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 DOCKET I FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH.NP41E AUTHOR AFFILIATION WI DAY, ~ . 0). Rochester Gas a Elt,ctric Corp.
RECIP.N+4E RECIPIENT AFFILIATION j 3//<c'OHNSON,A.R.
SUBJEC':.Rev -ll to AP-CCW.1, "Leakage into Component Cooling Loop."
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/ izui88 umw ROCHESTER GAS ANDELECTRIC CORPORATION re 89EASTAVENUE, ROCHESTER, N.Y. 14649<001 JOSEPH A. WIDAY TELEPHONE Rant Manager AREA CODE 716 546-2700 Ginna Nuclear Rant 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-RCC.3, Rev. 1 AP-TURB.2, Rev. 14 AP-CCW.2, Rev. 12 AP-PRZR.1, Rev. 8 AP-RCP.1, Rev. 9 AP-CVCS.1, Rev. 10 AP-RCC.1, Rev. 6 AP-RCS.1, Rev. 10 AP-ELEC.1, Rev. 12 AP-RCC.2, Rev. 6 AP-SW,1, Rev. 10 I I 9b030%0220 9b0222 PDR 'ADQCK 05000244 PDR
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REV 9 AP CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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:
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REV' AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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,
- 2. SYMPTOMS The symptoms of LEAKAGE INTO THE COMPONENT COOLING LOOP are;
- a. Annunciator A-5, HI LEVEL 58.8%,
lit or CCW SURGE TANK
- b. CCW radiation monitor (R-17) alarm, or
- c. Annunciator A-7 (15), RCP HI OR LO FLOW 165 GPM 125'F, lit or A (B) CCW RETURN TEMP
- d. Erratic RCP labyrinth seal D/P.
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REV: 9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 3 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- x 4 **x x x x
- CAUTION x *x 0 **************
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 a. IF level decreasing, THEN go to INCREASING 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.
- c. CCW radiation monitor, R-17; c. Check RCS leakrate. IF RCS INCREASING 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.
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REV 9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 4 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- ***
- x 0 x x x x **x x x **************
CAUTION IF EITHER RCP ¹1 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 IF either pump has indication of a Indications: thermal barrier leak, THEN perform the following:
o Labyrinth sea'1 D/Ps - GREATER THAN 15 INCHES OF WATER AND a. Verify seal injection flow to APPROXIMATELY EQUAL affected RCP.
o RCP ¹1 seal leak off flows b. Close CCW return from affected BETWEEN 0.25 GPM AND 5.5 GPM RCP thermal barrier (labyrinth seal D/P should increase).
o Annunciator A-7 (15), RCP A (B)
CCW RETURN HI TEMP OR LO FLOW ~ RCP A, AOV-754A 165 GPM 125'F - EXTINGUISHED ~ 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 Go to Step 7.
GREATER THAN 350'F
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REV: 9 AP-CCW 1 F LEAKAGE INTO THE COMPONENT COOLING LOOP 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 1) Close loop B cold leg to APPROXIMATELY 40 GPM REGEN Hx, AOV-427.
o Low press LTDN pressure 2) Close letdown orifice valves APPROXIMATELY 250 PSIG (AOV-200A, AOV-200B, and AOV-202).
o Letdown pressure control valve, PCV-135, demand 3) Place letdown pressure APPROXIMATELY 35% OPEN 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.
- 6) Go to Step 5.
- c. Go to Step 6
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REV: 9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 6 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 Check Stopped:
If CCW Inleakage Has
- 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.
- 3) Go to Step 13.
- b. Restore an intact letdown flowpath if available (Refer to Attachment LETDOWN)
- c. Check any letdown flowpath c. IF no letdown flowpath RESTORED available, THEN consult Plant Staff.
- d. Adjust charging as necessary to restore PRZR level
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REV .-9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 7 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 Establish Stable Plant Conditions:
- a. Check Tavg - TRENDING TO TREF a. Insert/withdraw control rods or, if necessary, adjust turbine load to match Tavg to Tref.
