ML13333A786
| ML13333A786 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/24/1984 |
| From: | Rosenblum R SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13310B167 | List: |
| References | |
| SO1-V-2.14, NUDOCS 8401270225 | |
| Download: ML13333A786 (22) | |
Text
ENCLOSURE I IST PROGRAM 8401270225 840124 PDR ADOCK 05000206 p
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.14 UNIT 1 REVISION 5 PAGE 1 OF 15 EFFECTIVE DATE IN-SERVICE TESTING OF PUMPS PROGRAM TABLE OF CONTENTS SECTION PAGE 1.0 OBJECTIVE 2
2.0 REFERENCES
2 3.0 PREREQUISITES 3
4.0 PRECAUTIONS 4
5.0 CHECK-OFF LIST 4
6.0 PROCEDURE 4
6.1 Basis for Test Requirements 4
6.2 Test Requirements 5
6.3 In-service Pump Testing Record, SO(123) 53 8
6.4 Operability Analysis 11 6.5 Instrumentation 14 6.6 Operator Responsibilities 14 7.0 RECORDS 14 8.0 ATTACHMENTS 15 8.1 Allowable Ranges of Test Quantities 8.2 Class 1, 2 and 2 Pumps 8.3 Check-Off Sheet 5.2 8.4 Check-Off Sheet 5.3 PAGES CHANGED WITH THIS REVISION:
ALL PREPARED BY:
AUTHOR DATE APPROVED BY:
R. M. ROSENBLUM DATE MANAGER, TECHNICAL DWB:0182d/daj
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 2 OF 15 IN-SERVICE TESTING OF PUMPS PROGRAM 1.0 OBJECTIVE 1.1 This procedure defines the in-service testing requirements for ASME Code Class 1, 2 and 3 pumps at San Onofre Unit 1 which are provided with an emergency power source. It is intended that this procedure, and its associate procedures meet the requirements of Reference 2.1.1 and 2.2.2 to the maximum extent practical.
2.0 REFERENCES
2.1 Cross-reference to Licensing Commitment Requirements 2.1.1 Code of Federal Regulations, Title 10, Part 50.55a (paragraphs e,g) dated January 1, 1980 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 Station Orders 2.2.1 Station Order SO1-E-122 Administrative Control of In-service Inspection 2.2.2 50123-XV-1.0, Calibration and Control of Measurement and Test Equipment 2.3 Station 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 S01-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
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 3 OF 15
2.0 REFERENCES
(Continued) 2.3.7 SO1-V-2.14.7, Spray Chemical Addition In-service Pump Test 2.3.8 S01-V-2.14.8, Saltwater Cooling In-service Pump Test 2.3.9 S01-V-2.14.9, Residual Heat Removal In-service Pump Test 2.3.10 SO1-V-2.14.10, Feedwater In-service Pump Test 2.3.11 SO1-V-2.14.11, Reactor Charging In-service Pump Test 2.3.12 SO1-V-2.15, In-service Testing of Valves Program 2.4 Other 2.4.1 Form SO(123) 53, In-service 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 Station 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 Station Document from CDM 3.2 The implementing procedures (References 2.3.1-2.3.11) shall be updated within one month after an approved revision of this procedure is released. Station Operations and Maintenance managers shall receive a copy of the approved revision to serve as notification of a revision.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 4 OF 15 4.0 PRECAUTIONS 4.1 The ASME Section XI test requirements (Reference 2.1.2) 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 pump In-service Testing Program delineated herein covers a ten (10) year interval commencing on January 1, 1978 and terminating on January 1, 1988.
5.0 CHECK-OFF LISTS 5.1 In-service Pump Test Record (SO(123) 53) 5.2 Summary of Record of Corrective Action 5.3 Summary of Current Test Status 6.0 PROCEDURE 6.1 Basis for Test Requirements 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.
6.1.1 Detection of Hydraulic Change Rotative speed, flowrate, and differential pressure are basic parameters which, when a pump is operating with adequate suction conditions describe the hydraulic characteristics of a pump.
