ML110070137
| ML110070137 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/21/2010 |
| From: | Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LR-N10-0355 S2.OP-SO.RC-00004(Q), Rev 15 | |
| Download: ML110070137 (43) | |
Text
PSEG Internal Use Only Page 1 of 1 PSEG NUCLEAR L.L.C.
SALEM/OPERATIONS S2.OP-SO.RC-0004(Q) REV. 15 IDENTIFYING AND MEASURING LEAKAGE USE CATEGORY: II Biennial Review Performed: Yes ____ No T DCP Packages and Affected Document Numbers incorporated into this revision: None OTSC(s) incorporated into this revision: None OPEX(s) incorporated into this revision: None REVISION
SUMMARY
1.
5.1.9 NOTE - Added bullet IF CFCU Service Water leakage is detected or suspected, THEN INITIATE SC.OP-DG.SW-0005, Service Water Spill Response in Containment.
(70103767) 2.
The following changes are considered editorial in nature as described in AD-AA-101. (70097395)
3.6 - Added definitions to Precaution and Limitation to define what Action Level I and Level II are as used in this P&L. Previously approved in S2.OP-ST.RC-0008(Q).
7.5 - Added WCAP16465, PWR Owners Group Standard RCS Leak Rate Action Levels and Response.
3.
Updated to incorporate current administrative standards for format, procedure references and personnel titles. Due to the number of editorial changes, no revision bars were used.
IMPLEMENTATION REQUIREMENTS Effective Date:
01/21/10
None
S2.OP-SO.RC-0004(Q)
Salem 2 Page 1 of 42 Rev. 15 IDENTIFYING AND MEASURING LEAKAGE TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE.............................................................. 3 2.0 PREREQUISITES........................................................ 3 3.0 PRECAUTIONS AND LIMITATIONS....................................... 3 4.0 EQUIPMENT/MATERIAL REQUIRED...................................... 5 5.0 PROCEDURE........................................................... 6 5.1 Locating RCS Leakage.............................................. 6 5.2 Measuring RCS Leakage To RCDT................................... 11 5.3 Measuring Leakage To Containment Sump............................. 12 5.4 Measuring Leakage To Reactor Sump.................................. 13 5.5 Measuring Leakage To Containment Fan Coils (CFCUs)................... 14 5.6 Quantifying Leakage............................................... 15 5.7 Assessing ECCS Leakage on Equipment Removed from Service and Drained.. 17 5.8 Completion And Review............................................ 18 6 0 RECORDS............................................................. 19
7.0 REFERENCES
......................................................... 19
S2.OP-SO.RC-0004(Q)
Salem 2 Page 2 of 42 Rev. 15 TABLE OF CONTENTS (Continued)
ATTACHMENTS PAGE Pump Data....................................................... 21 RCDT Leak Rate.................................................. 22 Containment Sump Leak Rate........................................ 24 Reactor Sump Leak Rate............................................ 26 CFCU Leak Rate.................................................. 28 Accumulator In-Leakage............................................ 29 Potential Sources Of PRT/RCDT In-Leakage............................ 30 Containment Sump Leakage Correction Data............................ 31 Inside Containment RCS Leak Rate................................... 32 0 Outside Containment RCS Leak Rate.................................. 33 1 Inside Containment Non-RCS Leak Rate............................... 34 2 PRT/RCDT In-Leakage............................................. 35 3 Valve Leakoff Lines............................................... 36 4 Valve Discharge Lines.............................................. 39 5 Completion Signoff Sheet........................................... 41
S2.OP-SO.RC-0004(Q)
Salem 2 Page 3 of 42 Rev. 15 1.0 PURPOSE 1.1 Provide instructions to:
1.1.1 Identify and trend RCS leakage.
1.1.2 Identify and trend non-RCS leakage to containment.
1.1.3 Identify leakage when Containment Sump, Reactor Sump, or CFCU Leak Rate exceeds 0.85 gpm.
1.1.4 Identify leakage when UNIDENTIFIED LEAKAGE exceeds 0.85 gpm IAW S2.OP-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance.
1.1.5 Identify sources of leakage to the RCDT and PRT.
1.1.6 When used in conjunction with S2.OP-DL.ZZ-0003(Q), Control Room Readings, Modes 1-4, performance of this procedure satisfies Technical Specification 4.4.7.2.1.b. This requirement is applicable in Modes 1-4.
1.1.7 Assess ECCS leakage when components are isolated and drained.
1.2 This procedure is performed in any mode.
2.0 PREREQUISITES None 3.0 PRECAUTIONS AND LIMITATIONS 3.1 All deficiencies and corrective actions taken during the performance of this procedure, including termination, are to be documented in the Comments Section of Attachment 15.
3.2 Any of the following may invalidate data collected:
Reactor Coolant Drain Tank (RCDT) manual pump operation
Chemistry Department sampling of RCS or systems in Containment
Filling RCP Standpipe(s)
Filling Safety Injection Accumulator(s)
Filling of Pressurizer Relief Tank (PRT) 3.3 In Modes 1-4, maximum allowable IDENTIFIED LEAKAGE is 10 gpm; maximum allowable UNIDENTIFIED LEAKAGE is 1 gpm IAW Technical Specification 3.4.7.2.
Technical Specification ACTION is required as soon as out-of-spec data is calculated and independently verified.
3.4 Any leakage NOT quantified is considered UNIDENTIFIED LEAKAGE.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 4 of 42 Rev. 15 3.5 Calculation of leak rates from steam leaks requires condensing of steam before measurement. Estimations of leak rates should NOT be performed.
3.6 The Shift Manager shall notify the Shift Operations Manager for communication to the Operations Director within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of any of the following:
Unidentified RCS Leakage as calculated in S2.OP-ST.RC-0008(Q),
Reactor Coolant System Water Inventory Balance exceeds any of the following conditions:
Absolute Action Levels:
o Any seven (7) day rolling average of Unidentified RCS Leakrate exceeds 0.10 gpm, or o
Any two (2) of three (3) consecutive RCS Unidentified leakrates exceed 0.15 gpm, or o
Any RCS Unidentified leakrate exceeds 0.30 gpm, or o
Any unexpected measurable, confirmed rise in RCS Unidentified leakrate as determined by the SM/CRS.
Deviation from Baseline Mean (Quarterly Average) Action Levels:
o Any nine (9) consecutive RCS Unidentified leakrates exceed the Monthly Average, or o
Any two (2) of three (3) consecutive RCS Unidentified leakrates exceed the Action Level I* value, or o
Any RCS Unidentified leakrate exceeds the Action Level II* value.
