ML13317B490
| ML13317B490 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/02/1985 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13317B491 | List: |
| References | |
| S01-V-2.14, S1-V-2.14, NUDOCS 8603050114 | |
| Download: ML13317B490 (20) | |
Text
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.14
)
UNIT 1 REVISION 6 PAGE 1hOF 20 COMPLETE REVISION TCN o-,L EFFECTIVE DATE f / /
IN-SERVICE TESTING OF PUMPS PROGRAM TABLE OF CONTENTS SECTION PAGE 1.0. OBJECTIVES 2
2.0 REFERENCES
2 3:0 PREREQUISITES 3
4.0 PRECAUTIONS 3
5.0 CHECKLISTS 4
6.0 PROCEDURE 4
6.1 Basis for Test Requirements 4
6.2 Test Requirements 4
6.3 SO(123) 53, Inservice Pump Test Record 7
6.4 Operability Analysis 10 6.5 Instrumentation 13 6.6 Operator Responsibilities 13 7.0 RECORDS 13 ATTACHMENTS 1
SO(123)53, Inservice Pump Test Record 15 2
Allowable Ranges of Test Quantities 16 3
Class 1, 2 and 3 Pumps 17 4
Summary of Current Test Status 20 8603050114 860303' PDR ADOCK 05000206 P
PDR_
QA PROGRAM AFFECTING
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SOI-V-2.14 UNIT 1 REVISION 6 PAGE 2 OF 20 TCN IN-SERVICE TESTING OF PUMPS PROGRAM 1.0 OBJECTIVES 1.1 To define the in-service testing requirements for ASME Code Class 1, 2 and 3 pumps at Unit 1 which are provided with an emergency power source.
1.2 To meet the requirements of References 2.1.1 and 2.1.2 to the maximum extent practical.
2.0 REFERENCES
2.1 Licensing Commitments 2.1.1 Code Federal Regulations, Title 10, Part 50.55(a), (e) and (g) 2.1.2 American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code,Section XI, 1977 Edition, including Addenda through Winter of 1979 2.2 Site Order 2.2.1 S0123-IN-1, In-Service Inspection Program 2.3 Procedures 2.3.1 S01-V-2.14.1, Auxiliary Feedwater In-Service Pump Test 2.3.2 SO1-V-2.14.2, Component Cooling Water In-Service Pump Test 2.3.3 SO1-V-2.14.3, Diesel Fuel Transfer In-Service Pump Test 2.3.4 SO1-V-2.14.4, Safety Injection In-Service Pump Test 2.3.5 SO1-V-2.14.5, Safety Injection Recirculation In-Service Pump Test 2.3.6 SO1-V-2.14.6, Refueling Water In-Service Pump Test 2.3.7 SO1-V-2.14.7, Spray Chemical Addition In-Service Pump Test 2.3.8 SO1-V-2.14.8, Saltwater Cooling In-Service Pump Test 2.3.9 SO1-V-2.14.9, Residual Heat Removal In-Service Pump Test 2.3.10 SO1-V-2.14.10, Feedwater In-Service Pump Test
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 6 PAGE 3 OF 20 TCN 2..0 REFERENCES (Continued) 2.3.11 SO1-V-2.14.11, Reactor Charging In-service Pump Test 2.3.12 SOI-V-2.15, In-Service Testing of Valves Program 2.3.13 S0123-II-1.0, Calibration and Control of Measurement and Test Equipment 2.4 Other 2.4.1 SO(123) 53, Inservice Pump Test Record 2.4.2 Letter from J. G. Haynes to D. M. Crutchfield, NRC, dated July 24, 1980 3.0 PREREQUISITES 3.1 Prior to use of an uncontrolled (pink) copy of this Site document to perform work, verify it is current by utilizing one of the following methods:
3.1.1 Checking a controlled copy and any TCNs 3.1.2 Accessing an SCE Document Cofiguration System (SDCS) TSO terminal 3.1.3 Referencing a current (within one week) Configuration Control Log and associated daily update 3.1.4 Contacting CDM by telephone or through counter inquiry 3.1.5 Obtaining an uncontrolled (pink) copy of the Site document from CDM.
3.2 The implementing Procedures (References 2.3.1 through 2.3.11) shall be updated as necessary within one month after revision of this Procedure is released. The Managers of Operations and Maintenance shall receive a copy of the approved revision from the IST Coordinator to serve as notification of a revision.
