ML20127P756
| ML20127P756 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/20/1985 |
| From: | Miosi A COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 0290K, 290K, NUDOCS 8507020509 | |
| Download: ML20127P756 (96) | |
Text
_
Commonwealth Edi:on One First Nabonal PlagChicago. libnois Addresa Repiy to Post Othee Box 767 Chicago, Ilhnois 60690 June 20, 1985 Mr. Harold R.
Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Braidwood Station Unit 1 Safety Evaluation Report Section 3.9.6 Preservice/ Inservice Testing of Pumps and Valves NRC Docket No. 50-456 Reference (a):
November 4, 1982 T.
R.
Tramm letter to H.
R. Denton
Dear Mr. Denton:
Enclosed is our response to open item section 3.9.6 of the l
Safety Evaluation Report. This provides the program plan for preservice/ inservice nondestructive examination of Braidwood Unit 1 i
ASME code Class 1,2, and 3 safety related pumps and valves.
This will ensu~re<that this equipment will be capable of performing their safety related functions.
This program will be implemented in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1980 Edition through the Winter of 1981 Addenda.
Specific requests for relief are included in the body of this document.
These lists are intended to be complete, however, additional relief may be necessary as determined during subsequent inservice tests.
This program is similar to Byron 1 preservice/ inservice testing program with the only dif ferences being in the component numbers and the fact that Braidwood does not have SX makeup pumps.
l It is requested that this program be compared against Byron 1.
Please address any questions that you or your staff may have concerning this matter to this office.
One signed original and fifteen copies of this letter and the enclosures are provided for your review and approval.
Very truly yours, f
I s
6
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E A.
D. Miosi Nuclear Licensing Administrator bs 0290K
R vicicn 0 O
SECTION 3.0 PRESERVICE/ INSERVICE TESTING PROGRAM PLAN FOR PUMPS O
O 3-1 0629m(041785) 0291A
R:vicien 0 Table of Contents O
3.0 Preservice/ Inservice Testing Program for Pumps Page 3.1 Program Description 3-1 3.2 Program Tables 3-3 l
3.3 Notes 3-5 l
l Note 1 Pump Bearings / Shaft Bearings 3-6 Note 2 Pumps Lubricated by Pumped Fluid 3-6 Note 3 Measurement of discharge pressure on 3-6 PD Pumps 3.4 Relief Requests 3-7 PR-1 Pump Vibration 3-8 PR-2 Pump Bearing Temperatures 3-11 PR-3 Individual Testing of Component Cooling 3-13 Water Pumps O
3-11 0629m(041785) 0291A
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3.1 PROGRAM DESCRIPTION O
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3-1 0629m(041785) 0291A
R::visien 0 Promram Description The Pump Preservice/ Inservice Testing Program for Braidwood Nuclear Power Station Unit 1 is implemented in accordance with the requirements of Subsection IWP of Section II of the ASME Boiler and Pressure Vessel Code, 1980 Edition, through the Winter of 1981 Addenda.
Where these requirements are determined to bo impractical, specific relief is requested.
Additional pump relief requests may be necessary and these will be identified during subsequent inservice tests.
The pumps subject to ISI testing are those pumps which are identified in the Braidwood FSAR au Active, and have an emergency power source. Active pumps are defined as those which are called on to perform a safety function as well as to accomplish and maintain a safe reactor shutdown.
The only exception is the diesel driven auxiliary feedwater pump, (IAF01PB) which is included in the program although it is not supplied by an emergency power source.
Pump reference values shall be determined from the results of a preservice test, which may be run during Preoperational testing, or from the results of the first inservice test run during power operation.
Reference values shall be at points of operation readily duplicated during subsequent inservice testing.
Additional reference values may be necessary and these will be taken in accordance with IWP-3111 and 3112.
In the event a pump must be declared inoperable as a result of inservice testing, limitations on plant operation will be as stated in the Technical Specifications.
Section II of the ASME Boiler and Pressure Vessel Code shall not be construed to supersede the requirements of any Technical Specification.
3-2 0629m(041785) 0291A 1
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0 3.2 s
PROGRAM TABLES
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3-3 0629m(041785) 0291A
Ravicicn 0 Noble Description The following infonnation is included in the sununary tables:
The first four columns include the unique Braidwood Station Equipment Piece Number, the Pump Name, the Code Class, and the P&ID on which the pumps are located.
1333d:
Speed will be messa.:ed by a tachometer or stroboscope for variable speed drives.
Inlet pressure:
Inlet pressure will be measured via permanently installed gauges or other means, provided the equipment accuracy meets the requirements of IWP-4150.
This is to be measured both before pump startup and during the test.
Differential pressure: Differential pressures will be measured using calibrated differential pressure gauges or by recording the difference
-e between calibrated inlet and outlet pressure gauges.
Flow rate: Flow rates will be measured using Permanently installed instrumentation or other means, provided that equipment accuracy meets the requirements of IWP-4150.
Vibration: Vibration measurement shall be made using portable or hand held instruments at locations as marked on the pumps.
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(_/
Bearina Temperature:
Bearing temperature will be measured by permanently installed devices where such devices are present.
Portable measurement devices will be used where temperature wells are provided.
Per IWP-3300, bearing temperatures are required caly once per year.
Braidwood Station takes the data for bearing temperatures once per year during summer testing.
Test Interval:
An inservice test shall be run on each pump nominally every 3 months during normal plant operation, in accordance with IWP-3400.
Lubrication Level:
Lubrication level will be observed through sight glasses for the pumps listed in the program.
Revision:
The current revision of the program is listed.
Table Pame: The table pages are numbered sequentially and show the total number of pages.
O 3-4 0629m(041785) 0291A J
INSERVICE TEST 90GRAN PLAN _
a 1
CLASS 1, 2, & 3 PUMPS BRAIDWOOD NUCLEAR POWER STATION REVISION TABLE PACE O
1 of 3 C
TEST PARAMETERS L
A LUBRI-S INLET DIFF FLOW BEARING TEST CATION PUMP NUMBER PUMP NAME S
P & ID SPEED PRES PRES RATE VIBRATION TEMP INTERVAL LEVEL RMARrst 1AF0lPA Auxiliary feedwater 2
M-37 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump 1AF0lPB Auxiliary feedwater 2
M-37 Yes Yes Yes Yes PR-1 Yes Quarterly Yes pump (Diesel)
OCC0lP Component cooling 3
M-66-3 No Yes Yes PR-3 PR-1 PR-2 Quarterly Yes Note 2 Pump ICC01PA Component cooling 3
M-66-3
.No Yes Yes PR-3 PR-1 PR-2 Quarterly Yes Note 2 Pump ICC0lPB Component cooling 3
M-66-3 No Yes Yes PR-3 PR-1 PR-2 Quarterly Yes Note 2 Pump ICS0lPA Containment spray 2
M-46 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 1 Pump ICS0lPB Containment spray 2
M-46 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 1 Pump ICV 0lPA Centrifugal charging 2 M-64-3 No Yes Yes Yes PR-1 Yes Quarterly Yes Note 2 Pump 1CV0lPB Centrifugal charging 2 M-64-3 No Yes Yes Yes PR-1 Yes Quarterly Yes Note 2 Pump 06292(041785) 0291A
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INSERVICE TEST RAM PL&E
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1 CLAS8 1, 2, & 3 PUMPS BRAIDWOOD BUCLEAR POWER STATION.
