ML110070162
| ML110070162 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/02/2009 |
| From: | Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LR-N10-0355 S2.OP-ST.RC-0008(Q), Rev 32 | |
| Download: ML110070162 (41) | |
Text
PSEG Internal Use Only Page 1 of 1 PSEG NUCLEAR L.L.C.
SALEM/OPERATIONS S2.OP-ST.RC-0008(Q) REV. 32 REACTOR COOLANT SYSTEM WATER INVENTORY BALANCE USE CATEGORY: I Biennial Review Performed: Yes ____ No ____ NA T DCP Packages and Affected Document Numbers incorporated into this revision: None The following OTSCs were incorporated into this revision: None REVISION
SUMMARY
Revised Attachment 3, Step 4.0 to reflect an actual IST leakage value of 39.0 sccm
[50113038]
for 2WR80. This change was incorporated to ensure actual 2WR80 inleakage is reflected in the RCS Water Inventory Balance, is consistent with calculation guidance currently delineated in Step 4.B (*), and is considered to be editorial in nature.
C, Step 4.0 B, changed 0.007 GPM to 0.01 GPM C, Step 4.0 C, changed 24.8 sccm to 39.0 sccm
[39.0 sccm x 2.6417E-4 gal/cm3 = 0.0103 gpm]
IMPLEMENTATION REQUIREMENTS Effective Date:
November 2, 2009 None
S2.OP-ST.RC-0008(Q)
Salem 2 Page 1 of 40 Rev. 32 REACTOR COOLANT SYSTEM WATER INVENTORY BALANCE TABLE OF CONTENTS SECTION TITLE PAGE 1.0 PURPOSE................................................................ 2 2.0 PREREQUISITES.......................................................... 3 3.0 PRECAUTIONS AND LIMITATIONS......................................... 4 4.0 EQUIPMENT/MATERIAL REQUIRED........................................ 8 5.0 PROCEDURE............................................................. 9 5.1 Plant Computer RCS Water Inventory Balance............................ 9 5.2 Manually Calculated RCS Water Inventory Balance....................... 12 5.3 Acceptance Criteria................................................. 14 5.4 Completion and Review............................................. 15 6.0 RECORDS............................................................... 19
7.0 REFERENCES
............................................................ 19 ATTACHMENTS PRT and RCDT Data.......................................... 21 Manual RCS Water Inventory Balance Test Data.................... 25 RCS Water Inventory Balance Calculation Sheet.................... 27 Manual Mass Leak Rate Correction............................... 30 Desktop Mass Leakrate Correction............................... 35 Reactor Coolant System Leak Rate Trending Data Sheet.............. 36 RCS Unidentified Leakrate Seven (7) Day Rolling Average Calculation Data Sheet......................................... 38 Completion Sign-Off Sheet..................................... 39
S2.OP-ST.RC-0008(Q)
Salem 2 Page 2 of 40 Rev. 32 1.0 PURPOSE 1.1 To provide instructions necessary to:
[CM-SC-2008-122] [C0265]
1.1.1 Calculate Unidentified Leakage IAW Technical Specification 3.4.7.2b.
This requirement is applicable in Modes 1-4.
1.1.2 Evaluate Primary to Secondary Leakage (as determined by Chemistry procedures)
IAW Technical Specification 3.4.7.2c. This requirement is applicable in Modes 1-4.
1.1.3 Calculate Identified Leakage IAW Technical Specification 3.4.7.2d.
This requirement is applicable in Modes 1-4.
1.1.4 Perform RCS Water Inventory Balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to satisfy Technical Specification 4.4.7.2.1.d. This requirement is applicable in Modes 1-4 (*).
1.2 Perform the Inservice Inspection and Testing of 2RH21, RHR TO RWST STOP VALVE, IAW Technical Specification 4.0.5. This requirement is applicable in Modes 1-4.
[C0611]
1.3 Performance of this procedure is required:
1.3.1 At least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in Modes 1-4 (*) to satisfy the requirements of Technical Specification 4.4.7.2.1.d.
1.3.2 Once per 24 months to verify 2RH21 leak rate is #2.0 gpm to satisfy the requirements of Technical Specification 4.0.5 (Reference Calculation S-C-RH-SEE-0922 and PR #951220233).
[C0611]
(*)
The provisions of Technical Specification 4.0.4 are NOT applicable for entry into Mode 4.
As delineated in Technical Specification Surveillance Requirement 4.4.7.2.1.d, completion of the Reactor Coolant System Water Inventory Balance is NOT required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 3 of 40 Rev. 32 2.0 PREREQUISITES
___ 2.1 ENSURE Charging, Letdown, and Seal Injection are in service IAW S2.OP-SO.CVC-0001(Q), Charging, Letdown, and Seal Injection.
___ 2.2 ENSURE Unit is in Mode 1-5 with Pressurizer bubble established.
___ 2.3 ENSURE Reactor power, Pressurizer level, Pressurizer pressure, and Tavg are stable.
___ 2.4 NOTIFY Chemistry that Accumulator Sampling System, and RCS Sampling System manipulations are NOT permitted during the RCS Water Inventory Balance.
___ 2.5 IF the RCS Water Inventory Balance is to be performed to satisfy the 2RH21 Leak Rate Surveillance requirement in Mode 4 or 5, THEN ENSURE OPEN the respective RH19 valve for the RHR Pump in service.
[C0611]
___ 2.6 IF Plant Computer is used to calculate the RCS Water Inventory Balance, THEN ENSURE the following computer points are available:
L0112N (L0112A OR L0114A as alternates) - VCT Level
T0140N (T0140A as alternate) - VCT Temperature
TRM1101N (TRM1101B as alternate) - Tavg
PRM0601N (PRM0601B as alternate) - Pressurizer Pressure
LRM0501N (LRM0501B as alternate) - Pressurizer Level 2.6.1 Tavg is $547°F.
2.6.2 All Reactor Coolant Pumps are operating.
2.6.3 Pressurizer pressure is stable between 2225 and 2245 psig.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 4 of 40 Rev. 32 3.0 PRECAUTIONS AND LIMITATIONS
___ 3.1 Steps identified with a dollar sign ($) are those items required to meet Technical Specification acceptance criteria. Such steps, if not satisfactorily completed, may have reportability requirements and should be brought to the immediate attention of the SM/CRS.
___ 3.2 Deborating Demineralizer alignment should NOT be changed throughout the duration of this surveillance test.
___ 3.3 Instruments monitored for indications of RCS leakage are to be the same for initial and final parameters.
___ 3.4 Any Plant computer point used in determining an average value (for example; L0480A, L0481A, L0482A used to determine average Pressurizer level LRM0501B) that is malfunctioning or undergoing testing or calibration is to be removed from scan by Maintenance Controls IAW SC.OP-DL.ZZ-0010(Q), Control Room Instrumentation and Alarms, until the RCS Water Inventory Balance test is completed. Failure to remove malfunctioning points, or points undergoing testing or calibration from scan may invalidate test results.
___ 3.5 Negative calculated RCS leak rate results are to be reviewed by SM/CRS to determine validity. Engineering is to be informed if a negative RCS leakrate result is considered valid.
___ 3.6 The Salem Station Administrative limit for single Steam Generator Primary to Secondary leakage is 140 gallons per day.
___ 3.7 IF a manual RCS Water Inventory Balance is required due to inoperability of the Plant Computer, Tavg <547°F, RCS pressure <2225 psig, or less than 4 RCPs operating, THEN a Plant Computer Primary System Leak Rate should be performed as soon as conditions permit.
___ 3.8 IF RHR is in service and all RCPs are secured, THEN manual RCS Water Inventory Balance data should be obtained from the following:
Plant Computer point T0630A (RHR Loop 21 operating)
Plant Computer point T0631A (RHR Loop 22 operating)
S2.OP-ST.RC-0008(Q)
Salem 2 Page 5 of 40 Rev. 32
___ 3.9 IF historical data is to be used to determine Primary System Leak Rate, THEN VERIFY the following for the time period the RCS Water Inventory Balance is to be calculated:
Sampling of Accumulator Sampling System, and RCS Sampling System manipulations have NOT occurred.
