ML17264A378
| ML17264A378 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/22/1996 |
| From: | Widay J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Andrea Johnson NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AP-CCW.1, NUDOCS 9603010220 | |
| Download: ML17264A378 (34) | |
Text
CATEGORY 1 REGULATORY INFORMATION DISTRIBUTION sYSTEM (RIDS)1 ACCESSION'BR:9603010220 DOC.DATE: 96/02/22 NOTARIZED':
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NP41E AUTHOR AFFILIATION WI DAY,~.0).Rochester Gas a Elt,ctric Corp.RECIP.N+4E RECIPIENT AFFILIATION j 3//<c'OHNSON,A.R.
DOCKET I 05000244 05000244 E SUBJEC':.Rev-ll to AP-CCW.1,"Leakage into Component Cooling Loop." , 8'/960222 ltr.A i DISTRIBUTION CODE: A003D COPIES RECEIVED:LTR I ENCL$SIZE: TITLE: OR/Lj.censing Submittal:
Suppl 1 to NUREG-0737(Generic Ltr 82-33)S!NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
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':"'R 9 ENCL 9 0 I~I 1 ZZi ZZZZI ANO IJIjit///I IjjjIjIjI/izui88 umw ROCHESTER GAS AND ELECTRIC CORPORATION re 89EASTAVENUE, ROCHESTER, N.Y.14649<001 JOSEPH A.WIDAY Rant Manager Ginna Nuclear Rant TELEPHONE AREA CODE 716 546-2700 February 22, 1996 U.S.Nuclear Regulatory Commission Document Control Desk ,Attn: Allen R.Johnson Project Directorate I-1 Washington, D.C.20555
Subject:
Emergency Operating Procedures R.E.Ginna Nuclear Power Plant Docket No.50-244
Dear Mr.Johnson:
As requested, enclosed are Ginna Station Emergency Operating Procedures.
Very truly yours, s hA.Wid 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-CCW.1, Rev.11 AP-ELEC.3, Rev.2 AP-CCW.2, Rev.12 AP-PRZR.1, Rev.8 AP-CVCS.1, Rev.10 AP-RCC.1, Rev.6 AP-ELEC.1, Rev.12 AP-RCC.2, Rev.6 I I 9b030%0220 9b0222 PDR'ADQCK 05000244 PDR AP-RCC.3, Rev.1 AP-RCP.1, Rev.9 AP-RCS.1, Rev.10 AP-SW,1, Rev.10 AP-TURB.2, Rev.14
~~I~T~a AP CCW.1 T I Tl.f: LEAKAGE INTO THE COMPONENT COOLING LOOPREV 9 PAGE 1 of 14 ROCHESTER GAS AND ELECTRIC CORPO TION GINNA STATION CONTROLLED COPY NUMBER TECHNICAL REVI PORC RE EW DATE PLANT S ERINTENDENT EFFECTIVE TE CATEGORY 1.0 REVIEWED BY:
aD 0~t~(~",)'>'<5.h1 II EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV'PAGE 2 of 14 A.PURPOSE-This procedure provides the actions required to identify and isolate leakage into the CCW system and to control the plant during the course of the event.B.ENTRY CONDITIONS/SYMPTOMS 1.ENTRY CONDITIONS
-This procedure is entered from;a.AP-CVCS.1, CVCS LEAK, or, b.AP-RCS.1, RCS LEAK, or, c.AP-RCP.l RCP SEAL MALFUNCTION, when CCW surge tank level increasing.
2.SYMPTOMS-The symptoms of LEAKAGE INTO THE COMPONENT COOLING LOOP are;a.Annunciator A-5, CCW SURGE TANK HI LEVEL 58.8%, lit or b.CCW radiation monitor (R-17)alarm, or c.Annunciator A-7 (15), RCP A (B)CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F, lit or d.Erratic RCP labyrinth seal D/P.
