ML20080T363
| ML20080T363 | |
| Person / Time | |
|---|---|
| Site: | Farley, 05000000 |
| Issue date: | 01/25/1980 |
| From: | Shipman W ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML20079E758 | List: |
| References | |
| FOIA-83-789 FNP-1-IMP-224.2, NUDOCS 8403010163 | |
| Download: ML20080T363 (62) | |
Text
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- 5 ^* VOL. 3 FNP-1-D!P-224.2 January 25, 1980
'j ' Revision 1 .
I FARLEY NUCLEAR PLANT . INSTRUMENT MAINTENANCE PROCEDURE FNP-1-IMP-224.2
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5 A F E T Y REACTOR COOLANT DRAIN TANK LEVEL, LT-1003 R E L A T E
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Approved: ,, ["' M MaintenanceSughrintendent
'Date Issued: h J/ h
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0403010163 840125
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VOL. 3 LIST OF EFFECTIVE PAGES iP ^1 ?"o-224'2
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PAGE
' REVISION NO. 0 NO. -
0 1 2 l, 4 3 5 6 7- 8 9 to
-l X 2 X '
3 X 4 X 5 X . 1 6 X l . 7 X 8 X 9 X 10 X 11 X 12 X DATA PACXAGE IMP-22 4.2A 1 X 2 X 3 X 4 X 5 X 6 X 7 X Paca 1 mf 1
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l VOL.,8 FNP-1-IMP-224.2 w FARLEY NUCLEA2 PLANT UNIT 1 INSTRUMENT MAINTENANCE PROCEDURE I:G-224. 2 REACTOR COOLANT DRAIN TANK LEVEL, LT-1003 l1.0 . Purpose , 1.1 The. purpose of this procedure is tov ' erify and, if required, re-establish the accuracies -and control functions of the channel sensor and ass ~ociated sig-nal processing equipment. l.2 This procedure is written for normal compler;a cali-bration; hewever, partial performance is also possible. Partial performance is divided into: 1) the sensor, sections 2.0 ~ through 7.1 and 7.9 or 2) signal pro-cessing equipment excluding the controller sections 2.0 through 6.0 and 7. 2 through 7.9 excluding sections
- 7. 7. or . 3) the controller .only, sections 2.0 through
- 6. 0, 7. 2 and 7. 7 through 7. 9.
T2.~ 0 Acceptance Criteria 2.1 The acceptance ' criteria for this test is that the process instrumentation provide in-tolerance con-version of the process parameter and perforn its as-designed indication and control functions. The setpoints. and tolerances to be used are contained in the data package listed as . reference 3.1. 3.0 Re ferences 3.1 - FNP-1-IMP-224.2A, Instrument Maintenance Procedure Data . Package / Surveillance Test Procedure Data Pack-age. 3.2 U-260930 Barton Model'396/352 D/P Transmitter, Calibra- < tion section 6-1-4.4, Maintenance section 6-1-3. Rev. 0
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FNP-1-I.AT-224.2 VOL. I S
- 3. 3 U-183501, Westinghouse Drawing 2 71C597, Sh. 43.
.4 3 U-183509, Westinghouse Drawing 271C59 7, Sh. 51.
c- -3. 5 U-183499, Westinghouse Drawing 2 71C597, Sh. 40. 3.6 U-183497, Westinghouse Drawing 271C597, Sh. 38.
- 3. 7 ' . U- 16 79 8 9, ~ Elem. Wiring Diag., RC Drain Tank Pump No. 1.
3.8 U-16 79 90, Elem. Wiring Diag., RC Drain Tank Pump No. 2. , I 3.9_ ~D-181762, Waste Process Liquid Pannel Connection Diagram N1G21NBWPP26033-N. . I 3.10- U-260716, . PCS Users Guide Instruction Manual. 3.10.1 Model 62-H Controller, sections 18-710, 18-711.
.3.10.2 Model 63U-B Duplex Alarm, sections 18-692, 18-693.
- 3.'10.3 Model 630-A Single Alarm, sections 18-690, 18-691.
'3.10.4 Acopian-- Power Supply, Non-Foxboro Material section.
3.11 U-260715, Waste Process Baron Recycle Panel Instruc-
' tion Manual.
' 3.12 L D-1750 42, Sh. 1, P&ID Waste' Process Sys. P&ID.
'4.0 Test Eculpment 4.1 Fluke _ Digital Multimeter, Model 8120A or equivalent
'.2).