Reactor power, Pressurizer level, Pressurizer pressure, and Tavg or RCS temperature are stable during the period.
RCDT pumps have NOT run during the period.
PRT pressure and temperature has NOT been adjusted during the period.
___ 3.10 IF RCS pressure is <1700 psig, THEN RCS Pressure should be obtained from:
Plant P0499A (RCL SYS PRESS I), P2752A (RCL SYS PRESS II),
Computer:
or PRM2027B (RCL SYS PRESS AVG I & II).
Console:
2PI405 (RCS Pressure).
___ 3.11 Changes to Pressurizer level should be minimized during performance of this procedure.
___ 3.12 Any of the following may invalidate RCS Water Inventory Balance test results requiring restart of test:
Makeup to the VCT
Chemical addition to the RCS
Changes in CVCS Demineralizer or Filter alignments
Letdown diversion to CVCS Holdup Tanks
Filling venting, or draining Pressurizer Relief Tank (during PRT leakrate)
Pressurizer level change is greater than 0.5% from initial to final data points Tavg temperature change is greater than 0.5° F from initial to final data points Reactor Thermal Power change is greater than 3.4 MWth (0.1%) from initial to final data points (preferred) OR Reactor Power change is greater than 0.5%
from initial to final data points (alternate) [applicable in Modes 1 and 2 only]
Reactor Coolant Drain Tank pump down (during RCDT leakrate)
Failure of Plant Computer during Primary System Leak Rate
Failure of Plant Computer point used in Primary System Leak Rate
Changes in RCS (RCP starts, RHR Pump starts, HX alignment, etc.)
Filling RCP Standpipe(s)
Starting Safety Injection Pump(s)
Starting RHR Pump(s)
Filling Safety Injection Accumulator(s)
Automatic or Manual Start of the Primary Water Pump(s) (except to adjust PRT after leakrate IAW S2.OP-SO.PZR-0003(Q), Pressurizer Relief Tank Operations)
S2.OP-ST.RC-0008(Q)
Salem 2 Page 6 of 40 Rev. 32
___ 3.13 Double isolation (2WR80 and 2WR82 closed) of the Primary Water source is required to ensure isolation of this NON-RCS source of leakage to the PRT. In addition, the Primary Water Pumps will not be operated during the PRT leakrate to ensure no lifting of the valves from their seats.
___ 3.14 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:
Referring to Attachment 6, RCS Leakrate Trending Data Sheet:
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 (Monthly 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.
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.
The above indicated criteria is to be utilized for trending only. Exceeding ANY of the above indicated parameters or action levels does NOT impact Reactor Coolant System Operational Leakage as delineated in Technical Specification 3.4.7.2.
___ 3.15 A routine RCS Water Inventory Balance that is performed to satisfy Technical Specification Surveillance Requirement 4.4.7.2.1.d should normally be performed over a two hour duration.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 7 of 40 Rev. 32
___ 3.16 IF an RCS Water Inventory Balance is to be performed for reasons other than to satisfy the requirements of Technical Specification Surveillance Requirement 4.4.7.2.1.d, THEN the time interval of the RCS Water Inventory Balance may be determined at the discretion of the SM/CRS.
___ 3.17 IF conditions require performance of an RCS Water Inventory Balance over a time interval of less than two hours AND the leakrate will be utilized to satisfy the requirements of Technical Specification Surveillance Requirement 4.4.7.2.1.d, THEN Section 5.1 of this procedure should be performed in parallel with Section 5.2.
While the RCS Leakrate test data obtained in Section 5.1 may NOT be used to satisfy the requirements of Technical Specification 4.4.7.2.1.d, performance of a Plant Computer RCS Water Inventory Balance will be useful in validating the abbreviated RCS Leakrate.
When Section 5.1 is performed in support on abbreviated RCS Leakrate, test data should be forwarded to System Engineering.
___ 3.18 RCS Leakrates should NOT be performed over a time interval of less than 30 minutes.
___ 3.19 Technical Specification 4.4.7.2.1.d (*) provides guidance indicating performance of the Reactor Coolant System Water Inventory Balance is NOT required to be completed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation. Based on this guidance, it is permissible to change Modes without a current RCS leakrate provided the requirement to perform a RCS leakrate within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of establishment of steady state conditions is complied with.
As delineated in the Bases for Technical Specification 3/4.4.7.2, Reactor Coolant System Operational Leakage, for RCS operational leakage determination by water inventory balance, steady state operation is defined as stable RCS pressure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and Reactor Coolant Pump seal injection and return flows.
___ 3.20 During performance of the RCS Water Inventory Balance, manipulation of CFCUs (e.g., starting and stopping CFCUs, performing CFCU flushes, etc.) should be minimized to ensure consistent RCS Leakrate test results. Experience has indicated the potential for elevated RCS Leakrate conditions exist when CFCUs are manipulated during performance of the RCS Water Inventory Balance.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 8 of 40 Rev. 32
___ 3.21 When calculating the RCS Unidentified Leakrate Seven (7) Day Rolling Average IAW, the following guidance should be utilized:
[WCAP-16465-NP]
ANY negative RCS Unidentified Leakrate (ULR) values should be set to 0.0 gpm prior to performing the average.
ANY missing RCS Unidentified Leakrate (ULR) values for a specific day should be set to the value recorded for the previous day.
___ 3.22 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 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 1 - Baseline mean plus two (2) times the standard deviation.
Action Level 2 - Baseline mean plus three (3) times the standard deviation.
4.0 EQUIPMENT/MATERIAL REQUIRED 4.1 Calculator
S2.OP-ST.RC-0008(Q)
Salem 2 Page 9 of 40 Rev. 32 5.0 PROCEDURE 5.1 Plant Computer RCS Water Inventory Balance NOTE Section 5.1 is NOT to be performed to satisfy Technical Specification 4.4.7.2.1.d OR 4.0.5 for 2RH21. This Section may only be used for operator trending [Order 80023756 (70031764) to update and validate Plant Computer program].
5.1.1 IF automatic RCDT pump start appears imminent during test, THEN PUMP RCDT to minimum level IAW S2.OP-SO.WL-0005(Q),
Reactor Coolant Drain Tank Operation.
5.1.2 IF makeup to the VCT appears imminent during test, THEN ADJUST VCT level and pressure IAW S2.OP-SO.CVC-0006(Q),
Boron Concentration Control.
5.1.3 IF PRT level, pressure, or temperature adjustments are required prior to the start of the test, THEN:
A.
ADJUST PRT parameters IAW S2.OP-SO.PZR-0003(Q),
Pressurizer Relief Tank Operations.
B.
WAIT at least 15 minutes for the PRT parameters to stabilize.
5.1.4 ENSURE CLOSED the following valves:
2WR80, CONT PRI WATER STOP
2WR82, PRT WATER SUPPLY 5.1.5 ENSURE both Primary Water Pumps are NOT running.
5.1.6 ENSURE 2CV134 is selected to FLOW TO VCT position.
5.1.7 ENSURE AT LEAST ONE of the following conditions exists:
2CV35 is selected to the MANUAL FLOW TO VCT position.
VCT level is adequate to preclude Automatic High Level Divert of 2CV35 for duration of RCS Water Inventory Balance.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 10 of 40 Rev. 32 5.1.8 START the Primary System Leak Rate on the Plant Computer as follows:
A.
Using the mouse left button, DOUBLE CLICK-ON the "PROCESS DIAGRAM *W1" icon.
B.
Using the mouse left button, CLICK-ON "PAGE" from the top menu bar.
C.
Using the mouse left button, CLICK-ON "PRIM SYS LEAK RATE" from the Application Programs screen.
D.
At the desired test time, CLICK-ON "TOGGLE" using the mouse left button to START test.