-~j1M l C tg EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 3 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED*************
x 4**x x x x*x*x 0***************
CAUTION o IF, AT ANY TIME DURING THIS PROCEDURE, A REACTOR TRIP OR SI OCCURS, THEN E-O, REACTOR TRIP OR SAFETY INJECTION, SHALL BE PERFORMED.
o IF CCW SYSTEM RADIATION MONITOR ALARMS, THEN VERIFY CCW SURGE TANK VENT, RCV-017, CLOSES.************x***x************************
1 Check CCW Indications a.Check CCW surge tank level INCREASING a.IF level decreasing, THEN go to AP-CCW.2, LOSS OF CCW DURING POWER OPERATION or AP-CCW.3, LOSS OF CCW-PLANT SHUTDOWN as necessary.
IF level stable, THEN return to procedure or step in effect.b.Direct RP tech to perform PC-12.3, DETERMINATION OF CCW SYSTEM LEAKAGE c.CCW radiation monitor, R-17;INCREASING c.Check RCS leakrate.IF RCS leakrate increasing, THEN go to Step 2 (Refer to RCS Leakage Surveillance Sheet)IF RCS leakage and R-17 indication normal, THEN go to Step 13.
I I IIr 4 I I A
>~EOP: AP-CCW.1 LITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 4 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED********x***0***x*x x x**x x x***************
CAUTION IF EITHER RCP¹1 SEAL OUTLET TEMPERATURE EXCEEDS 215'F, THEN THE AFFECTED RCP(S)SHOULD BE STOPPED.********x*****x x x**x x x*x x x***x***********
NOTE: RCPs may be safely operated without CCW to the thermal barrier if seal injection flow is maintained.
2 Check RCP Thermal Barrier Indications:
o Labyrinth sea'1 D/Ps-GREATER THAN 15 INCHES OF WATER AND APPROXIMATELY EQUAL o RCP¹1 seal leak off flows BETWEEN 0.25 GPM AND 5.5 GPM o Annunciator A-7 (15), RCP A (B)CCW RETURN HI TEMP OR LO FLOW 165 GPM 125'F-EXTINGUISHED IF either pump has indication of a thermal barrier leak, THEN perform the following:
a.Verify seal injection flow to affected RCP.b.Close CCW return from affected RCP thermal barrier (labyrinth seal D/P should increase).
~RCP A, AOV-754A~RCP B, AOV-754B c.Evaluate CCW surge tank level trend.IF leakage into the CCW system has stopped, THEN go to Step 17.3 Check RCS temperature GREATER THAN 350'F Go to Step 7.
0 I~W s'>0 EOP: AP-CCW F 1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 5 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED****x*********x x x%x 4*x x***4****x*x'*******CAUTION CLOSELY MONITOR PRZR LEVEL WHILE LETDOWN IS ISOLATED.********************w********************4 Check NRHX For Le'akage: a.Normal letdown-IN SERVICE a.IF excess letdown in service, THEN perform the following:
1)Close excess letdown flow control valve, HCV-123.2)Close EXCESS LTDN LOOP A COLD TO Hx, AOV-310.3)Go to Step 5.b.Check Letdown Indications:
b.Isolate Normal Letdown: o Letdown line flow APPROXIMATELY 40 GPM 1)Close loop B cold leg to REGEN Hx, AOV-427.o Low press LTDN pressure APPROXIMATELY 250 PSIG o Letdown pressure control valve, PCV-135, demand APPROXIMATELY 35%OPEN 2)Close letdown orifice valves (AOV-200A, AOV-200B, and AOV-202).3)Place letdown pressure controller, PCV-135, in MANUAL and close valve (demand at 100%).4)Control charging pump speed as necessary to maintain RCP labyrinth seal D/P less than 80 inches.5)Close charging flow control valve, HCV-142.c.Go to Step 6 6)Go to Step 5.
