ML20154P801
| ML20154P801 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 05/27/1988 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20154P787 | List: |
| References | |
| PROC-880527, NUDOCS 8806060082 | |
| Download: ML20154P801 (162) | |
Text
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IO INSERVICE PUMP AND VALVE TEST PROGRAM l
i FOR i
1 NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE UNIT 1
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- O I
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- l PREPARED BY
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1 NORTHEAST NUCLEAR ENERGY COMPANY l
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8806060082 880527 PDR ADOCK 05000245 P
DCD l
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TABLE OF CONTENTS REFERENCE DRAWINGS Page 1 PUMP INSERVICE TESTING 1-5 RANGES OF TEST PARAMETERS 1
VIBRATION ACCEPTANCE CRITERIA 1
INSERVICE PUMP TESTING REQUIREMENTS TABLES 1-3 PUMP RELIEF REQUESTS R-1 to 24 VALVE INSERVICE TESTING 1-9 LEGEND FOR VALVE TESTING 1
INSERVICE TEST VALVE LIST Feedwater Coolant Injection 1-5 Control Rod Drive Hydraulic 6-10 Low Pressure Coolant Injection 11-16 Core Spray 17-19 Standby Liquid Control 20
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Main Stean 21-24 Isolation Condenser 25-26 Service Water 27 Emergency Service Water 28 Shutdown Cooling 29-30 Fuel Pool Cooling 31 Reactor Building Closed Coolitty Water 32 Reactor Recirculation 33 Turbine Building Secondary Closed Cooiing Water 34 Reactor Water Clean-Up 35-36 Atmospheric Control 37-40 Standby Gas Treatment 41-42 Drywell Sump Isolation 43 Reactor Vessel Head Spray 43A Drywell Nitrogen Supply 44-45 Hydrogen and Oxygen Analyzer 46-47 Reactor Coolant Sample 48 Post Accident Sample 49 Transversing In-core Probe 50-51 Diesel Generator Air Start 52 Fuel Oil Forwarding 53 VALVE RELIEF REQUESTS V-1 to V-49 APPENDIX A - RECORD OF CHANGES H
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REFERENCE DRAWINGS FEEDWATER COOLANT INJECTION 25202-26013 CONTROL ROD DRIVE HYDRAULIC 25202-26024 LOW PRESSURE COOLANT INJECTION 25202-26008 CORE SPRAY 25202-26008 1
STANDBY LIQUID CONTROL 25202-26022 MAIN STEAM 25202-26317 ISOLATION CONDENSER 25202-26317 SERVICE WATER 25202-26015 EMERGENCY SERVICE WATER 25202-26008 f
SHUTDOWN COOLING 25202-26023 FUEL POOL COOLING 25202-26007 REACTOR BUILDING CLOSED COOLING 25202-26006 WATER
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REACTOR RECIRCULATION 25202-26027 TURBINE BUILDING SECONDARY CLOSED 25202-26011 COOLING WATER REACTOR WATER CLEAN-UP 25202-26025 ATMOSPHFRIC CONTROL 25202-26009 STANDBY GAS TREATMENT 25202-26034 DRYWELL SUMP ISOLATION 25202-26010 REACTOR VESSEL HEAD SPRAY 25202-26030 DRYWELL NITROGEN SUPPLY 25202-26009 HYDROGEN AND OXYGEN ANALYZER 25202-26009 REACTOR COOLANT SAMPLE 25202-26027 POST ACCIDENT SAMPLE 25202-26036 TRANSVERSING IN-CORE PROBE 25202-26009 DIESEL GENERATOR AIR START 25202-26037 FUEL OIL FORWARDING 25202-26028 1
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O PUMP INSERVICE TESTING O
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PUMP _ INSERVICE TESTING 1.
SCOPE This program establishes the requirements for inservice testing of certain safety related centrifugal and positive displacement pumps at Millstone Nuclear Power Station Unit 1.
The pumps included are those provided with an emergency power supply and are re@ ired in shutting down a reactor to the cold shutdown condition, maintaining the cold shutdown con-dition, or in mitigating the consequences of an accident.
Drivers, except where the pump and driver form an integral unit and the pump bearings are in the driver are excluded from this test program. Pumps that are supplied with emergency powel solely for operating convenience are also excluded from testing.
2.
DEFINITIONS A. Inservice test - A test to determine the operational readiness of a pump.
B. Instrument accuracy - The allowable inaccuracy of an instrument loop based on the square root of the sum of the
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squares of the inaccuracies of each instrument or compon-
's' ent in the loop.
C. Instrument loop - Two or more instruments or components le output (e.g, a vib-workingtogethertoprovideasin$gnalconditioningand ration probe and its associated s readout devices).
D. Operational readiness - The ability of a pump to perform its intended function.
E. Reference values - One or more values of test parameters measured or determined when the equipment is known to be operating acceptably.
F. Routine servicing - The performance of planned, preventive maintenance (e.g., re lacing or adjusting valves in recip-rocating pumps ch flushing the cooling system, adjusting pack 1ng,ang ng oil,ad ing packing rings or mechanical seal maintenance or replacment).
G. System resistance - The hydraulic resistance to flow in a system.
3.
TEST REQUIREMENTS Inservice testing shall be performed in accordance with this program when the pumps are required to be operable in accord-7_s
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ance with the test frequencies specified in the table of Pump a
Test Requirements. Relief requests are specified where test-ing cannot be performed in accordance with this program.
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The hydraulic and mechanical condition of a pump relative to a previous condition can be determined by attempting to I
duplicate by test a set of reference values. Deviations detected are symptoms of changes and, depending upon the degree of deviation, indicate the need for further tests or corrective action.
l RefGrence values shall be determined from the results of pre-service testing for new components or from the results of inservice tests when the pump is known to be operating satis-factorily. Reference values shall be at points of operation readily duplicated during subsequent tests. All subsequent test results shall be compared to these initial reference values.
l When a reference value or set of values may have been affected by repair replacement or routine servicing of a pump (e.g., replaclng or adjusting valves in reciprocating pumps, changing oil, flushing the cooling system, adj ustir.g packing, adding packing rings or mechanical seal maintenance or replacement) a new reference value or set of valuea shall be determined or the previous values reconfirmed by an inservice test prior to declaring the pump operable.
Os Deviations between the previous and the new set of reference values shall be identified, and verification that the new values represent acceptable operation, shall be placed in the record of tests.
1 If it is necessary or desirable to establich an additional i
set of reference values, an inservice test shall be run at l
the conditions of an existing set of reference values and the f
test results analyzed. If operation is acceptable, a second test run at the new reference conditions shall follow as soon as practical. The results of this test shall establish the additional set of reference values. Whenever an additional set of reference values is established, the reasons for so doing shall be justified and documented in the test records.
4.
INSTRUMENTATION Instrumentation accuracy shall be within the percent accuracy as given below:
Pressure
+2%
Flow rate
+2 %
Vibration
+5%
Differential Pressure
+2 %
Speed
+2 %
1 1
The full-scale range of each analog instrument shall not be greater than three times the reference value. Digital instru-
ments shall not exceed 70% of the calibrated range of the instrument. Vibration instruments are excluded from the range requirements of the above.
All pumps in the inservice test program are constant speed driven pumps.
All instruments are to be calibrated in accordance with the Millstone Quality Assurance Program.
The fre@ency response of the vibration measuring instruments and their readout system shall be from one-third minimum pump shaft speed to at least 1000 Hertz. The vibration measure-ments are to be broadband (unfiltered) peak velocity.
Vibration measurements shall be acquired on safety related pumps on the following locations:
A.
On centrifugal pumps, measurements shall be taken on each accessible pump bearing on a location that provides the highest vibration amplitude. Measure-ments shall also be taken on each accessible pump thrust bearing in the axial direction. (See Relief Request R-1) measurements shall be On vertical line shaft pumps,ing housing in three
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B.
taken on the upper motor bear
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orthogonal directions, one of which is the axial position.
C.
On reciprocating pumps, the location shall be on the bearing housing of the crankshaft, approximately perpendicular to both the crankshaft and the line of plunger travel.
5.
TEST FREQUENCY An inservice test shall be run on each pump nominally every three months when the pump is required to be operable, as given in the Table of Pump Test Requirements. Relief requests are specified when quarterly testing is not possible or practical.
For a pump in a system declared inoperable, the test schedule need not be followed. Within 3 months prior to placing the system in an operable status, the pump shall be tested and the test schedule followed in accordance with the Pump Test Requirements Table.
i Pumps which can only be tested during plant operation shall be tested within one week following return of the plant to normal power operation.
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6.
TEST REQUIREMENTS An inservice test shall be conducted with the pump operating at the specified test reference conditions as specified in component specific surveillance test procedures. The test arameters given in the Pump Test Requirements Table shall e determined and recorded.
The resistance of the system shall be varied until the flow rate e@als the reference value. The pressure shall then be Alter-determined and compared to its reference value.
natively, the flow rate can be varied until the pressuredeter-epals the reference value and the flow rate shall be mined and compared to the reference flow rate value.
Where system resistance cannot be varied, flow rate and pres-sure shall be determined and compared to their respective reference values. Relief requests are listed in the Pump Test Requirements Tables where this requirement cannot be met due to system design and the lack of instrumentation.
After pump conditions are stable as the system permits, each pump shall be run at least two minutes. At the end of this time at least one measurement of each of the test quantities required shall be made and recorded.
Test measurements shall be determined and compared with corresponding reference values. All deviations from the reference values shall be compared with the Ranges of Test Parameters Table and Vibration Acceptance Criteria Table.
7.
ACCEPTANCE CRITERIA If the test results fall within the Alert Range, the test fre@ency shall be doubled until the cause of the deviation is determined and the condition corrected.
i If deviations fall within the Required Action Range, the pump shall be declared inoperable until the deviation has been determined and the condition corrected.
When a test shows deviations outside of the Acceptable Ranges due to erroneous instrument response, the instrumentation may j
be recalibrated and the inservice test rerun.
All test data shall be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after com-pletion of an inservice test.
8.
RECORDS AND REPORTS The following records shall be maintained for each pump in f
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the inservice test program:
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A. The Manufacturer and the Manufacturer's model and serial number or other identification.
B. A copy or summary of the Manufacturer's acceptance test report if available.
A copy of the pump Manufacturer's operating limits.
C.
Test Plan Records and procedures shall include the following:
A. The hydraulic circuit to be used.
B. The location and type of measurement for the required test parameters.
C. The reference values.
D. The method of determining reference values which are not directly measured by instrumentation.
A record of each test shall be maintained and shall include the following:
A.
Pump identification.
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B. Date of testing.
C. Reason for testing (e.g., maintenance, routine IST, establishing reference valuas).
D. Values of measured parameters.
E. Identification of instruments used.
F. Comparisons with allowable ranges of test values and analysis of deviations.
G. Requirement for corrective action.
l H. Evaluation and justification for changes to reference values.
I. Signature of the person or persons responsible for conducting and analyzing the test.
9.
RECORD OF CORRECTIVE ACTION A pump Record of Corrective Action shall be maintained which will include a summary of corrections made and the subsequent inservice tests and confirmation of operational adequacy and the signature of the individual responsible for corrective action and verification of results.
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RANGES OF TEST PARAMETERS v
i REQUIRED TEST PARAMETER ACCEPTABLE RANGE ALERT RANGE ACTION RANGE LOW HIGH P
Positive t
.93 to 1.10 Pr
.90 to <.93 Pr
<.90 Pr
>1.10 Pr Displacement Pumps
. 10 DPr
.93 to <.95 DPr
<.93 DPr >1.10 DPr DP Verticle
.95 Line Shaft Pumps Q
Positive
.95 to 1.10 Qr
.93 to <.95 Qr
<.93 Qr
>1.10 Qr Displacement Pumps and Vertical Line Shaft Pumps
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<.90 DPr >1.10 DPr DP Centrifugal
.90 to 1.10 DPr Pumps
<.90 Qr
>1.10 Qr Q
Centrifugal
.90 to 1.10 Qr Pumps DEFINITIONS:
NOTE: The subscript r denotes reference value.
s P = Pump Discharge Pressure.
DP = Pump Differential Pressure.
Q = Pump Flow rate.
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s s
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VIBRAT}ON ACCEPTANCE CRITI:RIA w,_
w PUpGr 2
-' EMJMP TEST ACCEPTABLE ALERT REQUIRE 9 TYPE
SPEED PARAMETER RANGE RANGE ACTION RANGE
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s
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Centrifugal and
> 600 rpm Peak velocity
< 2.5 Vr
> 2.5 Vr to 6 Vr
> 6 Vr Vertical Line but not > 0.325 in/sec but not > 0.7 in/sec f
Shaft i
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-er
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l Reciprocating Peak Velocity
< 2.5 Vr
> 2.5 Vr to 6 Vr
> 6 Vr
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__ 7 s...
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NOTES:
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- 1. Vr = Reference velc, city measurement (initial measurement after installation or rework) measured in inches _per second (peak) from 5 Hz to 1000 Hz.
All cent;ifucal pumps _in the Inservice Test Program operate at speeds greater than 600 rpm
- 2. and since Peak Velocity measurements are used in lieu of Mils Displacement, Figure 6100-1 of l'
OM-6 does not apply.
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MP-1 INSERVICE PUMP TESTING REQUIREMENT 5 SC HC DP F
V F
R AL 0U IR L
I R
B E
R Q
A
~
TS RE ES A
0 R
PUMP Y
N RU
-t T
E K
T ER I
N S
NE O
C T
N Y
I A
l CONDENSATE (FWCI)
M2-6A 2
X R-4 R-2 X
Q R-3 M2-6B 2
X R-4 R-2 X
Q R-3 M2-6C
- 2 X
R-4 R-2 X
Q R-3 CONDENSATE BOOSTER (FWCI)
M2-7A 2
X X
R-5 R-1 Q
R-6 M2-7B 2
X X
R-5 R-1 Q
R-6 M2-7C
- 2 X
X R-5 R-1 Q
M2-10A 2
X X
X R-1 R-8 R-7 M2-10B 2
X X
X R-1 R-8 R-7 M2-10C
- 2 X
X X
R-1 R-8 R-7 EMERGENCY CONDENSATE TRANSFER (FWCI)
P?-28 2
X X
X R-1 Q
R-9 LOW PRESSURE COOLANT INJECTION (LPCI)
M8-75A 2
X X
X X
Q M8-75B 2
X X
X X
Q l
M8-75C 2
X X
X X
Q M8-75D 2
X X
X X
Q CORE SPRAY M8-74A 2
X X
X X
Q M8-74B 2
X X
X X
Q PAGE 1 0F 3
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O O
O MP-1 INSERVICE PUMP TESTING REQUIREMENTS SC MC DP F
V TF R
AL 00 IR L
I ER E
B SE M
R TQ A
TS RE ES A
U R
Y N
RU T
E K
PUMPf T
ER
-t I
N S
NE O
C T
H Y
I A
L EMERGENCY SERVICE WATER M4-13A 3
X R-10 X
X Q
M4-13B 3
X R-10 X
X Q
M4-13C 3
X R-10 X
X Q
M4-13D 3
X R-10 X
X Q
SERVICE WATER M4-7A
- 3 X
R-10 R-11 X
Q R-12 M4-7B
- 3 X
R-10 R-11 X
Q R-12 M4-7C 3
X R-10 R-11 X
Q R-12 M4-7D 3
X R-10 R-11 X
Q R-12 STANDBY LIQUID CONTROL (SBLC) 1102A 2
R-13 X
X Q
1102B 2
R-13 X
X 0
REAGTOR BUILDING CLOSED COOLING WATER M4-10A 3
X X
R-15 R-1 Q
R-14 t
M4-10B 3
X X
R-15 R-1 Q
R-14 SECONDARY CLOSED COOLING WATER (SCCW)
M4-15A 3
X R-16 R-1 Q
R-17 M4 -15B 3
X R-16 R-1 Q
R-17 SHUTDOWN C00LIN (SDC) 1002A 2
X R-18 R-1 R-19 1002B 2
X R-18 R-1 R-19 PAGE 2 0F 3
O O
O MP-1 INSERVICE PUMP TESTING REQUIREMENTS il SC MC DP F
V TF R
AL 00 IR L
I ER E
B SE M
R TQ A
TS RE ES A
U R
- PUMP, Y
N RU T
E K
T ER s
I N
S NE O
C T
N Y
I A
L L ROD DRIVE (CRD) 2 X
X X
R-1 R-20 302-3B 2
X X
X R-1 R-20 FUEL POOL COOLING (FPC)
M4-11A 3
X X
R-1 Q
M4-11B 3
X X
R-1 Q
E FUEL OIL TRANSFER X
Q M8-47B B31.1 R-21 R-22 X
Q GAS TURBINE GENERATOR FUEL FORWARDING M8-8SA B31.1 R-21 R-23 X
Q M8-85B B31.1 R-21 R-23 X
Q REACTOR FEEDWATER PUMP SEAL INJECTION M2-17A 2
X R-24 R-1 Q
M2-17B 2
X R-24 R-1 Q
M2-17C 2
X R-24 R-1 Q
REMARKS:
X = PARAMETERS MEASURED, RECORDED, AND TRENDED.