5.1.9 RECORD Initial Data on Attachment 1, Sections 2.0 and 4.0.
5.1.10 IF the PRT OR RCDT leakrate is to be captured and the system returned for normal operation prior to RCS Water Inventory Balance Test Data completion, THEN:
A.
RECORD Final Data on Attachment 1, Sections 2.0 or 4.0.
B.
OPERATE the Primary Water Pumps as required to adjust the PRT parameters IAW S2.OP-SO.PZR-0003(Q), Pressurizer Relief Tank Operations.
5.1.11 IF this test is being performed for routine RCS Water Inventory Balance calculation, THEN OBTAIN most recent Primary to Secondary Leak Rate from Chemistry and RECORD on Attachment 3, Step 2.E.
5.1.12 IF this test is being performed due to unexpected or unexplained increase in RCS leakage, THEN:
Direct Chemistry to calculate Primary to Secondary Leak Rate and RECORD on Attachment 3, Step 2.E.
Direct Radiation Protection to MONITOR 2R11A/2R12A and report results to SM/CRS.
INITIATE S2.OP-SO.RC-0004(Q), Identifying and Measuring Leakage.
5.1.13 When required time has elapsed since initiating RCS Water Inventory Balance, ENSURE the following Plant Computer points are available:
L0112N (L0112A OR L0114A as alternates) - VCT Level
T0140N (T0140A as alternate) - VCT Temperature
TRM1101N (TRM1101B as alternate) - Tavg
PRM0601N (PRM0601B as alternate) - Pressurizer Pressure
LRM0501N (LRM0501B as alternate) - Pressurizer Level
S2.OP-ST.RC-0008(Q)
Salem 2 Page 11 of 40 Rev. 32 5.1.14 When the following conditions exist, Reactor Thermal Power is within 3.4 MWth of initial power as indicated on QPP0004T, Reactor Thermal Output - Ten Minute Average (preferred)
OR Reactor Power is within 0.5% of initial power as indicated on either NRM0401N PR Nuclear Chan Avg Q 1M Avg, or N41-N44 (alternate)
[applicable in Modes 1 and 2 only], and
Final RCS Tavg is within +/-0.5°F of initial Tavg, and
Pressurizer pressure is between 2225 and 2245 psig, and
Pressurizer level is within 0.5% of initial level.
PERFORM the following:
A.
CLICK-ON "TOGGLE", using the mouse left button to STOP test.
B.
OBTAIN the Computer Leak Rate printout from the Sequence of Events printer which will automatically print when the RCS Water Inventory Balance is stopped.
OR C.
PRINT Test Results by moving cursor to the screens Blue Background Field and press the mouse right button, then SELECT Screen Print.
5.1.15 RECORD Leak Rate results on Attachment 3, Section 1.0.
5.1.16 IF the PRT AND RCDT are NOT returned to service, THEN RECORD Final Data on Attachment 1, Sections 2.0 and 4.0.
5.1.17 PLACE 2CV35, VCT 3 WAY INLET VALVE, in AUTO.
5.1.18 OPERATE the Primary Water Pumps as required to support current plant evolutions.
5.1.19 NOTIFY Chemistry that all sampling may resume.
5.1.20 COMPLETE Attachment 1, PRT and RCDT Data.
5.1.21 COMPLETE Attachment 3, RCS Water Inventory Balance Calculation Sheet.
5.1.22 ATTACH the completed RCS Water Inventory Balance test printout to this procedure.
5.1.23 DIRECT a second Operator to perform Independent Verification of all calculations performed in this procedure.
[C0284]
S2.OP-ST.RC-0008(Q)
Salem 2 Page 12 of 40 Rev. 32 5.2 Manually Calculated RCS Water Inventory Balance 5.2.1 IF Automatic RCDT pump start appears imminent during test, THEN PUMP RCDT to minimum level IAW S2.OP-SO.WL-0005(Q),
Reactor Coolant Drain Tank Operation.
5.2.2 IF makeup to the VCT appears imminent during test, THEN ADJUST VCT level and pressure IAW S2.OP-SO.CVC-0006(Q),
Boron Concentration Control.
5.2.3 IF PRT level, pressure, or temperature adjustments are required prior to the start of the test, THEN:
A.
ADJUST PRT parameters IAW S2.OP-SO.PZR-0003(Q),
Pressurizer Relief Tank Operations.
B.
WAIT at least 15 minutes for the PRT parameters to stabilize.
5.2.4 ENSURE CLOSED the following valves:
2WR80, CONT PRI WATER STOP
2WR82, PRT WATER SUPPLY 5.2.5 ENSURE both Primary Water Pumps are stopped.
5.2.6 ENSURE 2CV134 is selected to FLOW TO VCT position.
5.2.7 ENSURE AT LEAST ONE of the following conditions exists:
2CV35 is selected to the MANUAL FLOW TO VCT position.
VCT level is adequate to preclude Automatic High Level Divert of 2CV35 for duration of RCS Water Inventory Balance.
5.2.8 RECORD Initial Data on Attachment 1, Sections 2.0 and 4.0, and Attachment 2.
5.2.9 IF the PRT OR RCDT leakrate is to be captured and the system returned for normal operation prior to RCS Water Inventory Balance Test Data completion, THEN:
A.
RECORD Final Data on Attachment 1, Sections 2.0 or 4.0.
B.
OPERATE the Primary Water Pumps as required to adjust the PRT parameters IAW S2.OP-SO.PZR-0003(Q), Pressurizer Relief Tank Operations.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 13 of 40 Rev. 32 5.2.10 IF this test is being performed for routine RCS Water Inventory Balance calculation, THEN OBTAIN most recent Primary to Secondary Leak Rate from Chemistry AND RECORD on Attachment 3, Step 2.E.
5.2.11 IF this test is being performed due to unexpected or unexplained increase in RCS leakage, THEN:
Direct Chemistry to calculate Primary to Secondary Leak Rate and RECORD on Attachment 3, Step 2.E.
INITIATE S2.OP-SO.RC-0004(Q), Identifying and Measuring Leakage.
5.2.12 When required time has elapsed, AND the following conditions exist, Reactor Thermal Power is within 3.4 MWth of initial power as indicated on QPP0004T, Reactor Thermal Output - Ten Minute Average (preferred)
OR Reactor Power is within 0.5% of initial power as indicated on either NRM0401N PR Nuclear Chan Avg Q 1M Avg, or N41-N44 (alternate)
[applicable in Modes 1 and 2 only], and
Final RCS Tavg is within +/-0.5°F of initial Tavg, and
Pressurizer pressure is within 10 psig of initial pressure, and
Pressurizer level is within 0.5% of initial level.
RECORD Final Data on Attachment 2.
5.2.13 IF the PRT AND RCDT are NOT returned to service, THEN RECORD Final Data on Attachment 1, Sections 2.0 and 4.0.
5.2.14 PLACE 2CV35, VCT 3 WAY INLET VALVE, in AUTO.
5.2.15 OPERATE the Primary Water Pumps as required to support current plant evolutions.
5.2.16 NOTIFY Chemistry that all sampling may resume.
5.2.17 COMPLETE Attachments 1, 2, 3, and 4 or 5 as applicable.
5.2.18 IF Attachment 5 was used, THEN ATTACH the completed Desktop Mass Leak Rate Correction printout to this procedure.
5.2.19 DIRECT a second Operator to perform Independent Verification of all calculations performed in this procedure.
[C0284]
S2.OP-ST.RC-0008(Q)
Salem 2 Page 14 of 40 Rev. 32 5.3 Acceptance Criteria 5.3.1 This surveillance is satisfactory when applicable sections of Attachment 3 are completed with all equipment listed meeting Acceptance Criteria stated in Attachment 3.
OR 5.3.2 This surveillance is unsatisfactory.
A.
INITIATE Notification(s) to correct the unsatisfactory condition(s).
B.
RECORD Notification number(s), AND reason for unsatisfactory completion on Attachment 8 in the Comments section.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 15 of 40 Rev. 32 5.4 Completion and Review 5.4.1 COMPLETE Attachment 8, Sections 1.0 and 2.0, AND FORWARD this procedure to the SM/CRS for review.