42~ Transmation Transmitter Simulator, Model 1040 or equivalent (2). l 4. 3 General Radio Decade Box, Model 1433-T or equivalent. 4.4 Wallace and Tiernan Pneumatic Calibrator, Series 6 5-120 - (0-125 in. WC) or equivalent. __ 7,
-2' ?ev. O i '
=
UL. 8 FNP-1-IMP-224.2 5.0 Precautions and Limitations-5.1 All. reference'to dataisheets by this procedure is to data sheets contained in reference 3.1. All reference to attachments are to the attachments of FNP-0-IMP-443.1. .-- :5.2 Critical proceditre sections and steps are listed on page-2 of.the data package used with this procedure and are marked with an asterisk (*) within the
. body of this procedure.- As each critical step.or section is completed, initial on the space provided on Table 1 of th,e data package.
5.3 .0bserve all precautions and limitations listed in FNP-0-IMP-0, General Instrumentation and Controls
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Precautions and-Limitations.. 5.4 ;Do not perform any of the following during this test: 5.4.l' .PRT normal cooldown n 5.4.2 Excess letdown operation 5.4.3 Loop, Accumulator, or PRT draining operation 5.5 If clearance is required on RCDT LI-1003 root valves , 1-LWP-V-7145A and.3, PT-1004 will be disabled. Re-for to initial conditions, precautions and limitations of IMP-224.1. 5.6: Transmitter MUST be revented if the. Drain Tank is drained below the lower instrument tap.
'6.0 LInitial Conditions
' 6 .1 RCDT level- is less than - 504 if RCP No. 1- seal leak-
.off es established..
6.2 RCDT pumps lA and .UB are OFF and RCDT level control
, valve 1-LWD-LCV-1003 is in manual and closed.
- 6. 3 - ~The Shift. Foreman has granted administrative authority to perform this test and is aware of indications,
-alarms and printouts.that will' result.
7.0 Detailed Procedure 7.1 Calibrate D/P transmitter LT-1003 as follows:
*7.1.1- Open the equalizing valve.
Rev. 0
+ -
, , , ,- ,- ,-. , ..-.~,.,,.,,,,..._.-~,-.n,,,.,,,
r= - 9 yoL. 8' FNP-1-IMP-224.2 4
- 7.1. 2 Have the High pressure rcot valve, 1-LWP-V-7145A closed and tagged.
- 7.1. 3 Have the Lo pressure root valve, 1-LWP-V-7145B closed and tagged.
CAUTION: Do not open the vent fittings on [ the transmitter.
- 7.1. 4 Vent the high pressure leg by opening the process test connection (swacelok fitting) on the high pressure (upper) bellows iso-lation housing.
- 7.1. 5 Open the . drain and calibration vnive and drain the sensing lines. Collect any fluid in a suitable container.
CACTION: Observe caution when handling con-taminated fluids.
- 7.1. 6 Connect the test pressure source and test p pressure gauge to the drain and calibration connection.
- 7.1. 7 Close the equalizing valve.
7.1. 8 Connect a DVM to the transnitter test re-sistor. 7.1.9- Vary the transmitter input as necessary to obtain a transmitter output equal to 0.12 VDC across the 10 ohm test resistor. Verify that the D.'C. potential across the trans-mitter output terminals is 35 1 2.4VDC.
- 7. l'.10 If the voltage is out of tolerance, measure and record on data sheet i the " AS FOUND" potential at the Liquid Waste Process Cabinet, between TB-L4, terminal 11(-) and LP/1003, re d (+) test jack. Then adjust LQ-100 3, R-7 (voltage adjust pot) in the Liquid Waste Pro-cess Panel, to obtain 4 8. 0 - 0. 25VDC at the above terminals and record Ehe FINAL value.
7.1.11 Apply the inputs called for en data sheet 1 and record " AS FOUND" data. Rev. 0 mme m J r ' . - . . . . . .
VOL. 8 FNP-1-IMP-224.2 7.1.12 I f " AS FOUND" data is within tolerance, no , further adj us tments are required. Proceed to step 7.1.15. 7.1.13 If " AS FOUND" data is out of tolerance, apply a test pressure equal to 0% of the trans-mitter span and adjust the transmitter "ERO to obtain the required value shcwn on data sheet 1. 7.1.14 Apply a test pressure equal to 100% of the transmitter span, and adjust the SPAN to L obtain the required value shown on data sheet 1. T
'7.1. 15 Repeat step 7.1.12 and 7.1.13 until both zero and span meet required values.
7.1.16 Apply. the values called for on data sheet 1
.and ensure all output values are within tole-r ances . . If transmitter output is non-linear, offset the transmitter zero and span within the allowed tolerances to minimize the maxi-mum difference between "REQUIPID" and " FINAL"
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data. If the transmitter cannot be calibrated
-using these instructions, refer to reference 3.2. Record the " FINAL" data on data sheet 1.
