ML20056D601
| ML20056D601 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/19/1991 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20056D596 | List: |
| References | |
| 2-PT-24.6.4, NUDOCS 9308170141 | |
| Download: ML20056D601 (50) | |
Text
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- ENCLOSURE 5 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKET NOS. 50-325 & 50-324 OPERATING LICENSE NOS. DPR-71 & DPR-62 REQUEST FOR LICENSE AMENDMENT SERVICE WATER SYSTEM L l 2-PT-24.6.4 l'- i SERVICE WATER SYSTEM HYDRAULIC PERFORMANCE TEST UNCLUDING RESULTS) .l 1
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9308170141.930809 PDR ADDCK 05000324 p PD,R-i- ._ _- _ _____
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- : ente COMPrzTED _ / 2 //
UNIT 4 POWER 6 CMWE -A POREMAN/ SUPERVISOR ##/4 / Gr#/N(
< REASON FOR TEST (check one or more) :
M outine surveillance OUP # __
UR/JO # -- _-
Other (Explain) k CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAN ELECTRIC PIANT
- IBIIT 2
. . PROCEDURE TYPE: PERFORMANCE TEST NUMBER: ~ 2-PT-24.6.4 PROCEDURE TITLE: SERVICE WATER SYSTEM HYDRAULIC PERFORMANCE.
TEST-FREQUENCY: A. Once every Refueling B. ' Heat Exchanger Performance Monitoring =-
as. required-l_I REVISION 2 APPROVED BY:- Y/Yfs e, General Manager / _
4 Date- '
-Manager- ' Technical Support Page 1 of 48
" x2 FT-24.6.4 Rev. 2 .
- h! l4m f -a - _ - _ - - _ _ - - -
J DATE COMP 12TED- _
t POWER
' UNIT - . CMWE _ _
FOREMAN / SUPERVISOR REASON FOR TEST'(check one or more) : !
-Routine Surve111ance -
OWP #.
VR/JO w :
- r Other (Explain)
- CAROLINA POWER & LICHT COMPANY .
BRUNSVICK STE#w ELECTRIC PLANT i
UNIT 2
.. PROCEDURE TYPE: PERFORMANCE TEST NUMBER: 2-PT.24.6.4
~
PROCEDURE TITLE: SERVICE WATER SYSTEM HYDRAULIC PERFORMANCE TEST FREQUENCY: A. Once every Refueling- ;
B. Heat Exchanger Performance Monitoring-as required l
1 REVISION 2 !
s APPROVED BY:- ,, , __
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Mam; , - Techni:a1 Sapport Li i
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[ 2 PT.24.6'.4 Rev. 2-' Page 1 of'40 .
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i UNIT 2 PT-24.6.4 -
LIST OF EFFECTIVE PAGES ,
2J1111 Revision 1-48 2 i
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2'PT-24.6.4 Rev. 2 .Page 2 of 48 I l.
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UNIT 2
, PT-24.6.4 TABLE OF CONTENTS SECTION PAGE 1.0 FURPOSE . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
2.0 REFERENCES
, . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.0 GENERAL PREREQUISITES . . . . . . . . . . . . . . . . . . . . . . . 5 4.0 CENERAL PRECAUTIONS AND LIMITATIONS . . . . . . . . . . . . . . . . 5-5.0 RESPONSIBILITIES . . . . . . . . . . . . . . . . . . . . . . . . . . 6 6.0 SPECIAL TOOLS AND EQUIPMENT , . . . . . . . . . . . . . . . . . . . 6 7.0 ACCEPTANCE CRITERIA . . . . . . . . . . . . . . . . . . . . . . . 8 8.0 TEST EQUIPMENT SETUP . . . . . . . . . . . . . . . . . . . . . .. . . 8 9.0 PROCEDURE STEPS . . . . . . . . . . . . . . . . . . . . . . . . . . 9 10.0 RESTORATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 11.0 CONTROLOTRON FIDW INSTRUMENTATION SETUP AND DATA ACQUISITION GUIDELINES . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 ATTACHMENTS 1 2A NUCLEAR SERVICE WATER PUMP DISCHARGE SITE SETUP . . . . . . . . . . 25 2 2B NUCLEAR SERVICE WATER PUMP DISCHARGE SITE SETUP . . . . . . . . . . 28 3 No. 3 DIESEL CENERATOR JACYJ.T WATER COOLER SW SITE SETUP . . . . . . 31 4 No. 4 DIESEL GENERATOR JACKET WATER COOLER SW SITE SETD2 . . . . . 35 5 VITAL HEADER (FROM NUCLEAR HEADER) SW INLET SITE SETUP . . . . . . . 39 CERTIFICATIOP AND REVIEW FORM . . . . . . . . . . . . . . . . . . . . . . 43 DATA SHEET 1 . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . 44 DATA SHEET 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 DATA SHEET 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 46 DATA SHEET 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 47 DATA SHEET 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 2 PT-24.6.4 Rev. 2 Page 3 of 48
i UNIT 2 PT-24.6.4 1.0 ESE05%
1.1 The purpose of this Performance Test is to demonstrate, at refueling outa5e frequency, the Service Water System is hydraulically capable -
of meeting the design basis flow requirements to safety related components and provide a data source for non-modification performance trending of the Se rvice Water System and individual components thereof. This test is not intended to demonstrate particular set flow values at each component, but will collect data from which performance can be extrapolated. This test will also quantify Service Water leakage from the Nuclear to Conventional i Header.
Flow measurement at individual components will be accomplished utilizing Controlotron portable (temporary) ultrasonic flow metering '
systems. To observe system trending from performance to performance of this test the locations where the flow measurement are taken and the equipment se* up must be duplicated as close as possible every time this procedure is performed. Attachments 1 through 5 provide the means to accomplish this by establishing and recording initial setup locations and documenting any deviations thereafter.
2.0 REFERENCES
2.1 Technical Specification Interpretation, TSI 90-03 (Rev. 0) 2.2 FSAR Section 5.4.7, Residual Heat Removal System 2.3 FSAR Section 7.4.3, Residual Heat Removal (RHR) System, Reactor Shutdown Cooling System Mode 2.4 FSAR Section 9.2.1, Service Water System 2.5 FSAR Section 9.2.2, Reactor Building Component Cooling Water System 2.6 FSAR Section 15.0, Accident Analysis 2.7 Operating Procedure OP-43, Service Water System 2.8 operating Procedure OP-43.1, Chlorination System 2.9 Operating Procedure OP-44, Turbine Building Closed Cooling Water System 2.10 Operating Procedure OP-29, Circulating Water System g, 2.11 System Description SD-43, Servics Vater System 2.12 Drawings r
D 02041, Sheets 1, 2 and 3 Service Water System, Unit 2
, D-02274 Sheets 1 and 2, Diesel Cenerator Service Water and Demine;alized Vater System, Units 1 and 2 2 PT-24.6.4 Rev. 2 Page 4 of 48
UNIT 2 PT-24.6.4 2.0 Eg[IErNCES D-02537, Sheets 1 and 2, Reactor Building Service Water System, Unit 2 2.13 The Following Contro1otron" Field Manuals, Bulletins and Technical Advisories.
2.13.1 Field Manual 990PFM-1C-A 2.13.2 Field Manual 990PFM-2B 2.13.3 Bulletin 991XA 2.13.4 Technical Advisories #1, #3, #8, #14, and zero reversal procedure.
3.0 CENERAL PREREOUISITES 3.1 The Service Water System is lined up for normal operation per OP-43 (with Conventional Service Water, Nuclear Service Water, and RHR Service Water [A and B Loop] operable) with any deviation from the normal lineup affecting this procedure noted on this procedure's Certification and Review Form.
3.2 No other testing or maintenance is in progress that will adversely affect the performance of this test.
3.3 Unit 2 TBCCW will be diverted to the 2C TBCCW Heat Exchanger where it will be cooled by Unit 1 Service Water.
3.4 Unit 2 Circulating Water System is shut down and not in service.
3.5 Test gauges are to be installed at Pressure Switch, 2-SW-PS-3213, Pressure Switch 2-SV-PS-3214, Pressure Indicator, 2-SW-PI-819, and Pressure Indicacor, 2-SU-PI-821.
4.0 CENERAL PRECAUTIONS AND LIMITATIONS 1 4.1 When taking readings to be recorded during the performance of this procedure, the indicator / pointer fluctuation should be reduced to a minimum. An instrument isolation valve upstream of the instrument may be throttled to reduce fluctuation.
4.2 One RHR Pump Room Cooler shall be aligned to the NSW Header whenever gg the NSW Header is in service.
4.3 At Step 9.3.34, the Unit 2 Conventional Header will be depres-surized, and therefore all loads off the Unit 2 Conventional Header are to be. shut down or aligned to an alternate source of cooling.
4.4 Unit 2 shall be in Mode 4 or 5 during the performance of this procedure.
2 PT-24.6.4 Rev. 2 Page 5 of 48
l UNIT 2 PT-24.6.4 4.0 G W jt PRECAUTIONS AND LIMITATIONS 4.5 St*ps can be performed out of sequence with the concurrence of the Shif t Supervisor and the responsible engineer.
5.0 RESPONSILILITIES 5.1 Responsible Engineer: Determine system components which require flow ,
monitoring during the performance of this procedure, direct the performance of this procedure to include mobilization of forces for setup of temporary flow monitoring instrumentation, collection of l data and transmit the collected data to NSD for analysis. During initial performance of this Performance Test during Refueling Outage l B210R1, pipe wall thicknesses (per Section 11.3.4) will be obtained at each flow monitoring site location. On subsequent performances l of the Performance Test, the responsible engineer will evaluate if l pipe wall thicknesses (per Section 11.3.4) are needed to be determined if flow monitoring site locations have not changed. l
5.2 Operations
Operate plant systems, equipment and valves as directed l
by this procedure.
5.3 Maintenance
Install appropriate test equipment and gauges as directed by the responsible engineer.
5.4 NED: An".*tyze collected data and determine if system capabilities j are within the system design basis.
6.0 SPECIAL TOOLS AND EOUIPMENT 6.1 The following test gauges:
Preferred Range Acceotable Rance 6.1.1 Test Gauge #1 Heisse 0 - 150 psig 0 - 100 psig j i
6.1.2 Test Gauge #2 Heisse 0 - 150 psig 0 - 100 psig 6.1.3 Test Gauge #3 Heisse 0 - 150 psig 0 - 100 psig 6.1.4 Test Gauge #4 Heisse 0 - 150 psig D - 100 psig i
6.2 Uniflow Ultrasonic Flowmeter System 990 Portable Computers '
(Contro1otron) SB version (115 VAC Power) Group 4 (operates transducers sizes 1, 2, 3, 4, and 4A) with the appropriate transducer, cables and mounting tracks as necessary to support flow data collection during this procedure.
6.3 Ultrasonic wall thickness measuring. instruments (as needed).
EQIE:
A suitable test gauge shall have a total range of less than or equal to three-times the reference value for the parameter being monitored and an adequate range to prevent damage during use.
2 PT-24.6.4 Rev. 2 Page 6 of 48-
UNIT 2 PT-24.6 4.
6.0 M L TOOLS AND EOUIPMElq 6.4 A suitable test instrument may be installed in place of any instrument to obtain data. .
6.4.1 Instrument replaced by test instrument #4 6.4.2 Shift Supervisor's permission to replace //S Instrument '
6.4.3 Range of test instrument 8h 6.4.4 Instrument I.D. No. MM 6.4.5 Calibration due Date Nb 6.5 The following installed instruments with the required data ,
recorded below:
6.5.1 2-SW-PDIC-138 Calibration Date 3 E9/ 9l
/ [t/-l 6.5.2 2-SW-PDIC-138 Calibration Due Date 1 /10 /42.
6.5.3 2-SW-PDIC-140 Calibration Da*.* 3 /29 /H 6.5.4 2-SW-PDIC-140 Calibration Due Date 2 /lO /92 6.5.5 2-SW-PI-131-1 Calibration Date / 22/ $ 1 6.5.6 2-SW-PI-131-1 Calibration Due Date I /20 f92.
6.5.7 2-SW-PI-144 Calibration Date '7 / ZG f41 6.5.8 2-SV-PI-144 Calibration Due Date I /20 /92-6.5.9 2-SW-PI-145 Calibration Date 7/ 25 f9l l 6.5.10 2-SW-PI-145 Calibration Due Date I /20/92.
6.5.11 2-SW-PI-143-1 Calibration Date I / 11/ kI 6.5.12 2-SW-PI-143-1 Calibration Due Date I / Z0 /9 2.