R = RELIEF REQUEST.
Q = INSERVICE TESTING PERFORMED QUARTERLY.
- = PUMPS ARE NOT SAFETY RELATED. INSERVICE TESTING IS PERFORMED FOR BALANCE OF PLANT RELIABILITY.
PAGE 3 0F 3
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i PUMP RELIEF REQUEST 5 O
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l PUMP RELIEF REQUEST NUMBER:
R-1 COMPONENTS:
Condensate Booster, Reactor Feedwater, Emer-gency Condensate Transfer, Reactor Building Secondary Closed Cooling Closed Cooling Waterg Water, Shutdown Cooling, Control Rod Drive, Fuel Pool Cooling Water, and Reactor Feedwater Pump Seal Injection Pumps.
TEST REQUIREMENT:
Vibration Measurement Locations. On cen-trifugal pumps, measurements shall be taken in a plane approximately perpendicular to the rotating shaft in two orthogonal directions on each accessible pump bearing housing.
Measurement also shall be taken in the axial direction on each accessible pump thrust bearing housing.
BASIS FOR RELIEF:
Relief is requested from acquiring vibration measurements in two orthogonal directions on each accessible bearing housing on the centri-fugal pumps listed above.
The vibration instrumentation used at Mill-stone Unit i during inservice testing is not
('i the simple hand held velocity probe that is
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most commonly used for acquiring peak velocity measurements. Since 1977 when vibration measurments were first required for inservice testing, the Fast Fourier Velocity Spectrum Analysis method of acquiring vibration sig-natures is used in lieu of acquiring Mils Displacement (peak to peak).
Vibration measurements consist of overall velocity in inches per second (peak) and a vibration signature that consists of vibration amplitude in units of inches per second peak on a semi-logarithmic scale versus frequency in hertz.
Vibration measurements are made with an accelerometer mounted at a reference location generally on a bearing housing or its structural support, depending upon the pump 4
design configuration.
The locations were selected based on the results of inservice testing to determine the direction of maximum amplitude at the specific component bearing (i.e. horizontal or vertical). The locations for the velocity vibration test are specified in individual surveillance procedures. The vibration data acquisition is extremely repeatable since the accelerometer is attached to a mounting block that is bonded l
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to the componen*. being vibration tested.
The requirement af performing vibration
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measurements on each bearing housing in two orthogonal directions has proven to be a duplication of effort in assessing the condition of the machine based on the methods presently employed at Millstone. An additional vibration data point would provide very little, if any additional information as the peak amplitude would be less than the measurement points currently being used. By performing an additional vibration measurement, personnel radiation exposure will be increased due to the additional time spent while testing 20 pumps that are in radiation areas, of which 7 are in high radiation areas. An increase in personnel hazards would be experienced, since some of the bearing housings are close to the pump rotating shaft and coupling and are near hot components. Additionally, physical constraints such as bearing cap size and configuration prevent the addition of multiple test points.-
ALTERNATE TESTING:
On the centrifugal pumps listed above, measure-ments shall be taken on each accessible pump bearing in a location that provides the highest vibration amplitude. Measurements shall also be r~
taken on each accessible pump thrust bearing in
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the axial direction.
Vibration measurements shall censist of overall velocity measured in inches per second peak with a frequency response from at least one-third minimum pump shaft rotational speed to at least 1000 hertz. The acceptance criteria as given in this Program applies to the pumps listed above as well as all of the pumps listed in the IST Program.
Vibration spectral analy-sis will still be used as a diagnostic tool in assessing machine condition.
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PUMP RELIEF REQUEST NUMBER:
R-2 COMPONENTS:
Condensate Pumps A,B, and C.
TEST REQUIREMENT:
Measure individual pump flowrates during Inservice Testing nominally every 3 months.
BASIS FOR RELIEF:
No individual pump flowrate instrumentation is installed on these pumps. All 3 pumps are in service during normal plant operation and pump into a common header where condensate system flow is measured. Any degradation of pump per-formance would be identified by a change in system flow. The condensate system flowrate meter is monitored in the control room so any changes in system performance can be readily identified by the control room operators.
Measurement of pump discharge pressure and motor current is also readily monitored by the operators. Any degradation of pump performance would be identified by changes in system flow, pump motor current, and pump discharge pres-sure during normal operation.
ALTERNATE TESTING: During cold shutdown and reactor refueling, individual pump flowrate will be acquired by
([-)
operating one condensate pump at a time using s
the condensate system header flowrate meter.
Reference values for single pump operation will be established and evaluated to the Test requirements.
A Project Assignment (PA) has been issued to investigate, and if practical, design, procure and install permanent instrumentation for flowrate measurement for these pumps. This PA is being evaluated under the Millstone Unit 1 Integrated Safety Assessment Program (ISAP) and will be scheduled accordingly.
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PUMP RELIEF REQUEST NUMBER:
R-3 COMPONENTS:
Condensate Pumps A,B, and C.
TEST REQUIREMENT:
The resistancc of the system shall be varied until either the measured differential pressure or the measured flowrate equals the corresponding reference value.
BASIS FOR RELIEF:
This requirement requires establishing a constant reference flowrate each time an Inservice Test is performed by throttling the system so that operating parameters can be readily duplicated during subsequent tests.
This ECCS system is always in operation since it is the normal condensate supply to the Feedwater system. Throttling this system during power operation cannot be accomplished without causing flow and pressure fluctuat-ions along with reactor vessel level in-stability. At 100% reactor power, the flow-rate and discharge pressure of these pumps remain virtually at a constant which is readily duplicated during cach inservice test and meets the intent of the test requirement.
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ALTERNATE TESTING:
Inservice Testing will be performed in the as-found system lineup during normal power operation.
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PUMP RELIEF REQUEST NUMBER:
R-4 COMPONENTS:
Condensate Pumps A,B, and C.
TEST REQUIREMENT:
Measure pump differential pressure during Inservice Testing.
BASIS FOR RELIEF:
Relief is requested from calculating suction pressure required for measurement of pump differential pressure.
These pumps take suction from the condenser hotwells which are under a vacuum. No suction pressure inst-rumentation is installed. The hotwell level remains virtually constant due to the hotwell level controller system, and once set, never changes during power operation, so pump suction pressure is a constant value.
ALTERNATE TESTING:
Hotwell level will be measured along with pump discharge pressure in lieu of calculat-t ing differential pressure. Data acquisition will be simplified with less opportunity for error and is adequate to monitor pump per-
)
formance and meet the intent of the test requirement.
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PUMP RELIEF REQUEST
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NUMBER:
R-5 COMPONENTS:
Condensate Booster Pumps A,B, and C.
TEST REQUIREMENT:
Measure i.dividual pump flowrates during Inservice Testing nominally every 3 months.
No individual pump flowrate instrumentation BASIS FOR RELIEF:--
is installed on these pumps. All 3 pumps are in service during normal plant oper-ation and pump into a common header. No system header flowrate instrumentation is installed.
ALTERNATE TESTING:
During the quarterly Inservice Test, pump differential pressure and motor current will be measured and trended.
A project assignment (PA) has been issue 6 to investigate, and if practical, design, procure and install permanent instrumen-tation for flowrate measurement for these pumps. This PA is being evaluated under the Millstone Unit 1 Integrated Safety Assess-ment Program (ISAP) and will be scheduled accordingly.
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PUMP RELIEF REQUEST NUMBER:
R-6 COMPONENTS:
Condensate Booster Pumps A,B and C.
TEST REQUIRE!!ENTS:
The resistance of the system shall be varied until either the measured differential pressure or the measured flowrate equals the corresponding reference value.
BASIS FOR RELIEF:
This requirement requires establishing a constant reference flowrate each time an inservice test is performed by throttling the system so that operating parameters can be readily duplicated during subse@ent tests. This ECCS system is always in oper-ation since it is the normal condensate supply to the reactor vessel. Throttling this system during power operation cannot be accomplished without causing flow and pressure fluctuations along with reactor vessel level instability. At 100% reactor power, the flowrate and discharge pressure of these pumps remain virtually at a constant which is readily duplicated during each inservice test and meets the intent of the test requirement.
ALTERNATE TESTING:
Inservice testing will be performed in the as-found system lineup during normal power operation.
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PUMP RELIEF REQUEST
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NUMBER:
R-7 COMPONENTS:
Reactor Feedwater Pumps A,B and C.
TEST REQUIREMENTS:
The resistance of the system shall be varied until either the measured differential pressure or the measured flowrate equals the corresponding reference value.
BASIS FOR RELIEF:
This requirement requires establishing a constant reference flowrate each time an inservice test is performed by throttling the system so that operating parameters can be read!.ly duplicated during subseguent tests. Th3s ECCS system is always in oper-ation since it is the normal feedwater supply to the reactor vessel. Throttling this system during power operation cannot be accomplished without causing flow and pressure fluctuat-ions along with reactor vessel level insta-bility. At 100% reactor power, the flowrate and discharge pressure of these pumps remain virtually at a constant which is readily duplicated during each inservice test and meets the intent of the test requirament.
()
ALTERNATE TESTING:
Inservice testing will be erformed in the as-found system lineup dur ng normal power operation.
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PUMP RELIEF REQUEST NUMBER:
R-8 COMPONENTS:
Reactor Feedwater Pumps A,B and C.
TEST REQUIREMENTS:
An inservice test shall be run on each pump nominally every 3 months during plant operation.
BASIS FOR RELIEF:
Two of the three reactor feedwater pumps are in operation during normal plant operation.
On the average of every three months, the idle pump is started and one of the operating pumps is shutdown to equalize wear. Several years of operating experience of the feed-water pumps have established this schedule as being the most effective in terms of equip-ment reliability, operational readiness, and reduction of potential feed flow transients which might happen by pump switching.
ALTERNATE TESTING:
Inservice testing will be performed on the operating pumps in accordance with the IST Program.
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1 PUMP RELIEF REQUEST NUMBER:
R-9 COMPONENT:
Emergency Condensate Transfer Pump TEST REQUIREMENT:
The resistance of the system shall be varied until either the measured differ-ential pressure or the measured flow-rate equals the corresponding reference value.
B?, SIS FOR RELIEF:
During FWCI operation, this pump takes a i
suction from the condensate storage tank and pumps water into the condenser hotwell to provide a supply of makeup water for the condensate and feedwater systems. This hydraulic circuit allows only about 8 minutes of operation beforo the hotwells are filled. Throttling to a constant flow-rate or constant differential pressure can-i not be established due to the design and function of the system. Flow and pump dif-ferential pressure instrumentation are installed on this pump. Inservice testing is performed during the actual running condition that the system is designed for.
hs A review of past test results indicate virtually no change of the test parameters due to the level in the condensate storage tank being maintained within a normal oper-ating range.
ALTERNATE TESTING:
Inservice testing will be performed in the as-found condition. Pump flowrate, vibrat-ion and differential pressure measurements will be obtained as required by the test requirement.
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O PUMP RELIEF REQUEST NUMBER:
R-10 COMPONENTS:
Service Water Pumps A,B,C and D.
Emergency Service Water Pumps A,B,C and D.
TEST REQUIREMENT:
Measure pump differential pressure during inservice testing.
BASIS FOR RELIEF:
There are no suction pressure gauges instal-led on these pumps because there is no suction piping associated with these pumps.
These pumps are verticle turbine, deep well, line shaft pumps. The pump 1st stage impeller is open to seawater and is always flooded.
The minimal tidal swing experienced from Niantic Bay is inconsequential in regard to c'if ferential pressure measurement.
ALTERNATE TESTING:
Measure pump discharge pressure in lieu of calculating differential pressure from sea level. Pump discharge pressure measurement will provide sufficient information to ade wately assess service water pump con-dition and will meet the intent of the test O
requirement.
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O PUMP RELIEF REQUEST IIUMBER:
R-11 COMOONENTS:
Service Water Pumps A,B,C and D.
TEST REQUIREMENT:
Measure individual pump flowrates during inservice testing.
BASIS FOR RELIEF:
No flowrate instrumentation is installed in this system. During power operation either one, two and sometimes three service water pumps are operated in parallel and discharge into a common service water supply header.
Pump discharge pressure motor current, and ALTERNATE TESTING:
vibration velocity test 1ng will be performed during inservice testing.
A Project Assignment (PA) has been issued to investigate, and if practical, design, procure and install permanent instrumentation for flowrate measurement for these pumps.
This PA is being evcluated under the Mill-stone Unit 1 Integrated Safety Assessment Program (ISAP) and will be scheduled accord-ingly.
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PUMP RELIEF REQUEST NUMBER:
R-12 COMPONENTS:
Service Water Pumps A,B,C and D.
TEST REQUIREMENT:
The resistance of the system shall be varied until either the measured flowrate or the measured differential pressure equals the corresponding reference value during an inservice test.
BASIS FOR RELIEF:
This requirement requires establishing a constant reference flowrate each time an inservice test is performed by throttling the system so that operating parameters can be readily duplicated during subsequent tests.
The service water system is a variable resistance system that cannot be throttled to a fixed reference value. This system is always in operation with flow varying accord-ing to the heat load of the components the system supplies, changes in sea water inject-ion temperature and operating pump combinat-ions.
ALTERNATE TESTING:
Perform inservice testing in the "as-found" t'l condition of the system. Pump discharge
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pressure, motor current and vibration velocity measurements will be taken to evaluate pump performance to meet the intent of the test requirement.
New range limits of pump discharge pressure are established that allow acceptable operation using less conser-vative ranges other than those shown in the Ranges of Test Parameters Table. Analysis of the system operating under variable flow con-ditions has shown that overall pump perform-ance is not degraded from its intended function.
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PUMP RELIEF REQUEST NUMBER:
R-13 COMPONENTS:
Standby Liquid Control Pumps A and B.
TEST REQUIREMENT:
Measure differential pressure during Inservice i
Testing.
BASIS FOR RELIEF:
These pumps are positive displacement. No suction pressure instrumentation is installed.
During the Inservice Test, pump discharge pres-sure is throttled to a constant value when the capacity is measured.
ALTERNATE TESTING: Pump flowrate and discharge pressure are measured to ensure pump performance in accord-ance with the test requirements.
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PUMP RELIEF REQUEST NUMBER:
R-14 COMPONENTS:
Reactor Building Closed Cooling Water Pumps A and B (RBCCW).
TEST REQUIREMENT:
The resistance of the system shall be varied until either the measured differential pressure or the measured flowrate equals the i
corresponding reference value.
BASIS FOR RELIEF:
This requirement requires establishing a constant reference flowrate each time an inservice test is performed by throttling the system so that operating parameters can be readily duplicated during subsequent in-service tests.
The RBCCW system is a variable resistance system that cannot be throttled to a reference value. This system is always in operation with the flowrate varying according to the heat load of the components the system supplies.
ALTERNATE TESTING:
Inservice testing will be performed in the as-found system lineup.
New range limits of pump differential pressure are established that allow acceptable operation using less
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conservative ranges other than those shown in the Ranges of Test Parameters Table.
Analysis of the system operating under var-iable flow conditions has shown that overall pump performance is not degraded from its intended function.
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PUMP RELIEF REQUEST NUMBER:
R-15 COMPONENTS:
Reactor Building Closed Cooling Water Pumps A and B (RBCCW).