5.4.2 PERFORM the following to trend the Reactor Coolant System Leak Rate:
A.
RECORD the following on the Attachment 6 located in the Salem 2 Monthly RCS Leakrate binder:
Date Identified Leak Rate from Attachment 3, Line 3.0 Unidentified Leakrate from Attachment 3, Line 4.C RCDT Inleakage from Attachment 3, Line 5.0 NOTE The following guidance should be utilized when calculating the RCS Unidentified Leakrate Seven (7) Day Rolling Average:
[WCAP-16465-NP]
ANY negative RCS Unidentified Leakrate values should be set to 0.0 gpm prior to performing the average.
ANY missing RCS Unidentified Leakrate values for a specific day should be set to the value recorded for the previous day.
B.
RECORD the following on Attachment 7, RCS Unidentified Leakrate Seven (7) Day Rolling Average Calculation Data Sheet:
The previous six (6) days of RCS Unidentified Leakrates from Attachment 6, Reactor Coolant System Leak Rate Trending Data Sheet AND associated date(s).
Unidentified Leakrate from Attachment 3, Line 4.C C.
CALCULATE the Seven (7) Day Rolling Average for the RCS Unidentified Leakrate IAW Attachment 7, RCS Unidentified Leakrate Seven (7) Day Rolling Average Calculation Data Sheet.
D.
PERFORM Independent Verification of the Seven (7) Day Rolling Average RCS Unidentified Leakrate calculation IAW Attachment 7, RCS Unidentified Leakrate Seven (7) Day Rolling Average Calculation Data Sheet.
E.
RECORD the Seven (7) Day Rolling Average RCS Unidentified Leakrate on the Attachment 6 located in the Salem 2 Monthly RCS Leakrate binder:
(continued on next page)
S2.OP-ST.RC-0008(Q)
Salem 2 Page 16 of 40 Rev. 32 5.4.2 (continued)
NOTE The indicated criteria is to be utilized for trending purposes only. Exceeding ANY of the indicated parameters or action levels does NOT impact Reactor Coolant System Operational Leakage as delineated in Technical Specification 3.4.7.2. Based on the severity of the elevated RCS Leakrate condition, System Engineering will determine any additional corrective actions, if applicable.
When a notification was previously submitted documenting a similar elevated RCS leakrate condition, then initiation of an additional notification is NOT required, however, the Notification number(s) of the previously identified condition should be recorded on Attachment 8 in the Comments Section.
F.
IF ANY of the following conditions are met (referring to Attachment 6),
THEN ENSURE a notification to System Engineering documenting the elevated RCS Leakrate condition is initiated:
Absolute Action Levels:
Any seven (7) day rolling average of Unidentified RCS Leakrate exceeds 0.10 gpm, or Any two (2) of three (3) consecutive RCS Unidentified leakrates exceed 0.15 gpm, or Any RCS Unidentified leakrate exceeds 0.30 gpm, or Any unexpected measurable, confirmed rise in RCS Unidentified leakrate as determined by the SM/CRS.
Deviation from Baseline Mean (Monthly Average) Action Levels:
Any nine (9) consecutive RCS Unidentified leakrates exceed the Monthly Average, or Any two (2) of three (3) consecutive RCS Unidentified leakrates exceed the Action Level I value, or Any RCS Unidentified leakrate exceeds the Action Level II value.
(continued on next page)
S2.OP-ST.RC-0008(Q)
Salem 2 Page 17 of 40 Rev. 32 5.4.2 (continued)
G.
IF a notification is initiated to document ANY of the above conditions, THEN 1.
RECORD Notification number(s) on Attachment 8 in the Comments Section.
2.
EVALUATE performance of S2.OP-SO.RC-0004(Q), Identifying and Measuring Leakage, based on review of the following parameters:
___ Changes in RCDT Inleakage, or
___ Recent Plant Manipulations (e.g., shifting to Excess Letdown, shifting CVC Pumps which results in VCT and CVC temperature changes, etc.), or
___ Fluctuations in CCW temperature or river temperatures.
5.4.3 IF plant transient conditions required performance of an abbreviated Reactor Coolant System Water Inventory Balance (i.e., less than two hours),
THEN RECORD the following on Attachment 8 in the Comments Section:
Date and Test Results of the last performed S2.OP-ST.RC-0008(Q)
Description of Transient Condition and an Expected Time establishment of steady state conditions achieved allowing performance of a RCS Leakrate.
Any additional pertinent information as deemed appropriate by the SM/CRS (e.g., status of RCS leakrate instrumentation as identified in Technical Specification 3.4.7.1, recent S2.OP-PT.CAN-0001(Q)
Containment Walkdown results, Results of the Plant Computer RCS Water Inventory Balance, etc.).
S2.OP-ST.RC-0008(Q)
Salem 2 Page 18 of 40 Rev. 32 5.4.4 SM/CRS PERFORM the following:
A.
REVIEW this procedure with Attachments 1-8 for completeness and accuracy.
B.
IF ANY Evaluation Result is UNSAT for applicable Mode, THEN ENTER applicable Technical Specification Action Statement(s).
C.
COMPLETE Attachment 8, Section 3.0.
D.
IF 2RH21 Leak Rate is performed, THEN PLACE this procedure in the IST IMPLEMENTATION ENGINEER REVIEW REQUIRED mail slot.
E.
IF 2RH21 Leak Rate is NOT performed, THEN:
1.
RECORD N/A on Attachment 8, Section 4.0.
2.
FORWARD completed procedure to Operations Staff.
END OF PROCEDURE SECTION
S2.OP-ST.RC-0008(Q)
Salem 2 Page 19 of 40 Rev. 32 6.0 RECORDS 6.1 Retain the following IAW RM-AA-101, Records Management Program: (as applicable)
Primary System Leak Rate Hard Copy (as applicable)
7.0 REFERENCES
7.1 Updated Final Safety Analysis Report:
7.1.1 Section 15.2.12, Accidental Depressurization of the RCS 7.1.2 Section 15.3.1, Loss of Reactor Coolant 7.1.3 Appendix A, TMI Lessons Learned, 2.1.6.a, Leakage Outside Containment 7.2 Technical Specifications - Unit 2:
7.2.1 3.4.7.1, Leakage Detection Systems 7.2.2 3.4.7.2, Operational Leakage 7.2.3 4.0.5, Inservice Testing and Inspection
7.3 Procedures
7.3.1 ER-AA-321, Administrative Requirements for Inservice Testing 7.3.2 S2.OP-AB.RC-0001(Q), Reactor Coolant System Leak 7.3.3 S2.OP-AB.SG-0001(Q), Steam Generator Tube Leak 7.3.4 S2.OP-SO.WL-0005(Q), Reactor Coolant Drain Tank Operation
7.4 Drawings
7.4.1 205328, No. 2 Unit Chemical and Volume Control System P&ID 7.4.2 205301, No. 2 Unit Reactor Coolant System P&ID 7.4.3 220403, No. 1 and No. 2 Units CVCS
7.5 Others
7.5.1 Event Classification Guide:
A.
Section 1, Primary Leakage/SG Tube Leakage B., Unusual Event 7.5.2 NRC GL 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants 7.5.3 USNRC Regulatory Guide 1.45, Reactor Coolant Pressure Boundary Leakage Detection Systems
S2.OP-ST.RC-0008(Q)
Salem 2 Page 20 of 40 Rev. 32 7.5.4 USNRC NUREG-0986, RCSLK8: Reactor Coolant System Leak Rate Determination for PWRs 7.5.5 USNRC NUREG 0737, Clarification of TMI Action Plan Requirements 7.5.6 S-C-RH-SEE-0922, Dose Assessment for Potential RHR Valve Leakage to RWST Vented to Atmosphere.