- Definitions:
Baseline - A normal, steady state value for a given plant condition.
The RCS Leakrate is the mean and standard deviation value based on one operating quarter. The historical baseline should be recalculated, by System Engineering, at the end of each quarter for use in the next quarter.
Mean - Average Standard Deviation - Measure of the degree of dispersion of the data from the mean value.
Action Level I - Baseline mean plus two (2) times the standard deviation.
Action Level II - Baseline mean plus three (3) times the standard deviation.
PRT in-leakage $0.5 gpm**
Each 0.25 gpm rise above 0.5 gpm requires the notification process to continue. Should the leakage experience a prompt rise over a short duration (for example: a rise from 1.2 gpm to 1.45 gpm over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period),
then all means shall be utilized to determine the validity of the rise in leakage. This would include, but not limited to, using redundant indications and re-performance of the leak rate calculation.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 5 of 42 Rev. 15 3.7 Pressure indications may help to determine potential sources of PRT in leakage from the RWST.
3.8 Manual isolation upstream of air operated Primary Water makeup valves to the PRT or RCP Standpipes should be used to help determine in leakage to the PRT or RCDT.
3.9 should be used as a reference to help determine potential sources of PRT/RCDT in-leakage other than RCS.
3.10 SC.RA-AP.ZZ-0051(Q), Leakage Monitoring and Reduction Program, may be helpful in leak determination. The current Combined Leak Rate Data Sheets (Forms SC.RA-AP.ZZ-0051-3 and 4), identify known leakages which may have increased.
4.0 EQUIPMENT/MATERIAL REQUIRED
Suitable containers for collecting and measuring leakage
Hand held pyrometer for measuring temperature on valve leakoff/discharge lines
S2.OP-SO.RC-0004(Q)
Salem 2 Page 6 of 42 Rev. 15 5.0 PROCEDURE 5.1 Locating RCS Leakage NOTE
As determined by the SM/CRS, the steps in this section may be performed concurrently and in any order.
Once the source of leakage is located, any remaining steps need not be completed.
Leakage that has been located or identified should be quantified IAW Section 5.6.
5.1.1 ENSURE Letdown Divert valve 2CV35 is aligned for FLOW TO VCT.
ENSURE zero demand as indicated on 2HC-114, 2CV35 Auto/Manual Station (located in Rack 20).
5.1.2 CHECK for Pressurizer Relief Tank (PRT) in-leakage:
A.
Pressurizer Relief and Safety Valve Temperatures are normal and stable.
IF temperatures are elevated, THEN INITIATE S2.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction, to determine the source of the leakage.
B.
Reactor Head Vent Isolation Valves indicate closed at 2RP2.
C.
IF the PRT indicates in-leakage, THEN CHECK the valve lines as identified in Attachment 14, Section 1.0, and Attachment 13, Section 2.0.
5.1.3 CHECK for Reactor Coolant Drain Tank (RCDT) in-leakage:
A.
IF RCDT indicates in-leakage, THEN CHECK the Valve Discharge Lines as identified in Attachment 14, Section 2.0.
B.
Excess Letdown Divert valve 2CV134 is aligned for FLOW TO VCT.
(step continued on next page)
S2.OP-SO.RC-0004(Q)
Salem 2 Page 7 of 42 Rev. 15 5.1.3 (continued)
C.
RCP Seal Leakoff Flows are normal and stable.
1.
IF any flow is increasing, THEN INITIATE alarm response for console alarm "Seal Leakoff Flow Hi-Lo".
D.
IF Reactor Vessel Flange Leakoff temperature (TI401) is increasing, THEN:
1.
CLOSE 2RC4.
2.
ALIGN leakoff to outer flange as follows:
a.
CLOSE 2RC2 (local valve PRT Accum 78')
b.
OPEN 2RC3 (local valve PRT Accum 78')
c.
OPEN 2RC4 (Control Room) 3.
UPDATE WCM to reflect component off-normal positions.
5.1.4 CHECK Incore Flux Mapping Leak Detection Alarm is silent (Rack 97-2).
IF an alarm condition is indicated, THEN NOTIFY Reactor Engineering to determine corrective actions.
5.1.5 CHECK Charging flow vs Letdown flow indications for mismatch.
5.1.6 CHECK RCP Seal Injection Flow indications for mismatch.
IF any flow is suspect, THEN INITIATE actions, as determined by the SM/CRS, to isolate the leakage.
5.1.7 CHECK for CCW System in-leakage by monitoring CCW surge tank level, and RMS channels 2R17A/2R17B indication.
IF in-leakage is indicated, THEN INITIATE S2.OP-AB.CC-0001(Q),
Component Cooling Abnormality.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 8 of 42 Rev. 15 5.1.8 DISPATCH operators to investigate for leakage within the Auxiliary Building:
A.
23 Charging Pump seal water tank for any overflow or spray from the seals onto the plexiglass shield.
IF seal leakage or tank overflow is indicated, THEN NOTIFY the SM/CRS to evaluate IAW S2.OP-DL.ZZ-0006(Q), Primary Plant Log.
B.
2CV462, CHARGING CROSS-TIE MOV leakage.
1.
IF 2CV464, CHARGING CROSS-TIE ISOLATION VALVE is OPEN AND Unit 2 RCS Pressure is greater than Unit 1 RCS
- pressure, THEN CLOSE 2CV464 and re-evaluate the Water Inventory Balance.
2.
IF the Cross-Tie line is the identified Leakage, THEN PERFORM one of the following:
LEAVE 2CV464 CLOSED AND CONTACT the Appendix R - Safe Shutdown Program Engineer to ensure proper compensatory measures are in place.
OPEN 2CV464 AND ALIGN 23 Charging Pump to the RWST alignment for Appendix R to support Unit 1 IAW S2.OP-SO.CVC-0002(Q), if required.
C.
Auxiliary Building Sump Tank for increased pumping frequency.
D.
RCP Seal Injection and Return Filters for leakage.
1.
IF Seal Injection Filter leakage is detected, AND leakage can NOT be stopped, THEN REMOVE Seal Injection Filter from service IAW S2.OP-SO.CVC-0001(Q), Charging, Letdown, and Seal Injection.
IF Seal Injection Filter leakage continues, AND leakage can NOT be stopped, THEN CLOSE the associated inlet valve AND UPDATE WCM to reflect off-normal positions.
2.