TEST REQUIREMENT:
Measure individual pump flowrates during inservice testing.
j BASIS FOR RELIEF:
No flowrate instrumentation is installed in this system and no bypass or test loop exists. One pump is normally in operation with the other in standby. During the inservice test, pump differential pressure, motor current and vibration velocity are taken on the operating pump. Then the pumps are rotated and the same data is acquired on the other pump. By comparing the test results to each other, any degradation of the pump hydraulic performance can be readily ident-ified, since the system resistance is the same during the test and the pump different-ial pressures should be the same. This method of comparing one pumps tests results to the other has proven to be an effective way of monitoring pump performance.
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ALTERNATE TESTING:
Pump differential pressure, motor current and vibration velocity will be measured during inservice testing.
A Project Assignment (PA) has been issued to investigate, and if practical, design, procure and install permanent instrumentation for flowrate measurement for these pumps.
This PA is being evaluated under the Mill-stone Unit 1 Integrated Safety Assessment Program (ISAP) and will be scileduled accordingly.
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O PUMP RELIEF REQUEST NUMBER:
R-16 COMPONENTS:
Secondary Closed Cooling Water Pumps A and B (SCCW).
TEST REQUIREMENT:
Measure individual pump flowrates during inservice testing.
BASIS FOR RELIEF:
No flowrate instrumentation is installed in this system and no bypass or test loop exists. One pump is normally in operation with the other in standby. During the inservice test, pump differential pressure, motor current and vibration velocity are taken on the operating pump. Then the pumps are rotated and the same data is acquired on the other pump. By comparing the test results to each other, any degradation of the pump hydraulic performance can be readily ident-ified, since the system resistance is the same during the test and the pump different-ial pressures should be the same. This method of com7aring one pumps tests results to the other has proven to be an effective way of monitoring pump performance.
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ALTERNATE TESTING:
Pump differential pressure, and vibration velocity will be measured during inservice testing.
A Project Assignment (PA) has been issued to investigate, and if practical, design, procure and install permanent instrumentation for flowrate measurement for these pumps.
This PA is being evaluated under the Mill-stone Unit 1 Integrated Safety Assessment Program (ISAP) and will be scheduled accordingly.
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PUMP RELIEF REQUEST NUMBER:
R-17 COMPONENTS:
Secondary Closed Cooling Water Pumps A and B.
TEST REQUIREMENT:
The resistance of the system shall be varied until either the measured differential pressure or the measured flowrate equals the corresponding reference value.
BASIS FOR RELIEF:
This test requirement requires establishing a constant reference flowrate each time an inservice test is performed by throttling the system so that operating parameters can be readily duplicated during subsequent in-service tests.
This system is a variable resistance system that cannot be throttled to a reference value. This system is always in operation with the flowrate varying according to the heat load of the components the system supplies.
ALTERNATE TESTING:
Inservice testing will be performed in the as-found system lineup. New range limits of pump differential pressure are established that allow acceptable operation using less conservative ranges other than those shown
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in the Ranges of Test Parameters Table.
Analysis of the system operating under variable flow conditions has shown that overall pump performance is not degraded from its intended function.
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PUMP RELIEF REQUEST NUMBER:
R-18 COMPONENTS:
Shutdown Cooling Pumps A and B.
TEST REQUIREMENTS 1 Measure individual pump flowrates during Inservice Testing.
BASIS FOR RELIEF:
No flowrate instrumentation is installed in this system. During the Inservice Test at cold shutdown, each pump is operated at shutoff head with some recirculation flow for cooling through the minimum flow recirculation line. Differential pressure and vibration spectrum data are acquired.
By comparing the test results to each other and previous tests, any degradation of the pump hydraulic performance can readily be identified, since the system resistance is the same during the test and pump differ-ential pressure should basically be the same. This method of comparing one pumps test results to the other and previous tests is an effective way to monitor pump performance and meet the intent of the test requirement.
ALTERNATE TESTING:
Pump differential pressure measurement and comparison, along with vibration velocity measurements will be taken in lieu of flowrate measurement.
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PUMP RELIEF REQUEST NUMBER:
R-19 j
COMPONENTS:
Shutdown Cooling Pumps A and B.
TEST REQUIREMENTS:
An Inservice Test shall be performed on each pump nominally every 3 months during i
I normal plant operation.
BASIS FOR RELIEF:
These pumps can only be operated during cold shutdown or reactor refueling when the system is being used to remove residual heat. Interlocks prevent opening the shut-down cooling isolation valves when reactor recirculation loop temperature is greater than 350 degrees temperature.
ALTERNATE TESTING:
Inservice Testing will be performed at cold shutdown and at reactor refueling if the shutdown cooling system is placed in j
operation.
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PUMP RELIEF REQUEST NUMBER:
R-20 COMPONENTS:
Control Rod Drive Pumps A and B.
TEST REQUIREMENT:
An Inservice Test shall be performed on each pump nominally every 3 months during normal plant operation.
BASIS FOR RELIEF:
Only one CRD pump is in service during plant operation. The pumps are rotated when the pump suction strainers require changing (approximately 3 months). Observation of these pumps has shown that frequent starts and stops of these high pressure pumps lead to pump degradation.
ALTERNATE TESTING:
Inservice testing will be performed on the operating pump at least once every 3 months in accordance with the Pump Test Require-ments Table.
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PUMP RELIEF REQUEST NUMBER:
R-21 COMPONENTS:
Diesel Fuel Oil Transfer Pumps A and B.
Gas Turbine fuel Oil forwarding Pumps A and B.
TEST REQUIREMENT:
Measure pump differential pressure during Inservice Testing.
J BASIS FOR RELIEF:
There are no pump suction pressurn gauges installed on these pumps because/ there is no suction piping associated with pumps of this type design. These pumps are, vertical turbine, deep well, line shaft centrifugal pumps. The 1st stage impeller is open to the fluid pumped and is always flooded.
The diesel fuel oil storage tank.is normally filled to capacity so suction I
pressure is virtually a constant value.
ALTERNATE TESTING:
Measure pump discharge pressure'j_n lieu of j
l pump inlet pressure and differential!
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pressure during Inservice Testing.
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' PUMP RF LIEF REQUEST E
NUMBER:
R-22 COMPONENTS:
Diesel Fuel Oil Transfer Pumps A and B.
TEST REQUIREMENTS:
Measure individual pump flowrr/xes during
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Inservice Testing' nominally every 3 months.
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EASIS FOR RELIEF:
No flowrate; instrumentation is installed in this system. During operation of the diesel,
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pump discharge pressure and vibration velocity measurements will be acquired, evaluated and trended at least once every 3 months. The performance of these pumps is verified satisfactorily b the control room operators each time the d esel is operated, d
during the monthly Technical Specification Surveillance, by verifying that the. pump capacity is greater than the fuel consumpt-ion of the diesel generator when running at rated load.
AUTERNATE TESTING:
Perform inservice testing at least once every 3 montha, by measuring pump discharge pressure and vibration velocity.
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A project assignment (PA) has been issued to j
investigate, and if practical, design, procure, and install permanent instrumentat-ion for flowrate measurement for these pumps. This PA is being evaluated under the l
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Millstone Unit 1 Integrated Safety Assess-ment Program (ISAP) arid will be scheduled accordingly.
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PUMPRELIEFBIQUEST NUMBER:'
R-23 J
COMPONdNTS:
Gas itirbine Generator Fuel Forwarding Pumps A and B.
TEST REQUIREMENT:
Measure individual pump flowrates during inservice testing nominally every 3 months.
BASIS'FOR RELIEF:
No flowrate instrumentation is installed f-in this system.
AUTERNATE TESTING:
Pump discharge pressure and vibration velocity will be measured, evaluated and trended during inservice testing at least once every three months.
A Project Assignment (PA) has been issued to investigate, and it practical, design, procure and install permanent instrumentation for flowrate measurement for these pumps.
This PA is being evaluated under the Mill-stone Unit 1 Integrated Safety Assessment Program (ISAP) and will be scheduled accord-
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M PUMP RELIEF REQUEST
+l NUMBER:
R-24 COMPONENTS:
Reactor Feedwater Seal Injection Pumps A,B, and C.
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TEST REQUIREMENT:
Measure individual pump flowrates during
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inservice testing nominally every 3 months.
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BASIS FOR RE IEF:
No flowrate instrumentation is installed in this system.
ALTERNATE TESTING:
Pump differential pressure and vibration velocity will be measured, evaluated, and trended during inservice testing at least once every 3 months.
A Project Assignment (PA) has been issued to investigate, and if practical, design, procure and install permanent instrumentation for flowrate measurement for these pumps.
This PA is being evaluated under the Mill-stone Unit 1 Integrated Safety Assessment Program (ISAP) and will be scheduled accord-ingly.
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VALVE INSERVICE TESTING 1.
SCOPE This Prcgram establishes the requirements for inservice testing of certain safety related valves and pressure relief devices (and their actuating and position indication systems) at Millstone Nuclear Power Station Unit 1. The active or passive valves included in this program are those which are required to perform a specific function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or in mitigating the consequences of an accident.
The pressure relief devices included are those for protecting systems or portions of systems which perform a required function in shutting down the reactor to the cold shutdown condition, maintaining the cold shutdown condition or in mitigating the consequences of an accident.
Component relief valves (thermal reliefs) are not included.
Valves that are not required to perform a specific function such as those used only for operating convenience such as vent, drain, instrument and test valves are not included in this test program. Valves used only for system control, such as pressure regulating valves, valves used for system main-()
tenance, and external control and protection systems respon-sible for sensing plant conditions and providing signals for valve operation are excluded from the requirements of this program.
2.
DEFINITIONS A. Active Valves - Valves which are required to change obtur-ator position to accomplish their required function.
The demonstration based on direct visual or Exercising itive indications that the moving parts of a B.
indirect pos valve function.
1 C. Full Stroke Time - The time interval from initiation of the actuating signal to the indication of the end of the operating stroke.
D. Plant Operation - The conditions of startup, operation at power, hot standby, and reactor cooldown, as defined by the Unit Technical Specifications.
E. Obturator - Valve closure member (disk, gate, plug, ball, butterfly, etc.).
F.
Passive Valve - Valves which maintain obturator position and are not required to change obturator position to accomplish the required function as defined in the scope v
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AV of this program.
G.
Reactor Coolant Pressure Isolation -That function which prevents intersystem overpressurization between the reactor coolant system and connected low pressure systems.
H. Reference Values - One or more values of test parameters measured or determined when the equipment is known to be operating acceptably.
I. Operational Readiness - The ability of a valve to perforO its intended function.
3.
CATEGORIES Of VALVES Category A - Valves for which seat leakage is limited to a A. specific maximum amount in the closed position for fulfil-1 ment of their required function.
B. Category B - Valves for which seat leakage in the closed position is inconsequential for fulfillment of their re-quired function.
C. Category C - Valves which are self-actuating in response to some system characteristic, such as pressure (relief O-valves) or flow direction (check valves) for fulfillment of their required function.
D. Category D - Valves which are actuated by an energy source capable of only one operation that are explosively actuated.
4.
CATEGORY A AND B VALVE TEST REQUIREMENTS Inservice testing shall be performed in accordance with this program when the valves are required to be operable to ful-fill their required function.
Reference values (valve stroke times) shall be determined from the results of preservice testing or the results of inservice testing under conditions as near as practicable to those expested during subsequent tests.
Reference values shall only be established when the valve is known to be operating acceptably. If the particular parameter being measured can be signifigantly influenced by other related conditions, then these conditions shall be analyzed.
When a valve or its control system has been replaced, repaired or has undergone maintenance (e.g., adjustment of stem packing, limit switches, or removal of the bonnet, stem assembly, actuator, obturator, or control system components) that could affect the valve's performance, a new reference value shall be determined or the previous value reconfirmed by an inservice test. This test will be run prior to the time the
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O valve is returned to service or immmediately if not removed from service, to demonstrate that performance parameters which cou1J be affected by the replacement, repair or maintenance are within acceptable limits.
Deviations between the previous and new reference values shall be identified and analyzed. Verification that the new value represents acceptable operation shall be documented in the record of tests.
Safety and relief valves and nonreclosing pressure relief devices shall be tested as required by the replacement, repair and maintenance requirements of ANSI /ASME OM-1.
If it is desirable for some reason to establish additional reference values, an in6ervice test shall first be run at the conditions of an existing set of reference values; or, if not practical, at the conditions for which the new reference values are required and the results analyzed. If operation is accept-able, a second test shall be performed under the new conditions as soon as practical. The results of the second test shall establish the additional reference values. Whenever additional reference v31ues are established, the reasons for doing so shall be justified and documented in the record of tests.
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5.
CATEGORY A AND B VALNE TEST FREQUENCIES Category A and B valves shall be full stroke exercised to the position required to fulfill their function during plant operation nominally every 3 months.
If full stroke exercising is not practicable during plant oper-ation, it may be limited to part stroke operation during plant operation and full stroke operated during cold shutdowns.
If exercising is not practicable during plant operation, it may be limited to full stroke exercising during cold shutdown.
If exercising is not practicable during plant operation and full stroke exercising during cold shutdown is also not practicable, it may be limited to part stroke exercising during cold shutdowns, and full stroke exercising during refueling outages.
If exercisin, is not practicable during plant operation or cold shutdowns, it may be limited to full stroke exercising during refueling outages.
Valves requiring full stroke exercising at cold shutdowns shall be exercised during each cold shutdown. Such exercise is not required if the time period since the previous full stroke exercis is less than 3 months.
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O Valve exercising during cold shutdown shall commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power.
However, it is not the intent of this requirement to keep the
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plant in cold shutdown in order to complete cold shutdown testing.
All valve testing required to be performed during a reactor refueling outage shall be completed prior to returning the plant to operation.
Active and Passive Valves with remote position indicators shall be observed locally at least once every two years to verify that valve operation is accurately indicated.
f Valves requiring leakage rate tests shall be performed at least once every two years.
6.
CATEGORY A AND B VALVE EXERCISING REQUIREMENTS The necessan valve obturator movement shall be determined by exercising the valve while observing an appropriate indicator, such as indicating lights which signal the required change of obturator position, or by observing other evidence, such as changes in system pressure, flow rate level, or temperature, which reflect change of obturator pos tion.
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of full stroke time for each power oper-The limiting value(s)ied in the IST Valve List Tables and are ated valve are specif also specified on each respective valve surveillance data sheet.
The stroke time for all power operated valves shall be measured to at least the nearest second.
Any abnormality or erratic action shall be recorded and an evaluation shall be made regarding need for corrective action.
Valves which operate in the course of plant operation at a frequency which would satisfy tne exercising requirements of this program need not be additionally exercised, provided that the observations otherwise required for testing are made and analyzed during operation and are recorded in the plant record at intervals no greater than allowed by the valve test fre-quencies.
Valves with fail-safe actuators shall be tested by observing the operation of the actuator upon loss of valve actuating power in accordance with the frequencies and appropriate relief requests given in the IST Valve List Tables.
For a valve in a system declared inoperable or not required to be operable the exercising test schedule need not be
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followed. With n 3 months prior to placing the system in an
O operable status, the valves shall be exercised and the test schedule followed in accordance with the IST Valve List Table.
7.
CATEGORY A AND B STROKE TIME ACCEPTANCE CRITERIA Valve stroke times acquired during the inservice test shall be s
compared to the initial reference valve stroke time or ref-erence values established in accordance with section 4.
Electric motor operated valves with reference stroke times greater than 10 seconds shall exhibit no more than a +15%
change in stroke time when compared to the reference value.
Electric motor operated valves with reference stroke times less than or equal to 10 seconds shall exhibit no more than a 125% or il second change in stroke time, whichever is greater when compared to the reference value.
Power operated valves other than electric motor driven valves with reference stroke times greater than lo seconds shall exhibit no more than a +25% change in stroke time when compared to the reference stroke time.
Power operated valves other than electric motor driven valves with reference stroke times less than or equal to 10 seconds shall exhibit no more than a +50% change in stroke time when O
compared to the reference value.
The stroke time for valves that change position in less than 2 seconds shall be measured and recorded and shall be acceptable, provided that the measured stroke time is less than 2 seconds.
8.