*7.1.17 Replace the cap on the upper bellows isolation housing.
*7.1.18 Close the drain and calibration valve.
- 7. 1.19 Disconnect all test equipment connected to the transmitter and return the transmitter to service as follows:
*7. 1. 19. 1 Open the equalizing valve
. *7.1.19.2 Have the transmitter high pressure
- cot valve opened.
*7.1.19.3 Have the transmitter low pressure root valve opened.
7.1.19.4 Do not close the equalizing valve. Rev. 0
VOL .~ 8 FNP-1-IMP-224.2
*7.1.19.5 Vent .the low pressure leg at the Icwer bellows isolation vent (swage-lok fitting).
NOTE: If required, vent PT-100 4.
- 7. 2 Calibration' Setup
*7.2.1 Pull power supply, LQ-100 3 out of its socket in the Liquid Waste Process. Panel.
*7.2.2 Lift the, leads from Liquid Waste Process Panel, TB-L4, ' terminals 10 and 11 and connect the transmitter simulator to the terminals.
*7.2.3- Reinsert LQ-1003 in its socket'.
7.2.4 Conneet a DVM to LP.1003 inside the Liquid Waste Process Panel. This DVM is connected across a 250 chm resistor and is to be used for adjusting. transmitter simulator input values'during the remainder of this test.
*7.3 Calibration Acopian Modelof Pcwer Sucoly, 48-LIO,_L6 LC-1003,id cation - Liqu Waste Process Panel.
7.3.1 Adjust the transmitter simulator for an in-put of 12 mA. Measure and record on data sheet 2, the " AS FOUND" DC potential in the Liquid Waste Process Cabinet between terminals TB-L4, terminal 11 and LP/1003, red (+) test jack.
"* 7.3.2 Adjust power supply LQ-1003, R-7 (voltage adjust pot.) to cbtain a DC potential of -
48.0 VDC. 7.3.3 Record the FINAL DC potential on data sheet 2.
*7.4. Indicator Calibration, Number LI-1003 Location Liquid Waste Process Panel.
7.4.1 Apply the inputs called for on data sheet 2 by adjusting the transmitter simulator and record " AS FOUND" values . Rev. 0 9 6 i_u.
VOL.: 8 FNP-1-IMP-224.2
?
e 7.4.2 'If' required adjust the indicator's zero screw to' minimize the maximum error. NOTE: Do not turn zero screw more than t 1/4 turn in either direction. 7.4.3 If : tolerances cannot be met, replace the indicator and repeat 7.4.1.
; 7.4.4 Record " FINAL" data.
7.5 Calibration of Signal Comparator, LB-1003
.Model 63U-B,. Location Liquid Waste Process Panel.
7.5.1 Adjust the transmitter simulator so that the comparator LB-100 3A is reset (Annun-
+ciator-1-1, REACTOR COOLANT DRAIN TANK HI-LOW LEVEL, Liquid Waste Process Panel is OFF).
*7.5.2 H1' Alarm 7.5.2.1 Slowly increase the input from the transmitter simulator and record the " AS FOUND" value, on data sheet 3, at which the -comparator trips (as indicated by Ann. 1-1 turning ON).
7.5.2.2' Slowly decrease the input from the transmitter simulator and record the value at which the comparator resets (as indicated by Ann. 1- 1 turning OFF).
*7.5.3 Lo Alarm
'-J 7.5.3.1 Slowly decrease the input from the transmitter simulator and record the " AS FOUND" 'value , on data sheet 3, at which the comparator trips (as indicated by Ann. 1-1 turning ON) .
7.5.3.2 ' Slowly increase the input from the transmitter simulator and record the value at which the comparator e resets (as indicated by Ann. 1- 1 turning OFF) . Rev. 0 s v y- -m -w
Q m
~. .- - VOL, 8 FNP-1-IMP-224.2 7.5.4 If necessary adjust the comparator in accordance with reference 3.10.2. (Note:
reset is the same as lockup adjustment) . 7.5.5. Record FINAL trip and reset values on data sheet 3.
*7.6
_ Calibration of Signal Comparator, LB-100 3B Model 63U-A, Location ^ Liquid Waste Process Panel.
. 7. 6.1 Connect a DVM (ohms scale) to Liquid Waste Process Panel, relay LY-1003B , terminals 9 and 10.,
7.6.2 Adjust the transmitter simulator so that comparator, LB-100 3B is reset (short on relay LY-1003B, terminals 9 and 10). 7.6.3 Slowly decrease the input from the trans-mitter simulator and recard the " AS FOUND" value, on data sheet 4, at which the com-
.parator trips (as indicated by an open on LY-10038, terminals 9 and 10).