7.5.7 S-C-RC-MEE-1067, Non-conservative Reactor Coolant System Leakage Calculation.
7.5.8 Salem Generating Station IST Manual.
7.5.9 PR #951220233, 1RH21 & 2RH21 Seat Leak Testing 7.5.10 DCP 2EC-3337, P-250 Plant Computer Replacement 7.5.11 S-C-R200-MDC-080, Revision 2, Equation for Error Corrections in the RCS Leakage Calculations Induced by Changes in Pressurizer Level and Reactor Coolant System Temperature.
7.5.12 S-C-RCS-ECS-0178, RCS Water Inventory Balance Software for the Salem Control Room 7.5.13 Minor Modification S97-175, Rerouting of Non RCS Leakage to Containment Sump Instead of the PRT 7.5.14 AR980311093, Reactivity - Accumulator Purge Returns to VCT 7.5.15 NRC Inspection Manual 2515D 7.5.16 WCAP-16423, Standard Process and Methods for Calculating RCS Leak Rate for Pressurized Water Reactors 7.5.17 WCAP-16465, Standard RCS Leakage Action Levels and Response Guidelines for Pressurized Water Reactors 7.6 Cross-
References:
7.6.1 Technical Specifications - Unit 2:
A.
3.4.7.2, Operational Leakage
7.6.2 Procedures
A.
RM-AA-101, Records Management Program B.
NC.NA-AP.ZZ-0064(Q), Software Quality Assurance (Digital Systems)
C.
SC.OP-DL.ZZ-0010(Q), Control Room Instrumentation and Alarms D.
S2.OP-SO.CVC-0001(Q), Charging, Letdown, and Seal Injection E.
S2.OP-SO.CVC-0006(Q), Boron Concentration Control F.
S2.OP-SO.PZR-0003(Q), Pressurizer Relief Tank Operation G.
S2.OP-SO.RC-0004(Q), Identifying and Measuring Leakage H.
S2.OP-TM.ZZ-0002(Q), Tank Capacity Data
7.7 Commitments
7.7.1 C0265 - NSO LER 311/89-015-00 7.7.2 C0283 - NRC VIOL 311/87-018-01 7.7.3 C0284 - NRC VIOL 272/90-014-00 7.7.4 C0611 - NRC INFO 91-56 7.7.5 CM-SC-2008-122, Implement RCS Leak Rate Guidance Recommendations by December 31, 2008
S2.OP-ST.RC-0008(Q)
Salem 2 Page 21 of 40 Rev. 32 ATTACHMENT 1 (Page 1 of 4)
PRT AND RCDT DATA 1.0 PRT DATA Indicator Range
% Level Change Volume for 1% Change Volume Change 0 - 3.0%
73.1 gal/%
gal
>3.0 - 5.0%
82.8 gal/%
gal
>5.0 - 7.0%
91.3 gal/%
gal
>7.0 - 10.0%
98.9 gal/%
gal
>10.0 - 12.0%
105.7 gal/%
gal
>12.0 - 14.0%
111.8 gal/%
gal
>14.0 - 16.0%
117.4 gal/%
gal
>16.0 - 19.0%
122.4 gal/%
gal
>19.0 - 21.0%
126.9 gal/%
gal
>21.0 - 23.0%
131.1 gal/%
gal
>23.0 - 25.0%
134.9 gal/%
gal
>25.0 - 28.0%
138.2 gal/%
gal
>28.0 - 30.0%
141.5 gal/%
gal
>30.0 - 32.0%
143.5 gal/%
gal
>32.0 - 35.0%
146.0 gal/%
gal
>35.0 - 37.0%
148.3 gal/%
gal
>37.0 - 39.0%
150.4 gal/%
gal
>39.0 - 41.0%
151.5 gal/%
gal
>41.0 - 44.0%
152.3 gal/%
gal
>44.0 - 46.0%
153.7 gal/%
gal
>46.0 - 48.0%
154.1 gal/%
gal
>48.0 - 50.0%
154.3 gal/%
gal
>50.0 - 53.0%
154.3 gal/%
gal
>53.0 - 55.0%
154.1 gal/%
gal
>55.0 - 57.0%
153.7 gal/%
gal
>57.0 - 60.0%
152.3 gal/%
gal
>60.0 - 62.0%
151.5 gal/%
gal
>62.0 - 64.0%
150.4 gal/%
gal
>64.0 - 66.0%
148.3 gal/%
gal
>66.0 - 69.0%
146.0 gal/%
gal
>69.0 - 71.0%
143.5 gal/%
gal
>71.0 - 73.0%
141.5 gal/%
gal
>73.0 - 75.0%
138.2 gal/%
gal
>75.0 - 78.0%
134.9 gal/%
gal
>78.0 - 80.0%
131.1 gal/%
gal
>80.0 - 82.0%
126.9 gal/%
gal
>82.0 - 85.0%
122.4 gal/%
gal
>85.0 - 87.0%
117.4 gal/%
gal
>87.0 - 89.0%
111.8 gal/%
gal
>89.0 - 91.0%
105.7 gal/%
gal
>91.0 - 94.0%
98.9 gal/%
gal
>94.0 - 96.0%
91.3 gal/%
gal
>96.0 - 98.0%
82.8 gal/%
gal
>98.0 - 100.0%
73.1 gal/%
gal TOTAL gal
S2.OP-ST.RC-0008(Q)
Salem 2 Page 22 of 40 Rev. 32 ATTACHMENT 1 (Page 2 of 4)
PRT AND RCDT DATA 2.0 PRT LEAK RATE Parameter Initial Data (A)
Final Data (B)
Difference (B - A)
PRT LEVEL gal (2.4)
TIME min
___ 2.1 RECORD INDICATOR USED FOR DATA:
_____ Plant Computer point L0485A (preferred)
_____ Console Indicator 2LI470 (alternate)
___ 2.2 CONVERT the PRT % level change to gallons by multiplying the % level change X Volume Change for 1% for the applicable Indicator Range. IF the PRT level change spans two or more Indicator Ranges, THEN volume changes are to be calculated in each of the applicable Indicator Ranges [e.g., a PRT level increase from 69.2% to 71.6% is to be calculated as (1.8% X 143.5 gal/%) and (0.6% X 141.5 gal/%)].
