ML20062J368
| ML20062J368 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/28/1993 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20062J365 | List: |
| References | |
| PROC-931028, NUDOCS 9311040143 | |
| Download: ML20062J368 (19) | |
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4 ATTACHMENT QUAD CITIES STATION THIRD TEN-YEAR INTERVAL IST PLAN REVISION 9311040143 931028 C
t 3
IST PLAN EXECUTIVE
SUMMARY
PAGE BLSCRIPTION OF CHANGE il Changed PUMPS page number in table from 2-12 to 217 1 14 Under Pump 2 2302, Vibration, Added " Addendum" after RP-00A 2-4 Added Summary for RP-00A ADDENDUM 2 5 to 2 6 RP-00A, deleted specific reference to HPCI.
2-7 to 211 RP-00A ADDENDUM, New Document 2-12 to 2-17 RP-11 A, RP 52A, Page number changes only, no change in content s
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IST PLAN PAGE REPLACEMENT INSERUCTIONS REMOVE INSERT PAGE PAGE 11 11 1 14 1 14 2 4 TO 2-1 22-4 to 2-17
Quad Cities Wuclear Power Station, Units 1 and 2 INSERVICE TESTING PLAN INFOPRATION COMMON TO PUMPS AND VALVES j REVISION SIR 9%%Y SHEET
' Effective Page(s) Rev. .
INFORMATION COMMON TO PUMPS AND VALVES i to v 4 1-1 to 1-2 4 2-1 to 2-10 4 PUMPS 1-1 to 1-15 4 2-1 to 2-17 4 3-1 to 3-3 4 4-1 to 4-2 4 5-1 to 5-2 4 VALVES 1-1 to 1-187 4 2-1 to 2-65 4 3-1 to 3-5 4 4-1 to 4-21 4 5-1 to 5-2 4 ,
6-1 to 6-2 4 Revision 4 PUMPS AND VALVES ii
- Quad Cities Nuclear Power Station, Units 1 and 2 INSERVICE TESTING PLAN - PUMPS Table 1.0-2 UNIT 2 PUMP LISTING PUMP P&ID DWG IST TEST TEST RELIEF TECHNICAL NUMBER NUMBER COORD CLASS TYPE FREQ REQUEST POSITION 2A-1102 M-0082 D-7 2 INLET OTLY RP-11A PRESSURE DIFFERNTL RP-11A PRESSURE FLOW RATE VIBRATION RP-00A BEARING RP-00B TEMPERATURE FUNCTION: STANDBY LIQUID CONTROL PUMP 2A 2B-1102 M-0082 E-7 2 INLET QTLY RP-11A PRESSURE DIFFERNTL RP-11A PRESSURE FLOW RATE VIBRATION RP-00A BEARING RP-00B TEMPERATURE FUNCTION: STANDBY LIQUID CONTROL PUMP 2B 2-2302 M-0087 A-4 2 SPEED QTLY INLET PRESSURE DIFFERITI'L PRESSURE FLOW RATE VIBRATION RP-00A Addendum BEARING RP-00B TEMPERATURE FUNCTION: HIGH PRESSURE COOLANT INJECTION Revision 4 PUMPS 1-14
Quad Cities Nuclear Power Station, Units 1 &2 INSERVICE TESTING PLAM - PUMPS Table 2.0-1 RELIEF REQUEST SUMMARIES RELIEF REQUEST
SUMMARY
RP-00A Tables IWP-3100-1 and -2, IWP-4510 Vibration velocity will be used to assess pump mechanical degradation in lieu of vibration displacement. Vibration velocity is more sensitive than vibration displacement to all modes of pump degradation.
RP-00A Tables IWP-3100-1 and -2, IWP-4510 ADDENDUM Unit 2 HPCI has historically exhibited high vibrations not due to pump degradation. This Addendum is an interim relief to increase the upper Alert limit to allow ..w ral frequency testing until the U2 HPCI is modified to re?". the vibrations to meet the ranges specified in R1-sdA.
RP-00B IWP 3100, Table IWP-3100-1 Bearing temperature is not a particularly useful test. Pump bearing vibration tests will detect mechanical problems well before bearing temperature begins to increase.
RP-11A IWP-3100, Table IWP-3100-1, IWP-3110 Differential pressure and suction pressure cannot be measured for the Standby Liquid Control pumps. All evaluations of pump performance will be based on discharge pressure. Since these pumps are positive displacement pumps, discharge pressure is just as sensitive to change as differential pressure.