IF Seal Return Filter leakage is detected, AND leakage can NOT be stopped, THEN REMOVE Seal Return Filter from service IAW S2.OP-SO.CVC-0001(Q), Charging, Letdown, and Seal Injection.
(step continued on next page)
S2.OP-SO.RC-0004(Q)
Salem 2 Page 9 of 42 Rev. 15 5.1.8 (continued)
E.
Reactor Coolant Filter for leakage.
IF leakage is detected, AND leakage can NOT be stopped, THEN REMOVE Reactor Coolant Filter from service IAW S2.OP-SO.CVC-0001(Q), Charging, Letdown, and Seal Injection.
F.
INITIATE Attachment 13, Section 1.0, to determine Valve Leak-off Line leakage using the following guidance:
IF any Valve Leakoff Line leakage is detected, THEN INITIATE actions, as determined by the SM/CRS, to isolate the leakage.
5.1.9 CHECK for leakage inside Containment:
Containment Sump Pump run frequency increased
Reactor Sump Pump run frequency increased
Containment leak detection alarms, OHA C-38 or C-30 actuation
Elevated RMS Channels 2R11A, 2R12A, 2R12B, 2R2, 2R7, 2R10A or 2R10B
IF leakage is detected or suspected, THEN INITIATE actions, as determined by the SM/CRS, to isolate the leakage
IF CFCU Service Water leakage is detected or suspected, THEN INITIATE SC.OP-DG.SW-0005, Service Water Spill Response in Containment.
5.1.10 IF RHR is in-service, THEN:
A.
CHECK 2RH21 for leakage to the RWST.
IF leakage is detected, AND leakage can NOT be stopped, THEN:
- a.
CLOSE 21RH19 AND 22RH19 valves.
b.
EVALUATE LCO 3.5.3 for applicability.
c.
CLOSE 2RH20.
(step continued on next page)
S2.OP-SO.RC-0004(Q)
Salem 2 Page 10 of 42 Rev. 15 5.1.10 (continued)
B.
CHECK 2SJ70 for back-leakage to the RWST.
IF leakage is detected, THEN:
a.
PLACE 2SJ69 in VALVE OPERABLE at 2RP4.
b.
CLOSE 2SJ69.
c.
EVALUATE LCO 3.5.3 for applicability.
C.
CHECK RHR Sump Pump runs for increased frequency.
5.1.11 CHECK the RWST for an increasing level or increasing radioactivity.
5.1.12 CHECK with the Chemistry Technician for any in-progress RCS sampling activities.
5.1.13 CHECK with the Radiation Protection Personnel for area monitors which may provide information in identification of a leakage source.
5.1.14 REVIEW the WCC Tagging Log for evolutions in progress or recently completed.
5.1.15 REVIEW the Control Room Narrative Log for pump, valving, or filter manipulations.
5.1.16 REFER to the following for additional contributing leakage sources:
S2.OP-AB.RC-0001(Q), Reactor Coolant System Leak (Attachment 2)
P&ID 205326, Floor Drains - Contaminated
P&ID 205327, Equipment Vents and Drains - Contaminated 5.1.17 RECORD any additional actions and specific information which could be used to support locating the leakage or avoid unnecessary duplication of efforts in the Comments Section of Attachment 15.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 11 of 42 Rev. 15 5.2 Measuring RCS Leakage To RCDT 5.2.1 Each time a Reactor Coolant Drain Tank Pump starts, RECORD the following on Attachment 1, Section 2.0:
Operating RCDT Pump Number
Time of pump start 5.2.2 CALCULATE elapsed time in minutes between start time, and previous RCDT Pump stop time, AND RECORD on Attachment 1, Section 2.0.
NOTE Draining, sampling, or evolutions which add liquid to RCDT invalidate leak rate calculations for that time frame and should be annotated on Attachment 1, Section 2.0.
Subsequent STOP/START times should be used for accurate leak rate calculations.
5.2.3 ENSURE no draining, sampling, or liquid additions to RCDT have occurred during selected time frame.
5.2.4 CALCULATE RCDT in-leakage rate using Attachment 2.
5.2.5 RECORD calculated RCDT in-leakage rate on Attachment 1, Section 2.0.
5.2.6 Direct a second Operator to PERFORM Independent Verification of the calculation(s) performed in Attachment 1, Section 2.0.
[C0284]
5.2.7 RECORD RCDT Pump stop time AND date on Attachment 1, Section 2.0.
5.2.8 IF RCDT in-leakage is >10 gpm AND Unit is in Modes 1-4, THEN PERFORM S2.OP-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 12 of 42 Rev. 15 5.3 Measuring Leakage To Containment Sump 5.3.1 Each time a Containment Sump Pump starts, RECORD the following on Attachment 1, Section 2.0:
Operating Containment Sump Pump Number
Time of pump start 5.3.2 CALCULATE elapsed time in minutes between start time and previous Containment Sump Pump stop time AND RECORD on Attachment 1, Section 2.0.
NOTE Draining, sampling, or evolutions which add liquid to Containment Sump invalidate leak rate calculations for that time frame and should be annotated on Attachment 1, Section 2.0.
Subsequent STOP/START times should be used for accurate leak rate calculations.
5.3.3 ENSURE no draining, sampling, or liquid additions to Containment Sump have occurred during selected time frame.
5.3.4 CALCULATE Containment Sump Leak Rate using Attachment 3.
5.3.5 RECORD calculated Containment Sump leak rate on Attachment 1, Section 2.0.
5.3.6 Direct a second Operator to PERFORM Independent Verification of the calculation(s) performed in Attachment 1, Section 2.0.
[C0284]
5.3.7 RECORD Containment Sump Pump stop time and date on Attachment 1, Section 2.0.
5.3.8 IF leakage to Containment Sump exceeds 1.0 gpm AND Unit in Modes 1-4, THEN:
A.
INITIATE S2.OP-ST.RC-0008(Q), Reactor Coolant Water Inventory Balance.
B.
REFER to Technical Specification 3.4.7.2.
5.3.9 IF leakage to Containment Sump exceeds 0.85 gpm, THEN INITIATE Section 5.6 of this procedure.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 13 of 42 Rev. 15 5.4 Measuring Leakage To Reactor Sump 5.4.1 Each time the Reactor Sump Pump starts, RECORD the time of pump start on Attachment 1, Section 2.0.
5.4.2 CALCULATE elapsed time in minutes between start time and previous Reactor Sump Pump stop time AND RECORD on Attachment 1, Section 2.0.