6.5.13 2-SW-FI-5114 Calibration Date b / 5 / 91 6.5.14 2-SW-FI-5114 Calibration Due Date II / ' D /9 7-6.5.15 2-SW-FI-5115 Calibration Date 1 / 3 / kI
. 6.5.16 2-SW-FI-5115 Calibration Due Date lI / 3Of 9 2. -
,, 2 PT-24.6.4 Rev. 2 Page 7 of 48
UNIT 2 FT-24.6.4 6.0 SPECut To0LS AND EOUIPMENT 6.5.17 2-SCW-LT-285 Calibration Date i0 fio f 9i 6.5.18 2-SCV-LT-285 Calibration Due Date __ l/ b /91 6.5.19 2-SW-FI-1158 Calibration Date 7 ,l , $.N 6.5.20 2-SW-FI-1158 Calibration Due Date I /b / 92-6.5.21 2-E11-FT-N007A Calibration Date / / b l ',
6.5.22 2 -E11-FI-N007A Calibration Due Date 5 f 4f9L 6.5.23 2-E11-FI-R602A Calibration Date II / b / SI 6.5.24 2-E11-FI-R602A Calibration Due Date /1791
/
6.5.25 2-E11-FT-N007B Calibration Date 5 /9 f qt 6.5.26 2-E11-PT-N007B Calibration Due Date 5 fyfqz 6.5.27 2-E11-FI-R602B Calibration Date II / b / Sl 6.5.28 2-E11-FI-R602B Calibration Due Date N / 17/ 92-7.0 ACCEPTANCE CRITERIA 7.1 As such, there is no set flow rate established for the-individual Servics Vater System components or the system as a whole. Ongoing '
e modifications and system degradation due to age, corrosion and wear alter flow not only at the individual components, but throughout the whole system. Data collected by this procedure will be analyzed by NED for permissible near and long term operability.
8.0 Ig1T.EOUIPMENT SETUP 8.1 Obtain permission form the Shift Supervisor to perform this section.
8.2 Setup the controlotron flow measuring equipment at the N required sites and perform the zero flow calibrations as instructed in Section 11.0 of this procedure.
2 PT-24.6.4 Rev. 2 Page 8 of 48 I
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UNIT 2-PT-24.6.4 f- 9.0 PROCEDURE STEPS 9.1 Prerequisites 9.1.1 The Service Water. System is lined up for normal operation per OP 43 with any deviation from the normal lineup affecting this procedure noted on this procedure's Certification and Review Form.
9.1.2 Both NSW Pumps are available.
9.2 Precautions and Limitations 9.2.1 The RBCCW Service Water flow rate shall not be decreased below 2500 gpm nor exceed 5500 CPM indicated at 2-SU-FI-1158-1 on RTCB Panel XU-2.
9.2.2 TBCCW and RBCCW temperatures should be closely monitored while this test is being performed. If temperatures start to rise or. fall excessively, they should be allowed to-return to normal before this test is continued.
9.2.3 The data generated by this procedure shall be atelyzed by.
NED and approval given prior to unit start-up.
9.3 Procedure Steps 9.3.1 Ensure that all prerequisites listed in Section 9.1 are met.
9.3.2 Obtain permission from the Shift Supervisor to perform this test.
9.3.3 Open 2-SW-FS-3213 Instrument Test Valve, 2-SU-PS-3213-10.
9.3.4 Open 2-SU-PS 3214 Instrument Test Valve, 2-SU-PS-3214 10.
9.3.5 % I f" 4 -819 Instrument Drain Valve.
I'SW-PI-819-6.
2-9.3.6 Open 21-SW-PI-821' Instrument Drain Valve, 2-SW-PI-821-6. -
l 9.3.7 Open, or verify open, Nuclear Service Water
\
Pump A Discharge Pressure Indicator Root Valve to 2-SU-PI-144, 2-SW-V61.
,v -
Reme Q-su>-pz- et9-i 2~PT-24.6.4 Rev. 2- ~
Page 9 of 48
UNIT 2 PT-24.6.4
- 9. StoegDigg STEPS 9.1 Prerequisites 9.1.1 The Service Water System is lined up for normal operation per OP-43 with any deviation from the normal lineup affecting this procedure noted on this procedure's Certification and Deview Form.
9.1.2 Both NSW Pumps are available.
9.2 Precautions and Limitations 9.2.1 The RBCCW Service Water flow rate shall not be decreased below 2500 gpm nor exceed 5500 GPM indicated at 2-SW-FI-1158-1 on RTGB Panel XU-2.
9.2.2 TBCCW and RECCW temperatures should be closely monitored while this test is being performed. If temperatures start to rise or fall excessively, they should be allowed to return to normal before this test is continued.
9.2.3 The data generated by this procedure shall be analyzed by NED and approval given prior to unit start-up.
9.3 Procedure Steps ,
9.3.1 Ensure that all prerequisites listed in Section /
9.1 are met.
9.3.2 Obtain permission from the Shift Supervisor to ~
perform this test.
9.3.3 Open 2-SW-PS-3213 Instrument Test Valve, 2-SW-PS-3213-10.
9.3.4 Open 2-SW-PS~3214 Instrument Test Valve, 2-SW-PS-3214-10.
( 9.3.5 Open 2-SU-PI-819 Instrument Drain valve, Tt,J. W V4 / 2-SW-PI-819-6. 3 - - - '- -
- js' )
( 9.3.6 Open 21-SW-PI-821 Instrument Drain Valve, p
2-SW-PI-821-6. p ,
9.3.7 Open, or verify open, Nuclear Service Water Pump A Discharge Pressure Indicator Root Valve' to 2-SW-PI-144, 2-SW-V61. .
Page 9 of 48 2 PT-24.6.4 Rev. 2
UNIT 2 PT-24.6.4 9.0 PROCgwar STEPS 9.3.8 Open, or verify open, Nuclear Service Water Pump B Discharge Pressure Indicatcr Root Valve 2-SW-PI-145, 2-SW-V62.
9.3.9 Verify as aligned, or align the Vital Header to I the Nuclear Header per OP-43.
9.3.10 At RTCB Panel P601 place, or verify as placed, the WE1.L WATER TO VITAL HEADER VLV 2-SW-V141 control switch in the CIDSE position.
9.3.11 Fail open Core Spray Pump Room D Cooler Service M/,,/S Water Outlet Valve, 2-SW-V123, by deenergizing /
Circuit 18 on 120/208 VAC Dist. Pnl. 2D-HY1.
9.3.12 Fail open RHR Pump Room B Cooler Service Water /
Outlet Valve, 2-SW-V124, by deenergizing /
Circuit 20 on 120/208 VAC Dist. Pnl. 2D-HY1.
9.3.13 Fail open RHR Pumps B and D Coolers Service Water Outlet Valves, 2-SW-V125 and 2-SU-V126, by deenergizing Circuit 21 on 120/208 VAC Dist.
Pnl. 2B-HC7.
9.3.14 Fail open Core Spray Pump Room C Cooler Service Water Outlet Valve, 2-SW-V128, by deenergizing Circuit 18 on 120/208 VAC Dist. Pnl. 2C-HYO.
9.3.15 Fail open RHR Pump Room A Cooler Service Water Outlet Valve, 2-SW-V129, by deenergizing '
Circuit 20 on 120/208 VAC Dist. Pnl. 2C-HYO.
9.3.16 Fail open RHR Pump's A and C Coolers Service Water Outlet Valves, 2 SW-v130 and 2-SW-V131, #"
by deenergizing Circuit 18 on 120/208 VAC Dist.
Pnl. 2A-H06.
- +**************
CAUTION For pump protection, a Nuclear Service Water Pump should not be continuously operated with a flow rate of less than 2500 gpm or greater than 8000 gpm. A flow rate of 2500 gpm corresponds to a Nuclear Header pressure of 78 psig and a flow rate of 8000 gpm corresponds to a Nuclear Header pressure of 48 psig.
(As indicated on Panel XU-2 at 2-SW-PI-143-1) 9
- +++*******;;; ;;;;***************;;;;;;;;;**:.;;;;;;;;;******************
, EDIE: -
Start a second Nuclear Service Water Pump when required.
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2 PT-24.6.4 Rev. 2 Page 10 of 48
<a
UNIT 2 PT-24.6.4 9.0 PMocHDW E STEP 8 9.3.17 Initiate Service Water flow through the #3 Diesel Generator Jacket Water Cooler by performing the following:
9.3.17.1 Deenergize #3 Diesel Generator SW to Jacket Water Cooler Isolation Valve, 2-SW-V212, by placing the breaker at compartment EF2 at MCC DGC in the OFF position.
9.3.17.2 Manually OPEN valve 2-SV-V212.
9.3.18 Initiate Service Water flow through the #4 Diesel Generator Jacket Water Cooler by performing the following:
9.3.18.1 Deenergize #4 Diesel Generator SW to Jacket Water Cooler Isolation Valve, 2-SW-V213, by placing the breaker at compartment EF6 at MCC DGD in the OFF position.
9.3.18.2 Manually OPEN valve 2-SW-V213.
L-9.3.19 Align the Nuclear Header to supply RBCCW Service Water at a flow rate of 3500 gpm as indicated at Panel XU-2, FIDW TO RBCCW HX indicator 2-SW-FI-1158-1 by throttling the RBCCW Heat Exchanger Service Water Outlet Flow Control Valve 2-SW-V382.
EQTE:
Unit 2 TBCCW will be diverted to the 2C TBCCW Heat Exchanger where it will be cooled by Unit 1 service water. This iteration is necessary since flow through the Unit 2 Conventional service water header will be secured by this procedure.
e+++++++++++++++ ;. ; ; ; ; : :. :. ; : :. :. a **** ; ; ; :. :. :. ; :. **; ; ; :. :. ; ;q ;. :. ***** :. :. :. ; ;, :. ; :. ;. ; :. :. :. ; :. :. :. ; :.
CAUTION For pump protection, a Conventional Service Water Pump should not be continuously operated with a flow rate of less than 2500 gpm or greater than 8000 gpm. A flow rate of 2500 gpm corresponds to a Conventional Header pressure of 78 psig and a flow rate of 8000 gpa corresponds to a Conventional Header pressure of 48 psig. (As indicated at Panel XU-2 on 2-SU-PI-131-1)
- ei. a :. :. :. :. ; ****++w+;. ; :. :. :. ; + a :. :. :. ; :. :. ; :. ; ; :. :. :. :. ; ; :. :. *++ w****** ; :. :. :. ; :. :. :. :. :. ; :. :.+++++
9.3.20 Verify, or place, the 2C TBCCW Heat Exchanger in service on Unit 1 service water per 1-OP-43.
i 2 PT-24.6.4 Rev. 2 Page 11 of 48 ]
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UNIT 2 PT-24.6.4 9.0 PROCEDg g STEPS 9.3.21 Verify, or place, the 2C TBCCW Heat Exchanger $"
in service on Unit 2 TBCCW, and isolate TBCCW.
Heat Exchangers 2A and 2B, per OP-44.
EgIE: l The RER SW Loops will be fed by the Nuclear Header in this procedure. Either Unit 2 RHR SW loop may be put into service at this time for this test. Loop l swap per Steps 9.3.30 through 9.3.33 must be performed if the RHR SW Booster '
Pump Motor Coolers SW flow on the standby loop require flow monitoring. If flow monitoring on RER SW Booster Pump Motor Coolers is to be observed on one RER SW Loop only, the loop swap per Steps 9.3.30 through 9.3.33 need not be performed and the signoffs at these steps and the appropriate data sheet blocks should be N/A'ed.
9.3.22 Per OP-43 start, or verify operating, RER SW A(B) Loop with both RHR SW Booster Pumps A and C (B and D) operating supplied by the Nuclear Header at a flow rate of 3000 gpm indicated at 2-Ell-FI-R602A(B), RHR SW FIDW, on Panel P601.
9.3.23 At Panel P601 position, or verify as positioned, the WELL VATER SUPPLY VALVE 2-SW-V143 control switch in the CLOSE position.
9.3.24 Per OP-29 Shutdown, or verify shutdown the Unit 2 Circulating Water System. g 9.3.25 Close, or verify closed 2-SW-V36, using the SW TO CV PUMPS INB VLV 2-SU-V36 control switch at Panel XU-2.
9.3.26 Align Unit 1 to supply service water to the Chlorination System per the following:
,0 9.3.26.1 Open, or verify open, Chlorination System Service Water Supply Valves, 1-SW-V294 and 8 __
1-SW-V295.
?
9.3.26.2 Close, or verify closed, Chlorination f System Service Water Supply Valves, 2-SW-V294 and 2-SW-V295.
9.3.27 Throttle TBCCW-Heat y anger A' Service Water Outlet Val z-SV-V9, nd/or TBCCW Heat 7 )e Exchanger B Se' ater Outlet Valve, 2-SV-V10, to establish the Conventional header-pressure equal to the Nuclear header pressure within i 2 psi of 60 psig as indicated at test gauges installed at 2-SW-PS-3213 and 2-SW-PS-3214 I
2 PT-24.6.4 Rev. 2 Page 12 of 48 I
UltIT 2- I PT-24.6.4 '
9.0 PROCEDURE STEPS 9.3.28 Record Test Performance Site Setup Verification .A data per Section 11.5 on the site attachments for components in service.