RP-52A IWP-3100, Table IWP-3100-1, IWP-3110 Differntial pressure and suction pressure cannot be measured for the Diesel Fuel Oil Transfer pumps. All evaluations of pump performance will be based on discharge pressure. Since these pumps are positive displacement pumps, discharge pressure is just as sensitive to change as differential pressure.
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Revision 4 PUMPS l 2-4 4 I M.
Quad . Cities Nuclear Power Station, Units 1 & 2 INSERVICE TESTING PLAN - PUMPS RELIEF REQUEST NUMBER: RP-00A (Sheet 1 of 2)
COMPONENT IDENTIFICATION CODE PUMP NUMBER CLASS DRAWING NUMBER COORDINATE call pumps > 1, 2,
&3 FUNCTION (S1 All pumps in the IST Plan are affected. These pumps are required to perform a specific function in shutting down the reactor or mitigating the consequences of an accident and are provided with an emergency power source.
CODE REQUIREMENT ;
Table IWP-3100-1, " Inservice Test Quantities," Vibration amplitude (V)
Table IWP-3100-2, " Allowable Ranges of' Test Quantities,"
Acceptable, Alert Range, and Required Action-Range for vibration amplitude i Articls IWP-4510, " Vibration Amplitude," The Code requires vibration measurements to be recorded and analyzed based on displacement in mils (thousandths of an inch).
BASIS FOR RELIEF 10CFR50. 55a (a) (3 ) (i) , a neceptable level of quality and safety" Low amplitude, high frequency vibration due to misalignment, imbalance, or bearing wear is difficult to detect via vibration amplitude measurements when pump speed is greater than or equal l to 600 RPM.
Vibration velocity measurements are much more sensitive to small changes that are indicative of developing' mechanical problems.
Vibration velocity is a far more informative reading because it accounts for both displacement and frequency range. A vibration monitoring program based on velocity is more comprehensive than
- that required by the Code.
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I Revision 4 PUMPS 2-5 L
Quad Cities Nuclear Power Station, Units 1 & 2 INSERVICE TESTING PLAN - PUMPS RELIEF E REQUEST NUMBER: RP-00A (Sheet 2 of 2)
PROPOSED ALTERNATE TESTING Pump vibration measurements will be taken in vibration velocity (inches per second) if the pump speed is greater than or equal to 600 RPM. The allowable ranges of vibration velocity will be based on Table 1.
Table 1 ALLOWABLE _ RANG _ES OF VIBRATION VRLOCITY Acceptable Required Pump Type Range Alert Range Action Range Centrifugal with s 2. 5 V, or s > 2. 5 V, and > 6.0 V, speed a 600 RPM 0.325 ips s 6. 0 V, or or whichever is less > 0.325 ips > 0.700 ips and s 0.700 ips whichever is less whichever is less Reciprocating s 2.5 V, > 2 . 5 V, and > 6.0 V, s 6.0 V, Gear s 2.5 V, > 2 . 5 V, and > 6.0 V, s 6.0 V, V,: vibration reference value ips: inches per second mils: thousandths of an inch (applies to low speed pumps only)
NOTE: There are no. safety related centrifugal pumps that operate at speeds < 600 RPM at Quad Cities. There are-no safety related vertical line shaft pumps at Quad Cities.
APPLICABLE TIME PERIOD Relief is requested for the 3rd ten (10) year interval.
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Revision 4 PUMPS I 2-6
Quad Cities Nuclear Power Station, Units 1 &2 INSERVICE TESTING PLAN - PUMPS s.
RELIEF REQUEST NUMBER: RP-00A ADDENDUMfSheet 1 of St ,
_THJS IS A TEMPORARY RELIEF REOUEST COMPONENT IDENTIFICATION CODE EUMP NUMBER .CLAES 2-2302 DRAWING NUMBER COORDINATE 2 M-87 A-4 EUNCTION(S)
The Unit 2 High Pressure Coolant Injection (HPCI) pump is required to inject water into the reactor vessel under Loss of Coolant Accident conditions which do not depressurization of the pressure vessel. result in a rapid
.qqDE REQUIREMENT Table IWP-3100-1,
" Inservice Test Quantities," Vibration amplitude (V)
Table IWP-3100-2,
" Allowable Ranges of Test Quantities,"
Acceptable, Alert Range, and Required Action Range for vibratior. amplitude Article IWP-4510,
" Vibration Amplitude," The Code requires vibration measurements to be recorded and analyzed based on displacement in mils (thousandths of an inch) .