NOTE Draining, sampling, or evolutions which add liquid to Reactor Sump invalidate leak rate calculations for that time frame and should be annotated on Attachment 1, Section 2.0.
Subsequent STOP/START times should be used for accurate leak rate calculations.
5.4.3 ENSURE no draining, sampling, or liquid additions to Reactor Sump have occurred during selected time frame.
5.4.4 CALCULATE Reactor Sump Leak Rate using Attachment 4.
5.4.5 RECORD calculated Reactor Sump leak rate on Attachment 1, Section 2.0.
5.4.6 Direct a second Operator to PERFORM Independent Verification of the calculation(s) performed in Attachment 1, Section 2.0.
[C0284]
5.4.7 RECORD Reactor Sump Pump stop time and date on Attachment 1, Section 2.0.
5.4.8 IF leakage to Reactor Sump exceeds 1.0 gpm AND Unit is in Modes 1-4, THEN:
A.
INITIATE S2.OP-ST.RC-0008(Q), Reactor Coolant Water Inventory Balance.
B.
REFER to Technical Specification 3.4.7.2.
5.4.9 IF leakage to Reactor Sump exceeds 0.85 gpm, THEN INITIATE Section 5.6 of this procedure.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 14 of 42 Rev. 15 5.5 Measuring Leakage To Containment Fan Coil Units (CFCUs)
NOTE
Changing CFCU configuration invalidates CFCU Leakage measurements.
CFCU Condensate level measurement is accurate between 0.8 feet and 15.2 feet.
5.5.1 When Overhead Alarm C-38 actuates, INITIATE CFCU Leak Calculations on operating CFCUs as follows:
A.
CLOSE WD50, CFCU CONDENSATE DRAIN STOP VALVE(S).
B.
RECORD level (L1) and time of CFCU leak test on Attachment 5.
NOTE CFCU Condensate standpipe level should be recorded before level exceeds 15.2 feet.
5.5.2 When CFCU Condensate standpipe level increases to a level adequate to ensure accurate leakage calculations, OR Overhead alarm C-30 actuates, RECORD level (L2) and time on Attachment 5.
5.5.3 ENSURE no starting, stopping, or CFCU speed changes have occurred during test period.
5.5.4 COMPLETE Attachment 5, CFCU Leak Rate.
5.5.5 Direct a second Operator to PERFORM Independent Verification of the calculation(s) performed in Attachment 5.
[C0284]
5.5.6 OPEN WD50, CONDENSATE DRAIN STOP VALVE(S), on operating CFCUs.
5.5.7 IF total leakage to CFCUs exceeds 1.0 gpm AND Unit is in Modes 1-4, THEN:
A.
INITIATE S2.OP-ST.RC-0008(Q), Reactor Coolant Water Inventory Balance.
B.
REFER to Technical Specification 3.4.7.2.
5.5.8 IF total leakage to CFCUs exceeds 0.85 gpm, THEN INITIATE Section 5.6 of this procedure.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 15 of 42 Rev. 15 5.6 Quantifying Leakage NOTE Estimations of leakage are NOT permitted. Any leakage not collected and measured over a specific time frame is considered UNIDENTIFIED LEAKAGE.
1 cc/hr = 4.4x10-6 gpm 1gpm = 227,124.7 cc/hr 1 drop per minute = 3 cc/hr [located in SC.RA-AP.ZZ-0051(Q)]
5.6.1 IF this Section is entered due to high Containment Sump, Reactor Sump, or CFCU Leakage, THEN:
A.
INSPECT areas inside Containment for indications of leakage.
B.
IF Boric Acid deposits are observed, THEN INITIATE actions required by ER-AP-331, Boric Acid Corrosion Control (BACC) Program.
C.
COLLECT AND MEASURE leakage over a specific time frame.
5.6.2 IF primary system leakage is suspected, THEN NOTIFY BACM Program Owner with possible component or area.
5.6.3 IF this Section is entered due to S2.OP-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance, THEN:
A.
INITIATE Section 5.1, Locating RCS leakage, while continuing with this procedure.
B.
COLLECT AND MEASURE leakage over a specific time frame.
C.
Direct Chemistry to CALCULATE Primary to Secondary Leak Rate.
D.
COMPLETE Attachment 6, Accumulator In-Leakage.
E.
COMPLETE Attachment 12, PRT/RCDT In-Leakage.
F.
Direct a second Operator to PERFORM Independent Verification of the calculation(s) performed in Attachments 6 and 12.
[C0284]
5.6.4 IF any RCS PRESSURE BOUNDARY leakage is observed, THEN immediately REFER to Technical Specification 3.4.7.2
S2.OP-SO.RC-0004(Q)
Salem 2 Page 16 of 42 Rev. 15 5.6.5 IF leakage is from RCS, THEN A.
RECORD calculated leak rate on following Attachments (as applicable):
, Inside Containment RCS Leak Rate 0, Outside Containment RCS Leak Rate 2, PRT/RCDT In-Leakage.
B.
Direct a second Operator to PERFORM Independent Verification of the calculation(s) performed in Attachment 9, 10 or 12 (as applicable).
[C0284]
5.6.6 IF leakage is NOT from RCS, THEN A.
RECORD calculated leak rate on Attachment 11, Inside Containment Non-RCS Leak Rate.
B.
Direct a second Operator to PERFORM Independent Verification of the calculation(s) performed in Attachment 11.
[C0284]
5.6.7 IF leakage is inside Containment, THEN:
A.
COMPLETE Attachment 8, Containment Sump Leakage Correction Data.
B.
Direct a second Operator to PERFORM Independent Verification of the calculation(s) performed in Attachment 8.
[C0284]
S2.OP-SO.RC-0004(Q)
Salem 2 Page 17 of 42 Rev. 15 5.7 Assessing ECCS Leakage on Equipment Removed from Service and Drained
[70048015]
NOTE This section should be used when isolating and draining ECCS/RCS components that could impact RCS Leak Rate and ECCS Leakage outside the Containment when the Unit is in Modes 1 - 4.
5.7.1 IF a component is being removed from service AND the potential to exceed ECCS leakage limits as defined in SC.RA-AP.ZZ-0051(Q), Leakage Monitoring and Reduction Program exists, THEN PERFORM the following when the component is isolated and drained:
A.
CALCULATE the leakage from the isolated and drained component utilizing guidance delineated in SC.RA-AP.ZZ-0051(Q),
Leakage Monitoring and Reduction Program AND RECORD leakage results (including leak rate test methodology) on Attachment 15, Section 1.0.