- b. Check PRZR pressure - TRENDING b. Verify proper operation of PRZR TO 2235 PSIG heaters and spray or take manual control of PRZR pressure controller 431K.
- c. Check PRZR level -'RENDING TO c. Verify proper operation of PROGRAM charging pump speed controllers or take manual control of speed controllers to control PRZR level.
- d. Go to'Step 17
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REV 9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 a. IF the RCS is solid, THEN SCALE perform the following:
- 1) Stop any running RCP.
- 2) WHEN RCPs stopped, THEN stop any running charging pump.
- b. Isolate letdown flow to NRHX:
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%).
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EOP: TITLE REV 9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 Stopped:
If CCW Inleakage Has
- b. Narrow range PRZR level - ON b. IF RCS is solid, THEN perform SCALE the following:
- 1) Ensure both RCPs off.
- 2) Cycle charging pumps as necessary to control RCS pressure.
- c. Establish excess letdown (Refer to Attachment LETDOWN)
- d. Start one charging pump
- e. Adjust charging flow as necessary to restore PRZR level
- g. Go to Step 17
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REV' AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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).
- 2) Go to Step 10.
- b. Open letdown isolation valve, AOV-371
- c. Place letdown controllers in MANUAL at 40% open
~ TCV-130
~ PCV-135
- 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
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REV: 9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP 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 a. IF any loop isolated for this OPERABLE 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).
- 3) Go to Step 11.
- b. Isolate selected RHR loop (Refer to Attachment RHR ISOL) 11 Verify RCS temperature Increase cooling from available RHR STABLE OR DECEASING loop. Attempt to establish S/G cooling if necessary.
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REV' AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 12 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 12 Check Stopped:
If CCW Inleakage Has
- a. CCW surge tank level - STABLE 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.
- b. Go to Step 17 13 Check RMW .to CCW Surge Tank: IF RMW to CCW surge tank, MOV-823, open OR RMW pump running, THEN o Verify valve, CCW surge tank MOV-823 - CLOSED fill perform the following:
o Verify - OFF
- a. Close MOV-823.
CCW surge tank fillvalve, RMW pump(s)
- b. Shut off running RMW pumps.
- c. IF CCW inleakage stops, THEN go to Step 17.
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REV 9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 13 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 Check For Sample Hx Leaks:
- a. Direct AO to locally check a. Determine which sample Hx CCW nuclear sample room Hxs outlet temperature is high, THEN perform the following:
o Sample Hx (TI-602) common CCW return temperature from 1) Isolate the affected Hx.
sample Hxs - NORMAL (Refer to Aux Bldg log sheet, 3 of 3) 2) IF CCW inleakage has stopped, THEN go to Step 17.
o Sample Hx (FI-603) common CCW return flow from sample Hxs NORMAL (Refer to Aux Bldg log sheet, 3 of 3)
SAMPLING IN PROGRESS
'sampling
- d. Verify CCW inleakage - STOPPED 15 Check SW Header Pressure- Dispatch AO to check CCW pump LESS THAN 60 PSIG 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 IF any event in progress requiring ALL SAFEGUARDS PUMPS OFF safeguards pump operation, THEN consult Plant Staff for guidance on
~ SI pumps checking safeguards pumps for CCW
~ RHR pumps leakage.
~ CS pumps
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REV 9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 14 of 14 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 Evaluate Plant Conditions:
- a. CCW inleakage - IDENTIFIED AND a. Return to Step 2.
ISOLATED
- b. Determine if operation can b. IF plant shutdown is required, continue (Consult Plant staff necessary) - OPERATION CAN if THEN refer to 0-2.1, NORMAL SHUTDOWN TO HOT SHUTDOWN.
CONTINUE 18 Check CCW Surge Tank Level Consult RP tech to determine method APPROXIMATELY 50>o 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-
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REV: 9 AP-CCW.1 LEAKAGE INTO THE COMPONENT COOLING LOOP PAGE 1 of 1 AP-CCW.1 APPENDIX LIST TITLE PAGES
- 1) ATTACHMENT RHR ISOL
- 2) ATTACHMENT LETDOWN
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