4.0 PRECAUTIONS 4.1 The Reference 2.1.2 test requirements shall be met to the maximum extent practical.
It is not the intent of this Procedure to place the Plant in an unsafe condition for the purpose of testing a pump. Care should be exercised to ensure that no test will be conducted that would violate Technical Specifications or other Plant operating constraints.
4.2 The In-Service Testing of Pumps Program delineated herein covers a ten (10) year interval commencing January 1, 1978 and terminating January 1, 1988.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 6 PAGL 4 OF 20
)
TCN 5.0 CHECKLISTS 5.1 SO(123) 53, Inservice Pump Test Record 5.2 6.0 PROCEDURE 6.1 Basi: for Test Requirements 6.1.1 The hydraulic and mechanical condition of a pump relative to a previous condition can be determined by attempting to duplicate by test a set of basic reference parameters. Deviations detected are symptoms of changes and, depending upon the degree of deviation, indicate need for further tests or corrective action.
6.2 Test Requirements RIMOeAT" 6.2.1 specifies each pump subject to the M
I in-service testing requirements of Reference 2.1.2.
Each in-service test shall include the measurement and observation of all quantities listed in Attachment 3, except bearing temperatures. Bearing temperatures will be measured during at least one in-service test each year.
6.2.2 Each pump shall be tested in accordance with References 2.3.1 through 2.3.11.
NOTE:
The implementing Procedures indicate the preferred valve alignment for pump testing.
If Plant conditions warrant, a change in the valve alignment may be made with the Shift Superintendent and Cognizant Engineer's approval. If required, instrumentation may also be changed with their approval.
The deviation shall be indicated in the Procedure by a NOTE. Operations may also want the system left in an "as-tested" condition or in a different valve line up than indicated by the test Procedure. If so, the change in valve line-up may be noted and signed by the Shift Superintendent indicating that his Procedures permit this valve lineup.
6.2.3 Each pump should be tested nominally ( + 1 week) at the frequency specified in Attachment 3 under the Test Frequency column.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO-V-2.14 UNIT 1 REVISION 6 PAGE 5 OF 20 aTCN W d 6.0 PROCEDURE (Continued)
NOTE:
If the test cannot be performed within the specified frequency, an extense-of -the---
interval mpy be obtained.
An extension shall not exceed twenty-five percent (25%) of the inspection interval and must not cause any three (3) consecutive surveillance intervals to exceed 3.25 times the specified surveillance interval.
6.2.3.1 It is recommended that this test frequency be maintained during shutdown periods when this can reasonably be accomplished although this is not mandatory.
.2 If not tested during Plant shutdowns, the pump shall be tested prior to entering the Mode in which it is required to perform a safety function.
6.2.4 Pumps operated more frequently than every three (3) months need not be run or stopped for a special test, provided the records show such pumps were operated at least once every three (3) months at the reference conditions and the parameters specified were measured, observed, recorded and analyzed.
6.2.5 Reference values are defined as one or more fixed sets of values of the parameters shown in Attachment 3, as measured or observed when the equipment is known to be operating acceptably. All subsequent test results are compared to these reference values or to new reference values established in accordance with steps 6.2.5.1 through 6.2.5.2.2.
.1 Effect of Pump Replacement, Repair and Routine Servicing on Reference Values
.1.1 After a pump has been replaced, a new set, or sets, of reference values shall be determined.
.1.2 When a reference value, or set of values, may have been affected by repair or routine servicing, a new reference value, or set of values, shall be determined or the previous value reconfirmed by an in-service test run prior to return of the pump to normal service.
.1.3 Deviations between the previous and new set of reference values shall be identified. Verification that the new values represent acceptable pump operation shall be recorded in a Memorandum To File and placed in the IST files for that pump.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.14 UNIT I REVISION 6 PAGE 6 OF 20 TCN __it 6.0 PROCEDURE (Continued) 6.2.5.2 Establishment of an Additional Set of Reference Values
.2.1 Should it be necessary or desirable for a reason other than that stated in step 6.2.5.1 to establ-1sh-an additional set of reference values, an in-service test shall first be run at the conditions of an existing set of reference values and the results analyzed.
If operation is satisfactory, 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.
EpievED V
.2.2 If the reference values cannot be met due to Plant conditions but the results are within the pump Manufacturer's acceptance data and within the safety analysis, the pump will remain in operable status.