REVISION TABLE PAGE O
2 of 3 C
TEST PARAMETERS L
A LUBRI-S INLET DIFF FLOW BEARING TEST CATION PUMP NUMBER PUMP NAME S
P & ID SPEED PRES PRES RATE VIBRATION TEMP INTERVAL LEVEL RENABER 1RH0lPA Residual heat 2
M-62 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 1 removal pump 1RH01PB Residual heat 2
M-62 No Yes Yes Yes PR-1 PR-2 Quarterly No Note 1 removal pump ISIO1PA Safety injection 2
M-61-1 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump ISI0lPB Safety injection 2
M-61-1 No Yes Yes Yes PR-1 Yes Quarterly Yes Pump ISIO1PA Essential service 3
M-42-1 No Yes YeF PR-3 PR-1 Yes Quarterly Yes Note 2 water pump ISI0lPB Essential service 3
M-42-1 No Yes Yes PR-3 PR-1 Yes Quarterly Yes Note 2 water pump 1DOO1PA Diesel oil transfer 3
M-50-1 No Yes No PR-3 PR-1 PR-2 Quarterly No Note 1, 3 Pump ID00lPB Diesel oil transfer 3
M-50-1 No Yes No PR-3 PR-1 PR-2 Quarterly No Note 1, 3 Pump 1D00lPC Diesel oil transfer 3
M-50-1 No Yes No PR-3 PR-1 PR-2 Quarterly No Note 1, 3 Pump 1D001PD Diesel oil transfer 3
M-50-1 No Yes No PR-3 PR-1 PR-2 Quarterly No Note 1,3 Pump OWOOlPA Control room 3
M-118-1 No Yes Yes Yes PR-1 PR-2 Quarterly Yes chilled water 06292(041785) 0291A
15 SERVICE TEST ROGRAM PLAN.,
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CLASS 1. 2, & 3 PUMPS BRAIDWOOD NUCLEAR POWER STATION REVISION TABLE PAGE O
3 of 3 C
TEST PARAMETERS L
A LUBRI-S INLET DIFF FLOW BEARING TEST CATION PUMP NUMBER PUMP NAME S
P & ID SPEED PRES PRES RATE VIPRATION TEMP tuassVAL LEVEL REMARKS OWOO1PB Control room 3
M-118-1 No Yes Yes Yes PR-1 PR-2 Quarterly Yes chilled water 0629a(041785) 0291A
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l 3.3 NOTES J
Q 3-5 0629m(041785) 0291A
Revision 0 NOTE 1 The Diesel Oil Transfer, Residual Heat Removal and Containment Spray pumps cannot be measured for lubrication level. These pumps are lubricated by the fluid pumped and hence have no indication for lubrication level.
NOTE 2 These pumps are in a system which is in continuous operation.
The idle inlet pressure therefore cannot be obtained.
Proper pump operation is assured by continuous pump operation as well as quarterly monitoring of the remaining ISI pump parameters.
NOTE 3 The Diesel 011 Transfer Pumps are positive displacement pumps. The pump differential pressure is not a factor affecting pump performance but rather dependent only on the inlet pressure to the pump. As the pump discharge pressure is constant, and the inlet pressure varies with tank level, the differential pressure is not a valid operational parameter.
For this reason, pump discharge pressure will be used to evaluate pump performance in lieu of using pump differential pressure.
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O 3.4 RELIEF REQUESTS
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Rzvision 0 RELIEF REQUEST NO. PR-1 1.
PUMP NUMBER: All pumps in the program plan.
2.
NUMBER OF ITEMS:
21 pumps.
3.
ASME CODE CLASS:
2&3 4.
ASME CODE. SECTION XI REOUIREMENTS:
In reference to Table IWP-3100-2, " Allowable Ranges of Test Quantities", pump vibration is to be measured in and compared to values given in
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mils displacement.
5.
BASIS FOR RELIEF:
The measurement of pump vibration is required so that developing problems can be detected and repairs initiated prior to a pump becoming inoperable. Measurement of vibration i
only in displacement quantities does not take into account frequency which is also an important factor in determining the severity of the vibration.
6.
ALTERNATE TESTING: The ASME Code minimum standards require measurement of the vibration amplitude in mils (displacement).
Braidwood Station proposes an alternate program of measuring vibration velocity (inches per second) which is more comprehensive than that required by Section II.
This technique is an industry-accepted method which is much more meaningful and sensitive to small changes that are indicative of (q.
developing mechanical problems. Velocity measurements will f:
,~1 provide for a flat frequency response over the frequency range being measured.
A more accurate assessment of the energy being j
u produced in a rotating piece of equipment due to the various j
problems which can develop such as unbalance, misalignment, i
bearing wear, etc., is then possible.
The " General Machinery Vibration Severity Chart" published by IRD Mechanalysis, Inc., (see attached) will be used in place of Table IWP-3100-2 for the Allowable vibration ranges. The
" Alert Range" will be.314 in/sec < V <.628 in/sec.
The required action range will be V >.628 in/sec.
Evaluation of data, to assign equipment to the alert or action ranges, will i
be done within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> (per IWP-3220 of Section II).
This will be done using industry accepted vibration analysis equipment, such as a full spectrum analyzer.
3-7 0'29m(041785) 6 0291A
R*.visicn 0 7.
JUSTIFICATION: Measurement of vibration in mils displacement is not as sensitive as velocity measurements to small changes O-that are indicative of developing mechanical problems.
Therefore, the proposed alternate of measuring vibration amplitude in inches /second provides added assurance of the continued operability of the pumps.
8.
APPLICABLE TIME PERIOD: This relief is requested once per quarter during the first inspection interval.
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R5vielen 0 RELIEF REQUEST NO. PR-2
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1.
PUMP NUMBER:
OCC0lP, ICC0lPA, ICC0lPB, 1CS0lPA, ICS0lPB, 1RH0lPA, 1RH01PB, 1D001PA, 1D00lPB, 1D00lPC, 1D00lPD, OWOOlPA, OWOOlPB 2.
NUMBER OF ITEMS:
13 pumps 3.
ASME CODE CLASS:
2&3 4.
ASME CODE. SECTION XI REQUIREMENTS:
Per IWP-3100, Inservice Test Procedure pump bearing temperatures are required to be measured to detect any change in the mechanical characteristics of a bearing.
IWP-3500(b) requires three successive readings taken at ten minute intervals that do not vary more than 3%.
5.
BASIS FOR RELIEF:
a.
These pumps' bearings are not provided with permanent temperature detectors or thermal wells.
Therefore, gathering data on bearing temperature is Onpractical.
b.
The only temperature measurements possible are from the bearing housing. To detect high bearing tempe ature at the bearing housing would require that the bearings in question be seriously degraded.
c.
Measurement of housing temperature on many of t hese pumps does not provide information on bearing condition or degradation.
For example, the bearings on the Diesel Oil Transfer Pumps (1D00lPA, 1D00lPB, ID001PC, 1DOO1PD) are cooled by the fluid pumped.
Therefore, any heat generated by degraded bearings is
. carried away by the cooling fluid and would not be directly measured at the bearing housing.
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3-10 0629m(041785) 0291A
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R: vision 0 6.
ALTERNATE TESTING: No direct alternate test is proposed for bearing f--
temperatures. However, measurement of hydraulic parameters and vibration readings do provide a more positive method of i
monitoring pump condition and bearing degradation.
7.
JUSTIFICATION:
By measuring pump hydraulic parameters and vibration velocity, (as described in PR-1), pump operability and the trending of mechanical degradation is assured.
- Also, since these parameters (i.e., Hydraulic parameters and vibration) are measured quarterly, the pump mechanical condition will be more accurately determined than would be possible by measuring bearing temperature on a yearly basis.
J 8.
APPLICABLE TIME PERIOD:
This relief is requested once per year, during the first inspection interval.
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3-11 0629m(041785) 0291A
Rsvision 0 RELIEF REQUEST NO. PR-3 1.
PUMP BUMBER:
OCC0lP, ICC0lPA&B, ICV 01PA&B, ISX0lPA&B, ID00lPA-D 2.
NUMBER OF ITEMS:
11 pumps 3.
ASME CODE CLASS:
2&3 4.
ASME CODE. SECTION XI REOUIREMENTS:
Per IWP-4120, the full scale range of each instrument shall be three times the reference value or less.
5.
BASIS FOR RELIEF:
The full scale range of ultrasonic flowmeters,*2 sed to collect Section XI flow data, exceed three times the reference value.
..p 6.
ALTERNATE TESTING:
Ultrasonic flowmeters, with digital readouts and totalizer features will be utilized to obtain Section II flow data.
7.
JUSTIFICATION:
Ultrasonic flowmeters provide an accurate means of measuring flowrate.
They utilize a digital display whose accuracy is independent of the full scale range.
In r" - :
addition, use of the totalizer feature, and
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integrating the flow for five minutes provides an accuracy of less than 3% of the reading. This is well within the requirements of IWP-4110, which refers to an instrument accuracy of 2% of full Jeale.
8.
APPLICABLE TIME PERIOD:
This relief is requested once per quarter, during the first inspection interval.