___ 2.3 ADD all volume changes to obtain total gallons, as applicable.
___ 2.4 RECORD total volume change in Section 2.0 of this attachment.
___ 2.5 DIVIDE total gallons volume change by elapsed time (minutes) to determine leak rate:
TOTAL VOLUME CHANGE _______ gal ÷ ELAPSED TIME ______ min =
LEAK RATE _______ GPM
S2.OP-ST.RC-0008(Q)
Salem 2 Page 23 of 40 Rev. 32 ATTACHMENT 1 (Page 3 of 4)
PRT AND RCDT DATA 3.0 RCDT DATA Indicator Range
% Level Change Volume for 1% Change Volume Change 0 - 3.0%
4.6 gal/%
gal
>3.0 - 6.0%
4.7 gal/%
gal
>6.0 - 9.0%
4.8 gal/%
gal
>9.0 - 12.0%
4.8 gal/%
gal
>12.0 - 15.0%
4.8 gal/%
gal
>15.0 - 18.0%
4.9 gal/%
gal
>18.0 - 21.0%
4.9 gal/%
gal
>21.0 - 24.0%
4.9 gal/%
gal
>24.0 - 27.0%
4.9 gal/%
gal
>27.0 - 30.0%
4.9 gal/%
gal
>30.0 - 33.0%
4.9 gal/%
gal
>33.0 - 36.0%
4.8 gal/%
gal
>36.0 - 39.0%
4.8 gal/%
gal
>39.0 - 42.0%
4.8 gal/%
gal
>42.0 - 45.0%
4.7 gal/%
gal
>45.0 - 48.0%
4.6 gal/%
gal
>48.0 - 51.0%
4.6 gal/%
gal
>51.0 - 54.0%
4.5 gal/%
gal
>54.0 - 57.0%
4.4 gal/%
gal
>57.0 - 60.0%
4.3 gal/%
gal
>60.0 - 63.0%
4.2 gal/%
gal
>63.0 - 66.0%
4.0 gal/%
gal
>66.0 - 69.0%
3.9 gal/%
gal
>69.0 - 72.0%
3.7 gal/%
gal
>72.0 - 75.0%
3.6 gal/%
gal
>75.0 - 78.0%
3.4 gal/%
gal
>78.0 - 81.0%
3.2 gal/%
gal
>81.0 - 84.0%
2.9 gal/%
gal
>84.0 - 87.0%
2.7 gal/%
gal
>87.0 - 90.0%
2.4 gal/%
gal
>90.0 - 93.0%
2.0 gal/%
gal
>93.0 - 96.0%
1.5 gal/%
gal
>96.0 - 100.0%
0.8 gal/%
gal TOTAL gal
S2.OP-ST.RC-0008(Q)
Salem 2 Page 24 of 40 Rev. 32 ATTACHMENT 1 (Page 4 of 4)
PRT AND RCDT DATA 4.0 RCDT LEAK RATE Parameter Initial Data (A)
Final Data (B)
Difference (B - A)
RCDT LEVEL gal (4.4)
TIME min
___ 4.1 RECORD INDICATOR USED FOR DATA:
_____ LA-4144RB Recorder Channel A on 2RP1 (preferred)
_____ 2LT1003 on Panel 104 (alternate)
___ 4.2 CONVERT the RCDT % level change to gallons by multiplying the % level change X Volume Change for 1% for the applicable Indicator Range. IF the RCDT level change spans two or more Indicator Ranges, THEN volume changes are to be calculated in each of the applicable Indicator Ranges [e.g., a RCDT level increase from 69.2% to 72.6% is to be calculated as (2.8% X 3.7 gal/%) and (0.6% X 3.6 gal/%)].
___ 4.3 ADD all volume changes to obtain total gallons, as applicable.
___ 4.4 RECORD total volume change in Section 4.0 of this attachment.
___ 4.5 DIVIDE total gallons volume change by elapsed time (minutes) to determine leak rate:
TOTAL VOLUME CHANGE _______ gal ÷ ELAPSED TIME ______ min =
LEAK RATE _______ GPM Performed By ________________________________________________________
Date __________
Independent Verification _______________________________________________
Date __________
S2.OP-ST.RC-0008(Q)
Salem 2 Page 25 of 40 Rev. 32 ATTACHMENT 2 (Page 1 of 2)
MANUAL RCS WATER INVENTORY BALANCE TEST DATA 1.0 DATA COLLECTION NOTE
Available Plant Computer points should be used when possible.
Record console VCT and Pressurizer levels, and RCS Tavg to the nearest tenth.
Indications used shall be circled.
Initial data and final data shall be obtained from the same indicators.
or 5 is to be used to calculate Mass Leak Rate Correction.
Parameter Start Finish Difference TIME min.
Parameter Initial Data (A)
Final Data (B)
Difference or Average REACTOR POWER (MWth / %)
Computer: QPP0004T (10 Minute Avg)
NRM0401N (PR 1M Avg)
Console/NI Racks: Avg of N41-N44 (A-B)
(+/-3.4 MWth)
(+/-0.5% PR)
VCT LEVEL Computer: L0112N or L0112A or L0114A Console: 2LT112 Panel 116: 2LT114A (A-B)
VCT TEMPERATURE Computer: T0140N or T0140A Console: 2TI130A (A+B)/2
°F RCS TEMPERATURE TAVG Computer: TRM1101N or TRM1101B (Valid only when Tavg $547°F)
Console: 2TI412, 2TI422, 2TI432, 2TI442 (Valid only when RCP I/S)
RHR HX INLET TEMP (Valid only on operating RHR loop w/RCP O/S)
Computer: T0630A or T0631A WR HOT LEG TEMP (Valid w/RCPs I/S & Tavg <547°F)
Computer: T0419A, T0439A, T0459A, T0479A Console: TA-14, TA-16, TA-36, TA-38 (A-B)
(+/-0.5 °F)
°F
S2.OP-ST.RC-0008(Q)
Salem 2 Page 26 of 40 Rev. 32 ATTACHMENT 2 (Page 2 of 2)
MANUAL RCS WATER INVENTORY BALANCE TEST DATA Parameter Initial Data (A)
Final Data (B)
Difference or Average PRESSURIZER PRESSURE Computer: PRM0601N or PRM0601B
(
- P0499A, P2752A, PRM2027B)
Console: 2PI455A, 2PI456, 2PI457, 2PI474A,
(
- 2PI405)
(* Valid only with pressure <1700 psig)
(A+B)/2 PSIG (A-B)
(+/-10)
PRESSURIZER LEVEL Computer: LRM0501N or LRM0501B Console: 2LI459A, 2LI460A, 2LI461A Console: COLD CAL 2LI462 (Valid in Mode 4 or 5 with a bubble in the Pressurizer)
(A-B)
(+/-0.5)
BORIC ACID TOTALIZER (A-B) gal (must be zero)
PRIMARY WATER TOTALIZER (A-B) gal (must be zero)
___ 1.1 TRANSFER Difference or Average to Attachment 4 or 5 for Mass Leak Rate Correction.
Performed By ________________________________________________________
Date __________
Independent Verification _______________________________________________
Date __________
S2.OP-ST.RC-0008(Q)
Salem 2 Page 27 of 40 Rev. 32 ATTACHMENT 3 (Page 1 of 3)
RCS WATER INVENTORY BALANCE CALCULATION SHEET
___ 1.0 TOTAL CORRECTED VOLUME LEAK RATE (from Attachment 4, Attachment 5 or Step 5.1.15, as applicable)
__________GPM NOTE If the following (2A, 2B, 2C & 2D) Identified RCS Leak Rates are to be used in the Total Identified RCS Leak Rate, then identified leakage data must be obtained during performance of this procedure. If current leakrate is unavailable, a value of "0" shall be used.
___ 2.0 IDENTIFIED RCS LEAK RATE:
A.
IDENTIFIED RCS LEAKAGE INSIDE CONTAINMENT
[from S2.OP-SO.RC-0004(Q), Attachment 9]
__________GPM B.
IDENTIFIED RCS LEAKAGE OUTSIDE CONTAINMENT
[from S2.OP-SO.RC-0004(Q), Attachment 10]
__________GPM C.
IDENTIFIED RCS LEAKAGE TO ACCUMULATORS
[from S2.OP-SO.RC-0004(Q), Attachment 6]
__________GPM
IF value is a negative number, THEN RECORD "0" gpm.
D.
PRT INLEAKAGE (from Attachment 1, Section 2.0)
__________GPM E.
PRIMARY TO SECONDARY LEAK RATE (from Chemistry)
__________GPM
IF Leak Rate is $1 GPD, THEN RECORD the number: __________GPD AND DIVIDE by 1440.
IF RCS Leak Rate <1 GPD, THEN RECORD "0" GPM.
___ 3.0 TOTAL IDENTIFIED RCS LEAK RATE =2A+2B+2C+2D+2E
__________GPM
S2.OP-ST.RC-0008(Q)
Salem 2 Page 28 of 40 Rev. 32 ATTACHMENT 3 (Page 2 of 3)
RCS WATER INVENTORY BALANCE CALCULATION SHEET NOTE Unidentified Leakage >0.85 gpm requires performance of S2.OP-SO.RC-0004(Q),
Identifying and Measuring Leakage.
___ 4.0 UNIDENTIFIED LEAK RATE:
A.
SUBTRACT Line 3.0 from Line 1.0
__________GPM B.
2WR80 inleakage (*)
0.01 GPM C.
ADD 4A and 4B to obtain UNIDENTIFIED LEAK RATE
__________GPM
(*) Latest IST leakage for 2WR80 (39.0 sccm x 2.6417 E-4 gal/cm3).
NOTE Since the RCDT collects both RCS and Non-RCS inleakage, it is considered unidentified leakage. The RCDT inleakage is recorded for trending purposes only.