However, when Plant conditions permit, an in-service test shall be run at the conditions of the existing set of reference values and the results analyzed. 'If the pump operation is satisfactory, the new values will become the references under those Plant conditions.
.2.3 Whenever an additional set of reference values is established, the reasons shall be explained and documented in the pump record.
6.2.6 Methods of Measurement
.1 Methods of measuring pump parameters shall meet the requirements of Reference 2.1.2 (IWP-4000).
..6.2.7 Test Duration
.1 When measurement of bearing temperature is not required, each pump shall be run for at least five minutes under conditions as stable as the system permits.
.2 At the end of this time, at least one measurement or observation of each of the quantities specified shall be made and recorded.
.3 When the measurement of bearing temperature is required, each pump shall be run until the bearing temperature stabilizes and then the quantities specified shall be measured or observed and recorded.
.4 A bearing temperature shall be considered stable when three (3) successive readings taken at ten minute intervals do not vary by more than 3%.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE S 7O-V-2.14 UNIT 1 REVISION 6 PAGE 7 OF 20 TCN _k -.2 6.0 PROCEDURE (Continued) 6.2.8 Control, direction and scheduling of the Test shall be the responsibility of the Cognizant Engineer.
.1 Collection of data may be delegated to an Engineering Aide.
.2 In-Service Testing of pumps shall be coordinated with other operational testing when possible.
6.3 SO(123) 53, Inservice Pump Test Record NOTES: 1. The SO(123) 53 shall be prepared by Engineering which shall control the performance of the tests.
- 2. Not all spaces on SO(123) 53 must be completed for each pump test. Spaces not required will be completed.using N/A.
6.3.1 Completing the SO(123) 53 (see Attachment 1)
.1 Upper.Right-Hand Corner Above the words "EDM Encode No.", record the Plant tag number for the component tested and the test date.
Example:
Plant Tag No.: G13A In the blank marked "Record No.", place the record number determined as follows:
- 1) Pump number
- 2) Month tested
- 3) Year tested Example:
G-15A-9-81
.2 Line 1:
Enter the applicable system and pump identification.
NOTE: It is not mandatory to enter the pump class.
.3 Line 2:
Enter the date of the test and the name of the person recording the pump data.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 6 PAGE 8 OF 20 TCN 6.0 PROCEDURE (Continued) 6.3.1.4 Line 3:
Enter the pump area location and the reason for test, i.e. quarterly test, establish reference values, etc.
NOTE: It is not mandatory to enter the area location.
.5 Line 4:
Enter the Plant power level, or status, i.e., 400 MW, cold shutdown, hot shutdown, etc.
From the pump test records, enter the reference value record number and the effective date, i.e., the test date on that record.
.6 Line 5:
Enter the current testing frequency and the date of the last in-service pump test.
.7 Line 6:
Determine if the pump can be tested. If the pump cannot be operated under the current Plant conditions, check NO and document the reason. A record should be completed and provided to the IST Coordinator even though the pump cannot be tested.
NOTE:
Calculations should always be shown either in the space below Line 6 or on an attached sheet of paper.
.8 Line 7:
Enter the time the test begins and the time the test is completed. This time should include the pump run time before the measurements are taken. Run time before the test should not be less than 5 minutes.
.9 The following information shall be provided for each of the pump parameters in the Hydraulic, Mechanical, Lubrication and Bearing Temperature sections. For parameters that do not apply to the pump identified in Line 1, enter N/A under Inst. ID Heading.
.9.1 Inst. ID:
Enter the instrument tag number or the serial number of the instrument used to measure the parameter.
.9.2 Calibration Date:
Enter the instrument's calibration expiration date.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE Su1-V-2.14 UNIT 1 REVISION 6 PAGE 9 OF 20 TCN 6.0 PROCEDURE (Continued) 6.3.1.9.3 Units:
Enter the units of measure for the instrument.
.9.4 Ref. Value:
Enter the test value from the reference data set identified on Line 4.
.9.5 Hydraulic Section:
Identify with a check mark those parameters which are pretest requirements. Operations will adjust the system to the reference value within a specified tolerance.
.9.6 Test Value: After the pretest requirements have been met, record the instrument reading for each parameter to be measured.
.9.7 Acceptable Range:
This range is determined using.