9.3.29 Perform Test Data Acquisition per Section 11.6 56L for the sites being monitored for flow. Record all data required on Data Sheets 1 through 5.
NOTE:
The RHR SU Loop swap per Steps 9.3.30 through 9.3.33 must be performed if either of the RHR SW Booster Pump Motor Coolers SW flow on the standby loop require flow monitoring. If flow monitoring on RER SW Booster Pump Motor Coolers is to be observed only on the RHR SW Loop presently operating, the loop swap per Steps 9.3.30 through 9.3.33 need not be performed and the signoffs at these steps and the appropriate data sheet blocks should be N/A'ed.
- t.;;;;;***************************
CAUTION For pump protection, a Nuclear Service Water Pump should not be continuously operated with a flow rate of-less than 2500 gpm or greater than 8000 gpu. A flow rate of 2500 gpm corresponds to a Nuclear Header pressure of 78 psig and a flow rate of 8000 gpm corresponds to a Nuclear Header pressure of 48 psig.
(As indicated at Panel XU-2 on 2-SW-PI-143-1)
M:
Shutdown one of the operating Nuclear Setvice Water Pumps when it is not required.
9.3.30 Per OP-43 shutdown RHR SW A(B) loop operation.- ,,,,
E:
Start a second Nuclear Service Water Pump-when it is required.
9.3.31 Per OP-43 place RHR SV B(A) loop in operation, with both RHR SW Booster Pumps B and D (A and-C) operating, supplied by the Nuclear Header at flow rate of.3000 gpm as indicated at 2-E11-FI-R602B(A).
9.3.32 Record Test Performance Site Setup Verification data per Section 11.5 on the site Attachments for.RHR SW Bocater Pump Cooler flow for RHR SW-B(A) Loop.
9.3.33 Perform Test Data Acquisition per Section 11.6 for the sites being monitored for flow. Record-all data required on Data Sheets 1 through 5.
2 PT-24.6.4-Rev. 2 Page 13 of 48
J /,+,. es - a & - a
! UNIT 2 PT-24.6.4 .l l
9.0 PROCEDURE STEPS {
- ,*y,,u** ; ; ; ;, ;. :. ; * ****** * * ** ** *** ** ****************; ;, ; ;, ; ; * *********** * **** ***
CAUTION -
The following step will depressurize the Unit 2 Conventional Header. Ensure j all loads off of the Unit 2 Conventional Header are shutdown or aligned to an '
alternate source of cooling. If Nuclear Header pressure drops below 40.psig-as indicated at 2-SU-PI-143-1, indicating excessive leakage from the Nuclear, to the Conventional Header, immediately restart the Conventional Service Water 1 Pump (s). !
l **************************************************************************
- l. ',
9.3.34 Place all Unit 2 Conventional Service Water Pump mode selector switches in the MAN .
position.
9.3.35 Depressurize the Unit 2 Conventional Header by )
stopping the operating Unit 2 Conventional .;
Service Water Pump (s). ,
9.3.36 Deenergize the Conventional Service Water Pump '
A Discharge Valve to Conventional Header, 2-SW-V13, by placing the breaker at compartment E07 at MCC 2PA in the OFF position. !
9.3.37 Deenergize the Conventional Service water Pump PL i
i B Discharge Valve to Conventional Header, 2-SW-V15, by placing the breaker at compartment E36 at MCC 2PB in the OFF position. "
9.3.38 Deenergize the Conventional Service Water Pump C Discharge Valve to Conventional Header, 2-SW-V17, by placing the breaker at compartment BVO at'MCC 1PA in the OFF position.
9.3.39 Manually open Conventional Service Water Pump'A Discharge valve to Conventional Header, 2-SW-V13.
p 9.3.40 Manually open Conventional Service Wac-r *t.:p B- I Discharge Valve to Conventional Header. '
2-SW-V15.
9.3.41 Manually open Conventional Service Water Pump C fL Discharge Valve to Conventional Header, ;
l 2-SW-V17.
l-9.3.42 Perform Test Data Acquisition per Section 11.6 N for the sites being monitored for' flow. Record 6 all data required'on Data Sheets 1 through 5.
l ;
i 2 PT-24.6.4 Rev. 2 Page 14 of 48
- i l ,
I P
UNIT 2 PT-24.6.4
_ 9.0 PROCEDURE STEPS 9.3.43 Place the discharSe valve breakers for the two k Conventional Service Water Pumps to remain idle in the ON position. N/A signoffs below for the Conventional Service Water Pump to be started 'k*b in Step 9.3.46.
^
9.3.43.1 Breaker ON at compartment E07 at MCC 2PA + /<
for Conventional Service Water Pump A Ind.Ver.
Discharge Valve to Conventional Header, 2-SW-V13.
M4' d
9.3.43.2 Breaker ON at compartment E36 at MCC 2PB + / ~ F'*
for Conventional Service Water Pump B Ind.Ver.
Discharge Valve to Conventional Header, 2-SW-V15.
L - ....
9.3.43.3 Breaker ON at compartment BVO at MCC 1PA 4 /~
for Conventional Service Water Pump C Ind.Ver.
Discharge Valve to Conventional Header, 2-SW-V17.
9.3.44 Verify (locally) the respective valves for the breakers placed in the ON position in the above steps are CLOSED. N/A the signoffs for the valve for the breaker that remained p deenergized. )M 9.3.44.1 Conventional Service Water Pump A # i<
Discharge Valve to Conventional Header, Ind.Ver.
2-SW-vl3.
9.3.44.2 Conventional Service Water Pump B NAfaA Discharge Valve to Conventional Header, Ind.Ver.
2-SW-V15.
9.3.44.3. Conventional Service Water Pump C k/
Discharge Valve to Conventional Header, Ind.Ver.
2-SW-V17, 9.3.45 Manually close the Conventional Service Water Pump Discharge Valve to Conventional Header for the Conventional Service Water Pump to be placed in se-;vice.
O 2 PT-24.6.4 Rev. 2 Page 15 of 48
D UNIT 2 FT-24.6.4 9.0 PROCEDURE STEPS
- , ;, ; a
- ; ; ; ; ; ; :. ; . . :. ; :. :. :. :. ; ; ; ***********w***+*********; :. ;. ;. ;. ;. ; ; :. ;
- m*
CAUTION The Conventional Service Water Pump Discharge Valve to Conventional Header for the Conventional SW Pump must be manually opened slowly as the pump is started to prevent water hammer.
20 9.3.46 Perform the following for the Conventional SW )l Pump to be placed in service (Conventional Service Water Pump Discharge Valve to Conventional Header breaker open).
9.3.46.1 Align pump discharge selector switch to Conventional Header.
9.3.46.2 Start the pump.
9.3.46.3 Slowly (manually) open the Conventional Service Water Pump Discharge Valve to Conventional Header to the fully open position.
9.3.47 Place the breaker for the Conventional Service Water Pump Discharge Valve to Conventional Header opened in step 9.3.46.3 in the ON position and record the following:
MCC No. Bkr. Comet. Position 2 96 C3(* ON /
Ind.Ver.
9.3.48 Open 2-SW-V36 usin5 the SW TO CW PUMPS INB VLV / !
SW-V36 control switch on Panel XU-2. Ind.Ver.
9.3.49 Align SW Chlorinati upply as directed by Shift Supervisor. (U/1 or U/2 supplying) 1 9.3.50 Manually open TBCCW Header supply valves 2-SV-V3 and 2-SW-V4 9.3.51 Throttle TBCCW Heat Exchanger Service Water Outlet Valves 2-SW-V9 and/or 2-SW-V10 until the Conventional header pressure is 48 to 78 psig, as indicated on 2-SW-PI-131-1 on Panel XU-2.
9.3.52 Manually close #3 Diesel Generator SU to Jacket Water Cooler Isolation Valve, 2-SW-V212.
9.3.53 Energize #3 Diesel Generator SW to Jacke.t Water k/ ,
Cooler Isolation Valve, 2-SU-V212, by placing Ind.Ver.
the breaker at compartment'EF2 at MCC DGC in the ON position.
2 PT-24.6.4 Rev. 2 Page 16 of 48
.=,
UNIT 2 ,
PT-23.6.4
_' 9.0 PEOCEDURE ST M j
9.3.54 Verify the Green CLOSED indicator at MCC DGC PL/ M Compartment EF2 for Valve 2-SW-V212 is Ind.Ver.
illuminated.
9.3.55 Manually close s4 Diesel Generator SW to Jacket Ik Water Cooler Isolation Valve, 2-SV-V213.
9.3.56 Energize #4 Diesel Generator SW to Jacket Water b /
Cooler Isolation Valve, 2-SU-V213, by placing Ind.Ver.
the breaker at compartment EF6 at MCC DGD in the ON position.
9.3.57 Verify the Green CLDSED indicator at MCC DCD ?L /
Compartment EF6 for Valve 2-SW-V213 is Ind.Ver.
illuminated. .
9.3.58 Restore Unit 2 RECCW flow as per the Shift Supervisor's instruction.
9.3.59 Place the Conventional Service Water Pump mode /
selector switches for the idle Conventional Ind.Ver.
Service Water Pumps to the AUTO position.
9.3.60 Place the idle Conventional Service Water Pump /
Discharge Valve Selector Switches to the header Ind.Ver.
position (CONV/NUC HDR) as directed by the Shift Supervisor.
9.3.61 Restore Unit 2 PJ'.R SW as per the Shift Supervisor's instructions.
CAUTION One RHR Pump Room Cooler shall be aligned to the NSW Header whenever the NSW Header is in service.
- :. ; ; ; ; ;. ; ;. ; ; ; ********++++++++++*; ; ; ;. :. ; ; ; ;. ; a *; ;. ; ; ; ; ; ; ; ; ; ; ; ; ; ; **; ; ; ;. ; ; ; ;. ;. ; ; ; ;. ; ; ;. :.
9.3.62 Energize Core Spray Pump Room D Cooler Service N/
Water Outlet Valve, 2-SV-V123, by placing Ind.Ver!
Circuit 18 on 120/208 VAC Dist. Pnl. 2D-HY1 in the ON position.
9.3.63 Energize RHR Pump Room B Cooler Service Water N /W Outlet valve, 2-SV-V124, by placing Circuit 20 Ind.Ver) e on 120/208 VAC Dist. Pal. 2D-HY1 in the ON position.
9.3.64 Energize RHR Pumps B and D Seal Coolers Service N/
Water Outlet Valves, 2-SU-V125 and 2.SW-V126, Ind.Vor.
by placing Circuit 21 on 120/208 VAC Dist. Pnl.
2B-H07 in the ON position.
2 PT-24.6.4 Rev. 2 Page 17 of 48
UNIT 2 PT-24.6.4 '
') 9.0 PROCEDURE STEffg 9.3.65 Energize Core Spray Pump Room C Cooler Service /
Water Outlet Valve, 2-SU-V120, by placing Ind.Ver.
Circuit 18 on 120/208 VAC Dist. Pnl. 2C-HYO in the ON position.
9.3.66 Energize RHR Pump Room A Cooler Service Water /
Outlet valve, 2-SW-V129, by placing Circuit 20 on Ind.Ver.
120/208 VAC Dist. Pnl. 2C-HYO in the ON position.
9.3.67 Energize RHR Pumps A and C Coolers Service /
Water Outlet Valves, 2-SW-V130 and 2-SW-V131, Ind.Ver.
by placing Circuit 18 on 120/208 VAC Dist. Pnl.
2A-H06 in the ON position, 9.3.68 Close Nuclear Service Water Pump A Discharge . /
Pressure Root Valve to 2-SW-PI-144, 2-SU-V61. Ind.Ver.
9.3.69 Close Nuclear Service Water Pump B Discharge /
Pressure Root Valve to 2-SW-PI-145, 2-SW-V62. Ind.Ver.
9.3.70 Close 2-SW-PS-3213 Instrument Test Valve, /
2-SU-PS-3213-10. Ind.Ver.
9.3.71 Close 2-SU-PS-3214 Instrument Test Valve,
) 2-SW-PS-3214 10.
/
Ind.Ver.
9.3.72 Close 2-SW-PI-819 Instrument Drain Valve,
~
/
C' M M W-I-8'9-6.)
1 RE VISE
- kw Ind.Ver.
9.3.73 Close 2-SW-PI-821 Instrument Drain Valve, A' M /
2-SW-PI-821-6. Ind.Ver.
f 2-s w-PL- 8t?-]1, I a r - w x- 9.3.74 Place the WELL WATER SUPPLY VALVE 2-SW-V143 /
control switch, on Panel P601, to the AUT0/OPEN Ind.Ver.
position.
