ML110060776
| ML110060776 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/18/2009 |
| From: | Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LR-N10-0355 S2.OP-AB.RC-0001(Q), Rev 10 | |
| Download: ML110060776 (30) | |
Text
PSEG Internal Use Only PSEG NUCLEAR L.L.C.
SALENUOPERATIONS S2.0P-AB.RC-0001(Q) - REV. 10 REACTOR COOLANT SYSTEM LEAK A.
Biennial Review Performed: Yes No";
Page.1. of.1.
B.
Change Package(s) and Affected Document Number(s) incorporated into this revision: None C.
The following OTSC(s) were incorporated into this revision: None REVISION
SUMMARY
The following changes were incorporated into this revision:
Revised Step 3.22 and Attachment 3 to indicate a GDC-19 Control Room habitability leakage limit of "0.7 gpm" versus "2100 cc/hr". This change was incorporated to ensure consistency with guidance currently delineated in UFSAR Sections 6.3.2.11 and 15.4.1, is consistent with limitations established in SC.RA-AP.ZZ-0051 (Q), Leakage Monitoring and Reduction Program, and S2.0P-DL.ZZ-0006(Q), Primary Plant Log, is in response to Operator Feedback, and is considered to be editorial in nature.
[70068860-0020] [70074569-0020] [70093415';0020];
Revised Technical Basis Document Step 3.22 to indicate exceeding the 0.7 gpm ECCS'leakage'"
limit may result in exceeding ODC-19 limits for Control Room habitability. This change was incorporated to provide additional clarification regarding step performance, is consistent with guidance currently delineated in UFSAR Sections 6.3.2.11 and 15.4.1, and is considered to be editorial in nature.
[70068860-0020] [70074569-0020] [70093415-0020]
Revised Attachment 2, Step 6.1 to provide specific guidance for securing CVCS letdown versus referring to S2.0P-SO.CVC-0001 (Q), Charging, Letdown, and Seal Return. This change was incorporated to ensure prompt isolation of CVCS letdown once it is determined that the RCS leak is located in the evcs letdown piping, is in response to Operator Feedback obtained during Salem Licensed Operator Requalification (LOR), is consistent with guidance currently delineated in S2.0P-SO.CVC-0001(Q), and is considered to be editorial in nature.
[70065839-00201 Revised procedure to reflect current procedure format requirements.
IMPLEMENTATION REQUIREMENTS Effective Date o3j'0/7fx)9 None
S2.0P.AB.RC.OOOl(Q)
SELECTED CAS ITEMS IF AT ANY TIME, RCS temperature is >350°F AND:
PZR level cannot be maintained> 17%
VCT level cannot be maintained >4%
THEN TRIP the Reactor.
Is Reactor Trip Confirmed?
YES I
NO --> GO TO 2-EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Inj ection.
GO TO 2-EOP-TRIP-l, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE S2.0P-AB.SG-OOOl(Q), Steam Generator Tube Leak.
IF AT ANY TIME, the leak is detennined to be from a PORV, OR a Pressurizer Code Safety Valve, THEN INITIATE S2.0P-AB.PZR-OOO1 (Q), Pressurizer Pressure Malfunction.
IF AT ANY TIME, CNTMT pressure or temperature is rising, OR the leak is suspected to be into CNTMT, THEN PLACE 2 CFCUs in slow speed AND 2 CFCUs in fast speed.
IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure IA W S2.0P-AB.CONT-OOOl(Q),
Containment Closure.
Salem 2 Page 1 of24 Time Time
[C0330]
Rev. 10
s2.OP~AB.RC~OOOl(Q)
REACTOR COOLANT SYSTEM LEAK 1.0 ENTRY CONDITIONS DATE: ____ TIME: __
1.1 Any indication of an RCS leak.
1.2 Any indication of an interconnecting ECCS leak affecting RCS inventory.
2.0 IMMEDIATE ACTIONS 2.1 None 3.0 SUBSEOUENT ACTIONS 3.1 INITIATE Attachment 1, Continuous Action Summary.
3.2 Is RCS temperature <350°F?
(Mode 4, 5, or 6 LOCA)
YES NO-->
I V
3.3 Is RCS temper~ture >200°F7 (Mode 4)
NO YES-->
I V
GO TO Step 3.8 (Mode 1, 2, or 3 LOCA)
GO TO Step 3.9 (Mode 4 LOCA) 3.4 Is the RCS leak causing a loss or reduction in RHR System cooling?
(Mode 5 or 6 LOCA)
YES NO-->
GO TO Step 3.10 I
(Mode 5 or 6 RCS LEAK)
V Salem 2 Page 2 of24 Time Time Time Rev. 10
S2.0P~AB.RC~OOOl(Q)
SELECTED CAS ITEMS IF AT ANY TIME~ RCS temperature is >350°F AND:
PZR level cannot be maintained> 17%
VCT level cannot be maintained >4%
THEN TRIP the Reactor.
Is Reactor Trip Confirmed?
YES I
NO --> GO TO 2-EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Injection.
GO TO 2-EOP-TRIP-I, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE S2.0P-AB.SG-0001(Q), Steam Generator Tube Leak.
IF AT ANY TIME, the leak is determined to be from a PORV~
OR a Pressurizer Code Safety Valve, THEN INITIATE S2.0P-AB.PZR-0001(Q)~ Pressurizer Pressure Malfunction.
IF AT ANY TIME~ CNTMT pressure or temperature is rising, OR the leak is suspected to be into CNTMT, THEN PLACE 2 CFCUs in slow speed AND 2 CFCUs in fast speed.
IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q),
Containment Closure.
Salem 2 Page 3 of24 Time Time
[C0330]
Rev. 10
S2.0P-AB.RC-OOOl(Q) 3.5 Is RCS aligned for Reduced Inventory operation?
(Mode 5 or 6 LOCA)
YES NO-->
GO TO Step 3.7 I
V 3.6 While performing Attachment 2, Guidelines for Locating An RCS Leak, GO TO S2.0P-AB.RHR-0002(Q), Loss ofRHR at Reduced Inventory.
3.7 While performing Attachment 2, Guidelines for Locating An RCS Leak, GO TO S2.0P-AB.RHR-OOOl(Q), Loss ofRHR.
3.8 Is the Unit in Mode 3 after the accumulators are isolated?
YES NO-->
GO TO Step 3.12 I
(Mode 1,2 or 3 RCS LEAK)
V 3.9 GO TO S2.0P-AB.LOCA-000l(Q), Shutdown LOCA.
(Mode 3 with Accumulators isolated or Mode 4 LOCA) [C03S4]
3.10 Is P ZR level being maintained stable or rising?
(Mode 5 or 6 RCS LEAK)
NO YES-->
GO TO Step 3.18 I
V CAUTION Exceeding ONE train of Eees Pump operation raises the probability for cold overpressurization of the ReS.
3.11 START one Centrifugal Charging or Safety Injection pump to maintain Pressurizer Level between 11 and 50%,
AND GO TO Step 3.19 Salem 2 Page 4 of24 Time Time Time Time Time Time Time Rev. 10
S2.0P-AB.RC-OOOl(Q)
SELECTED CAS ITEMS IF AT ANY TIME, RCS temperature is >350°F AND:
PZR level cannot be maintained> 17%
VCT level cannot be maintained >4%
THEN TRIP the Reactor.
Is Reactor Trip Confirmed?
YES I
NO --> GO TO 2-EOP-TRlP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Injection.
GO TO 2-EOP-TRIP-l, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE S2.0P-AB.SG-0001(Q), Steam Generator Tube Leak.
IF AT ANY TIME, the leak is determined to be from a PORV, OR a Pressurizer Code Safety Valve, THEN INITIATE S2.0P-AB.PZR-OOOl(Q), Pressurizer Pressure Malfunction.
IF AT ANY TIME, CNTMT pressure or temperature is rising, OR the leak is suspected to be into CNTMT, THEN PLACE 2 CFCUs in slow speed AND 2 CFCUs in fast speed.
IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-0001(Q),
Containment Closure.
Salem 2 Page 5 of24 Time Time
[C0330]
Rev. to
S2.0P-AB.RC-0001(Q) 3.12 Is PZR level being maintained stable or rising?
NO YES-->
GO TO Step 3.18 I
V 3.13 Is a Centrifugal Charging Pump running?
NO YES-->
GO TO Step 3.15 I
V 3.14 TRANSFER to a Centrifugal Charging Pump as follows:
3.14.1 ENSURE Charging Master Flow Controller in AUTO.
3.14.2 CLOSE 2CV55~ CHARGING FLOW CONTROL VALVE.
3.14.3 START 21 OR 22 Charging Pump.
3.14.4 PLACE 23 Charging Pump Speed Controller in MANUAL.
3.14.5 While lowering 23 Charging Pump speed to minimum, ADJUST 2CV55 to maintain desired flow.
3.14.6 When 23 Charging Pump is at minimum flow, STOP 23 Charging Pump.
3.14.7 ADJUST 2CV55 to control Pressurizer level.
Time Time 3.14.8 PLACE 2CV55 in AUTO OR remain in MANUAL until directed by the SM/CRS.
Salem 2 3.14.9 ENSURE RCP Seal Injection flows are 6-12 gpm per pump, NOT to exceed 40 gpm total RCP Seal Injection Flow.
Page 6 of24 Rev. 10
S2.0P-AB.RC-OOOl(Q)
SELECTED CAS ITEMS IF AT ANY TIME, RCS temperature is >350°F AND:
PZR level cannot be maintained> 17%
VCT level cannot be maintained >4%
THEN TRIP the Reactor.
Is Reactor Trip Confmned?
YES I
NO --> GO TO 2-EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Inj ection.
GO TO 2-EOP-TRIP-I, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE S2.0P-AB.SG-OOOICQ), Steam Generator Tube Leak.
IF AT ANY TIME, the leak is determined to be from a PORV, OR a Pressurizer Code Safety Valve, THEN INITIATE S2.0P-AB.PZR-0001(Q), Pressurizer Pressure Malfunction.
IF AT ANY TIME, CNTMT pressure or temperature is rising, OR the leak is suspected to be into CNTMT, THEN PLACE 2 CFCUs in slow speed AND 2 CFCUs in fast speed.
IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q),
Containment Closure.
Salem 2 Page 7of24 Time Time
[C0330]
Rev.IO
S2.0P-AB.RC.OOOl(Q) 3.15 EVALUATE leak rate by attempting to stabilize Pressurizer level as follows:
3.15.1 ADJUST Charging flow, as necessary, to maintain Pressurizer level stable or rising while performing Step 3.15.2.
3.15.2 REDUCE Letdown flow to minimum as follows:
A.
PLACE 2CV18, NON-REGEN HX OUTLET VALVE in MANUAL, and control Letdown pressure at ::::300 psig while performing the following:
- 1.