CATEGORY A AND B VALVE CORRECTIVE ACTION If a valve exceeds the maximum specified stroke time as given in the Valve List Table or fails to exhibit the required change of obturator position, the valve shall be immediately declared inoperable.
Valves with measured stroke times which do not meet the requir-ed acceptance criteria given in section 7 above shall be immed-lately retested or declared inoperable. If retested and the second set of data also does not meet the acceptance criteria, the data shall be analyzed within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to verify that the new stroke time represents acceptable valve operation, or the valve shall be declared inoperable. If the second set of data meets the acceptance criteria, the cause of the initial dev-lation shall be analyzed and the results documented in the test j
records.
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Valves declared inoperable may be repaired, replaced, or the data may be analyzed to determine the cause of the deviation and the valve shown to be operating acceptably.
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O Valve operability based upon analysis shall have the results of the analysis recorded in the record of tests.
Prior to returning a repaired or replaced valve to service, a
test demonstrating satisfactory operation shall be performed.
9.
VALVE SEAT LEAKAGE RATE TESTING Containment isolation valves that are Appendix J, Type C, leak tested are included in this IST Program and are categorized as A or A/C.
The applicable leak test procedures and requirements for containment isolation valves are determined by 10 CFR 50, The maximum allowable leakage rates for Category A Appendix J.
or A/C valves are specified in the Plant Technical Specificat-ions (Ref:
4.7.A.3.e.).
Valves exceeding the maximum leakage rate shall be repaired or replaced and retested.
(Reft Relief Request V-9).
Containment isolation valves listed in the 10 CFR 50 Appendix J Program that do not receive a Type C local leak rate test are also included in this IST Program and are categorized as A or A/C.
Relief requests for exemption from leak testing these valves are not given in this IST Program but are given in the Millstone Unit 1 Appendix J Program submittal under separate docket. (Ref: Relief Request V-32).
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For valves 6 inches nominal pipe size and larger, if a leakage rate exceeds the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate by 50% or greater, the test fre pency shall be doubled.
The tests shall coincide with a cold shutdown until corrective action is taken, at which time the original test frequency shall be resumed.
If tests show a leakage rate increasing with time, and a projection based on three or more tests indicates that the leakage rate of the next scheduled test will exceed the maximum permissible leakage rate the valve shall be replaced or repaired.
by greater than 10%, ion XI, 1980 Edition including the Winter (Ref: ASME Code Sect 1980 Addenda, Articles IWV-3426 and IWV-3427, Analysis of leak-age Rates and Corrective Action).
Containment isolation valves which also provide a reactor coolant system pressure isolation function are specified in the IST Valve List Tables along with specific relief requests that operational observations provide the basis that system design and alternate testing constitute sat 1sfactory seat tightness.
(Ref: Relief Requests V-48 and V-49).
Valves which perform a function other than containment isolation are specified in the IST Valve List Table along with specific rel.ief requests that provide the test methods and acceptance criceria (Ref: Relief Requests V-42 and V-43).
10.
CHECK VALVE TEST REQUIREMENTS Check valves which operate in the course of plant operation at a frequency which would satisfy the exercising requirements of this Program need not be additionally exercised provided that the observations otherwise required for testing are made and analyzed during such operation and are recorded in the plant records at intervals no greater than the test frequency as specified in Section 11 of this Valve Test Program.
Valve obturator movement shall be demonstrated by exercising the valve and observing that either the obturator travels to the seat on cessation or reversal of flow, or opens to the position required to fulfill its intended function.
Observation may be by observing a direct indicator such as changes in system pressure, flow rate, level, temperature, seat leakage testing or other positive means.
As an alternative to the testing as given in the above, dis-ascomoly of check valves may be used to verify operability 15ef: Relief Request V-41).
11.
CHECK VALVE TEST FREQUENCIES Check valves shall be exercised or examined during plant oper-ation in a manner which verifies obturator travel to the clos-ed, full open or partially open position required to fulfill its function nominally every 3 months.
If full stroke exercising during plant operation is not pract-ical, it may be limited to part stroke exercising during plant operation and full stroke exercising during cold shutdowns.
If exercising is not practical during plant operation, it may be limited to full stroke exercising during cold shutdowns.
If exercising is not practical during plant operation and full stroke exercising is also not practical, it may be limited to part stroke exercising during cold shutdowns, and full stroke exercising during refueling outages.
If exercising is not practical during plant operation or cold shutdowns, it may be limited to full stroke exercising during refueling outages.
Valves requiring exercising at cold shutdowns shall be exercis-ed during each cold shutdown. Such exercising is not required if the time period since the previous full stroke exercise is less than 3 months.
Od Valve exercising shall commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown, and continue until all testing is complete or the plant is ready to return to power. However, it is not the intent of this program to keep the plant in cold shutdown in order to complete all cold shutdown testing.
All check valve testing required to be performed during a refueling outage chall be completed prior to returning the plant to operation.
12.
CHECK VALVE CORRECTIVE ACTION If a check valve fails to exhibit the required change of obturator position, it shall be declared inoperable. A retest showing acceptable performance shall be run following any required corrective action before the valve is returned to service.
13.
EXPLOSIVELY ACTUATED VALVE TESTS A record of the service life of each charge in each valve shall be maintained. This record shall include the date of manufac-ture, batch number, installation date, and the date when service life expires based on the manufacturer's recommen-dations. In no case shall the service life exceed ten years.
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Concurrent with the first test and at least once every two years, the service life records of each valve shall be review-ed to verify that the service life of the charges have not been exceeded before the next refueling outage. Appropriate action shall be taken to ensure charge service life is not exceeded.
At least 20% of the charges in explosively actuated valves shall be fired and replaced at least once every 2 years. If a charge fails to fire, all charges with the same batch number shall be removed, discarded, and replaced with charges from a different batch. (Ref: Relief Request V-35).
Replacement charges shall be from batches from which a sample i
charge shall have been tested satisfactorily and with a service life such that the requirements of the above are met for subsequent inrrection periods.
14.
VALVE RECORDS AND REPORTS The following records shall be maintained for each valve included in the IST Valve Program if available.
A. The manufacturer and manufacturer's model and serial or unique identification number.
B. A copy or summary of the Manufacturer's acceptance test
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report.
O C.
Preservice test results.
D. The limiting value of full stroke time as specified in Valve List Table.
The following record of test plans shall be maintained for each valve in the IST Valve Program. (Ref: IST Valve List Tables).
A.
Identification of valves subject to test.
B. Category of each valve.
C.
Tests to be performed.
D. Justification for deferral of stroke testing.
15.
RECORD OF TESTS Each Record of test shall include the following:
A.
Valve identification.
B.
Date of test.
O C.
Reason for test (e.g.
Tech Spec surveillance, routine inservice test establishing reference values, post maintenance restoration, etc).
D.
Values of measured parameters.
E.
Identification of instruments used.
F.
Comparisons with allowable ranges of test values and analysis of deviations.
G.
Requirements for corrective action.
H.
Signature of the person or persons responsible for conducting and analyzing the test.
16.
RECORD OF CORRECTIVE ACTION Records of corrective action shall be maintained which shall include a summary of the corrections made and the subsequent inservice tests and confirmation of operational adequacy and the signature of the individual responsible for corrective action and verification of results.
LEGEND FOR VALVE TESTING AO
- Air operated valve BALL - Ball valve BFLY - Butterfly valve B31.1-ANSI /ASME B31.1 Power Piping Code CL
- Closed valve position CIV
- Containment isolation valvo CK
- Cold shutdown DIAP - Diaphragm seated valve FP
- Fire protection FT
- Fail-safe actuator GA
- Gate valve GL
- Globe valve LT
- Leak test LLRT - Local Leak Kate Tested valve in accordance with 10 CFR 50 Appendix
'J' type
'C' test.
MO
- Motor operated valve MT
- Stroke time measurement OP
- Open valve position PI
- Position indication test PLUG - Plug type valve, rotary actuated PORV - Power Operated Relief Valve Q
- Quarterly REL _ Relief Valve RR
- Reactor refuel outaga SHEAR-Explosively actuated valve Solenoid valve SOL Safety and relief valve surveillance SRV Throttle valve
(])
THL Vacuum breaker VB l
1
O O
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A AT II EE IR MUMBER SE DESCRIPTION I
T LI NR FS NN REMARKS l
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1-MW-86 2C EMERGENCY CONDENSATE TRANS-3 REL SRV (1-FCX-1)
FER PUMP (ECT) RELIEF l
1-MW-96 2C ECT PUMP DISCHARGE CHECK 14 CK CL Q
s 1-MW-96A 2B ECT PUMP DISCHARGE ISOLATION 14 GA MO CL Q
90 SEC TO OPEN l
'J l 1-CN-2A 2C CONDENSATE PUMP
'A' 20 CK OP V-1 CS l
DISCHARGE CHECK p1-CN-2B 2C CONDENSATE PUMP
'B' 20 CK OP V-1 CS DISCHARGE CHECK 4
I s
!! 1-CN-2C 2C CONDENSATE PUMP
'C' 20 CK s OP V-1 CS p
DISCHARGE CHECK s
] 1-CN-30A 2C CONDENSATE BOOSTER PUMP "A'
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$1-CN-30B 2C CONDENSATE BOOSTER PUMP ~B' 20 CK OP V-1 CS l
i DISCHARGE CHECK
' 2C CONDENSATE BOOSTER PUMP
'C' 20 CK OP V-1 CS
'i l1-CN-30C DISCHARGE CHECK
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l
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VALVE AT E
A AT II EE IR L
NUMBER SE DESCRIPTION I
T I
O GE T
GA i
/O C
Y O
N M
T R
H P
N E
I Y
E E
N V
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E 1-CN-58 2B STEAM JET AIR EJECTOR 16 GA A0 CL Q
V-2 CS MINIMUM FLOW CONTROL MT 90 SEC TO CLOSE FT V-3 PI 1-CN-60 2B STEAM JET AIR EJECTOR 16 GL MO CL N/A PASSIVE MAINTENANCE MINIMUM FLOW BYPASS VALVE j 1-CN-701 2B CONDENSATE SUPPLY TO 6
BFLY A0 OP Q
V-4 CS 30 SEC TO CLOSE RECOMBINER CONDENSER MT FT V-3 PI 1-CN-67 2B HOTWELL REJECT TO CONDENSATE 4
GL A0 THL Q
V-5 STORAGE TANK LCV MT FT CS PI 1-CN-69 2B BYPASS AROUND 1-CN-67 6
GA MO CL N/A PASSIVE MAINTENANCE VALVE 1-MW-7 2B CONDENSATE TRANSFER TO CON-4 GL A0 THL Q
V-5 DENSER HOTWELL LCV MT FT CS PI 1-MW-9 2B BYPASS AROUND 1-MW-7 6
GA MO CL N/A PASSIVE MNTC. VALVE
MP-1 IST VALVE LIST SYSTEM NAME: FEEDWATER COOLANT INJECTION PAGE 3
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OO EE ;EE EL l
CC Z
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T LI NR FS NN RENARKS 4
SG H
T I
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GA
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N M
T R
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N E
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N Y
S T
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'A' 18 CK OP/
Q V-6 CS DISCHARGE CHECK CL 1 1-FW-2B 2C REACTOR FEED PUMP
'B' 18 CK OP/
Q V-6 CS DISCHARGE CHECK CL 1-FW-2C 2C REACTOR FEED PUMP
'C' 18 CK OP/
Q V-6 CS DISCHARGE CHECK CL 1-FW-4A 2B FEEDWATER BLOCKING 14 GA MO OP Q
V-7 CS 56 SEC TO OPEN ISOLATION MT PI 1-FW-4B 2B FhEDWATER BLOCKING 14 GA MO OP Q
V-7 CS 56 SEC TO OPEN ISOLATION MT PI 1-FW-4C 2B FEEDWATER START-UP BLOCKING 4
GA MO CL Q
V-7 CS 30 SEC TO OPEN/ CL ISOLATION MT PI l
1-FW-5A 2B FEEDWATER CONTROL 12 GL AO THL Q
V-7 CS 10 SEC TO OPEN MT 30 SEC TO CLOSE FT LOCK-AS-IS PI 4
O O
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FEEDWATER COOLANT INJECTION PAGE 4
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T LI NR FS NN REMARKS FG H
T I
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GA
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Y O
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T R
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N E
I Y
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N V
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E 1-FW-5B-2B FEEDWATER CONTROL 12 GL AO THL Q
V-7 CS 10 SEC TO OPEN MT 30 SEC TO CLOSE FT LOCK-AS-IS PI 1-FW-SC 2B FEEDWATER START-UP CONTROL 4
GL AO CL Q
V-7 CS 30 SEC TO OPEN/
MT CLOSE FT PI 1-FW-9A 1AC FEEDWATER CONTAINMENT 18 CK OP Q
V-8 CS ISOLATION CHECK LT V-9 LLRT CIV 1-FW-9B 1AC FEEDWATER CONTAINMENT 18 CK OP Q
V-8 CS ISOLATION CHECK LT V-9 LLRT CIV 1-FW-10A 1AC FEEDWATER CONTAINMENT 18 CK OP Q
V-8 CS ISOLATION CHECK LT V-9 LLRT CIV 1-FW-10B 1AC FEEDWATER CONTAINMENT 18 CK OP Q
V-8 CS ISOLATION CHECK LT V-9 LLRT CIV 1-FW-14A 2B REACTOR FEED PUMP
'A' RECIRC 6
GL AO CL Q
V-10 CS 30 SEC TO OPEN/
MINIMUM FLOW FCV MT CLOSE FT V-3 PI
5
/
/
E N
N G
E E
O A
P P
P S
O O
KR O
O A
T T
M E
C C
R EE EE SS SS O
O 0L 0L 3C 3C ALTERNATIVE S
S C
C TESTING 0
0 REQUEST 1
3 1
3 s
RELIEF V
V V
V T
REQUIREMENT TTI TTI QMFP QMFP Q
Q Q
TESTING S
/
/
/
I P0SITION L
L PL PL PL C
C OC OC OC L
N0RMAL O
O E
ACTUATION A
A VL L
L K
K K
VALVE TYPE G
G C
C C
A O V SIZE INCHES 6
6 2
2 2
T C
C S
R R
N N
N I
I O
O O
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C I
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TK TK TK R
JH JH JH B
C NC NC NC
~
I I
I N
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P LG LG LG I
M M
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SH SH SH I
C C
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DW DW DS DS DS C
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FF FF F
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TM TM T
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CI CI CP CP CP AN AN AM AM AM EI EI EU EU EU RM RM RP RP RP EMA CATEGORY B
B C
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N 2
2 2
2 2
CLASS /
M O
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C A
B C
S R
4 4
8 8
8 Y
EE 1
1 7
7 7
S VB LM W
W N
N N
AU F
F C
C C
VN 1
1 1
1 1
O Or MP-1 IST VALVE LIST SYSTEM NAME: CONTROL ROD DRIVE HYDRAULIC PAGE 6
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T LI NR FS NN REMARKS 1
SG N
T I
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GA
/O C
Y 0
N M
T H
H P
N K
I Y
E E
N V
S T
E 302-19A 2B MASTER SCRAM SOLENOID 1
GL SOL CL Q
302-19B 2B MASTER SCRAM SOLENO.D 1
GL SOL CL Q
V-11 CS T
MT V-36 Y
FT V-3 g
302-19C 2B ATHS SCRAM SOLENOID 1
GL SOL CL Q
302-19D 2B ATHS SCRAM SOLENOID 1
GL SOL CL Q
)g FT V-3 302-20A 2B SCR'AM DISCHARGE VOLUM8 VENT 1
GL SOL CL Q
V-11 CS AND DRAIN SOLENOID MT V-36 FT V-3 1
302-20B 2B SCRAM DISCHARGE VOLUME VENT 1
GL SOL CL Q
V-11 CS AND DRAIN SOLENOID MT V-36 FT V-3 1
301-122A 2C SCRAM PILOT AIR HEADER CHECK 1
CK CL Q
V-11 301-122B 2C SCRAM PILOT AIR HEADER CHECK 1
CK CL Q
V-11
=
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I Y
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N V
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E 301-122C 2C SCRAM PILOT AIR HEADER CHECK 1
CK CL Q
V-11 CS 305-114 2C HYDRAULIC CONTROL UNIT TO
.75 CK CL Q
V-11 CS SCRAM DISCHARGE VOLUME CHECK 305-115 2C CHARGING WATER SUPPLY TO
.5 CK CL Q
V-11 CS ACCUMULATOR CHECK 305-117 2B SCRAM PILOT AIR SOLENOID
.5 GL SOL CL Q
V-37 CS MT YT V-3 2B SCRAM PILOT AIR SOLENOID
.5 GL SOL CL Q
V-37 CS 1
MT ll FT V-3 28., SCRAM INSERT 1
GL A0 CL Q
o-s-127 f 2E SCRAM EXHAUST
.75 GL AO CL 0
5 FT V-3
~;05-120 20 CRD WITHDRAW EXHAUST WATER
.5 GL SOL CL Q.