9.3.75 If desired, place TBCCW Heat Exchangers 2A ;
and/or 2B in service, and shut down TBCCW Heat !
Exchanger 2C, per OP-43.
9.3.76 If desired, isolate Unit 1 service water from the 2C TBCCW Heat Exchanger per 1-OP-43.
9.3.77 Restore Unit 2 Vital Header lineup per OP-43 and the Shift Supervisor's instruction. :
9.3.78 Per OP-29 and the Shift rupervisor's instruction place the Unit 2 circulating Water System into service. (if required, otherwise N/A signoff)
)
9.3.79 Inform the Shift Supervisor that t.he test portion of this procedure is complete.
2 PT-24.6.4 Rev. 2 /} ;
~~
Page 18 of 48
o UNIT 2 PT-24.6.4 9.0 goCEDURE STEPS 9.3.65 Energize Core Spray Pump Room C Cooler Service /
Water Outlet Valve, 2-SW-V128, by placing Ind.Ver.
Circuit 18 on 120/208 VAC Dist. Pnl. 2C-HYO in the ON position.
9.3.66 Energize RHR Pump Room A Cooler Service Water /
Outlet Valve, 2-SW-V129, by placing Circuit 20 on Ind. Veri.
120/208 VAC Dist. Pnl. 2C-HYO in the ON position.
J 9.3.67 Energize RER Pumps A and C Coolers Service b/
Water Outlet Valves,.2-SW-V130 and 2-SW-V131 Ind. vee.
by placing Circuit 18 on 120/208 VAC Dist. Pnl.
2A-H06 in the ON position. ,
9.3.68 Close Nuclear Service Water Pump A Discharge /
Pressure Root Valve to 2-SW-PI-144, 2-SU-V61. Ind.Ver.
., 9.3.69 Close Nuclear Service Water Pump B Discharge /
} g Pressure Root Valve to 2-SW-PI-145, 2-SW-V62. Ind.Ver. p 9.3.70 Close 2-SU-PS-3213 Instrument Test Valve, 1'L / W
. 2-SW-PS-3213-10. Ind.Ver.
9.3.71 Close 2-SU-PS-3214 Instrument Test Valve. [/-. / ,
2-SW-PS-3214-10. I .Ver.
[p
\% 9.3.72 Close 2-SW-PI-819 Instrument Drain Valve, /
q r) 2 - SV- I - 819 - ( . - j .Ve 7 j.#! 9.3.73 Close 2-SW-PI-821 Instrument Drain Valve, /M 2-SU-PI-821-6. Inh
\. f er.
9.3.74 Place the WELL WATER SUPPLY VALVE 2-SU-V143 /
) control switch, on Panel P601, to the AUT0/0 PEN Ind.Ver.
position.
\'
9.3.75 If desired, place TBCCW Heat Exchangers 2A
, and/or 2B in service, and shut down TBCCW Heat Exchanger 2C, per OP-43.
9.3.76 If desired, isolate Unit 1 service water from 'N the 2C TBCCW Heat Exchanger per 1-OP-43. .
n.
9.3.77 Restore Unit 2 Vital Header lineup per OP-43 e and the Shift Supervisor's instruction.
9.3.78 Per OP-29 and the Shift Supervisor's instruction place the Unit 2 Circulating Water System into service. (if required, otherwise N/A signoff) 9.3.79 Inform the Shift Supervisor that the test /7A) portion of this procedare is complete.
2 PT-24.6.4 Rev. 2 Page 18 of 48
UNIT 2 PT-24.6.4
., 10.0 FISTORATION 10.1 Obtain the Shift Supervisor's permission to perform this section.
_b 10.2 Remove all Contro1otron test equipment used for this UNE' procedure.
10.3 Inform the Shift Supervisor that this section is complete. h 11.0 CONTROLOTRON FLOU INSTRUMENTATION SETUP AND DATA ACOUISITION GUIDELINES NOTE:
Attachments 1 through 5 contain the information required for programming the Uniflow flovmetar and appropriate locations to record the site specific information from the following instructions. After the first performance of this procedure track and transducer installation at each specific site shall be as close as possible to that recorded for the first performance of this procedure. The following instructions do not contain each line item in setting up the Contro1otron, as some are intrinsic to the operation of the machine and should be known to a proficient technician. The instructions given are intended to ensure each site is identified and appropriate information collected to ensure duplication of the site can be achieved and verified in future performances of this procedure and that the correct flow data is stored and is retrievable in the Contro1otron during the performance of the test section of this procedure.
11.1 Enter the SITE NAME as given on the attachment.
11.2 TEST EQUIPMENT NOTE:
Track and transducer installation shall conform to controlotron installation instructions and drawings. To ensure that exact as possible location of the transducers is accomplished for each performance of this procedure the upstream transducer shall always be located with the letter index track.
11.2.1 Record the Contro1otron serial number on the Site '
Attachment.
11.2.2 Record the Track / Transducer size and serial number to be used at the site on the Site Attachment.
11.2.3 Record Track / Transducer Mounting Mode on the Site Attachment.
11.3 PIPE DATA 11.3.1 From the site attachment sketch determine the approximate site location. Clean the pipe (remove paint to the pipe surface) to a clean, smooth surface at the anticipated transducer and pipe 0.D. measurement locations.
2 PT-24.6.4 Rev. 2 Page 19 of 48 F
l UNIT 2 PT-24.6.4 l 11.0 CO'trROTITRON FLOW INSTRUMENTATION SETUP AND DATA ACOUISITION CUIDELINES 11.3.2 Determine the pipe outside diameter by performing the following:
EQIE:
For the first performance of this procedure initial transducer locations can l be determined by setting up the tracks and transducer at the site and put the Contro1otron into service using standard nominal pipe data and appropriate Contro1otron default settings. A Vale of 50 or greater is acceptable for the initial location of tracks and transducers, but every effort should be made co obtain Vale readings of 60 or greater. For subsequent performances of this procedure install identical tracks and transducers at each site at the lo.--tion noted on each site attachment sketch using the dimensions recorded in the first performance of this procedure.
l l 11.3.2.1 Using micrometers or calipers, measure the O.D. of the pipe at the upstream transducer location. Record this dimension on the Site Attachment.
11.3.2.2 At a position 90* around the pipe from the above location measure the pipe O.D. Record this dimension on the Site Attachment.
11.3.2.3 Measure the O.D. of the pipe at the downstream transducer location. Record this dimension on the Site Attachment.
11.3.2.4 At a position 90* around the pipe from the above location measure the pipe O.D. Record this dimension on the Site Attachment.
11.3.2.5 Average the measured O.D.'s and record this number on the Site Attachment and enter as PIPE O.D. in the Contro1otron site setup.
11.3.3 Enter the PIPE MATERIAL as given on the Site Attachment.
11.3.4 Determine the pipe wall thickness by performing the following: ;
NOTE: l The greater the degree of accuracy of the UT pipe wall thickness measuring instrument, the greater the accuracy of the flow measurement, particularly in db !
the small bore pipe, obtained by the Contro1otron. The UT instrument used should have the greatest accuracy practically achievable for a given site. l Actual UT instrument used shall be determined by the UT Examiner based on site ;
parameters. An appropriate data sheet from the NDE procedure for the UT '
instrument used to determine pipe wall thickness shall be completed for each site.
2 PT-24.6.4 Rev. 2 Page 20 of 48
UNIT 2 PT-24.6.4 11.0 coNTROLOTRON FLOV INSTRUMENTATION SETUP AND DATA ACOUISITION CUIDELINES 11.3.4.1 Using a ultrasonic pipe wall thickness measuring instrument, measure the pipe wall thickness at the upstream transducer location. Record this on.the Site Attachment.
11.3.4.2 At a position 90* around the pipe from the.above location measure the pipe wall thickness. Record this dimension on the Site Attachment.
11.3.4.3 Using a ultrasonic pipe wall thickness measuring instrument, measure the pipe wall thickness at the downstream transducer location. Record this on the Site Attachment.
11.3.4.4 At a position 90* around the pipe from the above location measure the pipe wall thickness. Record this dimension on the Site Attachment.
11.3.4.5 Average the upstream and downstream pipe wall thicknesses and record the results on the Site Attachment. Enter this as the WALL THICKNESS in the Contro1otron setup.
11.3.5 Enter LINER MATERIAL and LINER THICKNESS as given on the Site Attachment, if applicable.
11.3.6 Enter Sea Water as LIQUID TYPE. Leave. ESTIMATED Vs and VISCOSITY (CS) at the default settings.
11.3.7 Enter, or verify, VOLUME UNITS as gallons.
11.3.8 Enter, or verify, TIME UNITS as minutes.
11.3.9 Verify that the flow total setup RESOLUTION-(0000x000, 00000x00, etc.) is appropriate for the anticipated flow rates.
11.3.10 Enter the following from the DATA SELECTED menu for datalogger setup: SITE NAME, DATE, TIME, FLOW TOTAL, Vs and Vale.
11.3.11 Enter the IDG INTERVAL SET in the datalogger setup as 1M.
11.3.12 In the Contro1otron Site Setup Site Load Menu move the cursor to SAVE SITE, then cursor right and press' ENTER to save this site in the AFAC memory of the Contro1otron.
2 PT-24.6.4 Rev. 2- Page 21 of 48
~
UNIT 2 L
, PT-24.6.4 i.
11.0 grwrruoIDTRON FIDW INSTRUMENTATION SETUP AND DATA ACOUISITICF _ GUIDELINES 11'.4 'Zero Flow Calibration Site track / transducer setup and cables shall remain in place after zero flow calibration and through test completion.~ Transducer couplant should be checked prior to the test initiation and if dried up the transducer and pipe
, shall be cleaned of residue and new couplant applisd.
g 11.4.1 Setup the tracks and transducers at the location shown at d described on the Site Attachment. Record the reference dimension on the Site Attachment.
p 11.4.2 RECALL the desired site in the Contro1otron Site setup menu. Initiate flow measuring with the Contro1otron using the default zero flow set and parameters generated in Sections 11.1, 11.2 and 11.3.
11.4.3 Record the Letter / Number Spacing Index established for this site.
11.4.4 Establish and verify the zero flow system line up.
11.4.5 Record the present flow reading as the Zero Offset on the Site Attachment.
11.4.6 In the installation menu of the Contro1otron enter ACTUAL ZERO as the zero flow set.
11.4.7 From the diagnostics menu of the Contro1otron record Vs.
Vale, fx, Vfmax, and vsmax at Diagnostic Data on the Site .
Attachment.
11.4.8 In the Conttolotron Site Setup Site Load Menu move the cursor to SAVE SITE, then cursor right and press ENTER to save this site in the AFAC memory of the Contro1otron.
11.5 Test Performance Site Setup Verification.
11.5.1 RECALL the desired site in the Contro1otron Site setup
- menu.
11.5.2 From the diagnostics' menu of the Contro1otron record Vs, Vale, fx, Vfmax, and Vsmax at Test Diagnostic Data on the Site Attachment.
l-
- 2 PT-24.6.4 Rev. 2 Page 22 of 48
UNIT 2 PT-24.6.4 11.0 CONTROIDTRON FIDW INSTRUMENTATION SETUP AND DATA ACOUISITION GUIDELINES H2IE: -
If,'during the performance of the procedure steps per Section 9.0, it appears that the zero flow calibration for the site has been lost or the present setup at a site is questionable determined from the diagnostic information, the tracks and transducers may be moved, reset and the site zero calibrated by.the transducer reversal method and noted as such in the comment section of the appropriate Site Attachment.
11.6 Test Data Acquisition 11.6.1 Record the appropriate Site Attachment number on the Data Acquisition Sheet. -
11.6.2 RECALL the desired site in the Controlotron Site setup menu.
EII:
The Net Totalizer Register may be reset to zero prior to performing the next step by pressing and holding the function key for the channel being used (F1 for Channel 1, F2 for Channel 2) and then press numeric key 1 on the hand held CDU.
11.6.3 At the Data Logger Setup in the Controlotron site setup menu, cursor to DataLogger Mode, cursor right to level D, scroll to MEMORY and press ENTER.
11.6.4 Return cursor to level A of the Contro1otron menus, then scroll to Operation Setup, cursor right to level B and scroll (down) to Display Select, cursor right to level C then scroll to DATAIDGCER and press ENTER. The Datalogger display should appear on the Graphic Screen.
11.6.5 Press and hold the down cursor button on the CDU until the data on the Graphics Display Screen stops scrolling.
11.6.6 Record the Attachment No., Site Name, Step No. and Date on the Data Acquisition Sheet.
11.6.7 Observe the Graphic Display on the Contro1otron and as new updates are displayed at 1 minute - intervals (this requires occasionally scrolling the down cursor on the CDU) record the data on the Data Acqaisition Sheet. At each gp subsequent update calculate the difference of the displayed Flow Total and record this in the appropriate box of the Flow Total Difference Column.