OPEN 2CV3, 45 GPM ORIFICE
- 2.
CLOSE 2CV4 AND 2CV5, 75 GPM ORIFICE
- 3.
RETURN 2CV18 to AUTO 3.15.3 When pressurizer level is stable, EVALUATE leak rate.
3.16 Can PZR level be maintained stable or rising?
NO YES-->
GO TO Step 3.18 I
V 3.17 TRIP the Reactor.
3.17.1 Is Reactor Trip Confirmed?
YES NO-->
I V
3.17.2 INITIATE a Safety Injection.
GO TO 2-EOP-TRIP 1, Reactor Trip or Safety Injection 3.17.3 GO TO 2-EOP-TRIP-1, Reactor Trip or Safety Injection.
3.18 PLACE CVC Makeup Control System in service as necessary to control VCT level.
Time Time Time 3.19 INITIATE S2.0P-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance.
Salem 2 Page 8 of24 Rev. 10
S2.0P-AB.RC-0001(Q)
SELECTED CAS ITEMS IF AT ANY TIME, RCS temperature is >350°F AND:
PZR level cannot be maintained> 17%
VCT level cannot be maintained >4%
THEN TRIP the Reactor.
Is Reactor Trip Confirmed?
YES I
NO --> GO TO 2~EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Injection.
GO TO 2-EOP~TRIP-l, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE S2.0P-AB.SG-OOOl(Q), Steam Generator Tube Leak.
IF AT ANY TIME, the leak is determined to be from a PORV, OR a Pressurizer Code Safety Valve, THEN INITIATE S2.0P-AB.PZR-OOOl(Q), Pressurizer Pressure Malfunction.
IF AT ANY TIME, CNTMT pressure or temperature is rising, OR the leak is suspected to be into CNTMT, THEN PLACE 2 CFCUs in slow speed AND 2 CFCUs in fast speed.
IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q),
Containment Closure.
Salem 2 Page 9 of24 Time Time
[C0330]
Rev. 10
. ~,.
S2.0P-AB.RC-OOOl(Q) 3.20 PERFORM the following to identify location of leak:
3.20.1 INITIATE actions to locate and isolate the leak lAW Attachment 2, Guidelines for Locating An RCS Leak.
3.20.2 INITIATE action to identify and isolate interconnecting ECCS System leakage IA W Attachment 3, Guidance For Locating Interconnecting ECCS Leakage.
3.21 NOTIFY SM/CRS to refer to the following:
Technical Specifications NOTE Any leakage that is unisolable or affects Pressurizer level should be considered Reactor Coolant System (RCS) Leakage when reviewing the Salem ECG for classification assessment.
Event Classification Guide 3.22 WAIT at this point until one of the following occurs:
ReS leak is located and reduced below Technical Specification limits.
Continued operation with leakage in excess of 0.7 gpm (ECeS leakage limit) and below Technical Specification limits has been evaluated.
SM/eRS directs Reactor shutdown.
3.23 Is Reactor shutdown and cooldown required?
YES NO-->
GO TO Section 4.0 I
V 3.24 COMMENCE normal Plant shutdown and cooldown IA W appropriate lOPs, using the following guidelines:
Salem 2 MAINTAIN RCS pressure as low as possible to minimize leak rate.
When Res temperature is <200oP, complete depressurization may be desirable.
Page 10 of24 Time Rev. 10
S2.0P-AB.RC-0001(Q)
SELECTED CAS ITEMS IF AT ANY TIME, RCS temperature is >350°F AND:
PZR level cannot be maintained> 17%
VCT level cannot be maintained >4%
THEN TRIP the Reactor.
Is Reactor Trip Confirmed?
YES I
NO --> GO TO 2-EOP-TRIP 1, Reactor Trip or Safety Inj ection.
V INITIATE a Safety Injection.
GO TO 2-EOP-TRIP-l, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE S2.0P-AB.SG-0001(Q), Steam Generator Tube Leak.
IF AT ANY TIME, the leak is determined to be from a PORV, OR a Pressurizer Code Safety Valve, THEN INITIATE S2.0P-AB.PZR-0001CQ), Pressurizer Pressure Malfunction.
IF AT ANY TIME, CNTMT pressure or temperature is rising, OR the leak is suspected to be into CNTMT, THEN PLACE 2 CFCUs in slow speed AND 2 CFCUs in fast speed.
IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure IA W S2.0P-AB.CONT-OOOl(Q),
Containment Closure.
Salem 2 Page 11 of24 Time Time
[C0330]
Rev. 10
S2.0P-AB.RC-0001(Q) 3.25 In conjunction with System Engineering DETERMINE a long term course of action for RCS inventory control. The following items should be considered:
Estimated duration for repairs RCS Leak Rate Available Boric Acid inventory (BASTs, RWST, Accumulators, HUTs, Concentrates Storage Tanks, etc.)
CNTMT Sump inventory CNTMT Sump pH control Boric Acid production/reprocessing capacity 3.26 When directed, ESTABLISH the long-term lineups and take other approved actions to maintain RCS inventory.
4.0 COMPLETION AND REVIEW 4.1 COMPLETE Attachment 4, Sections 1.0 and 2.0, AND FORWARD this procedure to SM/CRS for review and approval.
4.2 SM/eRS PERFORM the following:
Salem 2 4.2.1 REVIE'V this procedure with Attachments 1-4 for completeness and accuracy.