NOTE:
There may be data taken which is not required by Reference 2.1.2. For information purposes only, this data will be collected and evaluated independently of Reference 2.1.2 requirements.
.10 Lines 8 and 11:
Suction Pressure:
The pressure measured at the inlet side of the pump. In some cases, there is no instrumentation available to measure this parameter directly. In such cases, suction pressure must be calculated from available instrumentation. The equation used to make this calculation is in the appropriate implementing Procedure. The calculated or measured results shall be recorded on Lines 8 and 11 as suction pressure. If the pump is running prior to the in-service test, pre-start inlet pressure is not required.
NOTE:
When using instrumentation, i.e., a pressure gauge on the inlet of the pump, note the Pre-start (Line 8) and Post-start (Line 11) suction pressures.
.11 Line 9:
Speed: This parameter is shaft speed and is required only for pumps with variable-speed drivers.
.12 Line 10:
Discharge Pressure:
The pressure measured at the outlet eiMn m.f tha n%,grn
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 6 PAGE 10 OF 20 TCN
.-E 6.0 PROCEDURE (Continued) 6.3.1.13 Line 12:
Differential Pressure: The difference between discharge pressure and suction pressure. This value is the pump's head and, in some cases,.must be calculated from other formulae. These formulae will be in the specific implementing Procedure.
.14 Line 13:
Motor Current:
Electric current of the drive motor measures from meters in the Control Room.
This is not a required parameter and collection of this data is optional.
.15 Line 14:
Flowrate: Volumetric flowrate of the pumping system.
In cases where the resistance of the test loop is fixed, the words, minimum flow, may be entered (see, Note 1).
.16 Lines 15, 16, 17, 18, 19 and 20:
Vibration Measurements: These are open filter amplitude readings taken on, or as close as possible to, the bearings.
.17 Lines 21 and 22:
Lubrication Data: The level may be noted as SAT/UNSAT.
Pressure and temperature data on the lubrication system may be recorded if instrumentation is available.
.18 Line 23:
Bearing Temperatures are required to be taken once a year except when testing the Saltwater Cooling pumps.
Saltwater Cooling pump thrust bearing temperatures shall be taken once each month.
The bearing temperatures shall be considered stable when three successive readings, taken at ten minute intervals, do not vary by more than 3% (these tempera tures and their variations are required to be recorded).
6.4 Operability Analysis 6.4.1 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 collection of data and the SO(123) 53 signed by the Supervising Engineer.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO-V-2 14 UNIT 1 REVISION PAGE 11 OF 20 TCN 6.0 PROCEDURE (Continued) 6.4.1.1 If the component being tested was out of service prior to the in-service test, sign-off of SO(123) 53 by the Supervising Engineering is required prior to-returfit-ng the component to service.
.2 When the operability of a pump is changed due to in-service testing, the Shift Supervisor shall be notified in writing.
6.4.2 The purpose of this analysis is to demonstrate that pump conditions do not impair operability and that the pump will still fulfill its function.
6.4.3 The allowable ranges of in-service test quantities in relation to the reference valves are tabulated in, (Reference 2.1.2: IWP-3100-2). An Engineering analysis may change these ranges to meet specific pump requirements. The acceptable ranges of test quantities will be specified in each SO(123)
- 53.
6.4.4 If deviations occur:
.1 Engineering shall determine the cause of the deviation(s) and perform the type of analysis necessary to demonstrate operability of the pump.
This analysis shall be documented in a Memorandum to File placed in the IST files.
.2 Hydraulic Section of SO(123) 53:
.2.1 When the test results show deviations greater than allowed, the instruments involved may be recalibrated and the test rerun.
.2.2 Where deviations in these parameters can be attributed to normal pump wear or to other causes external to the pump, the test data shall be used to establish a revised pump head curve or the reason for the deviation.
.2.2.1 Under the conditions of normal wear, the shape of the pump curve can be assumed to be constant, allowing the revised curve to be determined by interpolation.
.2.2.2 Operability will be determined by comparing the revised pump curve to the operating requirements during normal and emergency conditions.
For causes external to the
- pump, an Engineering analysis will be used to determine the pumps operability.