V-13 NONE MT '
FT V-3
- DENOTES ONE OF 145 HYDRAULIC CONTROL UNITS
[
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O ALTERNATIVE N
N N
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O O
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TESTING N
N N
N N
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3 3
3 3
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REQUEST 1
3 1
3 1
3 1
1 U
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V V
V V
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V, DY T
REQUIREMENT TT TT TT H
QMF QMF QMF Q
Q 5
TESTING S
4 1
I POSITION L
L L
L L
C C
C C
C F
L NORMAL O
E L
L L
N E
ACTUATION O
O O
O S
S S
V SE L
L L
L K
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VALVE TYPE G
G G
C C
O O
A NE V
D 5
5 5
5 5
I UAR R
D E
W K
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TT H
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C R
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A L
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TC WC O
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LM AU 5
5 5
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3
O O
o MP-1 IST VALVE LIST SYSTEM NAME:
CONTROL ROD DRIVE HYDRAULIC PAGE 9
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l CC Z
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T I
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GA
/O C
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N M
T R
H P
N E
I Y
E E
N V
S T
E 1-SDV-1N 2A SCRAM DISCHARGE VOLUME 1
GL AO OP Q
V-14 CS 30 SEC TO CLOSE HEADER VENT BACKUP MT FT V-3 PI LT V-9 LLRT CIV 1-SDV-2N 2A SCRAM DISCHARGE VOLUME 1
GL AO OP Q
V-14 CS 30 SEC TO CLOSE HEADER VENT BACKUP MT FT V-3 PI LT V-9 LLRT CIV 1-SDV-IS 2A SCRAM DISCHARGE VOLUME 1
GL AO OP Q
V-14 CS 30 SEC TO CLOSE HEADER VENT MT FT V-3 PI LT V-9 LLRT CIV 1-SDV-2S 2A SCRAM DISCHARGE VOLUME 1
GL AO OP Q
V-14 CS 30 SEC TO CLOSE HEADER VENT BACEUP MT FT V-3 PI LT V-9 LLRT CIV
O O
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V A
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00 EE EE EL CC Z
L T
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T I
O GE T
GA
/0 C
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T R
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E l
1-SDV-3N 2A SCRAM DISCHARGE VOLUME TANK 2
GL A0 OP Q
V-14 CS 30 SEC TO CLOSE DRAIN ISOLATION MT FT V-3 PI LT V-9 LLRT CIV 1-SDV-4N 2A SCRAM DISCHARGE VOLUME TANK 2
GL A0 OP Q
V-14 CS 30 SEC TO CLOSE DRAIN BACKUP MT FT V-3 PI LT V-9 LLRT CIV 1-SDV-3S 2A SCRAM DISCHARGE VOLUME TANK 2
GL A0 OP Q
V-14 CS 30 SEC TO CLOSE DRAIN ISOLATION MT FT V-3 PI LT V-9 LLRT CIV 1-SDV-4S 2A SCRAM DISCHARGE VOLUME TANK 2
GL A0 OP Q
V,-14 CS 30 SEC TO CLOSE DRAIN BACKUP MT
~
O O
O MP-1 IST VALVE LIST PAGE 11 SYSTEM NAME: LOW PRESSURE COOLANT INJECTION S
V A
A C
00 EE EE EL CC Z
L T
RS SQ LQ ST LA E
V U
A AT II EE IR NUMBER SE DESCRIPTION I
T I
O GE T
GA
/O C
Y O
N M
T R
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N E
I Y
E E
N V
S T
E 1-LP-2A 2A PUMP "A'
SUCTION 18 GA MO OP Q
120 SEC TO OPEN/
LT V-32 CIV 1-LP-2B 2A PUMP
'B' SUCTION 18 GA MO OP Q
120 SEC TO OPFN/
MT CLOSE d
PI LT V-32 CIV 1-LP-2C 2A PUMP
'C' SUCTION 18 GA MO OP Q
120 SEC T0 'Wid -
MT CLOSE 3
PI i-LT V-32 CIV 1-LP-2D 2A PUMP
'D' SUCTION 18 GA MO OP Q
120 SEC TO OF, MT CLOSE PI LT V-32 CIV 1-LP-3A 2C PdMP
'A' DISCHARGE CHECK 12 CK CL Q
1-LP-3B 2C PUMP ~B' DISCHARGE CHECK 12 CK CL Q
1-LP-3C 2C PUMP
'C' DISCHARGE CHECK 12 CK CL Q
1-LP-3D 2C PUMP
'D' DISCHARGE CHECK 12 CK CL Q
1-LP-7A 2B HEAT EXCHANGER
'A' BYPASS 18 GA MO OP Q
30 SEC TO OPEN/
O O
o MP-1 IST VALVE LIST PAGE 12 SYSTEM NAME: LOW PRESSURE COOLANT INJECTION S
V A
A C
00 EE EE EL CC Z
L T
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A AT II EE IR NUMBER SE DESCRIPTION I
T I
O GE T
GA
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Y O
N M
T R
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E 1-LP-7B 2B HEAT EXCHANGER
'B' BYPASS 18 GA MO OP Q
30 SEC TO OPEN/
l MT CLOSE PI 1-LP-8A 2B LPCI CROSS CONNECT 18 GA MO OP Q
120 SEC TO OPEN/
MT CLOSE PI 1-LP-9A 2B LPCI TO RECIRCULATION SYSTEM 18 GL MO OP Q
20 SEC TO OPEN/
l l
GTOP-CHECK THROTTLE MT CLOSE PI 1-LP-9B 2B LPCI TO RECIRCULATION SYSTEM 18 GL MO OP Q
20 SEC TO OPEN/
l STOP-CHECK THROTTLE MT CLOSE PI 1-LP-10A 1A LPCI.TO RECIRCULATION 18 GA MO CL Q
18 SEC TO OPEN/
INJECTION MT 40 SEC TO CLOSE PI LT V-48 LLRT CIV / PIV g
1-LP-10B 1A LPCI TO RECIRCULATION 18 GA MO CL Q
18 SEC TO OPEN/
INJECTION MT 40 SEC TO CLOSE PI l
O O
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V A
A C
00 EE EE EL CC Z
L T
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LA E
V U
A AT II EE IR NUMBER SE DESCRIPTION I
T I
O GE T
GA
/O C
Y O
N M
T R
H P
N E
I Y
E E
N V
S T
'A' INJECTION CHECK 16 CK CL Q
'B' INJECTION CHECK 16 CK CL Q
V-16 CS\\RR 1-LP-13A 2B TORUS SPRAY OUTBOARD STOP 6
GA MO CL Q
SO SEC TO OPEN/
l MT CLOSE PI 1-LP-13B 2B TORUS SPRAY OUTBOARD STOP 6
GA MO CL Q
SO SEC TO OPEN/
l MT CLOSE PI 1-LP-14A 2A TORUS SPRAY INBOARD STOP 6
GL MO CL Q
25 SEC TO OPEN/
MT CLOSE PI LT V-9 LLRT CIV 1-LP-14B 2A TORiS SPRAY INBOARD STOP 6
GL MO CL Q
25 SEC TO OPEN/
l MT CLOSE PI LT V-9 LLRT CIV 1-LP-15A 2A DRYWELL SPRAY OUTBOARD STOP 10 GL MO CL Q
25 SEC TO OPEN/
l MT CLOSE PI LT V-9 LLRT CIV s
O O
O MP-1 IST VALVE LIST SYSTEM MAME: LOW PRESSURE COOLANT INJECTION PAGE 14 g
NP 'T E RR TA ii i
i i
1 I
I A
C OO EE EE EL CC Z
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A AT II EE IR NUMBER SE DESCRIPTION I
T I
O GE T
GA
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Y 0
N M
T R
H P
N E
I Y
E E
N V
S T
E 1-LP-15 B 2A TORUS SPRAY OUTBOARD STOP 10 GL MO CL Q
25 SEC TO OPEN/
1 MT CLOSE PI LT V-9 LLRT CIV 1-LP-16A 2B DRYWELL SPRAY INBOARD STOP 10 GA MO CL Q
25 SEC TO OPEN/
1-LP-iSB 2B DRYWELL SPRAY INBOARD STOP 10 GA MO CL Q
25 SEC TO OPEN/
1-LP-24A 2A PUMP
'A' MIN FLOW DECIRC TO 2
CK CL Q
V-41 RR TORUS CHECK
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LT V-32 CIV 1-LP-24B 2A PUMP ~B' MIN FLOW RECIRC TO 2
CK CL Q
V-41 RR TORUS CHECK LT V-32 CIV 1-LP-24C 2A PUMP
'C' MIN FLOW RECIRC TO 2
CK CL Q
V-41 RR TORUS CHECK LT V-32 CIV 1-LP-24D 2A PUMP
'D' MIN FLOW RECIRC TO 2
CK CL Q
V-41 RR TORUS CHECK n
LT V-32 CIV - _
h x
m O
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MP-1 IST VALVE LIST SYSTEM MAME: LOW PRESSURE COOLANT INJECTION PAGE 15 S
V A
NP TR
'R R TA I
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00 EE EE EL CC Z
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'A' AND
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GA MO OP Q
35 SEC TO OPEN/
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RECIRC TO TORUS MY CLOSE PI 1-LP-26B 2B PUMP
'B' AND
'D' MIN FLOW 3
GA MO OP Q
35 SEC TO OPEN/
{
RECIRC TO TORUS MT CLOSE PI 1-LP-32A 2C LPCI SYSTEM
'A' BELIEF 2.5 REL SRV 1-LP-32B 2C LPCI SYSTEM
'B' RELIEF 2.5 REL SRV 1-LP-43A 2A LPCI TEST LINE TO TORUS 10 GA MO CL Q
30 SEC TO OPEN/
OUTBOARD STOP MT CLOSE PI LT V-32 CIV 1-LP-43B 2A LPCI TEST LINE TO TORUS 10 GA MO CL Q
33 SEC TO OPEN/
OUTBOARD STOP MT CLOSE PI LT V-32 CIV 1-LP-44A 2B LPCI TEST TO TORUS INBOARD 10 GL MO CL Q
50 SEC TO OPEN/
[
O-O o
qj MP-1 IST VALVE LIST SYSTEM NAME:
LOW PRESSURf COOLANT INJECTION PAGE 16 V
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1-LP-44B 2B LPCI TEST TO TORUS INBOARD 10 GL MO CL Q
50 SEC TO OPEN/
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STOP MT CLOSE PI 1-LP-46 2AC CONDENSATE TRANSFER TO LPCI 2
CK Q
V-42 RR l
SYSTEM KEEP FILL CHECK LT V-42 1
1-LP-47 2AC CONDENSATE TRANSFER TO LPCI 2
CK Q
V-42 RR SYSTEM KEEP FILIs. CHECK LT V;42 1-LP-52A 2B COOLING WATER TO LPCI PUMPS 1
GL SOL CL Q
l
'A' AND
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GL SOL CL Q
'B' AND
'D' MOTOR BEARING MT V-44 OIL COOLERS PI V-44 FT V-3
O O
O MP-1 IST VALVE LIST PAGE 17 SYSTEM NAME:
V A
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1-CS-2A 2A CORE SPRAY PUMP
'A' SUCTION 12 GA MO
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90 SEC TO OPEN/
MT CLOSE PI LT V-32 CIV 1-CS-2B 2A CORE SPRAY PUMP
'B' SUCTION 12 GA MO OP Q
90 SEC TO OPEN/
MT CLOSE PI LT V-32 CIV 1-CS-3A 2C PUMP
'A' DISCHARGE CHECK 10 CK CL Q
1-CS-3B 2C PUMP
'B' DISCHARGE CHECK 10 CK CL Q
1-CS-4A 2B INJECTION VALVE BACKUP 10 GA MO OP Q
20 SEC TO OPEN/
j MT CLOSE PI 1-CS-4B 2B INJECTION VALVE BACKUP 10 GA MO OP Q
20 SEC TO OPEN/
MT CLOSE PI 1-CS-SA 1A INJECTION VALVE
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MP-1 IST VALVE LIST SYSTEM NAME: CORE SPRAY PAGE 18 in L'
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1-CS-6A IC INJECTION CHECK
'A' 10 CK CL Q
V-17 RR 1-CS-6B IC INJECTION CHECK "B'
10 CK CL Q
V-17 RR 1-CS-14A 2AC TEST LINE TO TORUS CHECK 6
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LT V-32 CIV g
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1-CS-18A 2C SYSTEM
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REL SRV 1-CS-18B 2C SYSTEM ~B' RELIEF 2
REL SRV 1-CS-21A 2B TEST LINE TO TORUS 6
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GA MO CL Q
20 SEC TO OPEN/
O O
O MP-1 IST VALVE LIST SYSTEM NAME:
CORE SPRAY PAGE 19
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PAGE 35 I
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VALVE RELIEF lEQUEST j
NUMBER:
V-1 SYSTEM:
Feedwater Coolant Injection (FWCI)
VALVES:
1-CN-2A, 1-CN-2B, 1-CN-2C, 1-CN-301, 1-CN-30B, 1-CN-30C.
CLASS / CATEGORY:
2C FUNCTION:
Condensate and Condensate Booster Pump Discharge Check Valves.
TEST REQUIREMENT:
Check valves shall be exercised at least once every 3 nonths.
BASIS FOR RELIEF:
111 of these valves are open during nor-mal operation. Exercising these valves re@ ires stopping and starting each pump which causes feedwater flow and pressure fluctuations which places the plant in an unstable condition.
ALTERNATE TESTING:
Verify that the check valves open upon pump starting at cold shutdown during reactor start-up. Valve closure is
{T verified by the Plant Equipment Operators observation of pump discharge pressures and reverse rotation of an idle pump during routine operators rounds.
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VALVE RELIEF REQUEST NUMBER:
V-2 SYSTEM:
Feedwater Coolant Injection (FWCI)
VALVE:
1-CN-58 CLASS / CATEGORY:
2B FUNCTION:
Steam Jet Air Ejector Minimum Flow Control Valve.
TEST REQUIREMENT:
Category A and B valves shall be exercised once every 3 months.
BASIS FOR RELIEF:
This valve is only open during reactor start-up at low condensate system flow.
Exercising this valve during normal power operation disrupts condensate flow and bypasses flow to the main condenser.
ALTERNATE TESTING:
Exercise valve during cold shutdown.
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VALVE RELIEF REQUEST NUMBER:
V-3 SYSTEM:
Various VALVES:
Fail Safe Valves CLASS / CATEGORY:
Various FUNCTION:
Various TEST REQUIREMENT:
Fail-Safe Valves. Test valves with fail-safe actuators by observing the operation of the valves upon loss of actuator power.
BASIS FOR RELIEF:
Normal actuation of these valves satis-fies the test requirement of fail-safe testing.
These valves operate to the position required to fulfill their funct-ion by de-energizing the electrical power supply and/or venting off the actuator air supply which is essentially the same as loss of actuator power.
ALTERNATE TESTING:
AG indicated above.
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VALVE RELIEF REQUEST NUMBER:
V-4 SYSTEM:
Feedwater Coolant Injection VALVE:
1-CN-701 CLASS / CATEGORY:
2B FUNCTION:
Condensate watar supply to the off-gas recombiner cor. denser.
TEST REQUIPEMENT:
Category A ard B valves shall be exercised once every 3 months.
