ML110060519
| ML110060519 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/18/2009 |
| From: | Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LR-N10-0355 S1.OP-AB.RC-0001(Q), Rev 9 | |
| Download: ML110060519 (30) | |
Text
PSEG Internal Use Only PSEG NUCLEAR L.L.C.
SALEM/OPERATIONS SI.0P-AB.RC-0001(Q) - REV. 9 REACTOR COOLANT SYSTEM LEAK A.
Biennial Review Performed: Yes No J Pagelofl 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 S 1.0P-DL.ZZ-0006(Q), Primary Plant Log, is in response to Operator Feedback, and is considered to be editorial in nature.
[70068860-0010] [70074569-00101 [70093415-0010]
Revised Technical Basis Document Step 3.22 to indicate exceeding the 0.7 gpm ECCS leakage*
limit may result in exceeding GDC-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.
[70068860-0010] [70074569-0010] [70093415-0010]
Revised Attachment 2, Step 6.1 to provide specific guidance for securing CVCS letdown versus referring to SI.0P-SO.CVC-000l(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 CVCS letdown piping, is in response to Operator Feedback obtained during Salem Licensed Operator Requalification (LOR), is consistent with guidance currently delineated in Sl.OP-SO.CVC-OOOl(Q), and is considered to be editorial in nature.
[70065839-0010]
Revised procedure to reflect current procedure format requirements.
IMPLEMENTATION REQUIREMENTS None
S 1.0P-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 1-EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Injection.
GO TO 1-EOP-TRIP-1, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE Sl.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 SI.OP-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 S1.0P-AB.CONT-0001(Q),
Containment Closure.
Salem 1 Page 1 of24 Time Time
[C0330]
Rev. 9
S 1.0P-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 temperature >200°F?
(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 1 Page 2 of24 Time Time Time Rev. 9
S 1.oP-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 l-EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Injection.
GO TO 1-EOP-TRIP-l, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE Sl.OP-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 Sl.OP-ARPZR-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 Sl.OP-ARCONT-OOOl(Q),
Containment Closure.
Salem 1 Page 3 of24 Time Time
[C0330]
Rev. 9
S 1.oP-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 Sl.OP-AB.RHR-0002(Q), Loss ofRHR at Reduced Inventory.
3.7 While performing Attachment 2, Guidelines for Locating An RCS Leak GO TO Sl.OP-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 Sl.OP-AB.LOCA-OOOl(Q), Shutdown LOCA.
(Mode 3 with Accumulators isolated or Mode 4 LOCA) [C0354]
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 ECCS Pump operation raises the probability for cold overpressurization of the RCS.
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 1 Page 4 of24 Time Time Time Time Time Time Time Rev. 9
S 1.0P-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 1-EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Injection.
GO TO l-EOP-TRIP-l, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE S1.0P-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 Sl.OP-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 Sl.OP-AB.CONT-0001(Q),
Containment Closure.
Salem 1 Page 5 of24 Time Time
[C0330]
Rev. 9
S 1.0P-AB.RC-OOOl(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 1CV55, CHARGING FLOW CONTROL VALVE.
3.14.3 START 11 OR 12 Charging Pump.
3.14.4 PLACE 13 Charging Pump Speed Controller in MANUAL.
3.14.5 While lowering 13 Charging Pump speed to minimum, ADJUST 1CV55 to maintain desired flow.
3.14.6 When 13 Charging Pump is at minimum flow, STOP 13 Charging Pump.
3.14.7 ADJUST 1CV55 to control Pressurizer level.
Time Time 3.14.8 PLACE 1CV55 in AUTO OR remain in MANUAL until directed by the SM/CRS.
Salem 1 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. 9
S 1.0P-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 1-EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Injection.
GO TO 1-EOP-TRIP-l, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE Sl.OP-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 Sl.OP-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 Sl.OP-AB.CONT-OOOl(Q),
Containment Closure.