4.2.2 COMPLETE Attachment 4, Section 3.0.
4.2.3 FORWARD completed procedure to Operations Staff.
END OF PROCEDURE Page 12 of24 Rev. 10
S2.0P-AB.RC-OOOl(Q)
ATTACHMENT 1 (Page toft)
CONTINUOUS ACTION
SUMMARY
1.0 IF AT ANY TIME, RCS temperature is >350°F AND:
PZR level cannot be maintained> 17%
VCT level cannot be maintained >4%
THEN TRIP the Reactor.
1.1 Is Reactor Trip Confinued?
YES I
NO->
GO TO 2-EOP-TRIP 1, Reactor Trip or Safety Injection 2.0 V
1.2 INITIATE a Safety Injection.
1.3 GO TO 2-EOP-TRIP-l, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is detennined to be into a Steam Generator, THEN INITIATE S2.0P-AB.SG-000l(Q), Steam Generator Tube Leak.
3.0 IF AT ANY TIME~ the leak is detennined to be from a PORV, OR a Pressurizer Code Safety Valve, THEN INITIATE S2.0P-AB.PZR-000l(Q), Pressurizer Pressure Malfunction.
4.0 IF AT ANY TIME, CNTMT pressure or temperature is rising, OR the leak is suspected to be into CNTMT, THEN PLACE 2 CFCUs in slow speed and 2 CFCUs in fast speed.
5.0 IF the Unit is in Mode 5 OR 6, THEN INITIATE Containment Closure lAW S2.0P-AB.CONT-OOOl(Q),
Containment Closure.
6.0 IF AT ANY TIME, RCS Temperature is <200oP, AND Pressurizer Level cannot be maintained> 11 %,
Time
[C0330]
THEN concurrently PERFORM Attachment 2, Guidelines for Locating An RCS Leak AND Attachment 3, Guidance For Locating Interconnecting ECCS Leakage, AND GO TO S2.0P-AB.RHR-000l(Q), Loss ofRHR.
Time Salem 2 Page 13 of24 Rev. to
S2.0P-AB.RC-0001(Q)
ATTACHMENT 2 (Page 1 of 6)
GUIDELINES FOR LOCATING AN ReS LEAK NOTE If an indicator shows rising trend or is reading unusually high, then equipment on the right side of Table 1 may be source of ReS leakage.
When potentially leaking equipment has been identified, further investigation should be performed to ensure affected equipment is the source of leakage. Investigation should be performed using available instrumentation and by local observation:
sound, visual, temperature, radiation survey, or other appropriate methods.
1.0 MONITOR indicators on the left side of Table 1 for high or rising readings.
2.0 ENSURE leak is not due to sampling activities in progress.
3.0 REQUEST Chemistry Department sample the following for RCS inleakage:
- Component Cooling 4.0 DIRECT Radiation Protection to increase monitoring of 2Rll Al2R12A and report any abnonnal indications to SMiCRS. '
5.0 INSPECT Plant areas with the following guidelines:
An RCS leak into another system may result in higher pressure in that system and may result in steam/water leaks, or unusual system response during nonnal evolutions. Other indications of abnonnal pressure include:
Accumulation of boric acid Excessive valve packing leaks Pump seal leaks Reliefvalves lifting Rising tank levels Excessive sump pump run times An RCS leak into another system may result in higher temperature in that system. Abnonnal temperatures may be identified by temperature alarms, water hammer, or piping that is unusually hot to the touch.
Salem 2 Particular attention should be given to interconnecting systems with on-going maintenance, or that have recently been operated, cleared for maintenance, or had valve alignments performed.
Page 14 of24 Rev. 10
S2.0P-AB.RC-OOOl(Q)
ATTACHMENT 2 (Page 2 of6)
GUIDELINES FOR LOCATING AN RCS LEAK 6.0 IF leak is determined to be from the CVCS letdown piping located in any of the following areas:
Piping penetration Areas (EL. 78')
OR Pipe Alley eEL. 84')
OR Letdown Heat Exchanger Room eEL. 84')
OR Safety Injection Pump Room (EL. 84')
6.1 SECURE CVCS letdown by performing the following:
A.
CLOSE the following LTDWN ORIFICE ISOL Valves:
2CV3, 45 GPM ORIFICE 2CV4, 75 GPM ORIFICE 2CV5, 75 GPM ORIFICE B.
CLOSE 2CV2, LTDWN LINE ISOL V.
C.
CLOSE 2CV277, LTDWN LINE ISOL V.
D.
CLOSE 2CV7, LTDWN HX INLET V.
E.
IF reduced charging flow is required for Pressurizer level control AND a Centrifugal Charging Pump is in service, THEN PLACE 2CA2015, CONTROL AIR SUPPLY TO CV55 BYPASS VALVE, in BYPASS.
F.
ADJUST 2CV71 as required to maintain 6-12 per pump, NOT to exceed 40 gpm total RCP Seal Injection Flow.
G.
PLACE Excess Letdown in service IA W S2.0P-SO.CVC-0003(Q),
Excess Letdown Flow, as required.
(step continued on next page)
Salem 2 Page 15 of24 Rev. 10
ATTACHMENT 2 (Page 3 of6)
GUIDELINES FOR LOCATING AN RCS LEAK S2.0P-AB.RC-OOOl(Q) 6.0 (continued)
Salem 2 6.2 PERFORM a walkdown of the affected area for boric acid accumulation, and if any found, implement ER-AP-331, Boric Acid Corrosion Control (BACC) Program.