2 PT-24.6.4 Rev. 2 Page 23 of 48
UNIT 2 PT-24.6.4 11.0 CONTROIDTRON FIDW INSTRUMENTATION SETUP AND DATA ACOUISITION CUIDELINES 11.6.8 Continue recording each update until at least 5 Flow Total Differences have been calculated. Average the flow total differences and record the results in the appropriate box for that site for the procedure step being performed on the appropriate data sheet.
11.6.9 Review recorded data on the Data Acquisition Sheet with the data displayed on the Graphics Display Screen for accuracy.
i 11.6.10 When sufficient data has been recorded on the Data Acquisition Sheet, return to the Datalogger Setup menu, go into Datalogger Mode and Enter OFF. Proceed to the next site for data acquisition or to the next test procedure step.
i i
l l
l 1
l i
l l
2 PT-24.6.4 Rev. 2 Page 24 of 48 a.
11 NIT 2 l PT-24.6.4 ;
ATTACHMENT 1 2A NUCIEAR SERVICE WATER PUMP DISCHARGE SITE SETUP 1.0 SITE NAME: 2ANPMP 1.1 TEST EOUIPMENT 1.1.1 Controlotron Serial No. M b 77 1.1.2 Track / Transducer size: Y 1.1.3 Transducer Serial Nos.: (up) U 736 A '
(down)# # 55 5 8 1.1.4 Track / Transducer Mounting Mode: (Direct / Reflect) M7ef 1.2 PIPE DATA 1.2.1 Pipe O.D.:
1.2.1.1 0.D. at upstream transducer location. /Y US in.
1.2.1.2 0.D. 90* around pipe from upstream /f f M in, transducer location.
1.2.1.3 0.D. at downstream transducer location. /YI88 in.
1.2.1.4 0.D. 90' around pipe from downstream MI@ in.
transducer location.
1.2.1.5 Average of measured O.D.'s: / E III ir..
Micrometers / Calipers: ,
CP&L No.:V M J Cal Date: O '/ I / 7/ Cal Due Date: 2 / I / II-1.2.2 Pipe Material: STEEL 1.2.3 Wall Thickness:
1.2.3.1 Pipe Wall thickness at upstream 83dI in.
transducer location.
1.2.3.2 Pipe wall thickness 90' around pir from 8 #7# in.
upstream transducer location.
1.2.3.3 Pipe Wall thickness at downstream 8. US in.
transducer location.
1.2.3.4 Pipe wall thickness 90* around pipe from 8M6 in.
downstream transducer location.
1.2.3.5 Average pipe wall thickness. #- in.
1.2.4 Liner Material: Cement Thickness: .313 in.
2 PT-24.6.4 Rev. 2 Page 25 of 48
UNIT 2
- PT-24.6.4 ATTACHMENT I 2A NUCLEAR SERVICE VATER PUMP DISCHARGE FLOW 2.0 ZERO FLOV CALIBRATION 2.1 Precautions and Limitations 2.1.1 The 2A Nuclear Service Water Pump can be removed from service.
2.2 System Lineup 2.2.1 Setup the tracks and transducers on line 2-SW-4-20-157 at the location shown on the 2A Nuclear Service Water Pump Discharge Site Setup Sketch. Measure and record below and on the sketch the reference dimension from the floor (El.
4' 0") to the upstream edge of the track, -
REFERENCE DIMENSION:
y9 2.2.2 Measure and record the axial displacement in inches on the pipe surface from the centerline of the Nuclear Header to the nearest edge of the track holding the upstream REFERENCE DIMENSION:
2.2.3 Remove from service, or verify as such, 2A N Nuclear Service Water Pump.
2.2.4 Verify the Nuclear Header Service Water Pump A N Discharge Valve, 2-SV-V19, is closed.
2.3 Zero Set 2.3.1 Letter / Number Spacing Index 8 /Y '
2.3.2 Zero Offset: C-) #6 som 2.3.3 Diagnostic Data: )
VsW #I m/s Vale f0 fx f2 Vfmax 34 47- Vsmax Il49*IS 3.0 TEST PERFORMANCE SITE SETUP VERIFICATION i
3.1 Test Diagnostic Data: I Vs INN /s Valc 5/ fx 2.2. !
Vfmax U* Vsmax M %
COMMENTS:
2 PT-24.6.4 Rev. 2 Page 26 of 48
UNIT 2
, PT-24.6.4 ATTACHMENT 1 2A NUCLEAR SWP DISCHARGE LINE 2-SW-4-20-157 V24 FLOOR EL. 20.O' I
AF 'A Of N
O.
w th V19 NUCLEAR HEADER C I FLOW FLOOR EL. 4.O' "s-* s .' *
.... .' . '. . ,*. . . . . l..
' L * .*
VIEW LOOKING WEST ,
. N Sil P 2. '.2 SECTION A-- A 2A NUCLEAR SERVICE WATER PUMP DISCilARGE SITE SETUP SKETCH UNIT 2 SERVICE WATER BUIIDING 2 PT-24.6.4 Rev. 1 Page 27 of 48
c UNIT 2 PT-24.6.4 ATTACHMENT 2 2B NUCLPAR SERVICE VATER PUMP DISCHARGE SITE SETUP 1.0 SITE NAME: 2BNPMP 1.1 TEST EOUIPMENT 1.1.1 Controlotron Serial No. # 079 1.1.2 Track / Transducer size: Y 1.1.3 Transducer Serial Nos.: (up) N YI8 A (down) W 158 6 1.1.4 Track / Transducer Mounting Mode:(Direct / Reflect) A'NCI 1.2 PIPE DATA 1.2.1 Pipe O.D.:
1.2.1.1 0.D. at upstream transducer location. /I 7#E in.
1.2.1.2 0.D. 90' around pipe from upstream /7 4Y/ in.
transducer location.
1.2.1.3 0.D. at downstream transducer location. !$IN in.
1.2.1.4 0.D. 90' around pipe from downstream /9. 52 7 in.
transducer location. .
1.2.1.5 Average of measured O.D.'s: ! YSE in.
Micrometers / Calipers:
CP&L No.:W##3 Cal Date: b / I //YCal Due Date: Z / 8 /Y2 1.2.2 Pipe Material: Copper Nickel (70/30) 1.2.3 Wall Thickness: '
1.2.3.1 Pipe Vall thickness at upstream 8 27# in transducer location.
1.2.3.2 Pipe Vall thickness 90* around pipe from 0- in.
upstream transducer location.
1.2.3.3 Pipe Vall thickness at downstrean dO# in.
transducer location.
1 1.2.3.4 Pipe Vall thickness 90* around pipe from 4 780 in.
downstream transducer location.
1.2.3.5 Average pipe wall thickness. '
]7Y in.
I 1
2 PT-24.6.4 Rev. 2 Page 28 of 48 l
UNIT 2 PT-24.6.4 L
ATTACHMENT 2 2B NUCLEAR SERVICE WATER PUMP DISCHARGE SITE SETUP 2.0 ZERO FLOW CALIBRATION 2.1 Precautions and Limitations 2.1.1 The 2B Nuclear Service Water Pump can be removed from service.
2.2 System Lineup 2.2.1 Setup the tracks and transducers on line 2-SW-5-20-046 at the location shown on the 2B Nuclear Service Water Pump Diccharge Site Setup Sketch. Measure and record below and on the sketch the reference dimension from the floor (El.
4' 0"j to the upstream edge of the track. -
REFERENCE DIMENSION:
O O p2 2.2.2 Measure and record the axial displacement in inches on the pipe surface from the centerline of the Nuclear Header to the nearest edge of the track holding the upstream REFERENCE DIMENSION: Mr 2.2.3 Remove from service, or verify as such, 2B M Nuclear Service Water Pump.
2.2.4 Verify the Nuclear Header Service Water Pump B M Discharge Valve, 2-SW-V20, is closed.
2.3 Zero Set 2.3.1 Letter / Number Spacing Index /
2.3.2 Zero Offset: 7/6 com 2.3.3 Diagnostic Data: "
VsN7I'7h/s Valc $I fx 2E vfmax 3f. 47 vsmax / 841. ft 3.0 TEST PERFORMANCE SITE SETUP VERIFICATION 3.1 Test Diagnostic Data:
Vs NN/s Valc 74 fx 32 vfmax M Of vsmax 18 M 9 COMMENTS:
2 PT-24.6.4 Rev. 2 Page 29 of 48
UNIT 2 PT-24.6.4 ATTACHMENT 2 28 NUCLEAR SWP DISCHARGE LINE 2-SW-5-20-046 V25
, FLOOR EL. 20.0'
.L '_ . . .. : . .. , , , , , _ . *"..., ... , , . , _ ,
AF 7A 9
N N
o.
W V20 Di NUCLEAR HEADER
{ U FLOW .. FLOOR EL. 4.0' y.,,'..__.'",'*....'5..,*..,*.**."s~'s.*.
. . . .~_ ~-
- VIEW LOOKING WEST ------------- ---------------
-N
...}'.......'.
--STEP 2.2 2 SECTION A- A 2B NUCLEAR SERVICE WATER PUMP DISCHARGE SITE SETUP SKETCH UNIT 2 SERVICE WATER BUILDING 2 PT-24.6.4 Rev. 1 Page _30 of 48
UNIT 2 r PT-24.6.4 ,
ATTACHMENT 3 No. 3 DIESEL GENERATOR JACKET WATER COOLER SV SITE SETUP 1.0 SITE NAME: 3DGJL"I 1.1 TEST EOUIPMENT ,
1.1.1 Contro1otron Serial No. M II #
1.1.2 Track / Transducer size: I 1.1.3 Transducer Serial Nos.: (up) N #/OA I (down)# # 4/O 6 1.1.4 Track / Transducer Mounting Mode:(Direct / Reflect) 8hrcI 1.2 PIPE DATA i
EQII:
Remove grating as necessary to access piping.
1.2.1 Pipe O.D.:
1.2.1.1 0.D. at upstream transducer location. 4 6 Y2 in.
1.2.1.2 0.D. 90* around pipe from upstream ISS Y in.
transducer location.
1.2.1.3 0.D. at downstream transducer location. I d' O in.
1.2.1.4 0.D. 90' around pipe from downstream I W in transducer location.
1.2.1.5 Average of measured O.D.'s: 8 6N i n.
Micrometers / Calipers:
CP&L No. : Vf 016 Cal Date: /Y / I/ Cal Due Date: /N 2/ 'I/ .
t 1.2.2 Pipe Material: STEEL 1.2.3 Wall Thickness:
1.2.3.1 Pipe Wall thickness at upstream # I/O in.
transducer location.
1.2.3.2 Pipe Wall thickness 90' around pipe from 4IM in.
upstream transducer location.
1.2.3.3 Pipe Wall thickness at downstream Al#I in.
transducer location.
l 2 PT-24.6.4 Rev. 2 Page.31 of 48 .l
UNIT 2 ,
PT-24.6.4 L
ATTACHMENT 3 No. 3 DIESEL GENERATOR JACKET WATER COOLER SW SITE SETUP [
1.2.3.4 Pipe Wall thickness 90' around pipe from # 275 in.
downstream transducer location.
1.2.3.5 Average pipe wall thickness. #*286 in.
1.2.4 Liner Material: Cement Thickness: 0.250 in.
2.0 ZERO FLOW CALIBRATION 2.1 Precautions and Limitations 2.1.1 The piping configuration at the primary setup location may -
not leave this pipe full of service water at all times.
If empty pipe indications are obtained with the Controlotron at this location, or flow anomalies are .
anticipated due to piping configuration, duplicate the [
setup at the alternate location.
2.2 System Lineup ,
2.2.1 Setup the tracks and transducers on line 2-SW-233-6-157 as shown on the No. 3 Diesel Generator Jacket Water Cooler SW Flow Setup Sketch. Measure and record the reference dimension from the U-bolt on the horizontal' pipe support ,
to the upstream edge of the track, p*
2 REFERENCE DIMENSION 2.2.2 Measure and record the axial location of the transducer '
track assembly as noted on the sketch. g J/ **
REFERENCE DIMENSION #
2.2.3 Verify No. 3 Diesel Generator is not running. M 2.2.4 Verify the No. 3 Diesel Generator Jacket Water M Cooler SW Isolation Valve, 2-SW-V212, is closed.
