVICE WATER LEAK 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 a. IF the SW leak is NOT in the CNMT, THEN go to Step 6.

o Sump A level - INCREASING

-OR-o Sump A pump start frequency-INCREASING (Refer to RCS Daily Leakage Log)

b. Evaluate Sump A conditions: b. Plant shutdown should be considered, consult plant staff.

1) Verify Leakage within capacity of one Sump A pump (50 gpm)

2) Check Sump A level - LESS THAN 10 FEET

c. Direct HP to establish conditions for CNMT entry

l

~ ~

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REV: 9 AP-SW.1 SERVICE WATER LEAK 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 Dispatch AO to perform Attachment indications: SW LOADS IN CNMT as necessary.

WHEN CNMT SW leak location o CNMT recirc fan collector dump identified, THEN go to Step 9.

frequency - NORMAL (Refer to RCS Daily Leakage Log) o CNMT recirc fan SW flows APPROXIMATELY EQUAL (INTER BLDG basement by IBELIP)

C EOP!

REV: 9 AP-SW.1 SERVICE WATER LEAK 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 a. Notify Control Room of any closed indication of check valve failure.

o Idle pump shaft stopped o Idle pump discharge pressure

- ZERO (unisolate and check local pressure indicator)

b. Investigate for SW leak in b. Perform the following:

Screenhouse - NO EXCESSIVE LEAKAGE INDICATED 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 Dispatch AO to the specific area to Location: investigate for leakage.

o AUX BLDG sump pump start frequency - NORMAL (Refer to RCS Daily Leakage Log) o Annunciator L-9, AUX BLDG SUMP HI LEVEL - EXTINGUISHED o Annunciator L-17, INTER BLDG SUMP HI LEVEL -, EXTINGUISHED

EN" T1TLEs REV: 9 AP-SW.1 SERVICE WATER LEAK 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: TITLE:

REV: 9 AP-SW.1 SERVICE WATER LEAK PAGE 9 of 10 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED If is lost to either refer to ER-D/G.2, ALTERNATE COOLING FOR if coolingD/G,is NOTE: SW EMERGENCY D/Gs, required. J 9 Evaluate SW Leak Concerns

a. Check SW pump status - AT LEAST a. IF either SW header pressure THREE PUMPS RUNNING less than 45 psig, THEN start third SW pump.

b. Intact SW loop header pressure b. Dispatch AO to perform the GREATER THAN 45 PSIG 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.

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. Verify leak location - IDENTIFIED c. Return to Step 3.

d. Verify plant operating at power d. Verify SW system conditions appropriate for plant mode (Refer to Tech Spec Section 3.3.4.1) and go to Step 10.

e. Leak isolation at power- e. IF plant shutdown required, THEN ACCEPTABLE refer to 0-2.1,'NORMAL SHUTDOWN TO HOT SHUTDOWN.

EOP: TITLE:

REV: 9 AP-SW.1 SERVICE WATER LEAK 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 a. IF SW leak can NOT be isolated within the affected header, THEN o SW loop header pressure- stop SW pumps in the affected RESTORED TO PRE-EVENT VALUE loop and go to Step 12.

Archive PPCS point ID loop A P2160 OR loop B P2161) o Both SW loop header pressures STABLE

b. Verify at least one SW pump b. Refer to Tech Spec Section available from each screenhouse 3.3.4.1 for limiting conditions AC Emergency bus for operation.

~ Bus 17, SW pumps A or B

~ Bus 18, SW pumps C or D 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:

REV: 9 AP-SW 1 SERVICE WATER LEAK PAGE 1 of 1 AP-SW.1 APPENDIX LIST TITLE PAGES

1) ATTACHMENT SW ISOLATION

2) ATTACHMENT SW LOADS IN CNMT