During testing, when the values of any two of these parameters are adjusted to reference values, the value of the third parameter is established. If the test data.indicates that a deviation from a previous reference value has occurred and all test data is correct, a change has taken place in the hydraulic components of the pump which may warrant corrective action. Thus, there is the requirement to measure these basic parameters.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 5 OF 15 6.0 PROCEDURE (Continued) 6.1.2 Detection of Mechanical Change Vibration and bearing temperature are two basic parameters which describe the mechanical characteristics of a pump. Values determined under a specific dynamic load, i.e., speed, differential pressure, and flow rate, should be duplicated in future tests under similar load conditions.
Deviations from reference values may indicate changes in the mechanical components which may warrant corrective action. Thus, there is the requirement to measure these basic parameters.
6.1.3 Detection of Hydraulic and/or Mechanical Changes Pump motor current is a basic parameter which describes pumping power of a pump. The pumping power is a function of flowrate, differential pressure, and friction. If the test data indicates that a deviation from previous reference valve has occurred and all test data is correct, a change has taken place in the pump characteristics which may warrant a corrective action. Thus there may be an additional requirement to measure this parameter when a pump is normally operated in parallel or where the flowrate cannot be measured or where additional data is desired.
6.2 Test Requirements 6.2.1 The attached Table 2 specifies each pump subject to the in-service testing requirements of Section XI.
Each in-service test shall include the measurement and observation of all quantities listed in Table 2 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 Engineering Procedures SO1-V-2.14.1 through SO1-V-2.14.12 (References 2.3.1 through 2.3.11).
NOTE:
The 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 Supervisor and IST Pump Test Engineer's approval. If required, Instrumentation may also be changed with their approval.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 6 OF 15 6.0 PROCEDURE (Continued) 6.2.2 (Continued)
NOTE:
(Continued)
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 this occurs, the change in valve line up may be noted and signed by the Shift Supervisor.
6.2.3 Each pump shall be tested nominally (+ 1 week) at the frequency specified under the column "Test Frequency." It is recommended that this test frequency be maintained during shutdown periods where this can reasonably be accomplished, although this is not mandatory. If it is 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 that are operated more frequently than every 3 months need not be run or stopped for a special test, provided the records show such pumps were operated at least once every 3 months at the reference conditions and the quantities specified were measured, observed, recorded and analyzed.
6.2.5 Reference values are defined as one or more fixed sets of values of the quantities shown in Table 2 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 sub paragraphs.1 and.2 below.
.1 Effect of Pump Replacement, Repair and Routine Servicing on Reference Values.
After a pump has been replaced, a new set or sets of reference values shall be determined. When a reference value or set of values may have been affected by repair or routine servicing of the pump, 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. Deviations between the previous and new set of reference values shall be identified and verification that the new values represent acceptable pump operation shall be recorded in the summary record of Correction Action (Check-off List 5.2) for that pump.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 7 OF 15 6.0 PROCEDURE (Continued) 6.2.5.2 Establishment of an Additional Set of Reference Values.
Should it be necessary or desirable for some reason other than stated in 6.2.5.1 to establish 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.
Whenever an additional set of reference values is established, the reasons for so doing shall be justified and documented in the pump record.
If reference values can not be met because of plant conditions, but the results are within the pump manufacturer's acceptance data, 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 references under those plant conditions.
6.2.6 Methods of Measurement
.1 Methods of measuring pump parameters shall meet the requirements of Article IWP-4000 of reference 2.1.2 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. At the end of this time at least one measurement or observation of each of the quantities specified shall be made and recorded.
.2 When measurement of bearing temperature is required, each pump shall be run until the bearing temperatures stabilize, and then the quantities specified shall be measured or observed and recorded. -A bearing temperature shall be considered stable when three successive readings taken at ten minute intervals do not vary by more than 3%, or no detectable change in temperature has occurred after 10 minutes.
6.2.8 Control, direction and scheduling of the test shall be the responsibility of the IST Pump Engineer.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UN.IT 1 REVISION 5 PAGE 8 OF 15 6.0 PROCEDURE (Continued) 6.2.8.1 Collection of data may be delegated to an Engineering Aide.
.2 IST pump testing shall be coordinated with operational testing when possible.
6.3 Inservice Pump Testing Record (SO(123)53)
The In-service Pump Testing Record shall be prepared by Engineering. Engineering shall control the performance of the test as follows:
6.3.1 Test Record in General.
.1 Line 1:
Enter applicable system and pump identification.
.2 Line 2:
Enter date of test and name of person recording pump data.