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3-12 0629m(041785) 0291A
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4.0 PRESERVICE/ INSERVICE TESTING PROGRAM PLAN FOR VALVES s.
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Revision 0 Table of Contents 4.0 Preservice/ Inservice Testing Program Plan for Valves Page 4.1 Program Description 4-1 4.2 Program Tables 4-3 4.3 Notes Note 1 Main Steam Isolation Valves 4-9 Note 2 CV Emergency Boration System Flowpath Valves 4-9 Note 3 Main Feedwater Isolation Valves 4-9 Note 4 CV system letdown and make-up isolation valves 4-9 Note 5 RHR pumps suction isolation valves 4-9 Note 6 Intersystem LOCA check valves 4-9 Note 7 Reactor vessel vent valves 4-10 Note 8 CV, RHR pump discharge check valves 4-10 Note 9 CV, RHR ECCS check valves 4-10 Note 10 Main feedwater waterhammer prevention valves 4-11 Note 11 VQ purge supply and exhaust isolation valves 4-11
' Note 12 AF suction and steam generator check valves 4-11 Note 13 CV high head injection isolation valves 4-11 Note 14 SVAG valves 4-11 Note 15 Containment recirculation sump isolation valves 4-11 4.4 Relief kequests VR-1 Appendix J valves 4-12 VR-2 Containment spray NaOH additive check valves 4-14 VR-3 ECCS injection check valves 4-15 VR-4 Containment spray ring header check valves 4-17 VR-5 Accumulator discharge check valves 4-18 VR-6 SI pump suction check valve 4-19 VR-7 Exemption from timing solenoid operated valves 4-20 VR-8 Component cooling RC pump thermal barrier valves 4-21 VR-9 RC pump seal injection CV check valves 4-22 VR-10 Instrument air containment isolation valves 4-23 VR-ll Position indication test 4-24 VR-12 Trending of fast actuating valves 4-26 4-il
m a.
Rsvision 0 4.1 PROGRAM DESCRIPTION 4-
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4-1 0629m(041785) 0291A
Rsvision 0 Pronram Description
(
The Preservice/ Inservice Testing Program for Class 1, 2, & 3 valves meets the requirements of Subsection IWV of the ASME Section II Code, 1980 Edition, through the Winter of 1981 Addenda.
Where code requirements are determined to be impractical, specific requests for relief are written, referenced, and included with the tables.
Additional valve relief requests may be necessary and these will be identified during subsequent inservice tests.
The tables list all code Class 1, 2 & 3 valves which have been assigned a specific code category as directed by Subsection IWV of Section II.
The tables are organized by system and further identified by code class and code category, using P&ID references.
After installation and prior to service, all valvos identified in this program will be tested as required by Subsection IWV-3100 of Section II of the ASME Code.
These tests will be conducted under conditions similar to those to be experienced during subsequent inservice tests. When a valve or its control system has been teplaced or undergone maintenance that could affect its performance, it will be retested, prior to its return to service, to demonstrate that all performance parameters are within acceptable limits.
In the event a valve must be declared inoperable as a result of inservice testing, limitations on plant operations will be stated in the Technical Specifications.
O)
Section XI of the ASME Boiler and Pressure Vessel Code shall not be S, '
construed to supersede the requirements of the Technical Specifications.
CE) 4-2 0629m(041785) 0291A
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0 4.2 PROGRAM TABLES 1
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4-3 0629m(041785) 0291A
Ravision 0 Table Description
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The following information is included in the summary tables:
A.
SYSTEN The system in which a valve is located is denoted by the abbreviated system identification.
B.
P & ID The P & ID column references the specific P & ID number and sheet number, which the valves are located on.
C.
REVISION The revision corresponds to the current revision of the program.
D.
EAEK The pages are numbered sequentially and show the total number of tables.
I.
VALVE NUMBER The valve number references the unique Braidwood Station
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equipment piece number (EPN).
This specific valve number identifies the unit and system.
F.
G9QER The coordinates reference a specific location on a particular P & ID, via an I-Y coordinate system.
G.
GL&gg The class refers to the ASME class assigned to the specific valve.
l H.
VALVE CJ.TEGORY i
The valve category identifies the valve category defined in subarticle IWV-2200 of ASME Section XI.
I.
VALVE SIZE The valve size lists the nominal pipe size of each valve in inches.
O 4-4 0629m(041785) 0291A
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VALVE TYPE
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The valve type categorizes the valve as to its valve design.
The following abbreviations will be used to identify specific i
valve types:
i Gate GA l
Globe GL Butterfly BTF Check CK Safety Valve SV Power Operated Relief Valve PORV Diaphragm Seated D
Plus P
K.
ACT. TYPE The actuator type identifies the valve actuator. The following abbreviations will be used to designate specific types of valve actuators:
Motor Operated M.O.
Air Operated A.O.
Hydraulic Operated H.O.
Self Actuated S.A.
Manual M
Solenoid Operated S.O.
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EORMAL POSITION Normal position identifies the normal operating position of a
' specific valve. Q for open and C for closed.
M.
STROKE DIRECT.
The stroks' direction identifies the direction the valve se.tuator moves a specific valve stem to place the valve disc in a position to perform its designed safety function. O for open, and E for closed.
This identifies the direction the valve stem will move when tested.
Note:
Exercising of power operated valves will involve stroking the valves to both its open and closed positions.
The valve will only be timed, however, in the direction designated to perform its safety function. Therefore, the program plan specifies only
,the direction in which valves must be stroked to be timed.
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062%s(041785) 0291A
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TEST METHOD
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The test method column identifies specific tests which will be performed on specific valves to fulfill the requirements of Subsection IWV of Section II.
The tests and abbreviations used are as follows:
1.
Seat Leakaxe Test (Lt)
The seat leakage tests will meet the requirements of IWV-3420 for Category A valves.
On these valves, seat leakage is limited to a specific maximum amount in the closed position for fulfillment of their safety function.
2.
Full Stroke Test (St) l Valve exercising tests of r;ategory A and B valves will be performed in accordance with IWV-3410.
The test will include full stroke testing to verify operability in the direction required to fulfill the required safety function.
3.
Check Valve Exercise Test (Ct)
The check valve disc will be exercised to the position required to fulfill its safety function in accordance d
with,IWV-3520.
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4.
Safety Valve Setpoint Check (Rt)
Safety valve setpoints will be verified in accordance with IWV-3510 of ASME Section II.
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5.
Fail Safe Test (Ft)
Valves with fail safe actuators will be tested to verify the valve operator moves the valve stem to the required fail safe position upon loss of actuating power in accordance with IWV-3415.
This will be accomplished during the normal stroking of the valve. Upon stroking a valve out of its fail position, the solenoid operator is de-energized causing air to be vented which, in turn, allows the spring to move the valve to its fail position.
This condition l
simulates loss of actuating power (Electric and/or Air) and hence satisfies the fail test requirements of IWV-3415.
6.
Position Indication Check (IT)
Valves which are identified to require a Position O
Indication Test (IT) will be inspected in accordance with IWV-3300 of ASME Section II.
4-6 0629m(041785) 0291A
Ravision 0 7.
Part-Stroke Test (Xt)
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If only limited operation is practical during plant operation, the valves shall be part-stroke (Xt) exercised during plant operation and full-stroke exercised during j
cold shutdowns, in accordance with IWV-3412 or IWV-3522.
l 0.
MAI STROKE TIME For power operated valves requiring a full stroke test (St),
in order to meet the requirements of IWV-3413, the maximum allowable stroke time is specified in seconds. N/A indicates that time is not a factor affecting valve operability.
P.
TEST NODE Denotes the frequency and plant condition necessary to perform a given test. The following abbreviations are used:
Normal Operation (0P)
Tests designated OP will be done once every 3 months, except in those modes in which the valve is not required to be operable.
Cold Shutdown (CS)
(b Valves that cannot be operated during plant operation shall be full stroke exercised during cold shutdowns. Completion of cold shutdown valve testing is not a prerequisite to plant startup. Valve testings which are not completed during a cold shutdown shall be completed during subsequent cold shutdowns to meet the code specified testing frequency.
In case of frequent cold shutdowns, valve testing need not be performed more often than once during any three-month period.
Reactor Refuelina (RR)
Tests with this designation will be conducted during reactor refueling outages only.