~~'f I t+Jf'4'J EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 6 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check If CCW Inleakage Has Stopped: a.CCW surge tank level-STABLE a.IF CCW surge tank level still increasing, THEN perform the following:
l)Restore letdown flowpath previously isolated (Refer to Attachment LETDOWN).2)Adjust charging as necessary to restore PRZR level.b.Restore an intact letdown flowpath if available (Refer to Attachment LETDOWN)3)Go to Step 13.c.Check any letdown flowpath RESTORED c.IF no letdown flowpath available, THEN consult Plant Staff.d.Adjust charging as necessary to restore PRZR level
~~-l'PC 5>~')y'4 EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV.-9 PAGE 7 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Establish Stable Plant Conditions:
a.Check Tavg-TRENDING TO TREF b.Check PRZR pressure-TRENDING TO 2235 PSIG a.Insert/withdraw control rods or, if necessary, adjust turbine load to match Tavg to Tref.b.Verify proper operation of PRZR heaters and spray or take manual control of PRZR pressure controller 431K.c.Check PRZR level-'RENDING TO PROGRAM c.Verify proper operation of charging pump speed controllers or take manual control of speed controllers to control PRZR level.d.Go to'Step 17 0
EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 8 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED****xx**xx**%x**xxxw4**x%***********x****
CAUTION o CLOSELY MONITOR PRZR LEVEL AND RCS PRESSURE WHILE LETDOWN IS ISOLATED.o UNFILTERED WATER MAY DAMAGE RCP SEAL SURFACES.****************
x**x**x x x****************
7 Check NRHX For Leakage: a.Narrow range PRZR level-ON SCALE a.IF the RCS is solid, THEN perform the following:
b.Isolate letdown flow to NRHX: 1)Stop any running RCP.2)WHEN RCPs stopped, THEN stop any running charging pump.o Ensure the following valves CLOSED~Loop B cold leg to REGEN Hx, AOV-427~Letdown orifice valves (AOV-200A, AOV-200B, and AOV-202)~RHR letdown flow control valve, HCV-133 o Close letdown isolation valve, AOV-371 o Place letdown pressure controller, PCV-135, in MANUAL and close valve (demand at 100%).
'I>g',)I l EOP: AP-CCW.1 TITLE LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 9 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED************x*x%
x*x**%%*>****************
CAUTION IF THE RCS IS WATER SOLID, THEN ANY INCREASE IN RCS TEMPERATURE MAY RESULT IN A SIGNIFICANT RCS PRESSURE INCREASE.RCS HEATUP SHOULD BE PREVENTED.
x x%*x*x x*4*x*0*************
8 Check If CCW Inleakage Has Stopped: a.CCW surge tank level-STABLE a.IF CCW inleakage continues, THEN go to Step 9.b.Narrow range PRZR level-ON SCALE b.IF RCS is solid, THEN perform the following:
1)Ensure both RCPs off.c.Establish excess letdown (Refer to Attachment LETDOWN)2)Cycle charging pumps as necessary to control RCS pressure.d.Start one charging pump e.Adjust charging flow as necessary to restore PRZR level f.Check RCS temperature
-STABLE g.Go to Step 17 f.Adjust RHR cooling as necessary.
~~o EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV'PAGE 10 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 Restore Letdown: a.Check RHR-IN SERVICE a.Perform the following:
1)Establish normal letdown'(Refer to Attachment LETDOWN).b.Open letdown isolation valve, AOV-371 2)Go to Step 10.c.Place letdown controllers in MANUAL at 40%open~TCV-130~PCV-135 d.Manually open RHR LETDOWN TO CVCS, HCV-133 e.Place TCV-130 in AUTO at 105'F f.Place PCV-135 in AUTO at desired pressure g.Start one charging pump h.Adjust charging flow as necessary to restore PRZR, pressure/level
~~
EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 11 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED**********%
x*xxx*x%%xx*%%%**%'x**xx**x**x*
CAUTION o ONE TRAIN OF RHR SHALL BE OPERABLE AT ALL TIMES.o IF AN RHR PUMP OR HX IS REMOVED FROM SERVICE, THEN OPERABILITY REQUIREMENTS SHOULD BE EVALUATED (REFER TO TECH SPEC SECTIONS 3.1.1.1 AND 3.3.1).**************%**************************10 Check RHR System For Leakage: a.Both RHR loops-ALIGNED AND OPERABLE a.IF any loop isolated for this leak investigation, THEN perform the following:
1)Restore isolated loop to service (Refer to Attachment RHR ISOL and S-13A, RHR LINEUP FOR SAFETY INJECTION).