.3 Line 3:
Enter pump area location from drawing 5147622 and reason for test, i.e. quarterly test, establish reference values, etc.
.4 Line 4:
Enter plant power level, or status, i.e., 400 MW, cold shutdown, hot shutdown, etc.
From pump test records enter the reference value Record Number and the effective date, i.e. the test date on that record.
.5 Line 5:
Enter current testing frequency, and date of last in-service pump test.
.6 Line 6:
Determine if the pump can or cannot be tested. If the pump cannot be operated under the current plant conditions check no, and document reason. A record should be sent to CDM, even though the pump cannot be tested.
III.
S!AN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 9 OF 15 6.0 PROCEDURE (Continued) 6.3.1.7 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.
.8 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 number one enter NA under Inst. ID Heading.
.8.1 Inst. ID -
Enter instrument tag number or serial number of instrument used to measure parameter.
.8.2 Calibration Date -
Enter instrument calibration date.
.8.3 Units - Enter units of measure for instrument.
.8.4 Ref. Value - Enter test value from reference data set identified on line 4.
.8.5 In the Hydraulic section, identify with a check mark, those parameters which are pretest requirements.
Operations will adjust system to the reference value within a specified tolerance.
.8.6 Test Value - After pretest requirements have been met, record instrument reading for each parameter to be measured.
.8.7 Acceptable Range -
This range is determined using Table 1.
NOTE:
There may be data taken which is not required by Section XI (Ref. 2:1.2).
For information purposes only, this data will be collected and evaluated independently of Section XI requirements.
0II
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.14 UNIT 1 REVISION 5 PAGE 10 OF 15 6.0 PROCEDURE (Continued) 6.3.1.9 Line 8 and 11:
Suction Pressure -
Pressure measured at the inlet side of the pump. In some cases there is no instrumentation available to measure this parameter.
In such a case suction pressure must be calculated from available instrumentation. The equation used to make this calculation is in the appropriate pump test procedure. The calculated or measured results shall be recorded on lines 8 and 11 as suction pressure.
NOTE:
When using instrumentation, i.e., a pressure gauge on the inlet of the pump, note Prestart (Line 8) and Poststart (Line 11) suction pressures.
.10 Line 9:
Speed - This parameter is shaft speed.
.11 Line 10:
Discharge Pressure -
Pressure measure at outlet side of pump.
.12 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 formulas.
.13 Line 13:
Motor Current-Electric current of drive motor.
Measured from meters in the Control Room.
.14 Line 14:
Flow Rate -
Mass flowrate of pumping system.
.15 Lines 15, 16, 17, 18, 19 and 20:
Vibration measurements -
These are open filter amplitude readings taken on or as close to the bearings as possible.
.16 Line 21 and 22:
Lubrication data -
Level may be noted as sat/unsat.
Pressure and temperature data on the lubrication system may be recorded if instrumentation is available.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 11 OF 15 6.0 PROCEDURE (Continued) 6.3.1.17 Block 23:
Bearing Temperatures are required to be taken once a year except when testing the Salt Water Cooling Pumps.
Saltwater Cooling Pump thrust bearing temperatures shall be taken once each month.
As noted, the bearing temperatures shall be considered stable when three successive readings taken at ten minute intervals do not vary by more than 3% or no detectable change in temperature occurs after 10 minutes of running (these temperatures and their variations must be recorded).
.18 Record Number -
The record number shall include the following:
- 1)
Pump Number
- 2)
Month Tested
- 3)
Year Tested An example of a Record number for a component cooling water pump follows:
G-15A-9-81 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 completion of a test.
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 Table 1 (IWP-3100-2 of Section XI).
An engineering analysis may change these ranges to meet specific pump requirements. The acceptable ranges of test quantities will be specified in each In-service Pump Test Record.
6.4.4 If deviations do occur:
.1 Engineering shall determine the cause of the deviation(s) and perform the type of analysis necessary to demonstrate the operability of the pump.
.2 In the Hydraulic Section of SO(123) 53:_
.2.1 When test results show deviations greater than allowed, the instruments involved may be recalibrated and the test rerun.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.14 UNIT 1 REVISION 5 PAGE 12 OF 15 6.0 PROCEDURE (Continued) 6.4.4.2.2 In the case where deviations in these parameters can be attributed to normal pump wear or to other causes external of the pump, the test data shall be used to establish a revised pump head curve or the reason for the deviation.