___ 5.0 RCDT INLEAKAGE (from Attachment 1, Section 4.0)
__________GPM
___ 6.0 IF UNIDENTIFIED LEAK RATE (Line 4C) is >1.0 GPM, THEN ENTER Tech Spec 3.4.7.2 AND EVALUATE RCS LEAKAGE IAW Attachment 1 of this procedure, AND S2.OP-SO.RC-0004(Q), Identifying and Measuring Leakage.
7.0 MODES 1-4 ACCEPTANCE CRITERIA:
Parameter Technical Specification Leak Rate Test Results SAT UNSAT IDENTIFIED LEAK RATE Line 3 10 GPM 3.4.7.2d UNIDENTIFIED LEAK RATE Line 4C 1 GPM 3.4.7.2b PRIMARY TO SECONDARY LEAK RATE Line 2E 150 GPD through any one SG (ADMIN LIMIT 140 GPD) 3.4.7.2.c
S2.OP-ST.RC-0008(Q)
Salem 2 Page 29 of 40 Rev. 32 ATTACHMENT 3 (Page 3 of 3)
RCS WATER INVENTORY BALANCE CALCULATION SHEET NOTE The following step is required to perform the Inservice Inspection and Testing of 2RH21, RHR TO RWST STOP VALVE, IAW Technical Specification 4.0.5. This requirement is applicable in Modes 1-4, and is performed at least once per 24 months while in Mode 4 OR 5 with a pressurizer bubble established. (M/I S2101428).
___ 8.0 2RH21 LEAK RATE ACCEPTANCE CRITERIA:
[C0611]
Test Required Yes ___ No ___
Parameter Technical Specification Leak Rate Test Results SAT UNSAT UNIDENTIFIED LEAK RATE Line 4C IST PROGRAM <2.0 GPM 4.0.5 Performed with an RHR Pump in service and the respective RH19 valve OPEN.
An RCS Unidentified Leakrate of <2.0 GPM satisfies the 2RH21 seat leakage limit.
Performed By ______________________________________________________ Date ____________
Independent Verification _____________________________________________ Date _____________
S2.OP-ST.RC-0008(Q)
Salem 2 Page 30 of 40 Rev. 32 ATTACHMENT 4 (Page 1 of 5)
MANUAL MASS LEAK RATE CORRECTION 1.0 Mass Leak Rate Correction for Changes in VCT Level
___ 1.1 CALCULATE VCT level change ()L) during the test as follows: (observe +/- sign)
)L = Initial Level - Final Level
)L = __________ % - __________ %
)L = __________ %
___ 1.2 CONVERT the % level change ()L) to volume rate of change ()V) as follows:
)V = [)L X (2.57 ft3/%] / test duration in minutes
)V = [(__________) % X (2.57 ft3/%) / (__________) minutes
)V = __________ ft3/minute
___ 1.3 Using the Saturated Steam: Temperature table, DETERMINE the specific volume of the water corresponding to the VCT average temperature.
vf = __________ ft3/lbm
___ 1.4 CALCULATE the mass leak rate ()M) of water from the VCT as follows:
)M = )V / vf
)M = (__________) ft3/minute / (__________) ft3/lbm
)M = __________ lbm/minute
___ 1.5 RECORD mass leak rate from VCT in Step 4.1.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 31 of 40 Rev. 32 ATTACHMENT 4 (Page 2 of 5)
MANUAL MASS LEAK RATE CORRECTION 2.0 Mass Leak Rate Correction for Changes in RCS Tavg
___ 2.1 RECORD Initial and Final RCS Tavg and Pressurizer Pressure.
Initial RCS Tavg = (__________ °F)
Pressurizer Pressure = (___________ psig)
Final RCS Tavg = (__________ °F)
Pressurizer Pressure = (___________ psig)
___ 2.2 CALCULATE Initial and Final Absolute Pressurizer Pressure as follows:
Absolute Pressurizer Pressure = Pressurizer Pressure + 14.7 psi Initial Absolute Pressurizer Pressure = (__________ psig) + 14.7 psi Initial Absolute Pressurizer Pressure = (__________ psi)
Final Absolute Pressurizer Pressure = (__________ psig) + 14.7 psi Final Absolute Pressurizer Pressure = (__________ psi)
NOTE The specific volume correction is based on a RCS volume of 11211 ft3.
___ 2.3 Using the Subcooled Liquid tables, DETERMINE the specific volume change (v) of the RCS corresponding to Initial and Final RCS Tavg and Absolute Pressurizer Pressure.
v Initial = (__________ ft3/lbm) v Final = (__________ ft3/lbm)
S2.OP-ST.RC-0008(Q)
Salem 2 Page 32 of 40 Rev. 32 ATTACHMENT 4 (Page 3 of 5)
MANUAL MASS LEAK RATE CORRECTION
___ 2.4 CALCULATE the RCS mass change ()Mass) due to the change in specific volume (v).
(observe +/- sign)
)Mass = 11211ft3 X [1/(v Initial) - 1/(v Final)]
)Mass = 11211ft3 X [__________ - __________]
)Mass = 11211ft3 X __________ (lbm/ft3)
)Mass = ___________lbm
___ 2.5 CALCULATE the mass leak rate ()M) due to changes in RCS Tavg as follows:
)M RCS Tavg = )Mass / test duration in minutes
)M RCS Tavg = ___________lbm / __________ minutes
)M RCS Tavg = ___________lbm/minute
___ 2.6 RECORD mass leak rate from the RCS due to changes in RCS Tavg in Step 4.2.
3.0 Mass Leak Rate Correction for Changes in Pressurizer Level
___ 3.1 CALCULATE Pressurizer level change ()L) during the test as follows:
(observe +/- sign)
)L = Initial Level -Final Level
)L = __________ % - __________ %
)L = __________ %
___ 3.2 CONVERT the % level change ()L) to volume rate of change ()V) as follows:
)V = [)L X (16.85 ft3/%] / test duration in minutes
)V = [(__________) % X (16.85 ft3/%) / (__________) minutes
)V = ___________ ft3/minute
S2.OP-ST.RC-0008(Q)
Salem 2 Page 33 of 40 Rev. 32 ATTACHMENT 4 (Page 4 of 5)
MANUAL MASS LEAK RATE CORRECTION
___ 3.3 CALCULATE Average Absolute Pressurizer Pressure as follows:
Average Absolute Pressurizer Pressure = Average Pressurizer Pressure + 14.7 psi Average Absolute Pressurizer Pressure = (__________ psig) + 14.7 psi Average Absolute Pressurizer Pressure = (__________ psi)
___ 3.4 Using the Saturated Steam: Pressure table, DETERMINE the specific volume of the water for saturated liquid and vapor corresponding to the Average Absolute Pressurizer Pressure.
vf = ___________ ft3/lbm vg = ___________ ft3/lbm
___ 3.5 CALCULATE the mass leak rate ()M) of water from the Pressurizer as follows:
)M = )V X (1/vf - 1/vg)
)M = (___________) ft3/minute X
[(1/___________ ft3/lbm) - (1/___________ ft3/lbm)]
)M = (___________) ft3/minute X
[___________lbm/ft3) - (___________lbm/ft3)]
)M = ___________ lbm/minute
___ 3.6 RECORD mass leak rate from Pressurizer in Step 4.3.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 34 of 40 Rev. 32 ATTACHMENT 4 (Page 5 of 5)
MANUAL MASS LEAK RATE CORRECTION 4.0 Calculate Corrected RCS Mass Leak Rate as Follows:
___ 4.1 RECORD the Mass Leak Rate correction for changes in VCT level. (Section 1.0)
________lbm/minute
___ 4.2 RECORD the Mass Leak Rate Correction for Changes in RCS Tavg. (Section 2.0)
________lbm/minute
___ 4.3 RECORD the Mass Leak Rate Correction for Changes in Pressurizer Level. (Section 3.0)
________lbm/minute
___ 4.4 CALCULATE the Corrected Mass Leak Rate (CMLR) as follows:
CMLR = (Step 4.1) + (Step 4.2) + (Step 4.3)
CMLR = (___________) + (___________) + (___________)
CMLR = ___________ lbm/minute
___ 4.5 CALCULATE the Corrected Volume Leak Rate (CVLR) as follows:
CVLR = CMLR X 0.121 gal/lbm CVLR = (___________) lbm/minute X 0.121 gal/lbm CVLR = ___________ gpm