BASIS FOR RELIEF:
Exercising this valve during plant oper-ation will cause the off-gas system to trip which will lead to a loss of main condenser vacuum and turbine trip,ible Partial stroke testing is not poss for valves of this design.
ALTERNATE TESTING.
Exercise valve during cold shutdown.
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VALVE RELIEF REQUEST NUMBER:
V-5 SYSTEM:
Feedwater Coolant Injection (FWCI)
VALVES:
1-MW-7, 1-CN-67 CLASS / CATEGORY :
2B FUNCTION:
Condenser hotwell level control valves.
TEST REQUIREMENT:
Category A and B valves shall be exercised once every 3 months.
BASIS FOR RELIEF:
These valves modulate continuously to maintain the condenser hotwell level in an operating band. They are not required to be full stroke exercised since they are level control valves.
They do not receive any safety actuating signal from FWCI.
Both valves are controlled from one level controller which, by design does not permit fully stroking individual valves.
The remote valve position indication in the control room does not give positive open or closed valve position, but rather per-cent open.
During the quarterly operability
/
surveillance test of the Emergency Condensate Transfer (ECT) pump, hotwell level is lowered approximately 9 inches to accomodate the extra condensate water. While lowering the hotwell level, the reject valve (1-CN -67) opens from the throttled position to full open, while the make-up valve (1-MW-7) closes fully from the throttled position. After the ECT pump surveillance is completed and the hotwell is filled, the level controller is adjusted to maintain the hotwell at normal operating level.
At this time, the reject valve opens fully and the make-up valve closes until the hotwell is at the normal level. This quarterly exercise of stroking the valves from a throt-tied position to the fully opened and closed position, demonstrates proper valve operabil-ity and meets the intent of the test require-ment.
In addition to the above, both valve actuators are fail-safe tested to the closed position during cold shudown.
ALTERNATE TESTING:
None.
(
1 i%)
VALVE RELIEF REQUEST NUMBER:
V-6 SYSTEM:
Feedwater Coolant Injection (FWCI) i VALVES :
1-FW-2A, 1-FW-2B, 1-FW-2C.
CLASS / CATEGORY:
2C l
FUNCTION:
Reactor Feed Pump Discharge Check Valves TEST REQUIREMENT:
Check valves shall be exercised at least once every 3 months.
BASIS FOR RELIEF:
Two of the three Feed pumps are running during normal reactor power operation.
Exercising these valves re@ ires cycling each pump which causes feedwater pressure and flow fluctuations, which may place the plant in an unstable condition.
ALTERNATE TESTIMG:
Verify that the check valves open upon pump starting during reactor startup at cold shutdown and during pump rotation.
Valve closure is verified by the Plant p)
Equipment Operators during routine oper-s ator rounds by observation of suction and discharge pressures and reverse rotation of an idle pump's shaft.
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VALVE RELIEF REQUEST NUMBER:
V-7
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Feedwater Coolant Injection (FWCI)
VALVES:
Feedwater Blocking Valves 1-FW-4A, 1-FW-4B, 1-FW-4C, and Feedwater Control Valves 1-FW-5A, 1-FW-5B, 1-FW-5C.
CLASS / CATEGORY :
2B TEST REQUIREMENT:
Category A and B valves shall be 1
exercised once every 3 months.
BASIS FOR RELIEF:
Exercisin these valves during power op-f eration d srupts the balanced feedwater flow to the reactor vessel and will cause reactor vessel water level fluctuations.
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ALTERNATE TESTING:
Exercise valves at cold shutdowns.
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VALVE RELIEF REQUEST NUMBER:
V-8 SYSTEM:
Feedwater Coolant Injection (FWCI)
VALVES:
1-FW-9A, 1-FW-9B, 1-FW-10A, 1-FW-10B CLASS / CATEGORY:
LAC FUNCTION:
Feedwater system inside/outside contain-ment isolatlon check valves.
TEST REQUIREMENT:
Check valves shall be exercised at least once every 3 months.
BASIS FOR RELIEF:
These valves remain open during normal power operation supplying feedwater to the reactor vessel. Exercising these valves requires disruption of the feed-water to the reactor vessel, which can-not be done during power operation.
ALTERNATE TESTING:
Verify that the check valves are open by observation of reactor vessel level changes and feedwater flow instrumen-()
tation. Verify that the valves are closed at refuel outages during performance of Appendix J type C Local Leakrate Testing.
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VALVE RELIEF REQUEST j
NUMBER:
V-9 SYSTEM:
Various VALVES:
Category A and AC Valves FUNCTION:
To ensure containment integrity in event of containment isolation.
TEST REQUIREMENT:
Category A and AC valves which are containment i
isolation valves shall be leak tested in accordance with Federal Regulation 10 CFR 50 Appendix J.
ADDITIONAL TEST Valves that are referenced in the IST Valve REQUIREMENT:
List that receive a LLRT (local leak rate test) as an Alternate Test shall have the following additional test requirements applied:
1)
Leakage rate measurements shall be compar-ed with the previous measurements and with the maximum permissible rates as specified in the Appendix J Submittal.
O 2)
Valves exceeding the maximum leakage rates shall be repaired or replaced and retest-ed.
3)
For valves 6 inches nominal pipe size and larger if a leakage rate exceeds the rate determ1ned by the previous test by an ammount that reduces the margin between measured leakage rate and the maximum per-missible rate by 50 % or greater, the test frequency shall be doubled.
The tests shall be scheduled to coincide with a cold shutdown until corrective action is taken, at which time the original test frequency shall be resumed. If tests show a leakage rate increasing with time, and a project-ion based on three or more tests indicates that the leakage rate will exceed the max-imum permissible leakage rate by grter than 10%, the valve shall be repairs. or replaced and retested.
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O VALVE RELIEF REQUEST NUMBER:
V-10 SYSTEMt Feedwater Coolant Injection (FWCI)
VALVES:
1-FW-14A, 1-FW-14B, 1-FW-14C.
CLASS / CATEGORY:
2B FUNCTION:
Reactor feed pump minimum flow recirc-ulation to the main condensers.
TEST REQUIREMENT:
Category A and B valves shall be exercised once every 3 months.
BASIS FOR RELIEF:
These valves are opened only during starting of the reactor feedwater pumps or partially open at low flow conditions to prevent overheating of the pumps. They do not receive any safety related actuat-ing signal from FWCI. Stroke time is not an appropriate reference parameter for valves serving this function. Exercising these valves during power operation dis-rupts the balanced feedwater flow to the
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reactor vessel.
ALTERNATE TESTING:
Exercise these valves at cold shutdown.
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-V-11 SYSTEM:
Control Rod Drive Hydraulic VALVES:
302-19A, 302-19B / 302-19C, 302-19D CLASS / CATEGORY:
2B FUNCTION:
Master Scram / ATWS Solenoid Valves VALVES:
302-20A, 302-20B.
CLASS / CATEGORY :
2B FUNCTION:
Scram Discharge Volume Vent and Drain Solenoids.
VALVES:
301-122A, 301-122B, 301-122C.
CLASS / CATEGORY:
2C FUNCTION:
Scram Piolt Air Header Check Valves VALVES:
305-114
- CLASS / CATEGORY:
2C FUNCTION:
Hydraulic Control Unit to Scram Discharge Volume Check Valve.
VALVE:
305-115 *
- O CLASS / CATEGORY:
2C FUNCTION:
Charging Water Supply to Accumulator Check.
VALVE:
305-126
- CLASS / CATEGORY:
2B FUNCTION:
Scram Insert Air Operated Valve VALVE:
305-127
- CLASS / CATEGORY :
2B FUNCTION:
Hydraulic Control Unit Exhaust to Scram Discharge Volume Header Air Operated Valve.
VALVE:
305-117 *, 305-118
- i CLASS /CATEGON.
2B 1
FUNCTION:
Scram Solenoid Valves TEST REQUIREMENT:
Exercise for operability every 3 months.
BASIS FOR RELIEF:
Exercising these valves during power operation would require a reactor scram.
i ALTERNATE TESTING:
All valves will be exercised at cold shutdown.
- Denotes one of 145 Hydraulic Control Units j
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RELIEF REQUEST V-12 DELETED 1
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V-13 SYSTEM:
Control Rod Drive Hydraulic VALVES:
305-120 *, 305-121 *, 305-122 *, 305-123*
CLAS67 CATEGORY:~
Control Rod Withdrawal / Insert Solenoids 2B FUNCTION:
VALVES:
305-137*, 305-138*.
CLASS / CATEGORY:
2C FUNCTION:
Control Rod Withdrawal / Insert Checks.
TEST REQUIREMENT:
Exercise for operability once every 3 months.
BASIS FOR RELIEF:
These valves are operated weekly during Stuck Control Rod Testing in accordance with Tech. Spec.
4.3.A.2.
Satisfactory operation of a control rod verifies proper valve operability.
ALTERNATE TESTING:
None. These valves operate in the course of normal plant operation at a frequency that exceeds the exercising requirements O
of the Code.
Denotes one of 145 hydraulic control units.
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C' VALVE RELIEF REQUESTS NUMBER:
V-14 Control Rod Drive HydrauliE'.
SYSTEM:
VALVES :
1-SDV-1N, 1-SDV-2N, 1-SDV-1S, 1-SDV-2S, 1-SDV-3N, 1-SDV-3S, 1-SDV-4N, 1-SDV-4S.
CLASS / CATEGORY:
2A i
FUNCTION:
Scram Discharge Volums Hoader Vent and Drain Valves.
TEST REQUIREMENT:
Exercise for operability every 3 months.
BASIS FOR RELIEF:
System design does not pesmit normal actuation during power operation without initiating a reactor scram. A test circuit allows for exercising these valves through an alternate vent path during power operation, but due to system design, the stroke times are not repre-sentative of normal operation.
ALTERNATE TESTING:
Exercise for operability via the test circuit every 3 months and stroke time
(~g test at cold shutdown by manually init-s/
iating a scram.
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'1 VALV[j> RELIEF,EQUESTS R
NUMEER:
V-15',
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SYSTEM:
Low Pressure \\ Coolant Injection (LPCI)
VALVE 1 1-LP-11A CLASS / CATEGORY:
1C FUNCTION:
LPCI System
'A' inside containment injection check valve.
TEST REQUIREMENT:
Check valves shall be exercised every 3 months.
Exercising this valve requires pumping BASIS FOR RELIEF:_
LPCI water into the reactor vessel. This is not possible during reactor power op-eration or at cold shutdown because of pressure differentials and the high vol-ume of water injected.
ALTERNATE TESTING:
Exercise this check valve at refueling outages when the reactor vessel water level is sufficiently lowered to accomo-O date the rapid vessel' level increase.
(Reference SER - Amendment 64).
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VALNE RELIEF REQUESTS NUMBER:
V-16 SYSTEM:
Low Pressure Coolant Injection (LPCI)
VALVE:
1-LP-11B CLASS / CATEGORY:
1C FUNCTION:
'B' inside containment injection check valve.
TEST REQUIREMENT:
Check valves shall be ext.rcised every 3 months.
BASIS FOR RELIEF:
Exercising this valve requires pt mping LPCI water into the reactor vessel. This is not possible at reactor power due to'.,
pressure differentials.
I ALTERNATE TESTING:
Exercise this valve at refuel outages when the reactor vessel level is suf-ficiently lowered to accomodate the rapid vessel level increase and exercise the valve at cold shutdown when the Shutdown (s
cooling System is in operation.
(
Reference:
SER Amendment 64).
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VALVE RELIEF REQUESTS NUMBER:
V-17 SYSTEM:__
Core Spray VALVES:
1-CS-6A, 1-CS-6B CLASS / CATEGORY:
1C FUNCTION:
Inside Containment Injection Check Valves TEST REQUIREMENT:
Check valves shall be exercised every 3 months.
BASIS FOR RELIEF:
Exercising these valves requires inject-ing Core Spray water into the reactor vessel. This is not possible at reactor power or cold shutdown because of pres-sure differentials and the high volume flow rates.
ALTERNATE TESTING:
Exercise check valves at refueling out-ages when the reactor vessel water level is sufficiently lowered to accomodate the rapid vessel level increase. (
Reference:
O SER Amendment 64).
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O VALVE RELIEF REQUEST NUMBER:
V-18 SYSTEM:
Standoy Liquid Control VALVES:
1-SL-7 / 1-SL-8 CLASS / CATEGORY:
1AC / 1AC FUNCTION:
Combined discharge injection check valves TEST REQUIREMENT:
Check valves shall be exercised every 3 months.
BASIS FOR RELIEF:
There are no provisions for manually stroking these valves. Hydraulic stroking requires the firing of a squib valve and pumping water into the reactor vessel.
ALTERNATE TESTING:
These check valves will be exercised each refueling outage when the standby liquid system is tested by pumping water into the reactor vessel. (
Reference:
SER Am7ndment 64).
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VALVE RELIEF REQUESTS i
NUMBER:
V-19 SYSTEM:
Main Steam VALVES:
1-MS-5, 1-MS-6 CLASS / CATEGORY:
1A FUNCTION:
Main Steram Line Bypass Isolation Valves TEST REQUIREMENT:
Exercise for operability every 3 months.
BASIS FOR RELIEF:
These valves are normally closed and are opened only during startup for equalizing steam pressure around the MSIV's.
ALTERNATE TESTING:
Exercise for operability at cold shutdown.
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V-20 SYSTEM:
Main Steam Relief Discharge Line to Torus VALVES:
1-MS-107A thru F, 1-MS-111A thru F, 1-MS-112A thru F.
CLASS / CATEGORY :
3C FUNCTION:
Main Steam Relief Discharge Line to Torus Vacuum Breakers TEST REQUIREMENT:
Check valves shall be exercised at least once every 3 months.
BASIS FOR RELIEF:
These valves can only be exercised man-ually by hand when access to the drywell is available.
ALTERNATE TESTING:
Exercise these valves at cold shutdown when access to the containment is avail-able.
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V-21 SYSTEM:
Isolation Condenser Makeup Water VALVE:
1-IC-11 / 1-FIRE-48 / 1-MW-59 CLASS / CATEGORY:
3C / Fire Protection C / ANSI B31.1 C FUNCTION:
Makeup water to the shell side of the Isolation Condenser.
TEST REQUIREMENT:
Exercise for operability every 3 months.
BASIS FOR RELIEF:
Exercising these check valves requires filling the shell side of the isolation condenser which will cause the level to increase above the normal operating band.
This cannot be done except at reactor refueling when it is possible to drain the shell side to a low level and refill it to the operating band.
ALTERNATE TESTING:
Exercise these valves at reactor refueling.
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VALVE RELIEF REQUEST NUMBER:
V-22 SYSTEM:
Service Water VALVE:
1-SW-9 CLASS / CATEGORY:
3B FUNCTION:
Service water stop valve to the Turbine Building Closed Cooling Water Heat Ex-changers.
TEST REQUIREMENT:
Exercise for operability every 3 months.
BASIS FOR RELIEF:
Closing this valve disrupts service water cooling to the Turbine Building Closed Cooling Water Heat Exchangers and will cause overheating of the Turbine Lube oil System during power operation.
ALTERNATE TESTING:
Exercise this valve at cold shutdowns.
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O VALVE RELIEF REQUESTS NUMBER:
V-23 SYSTEM:
Emergency Service Water (ESW)
VALVES :
1-LPC-4A, 1-LPC-4B CLASS / CATEGORY :
3B FUNCTION:
LPCI Heat Exchanger outlet throttle valves.
TEST REQUIREMENT:
Exercise Category A and B valves fully open and closed and measure valve stroke time.
BASIS FOR RELIEF:
Actuating power for these valves is only available when an Emergency Service Water Pump is in operation. Fully opening these throttle valves causes the ESW pump to run-out which may result in damaging the pump. Stroke time testing these valves cannot be done due to the type valve csntroller used in this installation.
ALTERNATE TESTING:
Exercise the valves to a position greater 1
than 25% open each time the ESW pump quarterly operability surveillance is performed. 25% open valve travel is more than the maximum open valve position l
1 that is required for these valves to fulfill their intended function without causing any damage to the ESW pumps, i
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VALVE RELIEF REQUESTS NUMBER:
V-24 SYSTEM:
Shutdown Cooling VALVES :
1-SD-1, 1-SD-2A, 1-SD-2B, 1-SD-3A, 1-SD-3B, 1-SD-4A, 1-SD-4B, 1-SD-5.