.2.3 Where deviations in these parameters cannot be attributed to normal wear or external causes, the pump shall be repaired or replaced.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE S01-V-2.14 UNIT 1 REVISION 6 PAGE 12 OF 20 TCN t-'>
6.0 PROCEDURE (Continued) 6.4.4.3 Mechanical Section of 50(123) 53:
.3.1 Mechanical pump test data shall be compared with the pump Manufacturer's recommendations. --If the-pump-+s--=
operating within the Manufacturer's specifications, it shall be considered operable and a new reference point established using the test data. Engineering shall ensure that the new reference point does not result in the Manufacturer's specifications being exceeded if the pump were to be operating in the Alert Range of.
.3.2 If the mechanical test data is found to exceed the Manufacturer's specifications, the pump shall be repaired or replaced.
6.4.5 Corrective Measures
.1 Alert Range:
The following action shall be performed for pumps found to be operating in the Alert Range of.
o
.1.1 The pump test frequency shall be doubled.
.1.2 The cause of the deviation shall be determined and the condition corrected. If the cause is determined to be external to the pump, the condition shall be analyzed and accounted for per step 6.4.4.2.2.
.1.3 When the test results show deviations greater than allowed, the instrument(s) involved may be recalibrated and the test rerun.
.1.4 For deviations resulting from normal wear, corrective action shall consist of the establishment of new reference values and the test frequency returned to normal if an operability analysis of the new Alert Range concludes that the pump is operable (see step 6.4.4.3.1).
.1.5 When the conditions of step 6.4.5.1.2 or 6.4.5.1.4 cannot be met, the pump shall be scheduled for maintenance or replacement at the first available outage of sufficient duration. The test frequency shall be returned to normal after the requirements of step 6.2.6.1 are met.
.1.6 The Shift Superintendent and Supervising Engineer shall be notified that the pump is in the Alert Range. They shall be responsible for any additional notifications.
.2 Required Action Range:
The following action shall be performed as appropriate for pumps determined to be operating within the Required Action Range of.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE S0l-V-2.14 UNIT 1 REVISION 6 PAGE 13 OF 20 TCN _L 6.0 PROCEDURE (Continued) 6.4.5.2.1 The cause of the deviation shall be determined and the condition corrected. If the cause is determined to be external to the pump, the condition shall be analyzed and accounted for ;sr stc;. 6.4.4.2.2.
.2.2 Pump operability and corrective action will be based on the limits specified in the limiting conditions for operation of the Plant Technical Specifications. A pump may remain operable if an Engineering analysis indicates that, even though a pump parameter is in the Required Action Range, the pump can still fulfill its intended functions.
.2.3 If the analysis indicates the pump will not fulfill its intended function, the Shift Superintendent, Supervising Engineer and Maintenance Supervisor shall be notified that the pump cannot be considered operable under the IST rules.
.2.4 The pump shall not be returned to service until the cause of the deviation has been determined per' step 6.4.5.2.1.
6.5 Instrumentation 6.5.1 Instrumentation used shall meet the requirements of Reference 2.1.2 (IWP-4110-1) to the maximum extent practical. Test instruments, with their transmitters where used, shall be calibrated in accordance with Reference 2.3.13. Instruments will be calibrated in accordance with the appropriate Procedure.
6.6 Operator Responsibilities 6.6.1 Operator responsibilities are defined in Reference 2.2.1.
7.0 RECORDS 7.1 Records pertaining to in-service testing of pumps shall include the following:
7.1.1 A list of pumps shall be maintained to record the current status of the test program per Reference 2.1.2 (IWP-6210).
The date of the test will be listed (see ).
7.1.2 There will be at least one SO(123) 53 per pump per test. The SO(123) 53 will show the test results for each test and will indicate any corrective action needed.
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO-V-2.14 UNIT 1 REVISION 6 PAGE 14 OF 20 TCN
'f 7.0 RECORDS (Continued) 7.1.3 Record of Corrective Action
.1 If a corrective action is taken on a pump listed in, it shall be documented. Maintenance Orders (either hard copy or SOMMS), NCRs and/or Memoranda for File may be used to provide a record of corrective action. Hard copies of the record shall be filed in CDM.
.2 Reference 2.1.2 (IWP-6250) shall be complied with by a combination of the records identified in step 7.1.3.1 and the SO(123) 53 showing confirmation of operational adequacy.
7.1.4 A record of Manufacturer's data for each pump including:
the name of the Manufacturer, the Manufacturer's model number, serial number or other identification number and a copy of the Manufacturer's acceptance test report, if any, or a summary thereof.
These records shall be filed in COM.