Salem 1 Page 7 of24 Time Time
[C0330]
Rev. 9
S 1.oP-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 1 CV18, NON-REGEN HX OUTLET VALVE in MANUAL, and control Letdown pressure at ~300 psig while performing the following:
- 1.
OPEN ICV3, 45 GPM ORIFICE.
- 2.
CLOSE 1CV4 AND 1CV5, 75 GPM ORIFICE.
- 3.
RETURN 1CVI8 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 1-EOP-TRIP 1, Reactor Trip or Safety Injection 3.17.3 GO TO 1-EOP-TRIP-1, Reactor Trip or Safety Injection.
3.18 PLACE CVC Makeup Control System in service as necessary to control VCT level.
3.19 INITIATE S1.0P-ST,RC-0008(Q), Reactor Coolant System Water Inventory Balance.
Salem 1 Page 8 of24 Time Time Time Rev. 9
S 1.0P-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 1-EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Injection.
GO TO I-EOP-TRIP-I, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE Sl.OP-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 Sl.OP-AB.PZR-OOOI(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 Sl.OP-AB.CONT-OOOl(Q),
Containment Closure.
Salem 1 Page 9 of24 Time Time
[C0330]
Rev. 9
s 1.oP-AB.Rc-0001(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 lAW Attachment 3, Guidance For Locating Interconnecting ECCS Leakage.
3.21 NOTIFY SMiCRS 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:
RCS leak is located and reduced below Technical Specification limits.
Continued operation with leakage in excess of 0.7 gpm (ECCS leakage limit) and below Technical Specification limits has been evaluated.
SM/CRS directs Reactor shutdown.
3.23 Is Reactor shutdown and cool down 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 1 MAINTAIN RCS pressure as low as possible to minimize leak rate.
When RCS temperature is <200°F, complete depressurization may be desirable.
Page 10 of24 Time Rev. 9
S 1.0P-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 1-EOP-TRIP 1, Reactor Trip or Safety Injection.
V INITIATE a Safety Injection.
GO TO 1-EOP-TRIP-I, Reactor Trip or Safety Injection.
IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE Sl.OP-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 Sl.OP-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 Sl.OP-AB.CONT-OOOl(Q),
Containment Closure.
Salem 1 Page 11 of24 Time Time
[C0330]
Rev. 9
S 1.oP-AB.Rc-OOOl(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/CRS PERFORM the following:
Salem 1 4.2.1 REVIEW 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. 9
S 1.0P-AB.RC-0001(Q)
ATTACHMENT 1 (Page 1 of 1)
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 Confirmed?
YES NO-->
I V
1.2 INITIATE a Safety Injection.
GO TO l-EOP-TRIP 1, Reactor Trip or Safety Injection 1.3 GO TO 1-EOP-TRIP-1, Reactor Trip or Safety Injection.
2.0 IF AT ANY TIME, the leak is determined to be into a Steam Generator, THEN INITIATE S1.0P-AB.SG-000l(Q), Steam Generator Tube Leak.
3.0 IF AT ANY TIME, the leak is determined to be from a PORV, OR a Pressurizer Code Safety Valve, THEN INITIATE S1.0P-AB.PZR-0001(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, Time Time THEN INITIATE Containment Closure lAW Sl.OP-AB.CONT-OOOl(Q),
Containment Closure.
[C0330]
6.0 IF AT ANY TIME, RCS Temperature is <200°F, AND Pressurizer Level cannot be maintained> 11 %,
Salem 1 THEN concurrently PERFORM Attachment 2, Guidelines for Locating An RCS Leak AND Attachment 3, Guidance For Locating Interconnecting ECCS Leakage AND GO TO S1.0P-AB.RHR-000l(Q), Loss ofRHR.