___ 4.6 TRANSFER Corrected Volume Leak Rate (CVLR) to Attachment 3, Step 1.0.
Performed By ________________________________________________________
Date __________
Independent Verification _______________________________________________
Date __________
S2.OP-ST.RC-0008(Q)
Salem 2 Page 35 of 40 Rev. 32 ATTACHMENT 5 (Page 1 of 1)
DESKTOP MASS LEAK RATE CORRECTION 1.0 Desktop CRT Calculation:
NOTE The following information provides guidance on the use a desktop CRT to perform the required Mass Leakrate Calculation. An approved LAN based EXCEL program developed IAW NC.NA-AP.ZZ-0064(Q), Software Quality Assurance (Digital Systems), is being used to automatically determine the specific volume of water based on the algorithms used to create the ASME Steam Tables. Reactor Engineering Department maintains control of the program.
___ 1.1 PERFORM the following:
1.1.1 IF the system desktop RCS LEAKRATE Icon is available, THEN OPEN the RCS LEAKRATE Program.
1.1.2 IF the system desktop RCS LEAKRATE Icon is NOT available, THEN OPEN the RCS LEAKRATE Program utilizing the following link:
K:\\EXCEL5\\EXCEL.EXE K:\\LEAKRATE\\LEAKRATE.XLS 1.1.3 Using the left mouse button, CLICK ON "AUTO FILL WITH TEST DATA" to perform a sample calculation.
1.1.4 IF "PROGRAM POSSIBLY CORRUPTED-RESULTS NOT RELIABLE" appears, THEN PERFORM a Mass Leak Rate Correction IAW Attachment 4.
1.1.5 IF "SAMPLE DATA RESULTS VERIFIED PLEASE CONTINUE" appears, THEN SELECT "CLEAR INPUTS".
1.1.6 ENTER DATA from Attachment 2.
1.1.7 When the data has been entered and the calculation completed, Using the left mouse button, SELECT "PRINT" to print the results AND SIGN the printout.
1.1.8 TRANSFER the Corrected Volume Leak Rate (CVLR) to Attachment 3, Step 1.0.
Performed By ________________________________________________________
Date __________
Independent Verification _______________________________________________
Date __________
S2.OP-ST.RC-0008(Q)
Salem 2 Page 36 of 40 Rev. 32 ATTACHMENT 6 (Page 1 of 2)
REACTOR COOLANT SYSTEM LEAKRATE TRENDING DATA SHEET Reactor Coolant System Leakrate Data (2)
Unidentified RCS Leakrate Comparison Values (1)
Date Identified Leakrate (gpm)
RCDT Inleakage (gpm) 7 Day ULR Rolling Avg (gpm)
Unidentified Leakrate (gpm)
Quarterly Average Leakrate Action Level I Leakrate Action Level II (1)
The Quarterly Average, Action Level I and Action Level II values are developed by Engineering utilizing leak rate historical data and are typically updated on the first of each quarter. In instances where new quarterly values have not been updated, utilize the previous quarters values and inform Engineering.
(2) IF ANY of the following conditions are met, THEN ENSURE a notification to System Engineering is initiated IAW Completion and Review Step 5.4.2:
Any seven (7) day rolling average of Unidentified RCS Leakrate (ULR) exceeds 0.10 gpm, or Any two (2) of three (3) consecutive RCS Unidentified leakrates exceed 0.15 gpm, or Any RCS Unidentified leakrate exceeds 0.30 gpm, or Any unexpected measurable, confirmed rise in RCS Unidentified Leakrate as determined by the SM/CRS, or Any nine (9) consecutive RCS Unidentified Leakrates exceed the Quarterly Average, or Any two (2) of three (3) consecutive RCS Unidentified Leakrates exceed the Action Level I value, or Any RCS Unidentified Leakrate exceeds the Action Level II value.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 37 of 40 Rev. 32 ATTACHMENT 6 (Page 2 of 2)
REACTOR COOLANT SYSTEM LEAKRATE TRENDING DATA SHEET Reactor Coolant System Leakrate Data (2)
Unidentified RCS Leakrate Comparison Values (1)
Date Identified Leakrate (gpm)
RCDT Inleakage (gpm) 7 Day ULR Rolling Avg (gpm)
Unidentified Leakrate (gpm)
Quarterly Average Leakrate Action Level I Leakrate Action Level II (1)
The Quarterly Average, Action Level I and Action Level II values are developed by Engineering utilizing leak rate historical data and are typically updated on the first of each quarter. In instances where new quarterly values have not been updated, utilize the previous quarters values and inform Engineering.
- 2) IF ANY of the following conditions are met, THEN ENSURE a notification to System Engineering is initiated IAW Completion and Review Step 5.4.2:
Any seven (7) day rolling average of Unidentified RCS Leakrate (ULR) exceeds 0.10 gpm, or Any two (2) of three (3) consecutive RCS Unidentified leakrates exceed 0.15 gpm, or Any RCS Unidentified leakrate exceeds 0.30 gpm, or Any unexpected measurable, confirmed rise in RCS Unidentified Leakrate as determined by the SM/CRS, or Any nine (9) consecutive RCS Unidentified Leakrates exceed the Quarterly Average, or Any two (2) of three (3) consecutive RCS Unidentified Leakrates exceed the Action Level I value, or Any RCS Unidentified Leakrate exceeds the Action Level II value.
S2.OP-ST.RC-0008(Q)
Salem 2 Page 38 of 40 Rev. 32 ATTACHMENT 7 (Page 1 of 1)
RCS UNIDENTIFIED LEAKRATE SEVEN (7) DAY ROLLING AVERAGE CALCULATION DATA SHEET NOTE The following guidance should be utilized when calculating the RCS Unidentified Leakrate Seven (7) Day Rolling Average:
[WCAP-16465-NP]
ANY negative RCS Unidentified Leakrate (ULR) values should be set to 0.0 gpm prior to performing the average.
ANY missing RCS Unidentified Leakrate (ULR) values for a specific day should be set to the value recorded for the previous day.
Date (mm/dd/yy)
RCS ULR (gpm)
Seven (7) Day Rolling Average T-6 T-5
+
T-4
+
T-3
+
T-2
+
T-1
+
Current RCS ULR from, Line 4.C
+
Total
=
÷ 7 =
gpm Independent Verification of Calculation Performed By:
S2.OP-ST.RC-0008(Q)
Salem 2 Page 39 of 40 Rev. 32 ATTACHMENT 8 (Page 1 of 2)
COMPLETION SIGN-OFF SHEET
1.0 COMMENTS
(Include procedure/test deficiencies and corrective actions.)
S2.OP-ST.RC-0008(Q)
Salem 2 Page 40 of 40 Rev. 32 ATTACHMENT 8 (Page 2 of 2)
COMPLETION SIGN-OFF SHEET
2.0 SIGNATURES
Print Initials Signature Date INDEPENDENT VERIFICATION:
3.0 SM/CRS FINAL REVIEW AND APPROVAL:
[C0283]
This procedure with Attachments 1-8 is reviewed for completeness and accuracy. All deficiencies, including corrective actions, are clearly recorded in the COMMENTS Section of this attachment.
Technical Specification compliance, procedure compliance, and Acceptance Criteria are evaluated.
Signature:___________________________________________ Date/Time:______________
SM/CRS 4.0 IST IMPLEMENTATION ENGINEER REVIEW:
Test Results are reviewed for acceptability. Forward completed procedure to Operations Staff.
Signature:___________________________________________ Date/Time:_______________
IST Program Engineer