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.
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 In the case where deviations in these parameters cannot be attributed to normal wear or external causes the pump shall be repaired or replaced.
.3 In the Mechanical Section of SO(123) 53:
.3.1 Mechanical pump test data shall be compared with the pump manufacturer's rcommendations. If the pump is operating within the manufacturer's specifications it shall be considered operable and a new reference point established using the test data. Engineering shall insure 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 Table 1.
.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 Table 1.
.1.1 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 analized and accounted for.
.1.3 Calibration checks shall be made on instruments involved and the test rerun.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.14 UNIT 1 REVISION 5 PAGE 13 OF 15 6.0 PROCEDURE (Continued) 6.4.5.1.4 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 6.4.4.3.1).
.1.5 When the conditions of 6.4.5.1.2 or 3 cannot be met QA shall be notified to prepare a non-conformance report. 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 Section 6.2.5.1 are met.
.1.6 The Shift Supervisor and Supervising Engineer or his designee shall be notified that the pump is in the alert range. They shall be responsible for any additional notifications.
.2 Required Action Range
.2.1 The following action shall be performed for pumps determined to be operating within the Required Action Range of Table 1.
.2.2 The cause of the deviation shall be determined, and the condition corrected. If the cause is determined to be external of the pump the condition shall be analized and accounted for.
.2.3 Calibration checks shall be made on instruments involved and the test rerun.
.2.4 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.
.2.5 If the retest and analysis confirms the initial test results the Shift Supervisor, Supervising Engineer, and Maintenance Supervisor shall be notified that the pump has been declared inoperative.
.2.6 The pump shall not be returned to service until the cause of the deviation has been determined per 6.4.5.2.2.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.14 UNIT 1 REVISION 5 PAGE 14 OF 15 6.0 PROCEDURE (Continued) 6.5 Instrumentation Instrumentation used shall meet the requirements of (IWP-4110-1) of Section XI to the maximum extent practical.
Instruments together with their transmitters where used shall be calibrated in accordance with S0123-XV-1.0 (Reference 2.2.2).
6.6 Operator Responsibilities 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 IWP-6210. The date of the test and the pump test record number will be listed. See Check-Off List 5.3.
7.1.2 In-service Pump Test Records SO(123) 53.
There will be at least one test record per pump per test. These pump records will show the test results for each test and will indicate if corrective action-is needed.
7.1.3 Summary Record of Corrective Action (Check-Off Sheet 5.2).
.1 This record shall include a summary of corrective action taken and the subsequent in-service tests or other methods used to confirm operational adequacy.
The signature of the individual responsible for corrective action and verification of results shall be included. A copy of the Memorandum for File, Nonconformance Report (NCR) and/or Licensee Event Report (LER) will be attached.
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 will be filed in the CDM Center.
7.2 This procedure and data described in 7.1.2 and 7.1.3 will be filed in the Station Engineering files and in the CDM Center.
AN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 15 OF 15 8.0 ATTACHMENTS 8.1 Table 1 "Allowable Ranges of Test Quantities". (1 page) 8.2 Table 2 "Class 1, 2 and 2 Pumps". (4 pages) 8.3 Check-Off List 5.2 (1 page) 8.4 Check-Off List 5.3 (1 page) 0182d
SAN 0 NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO-V-2.,
UNIT REVISION 5 PAGE 1 OF W WATTACHMENT 8.1 TABLE 1 (IWP-3100-2)
ALLOWABLE RANGES OF TEST QUANTITIES Alert Range Required Action Range Test Quantity Acceptable Range Low Values High Values Low Values High Values P
1 1
1 1
1 1
P
.93 to 1.02 P
.90 to.93 P
1.02 to 1.03 P
<.90 P
>1.03 P
r r
r r
r Q
.94 to 1.02 Q
.90 to.94 Q 1.02 to 1.03 Q
<.90 Q
>1.03 Q r
r r
r r
V When 0 < V < 0.5 mil 0 to 1 mil None 1 to 1.5 mil None
>1.5 mil r
V When 0.5 mil <
V < 2.0 mil 0 to 2V mil None 2 V mil to 3V mil None
>3V mil r
r r
r r
V When 2.0 mil <
V < 5.0 mil
.0 to (2+V ) mil None (2+V ) mil to (4+V ) mil None
>(4+V ) mil r
r r
r r
V When V >
5.0 mil 0 to 1.4V mil None 1.4V mil to 1.8V mil None
>1.8V mil r
r r
r r
T 2
2 2
2 2
b Pump Power 3
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:
All values in this table are subject to change by an engineering analysis of individual pump parameters.