2.2.5 Verify the No. 3 Diesel Generator Jacket Water M Cooler SW Isolation valve, 1-SW-V212, is closed.
2.3 Zero Set 2.3.1 Letter / Number Spacing Index 8 / I 2.3.2 Zero Offset: NN com 2.3.3 Diagnostic Data:
Vs ID'Un/s Vale II fx /d Vfmax A26 v3 ax M8. 4 2 PT-24.6.4 Rev. 2 Page 32 of 48 i l
UNIT 2 PT-24.6.4 ATTACHMENT 3 No. 3 DIESEL CENERATOR JACKET VATER COOLER SW SITE SETUP 3.0 TEST PERFORMANCE SITE SETUP VERIFICATION ,
3.1 Test Diagnostic Data:
Vs n/s Valc N fx /b ;
Vfaax $ I1 Vsmax l 9 18.06 COMMENTS:
i O
i 9
2 PT-24.6.4 Rev. 2 Page 33 of 48 l
UNIT 2
, PT.24.6.4~
ATTACHMENT 3
~
?.' i .. ,.l , : , ' ,*. *.,* ',. *. ' ' ' , . . _.. , ~. ..,. . : , ', C, . ',. . , . . . . .,'..*...-
2 *
. . . . . . . . . . . . . . . . . . . . . . 2. . S. W. . .V212.K. .S.W_ .23,3 157
( 11 / 1 . *
~~
2-SW-V274 3: o l ,-
o /. ;*
........................ 3 G' .' :
J-- SUPPORT ,'
N a -
. .b ..
J . . '.
. . . .N ..
. l DIESEL GENERATOR (3 l l lN **/
- .w a -
l l-
- 4A l
Ab o
. 1 -SW-215 157 -t. - ' ..- .
1-SW-215-6-157 l
,/ g GRATING ,
' ,+' .
- , 1 '
% STEP 2.2.2 I ..' '
~~~ / - ,
i - -
b 2-SW-233-6-157 '
SECTION A-A No. 3 DIESEL GENERATOR JACKET WATER COOLER SW. INLET SETUP SKETCH DIESEL GENERATOR BUILDING 2 PT.24.6.4.Rev. 1 Page 34 of 48 -
UNIT 2
.PT-24.6.4 i . ATTACHMENT 4 No. 4 DIESEL GENERATOR JACKET VATER COOLER SV SITE SETUP l
l 1.0 SITE NAME: 4DGJKT l
1.1 TEST EOUIPMENT 1.1.1 Controlotron Serial No. O 7 f>l 1.1.2 Track / Transducer size: 8 1.1.3 Transducer Serial Nos.: (up)// / 4/4 4 (down)4 # 4/ 4 #
l 1.1.4 Track / Transducer Mounting Mode:(Direct / Reflect) O//fcM l
l 1.2 PIPE DATA NOTE:
Remove grating as necessary to access piping. ;
1.2.1 Pipe O.D.:
1.2.1.1 0.D. at upstream transducer location. A # SY in.
1 1.2.1.2 0.D. 90' around pipe from upstream I 67Y in. i transducer location. !
l 1.2.1.3 0.D. at downstream transducer location, 8632 in.
1.2.1.4 0.D. 90' around pipe from downstream d 0YS in. l transducer location. i l 1.2.1.5 Average of measured O.D.'s: d 0Y2 in.
l Micrometers / Calipers:
l CP&L No..:f W s Cal Date: S /Y /7/ Cal Due Date: O / E / il 1.2.2 Pipe Material: STEEL ,
I 1.2.3 Vall Thickness: )
1.2.3.1 Pipe Wall thickness at upstream 8.U7# in.
transducer location.
1.2.3.2 Pipe Wall thickness 90* around pipe from 8 285 in.
upstream transducer location.
1 1.2.3.3 Pipe Wall thickness at downstream 0N fn. l transducer location.
I 1.
1 -
2 PT-24.6.4 Rev. 2 Page 35 of 48 l
l 1
UNIT 2 PT.24.6.4 ATTACHMENT 4 No. 4 DIESEL GENERATOR JACKET WATER COOLER SW SITE SETUP 1.2.3.4 Pipe Wall thickness 90' around pipe from O.770 in.
downstream transducer location. '
1.2.3.5 Average pipe wall thickness. 8. U 8 in.
1.2.4 Liner Material: Cement Thickness: 0.250 in.
2.0 ERO FLOW CALIBRATION
)
2.1 Precautions and Limitations 2.1.1 The piping configuration at the primary setup location may not leave this pipe full of service water at all times.
If empty pipe indications are obtained with the controlotron at this location, or flow anomalies are anticipated due to piping configuration, duplicate the setup at the alternate location.
2.2 System Lineup 2.2.1 Setup the tracks and transducers on line 2-SW-234-6-157 as shown on the No. 4 Diesel Generator Jacket Water Cooler SW -
Flow Setup Sketch. Measure and record the reference dimension from the U-bolt on the horizontal pipe support to the upstream edge of the track.
REFERENCE DIMENSION N 7 fE,,
2.2.2 Measure and record the axial location of the transducer track assembly as noted on the sketch. <-
REFERENCE DIMENSION 2 y&
2.2.3 Verify No. 4 Diesel Generator is not running. W 2.2.4 Verify the No. 4 Diesel Generator Jacket Water N Cooler SW Isolation Valve, 2-SW-V213, is closed.
1 2.2.5 Verify the No. 4 Diesel Generator Jacket Water j Cooler SW Isolation Valve, 1-SW-V213, is closed.
2.3 Zero Set I 2.3.1 Letter / Number Spacing Index 8 /I _
2.3.2 Zero Offset: f~)I7 mm 1 2.3.3 Diagnostic Data:
VslN14%/s Valc lO fx l5 l
vfmax 7.50 vs.,x /f 84 9 j 2 PT-24.6.4 Rev. 2 Page 36 of 48
l UNIT 2 !
PT-24.6.4 f
ATTACHMENT 4 No. 4 DIESEL CENERATOR JACKET VATER COOLER SW SITE SETUP 3.0 TEST PER MRMANCE SITE SETUP VERIFICATION 3.1 Test Diagnostic Data: -
VsI /s Valc 74 fx l ;
Vfmax 'b0 Vsmax (ibiiN COMMENTS:
t
?
i I
h J
I l
I 2 PT-24.6.4 Rev. 2 Page 37 of 48
UNIT 2 PT.24.6.4 ATTACllMENT 4
'^
.i.l .,; .'.' ;',.*:'*..*' . . ... ,, ,. .', , ', ; *. ; , =
,_ , .'l , , * . , ' . . . . ..
. . . . . . . . . . . . . . . . . . . . . . 2. .S.W. .v213. .
. .. 2. .S.W .234 15 7 .'
LVI .
2-SW-v275 d 5n o) ,
u . .
- r^-- SUPPORT l- ..
N . *.
.m *.
OIESEL GENERATOR J4 l lN *;
l ia iw
+
. .w .
l l l Ah l* 4A '
i................................a' m. t <
s ., ..
l . .
1-SW-216-6-157 --h.-
1 -SW-216 157 g GRATING
./
p STEP 2.2.2 ,,
/
' o
' 2-SW-234-6-157
=
SECTION A-A NO. 4 DIESEL GENERATOR JACKET WATER COOLER SW INLET SETUP SKETCll DIESEL GENERATOR BUILDING 2 PT 24.6.4 Rev. 1 O Page 38 of 48-
- _ - - _ _ _ _ _ - - - _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ - _ - _ _ _ _ _ _ . _ _ _. . . - . . , . . ~ . . - - . .- . -
UNIT 2 PT-24.6.4
^
ATTACHMENT 5 VITAL HEADER (FROM NUCLEAR HEADER) SW INLET SITE SETUP 1.0 SITE NAME: VITHDR 1.1 TEST EOUIPMENT 1.1.1 Contro1otron Serial No. N !Ii9 1.1.2 Track / Transducer size: 8 1.1.3 Transducer Serial Nos.: (up)l/ 2005 A (down)t/ 24 6 5 #
1.1.4 Track / Transducer Mounting Mode:(Direct / Reflect) O/Nd 1.2 PIPE DATA 1.2.1 Pipe O.D.:
1.2.1.1 O.D. at upstream transduce': Itcation. I I/O in.
1.2.1.2 0.D. 90' around pipe from upsr .r m DAN in.
transducer location.
1.2.1.3 0.D. at downstream transducer location. d IST in.
1.2.1.4 0.D. 90' around pipe from downstream I AU in.
transducer location.
1.2.1.5 Average of measured O.D.'s: I d/O in.
Micrometers / Calipers:
CP&L No. : WO/S Cal Date: 0 / I 8/ Cal Due Date: /2 / 2 / 9/
1.2.2 Pipe Material: COPPER NICKEL (70/30) 1.2.3 Wall Thickness:
1.2.3.1 Pipe Vall thickness at upstream 8N in.
transducer location.
1.2.3.2 Pipe Vall thickness 90* around pipe from 8 US in.
upstream transducer location.
1.2.3.3 Pipe Wall thickness at downstream 4255 in.
transducer location.
1.2.3.4 Pipe Wall thickness 90* around pipe from 8 Iff in.
downstream transducer location.
1.2.3.5 Average pipe wall thickness. II in.
2 PT-24.6.4 Rev. 2 Page 39 of 48
UNIT 2
-- PT-24.6.4 ATTACHMENT S VITAL HEADER (FROM NUCLEAR HEADER) SW INLET SITE SETUP 2.0 ZERO FLOW CALIBRATION 2.1 Precautions and Limitations 2.1.1 Performance of the zero flow calibration for the Vital Header (From Nuclear Header) SW Inlet Site Setup requires transfer of the Vital Header flow from the NSW Header to the CSW Header.
2.1.2 After zero flow calibration has been completed, the vital header is to be restored so that flow to the vital header is from the NSW header.
2.1.3 Flow and lineup restrictions shall be in place in accordance with TSI 90-03, Rev. O.
2.2 System Lineup 2.2.1 Set up the tracks / transducers on line 2-SW-117-6-046 as shown on the Vital Header (From Nuclear Hender).SW Inlet Site Setup Sketch. Measure and record the reference dimension. from the upstream elbow to the upstream edge of the track.
REFERENCE DIMENSION b "~3 "
2.2.2 Heasure and record the axial location of the transducer track assembly as noted on the sketch.
REFERENCE DIMENSION O O CAUTION TSI 90-03, Rev. O requires that at .least one RHR pump room cooler to be in service on the NSW header. Failure to meet this lineup restriction will invoke the requirements of Tech Spec 3.0.3 or 3.0.5, as applicable. 'Ihis will invoke this requirement for the short period of time needed to perform the zero flow set.
- +****************************
2.2.3 Close the Nuclear Header to Vital '
Header Valve. 1 0W "117 -
g@ 2.2.4- Close the Nuclear Header to Vital Header
_- Isolation Valve, 2-SW-V116.
[
f WJf7
-2 PT-24.6.4-Rev. 2 . . Page 40 of 48 -
=. .
UNIT 2 ,
PT-24.6.4 -
ATTACHMENT 5 VITAL HEADER (FROM NUCLEAR HEADER) SU INLET SITE SETUP 2.0 ZERO FIDW CALIBRATION 2.1 Precautions and Limitations i
2.1.1 Performance of the zero flow calibration for the Vital Header (From Nuclear Header) SW Inlet Site Setup requires <
transfer of the Vital Header flow from the NSW Header to the CSW Header.
2.1.2 After zero flow calibration has been completed, the vital header is to be restored so that flow to the vital header ,
2.1.3 Flow and lineup restrictions shall be in place in accordance with TSI 90-03, Rev. O.
2.2 System Lineup ,
2.2.1 Set up the tracks / transducers on line 2-SU-117-6 046 as shown on the Vital Header (From Nuclear Header) SW Inlet Site Setup Sketch. Measure and record the reference dimension from the upstream el'.ow to the upstream edge of ,
the track.
REFERENCE DIMENSION ,
2.2.2 Measure and record the axial location of the transducer track assembly as noted on the sketch.
REFERENCE DIMENSION CAUTION TSI 90 03, Rev. O requires that at least one RHR pump room cooler to be in service on the NSW header. Failure to meet this lineup restriction will invoke the requirements of Tech Spec 3.0.3 or 3.0.5, as applicable. This will -
invoke this requirement for the short period of time needed to perform the l
zero flow set.
- ++********************************
i Close the Nuclear Header to Vital I
2.2.3 Header Valve, 2-SW-V117. ;
i 2.2.4 Close the Nuclear Header to Vital Header Isolation valve, 2-SW-V116.
l!
l-l 2 PT-24.6.4 Rev. 2 Page 40 of 48 l
- - - - . - _ _ - - . ~
'i.' ,
UNIT 2 i PT-24.6.4 !1 i
ATTACHMENT 5 VITAL HEADER (FROM NUCLEAR HEADER) SV INLET SITE SETUP !
-l ;
i 2.3 Zero Set' .;
2.3.1 Letter / Number Spacing Index /
.{
2.3.2 Zero Offset: 5 3 ro. j
\,
2.3.3 Diagnostic Data.
O
~
Vs M38# mis vale fx li vfmax 7.71 vsmax 19 % li 2.4 System Restoration C N l ;
2.4.1 Open the Nuclear Header to Vital Header Isolation Valve, 2-SW-V116. [
g\fkV -
2.4.2 Open the Fuclear Header to Vital Header Valve, 2-SW-V117. '
l 3.0 TEST PERFORMANCE SITE SETUP VERIFICATION s l
3.1 Test Diagnostic Data: ,
Vsb3' s Vale fx ) !