B.
PERFORM an abbreviated (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) Plant Computer RCS Water Inventory Balance IAW S2.OP-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance, AND RECORD results on Attachment 15, Section 1.0.
C.
IF it is determined that leakage from the isolated component exists, THEN 1.
COMPLETE Form SC.RA-AP.ZZ-0051-3 AND FORWARD to ISI Leakage Monitoring Coordinator.
2.
EVALUATE the requirement to initiate a notification IAW LS-AA-125, Corrective Action Procedure (CAP) Procedure.
5.7.2 The ISI Leakage Coordinator should review the supplied leakage results contained in Form SC.RA-AP.ZZ-0051-3 and sum the results of the total system leakage, AND NOTIFY the SM/CRS with the revised Total ECCS leakage.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 18 of 42 Rev. 15 5.8 Completion And Review 5.8.1 COMPLETE the appropriate attachments AND FORWARD to SM/CRS for review and approval.
5.8.2 SM/CRS PERFORM following:
A.
REVIEW this procedure with Attachments 1, 5, 6, 8, 9, 10, 11, 12, 13, 14 and 15 (as applicable), for completeness and accuracy.
B.
COMPLETE applicable attachments.
C.
FORWARD Attachments 1, 5, 6, 8, 9, 10, 11 and 12 (as applicable),
to the NCO for the following actions:
1.
TRANSFER Attachment 1 Pump Data to Section 1.0, Previous Pump Data of new procedure for following day.
2.
RETAIN Attachment 1 with Control Room Narrative Log.
3.
PLACE any other attachments in Control Room File for this procedure.
4.
FORWARD any superseded attachment pages from Control Room File for this procedure to Operations Staff.
5.
RETAIN current attachment pages in Control Room File for this procedure until corrective action is completed or Attachment is superseded.
END OF PROCEDURE SECTION
S2.OP-SO.RC-0004(Q)
Salem 2 Page 19 of 42 Rev. 15 6.0 RECORDS Retain the following IAW RM-AA-101, Records Management Program:
Attachments 5 - 14 (as applicable) 5
7.0 REFERENCES
7.1 Updated Final Safety Analysis Report
Section 15.3.1, Loss of Reactor Coolant
Section 15.4.1, Major RCS Rupture
Appendix A, TMI Lessons Learned, 2.1.6.a, Leakage Outside Containment 7.2 Technical Specifications - Unit 2 3.4.7.1, Reactor Coolant System - Leakage Detection Systems 7.3 Procedures
SC.CH-AB.ZZ-1101(Q), Detection and Determination of Primary to Secondary Leakage
S2.OP-AB.SG-0001(Q), Steam Generator Tube Leak
S2.OP-SO.CBV-0001(Q), Containment Ventilation Operation
S2.OP-SO.PZR-0003(Q), Pressurizer Relief Tank Operation
S2.OP-SO.WL-0005(Q), Reactor Coolant Drain Tank Operation
S2.OP-TM.ZZ-0002(Q), Tank Capacity Data 7.4 Drawings
205326, Floor Drains - Contaminated
205327, Equipment Vents and Drains - Contaminated
205301, No. 2 Unit Reactor Coolant System P&ID
205328, No. 2 Unit Chemical and Volume Control System P&ID
205330, No.2 Chemical & Volume Control Primary Water Recovery
205332, No.2 Residual Heat Removal
205334, No.2 Safety Injection
205335, No.2 Containment Spray
205339, No.2 Waste Disposal Liquid
220403, No. 1 and No. 2 Units CVCS
S2.OP-SO.RC-0004(Q)
Salem 2 Page 20 of 42 Rev. 15 7.5 Others
Event Classification Guide:
Section 1, Primary Leakage/SG Tube Leakage
, Unusual Event
NRC INFO 84-55, Seal Table Leaks At PWRs
WCAP16465, PWR Owners Group Standard RCS Leak Rate Action Levels and Response
NRC GL 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants
USNRC Regulatory Guide 1.45, Reactor Coolant Pressure Boundary Leakage Detection Systems
USNRC NUREG-0986, RCSLK8: Reactor Coolant System Leak Rate Determination for PWRs
USNRC NUREG 0737, Clarification of TMI Action Plan Requirements
S-C-RC-MEE-1067, Non-conservative Reactor Coolant System Leakage Calculation
Minor Modification S97-175, Rerouting of Non RCS Leakage to Containment Sump Instead of PRT
DCP 2EE-0327, Elimination of RCS Valve Stem Leak Off Lines
DCP 80029150/80029155, CVCS Unit Cross-Tie
DCP 80065299, Restoration of the Positive Displacement Pump for Normal Operation 7.6 Cross-References 7.6.1 Technical Specifications - Unit 2:
3.4.7.2, Reactor Coolant System - Operational Leakage
4.4.7.2.1.b, Reactor Coolant System - Operation Leakage Surveillance Requirements
7.6.2 Procedures
RM-AA-101, Records Management Program
S2.OP-AB.CC-0001(Q), Component Cooling Abnormality
S2.OP-AB.PZR-0001(Q), Pressurizer Pressure Malfunction
S2.OP-AB.RC-0001(Q), Reactor Coolant System Leak
S2.OP-ST.RC-0008(Q), Reactor Coolant System Water Inventory Balance
S2.OP-SO.CVC-0001(Q), Charging, Letdown, and Seal Injection
S2.OP-SO.CVC-0002(Q), Charging Pump Operation
S2.OP-AR.ZZ-0003(Q), Overhead Annunciators Window C
S2.OP-AR.ZZ-0011(Q), Control Console 2CC1
S2.OP-PT.CAN-0001(Q), Containment Walkdown.
S2.OP-DL.ZZ-0003(Q), Control Room Readings Mode 1-4
SC.RA-AP.ZZ-0051(Q), Leakage Monitoring and Reduction Program
S2.OP-DL.ZZ-0006(Q), Primary Plant Log
ER-AP-331, Boric Acid Corrosion Control (BACC) Program 7.7 Commitments
C0284, LER 90-014-00
CM-SC-2008-122, Implement RCS Leak Rate Guidance Recommendations by December 31, 2008
S2.OP-SO.RC-0004(Q)
Salem 2 Page 21 of 42 Rev. 15 ATTACHMENT 1 (Page 1 of 1)
PUMP DATA 1.0 Previous Pump Data Date:
Pump Name Stop Time Leak Rate Date Elapsed Run Time Investigation Time (1)
RCDT N/A Cont Sump 7 days RX Sump 30 days 2.0 Daily Pump Data Pump Name Start Time Stop Time Date Stop-Start Elapsed Time Leak Rate (2)
Initials IV Initials Comments:
(1)
Investigation is required if AUTO pump run has not occurred in specified time frame:
ENSURE OHA-C10 CONT SUMP OVRFLO not in alarm.