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RELIEF REOUEST
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Relief requests reference a specific request for relief from code requirements. All relief requests are included Lamediately following the presentation tables.
O 4-7 0629m(041785) 0291A
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INSERVICE PROGRAM
(
NWEALTH EDISON ISI CLAS3 1, 2 and 3' VALVES UNIT 1 BRAIDWOOD NU'rm POWER STATION P & ID REVISIOW PAGE SYSTEM CS M-46-1 0
7 of 46 f
k l
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NORMAL STROKE MAI. STROKE TEST TEST RELIEF BRMARER
[
NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST (IN.)
(SEC.)
}
(
1CS007A E-7 2
A 10.0 CA M.O.
C 0
30.0 Lt RR VR-1 St OP I
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1CS007B C-7 2
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{
St OP It RR VR-11 ICS008A E-7 2
AC 10.0 CK S.A.
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1CS008B C-7 2
AC 10.0 CK S.A.
C 0
N/A It/Ct OP/RR VR-4 Lt RR VR-1 ICS011A D-2 2
C 6.0 CK S.A.
C 0
N/A Ct OP ICS011B C-2 2
C 6.0 CK S.A.
C 0
N/A Ct OP 1CS019A C-5 2
B 3.0 CA M.O.
C 0
30.0 St OP It RR VR-11 1CS019B B-5 2
B 3.0 GA M.O.
C 0
30.0 St OP It RR VR-11 1CS020A C-3 2
C 3.0 CK S.A.
C 0
N/A Ct RR VR-2 1CS020B B-2 2
C 3.0 CK S.A.
C 0
N/A Ct RR VR-2 1CS003A E-3 2
C 10.0 CK S.A.
C 0
N/A It/Ct OP/RR VR-4 1CS003B C-3 2
C 10.0 CK S.A.
C 0
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00
INSERVICE T NC PROGRAM
()
WWEALTH EDISOE ISI CLASS 1, 2 and 3 VALVES
'" UNIT 1 BRAIDWOOD NUCLEAR POWER STATION P & ID REVISION PAGE
}.
SYSTEM FW M-36-1 0
15 of 46 l
VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE MAX. STROKE TEST TEST RELIEF REMARKS NUMBER COORD CLASS CATECORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST g
(IN.)
(SEC.)
l IFWOO9A D-5 2
B 16.0 GA H.O.
O C
5.0 St/It CS/0P VR-12 Note 3 j
It RR VR-11 i
IFWO35A E-4 2
B 3.0 CL A.O.
O C
6.0 St OP VR-12 i
r It RR VR-11 I
Ft OP IFWOO9B A-5 2
B 6.0 CA H.O.
O C
5.0 St/It CS/0P VR-12 Note 3 i
It RR VR-11 IFWO35B B-4 2'
B 3.0 CL A.O.
O C
6.0 St OP VR-12 It RR VR-11 Ft OP IFWOO9C E-5 2
B 6.0 CA H.O.
O C
5.0 St/It CS/0P VR-12 Note 3 It RR VR-11 IFWO35C F-4 2
B 3.0 CL A.O.
O C
6.0 St OP VR-12 It RR VR-11 Ft OP 1FWOO9D B-5 2
B 16.0 CA H.O.
O C
5.0 St/It CS/0P VR-12 Note 3 It RR VR-11 1FWO35D C-4 2
B 3.0 CL A.O.
O C
6.0 St OP VR-12 It RR VR-11 Ft OP IFWO43A D-5 2
B 3.0 CL A.O.
C C
6.0 St OP VR-12 Passive It RR VR-11 IFWO43B A-5 2
B 3.0 CL A.O.
C C
6.0 St OP VR-12 Passive It RR VR-11 IFWO43C F-5 2
B 3.0 CL A.O.
C C
6.0 St OP VR-12 Passive It RR VR-11 IFWO43D C-5 2
B 3.0 GL A.O.
C C
6.0 St OP VR-12 Passive It RR VR-11 IFWO39A D-4 2
B 6.0 CA A.O.
O C
6.0 St CS Note 10 It RR VR-11 IFWO39B A-4 2
B 6.0 CA A.O.
O C
6.0 St CS Note 10 It RR VR-11 IFWO39C E-4 2
B 6.0 CA A.O.
O C
6.0 St CS Note 10 It RR VR-11 IFWO39D B-4 2
B 6.0 CA A.O.
O C
6.0 St CS Note 10 It RR VR-11 0629m(041785)
C291A
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h INSERVICE EG P e nau E___ r atTH EDISON ISI CLASS 1, 2 and 3 VALVES UNIT 1 F.
BRAIDWOOD F M *A* POWER STATION P & ID REVISION PAGE
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l C* ST,G MS M-35-1 0
17 of 46 V LVE VALVE VALVE VALVE ACT.
WORMAL STROKE MAX. STROKE TEST TEST RELIEF RE38 Ann NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST
[
(IN.)
(SsC.)
l St/It CS/OP VR-12 Note 1 IMS001B E-5 2
B 32.75 CA H.O.
O C
5.0 It RR VR-11 l
St/It CS/OP VR-12 Note 1 IMS001D B-5 2
B 30.25 GA H.O.
O C
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C 6.0110.0 SV S.A.
C 0
N/A Rt RR I
6 INS 013D C-4 2
C 6.0I10.0 SV S.A.
C 0
N/A Rt RR
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C 6.0110.0 SV S.A.
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C 6.0110.0 SV S.A.
C 0
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C 6.0110.0 SV S.A.
C 0
N/A Rt RR INS 315D C-3 2
C 6.0110.0 SV S.A.
C 0
N/A Rt RR INS 016B E-2 2
C 6.0110.0 SV S.A.
C 0
N/A Rt RR i
INS 016D C-3 2
C 6.0110.0 SV S.A.
C 0
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C 6.0110.0 SV S.A.
C 0
N/A Rt RR INS 017D C-2 2
C 6.0I10.0 SV S.A.
C 0
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B 4.0 CA A.O.
C C
6.0 IT RR VR-11 Passive St OP VR-12 1MS101D B-5 2
B 4.0 CA A.O.
C C
6.0 It RR VR-11 Passive IMS018B F-2 2
C 8.0110.0 PORV M.O.
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l INSERVICE T NC PROGRAM WWEALTH EDISON ISI CLASS 1, 2 d 3 VALVES UNIT 1 BRAIDWOOD NUCLEAR POWER STATION
~ I P & ID REVISION PACE i
SYSTEM MS M-35-2 0
18 of 46 t
VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE MAI. STROKE TEST TEST RELIEF REMARKS NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST
['
(IN.)
(SEC.)
{
f St/It CS/0P VR-12 Note 1 INS 001A C-4 2
B 30.25 GA H.O.
O C
5.0 It RR VR-11 St/It CS/0P VR-12 Note 1 INS 001C E-4 2
B 32.75 CA H.O.
O C
C 6.0110.0 SV S.A.
C 0
N/A Rt RR INS 013C F-4 2
C 6.0I10.0 SV S.A.
C 0
N/A Rt RR IMS014A F-3 2
C 6.0110.0 SV S.A.
C 0
N/A Rt RR INS 014C F-3 2
C 6.0110.0 SV S.A.
C 0
N/A Rt RR IMS315A F-3 2
C 6.0110.0 SV S.A.
C 0
N/A Rt RR INS 015C F-3 2
C 6.0110.0 SV S.A.
C 0
N/A Rt RR IMS016A F-3 2
C 6.0110.0 SV S.A.
C 0
N/A Rt RR IMS016C F-3 2
C 6.0110.0 SV S.A.
C 0
N/A Rt RR IMS017A F-2 2
C 6.0X10.0 SV S.A.
C 0
N/A Rt RR IMS017C F-2 2
C 6.0X10.0 SV S.A.
C 0
N/A Rt RR St OP VR-12 1MS101A C-4 2
B 4.0 CA A.O.
C C
6.0 It RR VR-11 Passive St OP VR-12 IMS101C E-4 2
B 4.0 CA A.O.
C C
6.0 It RR VR-11 Passive IMS018A D-1 2
C 8.0X10.0 PORV M.O.
C 0
20.0 St OP VR-12 Passive It RR VR-11 IMS018C F-1 2
C 8.0X10.0 PORV M.O.