7.2 Any proposed changes to this Procedure and any changes to other documentation associated with this Procedure shall be transmitted to the IST Coordinator.
90 DLETdD 0182d
NUCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.14 UNIT I REVISION 6 PAGE 15 OF 20 ATTACHMENT I SO(123) 53, INSERVICE PUMP TEST RECORD MUCMA~ GI UAW TAITg INSCRVICE PUMP TEST RECORD syy
- er 0......
Oa ss""
TDRAUL t*I-
__I* -5
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ams a
It IC AM0CAL a
01 82 ATTC*MET AGE IF
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FACSIMILE 0182dATTACHMENT 1 PAGE 1 OF 1
N(ICIAARIV Al ION SI I E LNGINEERIN PR0CLOui(L bu1-V-,.
UNil I
IREVISION 6
PAGE 16 ATTACHMEN 2
TCN ALLOWABLE RANGES OF TEST QUANTITIES (IWP-3100-2)
Test Alert Range Required Action Range QuantitY Acceptable Range 1ow Values High Values w Values Hiqh Values A P
.93 to 1.02 AP
<.90 AP
>1.03 AP Q
.94 to 1.02 Q
.90 to.94 0 1.02 to 1.03 0
<.90 0
>1.03 0
r r
r r
V When 0 5 V r 0.5 all 0 to 1 mit None I to 1.5 mil None
>1.5 mil V When 0.5 mil <
Vr < 2.0 mil 0 to 2V rll None 2 V mil to 3V mil None
>3V mll rrr r
r V When 2.0 muf <
V < 5.0 mil 0 to (2+V ) mli None (2+V mil to (4+V
) mil None
>(4+v )all r
r r
r p
V When V r>
5.0 mil 0 to 1.4V rml None 1.4v ill to 1.8V mil None
>1.8V el Tb 2
2 2
2 2
Pump Power 3
3 3
3
- 1.
P shall be within the limits specified in the pump record.
- 2.
T shall be within the limits specified in the pump record.
b
- 3. Pump Power shall be calculated from the voltage and input amps.
The value shall be within the limits specified In the pump record.
NOTE:
AlI values in this table are subject to change by an engineering analysis of individual pump parameters.
018?d ATTACHMENT 2 PAGE 1 OF 1
N!UCLEAR GENERATION SITE ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 6 PAGE 17 OF 20
)
ATTACHMENT 3 TCN 7
CLASS 1, 2 OR 3 PUMPS (NOTES AND CLARIFYING REMARKS)
YES Indicates quantity can be measured, calculated or observed.
NO Indicates quantity not available for measurement or not needed.
N/A Not Applicable PRR Pump Relief Request NOTE 1:
During normal operation both feedwater pumps discharge into a common header. Flow is dependent on station load. Feedwater flow (as measured by FE-456, FE-457 and FE-458) is indicative of both feedwater pumps operating in parallel.
Pumps should be tested at or near Plant full power operating when possible.
Pump motor amperage should-also be recorded for each pump.
NOTE 2:
This pump will be tested on a monthly frequency. Motor thrust bearing temperature and vibration will be taken monthly as required by Reference 2.4.2.
NOTE 3:
There is no installed instrumentation to allow the measurement of bearing temperature. Therefore, a surface pyrometer is used on the bearing casing to measure this parameter.
NOTE 4:
The recirculation pumps can only be run dry since they are located in a sump that is filled only during accident conditions. It is therefore not possible to perform the pump tests required by Reference 2.1.2.
The requirements of Reference 2.1.3 shall be used in lieu of the Reference 2.1.2 pump testing requirements. This requires that proper starting of each pump be confirmed by observation of running current and voltage.
Every Refueling, or once every 2 years, a test requiring the sump to be filled with water and the pump to be run at shut-off head will be accomplished (see Reference 2.3.5).
NOTE 5:
Testing will be performed at cold shutdown conditions at a frequency to meet as cosely as possible the requirements of Reference 2.1.2.
NOTE 6:
Inlet pressure for this pump is determined from tank levels and system pressure upstream of the pump.