6.3 Send an Operator to INSPECT the blowout panels on the four sides of the Pressure Relief Penthouse (Camp. ID: 2PENTHELB at the penetration area roof EL. 141', southwest side of containment on left side of plant vent).
6.4 IF the panels are found to be dislodged from the penthouse structure or the panels appear to be damaged, THEN:
A.
NOTIFY the SM/CRS to refer to the ECG B.
NOTIFY Radiation Protection to survey the area around the vent penthouse, C.
INITIATE an Notification to have the panels reattached and/or repair panels as required.
Page 16 of24 Rev. 10
S2.0P-AB.RC-000l(Q)
ATTACHMENT 2 (page 4 of6)
GUIDELINES FOR LOCATING AN RCS LEAK TABLE 1 INDICATORIITEM TO OBSERVE POSSIBLE SOURCES OF LEAKAGE Tailpipe Temperatures PORV/Pressurizer Code Safety Valve TI463, Relief Valves TI465, Safety Valve TI467, Safety Valve TI469, Safety Valve PR T Indications Sources Discharging to PRT:
11470, Level Seal Water Relief Valve PI472, Pressure PORV/Pressurizer Code Safety Valves TI471, Temperature Reactor Vessel Head Vents Letdown Line Relief Valve Leakoff RV Flange LeakoffTemperature - TI401 RV Flange Leakoff Condensate Polish Filter Rad Monitor - 2R40 Steam Generator Tube Leak Condensate Air Ejector Rad Monitor - 2R15 Steam Generator Blowdown Radiation Monitor 2R19A, 21 Steam Generator 2R19B, 22 Steam Generator 2R19C,23 Steam Generator 2R19D, 24 Steam Generator RWST Sources of RWST Inleakage:
Level 211960 - 11963 RCS. CVCS, SI:
Valve Leakby Salem 2 Page 17 of24 Rev. 10
S2.0P-AB.RC-OOOl(Q)
ATTACHMENT 2 (page 5 of 6)
GUIDELINES FOR LOCATING AN RCS LEAK TABLE 1 INDICATIONIITEM TO OBSERVE POSSIBLE SOURCES OF LEAKAGE S1 Accumulator Level LI934A - LI934D LI935A - LI935D Press PI936A* PI936D PI937A - PI937D Sources ofInleakage:
RCS,CYCS:
Yalve Leakby CNTMT Differential Pressure - P A9607 Leak To CNTMT Atmosphere:
CNTMT Temperature (Plant Computer) (U1304)
Pressure Boundary Leakage CNTMT Pressure** PI948A1B/ClD CNTMT Rad Monitors 2R2 2RI1A 2R7 2R12AIB CFCU Leak Detection* LI730 Rx Yessel Sump Pump Frequency RCS, CYCS, RHR, SI:
Pipe/Tubing RupturelBreak PRT Rupture Disk Mechanical Joint Leakage Valve Stem Leakage RCP #3 Seal Leakoff Excess Letdown HX Relief Charging Pump Reliefs RHRReliefs SI Pump Reliefs CNTMT Spray Reliefs CNTMT Sump Pump Frequency RV Flange Leakoff(Ifaligned to sump)
CNTMT Dewpoint - TA6124 Salem 2 Page 18 of 24 Rev. 10
S2.0PwAB.RCw0001(Q)
ATTACHMENT 2 (Page 6 of6)
GUIDELINES FOR LOCATING AN RCS LEAK TABLE 1 INDICATIONIITEM TO OBSERVE POSSIBLE SOURCE OF LEAKAGE Aux Bldg Rad Monitors Leakage to Aux Bldg Atmosphere:
Unit 1:
Unit 2:
1R3 2R4 CVCS, RHR, SI, Sam12ling:
lR6A 2R34 Pump Seal Leakage 1R20B Mechanical Joint Leakage Valve Stem Leakage Aux Bldg Sump Level/Sump Pump Frequency Relief Valves Lifting/Leaking RHR Sump Pumps Frequency CC Surge Tank Level Leakage into CC System LI628A LetdownHX LI628C RCP Thermal Barrier HX RCP Seal Ret\\.ln1 HX CC Rad Monitors Excess Letdown HX RHRHXs 2Rl7A PASS HXs 2R17B Pump Seals (CHG, S1, RHR)
Sample System HXs *
- (Cooled by Unit 1 CC)
RCDT Sources Discharging to RCDT Level LA4144 RCP #2 and #3 Seal Leakoff Excess Letdown 3-Way Valve Panel 104-2:
CVCS Valve Leakoff Level 2LIlOO3 Reactor Coolant Loop Drains Pressure 2PIIOO4 RV Flange Leakoff Temperature 2TII058 (If aligned to RCDT)
Salem 2 Page 19 of24 Rev. 10
S2.0P-AB.RC-0001(Q)
ATTACHMENT 3 (Page 1 of 2)
GUIDELINES FOR LOCATING AN INTERCONNECTING ECCS LEAK NOTE SC.RA-AP.ZZ-0051 (Q)I Leakage Monitoring and Reduction Programl provides a program for monitoring the leakage from systems outside containment that could contain highly radioactive fluids following an accident lAW Technical Specification 6.8.4.a Exceeding the 0.7 gpm leakage limit may result in exceeding GDC-19 limits for Control Room habitability.