C 0
20.0 St OP VR-12 It RR VR-11 Passive 0629m(041785) 0291A
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h?.ALTH EDISOE ISI CLASS 1. 2 3 VALVES
UNIT 1 BRAIDWOOD WUCf m F0WER STATION l
l P & ID REVISION PAGE i
SYSTEM PS M-68-1 0
22 of 46 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE MAX. STROEE TEST TEST RELIEF RENaars NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST I
(IN.)
(SEC.)
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25 of 46
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NORMAL STROKE MAX. STROKE TEST TEST RELIEF REMARKS l
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TIME METHOD MODE REQUEST (IN.)
(SEC.)
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NWEALTH EDISON ISI CLASS 1, 2 and 3 VALVES i
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i P & ID REVISION PAGE I
SYSTEM SD M-48-5 0
31 of 46 l
t r
VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE MAI. STROKE TEST TEST RELIEF REMARKS t
NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST (IN.)
(SEC.)
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INSERVICE T NG PROGRAM
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t NWEALTH EDISON ISI CLASS 1, 2 d 3 VALVES
' UNIT 1 BRAIDWOOD NUCLEAR POWER STATION i
P & ID REVISION PAGE SYSTEM SD M-48-5 0
32 of 46 VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE MAX. STROKE TEST TEST RELIEF RMARER NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST (IN.)
(SEC.)
l St OP VR-12 l
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CO NWEALTH EDISON ISI CLASS 1, 2 and 3 VALVES
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35 of 46 VALVE
, VALVE VALVE VALVE ACT.
NORMAL STROKE MAX. STROKE TEST TEST RELIEF BRMARER t
NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
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(IN.)
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ISICLASS1,hMGPROGRAM
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INSERVICE T C
MWEALTH EDISON 2 and 3 VALVES UNIT 1 j
BRAIDWOOD NUCLEAR POWER STATIcq I
P & ID REVISION PAGE I
SYSTEM SI M-61-6 0
39 of 46 I
VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE MAI. STROKE TEST TEST RELIEF REMARKS NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST k-(IN.)
(SEC.)
{
St OP j
ISI8880 F-3 2
A 1.0 CL A.O.
C C
10.0 Lt RR VR-1 Passive It RR VR-11 I
{
ISI8956C B-7 1
AC 10.0 CK S.A.
C 0
N/A Lt RR Note 6 Ct CS VR-5 1SI8956D B-4 1
AC 10.0 CK S.A.
C 0
N/A Lt RR Note 6 Ct CS VR-5 ISI8948C B-8 1
AC 10.0 CK S.A.
C 0
N/A Ct CS VR-5 Note 9 Lt RR Note 6 ISI8948D B-5 1
AC 10.0 CK S.A.
C 0
N/A Ct CS VR-5 Note 9 Lt RR Note 6 St OP VR-12 ISI8871 A-3 2
A
.75 CL A.O.
C C
10.0 Lt RR VR-1 Passive It RR VR-11 St OP VR-12 ISI8964 D-3 2
A
.75 CL A.O.
C C
10.0 Lt RR VR-1 Passive It RR VR-11 ISI8968 F-4 2
A 1.0 CK S.A.
C C
N/A Lt RR VR-1 Passive i
0629s(041785) 0291A
h ISI CLASS 1, hMG PROGRAM INSERVICE T COMMONWEALTH EDISON 2 and 3 VALVES UNIT 1 4
BRAIDWOOD NUCLEAR POWER STATION I
l l
P & ID REVISION PAGE SYSTEM SK M-42-3 0
40 of 46 i
i i
VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE MAX. STROKE TEST TEST EELIEF REMARKS j
i NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE R2QURST (IN.)
(SEC.)
f It RR VR-11 I
ISX112A E-5 3
B 12.0 BTF A.O.
O C
6.0 St OP VR-12 Ft OP ISX114A E-3 3
B 12.0 BTF A.O.
O C
6.0 St OP VR-12 It RR VR-11 Ft OP ISK112B C-5 3
B 12.0 BTF A.O.
O C
6.0 St OP VR-12 It RR VR-11 Ft OP ISK114B C-5 3
B 12.0 BTF A.O.
O C
6.0 St OP VR-12 It RR VR-11 Ft OP ISK101A E-3 3
B 1.5 GL S.O.
C 0
N/A St OP VR-7 Ft OP f
ISK173 C-3 3
B 6.0 CA A.O.
C 0
10.0 St OP Ft OP ISK178 A-3 3
B 6.0 GA A.O.
C 0
10.0 St OP Ft OP ISK169A F-8 3
B 10.0 BTF A.O.
C 0
20.0 St OP VR-12 It RR VR-ll Ft OP ISK169B D-8 3
B 10.0 BTF A.O.
C 0
20.0 St OP VR-12 It RR VR-11 Ft OP 0629m(041785) 0291A
f'i
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ITISERVICE ING PROGRAM C
NWEALTH EDISON ISI CLASS 1, and 3 VALVES UNIT 1 BRAIDWOOD NUCLEAR POWER STATION l
t P & ID REVISION PAGE I
SYSTEM VQ M-105-1 0
43 of 46 I
i VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE MAX. STROKE TEST TEST RELIEF REMARKS NUMBER COORD CLASS CATEGORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST (IN.)
(SEC.)
IVQOO1A E-5 2
A 48.0 BTF H.O.
C C
5.0 Lt RR VR-1 Passive i
St CS VR-12 Note 11 It RR VR-11 IVQ001B E-6 2
A 48.0 BTF H.O.
C C
5.0 Lt RR VR-1 Passive i
St CS VR-12 Note 11 It RR VR-11 5
IVQOO2A E-4 2
A 48.0 BTF H.O.
C C
5.0 Lt RR VR-1 Passive St CS VR-12 Note 11 It RR VR-11 IVQ002B E-3 2
A 48.0 BTF H.O.
C C
5.0 Lt RR VR-1 Passive St CS VR-12 Note 11 It RR VR-11 IVQOO3 C-4 2
A 8.0 BTF A.O.
C C
5.0 Lt RR VR-1 Passive St OP VR-12 It RR VR-11 IVQ004A D-5 2
A 8.0 BTF A.O.
C C
5.0 Lt RR VR-1 Passive St OP VR-12 It RR VR-11 IVQ004B D-6 2
A 8.0 BTF A.O.
C C
5.0 Lt RR VR-1 Passive St OP VR-12 It RR VR-11 IVQOOSA E-4 2
A 8.0 BTF A.O.
C C
5.0 Lt RR VR-1 Passive St OP VR-12 It RR VR-11 IVQOO5B E-4 2
A 8.0 BTF A.O.
C C
5.0 Lt RR VR-1 Passive St OP VR-12 It RR VR-11 1hQ005C E-4 2
A 8.0 BTF A.O.
C C
5.0 Lt RR VR-1 Passive St OP VR-12 It RR VR-11 e
l 0629m(041785) 0291A l
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I
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L L
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)
VE LZN 0
0 0
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5 5
5 VS(
YR EO VG LE A
A A
A AT VAC NO S
S I
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A 2
2 2
2 E
LC HTLA D
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7 7
5 5
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INSERVICE NG PROGRAM
~
f COMMONWEALTH EDISJN ISI CLASS 1, 2 and 3 VALVES UNIT 1 BRAIDWOOD NUCLEAR POWER STATION I
(
f P & ID REVISION PAGE SYSTEM WO M-118-5 0
46 of 46 I
VALVE VALVE VALVE VALVE ACT.
NORMAL STROKE MAX. STROKE TEST TEST RELIEF REMARKS i
NUMBER C'00RD CLASS CATECORY SIZE TYPE TYPE POSITION DIRECT.
TIME METHOD MODE REQUEST (IN.)
(SEC.)
l St OP f
1WOOO6A E-5 2
A 10.0 CA M.O.
O C
St OP l'
IWOOO6B B-4 2
A 10.0 GA M.O.
O C
I IWOOO7A E-6 2
A 10.0 CK S.A.
O C
N/A Lt RR VR-1 i
St OP IWOO20A D-5 2
.A 10.0 CA M.O.
O C
50.0 Lt RR VR-1 i
It RR VR-11 i
St OP i
IWOO20B B-4 2
A 10.0 CA M.O.
O C
50.0 Lt RR VR-1 It RR VR-11 IWOOO7B B-4 2
A 10.0 CK S.A.