CLASS / CATEGORY :
Various FUNCTION:
Shutdown cooling system power operated valves and pump discharge check valves.
TEST REQUIREMENT:
Power operated valves and check valves shall be Exercised for operability every 3 months.
BASIS FOR RELIEF:
These valves are normally closed during reactor power operation. Interlocks pre-vent opening the isolation valves or starting the Shutdown Cooling Pumps when reactor recirculation loop temperature is greater than 350 degrees F.
r-ALTERNATE TESTING:
Exercise for operability at reactor 4
refueling outages and at cold shutdown if the shutdown cooling system is placed in operation.
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VALVE RELIEF REQUEST NUMBER:
V-25 SYSTEM:
Reactor Building Closed Cooling Water (RBCCW)
VALVES:
1-RC-6 and 1-RC-15.
1 CLASS / CATEGORY :
3AC / 3A.
FUNCTION:
Reactor Building Closed Cooling Water Supply and Return Valves.
TEST REQUIREMENT:
Exercise check valves and power operated valves every 3 months.
BASIS FOR RELIEF:
Exercising these valves disrupts cooling water to the reactor recirculation pumps and may cause overheating of the pump motors and damage the pump seal assemblies. If the valves 1
were to fail in the closed position during testing, drW ell ambient air temperature would increase which would increase drywell air (s ')
pressure resulting in a reactor scram, since j
RBCCW water also provides cooling to the 4
drywell air coolers.
ALTERNATE TESTING:
Exercise these valves at cold shutdown and reactor refueling outages.
O VALVE RELIEF REQUESTS NUMBER:
V-26 SYSTEM:
Reactor Recirculation VALVES:
1-RR-2A, 1-RR-2B, 1-RR-5A CLASS / CATEGORY:
1B FUNCTION:
Reactor Recirculation System power operated valves.
TEST REQUIREMENT:
Exercise for operability every 3 months.
BASIS FOR RELIEF:
Exercising these valves requires reducing reactor power, securing the reactor recirc-ulation pumps and entering an LCO for single recirculation pump operation.
ALTERNATE TESTING:
Exercise these valves during cold shutdown and at reactor refueling when the recirculation pumps can be secured.
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O VALVE RELIEF REQUESTS NUMBER:
V-27 SYSTEM:
Reactor Water Clean-up VALVE:
1-CU-5 CLASS / CATEGORY:
1A FUNCTION:
Auxiliary' Clean-up Pump Suction Valve.
TEST REQUIREMENT:
Exercise for operability every 3 months.
BASIS FOR RELIEF:
This valve is normally closed and in its accident position during normal power op-eration. Opening this valve at power causes pressure and flow transients in the clean-up system.
ALTERNATE TESTING:
Exercise this valve at cold shutdown when the auxiliary clean-up pump la placed in operation.
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VALVE RELIEF REQUESTS NUMBER:
V-28 SYSTEM:
Standby Gas Treatment VALVES:
All CLASS / CATEGORY:
3B FUNCTION:
Standby Gas Treatment Sequence Valves TEST REQUIREMENT:
Exercise for operability every 3 months.
BASIS FOR RELIEF:
These valves operate automatically during the start sequence of the standby gas treatment systems. Individual stroking of these valves is not possible. Observation of their proper operation during starting of the standby gas systems satisfies the exercising test requirements.
ALTERNATE TESTING:
These valves will be exercised and stroke O,
timed as a group at least every 3 momths.
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VALVE RELIEF REQUESTS NUMBER:
V-29 SYSTEM:
Head Spray VALVES:
1-HS-4 / 1-HS-5 CLASS / CATEGORY:
lA / 1AC FUNCTION:
Head Spray Inner and Outer Containment Isolation Valves TEST REQUIREMENTS:
Exercise for operability every three months.
BASIS FOR RELIEF:
These valves are normally closed and are opened only to admit water to cool the reactor vessel head and reactor internals before removal of the closure head during refuel outages.
ALTERNATE TESTING:
Exercise for operability at reactor refueling outages.
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VALVE RELIEF REQUEST NUMBER:
V-30 SYSTEM:
Drywell Nitrogen Compressor Supply VALVES :
1-AC-50 / 1-AC-162 (Formerly 1-IA-68 / 1-IA-69)
CLASS / CATEGORY:
3A / 3AC FUNCTION:
Drywell nitrogen compressor supply to the drywell TEST REQUIREMENT:
Exercise power operated valves and check valves every 3 months.
BASIS FOR RELIEF:
Closing these valves isolates the drywell nitrogen supply system that is required for operation of vital safety related valves inside the drywell (e.g., MSIV's and APR relief valves).
ALTERNATE TESTING: Exercise these valves at cold shutdown and reactor refueling.
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O VALVE RELIEF REQUESTS NUMBER:
V-31 SYSTEM:
Reactor Water Clean-up VALVE:
1-CU-2A J
CLASS / CATEGORY:
lA FUNCTION:
Bypass valve around clean-up supply isolation valve 1-CU-2.
TEST REQUIREMENT:
Exercise for operability every 3 months.
~~ BASIS FOR RELIEF:
This containment isolation valve remains closed during all modes of plant oper-1 i
ation. The valve is opened only when equalizing around supply isolation valve l-CU-2 when placing the system in oper-j ation. Failure of this valve to close during operability testing will result in a loss of containment isolation.
ALTERNATE TESTING:
Exercise for operabilit at cold shut-(])
down and reactor refuel ng.
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V-32 SYSTEM:
Various VALVES:
Category A and AC Valves FUNCTION:
To ensure containment integrity in event of containment isolation.
TEST REQUIREMENT:
Category A and AC valves which are contain-ment isolation valves shall be leak tested in accordance with Federal Regulation 10 CFR 50 Appendix J.
BASIS FOR RELIEF:
Containment isolation valves applicable to this relief request as specified in the IST Valve List do not receive an Appendix J type C Local Leak Rate Test. Relief Requests for exemption from leak testing these valves are not given in this IST Program, but are given in the Millstone Unit 1 Appendix J Program under separate docket.
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V-33 SYSTEM:
Reactor Water Clean-up VALVE:
1-CU-29 CLASS / CATEGORY :
1AC FUNCTION:
Clean-up system return to feedwater check TEST REQUIREMENT:
Check valves shall be exercised at least once every J months.
BASIS FOR RELIEF:
This normally open check valve cannot be test-ed in a manner that verifies that the disk travels to the seat promptly on cessation of flow. No position indicating devices are in-stalled on this valve. This valve is presumed to be exercised quarterly during the Contain-ment Isolation Valve surveillance when valve 1-CU-28 is cycled open and closed. Appendix
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'J' type C local leakrate testing is not performed on this valve due to the existing piping configuration, but local leakrate test-ing is performed on the outside containment isolation valve 1-CU-28. Exemption requests have been submitted with the Appendix
'J' Program identifying the justification bases for valve 1-CU-29.
ALTERNATE TESTING:
Verify that check valve 1-CU-29 opens by observing clean-up system flow upon return of the clean-up system to operation after per-forming the gaarterly containment isolation Valve operability surveillance and perform a water leakage test during reactor refueling i
outages when the clean-up system is out of service that verifies closure of the valve disk.
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V-34 SYSTEM:
Post Accident Sample i
VALVES:
1-PAS-17, 1-PAS-20, 1-PAS-24, 1-PAS-25 CLASS / CATEGORY:
2A FUNCTION:
Containment Isolation SYSTEM:
Reactor Coolant Sample VALVES:
1-RR-36, 1-RR-37 CLASS / CATEGORY:
1A FUNCTION:
Containment Isolation SYSTEM:
Hydrogen and Oxygen Analyzer VALVES:
1-AC-194, 1-AC-195, 1-AC-196, 1-AC-197 1-AC-198, 1-AC-199, 1-AC-205, 1-AC-206 CLASS / CATEGORY:
2A FUNCTION:
Containment Isolation SYSTEM:
Drywell Nitrogen Compressor Suction VA LVES :
1-AC-40, 1-AC-41 CLASS / CATEGORY:
2A FUNCTION:
Containment Toolation SYSTEM:
Torus to Drywell Pumpback System VALVES:
1-AC-133, 1-AC-134, 1-AC-139, 1-AC-140.
CLASS / CATEGORY :
2A FUNCTION:
Containment Isolation TEST REQUIREMENT:
Valves with remote position indication shall be observed at least once every 2 years to verify that valve operation is accurately indicated.
BASIS FOR RELIEF:
These solenoid actuated valves have in-ternal position indicators (magnetic reed switches). The valve stems are also in-ternal and cannot be observed for move-ment.
ALTERNATE TESTING:
Open valve position is verified by flow through the system. Closed valve position is verified by cessation of flow and further verified by performance of Appen-dix J type C Local Leak Rate Testing.
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O VALVE RELIEF REQUESTS NUMBER:
V-35 SYSTEM:
Transversing In-Core Probe (TIP)
VALVES:
Tip Squib Valves No.
1,2, 3 and 4.
CLASS / CATEGORY :
2AD FUNCTION:
Explosively Actuated Shear Valves TEST REQUIREMENT:
At least 20% of the charges in explosively actuated valves shall be removed, fired, and replaced every 2 years with charges from a fresh batch.
A sample charge from the fresh batch shall have been tested satisfactorily.
Charges shall not be older than 10 years.
If a charge fails to fire, all charges with the same batch number shall be removed, destroyed and replaced with charges from a fresh batch from which a sample charge shall have been tested satisfactorily.
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BASIS FOR RELIEF:
The test frequency requirements cannot be maintained due to the shelf life of the explosive charges used in this system. The limited guaranteed operating lif9 of these charges is five years. Testing 20% of the 4 valves every 2 years cumulatively tests all 4 in 8 years which exceeds the shelf life.
ALTERNATE TESTING:
All 4 charges will be removed and fired every 4 years. A sample charge from a fresh batch shall have been tested sat-isfactorily. If a charge fails to fire, all charges with the same batch number will be re.noved, destroyed and replaced with a fresh batch from which a sample charge shall have been tested satis-factorily.
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VALVE RELIEF REQUESTS NUMBER:
V-36 SYSTEM:
Control Rod Drive Hydraulic
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i VALVES:
302-19A, 302-19B / 302-19C, 302-19D /
302-20A, 302-20B.
CLASS / CATEGORY:
2B FUNCTION:
Master Scram / ATWS Scram / Scram Discharge Volume Vent and Drain Solenoid Valves.
TES_T REQUIREMENT:
The stroke time of all power operated valves shall be measured to the nearest second, for stroke times 10 seconds or less.
BASIS FOR RELIEF:
These valves cannot be full-stroke-tested since they do not have any remote position indication. Valve stem position cannot be visually observed since the valve stem is internal to the valve body.
ALTERNATE TESTING: Valve operability shall be demonstrated satisfactorily provided that:
(1) Valves 302-19A and 19B energize and vent air from the scram pilot air header.
(2) Valves 302-19C and 19D energize and vent air from the scram pilot air header.
(3) Valves 302-20A and 20B energize and vent air from the scram discharge vent and drain headers.
The test freguency shall be at cold shutdown as identified in relief request V-11.
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VALVE RELIEF REQUESTS NUMBER:
V-37 SYSTEM:
Control Rod Drive Hydraulic VALVES:
305-117*
305-118*
CLASS / CATEGORY:
2B FUNCTION:
Scram Pilot Solenoid Valves VALVES:
305-126* / 305-127*
CLASS / CATEGORY :
2B FUNCTION:
Scram Insert / Scram Exhaust Air Operated Valves.
TEST REQUIREMENT:
The stroke time of all power operated valves shall be measured to the nearest second for valves with stroke times less than 10 seconds.
BASIS FOR RELIEF:
The scram pilot solenoid valves do not have remote valve position indicators.
The valve stems are also internal and cannot be observed for movement. The scram insert / exhaust air operated valves do not have individual valve position indicators for full stroke time testing.
Limit switches on each valve energize the f]
Rod Scram Light on the Control Room full-core display panel when both valves are fully opened during a scram. At cold shutdown when the reactor mode switch is placed in the shutdown position, a scram signal is initiated which opens these valves. Following each refueling outage, each individual control rod is subjected to scram insertion time testing fron the fully withdrawn position as required by Tech. Spec.
4.3.C.
The scram insertion time is based on de-energizing the scram pilot valve solenoids, the rod scram light (valves 305-126 and 305-127 open-ing) and the rod bottom position indic-ation. This test method verified that the scram pilot valve solenoids and the scram insert and scram exhaust air operated valves actuate to fully insert the control rod within the time limits re-quired by Technical Specifications.
ALTERNATE TESTING:
These valves will be exercised at cold shutdown by initiation of a reactor scram and exercised following each reactor refueling i
by satisfactory performance of control rod i
scram insertion time surveillance test-l ing.
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- DENOTES ONE OF 14 5 CRD HYDRAULIC CONTROL UNITS 1
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V-38 SYSTEM:
Reactor Building Closed Cooling Water i
VALVE:
1-RC-39 CLASS / CATEGORY:
3B FUNCTION:
Shutdown Cooling Heat Exchanger RBCCW 1
Outlet Throttle Valve TEST REQUIREMENT:
Category A and B valves shall be exercised once every 3 months.
BASIS FOR RELIEF:
This valve is only throttled open when 1
the shutdown cooling system is in oper-ation and is not required to be fully stroked open to perform its intended
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function. Fully opening this valve with the RBCCW system in the normal power operation lineup diverts too much flow through the shutdown cooling heat exchan-gers and runs the RBCCW pur.ps out. Part stroke opening this valve may also run the pump out if the valve is opened too far.
l ALTERNATE TESTING:
Full stroke exercise this valve at cold shutdown when the RBCCW system is lined up for service to the shutdown cooling heat exchangers.
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OV VALVE RELIEF REQUESTS NUMBER:
V-39 SYSTEM:
Drywell Nitrogen Compressor VALVES:
1-AC-48 / 1-AC-49 CLASS / CATEGORY:
B31.1 C / 3 C FUNCTION:
Drywell Compressor Discharge to Drywell VALVES:
1-AC-51, 1-AC-70A, 1-AC-70B CLASS / CATEGORY:
3C FUNCTION:
Secondary Nitrogen Gas bottle Supply TEST REQUIREMENT:
Check valves shall be exercised every 3 months.
BASIS FOR RELIEF:
Exercising these valves requires securing the drywell nitrogen compressors and bleeding down the header to initiate the secondary nitrogen gas supply. This may O
result in a potential inadvertent Main Steam Isolation Valve closure and sub-sequent reactor scram.
ALTERNATE TESTING:
All valves will be exercised at cold shutdown during an operability test of initiating the secondary nitrogen gas supply system while securing the drywell nitrogen compressors.
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VALVE RELIEF REQUESTS NUMBER:
V-40 SYSTEM:
Drywell Nitrogen Supply VALVES:
1-AC-164A thru F, 1-AC-165A thru F.
CLASS / CATEGORY:
3 / NONE FUNCTION:
ADS (Automatic Depressurization System) accumulator check valves.
TEST REQUIREMENT:
NONE - Delete from IST Program.
BASIS FOR RELIEF:
The need for inclusion of these valves into the IST Program has been reviewed by Plant Engineering. The need for leak testing these valves was initially in-stituted because of IE Bulletin 80-01 as a result of the seismically unqual-()
ified portion of the nitrogen supply line piping (piping inside the drywell This portion to the ADS check valves)ically qualified of piping has been seism during the 1987 refueling outage as part of the IE Bulletin 79-14 hanger modif-ication program. These modifications alleviate any further concerns associated with the evaluation of seismic events.
The secondary nitrogen gas supply along with the supply piping to each one of the ADS valves is all seismically qualified.
ALTERNATE TESTING:
None required.
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O VALVE RELIEF REQUESTS NUMBER:
V-41 SYSTEM:
Low Pressure Coolant Injection (LPCI)
VALVES:
1-LP-24A, 1-LP-24B, 1-LP-24C, 1-LP-24D CLASS / CATEGORY:
2AC FUNCTION:
LPCI Pumps A,B,C and D Min Flow Recirc To Torus Check TEST REQUIREMENT:
Check valves shall be exercised every three months.