7.6.4 Slowly increase the input from the. trans-mitter simulator and record the " AS FOUND" value at which the comparator resets (as indicated by a short on LY-100 3B, terminals 9 and 10) . 7.6.5' If necessary adjust the ccmparator in accer-dance with reference 3.10. 3. (Note: reset is the same - as lockup adjustment) . 7.6.6 Record. FINAL trip and reset values on data
, sheet 4. Remove the DVM.
*7.7 Calibration of Controller, LC-100 3 Model 62H, S tyle C', Location Liquid Waste Process Panel.
7.7.1 Record the " AS FOUND" switch and potentiometer settings on data sheet 5. 7.7.2 Unplug controller LC-100 3. 7.7.3 Lift the leads from Liquid Waste Process Panel,-TB-L4, terminals 13 and 14. 7.7.4 Connect a decade resistance adjusted for 250. 00 ohms , to TB-L4, terminals 13 and 14, in order to monitor controller output. Rev. O
P VOL. 8 FNP-1-IMP-224.2 1 7.7.5 Re-energize LC-1003. 7.7.6 Position transfer switch to MANUAL. 7.7.7 Position the transfer switch to the extreme right until the output is maximum. Record - the "AS FOUND" DVM and controller output meter readings on data sheet 5. 7.7.8 Position the transfer switch to the extreme left until the output is minimum. Record the " AS . FOUND" DVM and controller output meter readings on data sheet 5. 7.7.9 If necessary, adjust the outpur limits in accordance with- reference 3.10.1 and repeat step 7.7.7 and 7.7.8. 7.7.10 Position the transfer switch to AUTO. 7.7.11- Turn Reset kneb to maximum. 7.7.12 Turn Derivativa knob to minimum (OFF) . 7.7.13 Turn set point knob to 50% of scale. 7.7.14 Apply the inpt es called for en data sheet
- 5. Allow the controller to stabilize and record the "AS FOUND" controller output.
7.7.15 If necessary, adjust the controller in accordance with reference 3.10.1 and repeat steps 7. 7.10 thru 7. 7.14. 7.7.16 Record " FINAL" data. 7.7.17 Unplug controller LC-1003. 7.7.18 Remove the decade resistor connected in step 7.7.4. Remove the transmitter simulator. 7.7.19 At LC-1003 rear terminal beard, jumper terminal 7 to 3 and terminal 6 to 2. 7.7.20 Centroller setup 7.7.20.1 Turn Proportional Band kneb to minimum. Rev. O w.
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-u, 1 .
f VOL.' 8 , r3p _1-I,v.P- 2 2 4 . 2 f 7.7.20.2 Turn Reset knob to minimum. 7.7.20.3 . Turn Derivative knob to minimum.
-7.7.20.4 Set Reversing switch to CEC.
7.7.20.5 Turn set point knob to 50%. 7.7.20.6 Position transfer switch to AUTO. 7.7.20.7 Reenergize controller LC-100 3. 7.7.21 Controller Functional Check. If any of the required controller operations in step 7.7.21 are incorrect, trouble shoot in accordance with reference 3.10.1 and repeat step 7. 7.21. 7.7.21.1 Verify Deviation Meter reads null t two devisions (center scale) . 7.7.21.2 verify outpit meter reads 50 5% of scale. 7.7.21.3 Rotate setpoint knob upscale and down-scale. Verify the output meter tracks and the deviation meter always reads null. 7.7.21.4 Position the transfer switch to MANUAL. 7.7.21.5 Turn the setpoint knob to 50% of scale. Use the transfer switch to manually adjust the controller output meter to 50% of scale. Verify the deviation meter reads. null
- 2 divisions.
7.7.21.6 Position the transfer switch to AUTO. Turn Proportional Band knob to maximum.
- Verify the deviation meter reads null t 2 divisions.
7.7.21.7 Record (initial) controller functional check'on data sheec 5. % .7.7.22 Controller Derivative Check. If the controller operation is incorrect in S tep 7. 7.22, troub le -
-shoot in accordance with' reference 3.10.1 and repeat step 7.7.22.