O C
N/A Lt RR VR-1 St OP 1 WOOS 6A D-6 2
A 10.0 CA M.O.
O C
50.0 Lt RR VR-1 It RR VR-11 St OP IWOOS6B B-3 2
A 10.0 CA M.O.
O C
50.0 Lt RR VR-1 It RR VR-11 06292(042385) 0291A
Ravision 0 O
4.3 NOTES O-t l
O
~
0629m(041785) 0291A
Rsvision 0 l
i j
NOTE 1
()
Closure of the Main 3 team isolation valves, 1MS001A-D, during unit operation would result in reactor trip and safety injection l
actuation.
To avoid this transient, these valves will be partially stroked every three months.
Full stroke testing will be done during l
Mode 4 following, or preceding cold shutdown, per IWV-3412.
NOTE 2 The testing of any emergency boration flowpath valves during unit opration is not practical.
Stroke testing the Boric Acid injection isolation valve, 1CV8104, and check valve, 1CV8442, the RWST to CV pump suction check valve, 1CV8546, the RH to CV pump suction isolation valve, ICV 8804A, or the RWST to CV pump suction isolation valves ICV 112DE, could result in boration of the RCS, resulting in a cooldown transient.
Aligning the system in this configuration, even for a short duration, is therefore unacceptable.
These valves will be stroke tested during cold shutdown, in accordance with IWV-3412.
NOTE 3 These valves are the Main Feedwater isolation valves, IFWOO9A-D, and I
cannot be fully stroked during operation as feedwater would be terminated causing a reactor trip.
They will, however, be partially stroke tested during operation as well as full stroke tested during cold shutdown per the requirements of IWV-3412.
7 NOTE 4 Closure of these letdown and makeup valves, 1CV112B, C, 1CV8149A-C, ICV 8105, ICV 8106, ICV 8152 and ICV 8160 during normal unit operation would cause a loss of charging flow which would result in a reactor coolant inventory transient, and possibly, a subsequent reactor trip.
These valves will be full stroke exercised during cold shutdown as required by IWV-3412.
NOTE 5 The IRH8701A, B and 1RH8702A, B are the isolation boundary between the Residual Heat Removal Punps and the Reactor Coolant System.
Opening one of these valves during unit operation will leave only one valve isolating RHR from the high RCS pressure.
This would place the plant in an undesirable condition.
Therefore, the valves will be full stroke tested during cold shutdown, per IWV-3522.
NOTE 6 The following valves have been identified as intersystem LOCA valves. They form a pressure boundary between the RCS and other l
essential components in order to protect these components from damage. These valves will be leak tested in accordance with the Braidwood Technical Specifications.
4-9 0629m(041785) 0291A
Rsvision 0 Braidwood Unit 1 Intersystem LOCA Valves 1RH8701A,B 1RH8702A,B 1RH8705A,B 1SI8815 ISI8818A-D ISI8905A-D ISI8819A-D ISI8948A-D ISI8841A,B 1SI8949A-D ISI8900A-D ISI8956A-D NOTE 7 The reactor pressure vessel vent valves, 1RC014A-D, cannot be stroked during unit operation as they provide a pressure boundary between the Reactor Coolant system and containment atmosphere.
Failure of one of these valves in the open position would result in leaving only one valve as the high pressure boundary.
These valves will be stroked when the RCS pressure is at a minimum during Cold Shutdown, per IWV-3412.
NOTE 8 The Residual Heat Removal Pump discharge check valves, 1RH8739A,B, and the Centrifugal Charging Pump discharge check valves, 1CV8481A,B, cannot be full stroke exercised during unit operation due to the high RCS pressure.
These check valves will be partial stroke tested, however, on a quarterly basis and full stroke
( ).
exercised during cold shutdown.
This is in accordance with IWV-3522.
NOTE 9 Due to RCS pressure, the check valves li.ted below cannot be full stroke exercised during unit operation:
ISI8818A-D RHR Cold Leg Injection ISI8948A-D RHR/ Accumulator /SI Cold Leg Injection ISI8841A,B RHR Hot Leg Injection ISI8849A.C RHR/SI Hot Leg Injection ISI8958A,B RWST to RHR Sump Suction ISI8815 CV Cold Les Injection ISI8900A-D CV Cold Les Injection These valves will be full stroke exercised during cold shutdown, in.
accordance with IWV-3522.
NOTE 10 The 1FWO39A-D valves cannot be stroke tested during unit operation as closure of these valves would result in termination of the waterhammer prevention feedwater flow.
This would result in undesirable affects on the Steam Generators.
These valves will be full stroke tested during cold shutdown per IWV-3412.
4-10 0629m(041785) 0291A
E R: vision 0 WOTE 11 The Primary Containment Purge Supply and Exhaust Valves, IVQ001A,B, and IVQ002A,B, cannot be stroke timed during unit operation. These 48 inch valves are the only isolation points between the containment atmosphere and the environment.
Stroking these valves at any time other than mode 5 or 6 would be a violation of the Braidwood Technical Specifications.
These valves will be full stroke tested during cold shutdown in accordance with IWV-3412.
E9II._L.
I t The Auxiliary Feedwater check valves, IAF001A,B, 1AF003A,B, 1AF014A-H and 1AF029A,B cannot be full stroke tested during unit
[_
operation, as this would induce potentially damaging thermal stresses in the upper feedwater nozzle piping.
The 1AF001A,B and s
1AF003A,B valves will be partially stroke tested during operation, j
and all valves full stroke tested during cold shutdown. This will be performed per Tech Spec. 4.7.1.2.2 and is in accordance with IWV-3522.
NOTE 13 t
The High Head Injection Isolation Valves,1SI8801A,B cannot be stroke tested during unit operation.
These valves isolate the CV system from the RCS.
Opening them during operation would enable i
charging flow to pass directly into the RCS, bypassing the O;'
regenerative heat exchanger.
The temperature difference of the charging flow and the RCS could result in damaging thermal stresses
,m 9
to the cold les nozzles as well as causing a reactivity change which would, in turn, cause a plant transient.
These valves will be full i
stroke tested during cold shutdown in accordance with IWV-3412.
NOTE 14 The safety injection system SVAG (Spurious Valve Actuation Group) valves cannot be stroke tested during unit operation.
These valves are required by the Technical Specifications, as well as defeating the de-energized SVAG valve principle.
These valves will be stroke tested during cold shutdown when they are not required to be de-energized. This is in accordance with IWV-3412.
NOTE 15 The containment recirculation sump isolation valves, 1SI8811A,B cannot be stroke tested during unit operation, as this would drain a portion of the residual heat removal pump suction, rendering the pump inoperable. This would be a violation of the Technical Specifications, which requires two operable RHR pumps in Mode 1, 2 and 3.
The ISI8811A,B valves will be full stroke tested in cold shutdown, in accordance with 1WV-3412.
O 4-11 0629m(041785) 0291A
R3 vision 0 0
0 44 RELIEF REQUESTS O
)
i O
4-12 0629m(041785) 0291A
Rsvicion 0 VR-1 l'.
Valve Number:
All primary containment isolation valves in this program are listed as Category A:
VALVE #
VALVE #
VALVE #
1)
ICC685 45)
IPS9354A' 89)
IVQOO2A 2) 1CC9413A 46)
IPS9354B 90) 1VWOO2B 3) 1CC9414 47) 1PS9355A 91) 1VQ003 4) 1CC9416 48) 1PS9355B 92)
IVQOO4A 5)
ICC9438 49) 1PS9356A 93) 1VQ004B 6) 1CC9486 50) 1PS9356B 94) 1VQ005A 7)
ICC9518 51)
IPS9357A 95) 1VQ005B 8)
ICC9534 52) 1PS9357B 96) 1VQ005C 9)
ICS007A 53) 1RE9157 97)
IVQOl6 10) 1CS007B 54) 1RE9159A 98) 1VQO17 11) 1CS008A 55) 1RE9159B 99) 1VQO18 12) 1CS008B 56) 1RE9160A 100) 1VQO19 13)
ICV 8100 57) 1RE9160B 101)
IWM190 14)
ICV 8112 58) 1RE9170 102)
IWM191 15)
ICV 8113 59) 1RE1003 103)
IWOOO6A 16)
ICV 8160 60) 1RF026 104)
IWOOO6B L
17)
ICV 8152 61) 1RF027 105)
IWOOO7A O
18) 1FC009 62) 1RY8025 106)
IWOOO7B 19) 1FC010 63) 1RY8026 107)
IWOO20A 20) 1FC011 64) 1RY8028 108)
IWOO20B 21) 1FC012 65) 1RY8033 109)
IWOOS6A 22)
IIA 065 66) 1RY6046 110) 1 WOOS 6B 23)
IIA 066 67) 1RY8047 111)
IPR 002E 24)
IIA 091 68)
ISA032 112)
IPR 002G 25) 10G057A 69)
ISA033 113).