2)WHEN loop restored, THEN isolate other RHR loop (Refer to Attachment RHR ISOL).b.Isolate selected RHR loop (Refer to Attachment RHR ISOL)3)Go to Step 11.11 Verify RCS temperature-STABLE OR DECEASING Increase cooling from available RHR loop.Attempt to establish S/G cooling if necessary.
0'litV,f I v".J~Es'e J I'k%t EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV'PAGE 12 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check If CCW Inleakage Has Stopped: a.CCW surge tank level-STABLE b.Go to Step 17 a.IF any RHR loop has NOT been checked for leakage, THEN return to Step 10.IF both RHR loops have been checked, THEN restore RHR loops to operable and go to Step 13.13 Check RMW.to CCW Surge Tank: o Verify CCW surge tank fill valve, MOV-823-CLOSED o Verify RMW pump(s)-OFF IF RMW to CCW surge tank, MOV-823, open OR RMW pump running, THEN perform the following:
a.Close CCW surge tank fill valve, MOV-823.b.Shut off running RMW pumps.c.IF CCW inleakage stops, THEN go to Step 17.
~~Np EOP: AP-CCW.1 TITLE: LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 13 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check For Sample Hx Leaks: a.Direct AO to locally check nuclear sample room Hxs o Sample Hx (TI-602)common CCW return temperature from sample Hxs-NORMAL (Refer to Aux Bldg log sheet, 3 of 3)o Sample Hx (FI-603)common CCW return flow from sample Hxs NORMAL (Refer to Aux Bldg log sheet, 3 of 3)a.Determine which sample Hx CCW outlet temperature is high, THEN perform the following:
1)Isolate the affected Hx.2)IF CCW inleakage has stopped, THEN go to Step 17.b.Direct RP Tech to check PASS,-SAMPLING IN PROGRESS b.Go to Step 15.c.Direct RP Tech to terminate PASS'sampling d.Verify CCW inleakage-STOPPED 15 Check SW Header Pressure-LESS THAN 60 PSIG Dispatch AO to check CCW pump discharge pressure.IF SW pressure greater than CCW pressure, THEN investigate possible SW leak into CCW system.**x x x**x*%**x*x x~x x x****%****************
CAUTION IF A SAFEGUARDS PUMP IS TO BE REMOVED FROM SERVICE DURING AN EMERGENCY CONDITION, THEN CONSULT WITH PLANT STAFF PRIOR TO STOPPING PUMP.**************0
- 0%***%x******************
16 Check Safeguards,Pump Status ALL SAFEGUARDS PUMPS OFF~SI pumps~RHR pumps~CS pumps IF any event in progress requiring safeguards pump operation, THEN consult Plant Staff for guidance on checking safeguards pumps for CCW leakage.
0 4 EOP: AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV 9 PAGE 14 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Evaluate Plant Conditions:
a.CCW inleakage-IDENTIFIED AND ISOLATED a.Return to Step 2.b.Determine if operation can continue (Consult Plant staff if necessary)
-OPERATION CAN CONTINUE b.IF plant shutdown is required, THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.18 Check CCW Surge Tank Level-APPROXIMATELY 50>o Consult RP tech to determine method to drain and dispose of excess CCW.NOTE: Refer to 0-9.3','RC IMMEDIATE NOTIFICATION, for reporting requirements.
19 Notify Higher Supervision 20 Return To Procedure Or Guidance In Effect-END-A ytgye'(r AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP REV: 9 PAGE 1 of 1 AP-CCW.1 APPENDIX LIST TITLE 1)ATTACHMENT RHR ISOL 2)ATTACHMENT LETDOWN PAGES
.0 ll 0~4 ji~y 1 4