BASIS FOR RELIEF:
These pump min-flow check valves are presumed to ha cycled open each time a respective LPCI pump is started. Due to the piping design and location of these check valves, there is no positive method
({)
of verifying that these valves either open or close upon pump starting or stopping due to operation of motor oper-ated min-flow control valve 1-LP-26A or 1-LP-26B.
ALTERNATE TESTING:
All 4 of these valves will be disassembl-ed dhring the next scheduled refueling outage for internal visual inspection and manually exercised to verify operability.
At subsequent refuel outages, one check valve will be disassembled for inspection on a rotating basis.
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VALVE RELIEF REQUEST NUMBER:
V-42 SYSTEM:
Low Pressure Coolant Injection VALVES:
1-LP-46, 1-LP-47 j/
CLASS / CATEGORY:
2AC FUNCTION:
Condensate' Transfer to LPCI System Keep Fill Check Valves.
TEST REQUIREMENT:
Check valves shall be exercised at least once every 3' months.
Category A,v'alves shall be leak tested at least once every 2 years.
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BASIS FOR RELIEF:
These check. valves provide makeup water to the LPCI system to,ensureithat the LPCI system is
(')s finl of water. Prior to starting a LPCI pump s_
daring the quarterly pump operability surveil-lance, open position of the keep fill check valves is verified by observation of keep fill prescure being maintained on the LPCI system.
Closed valve position cannot practicably be verified during operation of the LPCI pumps These valves do not fall under the criteria of 10 CFR 50 Appendix A General Design Criteria 54-57 and are not considered to be containment isolation valves and are therfore not subject to 10 CFR 50 Appendix J leak test require-ments. However, these check valves are class-ified as Category A valves based on their location in the LPCI system such that' seat tightness should be maintained on not breaking the water sedl in any torus water sealed pene-tration in 30 days (Ref: Millstone Unit 1 Appendix Jitubmittal).
Leakage limits will be set at 1.5 gpm total through each pair of valves at pressures
> 1. l(4 3 psig). This is a conservative pro-Tection not set by off-site dose consequences as calculated by Radiation Assessment, because water leakage in these lines is not considered (V'%
to be limiting in terms of off-site dose con-sequences. In addition to the above, the 1.5 gpm leakage during LPCI pump operation will not degrade ECCS flow.
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ALTERNATE TESTING:
Verify operation of the keep-fill valves by i
observing keep fill pressure prior to LPCI pump starting during the quarterly pump oper-(
ability surveillance test and-perform a seat leakage test to the criteria specified in the
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above during refueling outages.
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VALVERbLIEFREQUEST NUMBER:
V-43 i
SYSTEM:
Core Spray A and B VALVES:
1-CS-19A, 1-CS-20A, (Core Spray A) 1-CS-19B, 1-CS-20D, (Core Spray B) t~
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b CLASS / CATEGORY:
2AC FUNCTION:
Condensate Transfer to Core Spray A and B Systems Fill Check Valves.
TEST AEQUIREMENT:
Check valves shall be exercised at least once evr:y 3 months.
Category A valves shall be leak tested at i
least once every 2 years.
BASIS FOR RELIEF:
These check valves provide makeup water to the
]h Core Spray systems tc gnsure that they are full of water. Prict to starting a Core Spray pump during the quarterly pump operability, j
surveillance,is verified by observation ofopen position.of the k check valves keep fill pressure.
Closed valve position cannot practicably be ver fied during oper-ation of the Core Spray pamps.
These valves do not fall under the criteria of 10 CFR 50 Appendix A General Design Criteria 54-57 and are not considered to be containment isolation valves and are not subject to 10 CFR 50 hppendix J leak test requirements. However, these check valves are classified as Categogy A valves based on their location in the Core Spray system such that seat tightness should be maintained on not breaking the water seal in any torus water sealed penetration in 30 days (Ref: Millstone Unit 1 Appendix J Submittal).
Leakage limits will be set at 1.5 gpm total through each pair of valves at pressures
> 1.1(43 psig). Thi2 is a conservative pro-Jection not set by off-site dose consequences as calculated by Radiation Assessment, because water leakage in these lines is not considered s,)
to be limiting in terms of off-site dose con-sequences. In addition to the above, the 1.5 gpm leakage during Ccre Spray pump operation will not degrade ECCS flow.
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ALTERNATE TESTING:
Verify operation of the keep-fill valves by observing keep fill pressure prior to core Spray pump starting during the quarterly pump operability test and perform a seat leakage test to the criteria specified in the above during refueling outages.
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O VALVE RELIEF REQUEST NUMBER:
V-44 SYSTEM:
Core Spray and LFCI VALVES:
1-CS-25A, 1-CS-25B, 1-LP-52A, 1-LP-25B CLASS / CATEGORY:
2B FUNCTION:
Cooling Water to Core Spray and L7CI Pump Motor Bearing 011 Coolers TEST REQUIREMENT:
The stroke time of all power operated valves shall be measuresd to the second.
BASIS FdR RELIEF:
These solenoid valves open upon starting a Core Spray or LPCI pump to provide cooling water to the motor bearing oil coolers. No remote position indication is installed on solenoid valves of this s
s) design nor is the valve stem visible for observation of valve stem movement.
ALTERNATE TESTING:
Proper valve operation shall be verified by observation of cooling water pressure supplied to the motor bearing oil coolers during the quarterly pump operability surveillance.
O VALVE RELIEF REQUEST NUMBER:
V-45 SYSTEM:
Reactor Water Clean-up (RWCU)
VALVE:
1-CU-69 CLASS / CATEGORY:
ANSI B31.1 / C FUNCTION:
RWCU System Relief Valve Vent Line to Torus Check TEST REQUIREMENT:
Check valves shall be exercised at least once every 3 months.
BASIS FOR RELIEF:
This valve is in the RWCU system pressure relief discharge line to the torus. This check valve serves no other safety relat-ed function other than containment isolation. There is no possible method
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of-full stroke or partial stroke exercise operation that can be performed on this check valve due to the system design.
(
Reference:
Appendix J exemption request for penetration X-212).
ALTERNATE TESTING:
Appendix J type A test (ILRT).
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VALVE RELIEF REQUEST NUMBER:
V-46 SYSTEM:
Transversing In-Core Probe (TIP)
VALVE:
TIP Purge Check Valve CLASS / CATEGORY:
2AC FUNCTION:
TIP Nitrogen Purge Containment Isolation Valve TEST REQUIREMENT:
Check valves shall be exercised at least once every 3 months.
BASIS FOR RELIEF:
This check valve remains closed during normal power operation and is opened only when the TIP machines are in use, usually on a monthly basis. This 3/8" check valve provides no safety function
(])
other than containment isolation.
ALTERNATE TESTING:
This caeck valve will be exercised open during operation of the TIP machines and will be verified closed during local leak testing in accordance with 10 CFR 50 Appendix J type C tests during refuel outages.
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VALVE RELIEF REQUEST NUMBER:
V-47 SYSTEM:
Diesel Air Start VALVES:
1-AS-1, 1-AS-2, 1-AS-3 CLASS / CATEGORY:
ANSI B31.1 / B FUNCTION:
Diesel air start solenoids and air start header vent solenoid valve J
TEST REQUIREMENT:
The stroke time for all power operated valves shall be measured to the nearest second.
BASIS FOR RELIEF:
These solenoid valves have no position indication nor is it possible to verify valve stem travel since the valve stem is internal to the valve body. Proper valve operation is verified by normal starting of the diesel during the bi-weekly diesel operability surveillance.
This surveillance procedure requires using either valvo 1-AS-1 or 1-AS-2 to start the diesel not both at the same time. Operation of the air start valves are on a rotative basis. The air start header vent solenoid valve 1-AS-3 is operated each time the diesel is started. Failure of the diesel to start indicates failure of this vent valve to properly actuate. The manual air start valve is used during refuel outages to start the diesel during overhaul testing, but not normally used for surveillance testing. This valve is exurcised every time the diesel is biweekly surveillance tested to roll the engine over slowly to pump over any lube oil that is collected on the upper piston after the test run.
ALTERNATE TESTING.
None. Proper operation of the air start solenoid valve assemblies and the air header vent solenoid are verified by starting of the diesel during the normal operability surveillance test required by i
O Technical Specifications.
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VALVE RELIEF REQUEST NUMBER:
V-48 SYSTEM:
Low Pressure Coolant Injection (LPCI)
VALVES:
1-LP-10A, Loop A injection valve 1-LP-10B, Loop B in;ection valve CLASS / CATEGORY:
1A (CIV/PIV).
FUNCTION:
LPCI Injection Motor Operated Valves.
TEST REQUIREMENT:
Containment Isolation Valves (CIV's) which also perform a reactor coolant pressure isol-ation (PIV) function shall, in addition to being tested in accordance with 10 CFR 50 Appendix
'J' leakrate test criteria, be seat leakage tested to verify their leak-tight integrity. Valve closure prior to seat leakage testing shall be by using the valve operator with no additional closing force applied.
BASIS FOR RELIEF:
Relief is requested from performing the Pressure Isolation Valve tests on the basis that these valves due to the system design, function in the course of normal plant oper-ation in a manner that demonstrates adequate
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seat leak-tightness.
The LPCI system is designed to inject water into the reactor vesse't, following a LOCA with the reactor coolant system depressurized. The LPCI low pressure piping interfaces with the high pressure piping upstream at valve 1-LP-9A(B) (See ref. <!vg. 25202-26008 sh.2).
The low pressure piping sides are each pro-tected by 3 valves in series on the high pres-sure side. These valves and their descriptions are as follows:
- 1) Swing check valves 1-LP-11A(B) inside the drywell.
- 2) Motor operated injection valves 1-LP-10A(B) located outside the drywell (nor-mally closed).
- 3) Motor operated globe "stop-check" valves 1-LP-9A(B) located upstream of 1-LP-i 10A(B).
The only potential of Inter-System LOCA (ISL) for the low pressure piping is based on a failure of check valves 1-LP-11A(B). Should this event occur, the low pressure piping would still be protected unless 1-LP-10A(B) and 1-LP-9A(B) were both open. Valve inter-O I
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locks prevent both valves being en when reactorpressureisabove350ps$ginthat:
Outboard injection valve 1-LP-9A(B) can only be opened if the inboard valve 1-LP-10A(B) is closed and inboard injection valve 1-LP-10A(B) can be opened only if the outboard injection is closed. In the event that valve 1-LP-9A(B)ils or if valves 1-LP-10A(B) the interlock fa leak, globe stop-check valve 1-LP-9A(B) would still have to fail before the low pressure piping experienced overpressure. In addition to the interlocks, the LPCI system has a Head-er High Pressure Alarm with a setpoint of 400 psig downstream ef the heat exchangers which alerts the control room operators to verify that valves 1-LP-10A(B) are closed and to bleed pressure to the torus through valves 1-LP-43A(B) and 1-LP-44A(B).
Based on the PRA work conducted for Millstone Unit 1 the combined frequency of occurence for th1s scenario is 1.6 x 10-8/ year.
It should be noted that this is not the frequency of ISL, but is rather the frequency of over-pressurizing the low pressure piping. Even if this event led directly to an ISL, 50% of the time, the control room operator could recover by closing motor operated valve 1-LP-10A(B) gs
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since the LPCI header high pressure alarm would actuate in the control room. Assuming overpressurization leads to LOCA and operator recovery from this event, the frequency of ISL is 8 x 10-9/ year.
ALTERNATi TESTING:
Perform Appendix
'J' Type C local leakrate tests on motor operated injection valves 1-LP-10A(B). In addition to the above, the Corrective Action of Article IWV-3427(a) and (b) of Section XI of the ASME Code will apply to valves 1-LP-10A(B).
1
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VALVE RELIEF REQUEST NUMBER:
V-49 SYSTEM:
Core Spray Systems A and B VALVES:
1-CS-5A, Loop A infection valve 1-CS-5B, Loop B ingection valve CLASS /CATEGORYi 1A (CIV/PIV).
FUNCTION:
Core Spray System Motor Operated Injection Valves.
TEST REQUIREMENT:
Containment Isolation Valves (CIV's) which also perform a reactor coolant pressure isol-ation (PIV) function shall, in addition to being tested in accordance with 10 CFR 50 Appendix
'J' leakrate test criteria, be seat leakage tested to verify their leak-tight integrity. Valve closure prior to seat leakage testing shall be by using the valve operator with no additional closing rurce applied.
BASIS FOR RELIEF:
Relief is requested from performing the Pressure Isolation Valve tests on the basis that these valves due to the system design, function in the course of normal plant oper-g-)s ation in a manner that demonstrates adequate
(,
seat leak-tightness.
The Core Spray cystem is designed like the LPCI system since it has two injection paths, each of which contains three isolation valves in series on the high pressure piping side.
Valve interlocks prevent both valves from being open when reactor recirculation pressure is above 350 psig in that: Outboard injection valve 1-CS-4 A(B) can be opened only if the in-board valve 1-CS-5A(B) is closed and inboard injection valve 1-CS-SA(B) can be opened only if the outboard injection valve 1-CS-4A(B) is closed. However, there are several differences between the two systems. First, the outboard motor operated valve 1-CS-4A(B) is a normally open gate valve unlike its counterpart (ie.
globe stop check 1-LP-9A(B) in LPCI). Second-j ly, the Core Spray valve opening logic has an extra low pressure permissive switch which j
could, if it were to fail, allow an operator to mistakenly open the inboard valve 1-CS-SA (B) before closing 1-CS-4A(B).
A similar error could not occur in testing LPCI valves, since 1-LP-9A(B) is always closed by virtue of l
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being a stop check. Based on Core Spray system design there are two ways that the low pres-sure p1 ping could be overpressurized.
- 1. Failure of the check valve 1-CS-6A(B) inside the containment, combined with coincident failure of motor operated valve 1-CS-5A(B) to remain closed.
- 2. Failure of check valve 1-CS-4A(B) coincident with failure of the operator to close valve 1-CS-4A(B) before open-ing 1-CS-5A(B).
The frequency of overpressurization due to the above events is 1.1 x 10-5/ year. Again, over-pressurization does not lead to ISL and the operator can recover from this event 99% of the time by closing valve 1-CS-4A(B). The 1%
that cannot be recovered is due to random f ailure of motor operated valve 1-CS-4 A(B).
Assuming overpressurization leads to ISL and operator recovery takes place, the frequency of ISL is 1.1 x 10-7/ year.
Furthermore, during the quarterly operability testing of injection valves 1-CS-5A(B), when 1-CS-4A(B) are closed and 1-CS-SA(B) are open-ed, the 350 psig Core Spray system valve leak-age detection pressure switch alarm is verif-ied not to actuate, which essentially is a 1
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leak test of the inside check valve 1-CS-6A(B). These check valves were replaced in 1980 during the Core Spray piping replacement and do not have the testable check feature option. The integrity of the isolation valves 1-CS-5A(B) is further verified by perforr.ance of the Appendix
'J" Type C local leak rate j
testing.
Based on the frequency of ISL of once in 10 million years for core Spray and once in 125 million years for LPCI, neither system signifigantly contributes to core melt. The design of each system, redundant isolation valves, system interlocks and leakage detect-ion alarms complimented w1th the Appendix
'J' Type C local leak rate testing, clearly demonstrates the condition of the system and does not consider that any additional testing is required.
ALTERNATE TESTING:
Perform Appendix
'J' Type C local leakrate tests on motor operated injection valves 1-CS-5A(B). In addition to the above, the O
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xa 1v t or t x 9 a t aa correceiv-Action of Articles IW-3426 and IW-3427(a) and (b) of Section XI of the ASME Code will apply.
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O REVISION 3 RECORD QF CHANGES INSERVICE PUMP AND VALVE TEST PROGRAM LIST QE AFFECTED PAGES PAGES SECTION 1-5 Pump Inservice Testing 1
Ranges of Test Parameters 1
Vibration Acceptance Criteria 1-3 Inservice Pump Testing Requirements Tables R-1 to R-24 Pump Relief Requests 1-9 Valve Inservice Testing 1
Legend for Valve Testing 1-53 Inservice Test Valve List O
V-1 to V-49 Valve Relief Requests
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