IF C-10 can NOT be cleared IAW S2.OP-AR.ZZ-0003(Q),
THEN containment entry is required to inspect sump level and annulus drain path for leakage.
ENSURE OHA-C18 RX SUMP OVRFLO not in alarm, AND RX Sump requires inspection during next Containment Walkdown IAW S2.OP-PT.CAN-0001(Q).
(2)
IF pumps are manually started OR tank/sump is purposely filled, THEN ENTER "Baseline" in Leak Rate column.
IF Containment Sump OR Reactor Sump Leakrate exceed 0.85 gpm, THEN PERFORM Section 5.6. (Applicable Modes 1-4)
IF RCDT Leak Rate exceeds 10.0 gpm, THEN REFER to Technical Specification 3.4.7.2d Action "b".
SM/CRS Review________________________________________________
Date_______________
RETAIN a copy of this attachment with current Control Room Narrative Log.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 22 of 42 Rev. 15 ATTACHMENT 2 (Page 1 of 2)
RCDT LEAK RATE LEAKAGE LESS THAN 1 GPM
S2.OP-SO.RC-0004(Q)
Salem 2 Page 23 of 42 Rev. 15 ATTACHMENT 2 (Page 2 of 2)
RCDT LEAK RATE LEAKAGE BETWEEN 1 GPM AND 10 GPM NOTE RCDT in-leakage greater than 10 gpm in Modes 1-4 requires entry into Technical Specification Action Statement.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 24 of 42 Rev. 15 ATTACHMENT 3 (Page 1 of 2)
CONTAINMENT SUMP LEAK RATE LEAKAGE LESS THAN 1 GPM
S2.OP-SO.RC-0004(Q)
Salem 2 Page 25 of 42 Rev. 15 ATTACHMENT 3 (Page 2 of 2)
CONTAINMENT SUMP LEAK RATE LEAKAGE BETWEEN 1 GPM AND 10 GPM
S2.OP-SO.RC-0004(Q)
Salem 2 Page 26 of 42 Rev. 15 ATTACHMENT 4 (Page 1 of 2)
REACTOR SUMP LEAK RATE LEAKAGE LESS THAN 1 GPM
S2.OP-SO.RC-0004(Q)
Salem 2 Page 27 of 42 Rev. 15 ATTACHMENT 4 (Page 2 of 2)
REACTOR SUMP LEAK RATE LEAKAGE BETWEEN 1 GPM AND 10 GPM
S2.OP-SO.RC-0004(Q)
Salem 2 Page 28 of 42 Rev. 15 ATTACHMENT 5 (Page 1 of 1)
CFCU LEAK RATE NOTE CFCU Leakage calculations are required on operating CFCUs only.
Idle CFCU Leakage calculations should be marked N/A.
CFCU Initial Data Final Data Level Change Elapsed Time Leak Rate Level (L1)
Time Level (L2)
Time (L2 - L1) (ft)
(min)
(1) 21 gpm 22 gpm 23 gpm 24 gpm 25 gpm Total Leak Rate gpm Performed by______________________________________________________ Date____________
Independent Verification_____________________________________________ Date____________
SM/CRS Review_________________________________________________
Date____________
RETAIN a copy of this attachment in the Control Room file for this procedure until corrective action is completed or attachment is superseded.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 29 of 42 Rev. 15 ATTACHMENT 6 (Page 1 of 1)
ACCUMULATOR IN-LEAKAGE NOTE
Elapsed time should be at least 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Increasing elapsed time increases accuracy of Leak Rate. Accumulator makeup, sampling, or draining voids Accumulator in-leakage calculations.
In-leakage is positive (+), Outleakage is negative (-).
In-leakage must be #0 when RCS pressure is less than accumulator pressure.
Negative accumulator leakage should be evaluated by System Engineer for effects on IDENTIFIED LEAKAGE and UNIDENTIFIED LEAKAGE.
Identified leakage data must be obtained within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of final leak rate calculations.
Initial Final Date:
Time:
Date:
Time:
Accumulator Levels (%)
Accumulator Levels (%)
Accum.
Ch A Ch B Average Accum.
Ch A Ch B Average 21 21 22 22 23 23 24 24 In-leakage 21 gpm 22 gpm 23 gpm 24 gpm Total gpm Performed by _______________________________________________ Date____________
Independent Verification ______________________________________ Date____________
SM/CRS Review___________________________________________
Date____________
RETAIN a copy of this attachment in the Control Room file for this procedure until corrective action is completed or attachment is superseded.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 30 of 42 Rev. 15 ATTACHMENT 7 (Page 1 of 1)
POTENTIAL SOURCES OF PRT/RCDT IN-LEAKAGE 1.0 POTENTIAL SOURCES OF IN-LEAKAGE TO THE PRT COMPONENT TYPE COMMENTS 2WR82 (1)
Air oper. globe PRT primary water makeup (1)
There are other closed valves upstream of this valve.
2.0 POTENTIAL SOURCES OF IN-LEAKAGE TO THE RCDT COMPONENT TYPE COMMENTS 21SJ27 22SJ27 23SJ27 24SJ27 Air operated gate valve SI Accumulator drain valves.
2WL3 Diaphragm valve Refueling Canal is not a source of RCDT in-leakage during Mode 1-5 operation.
21WR62 22WR62 23WR62 24WR62 Air operated globe valve Primary makeup water supply valve to RCP Standpipe.
3.0 CONFIRMATORY ACTIONS TO CLASSIFY PRT AND RCDT IN-LEAKAGE COMPONENT COMMENTS 21WR62 22WR62 23WR62 24WR62 If in-leakage of primary makeup water via the RCP standpipes to the RCDT is suspected, it can be verified by temporary closure of normally open valves in the primary makeup water supply to the RCP Standpipe.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 31 of 42 Rev. 15 ATTACHMENT 8 (Page 1 of 1)
CONTAINMENT SUMP LEAKAGE CORRECTION DATA NOTE Identified leakage data must be obtained within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of final leak rate calculations.
1.0 UNIDENTIFIED leak rate from Containment Sump (X) _________ GPM (Attachment 1) 2.0 DETERMINE IDENTIFIED leak rate as follows:
A.