JCLEAR GEN@ON SITt ENGINEERING PROCEDURE SO1-V-2.14 2 4IT 1 REVISION 6 PAGE 18 OF 2 TCN a CLASS 1, 2 OR 3 PUMPS (Continued)
I II I
iMP PUMP NAME ICLASSI P & ID AND l
TEST PARAMETERS I
JMBER I
I COORDINATESI IINLET IDIFF I FLOW I VIORA-1 OEARINC I LUBE I TEST I
II SPEED IPRESS IPRESS I RATE I
TION I
TEMP LEVELI FREQUENCY INOTES I
I I
I I
I I
II 10S AUX, FEEDWATER PUMP (ELECTI I 2 I 5159570 6-5 I N/A IYES I YES I
N0 I -YES I YES I YES I-MONTHLY J3. PRR-6 I
i 1
I I
II I
I II
-10 AUIX FEEDWATER PUMP (STEAMI I 5I$159570 D-5-1 YES I YES-I YES I NO I YES I YES I YES I MONTHLY
- 13. PRR-6
-1A COMPONENT COOLING PUMP 3
I68768 C-8 I
N/A I
YES I YES I
YES I
YES I YES I QUARTERLY 13. 6 I
I I
I I
I I
I I
I I
-158 COMPONENT COOLING PUMP 1,
1 568760 C-8 I
N/A I YES IES I
YES I YES I
YIES I YES I QUARTERLY 13.6
-15C COMPONENT COOLING PUMP I3L.I 565768 C-0 I
N/A I YES I YES I YES I
YES I
YES-I YES I QUARTERLY-16 3
1 I I
I I
I I
I I
I I
-71sA DIESEL FUEL TRANSFER PUMP I
3 I 5154026 H-5 I N/A IESI YES I YES I YNS I
NO NO I
40 QUARTERLY 16, PRR-2 I
I I
I I
I I
I I
I I
-74B DIESEL FUEL TRANSFER PUMP I 3 I 5154026 H-5 I N/A I YES I YES I YES I NO.I No I
NO I
I!Q.
1 QUARTERLY 16. PRR-2 I
I I
I I
I I
I I
I I
-75A DIESEL FUEL TRANSFER PUMP I
3 I 5154031 H-7 I N/A I S
YES I YES I Y
-S I
NO 0
I NO
-I QUARTERLY 16, PRR-2 I
I I
I I
I I
I I
I I
-758 DIESEL FUEL TRANSFER PUMP 1 3I 5154031 1-8 I.N/A I YES I YES I YES I No I N4 I NO QUARTERLY 16.
PRR-2 I
I I
I I
I I
1I 1
-50A SAFETY INJECTION PUMP 1 2 1 568769 B-11 I N/A I YES I YES I N0 I
YES I
YES I YES I QUARTERLY 13.6.PRR-6 I
I I
I I
I I
I I
I I
-50B SAFETY INJECTION PUMP 1 2 I 568769 0-11 I N/A I YES I YES I N0 I
YES I
YES I YES I QUARTERLY 13.6.PRR-6 I
I
- I I
I1 I
I I
I I
I
-45A SAFETY INJECTION I 2 I 568769 H-2 I MOTOR I NO I NO I NO I NO I
NO I NO I QUARTERLY 14, PRR-3 RECIRCULATION PUMP I
I I AMPS I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I VOLTSI I
I I
I I
I I
I I
I I
I I
-45B SAFETY INJECTION I 2 I 568769 H-3 I MOTOR I NO I NO I NO I NO I
NO I NO I QUARTERLY 14, PRR-3 RECIRCULATION PUMP I
I I AMPS I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I I
I VOLTS I I
I I
I I
I I
I I
I I
I I
I I
I I
I s-27N REFUELING WATER PUMP I 2 1568776 H-5 N/HA I YES I YES I N0 I
YES I
YES I YES I QUARTERLY 13.6.PRR-6
-27S REFUELING WATER PUMP 1 2 I 568776 H-51 INYE I YES I YES I NO I YES I
YES I YES I QUARTERLY 13.6.PRR-6 I
I I
I I
I I
I I
I I
-200A SPRAY CHEMICAL ADDITION PUMPI 2
1 568777 H-11 I YES I YES I YES I YES I
YES I
-YES I YES I QUARTERLY 3.6.PRR
-2008 SPRAY CHEMICAL-ADITION PUMPI 2 I 568777 G-11 I YES I YES I YES I YES I YES I YES I YES IJotTLY 13.6.PRR-7 I
I I
I,
I I
I I
I
- -136 SALTWATER COOLING PUMP -
1-3-1-68775 C-NfA I YES I YES I YES I YES I YES I YES I MONTHLY 13.6.PRR-7 I
I I
I I
I1 I
I I
I
- -136 SAT/TE CILN PM YES I YES I YES I YES I
YES I YES I M0tITHLY 1..R
-13C SALTWATER COOLING PUMP I 3 I 568775 C-2 I N/A I YES I YES I YES I YES I
YES I YES I MO THLY 13,6,PRR-7 AUXILIARY)
I II II ATTACHMENT 3 AGE 2 OF 3
JCLEAR GSN N SITE ENGINEtRING PROCEDURE SOI-V-2.1 5 lIT 1 REVISION 6 PAGE 19 OF 2010 ATTACHMENT 3 TCN CLASS 1, 2 OR 3 PUMPS (Continued)
I I
I I
IMP PUMP NAME ICLASSI P & ID AND I
TEST PARAMETERS IMBER I
I COORDINATES I IINLE IDIFF I FLOW I VIBRA-IBEAING I LUBE I TESTf I
I I..