7.7.22.1 Unplug controller LC-1003. 7.7.22.2 Remove jumpers connected in step 7.7.19. Rev .- 0
\
VOL. 8 FNP-1-IMP-224.2 7.7.22.3 At the Liquid Waste Precess Panel, TB-L4, jumper terminals 13 and 14. 7.7.22.4 Connect 2 transmitter simulators and a switch to TB-L4, terminals 10 and 11 to provide a step change input. 7.7.22.5 Turn Proportional knob to 100%. 7.7.22.6 Turn Reset kncb to maximum. 7.7.22.7, Turn Derivative kncb to 1.2 minutes. 7.7.22.8 Set reversing switch to INC. 7.7.22.9 Turn set point knob to 0% of crale. 7.7.22.10 Verify load switch (SW5) is turned clockwise. 7.7.22.11 Reenergize LC-1003 7.7.22.12 Position transfer switch to AUTO. 7.7.22.13 Af ter the controller has stabilized, step the input from 10mA to 12=A. 7.7.22.14 Verify that the output meter reaches a peak between 30% and 40% and slowly drops back to approximately 5%. 7.7.22.15 If necessary, trouble shoot the con-troller in accordance with reference 3.10.1 and repea: 7.7.21. 7.7.22.16 Record (initial) controller derivative check on data sheet 5. 7.8 . Restoration
*7.8.1 Unplug controller LC-1003. Remove Power Supply LQ-1003.
*7.8.2 Remove all test equipment.
*7.8.'3 Remove jumpers attached in step 7.7.22.3.
*7.8.4 Reconnect leads TB-L4, terminals 10 and 11 (step 7.2. 2) and TB-L4, terminals 13 and 14 (step 7. 7. 3) .
, Rev. 0 k_
t - VOL. 8 FfP-1-IMP-224.2
*7.8.5 Reenergize LC-1003. Reinsert LQ-1003. .
*7.8.6 Return all controller settings to their initial values.
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NOTE: Proportional band may have a new setting if adjusted in step 7.7.15.
- 7.9- Notify the.. shift foreman that the test is complete.
e 1 Rev. 0 h f 4 he m
..___.c_. , _ ._ _ , , , _ . _ _ . . _ . , _ . - . - , . _,
VOL. 8 FNP-1-IMP-224.2A FARLEY NUCLEAR PLXIT UNIT 1 INSTRUMENT .'!AINTENANCE PROCEDUPE DATA PACKAGE IMP-22 4. 2 REACTOR CbOLANT DRAIN TANK LEVEL, LT-1003 1.0 Purpose This data package is to be used in conjunction with procedure FNP-1-IMP-224.2 to record calibration data and provide calibration setpoints and tolerances. 2.0 Re ferences 2.1 Farley. Nuclear Plant Precautions, Limitaticns and Set Points for Nuclear Steam Supply Systems. 2.2 Farley Nuclear Plant Process Instrumentation Accuracy Requirements and Guidelines, E-PCS-8327. 3.0 Procedure Sicn-Of f Sheet and Alteration Loc 3.1 Initial the appropriate space in Table 1 as each step or section is completed in IMP-224.2.
- 3. 2 Record any temporary alteration directed by attach-ments to IMP-2 24. 2 on Table 2.
4.0 Test Results' 4.1 Test completed satisfactory 4.2 ((} Deficiencies occurred (see data sheets for explana-tion) 4.3 Time required for test Procedure Rev. used 4.4 Test performed by Date
' ~~
4.5 Test reviewed by Date r> This data package consists of 7 pages. Rev. 0 1
3 Vol. 8 FNP-1-TMP-224.2A'. PACE 2. REACTOR OMM. ANT DRAIN TANK LEVEL., l.T-1003
~ ' 'sT.l* O':... _SI'C T I D N -. . . . _ _ _ _ .
INITIAL.S STl:P 01: S ECT IOli
-.....__..__......_--__.._c___.
1 H I T I Ai.'. InESCRIPT10ii 013 AI. TEN AT IDH AI.TER F.I. R ES'l Ol: Ell { 6.0 , , , I ni t ia I Cond I t.1 o.ns_ _ . _ . _ . _ , 7.3 __.fwr. Sup.Ca1. _._ . ___. . _ _ _ _ _ _ _ . , . _ _ _ . _ _ . . . _ _ . _ . _ . . . . _ , . . . . .. .__ . , _ _ , . _ j 7.1 . . .
,, Transeitter.Ca.l._ , . _ _ _ . _ 7.4 ___ind.1cator Ca1.______. __ , _ . , _ _ __ _ .._ ._ _... . _ _ _ . _ _ _ . _ . _ _ _ .._
!7.1.I .