Page 13 of24 Time Rev. 9
S 1.0P-AB.RC-0001(Q)
ATTACHMENT 2 (Page 1 of6)
GUIDELINES FOR LOCATING AN RCS 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:
Steam Generators Component Cooling 4.0 DIRECT Radiation Protection to increase monitoring of lRlIA11R12A and report any abnormal indications to SM/CRS.
5.0 INSPECT Plant areas with the following guidelines:
Salem 1 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 normal evolutions. Other indications of abnormal pressure include:
Accumulation of boric acid Excessive valve packing leaks Pump seal leaks Relief valves lifting Rising tank levels Excessive sump pumps run time An RCS leak into another system may result in higher temperature in that system. Abnormal temperatures may be identified by temperature alarms, water hammer, or piping that is unusually hot to the touch.
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. 9
S 1.0P-AB.RC-OOOl(Q)
ATTACHMENT 2 (Page 2 of 6)
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 (el. 84')
OR Letdown Heat Exchanger Room (el. 84')
OR Safety Injection Pump Room (el. 84')
THEN:
6.1 SECURE CVCS letdown by performing the following:
A.
CLOSE the following LTDWN ORIFICE ISOL Valves:
1 CV3, 45 GPM ORIFICE lCV4, 75 GPM ORIFICE lCV5, 75 GPM ORIFICE B.
CLOSE lCV2, LTDWN LINE ISOL V.
C.
CLOSE ICV277,LTDWNLINEISOL V.
D.
CLOSE ICV7, 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 ICA2015, CONTROL AIR SUPPLY TO CV55 BYPASS VALVE, in BYPASS.
F.
ADJUST I CV71 as required to maintain 6-12 per pump, NOT to exceed 40 gpm total RCP Seal Injection Flow.
G.
PLACE Excess Letdown in service lAW SI.0P-SO.CVC-0003(Q),
Excess Letdown Flow, as required.
(step continued on next page)
Salem 1 Page 15 of24 Rev. 9
ATTACHMENT 2 (Page 3 of 6)
GUIDELINES FOR LOCATING AN RCS LEAK S 1.0P-AB.RC-OOOl(Q) 6.0 (continued)
Salem 1 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 (Comp. ID: 1PENTHELB at the penetration area roof el. 141', next to 12 SG Blowdown Tank Exhaust Head).
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 a Notification to have the panels reattached and/or repaired as required.
Page 16 of24 Rev. 9
S 1.oP-AB.RC-0001(Q)
ATTACHMENT 2 (Page 4 of 6)
GUIDELINES FOR LOCATING AN RCS LEAK TABLE 1 INDICATORIITEM TO OBSERVE POSSIBLE SOURCES OF LEAKAGE Tailpipe Temperatures PORVlPressurizer Code Safety Valve TI463, Relief Valves TI465, Safety Valve TI467, Safety Valve TI469, Safety Valve PRT Indications Sources Discharging to PRT:
LI470, 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 - lR40 Steam Generator Tube Leak Condensate Air Ejector Rad Monitor - lR15 Steam Generator Blowdown Radiation Monitor lR19A, 11 Steam Generator 1R19B, 12 Steam Generator lR19C, 13 Steam Generator 1R19D, 14 Steam Generator RWST Sources of RWST Inleakage:
Level 1 LI960 - LI963 RCS, CVCS, SI:
Valve Leakby Salem 1 Page 17 of24 Rev. 9
ATTACHMENT 2 (Page 5 of6)
S 1.0P-AB.RC-OOOl(Q)
GUIDELINES FOR LOCATING AN RCS LEAK INDICATIONIITEM TO OBSERVE SI Accumulator Level LI934A - LI934D LI935A - LI935D Press PI936A - PI936D PI93 7 A - PI937D CNTMT Differential Pressure - P A9607 TABLE 1 POSSIBLE SOURCES OF LEAKAGE Sources of Inleakage:
RCS,CVCS:
Valve Leakby Leak To CNTMT Atmosphere:
CNTMT Temperature (Plant Computer) (U1304)
Pressure Boundary Leakage CNTMT Pressure - PI948A1B/C/D CNTMT Rad Monitors IR2 lRllA lR7 1 R12A1B CFCU Leak Detection - LI730 Rx Vessel Sump Pump Frequency CNTMT Sump Pump Frequency CNTMT Dewpoint - TA6124 Salem 1 Page 18 of24 RCS, CVCS, RHR. SI:
Pipe/Tubing Rupture/Break 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 RV Flange Leakoff (If aligned to sump)
Rev. 9
S 1.0P-AB.RC-0001(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:
lR3 2R4 CVCS, RHR, SI, Samnling:
lR6A 2R34 Pump Seal Leakage lR20B Mechanical Joint Leakage Valve Stem Leakage Aux Bldg Sump Level/Sump Pump Frequency Relief Valves LiftinglLeaking RHR Sump Pumps Frequency CC Surge Tank Level Leakage into CC System LI628A LetdownHX LI628C RCP Thermal Barrier HX RCP Seal Return HX CC Rad Monitors Excess Letdown HX RHRHXs lR17A PASS HXs lR17B Pump Seals (CHG, SI, 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 104-1:
CVCS Valve Leakoff Level lLII003 Reactor Coolant Loop Drains Pressure IPIlO04 RV Flange Leakoff (If aligned to RCDT)
Temperature 1 TIl 058 Salem 1 Page 19 of24 Rev. 9
S 1.0P-AB.RC-000l(Q)
ATTACHMENT 3 (Page 1 of2)
GUIDELINES FOR LOCATING AN INTERCONNECTING ECCS LEAK NOTE SC.RA-AP.ZZ-0051 (Q), Leakage Monitoring and Reduction Program, 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 SJ1 and SJ2 to the Containment Intermediate Head Safety Injection - Cold Leg and Hot Leg from SJ30 to the Containment CVCS - Charging and Seal Injection and Seal Return (Includes 2CV462, CHARGING CROSS TIE MOV, header and leakofflocated on Unit 2)
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 ECCS leakage is >0.7 gpm, THEN:
4.1 INITIATE ECG RAL 11.2.1.a OR 11.2.2.b, as applicable.
4.2 ATTEMPT to reduce leakage to sO.7 gpm.
Salem 1 Page 20 of24 Rev. 9
ATTACHMENT 3 (Page 2 of2)
S 1.0P-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 required.
Salem 1 Page 21 of24 Rev. 9
ATTACHMENT 4 (page 1 of2)
COMPLETION SIGN-OFF SHEET S 1.0P-AB.RC-OOOl(Q) 1.0 COMMENTS (INCLUDE procedure deficiencies and corrective actions.
Attach additional pages as necessary.)
Salem 1 Page 22 of24 Rev. 9
S 1.0P-AB.RC-OOOI (Q) 2.0 SIGNATURES Print ATTACHMENT 4 (page 2 of 2)
COMPLETION SIGN-OFF SHEET Initials Signature 3.0 SMICRS FINAL REVIEW AND APPROVAL This procedure with Attachments 1-4 is reviewed for completeness and accuracy.
Date Entry conditions and all deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section of this attachment.
Signature: __________________ _
Date: ____ _
SMiCRS Salem 1 Page 23 of24 Rev. 9
S 1.0P-AB.RC-0001(Q)
EXHIBIT 1 (Page 1 of 1)
SMICRS 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. 3.4.6.2.
If Containment pressure rises to >0.3 psig, refer to T.S. 3.6.1.4.
If Containment avg air temperature exceeds 120oP, 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 1 Refer to Attachment 2, Guidelines for Locating an RCS Leak.
Reactor Trip/SI criteria IA W CAS.
Brief reactivity plan for power reduction, if required.
Long term course of action for RCS inventory control.
Estimated leak rate and TSIECG considerations.
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S 1.0P-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, Major RCS Rupture B.