Inside Containment RCS leak rate
__________GPM (Attachment 9)
B.
Inside Containment Non-RCS leak rate
__________GPM (Attachment 11)
C.
IDENTIFIED Leak rate (A + B) =
(Y) __________GPM 3.0 CORRECTED UNIDENTIFIED Leak rate (X - Y) =
__________GPM Performed by _______________________________________________ Date ___________
Independent Verification ______________________________________ Date____________
SM/CRS Review___________________________________________
Date____________
RETAIN a copy of this attachment in the Control Room file for this procedure until corrective action is completed or attachment is superseded.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 32 of 42 Rev. 15 ATTACHMENT 9 (Page 1 of 1)
INSIDE CONTAINMENT RCS LEAK RATE Estimations of leakage is NOT permitted. Steam leakage should be condensed and calculated to provide valid data. RCS leakage should be collected into a suitable container over a selected time frame and leak rate calculated. Leakage which cannot be collected or measured is considered UNIDENTIFIED LEAKAGE.
NOTE Identified leakage data must be obtained within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of final leak rate calculations.
Leakage Source Leak Rate (gpm)
SAP Order Number Date Method of Leak Rate Identification Performed by _____________________________________________________ Date _____________
Independent Verification ____________________________________________ Date _____________
SM/CRS Review _________________________________________________
Date _____________
RETAIN a copy of this attachment in Control Room File for this procedure until corrective action is completed or attachment is superseded.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 33 of 42 Rev. 15 ATTACHMENT 10 (Page 1 of 1)
OUTSIDE CONTAINMENT RCS LEAK RATE Estimations of leakage is NOT permitted. Steam leakage should be condensed and calculated to provide valid data. Leakage from systems containing Reactor Coolant (e.g., Chemical Volume Control and Sampling Systems) should be collected into a suitable container and leak rate calculated.
23 Charging Pump Seal Water Tank overflow (2FL17150) is considered IDENTIFIED LEAKAGE.
Leakage which cannot be collected or measured is UNIDENTIFIED LEAKAGE.
NOTE Identified leakage data must be obtained within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of final leak rate calculations.
Leakage Source Leak Rate (gpm)
SAP Order Number Method used to determine leak rate Performed by _____________________________________________________ Date ____________
Independent Verification ____________________________________________ Date ____________
SM/CRS Review _________________________________________________
Date ____________
RETAIN a copy of this attachment in Control Room File for this procedure until corrective action is completed or attachment is superseded.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 34 of 42 Rev. 15 ATTACHMENT 11 (Page 1 of 1)
INSIDE CONTAINMENT NON-RCS LEAK RATE Estimations of leakage is NOT permitted. Steam leakage should be condensed and calculated to provide valid data. Leakage from systems NOT containing Reactor Coolant (Service Water, Component Cooling, Primary Water, etc.) should be collected into a suitable container over a selected time frame and leak rate calculated. Leakage which cannot be collected or measured is considered UNIDENTIFIED LEAKAGE.
Leakage Source Leak Rate (gpm)
SAP Order Number Date Method of Leak Rate Identification Performed by _____________________________________________________ Date ____________
Independent Verification ____________________________________________ Date ____________
SM/CRS Review _________________________________________________
Date ____________
RETAIN a copy of this attachment in Control Room File for this procedure until corrective action is completed or attachment is superseded.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 35 of 42 Rev. 15 ATTACHMENT 12 (Page 1 of 1)
PRT/RCDT IN-LEAKAGE may be used to help identify potential sources of in-leakage. Estimations of in-leakage is NOT permitted. In-leakage which cannot be measured is UNIDENTIFIED LEAKAGE.
NOTE Identified leakage data must be obtained within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of final leak rate calculations.
Leakage Source Leak Rate (gpm)
SAP Order Number Method used to determine leak rate Performed by _____________________________________________________ Date ____________
Independent Verification ____________________________________________ Date ____________
SM/CRS Review _________________________________________________
Date ____________
RETAIN a copy of this attachment in Control Room File for this procedure until corrective action is completed or attachment is superseded.
S2.OP-SO.RC-0004(Q)
Salem 2 Page 36 of 42 Rev. 15 ATTACHMENT 13 (Page 1 of 3)
VALVE LEAKOFF LINES NOTE Sources of RCS leakage which are located require that actions be taken, as determined by the SM/CRS, to terminate the leakage.
1.0 OUTSIDE CONTAINMENT 1.1 CHECK the following valve gland leakoff lines, as determined by the SM/CRS, for the following:
Temperature $10°F above ambient temperature.
Temperature $5°F above other valve gland leakoff lines expected to be at same temperature.
Flow, noise, radiation levels or any other indication of gland leakage.