SAN ON NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.1 UNIT 1 REVISIONN5 82 PAGE 1 OF W
W ATTACHMENT 8.2 TABLE 2 ASME-CLASS 1, i AND 3 PUMPS (UNIT 1)
PUMP PUMP NAME CLASS P & ID AND TEST PARAMETERS NUMBER COORDINATES INLET DIFF FLOW VIBRA BEARING LUBE TEST SPEED PRESS PRESS RATE TION TEMP LEVEL FREQUENCY NOTES G10S AUX. FEEDWATER PUMP (ELECT) 2 5159570 8-5 N/A YES YES NO YES YES YES MONTHLY 3, PRR-6 G-10 AUX. FEEDWATER PUMP (STEAM) 2 5159570 D-5 YES YES YES NO YES YES YES MONTHLY 3, PRR-6 G-15A COMPONENT COOLING PUMP 3
568768 C-8 N/A YES YES YES YES YES YES QUARTERLY 3
G-15B COMPONENT COOLING PUMP 3
568768 C-8 N/A YES YES YES YES YES YES QUARTERLY 3,6 G-15C COMPONENT COOLING PUMP 3
568768 C-8 N/A YES YES YES YES YES YES QUARTERLY 6
G-74A DIESEL FUEL TRANSFER PUMP 3
5154026 H-5 N/A YES YES YES NO NO NO QUARTERLY 6, PRR-2 G-74B DIESEL FUEL TRANSFER PUMP 3
5154026 H-4 N/A YES YES YES NO NO NO QUARTERLY 6, PRR-2 G-75A DIESEL FUEL TRANSFER PUMP 3
5154031 H-7 N/A YES YES YES NO NO NO QUARTERLY 6, PRR-2 G-75B DIESEL FUEL TRANSFER PUMP 3
5154031 H-8 N/A YES YES YES NO NO NO QUARTERLY 6, PRR-2 G-50A SAFETY INJECTION PUMP 2
568769 B-11 N/A YES YES NO YES YES YES QUARTERLY 3,6,PRR-6 G-50B SAFETY INJECTION PUMP 2
568769 D-11 N/A YES YES NO YES YES YES QUARTERLY 3,6,PRR-6 G-45A SAFETY INJECTION 2
568769 H-2 MOTOR NO NO NO NO NO NO QUARTERLY 4, PRR-3 RECIRCULATION PUMP AMPS
& VOLTS G-45B SAFETY INJECTION 2
568769 11-3 MOTOR NO NO NO NO NO NO QUARTERLY 4, PRR-3 RECIRCULATION PUMP AMPS
& VOLTS G-27N REFUELING WATER PUMP 2
568776 H-5 N/A YES YES NO YES YES YES QUARTERLY 3,6,PRR-6 G-27S REFUELING WATER PUMP 2
568776 H-5 N/A YES YES NO YES YES YES QUARTERLY 3,6,PRR-6 G-200A SPRAY CHEMICAL ADDITION PUMP 2
568777 H-11 YES.
YES YES YES YES YES YES QUARTERLY 3,6 G-200B SPRAY CHEMICAL ADDITION PUMP 2
568777 G-11 YES YES YES YES YES YES YES QUARTERLY 3,6 G-13A SALT WATER COOLING PUMP 3
568775 8-6 N/A YES YES YES YES YES YES MONTHLY 3,6,PRR-7 0-138 SALT WATER COOLING PUMP 3
568775 C-6 N/A YES YES YES YES YES YES MONTHLY 3,6,PRR-7
SAN ON NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT REVISION 5 PAGE 2 OF UNTITYATTACHMENT 8.2 TABLE*
ASME-CLASS 1, '2 AND 3 PUMPS (UNIT 1)
PUMP PUMP NAME CLASS P & ID AND TEST PARAMETERS NUMBER COORDINATES INLET DIFF FLOW VIBRA HEARING LUBE TEST SPEED PRESS PRESS RATE TION TEMP LEVEL FREQUENCY NOTE G-130 SALT WATER COOLING PUMP 3
568775 C-2 N/A YES YES YES YES YES YES MONTHLY 3,6,PRR-7 (AUXILIARY)
G-14A RESIDUAL HEAT REMOVAL PUMP 2
5130354 G-7 N/A YES YES YES YES YES YES COLD 3,5,6, SHUTDOWN PRR-t4 G-14B RESIDUAL HEAT REMOVAL PUMP 2
5130354 H-7 N/A YES YES YES YES YES YES COLD 3,5,6 SHUTDOWN PRR-4 G-3A FEEDWATER PUMP 2
568779 C-4 N/A YES YES YES YES YES YES QUARTERLY 1,3,PRR-5 G-3B FEEDWATER PUMP 2
568779 F-4 N/A YES YES YES YES YES YES QUARTERLY 1,3,PRR-5 G-8A REACTOR CHARGING PUMP 2