(
Vfmax 7 N Vsmax b iY' r
l COMMENTS: i f
e
.j r
i i
^
l l 1 1 a fl- 3 [ Y f#7 0 raga 41 .t u L 2 rT-2 u .4 Rev. 2 <
I
UNIT 2 PT-24.6.4 ATTACHMENT 5 VITAL HEADER (FROM NUCLEAR HEADER) SV INLET SITE SETUP 1
2.3 Zero Set ,
2.3.1 Letter / Number Spacing Index /
rpm 2.3.2 Zero Offset:
2.3.3 Diagnostic Data:
Vs m/s Vale fx Vfmax Vsmax 2.4 System Restoration i
2.4.1 Open the Nuclear Header to Vital Header ;
Isolation Valve, 2-SV-V116.
4
?. 4. 2 Open the Nuclear Header to Vital Header Valve, 2-SV-V117. ,
I 3.0 TEST PERFORMANCE SITE SETUP VERIFICATION 3.1 Test Diagnostic Data:
Vs m/s Vale fx Vfmax Vsmax COKKENTS:
i I
i l
i l
2 PT-24.6.4 Rev. 2 Page 41 of 48 l l
1-UNIT 2 -
PT-24.6.4 ATTACHMENT 5 2-SW-307-3/4-046 v117
/ i
!X] ,3 . EL. 9'-0" 2-SW-117-6-046 STEP 2.2.1 W
A& vA STEP 2.2.2 v EL. O'-3 5/8" f% - ,.
K SECTION A - A VITAL HEADER (FROM NUCLEAR HEADER) SW INLET SITE SETUP f' UNIT 2 REACTOR BUILDING EL. -17' 2 PT-24.6.4 Rev. 2 Page 42 of 48
^
. j
- OPERATING MNUAL TrupORAM REvi$f 0N FORN BSEP Fcre 7A (10/9]) n r_ .-
s X Tagorary Revision No. 7/ - 5 5 / . -
L DESCRIPT10M Volume Title, Procedure No., and Current Revision No. of Procedure kNNf M4[fr Ivi N8" "
I Hain ht bder muc oTn1 2 - P T- 2 4. 6. 4 , /2ev. 2-D 4/ 4O ik /t' /4 T / N k b* *i i Pages and Paragraphs Revised feust <l</f46,ealtn,j 2d2
! /
Reason for Rev1ston i
II R4lf VO N W W ** Y S k C'Esb Y D # 0" Coh /dth . Y & /5 9 m-ahd as<gt Originator I Date //~[8"Y[
II. Ih!TIAL APPRDVAL/ REVIEW kame Title N A ~ Date U ##
kame ! Title Thift S eervisor Date / /' D I t- v Er.te . in Cont , (es: Unit I / it 2 Ih// O% Title AY Cate #
/
/
// ~l' /
111. NpEAR SAFETT AND TECHNICAL REVIEWS (Vithin 14 days of implementation)
Technical feviews:
First Technical Reviewer Discipline Cate Second Technical Reviewer Discipline Date Sefety Deviews:
A!-109. Attachment 2, Safety Review Forms completed and attached. Date IV. TEMPORARY REV!510N APPROVAL / DISPOSITION
~
- 1. (K) Onetime use only. This revision mst be removed from Control Room copies on or before t/~3p 9 /
p,2 g PfMOVE from Control Room
- 2. () Permanent revision required on or before copies untti permanent revision is received.
- 3. ()
- Extension. This Temporary Revision has t.een extended until By Approved
- Person extending this Temporary Revision snest route copies as indicated in routing section.
Approved General Manager / Designee PkSC Required Cate Recomended PNSC Not Recomended Date V. i[MPORARY REV1510N REMOVAL (Onetime Use Only) j Tegorary Revision deleted from Control Roan copies. Unit 1 Unit 2 l Name Title Date 1
l
- Routing:
{
Criginal - Originating Unit / Subunit Copy - Control Room copy of procedure revised Copy - Records Management NOTE: 1.Ji H
PEVISTM til E 15153 ArTER ETrfrAir0N E.
BSEP/Vol. I, Ek. I 13 3 Rev. 134 i
t UNIT 2 -
PT-24.6.4 l CERTIFICATION AND REVIEW FORM ,
General Comments and Recommendations [8[ (/d /h CC24t 1/$ 8 /&
~ N'~! -kN fitAkurtin$ ,~)th ky f/&fdf l}r jfffyjjfg f f/ jj;4g9V
, Jt-6)-'1/
IV-2 5705 UwH Ftf M TfrW JW 9 '- 'M tr-T s rf f'S Cf6A//2)
C F F c? /LJ $ $l0lAh?L AEl/ 2 h?ct. i " " " *'i~'! t l A to fEbgW$;
l Initials Name (Print)
Test procedure performed by:
IV M/>A ' IC%M OA>A) h07 htK V
//g tJ_ A-/dr. /h ,7
%ltL H J,a 4!?, G<L Sh C Exc*ptions to satisfactory performance f *5a* ili[f( f g g;T Corrective action required a )
Test procedure hp_s bee /
atisfactorily to l'
/p f 9[
i Foreman ' '#
'? L w- '
/ c ~6 ' l' ***'
Signature Date Test procedure has not been satisfactorily completed Foreman 8 M Signature Date l Test has been reviewed by /2 91 Supervisor n- '
/ F # c
_/ ff 4** '
m
' /~ VTl 44-4:
Signature Date l l
2 PT-24.6.4 Rev. 2 , Page 43 of 48
l i
FIGURE 11.7.1 l Purpos.: Pr 2+. L A j Date: t l-74 A I I This figure is to be used to perform independent verifications with procedures l Iisted in ll.7.lb which do not contain provisions for independent verification sign-offs. All components repositioned as a result of the control procedure j shall be identified below, t
CUMPONENT POSITION VERIFICATIONS !
AS AS 1st 2nd j FOUND LEFT INIT. METHOD INITS METHOD mec us t. s . ws e.-- co, ca c> a PL AP L As C, l
.N og od [/-, d[ b n b 1'r10 ea n,a fL- Ae L / C l
$/u.h I r o l t
- The method for each verification must be identified. The code listed below i may be used. ,
.f&DI METHOD A Physical verification by hands on and confirming movement to the .
open/ throttled /close position. !
B Functional testing of the inte5 rated system or component as appropriate. ,
l C Visual verification of the component's position by direct '
l observation or remote indication. '
D Visual verification of the component's position by system process parameter changes as indicated by direct or remote indication or annunciation. !
e i Performed By:
(N==1 Initials
$d*MN fN '
N\.41tgl #'
klMI6X. $4 r
BSEP/Vol. I, Bk. 1 11-7 Rev. 134
4 9- ,
1- !
, UNIT 2 l- PT-24.6.4- !
i CERTIFICATION AND REVIEW FORM ceneral Com:nents - and Recommendations 1
Initials Name (Print)
Test procedure performed by; f'd**f Ob a si eime Exceptions to satisfactory performance Corrective action required Test procedure han been satisfactorily completed Foreman Signature Date Test procedure has not been satisfactorily completed Foreman Signature Date Test has been reviewed by Supervisor i Si 5nature Date F
f
~
2 PT-24.6.4 Rev. 2 Page 43 of 48
UNIT 2 FI-24.6.4 DATA SHEET 1 CONTROL ROOM CANAL NUC CONV RHRSV RBCCV VITAL VITAL TEXP CANAL HDR HDR STEP A(B) -I4OP SV HDR HDR TIME LEVEL PRE $S PRESS FI4V NO.
FI4V FIAV FIAV COMP 2-SCV- 2-SV-PI 2-SV-PI 2-E11 2-SV A-Ih0F B-IDOP POLNT LR-285 -143-1 -131-1 -FI-C382
-FI- 2-SV-FI 2-SV-FI R602A(B) 1158-1 -5114
+ r9t~) (ypu ) ty,- ) -5115)
(97-9.3.29 55.*?'f + /. O 13: 3 0 43 p; 6o n' 3000 - At*r 3500 Sr o SW 9.3.33 /5l27 ff 4*f - D. 6 fo r ST. S ' 3000 - 9t e , 3500 S20 SSO 9.3.42 ffo "Z. 9 ST S*f - 4 *1 6E" / I. 30@ ~ Af**y* 3500 WO
, Sto ,
2 PT-24.6.4 Rev. 1 Page 44 of 48 t
^
UNIT 2 PT-24.6.4 DATA SHEET 2 DIESEL CENERATORS SERVICE VATER FLOWS
,__.. _ ... m ___...-_ _. . _
DIESEL DIESEL CENERATOR #3 CENERATOR #4 STEP NO. JArKET VATER JACKET WATER COOLER SW COOLER SW FLOW FDW 9.3.29 _
/,19G Kye//4, / '/J/, 4 1< //u,'.
9.3.33 /.34 % Kgo// win J. 2 s*] E 9 e//,;,
9.3.42 fyYf5 Wyol/mlh -
/.172 hol/>in 1
~j,TGS~
et uult Y 1
i l
l l
i i
i l
l l
k 2 PT 24.6.4 Rev. 2 Page 45 of 48 a j
4 UNIT 2 PT-24.6.4 DATA SHEET 3 SERVICE VATER BUILDING
...r_...._:- = . - ~-=m._._. =.--------=._.__
_ _ _ ._ -=___ . - = ..:: _- -- -
CONV NUC NSW NSW NSW NSW FSW NSW FDR l4DR PMP A PMP B FMP A PMP A FUMP PUMP PRESS PRESS DISCH DISCH DISCH DISCH STEP 2A 2B TEST TEST PRESS PRESS STRN STRN NO. FLOW FLOW CAUGENI CAUGE42 PI- PI- AP AP at at 144 145 PDIC PDIC L PS- PS- -138 -140 ,
3213 3214 9.3.?9 5,7%, ,4,,,, $ _qq,7 gd ,,- g,, ; ,, . g,3 ,,; o , 3 _, s *,
G2 9 3*33 f'8 '
- Dim 4. cat n u 59. < p,' cc2 p 59 o s e' tO p ,. O.h p <* n.3 y _d y .._' ' i . ._ W_. B t-O _] O.. @ * & I&L 5%' lo O o s O'& P
C*4?si f.T* s ... u .. , '
Test Cauge #1 Data:
o CP&L No. DIN Range: O'/ f@ f' Installed El.: bO Cal Date: /l' 2,O' 9 / Cal. Due Date: /E / /0/f /
Test Gauge #2 Data:
CP&L No, b l26 Range: O'/N/3r Installed El.: 60' i Cal Date: [ldO'91 Cal. Due Date: l2 / lb / Ol
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l 2 PT-24.6.4 Rev. 2 Page 46 of 48 -
Y UNIT 2-PT-24.6.4 ;
-i DATA SHEET 4 :
REACTOR BUILDING EL. -17' i t
i VITAL VITAL VITAL HDR HDR HDR ,
SW A IDOP B IDOP STEP FIDW PRESS PRESS ;
NO. TEST TEST . !
GAUGE *3_ GAUGE 84 s at at Nf([! Aria) PI-821[per) PI-819(/97) 9.3.29 f. 046 7 63 'lt. (, 4 9.3.33 /.854 6 .'3 66 f 9.3.42 /. # 6 7 63 dr 4 It ;
Test Gauge #3 Data: ;
CP&L No. b I14 ' Range: 0-l00 Pd Installed El.: (-) / 2.G E S t
Cal Date: II-IS'i I Cal. Due Date: 11/ S' I / TI ;
l 1
Test Gauge #4 Data:
CP&L No. b"207,__ Range: 0 " LOO 94[ Installed El.: b I3 O j Cal Date: /l' II~ TI Cal. Due Date: IE / i / 9I '
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UNIT 2 .;
PT-24.6.4 , !
i DATA SiiEET 5 ;
l DATA ACQUISITION SHEET i
ATTAC1'J4ENT NO. : _ _ _ ./ j e
SITE NAME: 2 A A/PA/P j srEP No.: __9 3 f 7 t
DATE: Il J2& 14*
~n.,, ._= - = en =----..:.=.=_---..._-n...a..
._ -_ ,., .a--=.a.
TIME Vs VALC FI4W TOTAI. FIDW TOTAL DIFFERENCE !