I SPEED IPRESS IPRESS I RATE I TION I TEMP I LEVELI FREQUENCY INGTES I
I I
I I
I I
I I
I I
14A RESIDUAL HEAT REMOVAL PUMP I 2 I 5130354 C-7 I N/A I YES I YES I YES I
YES I
YES I YES I COLD 13,5,6, I
I II I
I SUrTOWN IPRR-9 I
I I
I I
II I
I I
I
.118 RESIDUAL HEAT REMOVAL PUMP I 2 I 5130354 H-7 I N/A I YES I YES I YES I
YES I
YES I YES I COLD 13,5,6 l
1 1
1 II SHUTDOWN-IPRR I I I
I I
I I
I I
I
- 3A FEEDWATER PUMP 1 2 1 568779 C-4 NJI/A I YES IES I I YES I
YES I.YES I YES I QUARTERLY 11,3.PRR-5 I
I I
I I
I I
I' I
I I
.38 FEEDWATER PUMP I 2 1 568779 F-4 I-N/A SI YES I YES i
YE YE I
YES I YES I QUARTERLY 113.PRR-5 I
I I
I I
I I
I I
I I
-8A REACTOR CHARGING PUMP I
2 1 568767 F-6 I
N/A IESI YES I1ES I YES YYES I Yi ES I QUARTERLY 13 I
I I
I I
I I
1 I
I I
-0B REACTOR CHARGING PUMP I 2 1 568767 C-6 I N/A I YES IY I YEI YS YES I YI Y
IYES I QUARTERLY 13 182d ATTACHMENT 3 PAGE 3 OF 3
I GENCRATION 1
INGINURING PROCEDURE SOI-V.2.14 KION 4
PAGE 20 OF 20 W
W ATTACHMENT 4 TCN SiMARY OF CURRENT TEST STATUS TEAR:
Instrutions: 1.
Record the year
- one ftheet per year.
- 2.
As tests are completed, record the date under the
. pproprte tomonth.
@3._review to ensure test intervals are not exceeded.
UMP NXtH JAN EBRHAPE I
AT I
JUN I
JUL I
AUGt SEP I OC NO DtE I
FeeAater Pump Feedwater Pump Reactor Charging Pump I 1I I
I 1V Reactor Charging Pump I
I I
VI TFVI Auxiliary Feedwater Pump (STEAM)I
_I I
Auxiliary Feedwater Pump (ELECT)
I I
TFVIIVIIF Salt Water Cooling Pump I
I i
V-I-i Salt Vater Cooling Pump I
I Auxiliary Salt Water Cooling Pump I
I Residual leat Removal Pump T
Residual Reat Removal Pump I
I Component Cooling Water Pump I_
Component Cooling Water Pump I
F TFTI ITF efuelingtelin tfater Pump Pefuel1ing1 Materr Pump Refueling Water Pump I
V.
I I
I VF*
Safety Injection Rec trculationuPumpII__
(
I I
V11 I
FTVFTI Safety Injection Rectrculation Pump I
II II Safety Injection Pump__
II IIV I1 1
TVIFI Safety injection Pump I
I Diesel Fuel Transfer Pump Diesel Fuel Transfer Pump I
l Oiesel Fuel Treaster1 Diesel Fuel Transfer Peop__
II Spray Chemical Addition Pump Spray Chemical AdditionPump I
I I
I I TAFWIENT 4
PIt El OF I