BASIS FOR RELIEF 10CFR50. 55a (a) (3 ) (1) ,
" acceptable level of quality and safety" vibration limits to the Unit 2 HPCI pump. Interim relief is requested to based on the consistently high vibration level historyThis interim relief is experienced with the inboard bearing (Bearing 3) of the main pump on Unit 2 HPCI.
Since 1988, vibration amplitudes on bearing 3.the station has made gradual progress in reducin From January 1988 until June 1988 ranged from 0.500 inches per secon,dthe (ips)vibrations to 0.750onips Bearing in the3 horizontal direction and 0.344 direction. The Acceptable Range at thatips to 0.489 ips in the vertical time was 0 -
which was Request from PR-1. the 2nd Ten Year Interval IST program Relief 0.900 ips WA/NE-5, Table 2. This limit was based on ASME Technical Paper #78-Revision 4 PUMPS h,
- Quad Cities Nuclear Power Station, Units 1 & 2 INSERVICE TESTING PLAN - PUMPS RELIEF REQUEST NUMBER: RP-00A ADDENDUM (Sheet 2 of 5)
BASIS FOR RELIEFfCONT.)
Although the vibrations were considered at that time to be in the acceptable range, the station realized that there was a need to reduce the vibration levels. -
In June 1988, the station installed a five vane split impeller. [
into the HPCI booster pump. This vendor-recommended change was implemented to eliminate a vane passage frequency which was resonating the crossover piping from the booster pump to the main pump. The resonating crossover piping induced a high horizontal vibration on the inboard bearing bracket of the main pump (Bearing 3). The impeller change and an alignment of the turbine i to the main pump resulted in a reduction in horizontal vibration to 0.494 ips and vertical vibration to 0.344 ips.
In May 1992, the station made another attempt to reduce vibrations by balancing the HPCI Turbine rotor and performing another alignment. This work resultyd in a reduction in horizontal vibration in Bearing 3 tc D.189 ips. However the vertical vibration in Bearing 3 increased to 0.614 ips. During this time the station revised the IST Program to reflect the more conservative vibration limits specified in ANSI /ASME OM-6. This placed the Unit 2 HPCI in the ALERT range and 45-day increased frequency testing commenced. The station also decided to try '
specialized alignment equipment called Permalign to measure and track the thermal and dynamic movements of the HPCI train._ The resulting Permalign information was intended to provide insight into how to align the HPCI train so that the thermal and dynamic movements would allow the train to grow into alignment while running. The station has previously used the Permalign equipment on such constant running pumps as the Reactor Feed and Condensate pumps. However, since this was first time the Permalign process was used on HPCI, the information gathered was considered to be for information only.
- The Permalign equipment is designed to identify thermal and dynamic movement in rotating assemblies. It is normally used on constantly running equipment. Standard practice is to zero out the Permalign lasers when the equipment is in the " cold" condition. The test is then initiated in conjunction with starting up the rotating equipment. The rotating equipment is then allowed to reach its nornal operating parameters and target values are obtained with the Permalign lasers. This data is then '
used at a later date when the rotating equipment is re-aligned in the " cold" condition. During this re-alignment process, the rotating equipment is purposely offset in accordance with the previously obtained target values so that the equipment thermally and dynamically " grows" into alignment.
In the case of the HPCI Permalign test, the HPCI was run,for approximately twenty' minutes. The data gathered by the Permalign equipment was in relation to the thermal and dynamic changes Revision 4 PUMPS 2-8
Quad Cities Nuclear Power Station, Units 1 &2 INSERVICE TESTING PLAN - PUMPS RELIEF REQUEST NUMBER: RP-00A ADDENDUM (Sheet 3 of 5)
BASIS FOR RELIEF (CONT. )
identified for the first twenty minutes of run time. The station believes that the twenty minute run time was insufficient for the HPCI to reach its full thermal and dynamic growth.
In August 1992, the station took a Limiting Condition of Operation (LCO) to perform alignments using the Permalign data obtained in May 1992. Some limited moves were conducted using this data and the resulting vibrations on bearing 3 ranged from 0.305 to 0.369 ips in the horizontal and 0.325 to 0.529 ips in the vertical direction. Using all of the Permalign data to the fullest extent would have entailed perfonning modifications such as the shaving of the pump footings and the cutting and redesign of the pump's discharge piping supports. The station was reluctant to perform these tasks because of the cost involved in designing and performing these modifications and the level of uncertainty in the interpretation of the Permalign data. This uncertainty was based on the fact that the data was taken after only a twenty minute run time, which was insufficient for the HPCI to reach its full thermal and dynamic growth.