1.0 INITIATE walkdowns of the following systems to identify and isolate leak:
RHR from RH4s to the Containment Containment Spray from CS2s to the Containment High Head Safety Injection from sn and SJ2 to the Containment Intermediate Head Safety Injection - Cold Leg and Hot Leg from SJ30 to the Containment evcs -Charging and SealInjection and Seal Return (Includes* ICV 462, CHARGING CROSS TIE MOV, header and leakoff located on Uilit'l),:.. ;..., ;
. 1. ':'.;".
Liquid Waste Gaseous Waste PASS 2.0 IF evidence of boric acid accumulation is observed, THEN IMPLEMENT ER-AP-331, Boric Acid Corrosion Control (BACC) Program.
3.0 IF leak cannot be isolated, THEN QUANTIFY any identified leaks lAW SC.RA-AP.ZZ-0051(Q),
Leakage Monitoring and Reduction Program.
4.0 IF total BCCS leakage is >0.7 gpm, THEN:
4.1 INITIATE BCG RAL 11.2.1.a OR 11.2.2.b, as applicable.
4.2 ATTEMPT to reduce leakage to s:0.7 gpm.
Salem 2 Page 20 of24 Rev. 10
ATTACHMENT 3 (Page 2 of2)
S2.0P-AB.RC-0001(Q)
GUIDELINES FOR LOCATING AN INTERCONNECTING ECCS LEAK 5.0 IF isolation is required, THEN REFER to the following applicable Technical Specifications:
3.1.2.1, Boration Systems - Flow Paths - Shutdown 3.1.2.2, Boration Systems - Flow Paths - Operating 3.1.2.3, Charging Pumps - Shutdown 3.1.2.4, Charging Pumps - Operating 3.4.1.3, Reactor Coolant System - Shutdown 3.4.1.4, Reactor Coolant System - Cold Shutdown 3.5.2, Emergency Core Cooling Systems - ECCS Subsystems - Tave ~350°F 3.5.3, Emergency Core Cooling Systems - ECCS Subsystems - Tave <350°F 3.6.2.1, Depressurization and Cooling Systems - Containment Spray System 3.6.2.2, Depressurization and Cooling Systems - Spray Additive System 3.9.8.1, Refueling Operation - All Water Levels 3.9.8.2, Refueling Operation - Low Water Level 6.0 IF total ECCS leakage is ~0.7 gpm, THEN no additional action is required.
Salem 2 Page 21 of24 Rev. 10
ATTACHMENT 4 (Page 1 of 2)
COMPLETION SIGN-OFF SHEET S2.0P-AB.RC-0001(Q) 1.0 COMMENTS (INCLUDE procedure deficiencies and corrective actions.
Attach additional pages as necessary.)
Salem 2 Page 22 of24 Rev. 10
2.0 SIGNATURES Print ATTACHMENT 4 (page 2 of2)
COMPLETION SIGN-OFF SHEET Initials Signature 3.0 SMiCRS FINAL REVIEW AND APPROVAL S2.0P-AB.RC-0001(Q)
Date This procedure with Attachment 1-4 is reviewed for completeness and accuracy.
Entry conditions and all deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section of this attachment.
Date:
Signature: __________________ _
8M/CRS Salem 2 Page 23 of 24 Rev. 10
S2.0P-AB.RC-0001(Q)
EXHIBIT 1 (Page 1 of 1)
SM/CRS BRIEFING SHEET NOTE The following items are a list of potential topics which should be covered during the briefing, at SM/CRS discretion.
- 1)
SAFETY:
If sending Operators to inspect for suspected leaks) obtain Radiation Protection support due to potential elevated radiation levels.
- 2)
TECHNICAL SPECIFICATIONS and ECGs:
If unidentified RCS leakage exceeds 1 gpm or if total RCS leakage exceeds 10 gpm refer to T.S. 3.4.7.2.
If Containment pressure rises to >0.3 psig, refer to T.S. 3.6.1.4.
If Containment avg air temperature exceeds 120°F, refer to Technical Specification. 3.6.1.5.
- 3)
PARAMETERS TO BE MONITORED:
PZR and VCT levels Containment and Auxiliary Building radiation levels.
- 4)
SOURCES OF LEAKAGE:
- 4)
CONTINGENCIES:
Salem 2 Refer to Attachment 2) Guidelines for Locating an RCS Leak.
Reactor Trip/SI criteria IA W CAS.
Briefreactivity plan for power reduction, if required.
Long term course of action for RCS inventory control.
Estimated leak rate and TS/ECG considerations.
Page 24 of24 Rev. 10
S2.0P-AB.RC-OOOl(Q)
1.0 REFERENCES
REACTOR COOLANT SYSTEM LEAK TECHNICAL BASES DOCUMENT 1.1 Technical Documents A.
Salem Generating Station Updated Final Safety Analysis Report:
Section 15.2.12, Accidental Depressurization of the RCS Section 15.3.1, Loss of Reactor Coolant Section 15.4.1, MajorRCS Rupture B.
Salem Generating Station Technical Specifications Unit 2:
3.1.2.6, Borated Water Sources - Operating 3.4.7.2, RCS Operational Leakage 3.6.1.4, Containment Systems - Internal Pressure 3.6.1.5, Containment Systems - Air Temperature 1.2 Procedures A.
SC.RA-AP.ZZ-0051 (Q). Leakage Monitoring and Reduction Program B.
S2.0P-AB.LOCA-000l(Q), Shutdown LOCA C.
S2.0P-AB.CONT-0001(Q), Containment Closure D.
S2.0P-AB.PZR-0001(Q), Pressurizer Pressure Malfunction E.
S2.0P-AB.RHR-0001(Q), Loss ofRHR F.