COMPONENT DESCRIPTION LOCATION REMARKS 2CV8 LETDOWN ISOL FOR RHR AUX 84' 22 SI PUMP ROOM 2CV18 LETDOWN PRESSURE CONTROL VALVE AUX 84' LETDOWN HX VALVE ROOM 2CV21 LETDOWN DEMIN BYPASS ION EXCHANGER RM/DM ALLEY 2CV27 DEBORATING DEMIN 3-WAY INLET V ION EXCHANGER RM/DM ALLEY 2CV40 VCT OUTLET STOP MOV AUX 100' ROOM BY BA TRANSFER PUMPS 2CV41 VCT OUTLET STOP MOV AUX 100' ROOM BY BA TRANSFER PUMPS 2CV44 21 CHG PUMP SUCT VALVE AUX 84' 21 CHARGING PUMP ROOM 2CV48 21 CHG PUMP DISCH VALVE AUX 84' CHARGING PUMP VALVE ALLEY 2CV49 22 CHG PUMP SUCT VALVE AUX 84' 22 CHARGING PUMP ROOM 2CV53 22 CHG PUMP DISCH VALVE AUX 84' CHARGING PUMP VALVE ALLEY 2CV54 CENT CHG PUMP FLOW CONT VALVE INLET AUX 84' CHARGING PUMP VALVE ALLEY 2CV464 CHARGING CROSS TIE ISOLATION VALVE U1-AUX 84'CHARGING PUMP VALVE ALLEY BY 1CV55 1CV462 CHARGING CROSS TIE MOV AUX 84' CHARGING PUMP VALVE ALLEY BY 1CV55
S2.OP-SO.RC-0004(Q)
Salem 2 Page 37 of 42 Rev. 15 ATTACHMENT 13 (Page 2 of 3)
VALVE LEAKOFF LINES 1.0 OUTSIDE CONTAINMENT (continued)
COMPONENT DESCRIPTION LOCATION REMARKS 2CV55 CENT CHG PMP FLOW CONT VALVE AUX 84' CHARGING PUMP VALVE ALLEY 2CV56 CENT CHG PMP FLOW CONT VALVE OUTLET AUX 84' CHARGING PUMP VALVE ALLEY 2CV64 23 CHG PUMP DISCH VALVE AUX 84' CHARGING PUMP VALVE ALLEY 2CV71 CHG HDR PCV AUX 78' MECH PENET AREA SG B/D HX 2CV81 21 CHG PUMP DISCH VALVE AUX 84' CHARGING PUMP VALVE ALLEY 2CV82 22 CHG PUMP DISCH VALVE AUX 84' CHARGING PUMP VALVE ALLEY 2CV95 SEAL WTR INJ FILT BYP VALVE AUX 84' SEAL WTR INJ FILTERS VA RM 2CV116 RCP SEAL WTR RET HDR STOP MOV AUX 78' MECH PENET AREA SG B/D HX 2SJ4 BIT INLET MOV AUX 78' BIT RM LOWR LVL 2SJ5 BIT INLET MOV AUX 78' BIT RM LOWR LVL 2SJ12 BIT OUTLET MOV AUX 78' BIT RM LOWR LVL 2SJ13 BIT OUTLET MOV AUX 78' BIT RM LOWR LVL 21SJ45 RHR TO SI PMPS STOP MOV 22 SI PUMP ROOM 22SJ45 RHR TO CHG SI PMPS STOP MOV 21 COMP COOLING VA RM 21SJ49 RHR DISCH TO COLD LEGS MOV BIT RM UPPER LVL 22SJ49 RHR DISCH TO COLD LEGS BIT RM UPPER LVL
S2.OP-SO.RC-0004(Q)
Salem 2 Page 38 of 42 Rev. 15 ATTACHMENT 13 (Page 3 of 3)
VALVE LEAKOFF LINES 2.0 INSIDE CONTAINMENT 2.1 CHECK the following valve gland leakoff lines, as determined by the SM/CRS, for the following:
Temperature $10°F above ambient temperature.
Temperature $5°F above other valve gland leakoff lines expected to be at same temperature.
Flow, noise, radiation levels or any other indication of gland leakage.
COMPONENT DESCRIPTION LOCATION REMARKS 2CV132 EX LTDWN FCV NO 23 ACCUMULATOR 2CV134 EX LTDWN 3 WAY VALVE CAN 78' NO 23 ACCUM 2RH1 RHR COMMON SUCT MOV CAN 78' 23 S/G RCP & PRESS SUPPORTS
S2.OP-SO.RC-0004(Q)
Salem 2 Page 39 of 42 Rev. 15 ATTACHMENT 14 (Page 1 of 2)
VALVE DISCHARGE LINES NOTE Sources of RCS leakage which are located require that actions be taken, as determined by the SM/CRS, to terminate the leakage.
1.0 PRT SOURCES 1.1 CHECK the following valve discharge lines, as determined by the SM/CRS, for the following:
Temperature $10°F above ambient temperature.
Temperature $5°F above other valve discharge lines expected to be at same temperature.
Flow, noise, radiation levels or any other indication of leakage.
COMPONENT DESCRIPTION LOCATION REMARKS 2CV6 (SET @600 PSI)
LETDOWN PRESS RELIEF CAN 78' REGEN HX ROOM 2CV115 (SET @150 PSI)
SEAL RETURN RELIEF CAN 78' ELEVATOR AREA 2PR1 PZR PWR OP RELIEF V NO 2 PRESSURIZER AREA 2PR2 PZR PWR OP RELIEF V NO 2 PRESSURIZER AREA 2PR3 (SET @2485 PSI)
PZR SAFETY CAN 150' PRESSURIZER 2PR4 (SET @2485 PSI)
PZR SAFETY CAN 150' PRESSURIZER 2PR5 (SET @2485 PSI)
PZR SAFETY CAN 150' PRESSURIZER 2PR23 PZR SPRAY VALVE LOOP SEAL DRN TO PRT CAN 130' NO 2 PRESSURIZER AREA 2RC41 HEAD VENT SOLENOID VALVE CAN 140' NO 23 STEAM GENERATOR AREA 2RC43 HEAD VENT SOLENOID VALVE CAN 140' NO 23 STEAM GENERATOR AREA
S2.OP-SO.RC-0004(Q)
Salem 2 Page 40 of 42 Rev. 15 ATTACHMENT 14 (Page 2 of 2)
VALVE DISCHARGE LINES 2.0 RCDT SOURCES 2.1 CHECK the following valve discharge lines, as determined by the SM/CRS, for the following:
Temperature $10°F above ambient temperature.
Temperature $5°F above other valve discharge lines expected to be at same temperature.
Flow, noise, radiation levels or any other indication of leakage.
COMPONENT DESCRIPTION LOCATION REMARKS 2CV134 EX LTDWN 3 WAY VALVE CAN 78' NO 23 ACCUM 2RC4 VESSEL FLANGE LEAKOFF PLANT COMPUTER/TI401 21RC14 LOOP DRN 21 S/G & RCP SUPPORTS AREA 22RC14 LOOP DRN 21 S/G & RCP SUPPORTS AREA 23RC14 LOOP DRN 21 S/G & RCP SUPPORTS AREA 24RC14 LOOP DRN 21 S/G & RCP SUPPORTS AREA RCPs
S2.OP-SO.RC-0004(Q)
Salem 2 Page 41 of 42 Rev. 15 ATTACHMENT 15 (Page 1 of 2)
COMPLETION SIGN-OFF SHEET 1.0 COMMENTS (Include test deficiencies and corrective actions.)
S2.OP-SO.RC-0004(Q)
Salem 2 Page 42 of 42 Rev. 15 ATTACHMENT 15 (Page 2 of 2)
COMPLETION SIGN-OFF SHEET 1.0 COMMENTS (continued) 2.0 SIGNATURES Print Initials Signature Date INDEPENDENT VERIFICATION 3.0 SM/CRS FINAL REVIEW AND APPROVAL This procedure with Attachments 1, 5, 6, 8, 9, 10, 11, 12, 13, 14 and 15 (as applicable),
is reviewed for completeness and accuracy. All deficiencies, including the corrective actions, are clearly recorded in the COMMENTS Section of this attachment.
Signature:__________________________________________________
Date:______________
SM/CRS