Open Equa1 VaIve , _ , _ . _ _ _ _ _ 7,5.[2__Compa to to r.,Ca [ . _Il! . _ .._ . .._. .. . _ _ _ _ . . . . , _ . _ _ _ _ . . _ _ . _ . . _ _ _ _ _ . _ 1-l7.1.2 IIP Root Va1ve . 7 5 3_._Comparator_Ca1._l,qw_ _ _ _ _ . . . _ _ _ ____ _ _ , _ _ _ _ _ _ i
]7.1.3 1.P Root Valve 7.6 Cpoparator Cal,__ _...__ ...
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- I +!L _.. Ven t _ IIP. L.eg -
. 77 ControMer Cal.__,,,.._, _ ___ _ . . . . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ , _ _. ;7.1.5 Drain Lines 7.8.1 Decnergize Ckt.
t 1 7 .I.6
. Test Source _ 7.8.2. Remove Test Equip. . . . .._ . . . . _ _. . _ , . . .- __. . _ .
7.1.7 , Close Equal VaIve. _ 7. 8.3 Remove. Jumpers. . . . . . . . _ _ _ . . . _ . . . . . . . _ _ - . _ _ . .. .. i7.1.17 ,, Replace Cap _ _ _ _ , _ , _ 7.8.4 Coi,;<:et Info 7.1.18 Close Valve 7.8.5 Energize Ckt. ;
'7.1.19.1 Open Equal Valve 7.8.6 Controller Settings 7.1.19.2 IIP Root Valve 7.9 Noti fy_ S.tilf t Foreman I
7.l.19.3 I.P Root VaIve f
,7.1.19.5 Vent LP 1.cg I ;7.2.1 Remove Pwr. Sup.
7.2.2 Lift 1. cads 7.2.3 Insert Pw. Sup. I' !;'.:
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'g -1 W ST?-04271 PIACTOR C00LAN~ SYSTE4 LEAKAG" EVALUATION dji I. GE.*ERAL PRECAU'" IONS }}7
- 1. The Reactor Coolant Syste= leakage rate =ust be in acecrdance with Tech.-Spec. 3.1 - I.
- 2. If . emergency boration has taken place, the a=t. of =akeup to the RCS must be esti=ated and added to the total makeup for the day, or-a new set of initial data =ust be taken.
II. GROSS LEAKAGE E7ALUATION ~. A. Initial Conditions
- 1. System pressure is 2250 psia. .
- 2. The following data is available:
- a. Fro = start of ti=e interval under consideration (a) Tave v
@m.= . -(b) Volume Control Tank Level (c) Diversion flev integ ator reading (d) Pressuricer level
- b. At the time of de ,e ._ination
-(a) Tave (b) Volume control tank level S~ .( c) Diversion flov integrator reading ,; .. y (d) -Pressuricer level
- c. The amount of Reacter Coclant Syste= =akeup in last 24 hours.
- _ 3. Procedure-
. l.. C apute the gross Recesor Coolant Syste= leakage, in Ft. 3 for a=v length of time fro = the followin5 fo: =ula (specific volu=es are listed in Table 1.): .:-2:. - *Es . ::CT2 - Subtract any =akeup flov not sent the RCS or VCT.L(i.e. makeup to 31.7, ete). Fev. 1 GROSS ROS L*:ATAGE (? 3 6 120*F) n .f t, -)f .. ._ _ _ -- _ _ y~ 154.6 (V1-Vo ) + M/u-Div - 2.L9L ($1-LPO) - 3.651 (LVl-LVO) yy 7.460 -Where: Vo= Specific volu=e at previous Tave . . Vi= Specific volune at present Tave . . . . _ ~ M/u = Gallons of Make-up Div- = Gallons of letdovn diverted LPO = Previous pressurizer level (in.) LPl = Present pressurizer level (in.) LVO = Previous VCT level . LV1 = Presen: VCT level
- 2. Change the leakage obtained in Step 1 to GPM by:
- a. GPM = f:3 (0.12hT) t gjjs Where:
ft3 =_ Leakage fro: Step 1 t = Time interval in hours between sets of data - NOTE - .If time interval is 2h hours use: GPM = F:3 (5,195 x ic-3) , , Specific volu=es are 61ven in Table 1 . =. . . S ?ev. 1 L r. h ' III. DAILY DETERMINATION OF RIftCTOR COCLAIC SYSTI'! LE.FAGE TO THE EACTOR - C00LluO DRAI'i TANK F' -- in? A. . Initial' Conditions
- 1. . - The R.C. Drain Punp is not r=ning. ?iot draining RC Drn Tank.
- 2. NSSS Te.perature is greater than 532 F. .
- 3. The regenerative heat exchanger drains (CVC-193, CVC-19h, CVC-318, and CVC-319) are shut.