237.0,I^ tut I 13 :3 I _ . . 14 tl % 4 "l.5 49 5. 5 n ad-13: 32 - LM 4 4 4 49 243 22 ^5 n l 13 :3 3 1444.4 _ J_9 248.95 e , n
- . ~ ,
tus4 ._j.g.q u. 4 . 49 _ _254.64 _ 5, q c IS l S_5 I444.4 a9 Pho.S4 e
- s. n. ~,
. _ _ _ I S
- S l> _L444.4 49 ' s tu b . n ca $_ n i; _
.._ _] 3 : 3 'l .I444.4 Sn 2 7 I. 8 o Average 5.70 #
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m u.h.. ,n UNIT 2 '!
PT-24.6.4'
{
DATA SilEET 5 !
DATA ACQUISITION SHEET .l ATTACllMENT NO.: .!
SITE NAME: 2AMM# !;
STEP NO.: 'YN ;
DATE: .11. /_ Edel_9_L.
'f!
r r=:e . ew.-use.*r =.m.--= m . .m-a=.me.s ==r m TIME Vs VALC FIDW TOTAL FLOW TOTAL DIFFERENCE
_.1 5 '28 1943.5 _ __ 'l9 S & '1. D 7 5, 3 g %au ;
15:29 !a sk ._
146 s't3.0 2 5 s er _
_ /S: An L4 4 3. 5 49 - _S 'l f . 9 9 g,9 2 16*31 2 4.4 3 5 -
4A 384.91 c me a.<,, ,
15 : 'S &_ i4 4_ _Sg_5 44 9 39oe64 , -,
w.v.
i 15 33 144s,4 LI B 394.85 nn
.. . s .,
I 5: 3 '] I443$ _
'l9 40 2 .'78 5.a. ,- l 1535 /qqq,5 4g yos.'T l-
-- Average 5.94_.E'*[m. .,
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'2 PT-24.6.4'Rev.'2- Page'48 of 48
UNIT 2 '
PT-24.6.4 DATA SHEET 5 :
DATA ACQUISITION SHEET ATTACllMENT NO.:
SITE NAME: ._
P STEP NO.:
- 3 'N _
DATE: .l_l. /.E419I
.::au . ,- a ~ _ - -
=.= n = - .---- - . - - -
i TIME Vs VALC FIDW TOTAL FIDW TOTAL DIFFERENCE IGE.$ ___
r el 4 3,1 49 IR4.cs 5 ao 1626 14 4 So __l Ll9 l 9 0. 0 S e _-
- u. a .-
._ 16 fl.e_ _.__. 14 tl 3. l 49 195. 9% -
- s. a v 16 2'1 1443.2 L19 201 89, c
-.s,n ;
/L 7n .
I443 2. 49 . 2 n7 8 Q_ .
.e, 9 n IG29- s q t-l 2. 2 a9 2 g 3, g l , d , a_ n 6.
,y V
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l_G3n l ud 3,2 49 219.69' e
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1 49 2E5.6 I !
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DATA ACQUISITION SHEET ATTAClbli.NI NO.: _
2 _._
i SITE NAME: _O#
2 ## -
3 STF.P NO.:
t DATE: .1L. ./.fk_/ AL
....,.m,_---;-..-..w.,,_-____
. . . , = . ._.n _ ,
TIME Vs VALC FLOW TOTAL- FIDW TOTAL i DIFFERENCE -l lo 2 9 -
(c.w p'"- 7 15:_3 .9 1443 5___. _ 'T 4 _ _ __ _ 4, g t
-- 15 4 o 14 U 3. r1 '74 14. 9 5 ~ ,,,.,. a. :
t 5'lI .._t 4 4.Lb '14 19. 5 A ,1,5e i542 14 st3. t.o !!4 24.I"1 > .;
z.u . i ~ ,
154 3 s q u 3. c, ry l p g , r7 3 o. . , _e,. i iS4 4 144t G .
'/ 4 33.44 ,, ,-
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1545 1445 G 'l4 3 8. b H ,, , ..
ew 15M6 1443.'1 44 42sfo 8 Average'4,t,z Yb*l/,-
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DATA ACQUISITION SHEET ,
ATTACHMENT NO.: (
SITE NAME: 2O# !
STEP No.: __ . S. 4 Z l DATE: 11 /26/91 !
.. - _ -, n - ... , = . - . __,__a ._
TIME Vs VALC FLOW TOTAL FIDW TOTALL l DIFFFRENCE f a
/634
/443.2 74 ~/ 2, 23 u_ g 3 i I G 3 5____ __ _ 144 %.2 '74 IL ,8 6 ,,_,e
._ /636 __ 1443.I _
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21.5l ,,
1639 1443.7 74 26,12 ,,
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7
/638 ) I./ 4 3. 2 '7 'l 36,9I ,
., . :- -o l639 ._ i44 s, t 14 35,29 ,, , ,,
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I&4O I44_3.? 'I4 39.91 ,1,r9-I&4I I44 3. l /74 4 4.52 :
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PT-24.6.4 i DATA SHEET 5 i
- l. DATA ACQUISITION SHEET AYTACHMENT NO.: __
SITE NAME: -- Od M 7 f /f/
l STEP NO.: .
7 E 2' 7 DATE: // ./30 / _9I_
l i
.. =:=-- cw-- -
l TIME Vs VALC F1hW TOTAL FLOW' TOTAL DIFFERENCE 1352 _] 367.1 _
50 3 I 91.45 K 1333 .. I381.0 50 3192.44 K l .49 K I334- l311. I 50 3I 44.44-K I.50 K }
I535 t 3 87. 0 60 3I96.94 K I .50 K ~l 135(o ._)387.o 5o 3197.43 K I .49 l<
1337 I387.0 SO 3t48,93 K I .50 K :l l338 1367.0 50 3200.43 K I.50 K l
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DATA SHEET 5 DATA ACQUISITION SHEET ATTACllMENT NO.: _ ___
3 i SITE NAME: _3 0 c. Je r__
STEP NO.: '3* 33 DATE: _/b 25.]i! ,
.i
..ta,_._&menv e=_.- .e= - _.---e -
TIME Vs VALC FIhW TOTAL FIDW TOTAL ,
DIFFERENCE ;
/530 .[_ / 3+7. / 50 5345.zz x ;
153I 1347.1 So 336 6.58 K I 3& K ^ i 1532. I347.1. 50 33C7.44 K I . 3to K ,
/5 33 / Sf7,2. So 3369.3o R / .34 K
/53f_ _. /3f 7,Z. So 337o. 47 K I.37 R !
t
/532 /347.Z. 50 3372.03R l.36 k l534
/3+7,0 49 3373.39 K 1. 3 /, K -
r Average /.3[,ZR 9
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DATA SHEET 5 t
DATA ACQUISITION SHEET !
1 AlfACllMENT NO.: _ 3 __.
SITE NAME- 3 0b M T -
. STEP NO.: . Y* k _
DATE: //l-25/N._
- im a_~.- -m.m ::x - :n-:xm.r=w w -
TIME Vs VALC FIDW TOTAL- FLOW TOTAL DIFFERENCE ,
)621 _ _ i349.0 50 3443.50X ;
/428 _
l.347.0 _
50 3444.64X I.56 K
__/G 2.4 /547.0 ._
50 5444. 23 K I . 57 K p 1630 - _J 546.7- 50 3447.54K 1. 56 K l 14 3 I J 5 4-6 8 50 5448.4( K .
I.57 K
/632- /314.7 50 3450.32 K 1.3/o K !
_. /433 /3 6.4 50 345/.49 K l.37 K i
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DATA SilEET 5
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DATA ACQUISITION SliEET ]
ATTACIL%NT NO. :
3 1 SITE NAME: 4M7 /4//
STEP NO.: Y 3 E9 DATE: .l_I_./ 20./ il l l
._,,n.,,.--c.-- ~ . - - - - ;.
n.-- _ =m ; . -a TJHE Vs VALC FLOW TOTAL FIDW TOTAL 3 '
DIFFERENCE I333 _
' ] 4to , 5' 90 119.f,4-K I334 I +20.4- 70 _ 119. 58 K I.44 K l l335 142.0.5 10 121.51 K I.4 5 K
)334 /420.5 10 IZ3.46' K I.4414 l 1337 If 20.5 10 /2 5.39 l< I.94 K l
__1338 I420.5 70 127.32 K 1.43 K I i
1534 _
1420.5 90 129.z4 K I .14 K I
AverageI.436g y/g7;
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2 PT-24.6.4 Rev. 2. Page 48_ of 48
UNIT.2 PT-24.6.4 j DATA SilEET 5 ;
DATA ACQUISITION SHEET ATTACHMENT NO.: . _ . _ Y !
SITE NAME: .
- 7 O 4 7E 7 STEP NO.: .
3 33 DATE: // / 2d] 8/ ~i w_w r.:.=_mm. v_. . _ _ 1 . _ _ . . _ _ _ _ . ==
f TIME Vs VALC F1hW iOTAL FIhW TOTAL DIFFERENCE *
/544 /439.o _
41 0.15 K j 1545 _
l441.7 41 2.16 K I.zI K .
/544 ._- _L4 31.o di 3.42 R l.24.K l
/547 _19_o.3 61 4,49 K l.z? K :
IS48 1441.7 4I 5,45 K l. 2.C. K _
1541 1441,1 4I 7.2I K t.26 K 1550 _.
14+1.9 6I 9.49 K l.Z6 K Average /,Z$fg ,.
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UNIT 2 PT-24.6.4 DATA SHEET 5 DATA ACQUISITION SHEET ATTAcilMENT NO.: 4 SITE NAME: Y 04 JM I STEP NO.: _ 7 3 iE DATE: , /b 2d i/ [
- - - = . ,
TIME Vs VALC FITN TOTAL FIDW TOTAL DIFFERENCE
/427 /4:T6.4 69 62.41 K , ' . !? K rh n
/6tS I431,o _
_ 41 53.86 K 1. I ? R 1629 I438,7 fa4 55.04 K l. I8 K ,
IG30 (435,*7 4,9 54.2I k II9K ;
__. I45l 1 +3 8. 9 70 5738K I.'I1k
/432. /+39.6 61 58.55 K / , / 7 /<
16 33 1438.7 49 54.72. K l. I 7 K m___ Average /.172R g [p, *, ,
e 2 PT-24.6.4 Rev. 2 Page 48 of 48
f UNIT 2
~
PT-24.6.4.
DATA SHEET 5 ,
DATA ACQUISITION SHEET i ATTACHMENT NO.: __
5 '
SITE NAME: ._ Yl I [ O M.
STEP NO.: *
-h7 ;
DATE: II / 2 E4 '/ 'l I +
mm.,--m = : __ -- _ - _ _ - - -
l TIME Vs VALC FIDW TOTAL FLOW TOTAL. ~'
DIFFERENCE lb.
- Nbb s'Y D ____ bbN.Nh -
i ,, a F56 i N33,8 85 335,65 7,!!- :
a31 NM , O f(5 3% . '70 ,' ' . 3 1 13 28 N 23,g xg- 33s7 75 ', ;p
.i is 64 N 33.5 x6 33 y. #L,> , ,, r- 1 E 35 ja 33. 5 0 33') . Y6 ', 3 6% N 33 X %4 340. Y7 _
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- 2 PT-24.6.4 Rev.-2 Page 48 of '.48 !'
i UNIT 2 PT-24.6.4 DATA SHEET 5 DATA ACQUISITION SHEET ATTACHMENT NO.:
I SITE NAME: 88_
STEP NO.: _ 3 3_ __
DATE: // /_f.81 //
l
= _ . --..~. = -- - __,
TIME Vs VALC F1hV TOTAL FlfW TOTAL DIFFERENCE J526 /4M z. 85 o.440 M / o&
_ _ J 52<1 /433 1 BD /. 59 /. o f
_ J 630 /432 6 65 2-51 /. t> 5~
_ /UI MM. O 8V 3.6V /. 06
_ J 532- / A32 . '1 _ 89 A.70 /. 0C
_.J 633 /4324 65 F.76
._ Average /gpf- -/<444/_
r 2 PT-24.6.4 Rev. 2 Page 48 of 48
'.. =; .
UNIT 2- 1 PT-24.6.4 !
i
' DATA SHEET 5 I
-l DATA ACQUISITION SHEET !
ATTACllMENT NO.: 8 SITE NAME: _ Y_ N l STEP NO.*
- I-DATE: [_f_fdf 9/ !
"he~ 7 - ~~'
_ _ . .- - - ._. __ _ ,aa ,_ _ . f TIME Vs VALC FIDW TOTAL FLOW TOTAL -!
DIFFERENCE I L A2+ I
/+3z .J 85 2 .i +- -
/.or, Eka e 425 /+32. +- 65 5.30 M'M
/626 M32.f 85 f 37 /.0 7 *
// 27 M 52 6 _ 85 54+ j. o y )
- /628 i+ 32. 4- 85- 65o /. 0 6 -
- . +
H29 M 3z.3 as 7 54 /. 06 1
/430 /A v .4- 89 8. t; + J. oe. _ ;
~
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