IPR 033A 26) 10G079 70)
ISD002A 114) 1PR033B 27) 10G080 71)
ISD002B 115) 1PR002F 28) 10G081 72)
ISD002C 116)
IPR 002H 29) 10G082 73) 1SD002D 117)
IPR 033C 30) 10G083 74) 1SD002E 118) 1PR033D 31) 10G084 75)
ISD002F 32) 10G085 76)
ISD002G 33) 1PR001A 77)
ISD002H 34) 1PR001B 78)
ISD005A 35) 1PR032 79)
ISD005B 36)
IPR 066 80)
ISD005C 37) 1PS229A 81)
ISD005D 38) 1PS228B 82)
ISI8871 39)
IPS229A 83)
ISI8880 40) 1PS229B 84)
ISI8888 41) 1PS230A 85)
ISI8964 42)
IPS230B 86)
ISI8968 O
I 43)
IPS231A 87) 1VQ001A 44) 1PS231B 88) 1VQ001B 4-13 0629m(041785)
)
ccenn
Rsvisicn 0 2.
Number of Items:
118.
()
3.
ASME Code Catemory:
A.
4.
ASME Code.Section II Requirements:
Seat Leakage Measurement per IWV-3420, 5.
Basis for Relief:
Primary containment isolation valves will be seat leak tested in accordance with 10 CFR 50, Appendix J.
For these valves.
Section II testing requirements are essentially equivalent to those of Appendix J.
6.
Alternate Testina:
Primary containment isolation valves will be seat leak tested in accordance with the Appendix J requirements of 10 CFR 50.
7.
Justification:
No additional information concerning valve leakage would be gained by performing separate tests to both Section II and Appendix J.
Therefore, overall plant safety is not affected.
8.
Aeolicable Time Period:
This relief is requested once per year during the first inspection interval.
O 4-14 0629m(041785)'
0291A
Rsvision 0 VR-2
()
1.
Valve Number:
ICS020A ICS020B 2.
Number of Items:
2 3.
ASME Code Category: C 4.
ASME Code.Section XI Requirements:
Exercise for operability (Ct) of check valves every 3 months, per IWV 3521.
5.
Basis for Relief:
These check valves in the spray additive system cannot be stroked without introducing NaOH into the CS system.
6.
Alternate Testinz:
These valves will be dismantled each refueling outage in order to demonstrate operability.
In addition to this, they will be full flow tested once every five years.
The full flow test will be performed in lieu of dismantling the valves.
7.
Justification:
This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as is safely possible.
8.
Applicable Time Period:
This relief is requested once per quarter during the first inspection interval, i
i C:)
4-15 0629m(041785) 0291A
Rsvision 0 VR-3
()
1.
Valve Number:
ISI8905A-D, 1SI8949B,D 1SI8819A-D ISIS 922A,B 2.
Number of Items:
1,2 1
3.
AglE Code Catemory:
AC & C l
l 4.
ASME Code.Section II Requirements:
Exercise for operability (Ct) of check valves every 3 months, per IWV-3521.
5.
Basis for Relief:
These check valves cannot be full flow tested during operation as the shutoff head of the Safety Injection pump is lower than the reactor coolant system pressure.
Performance of this test with the RCS depressurized, but intact, could lead to inadvertent overpressurization of the system.
The alternate method of protecting against overpressurization by partially draining the RCS to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
s 8-).
6.
Alternative Testinz:
These valves will be full stroke tested during cold shutdowns provided the reactor vessel head is removed. The testing period will be each refueling outage as a minimum, but no more frequently than once per quarter.
7.
Justification:
This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.
8.
Applicable Time Period:
This relief is requested once per quarter during the first inspection interval.
O 4-16 0629m(041785) 0291A
Rsvision 0 VR-4
)
()
1.
Valve Number:
ICS008A, B ICS003A, B 2.
Number of Items:
4 3.
ASME Code.Section II Requirements:
Exercise for operability (Ct) of check valves every 3 months, per IWV-3521.
5.
Basis for Relief:
These valves cannot be full flow tested during unit operation as water from the CS pumps would be discharged through the CS ring headers causing undesirable effects on system components inside containment.
6.
Alternate Testinz:
The ICS008A B valves will be partial stroke tested, using air, on a quarterly basis and full flow tested, or dismantled to demonstrate operability, each refueling outage.
The ICS003A,B valves will be partial stroke tested during the quarterly pump O,,
surveillance and dismantled, to demonstrate operability, each
- refueling outage.
.="
7.
Justification:
Partial stroke testing of the ICS008A,B, check valves using air is an adequate means to demonstrate operability.
Positive verification of disk movement will be accomplished by noting the rush of air through the test connection.
Performance of a partial stroke test during the CS pump quarterly surveillance, on the ICS003A,B check valves will ensure adequate check valve operation.
l l
8.
Anolicable Time Period:
1 This relief is requested once per quarter during the first inspection interval.
O 4-17 0629m(041785) 0291A
Revision 0 VR-S O
1.
va1ve umser: 1SI8esei-o 2.
Number of Items:
4 3.
ASME Code Category:
AC 4.
ASME Code.Section XI Requirements:
Exercise for operability (Ct) of check valves every 3 months, per IW-3521.
5.
Basis for Relief:
The accumulator check valves cannot be tested during unit operation due to the pressure differential between the accumulators (600 psis) and the reactor coolant system (2235 psis). Fu11 stroke exercising of these valves could occur only with a rapid depressurization of the reactor coolant system.
6.
Alternate Testinz:
These valves will be full stroke tested during cold shutdown by providing a surge volume in the pressurizer and " burping" the accumulator discharge isolation valves.
Positive O
verification of va1ve ePeradi11tv wi11 de er notins a chanse in accumulator level.
7.
Justification:
This alternative wil1 adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.
8.
Applicable Timer Period:
This relief is requested once per quarter during the first inspection interval.
O 4-18
{
0629m(041785) 0291A
l Rtvision 0 VR-6
. ()
1.
Valve Number:
1SI8926 1
2.
Number of Items:
1 3.
ASME Code Catemory: C l
l 4.
ASME Code.Section II Requirements:
Exercise for operability (Ct) of check valves every 3 months, I
per IWV-3521.
5.
Basis for Relief:
Full stroke exercising of the Safety Injection pump suction valves cannot be demonstrated during unit operation as the reactor coolant system pressure prevents the pumps from reaching full flow injection conditions.
Performance of this test with the reactor coolant system depressurized, but intact could lead to an inadvertent overpressurization of the system. The alternate method of protecting against overpressurization by partial draining of the reactor coolant system to provide a surge volume is not considered a safe practice due to concerns of maintaining adequate water level above the reactor core.
()-
6.
Alternate Testinz:
The ISI8926 valve will be partial stroke tested during periodic inservice tests with the SI pumps in the recirculation mode.
Full Stroke exercising for this valve will be done at cold shutdown, providing the reactor vessel head is removed.
This testing frequency will be each i
refueling outage as a minimum, but no more frequently than once per quarter.
7.
Justification:
1 l
This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, but testing the valves as often as safely possible.
8.
Applicable Time Period:
This relief is requested once per quarter during the first inspection interval.
O 4-19 0629m(041785) 0291A
R: vision 0 l
1 VR-7
()
1.
Valve Number:
IPS228A, B 1RC014A-D 1PS229A, B ISIl01A 1PS230A, B 2.
Number of Items:
11 3.
ASME code Catemory: A&B 4.
ASME Code Section Requirements:
Stroke timing (St) of power operated valves per IWV-3411.
5.
Basis for Relief:
Stroke timing of Solenoid Operated valves is impractical due to the fast actuation of these valves.
6.