Salem Generating Station Technical Specifications Unit 1:
3.1.2.6, Borated Water Sources - Operating 3.4.6.2, 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.
Sl.0P-AB.LOCA-0001(Q), Shutdown LOCA C.
S1.0P-AB.CONT-0001(Q), Containment Closure D.
S1.0P-AB.PZR-0001(Q), Pressurizer Pressure Malfunction E.
S1.0P-AB.RHR-0001(Q), Loss ofRHR F.
S1.0P-AB.RHR-0002(Q), Loss ofRHR at Reduced Inventory G.
Sl.0P-AB.SG-0001(Q), Steam Generator Tube Leak H.
S1.0P-SO.CVC-0001(Q), Charging, Letdown, and Seal Return
- 1.
S 1.0P-SO.CVC-0002(Q), Charging Pump Operation J.
S1.0P-SO.RHR-0001(Q), Initiating RHR K.
S1.0P-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance L.
1-EOP-TRIP-1, Reactor Trip or Safety Injection M.
ER-AP-331, Boric Acid Corrosion Control (BACC) Program 1.3 Drawin~s A.
205228 No 1 Unit, CVCS P&ID C.
205234 No 1 Unit, SIS P&ID 1.4 Conformance Documents A.
C0330, NRC GL 88-17-F1, Task 0005, develop procedures for Containment Closure.
Salem 1 B.
C0354, Westsalepse-86-532, ECCS Performance During Mode 4 Operations, Shutdown LOCA.
Page 1 of5 Rev. 9
S 1.0P-AB.RC-OOOl(Q) 1.5 Other A.
DCP lEC-3308 B.
SGS Emergency Classification Guide C.
DCP lEC-3474, 13 AFP Enclosure Shield Panel Modification D.
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 80065300, 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. If the RCS is initially at or above 350°F (Modes 1,2, or 3 with accumulators in service) the crew utilizes, 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 ECCS equipment.
Direction is provided by l-EOP-TRIP-I, Reactor Trip or Safety Injection and S 1.0P-AB.LOCA-000 1 (Q), Shutdown LOCA.
2.3 Entry 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. RCS 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 Subseguent Actions The major steps of this procedure are designed to stabilize the RCS (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 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 1-EOP-TRIP-I.
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Salem 1 S 1.oP-AB.Rc-OOOl(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 Operator's attention is not diverted:
+
RCS Temperature >350°F with either PZR level ::s; 17% or VCT level ::s;4%. In this case, the Operator is directed to manually trip the reactor, initiate SI, and proceed to 1-EOP-TRIP-1. 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, there is no hope of recovering. 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 S1.
+
If the leak is determined to be from 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 in slow speed and 2 CFCUs in fast speed. This is to attempt to prevent an automatic Safety Injection and minimize the potential for off-site releases when the leak is in Containment. Aligning CFCU s 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 direct 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.
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Salem 1 S 1.oP-AB.Rc-OOOl(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 ofRHR, or Loss ofRHR At Reduced Inventory.
Blocking SI, and isolating the accumulators, are not addressed anywhere 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 3.15 address a Mode 1, 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 confirm the Reactor trips. Ifthe Reactor trips, Safety Injection is initiated and the Operator goes to I-EOP-TRIP-I, 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 l-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 ICV55 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 1CV55 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 CVC Makeup Control System in service as necessary to control VCT level.
This should already exist, therefore this step is a reminder to monitor V CT 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 1 S 1.0P-AB.RC-OOOl(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 ECCS 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 to Technical Specifications. RCS Leakage definition for ECG classification purposes is "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".
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 (ECCS leakage limit) and below Technical Specification limits has been evaluated, OR the SMiCRS 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. Ifnot, Step 3.24 directs a normal Reactor shutdown and cooldown lAW the appropriate lOPs.
During the Reactor shutdown, efforts will continue to locate the leak. If the 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.
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