As part of an effort to improve the MPCI System performance, the station plans to perform some significant maintenance activities on the Unit 2 HPCI during the Fall 1993 maintenance outage. Five Exempt changes (minor modifications) are scheduled which will replace all of the oil pressure switches, upgrade the level switches, and upgrade the flow and pressure transmitters.
Additionally, nine Corrective Maintenance work requests are scheduled which include valve repairs, local valve control :
stations and control switch repairs, replacement of temperature recorders, and the disassembly of the motor gear unit.
As part of this work, the station will make adjustments to the HPCI motor speed changer and motor gear unit to adjust the pump flow characteristics to better meet the pump curve. The station will also take alignment readings of the HPCI turbine / pump train in the cold condition using the station's regular alignment equipment to establish a baseline for future Permalign tests.
The pump's vendor has also recently recommended a modification intended to reduce another vane passage frequency which was resonating the crossover piping from the booster pump to the main pump. It is believed that the resonating crossover piping is inducing a high vibration en the inboard bearing bracket of the main pump (Bearing 3). The recommendation is to disassemble the-booster pump and cut the volute lips to increase the " Gap B" clearance. The station plans on performing the Gap "B" clearance Modification during the Q2R13 Refuel Outage in September 1994. Since an investigation into the Permalign process revealed that the actual Permalign data would be affected by the higher flow rates of the system and the gap "B" clearance, Revision 4 PUMPS 2-9
Quad Cities Nuclear ~ Power Station, Units 1 &2-INSERVICE TESTING PLAN --PUMPS RELIEF REQUEST NUMBER: RP-00A ADDENDUM (Sheet 4 of 5)-
BASIS FOR RELIEF (CONT.)
the station plans on completing these modifications and maintenance actions prior to retaking the Permalign data.
Once the listed modifications and maintenance actions are complete, the station plans to enlist the assistance of the Permalign technical representative to incorporate a new improved set up process for this device. The assistance is intended to allow the station to gain the most effective use of the Permalign and eliminate the uncertainties in the previously collected Permalign data. Preliminary d.iscussions indicate that an improved set up process may be required which will entail the '
fabrication of new brackets to support the Permalign device components. The station plans to be ready to retest using the Permalign device at the end of Q2R13 (December 1994) and -
evaluating the results with technical experts thereafter. Actual alignment moves based on the new Permalign data would then be scheduled to be performed during the following refueling cutage, Q2R14 (Spring 1996).
Spectral Analysis of the current vibration data indicates no evidence of bearing degradation on any of the Unit 2 HPCI pump bearings. The pump vendor considers the current vibration level of 0.374 ips on bearing 3 to be "relatively moderate" and only recommended to continue monitoring for any sudden increases in vibration amplitude until the Gap "B" clearance Modification is performed during the Q2R13. Spectral Analysis is routinely performed on all of the bearings on the Unit 2 HPCI during the quarterly IST surveillance. Based on the spectral analysis and-the vibration improvements already achieved, the' station is confident that the existing vibration levels are not indicative of a degraded condition. If the planned maintenance and i
modifications prove to be successful in reducing the vibration _
levels consistently below 0.300 ips, this interim relief request will be withdrawn and the provisions of RP-00A will be followed for the Unit 2 HPCI.
EROPOSED ALTERNATE TESTING The allowable ranges of vibration velocity for Unit 2 HPCI will ,
be based on Table 2. The purpose of the increased Alert Range limit of 0.425 ips is to relieve the station of_having to test the Unit 2 HPCI on an increased frequency which would cause additional normal wear of the pump. Since the increased frequency test is to monitor a degraded condition and no degradation has been detected, then there is no_ benefit to running the HPCI pump on an increased frequency. However, 0.425 ips is also relatively close.enough.to the highest measured vibration data, so that if any additional pump degradation occurs, the pump would still be placed in the Alert Range and on '
an increased monitoring frequency.