S2.0P~AB.RHR-0002(Q), Loss ofRHR at Reduced Inventory G.
S2.0P-AB.SG-0001(Q), Steam Generator Tube Leak H.
S2.0P-SO.CVC-0001(Q), Charging, Letdown, and Seal Return
- 1.
S2.0P-SO.CVC-0002(Q), Charging Pump Operation J.
S2.0P-SO.RHR-0001(Q), Initiating RHR K.
S2.0P-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance
- 1.
2-EOP-TRIP-1, Reactor Trip or Safety Injection M.
ER-AP-331, Boric Acid Corrosion Control (BACC) Program 1.3 Drawines A.
205328 No 2 Unit, CVCS P&ID C.
205334 No 2 Unit, SIS P&ID 1.4 Conformance Documents A.
C0330, NRC GL 88-17-Fl, Task 0005, develop procedures for Containment Closure Salem 2 B.
C0354, Westsalepse-86-532, ECCS Performance During Mode 4 Operations, Shutdown LOCA Page 1 of5 Rev. 10
s2.OP-AB.RC-OOOI (Q) 1.5 Other A.
DCP lEC-3308 B.
SGS Emergency Classification Guide C.
PSBP 320832, EOP Setpoint Document E.
CR#70000992, Lost VCT Level F.
DCPs 80029150 and 80029155, Unit CVCS Cross-Connect G.
Safety Evaluation SOO-019, Removal of PDP from Normal Operation H.
DCP 80065299, Restoration of PDP for Normal Operation 2.0 DISCUSSION 2.1 This procedure is intended to provide the direction necessary for responding to a primary leak in the RCS and interconnecting systems outside Containment. Ifthe RCS is initially at or above 350°F (Modes 1,2, or 3 with accumulators in service) the crew utilizes Attachment 2, Guidelines for Locating An RCS Leak. The crew is directed to the Shutdown LOCA procedure for RCS leaks that occur while the plant is in Mode 3 with the accumulators isolated or while in Mode 4. In all cases where RCS is being cooled by RHR in Mode 5, 6, or defueled; this procedure is used to locate and isolate the leak.
RCS leaks in Modes 5, 6, or defueled where the RHR system cooling is challenged and a loss ofRHR is imminent require this procedure to be performed concurrently with the appropriate loss of RHR procedure.
2.2 This procedure is written for leaks that are smaller than the capacity of a centrifugal Charging Pump with Letdown flow at a minimum. For large uncontrolled leaks the correct procedure guidance will depend on plant mode and amount of operable ECeS equipment.
, Direction is provided by 2-EOP-TRIP-l, Reactor Trip or Safety Injection and;'
S2.0P-AB.LOCA-0001CQ), Shutdown LOCA.
2.3 EntlY Conditions Entry into this procedure may be from alarms, other procedures, or Operator observation of an RCS leak OR interconnecting ECCS leak outside Containment. There are no distinct symptoms associated with the entry condition other than direct visual observation or calculation. ReS leakage must be inferred from several simultaneous symptoms (higher Charging with Letdown and Pressurizer level constant and no cooldown in progress).
2.4 Immediate Actions None 2.5 Subsequent Actions The major steps of this procedure are designed to stabilize the ReS (Pressurizer level), and then attempt to locate and isolate the leak. For leaks smaller than Technical Specification limits, the procedure is exited and the Plant remains at power.
For all other sizes, a Plant shutdown and cooldown is initiated. If leak isolation does Salem 2 not occur, the procedure puts the Plant in a condition that allows long term core cooling and inventory control. If a Reactor Trip or Safety Injection occurs while performing this procedure, the Operator would go to 2-EOP-TRIP-I.
Page 2 of5 Rev. 10
Salem 2 S2.0P-AB.RC-0001(Q)
Step 3.1 directs the Operator to initiate Attachment 1 which captures all the continuous action steps into a single summary. The intent is for the Operator to remove the attachment from the procedure and allow another person (Operator/STA) to monitor for the following conditions so the Control Room Operatorts attention is not diverted:
RCS Temperature >350°F with either PZR level s 17% or VCT level s4%.
In this case, the Operator is directed to manually trip the reactor, initiate SI, and proceed to 2-EOP-TRIP-I. Pressurizer level at 17% corresponds to the low level interlock for Pressurizer heaters. If Pressurizer pressure/level is already lowering and the heaters are lost, recovering pressure is not possible. VCT level at 4% indicates that makeup capacity has been exceeded and a transfer to the RWST is required.
Direction from Salem management is that this is a severe enough leak size to require a manual reactor trip and 81.
If the leak is determined to be into a Steam Generator, then the Operator is directed to proceed to the Steam Generator Tube Leak procedure. The Steam Generator Tube Leak procedure contains all the necessary actions required to cope with a leak into this secondary system.
If the leak is determined to be from a PORV or a Pressurizer Code Safety Valve, then the Operator is directed to proceed to the Pressurizer Pressure Malfunction procedure. The Pressurizer Pressure Malfunction procedure contains all the necessary actions to deal with this situation.
If the leak is suspected to be into Containment, then the Operator is directed to place 2 CFCUs inslowspeed:and2 CFCUs in fast speed. This is to attemptto prevent, '
an automatic Safety Injectibn'andminimize the potential for off-site releases when,.: ",
the leak is in Containment. Aligning CFCUs to 2 slow and 2 fast is the optimum configuration to maintain ring duct pressure low enough to accommodate slow speed fans.