- 1. .The safety injection leakage isolation valve (SI-661) is shut.
5 Draining from the Reactor Coolant Syste is not in progress.
- 6. Draining of the qu'ench tank is not in progress.
- 7. Reactor Coolant Pu=p contro' ad v eed-off'is aligned to the VCT ,
and the RCP controlled bleed-off rt: lief (CVC-199-RV) is shut.
- 8. The follovf.ng reliefs have not lifted:
A. RCP 11A Co ponent Cocling Water Relief (CC-3835)
- 55. 3. RCP 113 Cc=ponent Cooling Water Relief (CC-3S36)
=.. - -C. RCP 12A Co=ponent Cooling Water Relief (CC-3837) D. RCP 123 Co=penent Coolins Water Relief (CC-3335) - NOTE - The major sources of leakage to the reactor coolant drain tank is frc= valve ste: leakoff and 'the reactor coolant p=p vaper seals.
- 3. Procedure
- 1. Observe the R.C. drain tank level fer a period of six (6) hours.
- 2. From the cha:.ge in level and Table 2 cc=nute the vol=e changs g
~ '*n the Reactor Coolant drain tanh.
- 3. To obtain the valve ste= leak rate in G.P.M. divide the value 55 from Step 2 by 360.
- -=- 2ev. 1 IV.: NET LEAXAGE EVALUATION ~' c .. 'A. -Initial Conditions See 9'2' _ -1. Section II & III of this STP have been perfor:ed.
- 3. Procedure -
, Subtract value of reactor coolant syste= leakage to the reacter coolant d. rain tank' fre= the value obtained in Section II. 9 e *5.....*_ . . Sste O w S S $ 43 k 'ev. 1. 4._ m,. 7 .- 4 ~ cp r i .d . c
- V'( ft3) ct 2250 PSIA
, 5-;- , ( LSM ) ,.: .ra. '0!i* TEMP *? 'v- TD9 ? T 530 .o.02079 553- 0.021h3 531 0.02082 55h 0.021L6 532 0.020Bk 555 - - -- - 0.~o 21h 9 533 0.02087 556 0.02152 53h 0.02089 557 0.02155 535 0.02092 , 556 0.02158 536 0.02095 559 0.02161 . 537 -0.02097 560 0.0216h 538 0.02100 561 0.02167 539 0.02102 - 562 0.02171 Sho 'O.021oS 563 0.0217h k d. figt ski 0.02105 56h 0.02177 SL2 0.021n 565 0.02180 . Sh3 0.0211h 566 0.021BL Shh 0.02n7 567 0.02187 Sh5- 0.02120 56S o.02190 Sk6 0.02122 -569 0.0219h . 5Tk o.02125 ~ 570 0.02197 Sh8 0.02128 - 571 0.02201 549 0.02131 572 0.0220h -.'.- 750 o.0213h 573 c.0220S 551 O.02137 57h c.02211 552 0.021ko 575 0.02215 ft+ =~ . Rev. 1 L: - p 1A=L:. c .. . . . &D < ,:. DEm - u . VOL. U CAL. D1M - U . VOL. U GAL, .??$1 1 3.76 28 . h9h.23 2 10.56 29 517.0h 3 19.20 30 539.60 ; f. -U . . k 29.66 31 562.06 ' ~~ "4 2.f . ./ ' '5 kl.28 32 Slk.22 i., s , s w. M 6 Sk.38 33 607.h5 7 68.36 3h 628.h7 gJ. ( t, 39 3 t-8 83.5h- - 35 650.17 .9 99.k3 36 , 671.61 10 115.98 37 692.59 11 133.52 38 713.27 12 -151.80 39 , 733.6h "91 13 170.37 bo". 753.'hk . =k5- ~ 1h 189.77, kl 772.8h ...,7. fc : :,7 15 209.58 h2 791.k1 I ' ,- l ( c . ' '~ 16 229.9h h3 809.69 1T 250.62 hk 827.23 2.4 ).1 ) '#"* I 1( 3 5~. Fd 18 271.60 h5 8h3.78 ^ 19 ,293.0L . h6- 859.67 20 31k.7h kT 87k.85 . 21 333.75 h6 888.82 f v 1. E ! 22 358.99 49 901.93 -23 381.15 50 913.55 2h h03.61 51 92k.01 25 h26.17' 52 932.65 26 hh8.98 53 939.h5 9h3.21 ~ 27 L71.60 Sh - l, s 4- ?.ev. 1 E r- ': y .I -l T b .N! Wj, ' il '; I" g l E E .N k P'. S O t sg \n h< e <:; ' r,
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- =-
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= = * = ; O C' O- ": x t = C6 e = O i =, -= s w =- -' i e. s. f ;< < < l: M : .m.:- .- " e II - c 1 h.,: w:' O, n :,'e .- -.o c - 6.,. O o - n em,o e c . = - r 'l - - - 0 - ') ~ [* 3 c .c ,h..r s g.3 h .=-* ;af af < :" < < 3 3it 4 3 9 ft *I 4 I,; 4 il 4. I L. I " ! h 2i .e .- ..o r" r-'i.=... - J. . . r 8 . . .., . . l '* -l
- d. d A A c
== r= r - -. -
- 1
=g =v . r g . . * == - Q =,= l]g . L g=. A A g g .g u g ) l l 8 i H - 54 - = --- w- - y- w ., , , - ' . _ , - - , - , , , , , ,-w - - . - ,- , yy ~ F: . g; ' ST?-0-27-l REACTOR ' C00LA:iT SYSTC l?M T,E EVALUATION ~I. GriESAL PRECA TIO!;S '1. ""ne Reactor Coolant Systen leGace rate nust be in accorhnee with Tech. Spec. 3.1 - E.