Revision 4 PUMPS 2-10
Quad Cities Nuclear Power Station, Units 1 &2 INSERVICE TESTING PLAN - PUMPS j RELIEF REQUEST NUMBER: RP-00A ADDENDUM (Sheet 5 of 5)
Table 2 ALLOWABLE. RANGES OF VIBRATION VELO _C_I_TY Acceptable Ret,uired Pump Type Range Alert Range Action Range ,
Centrifugal with s 1. 5 V, or > 1. 5 V, and > 2 . 5 V, or speed a 600 RPM s 0.425 ips s 2.5 V,or > 0.700 ips (U2 HPCI oNLY) whichever is less > 0.425 ips whichever is less and s 0.700 ips i whichever is less '
V,: vibration reference value ips: inches per second APPLICABl.E TIME PER7_OJ2 Interim Relief is requested for until the end of Q2R14 (June 1996) or until the station is successful in reducing the vibration levels consistently below 0.300 ips. Whichever is ,
sooner.
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k Revision 4 PUMPS .
2-11
- Quad Cities- Nuclear Power Station, Units 1, & 2 INSERVICE TESTIWG PLAN - PUMPS RELIEF REOUEST NUMBER: RP-00B (Sheet 1 of 2)
COMPONENT IDENTIFICATION CODE PUMP NUMBER CLASS DRAWING NUMBER COORDINATE
<All pumps > 1, 2,
&3 FUNCTION (S)
All pumps in the IST Plan are affected. These pumps are_ required to perform a specific function in shutting down the reactor or mitigating the consequences of an accident and are provided with an emergency power source.
CODE REQUIREMENT IWP-3100, " Inservice Test Procedure," The test quantities shown in Table IWP-3100-1 shall be measured or observed and recorded.
Table IWP-3100-1, " Inservice Test Quantities," Bearing Temperature (T.) shall be measured.
SASIS FOR RELIEF 10CFR50. 55a (a) (3 ) (i) , " acceptable level of quality and safety" Pump bearing vibration monitoring can be used to detect: worn bearings, misalignment of bearings, a change in the balance of rotating parts, a change in hydraulic forces, and general pump integrity. Quarterly pump bearing vibration measurements, combined with an observation of lubricant level / pressure, are more sensitive than bearing temperature measurements to the types of problems that may be exhibited by increased bearing temperature. Since bearing vibration monitoring is more sensitive and is performed more frequently, there is no need to measure bearing temperature.
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l Revision 4 PUNPS 2-12
- Quad Cities Nuclear Power Station, Units 1 & 2 3
INSERVICE TESTING PLAN - PUMPS R
^
RELIEF REQUEST NUMBER: RP-00B (Sheet 2 of 2)
BASIS FOR RELIEF (Continued)
Given controlled environmental conditions, bearing temperature measurements may be capable of detecting pump degradation, but the following problems exist in a power plant setting:
- 1. Many bearings are lubricated by the pumped fluid; .and the temperature of the pumped fluid will change depending on the season.
- 2. Long run times to stabilize bearing temperature are'not practical for the HPCI pump (during the summer, the Suppression Pool temperature may approach the 95 F limit because the HPCI turbine exhaust is directed to the Suppression Pool).
These environmental condition variables make it extremely difficult, if not impossible, to evaluate bearing temperature test results.
Bearing temperature measurements could potentially be misinterpreted and they do not provide any additional information concerning the pump's condition. This inservice test quantity is impractical to measure and evaluate.
PROPOSED ALTERNATE TESTING In comparison to the other tests used to detect mechanical-and hydraulic change, a bearing temperature test does not provide additional, meaningful information. Vibration velocity measurements are'much more sensitive to pump degradation. No alternate testing is appropriate.
APPLICABLE TIME PERIOD Relief is requested for the 3rd ten (10) year interval.
Revision 4 PUMPS 2-13
Quad Cities Nuclear Power Station, Units 1 &2 i INSERVICE TESTING PLAN - PUMPS RELIEF REQUEST NUMBER: RP-11A (Sheet 1 of 2)
COMPONENT IDENTIFICATIOR CODE PUMP NUMBER CLASS DRAWING NUMBER COORDINATE Unit 1 1102A 2 M-0040 D-7 1102B 2 M-0040 E-7 Unit 2 1102A 2 M-0082 D-7 1102B 2 M-0082 E-7 -
FUNCTION (S)
The Standby Liquid Control (SBLC) pumps are used to inject poison (sodium pentaborate) into the reactor vessel, if the Control Rod Drive Hydraulic system fails. The poison injected by the SBLC system will absorb neutrons and control reactivity.
CODE REOUIREMENT IWP-3100, " Inservice Test Procedure," The test quantities shown in Table IWP-3100-1 shall be measured or observed and recorded.