Alternate Testinz:
The PS and SI valves will be demonstrated operable by l
quarterly full stroke testin5 and fail testing.
The RC valves will be tested in accordance with Note 7.
7.
Justification:
~()
Proper valve operation will be demonstrated by verifying that the valves stroke to their required positions.
l 8.
Aeolicable Time Period:
This relief is requested once per quarter during the first inspection interval.
t O
4-20 0629m(041785) 0291A
R:visicn 0 i
VR-8
()
1.
Valve Number:
ICC685 1CC9438 1CC9413A, B ICC9414 1CC9416 2.
Number of Items:
6 3.
ASMI Code Cateaory: A 4.
ASME Code.Section II Requirements:
Exercise for operability (St) of Category A and B valves every 3 months, per IW-3411.
5.
Basis for Relief:
- L Component cooling water flow to the reactor coolant pumps is required at all times while the pumps are in operation and for L,
an extended period of time while in cold shutdown. Failure of one of these valves in a closed position during an exercise test would result in a loss of cooling flow to the pumps and
+
eventual pump damage and/or trip.
6.
Alternate Testina:
()'
These valves will be exercised during cold shutdown, provided Ti all of the reactor coolant pumps are not in operation. This testing period will be each refueling outage as a minimum, but no more frequently than once per quarter.
j 7.
Justification:
This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely i
possible.
8.
Aeolicable Time Period:
This relief is requested once per quarter during the first inspection interval.
p
- (:)
4-21 0629m(041785) 0291A
Rtvision 0 VR-9 1.
Valve Number:
ICV 8100 1CV8112 2.
Number of Items:
2 3.
ASME Code Catezory: A 4.
ASME Code.Section II Requirements:
Exercise for operability (St) of Category A & B valves every 3 months per IWV-3411.
5.
Basis for Relief:
These valves cannot be tested during unit operation as seal water flow to the reactor coolant pumps is required at all times while the pumps are in operation.
Failure of one of these valves in the closed position during an exercise test would result in seal water flow being diverted to the PRT by lifting a relief valve upstream of the isolation valves.
6.
Alternate Testinz:
These valves will be exercise tested during cold shutdown, providing all reactor coolant pumps are not in operation.
This testing period will be each refueling outage as a minimum, but no more frequently than once per quarter.
7.
Justification:
This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.
8.
Aeolicable Time Period:
This relief is requested once per quarter during the first inspection interval.
4
?
t O
4-22 0629m(041785) 0291A
Rsvision 0 VR-10
/~h
(_/
1.
Valve Number:
IIA 066 j
IIA 065 2.
Number of Items:
2 3.
ASME Code Catemory:
A l
4.
ASME Code.Section XI Requirements:
Exercise for operability (St and Ft) of category A and B valves every 3 months per IWV-3411.
5.
Basis for Relief:
stroke testing of these valves during plant operation would isolate the air operated instruments and valves inside the containment building.
6.
Alternate Testinz:
These valves will be exercised during cold shutdown, providing that all necessary equipment required for cold shutdown operations would not be affected.
This~ testing period will be each refueling outage as a minimum, but no more frequently than once per quarter.
1 7.
Justification:
Stroke exercising of these valves would be impractical because if these valves failed in the close position during unit g
\\
operation, instrumentation would not function properly and valves would stroke to their failure position, causing the x
loss of support equipment and possibly a reactor trip.
This alternative will adequately maintain the system in a state of operational readiness, while not sacrificing the safety of the plant, by testing the valves as often as safely possible.
8.
Acolicable Time period:
This relief is requested once per quarter during the first inspection interval.
a O~
4-23 0629m(041785) 0291A
~ ~ ~
~~
... - -.~ ~..... - -..--,,.
e R; vision 0 VR-11 0
1.
Valve Number:
All valves subject to Travel / Position Indication Test 2.
Number of Itemg.;. 183 3.
ASME Code Cateaory: A&B 4.
ASME Code.Section II Requirements:
Observation of remote position indicators once every 2 years to verify that the valve operation is accurately indicated per IWV-3300.
5.
Basis for Relief:
Position indication checks are required once every two years.
Historically, plants have been on a one year refueling cycle and thus, performed this test every other refueling outage.
Therefore, the intent of the code appears to be that the test be executed every other refueling outage. Braidwood Station, however, is on an 18 month refueling cycle. Executing a position indication test by either coming down in power or every refueling outage is not practical. Increaring the frequency of testing, in radiation areas, would increase
()
personnel exposure by as much as 25% over plants on a two year testing cycle.
6.
Alternate Testina:
Position / Travel indication examinations will be performed on a frequency of approximately once every 3 years, or once every other refueling outage. All active power operated valves listed in the ISI Valve Program will be stroke timed. For valves with remote indication, timing is done remotely.
This time is then recorded in a procedure which trends the stroke time of each valve. If either the maximum stroke time for the valve or the trending criteria is exceeded, a local stroke timing of the valve will be initiated.
If the local time varies by more than 20% or 1 second, whicever is greater, from the remote time, the limit switches will be adjusted accordingly.
O 4-24 0629m(041785) 0291A
. ~ ~,
~. -.. ~,.....
Ravision O s
7.
Justification:
O Position indication tests executed on a frequency of once every 3 years, along with a case by case investigation of Position / Travel Indication discrepancies, will adequately i
maintain the system in a state of operational readiness.
In addition to this, radiation exposure levels for personnel will be greatly reduced.
8.
Apolicable Time Period:
I This relief is requested every other refueling outage during the first inspection interval.
4 O
O 4-25 0629m(041785) 0291A
.~ s _.. _.,,. -..... ~. -- - -. -
R vision 0 VR-12 1.
Valve number: Valves that normally stroke in 5 seconds or less:
Valve #
Valve #
Valve #
Valve #
ICC9437A,B 1PR066 1RY455A ISI8880 1CV8149A-C 1PS9354A,B 1RY456 ISI8888 1CV8152 1PS9355A B 1RY8025 ISI8964 1CV8160 1PS9356A,B 1RY8026 ISX112A,B 1FWOO9A-D 1PS9357A,B 1RY8028 ISX114A,B 1FWO35A-D 1RE9157 1RY8033 ISX169A,B 1FWO43A-D 1RE9159A,B ISA032 IVQ001A,B LEB001A-D 1RE9160A,B 1SA033 1VQ002A.B 1M8018A-D 1RE9170 ISD002A-H IVQOO3 1MB101A-D 1RF026 ISD005A-D IVQOO4A,B 1PR001A,B 1RF027 ISI8871 1VQ005A-C 2.
Bumber of Items: 90 3.
ASHI Code Catesorv: A&B 4.
ASME Code.Section II Requirements:
+
Verification, by trending of power operated valve times, that an increase in stroke time of 50% or more, from the previous test, does not occur, per IWV-3417.
O 5.
Basis for Religf,:
Minor timing inaccuracies, with small stroke times can lead to substantial increases (percent wise) in stroke times. For 1-example, a valve with a stroke time of 1 second in an initial test, and 1.6 seconds in the subsequent test, has experienced an apparent 60% increase in stroke time.
If the accypacy requirements of IWV-3414(b) are utilized, it could be asgued that stroke times between 2 and 3 seconds could constitute as much as a 50% increase in stroke time when in fact, only a 0.2 second increase occurred. For instance, if the initial time was 2.4 seconds, (measured to the nearest second is 2.0 seconds) and if the next time is 2.6 seconds, (measured to the nearest second is 3.0 seconds) the percent is 50%.
6.
Alternate Testina:
Fast-acting valves will be defined as those valves that normally stroke in 5 seconds or less. These valves will have a maximum stroke time limit increase of 100%, at which time, the test frequency shall be increased to monthly, until corrective action is taken. No trending of stroke times will be required.
Additionally, valves that normally stroke in 1 second or less will have a maximum stroke time limit of two seconds with no
()
stroke time trending required.
4-26 0629m(041785) 0291A
u___._._.__.-
R visicn 0 7.
Justification For short stroke times, the trending requirements are too stringent for the accuracies specified in the code. The alternative specified will adequately maintain the system in a state of opersticnal readiness, while not sacrificing the safety of the plant.
8.
Aeolicable Time Period:
This relief is requested once per quarter, during the firs't inspection interval.
O e
e W
-)
4-27 0629m(041785) 0291A