When the plant is in Mode 5 or 6, the operator is direct to initiate Containment Closure to limit the potential release of radioactive material.
If the RCS leak is large enough where pressurizer level cannot be maintained on scale and the plant is in Mode 5,6, or defueled; the operator is directed to leave this procedure and go to LOSS OF RHR. The magnitude ofRCS inventory loss will cause RHR pump cavitation or Core Exit Thermocouple temperatures to rise.
Page 3 of5 Rev. 10
Salem 2 S2.0P-AB.RC-0001(Q)
This procedure is entered if the RCS has a leak. Steps 3.2 through 3.9 direct the Operator to the appropriate procedure if the RCS is experiencing: a RCS leak while in Modes 1,2, or 3 with the accumulators in service; a SID LOCA while in Mode 3 with the accumulators isolated, or Mode 4. Also, a RCS leak (mode 5, 6, or defueled) which potentially causes a Loss of RHR, or Loss of RHR At Reduced Inventory.
Blocking SI, and isolating the accumulators, are not addressed in this procedure. If the leak is slow enough and under control, the normal lOPs will perform this function. If the leak is too fast or uncontrolled for the lOPs to accomplish these tasks, then their ECCS function will be needed in order to mitigate the accident.
Step 3.10 evaluates Pressurizer level. If Pressurizer level is being maintained or rising, the Operator is directed to Step 3.19 to conduct an RCS inventory balance. At step 3.11, if Pressurizer level is lowering the operator starts one centrifugal charging or safety injection pump to cope with a Mode 5 or 6 RCS leak. Steps 3.12 through 3.16 address a Mode I, 2 or 3 RCS leak. This is accomplished by directing the operator to evaluate the leak rate by transferring to a centrifugal charging pump and a 45 gpm letdown orifice, and by adjusting charging flow to stabilize pressurizer level. Step 3.16 evaluates Pressurizer level again. If level is being maintained or rising, the Operator is directed to Step 3.18.
If level is still lowering, Step 3.17 directs the Operator to manually trip the reactor and confim1 the Reactor trips. If the Reactor trips, Safety Injection is initiated and the Operator goes to 2-EOP-TRIP-1, Reactor Trip or Safety Injection. A manual reactor trip and Safety Injection is initiated from normal operating pressure with a leakrate greater than ~ 93 gpm.
This value comes from the capacity of a centrifugal Charging Pump (~ 150 gpm),
subtracting minimum Letdown (:::: 45 gpm) and RCP seal water return flow (:::: 12 gpm).
If the Reactor does not trip, the Operator is directed to 2-EOP-TRIP-l to address the ATWS.
The procedure does not place the BIT flowpath in service for several reasons. First, the BIT is no longer a highly borated source that would expedite the shutdown. Second, substantial control of Charging flowrate is available through the 2CV55 path than through the BIT.
This control is vital on small break LOCAs where Charging can easily repressurize the RCS.
Finally, even though the total Charging flowrate may be slightly less, (due to the head loss of the 2CV55 path), the difference is not appreciable and the manual SI option is still available if insufficient Charging flow exists.
If Pressurizer level is being maintained or is rising, Step 3.18 directs the Operator to place cve Makeup Control System in service as necessary to control VCT level. This should already exist, therefore this step is a reminder to monitor VCT level.
Step 3.19 directs the Operator to initiate a leak rate calculation. This will be necessary to classify the event and aids in subsequent procedure direction.
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Salem 2 S2.0P-AB.RC-0001(Q)
At Step 3.20, efforts are initiated to locate and isolate the leak using Attachment 2, Guidelines for Locating An RCS Leak AND Attachment 3, Guidelines for Locating An Interconnecting BCeS Leak. If evidence of boric acid accumulations are observed during the conduct of walk downs, procedure ER-AP-331, Boric Acid Corrosion Control (BACC) Program is implemented to meet commitments made in response to NRC Generic Letter 88-05.
At Step 3.21, the SM/CRS is notified to refer to the Event Classification Guide and Technical Specifications, for classifying the event and determining applicable LCOs.
RCS Leakage definition for ECG classification purposes is "Any leakage that is llllisolable or affects Pressurizer level should be considered Reactor Coolant System (RCS) Leakage when reviewing the Salem ECG for classification assessmentrt.
Step 3.22 directs the Operator to wait until either the leak rate is reduced below the Technical Specification limit, OR continued operation with leakage in excess of 0.7 gpm (BCCS leakage limit) and below Technical Specification limits has been evaluated, OR the SM/CRS directs a Reactor shutdown. Exceeding the 0.7 gpm leakage limit may result in exceeding GDC-19 limits for Control Room habitability. If the leak is located and reduced below GDC-19 and Technical Specification limits, then the procedure may,
be exited. lfnot, Step 3.24 directs a normal Reactor shutdown and cooldown IA W the appropriate lOPs.
During the Reactor shutdown, efforts will continue to locate the leak. lfthe leak is reduced '
,to less than Technical Specification limits during the shutdown, then the procedure may' be exited. If the leak has not been isolated by the time the shutdown is completed,a strategy:;,
needs to be developed to maintain core cooling and inventory control while at the same time*,
completing repairs. With the leak rate less than 138 gpm, adequate time exists to develop;"
a strategy for long term inventory control. Step 3.25 assigns System Engineering this task.
Step 3.26 implements the System Engineering recommendations. The procedure is then exited in Section 4.0.
END OF DOCUMENT Page 5 of5 Rev. 10
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