Table IWP-3100-1, " Inservice Test Quantities," Inlet Pressure
( P,) shall be measured before pump startup and during the test. Differential pressure (dP) shall be measured.
IWP-3110, " Reference Values," Differential Pressure will be duplicated during subsequent inservice testing.
BASIS FOR RELIEF 10CFR50. 55a (a) (3) (i) , " acceptable level of quality and safety" The SBLC inservice test is conducted using the SBLC Test Tank ,
(1104 @ B-7), rather than the Standby Liquid Control Tank (1103 e i A-10). The Test Tank is filled at the start of the test (minimum water level 16"), and the Test Tank level remains virtually constant throughout the inservice test.
Revision 4 PUMPS 2-14 J
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Quad Cities Muclear Power Station, Units 1 & 2 INSERVICE TESTING PLAN - PUMPS RELIEF-REQUEST NUMBER: RP-11A (Sheet 2 of 2)
BASIS FOR RELIEF (cont'd)
Inlet pressure instrumentation was not installed.for the SBLC pumps. Inlet pressure before the test (P S ) could be calculated based on Test Tank level, but this calculated-hydrostatic ,
pressure is meaningless once the pump starts. L The SBLC pumps are positive displacement pumps. The performance of the SBLC pumps is not sensitive to changes in pump inlet ~
pressure. SBLC discharge pressure can be substituted for differential'> *ssure, and the ability to detect changes in hydraulic pezio ,ince will not be affected.
OM-6 recognizes the validity of this approach and requires that outlet pressure be measured in lieu of AP.
PROPOSED ALTERNATE TESTING Discharge pressure will be substituted for differential pressure in any test requirements or acceptance criteria for the SBLC pumps.
APPLICABLE TIME PERIOD ,
Relief is requested for the 3rd ten (10) year interval.
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Revision 4 PUMPS I 2-15
- Quad Cities' Nuclear Power Station, Units 1 &2 INSERVICE TESTING PLAN - PUMPS RELIEF REOUEST NUMBER: RP-52A (Sheet 1 of 2)
COMPONENT IDENTIFICATION CODE PUMP NUMBER CLASS PRAWING NUMBER COORDINATE Unit 1 5203 NC M-0029 F-3 Unit 1/2 5203-1/2 NC M-0029 F-3 Unit 2 5203 NC M-0029 F-3 FUNCTION (S)
The Diesel Fuel Oil Transfer pumps are used to keep the Diesel Fuel Oil Day Tank (5202) full while the diesel generator is '
required to generate emergency power.
CODE REQUIREKERT IWP-3100, " Inservice Test Procedure," The test quantities shown in Table IWP-3100-1 shall be measured or observed and recorded.
Table IWP-3100-1, " Inservice Test Quantities," Inlet Pressure
( P;) shall be measured before pump startup and during the test. Differential pressure (dP) shall be measured. P IWP-3110, " Reference Values," Differential Pressure will be duplicated during subsequent inservice testing.
BASIS FOR RELIEF 10CFR50. 55a (g) (6) (i) , " impractical" 10CFR50. 55a (a) (3 ) (1) , " acceptable level of quality and safety" Inlet pressure instrumentation was not installed for thefDiesel Fuel Oil Transfer pumps. The Diesel Fuel Oil Storage Tanks (5201) are located below the Diesel Fuel Oil Transfer pumps. .
Therefore, the suction pressure will be negative, and the suction-pressure before the test will vary from test-to-test depending.on the tank level. Positive displacement, gear pumps are used in this application because they do not require positive suction head for proper operation. Diesel Fuel Oil Transfer pump Revision 4 PUMPS 2-16
Quad Cities Nuclear Power Station, Units 1 & 2 INSERVICE TESTING PLAN - PUMPS F_E_T.,I E F R E Q U E S T N U M B E R : RP-52A (Sheet 2 of 2) discharge pressure can be substituted for differential pressure,.
and the ability to detect changes in hydraulic performance will not be affected.
OM-6 recognizes the validity of this approach and requires that outlet pressure be measured in lieu of AP.
PROPOSED ALTERNATE TESTING Discharge pressure will be substituted for differential pressure in any test requirements or acceptance criteria for the Diesel Puel Oil Transfer pumps.
APPLICABLE TIME PERIOD Relief is requested for the 3rd ten (10) year interval.
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l Revision 4 PUNTS 2-17 l