568767 F-6 N/A YES YES YES YES YES YES QUARTERLY 3
G-8B REACTOR CHARGING PUMP 2
568767 G-6 N/A YES YES YES YES YES YES QUARTERLY 3
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE S01-V-2.14 UNIT 1 REVISION 5 PAGE 3 OF 3 ATTACHMENT 8.2 TABLE 2 PUMP IN-SERVICE TESTING PROGRAM NOTES AND CLARIFYING REMARKS YES Indicates quantity can be measured, calculated or observed.
NO Indicates quantity not available for measurement or not needed.
NOTES:
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 per ref. letter, J. G. Haynes to D. M. Crutchfield, NRC, dated July 24, 1980.
NOTE 3:
There is no installed instrumentation to allow 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 Section XI.
The requirements of Technical Specification 4.2.II.B(3) shall be used in lieu of the Section XI pump testing requirements. This requires that proper starting of each pump be confirmed by observation of running current and voltage, demonstrated on a monthly basis.
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. This procedure is covered in ST1-V-2.14.5 (Reference 2.3.5).
lNOTE 5:
Testing will be performed at cold shutdown cocnditions ata frequency to meet as cosely as possible the requirements of Section XI (Reference 2.1.2).
NOTE 6:
Inlet pressure for this pump is determined from tank levels and system pressure upstream of pump.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.14 UNIT 1 REVISION 5 PAGE 1 OF 1 ATTACHMENT 8.3 CHECK-OFF SHEET 5.2
SUMMARY
OF RECORD OF CORRECTIVE ACTION PUMP NUMBER PUMP DESCRIPTION MANUFACTURER'S IDENTIFICATION NUMBER DATE DESCRIPTION OF PROBLEM, CORRECTIVE ACTION TAKEN, AND RESULTS.
OF INCLUDE SIGNATURE OF PERSON RESPONSIBLE FOR CORRECTION ACTION TEST AND VERIFICATION OF RESULTS.
SAN E NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SalV-2 lb UN I REVISION 5 PAGE 1 UIATTACHMENT 8.4 0
CHECK-OFF SHEET 5.3
SUMMARY
OF CURRENT TEST STATUS PUMP NUMBER PUMP NAME DATE RECORD#
DATE RECORD#
DATE RECORD#
DATE RECORD#
G-10S Auxiliary Feedwater Pump (ELECT)
C-10 Auxiliary Feedwater Pump (STEAM)
G-15A Component Cooling Water Pump G-158 Component Cooling Water Pump G-15C Component Cooling Water Pump G-714A Diesel Fuel Transfer Pump G-7.5B Diesel Fuel Transfer Pump G-75A Diesel Fuel Transfer Pump G-750 Diesel Fuel Transfer Pump G-ROA Safety Injection Pump G-508 Safety Injection Pump G-4SA Safety Injection Recirculation Pump
-4s5B Safety injection Recirculation Pump G-27N Refueling Water Pump G-27S Refueling Water Pump G-200A Spray Chemical Addition Pump C-200B Spray Chemical Addition Pump G-13A Salt Water Cooling Pump G-13B Salt Water Cooling Pump G-14A Residual-Heat Removal Pump G-14A Residual Heat Removal Pump G-3A Feedwater Pump G-3B Feedwater Pump G-BA Reactor Charging Pump G-8B Reactor Charging Pump G-13C Auxiliary Salt Water Cooling Pump