- 2) .If energency boration hss taken pisce, the ant. of nakeup to the RCSI=ust be estinated and sided to the total :.deup for the day,
- or a'new set of initial data nust be taken. II. G30SS~ LEAKAGE EVAL"ATION ' ~ A.' - Initial Conditions .1._' System pressure is 2250 psia. -2. The following data is available:
- a. From start of tine interval under consideration (a) Tsve v
~ (b) 1Volune Control . Tank Level ' t (c) Diversion flov integrator reading ~ (d) Pressurizer level b.- - At the tine of deter =ination . (a)' Tave (b) Volume control tank level (c) ~ Diversion flow intecrator reading ; (d) Pressurizer -1r.el ,. c. The anonnt of Reactor Coolant Systen nGeup in last 2h * :crs.
- 3. Procedun .
- 1. Co .pute the gress ?ctetor Coolant Cysten Ic2ksge, in 7t. 3 for any lenctn of tine from the follodng for. uls (specific volunes are s
listed in Table 1.): 2 72 - Suttrset av .Gup flow not sent the ?"3 or VCT (i.e. nWeup to .Ta?, etc). fev. 1 y -- .-,..,,p. ,p., , ,- ..w -- , m-. -- w , -, .--y a -*- --' - T .- * ; , /; , . L I 0 . /./ GMr3 ""' S LEAGGE (Ft3 9 120*F) = / r.. [ -/fl _ _ -. I ;' ( *. L -- 4 K r.41 154.'6 (Vy -V o) + J/u-Div - 2.L91 (LPl-LPO) - 3.651 (LVl-Lyo) ' ~. ~ -
- VlYo 73g[7
- p. '
- Where: r .- ? :. ; C . ' Vo= Specific volune at previous Tsve fl, n .- ((,p . , , ( 9, ' d. . s ;A,/ . , - t . . ,l,,;_ Vi_=~ Specific volume at present Te.ve 't, ,'. , y' . .w - . !. e* ,1 C, ,,. Q-'-- M/.u = Gr.11ons of "s'.e-up .. Div = Gallons of letacvn diverted ' w.. LP0 = Previous pressurizer level (in.) * - LP1 =- Present pressurir.er level (in.) LVO.= Previous VCT level - LV1 = Present VCT level . -2. Chr.nge the ledu;e cbtained in Step 1 to GPM by: .
- a. GFM = ft3 (0.12kT): #' ~ /
*,( *'cere: ft 3 '= Ledase frc. Step 1
- t = Tine interval in h:urs between sets of data NOTE - -
If time interval is 2k hou s use: GPM = Ft3 (5 195 x 10-3) , . Specific voluees are given in '~sble 1 8 e . t + * . e e 3e w e 4 -g e d 6 'm .1 4-IV. ET LE?d?SE EVtL*iATION A. Initial Con-litions s
- 1. Section II & III of this STP have teen perfor:.ed.
B. Procedure Subtract value of reactor coolant systes leakage to the re te!.or coolant drain tank frcm the value obtained in Section II. e # 4 ru. 1 y_ -- .i. -;- U . ? , ; III.- MILY GCE?uiIJJATIOM 0F FFACTOR COOLKiT SYSTF21 LFK~X,F: 70 '""rt E RFACTOR ;COOLRLiT 3?AT3 ?KiK e. A. Initial Conditions - 3
- 1. The R.C. Drain Pump is not-running. Not irsining RC Drn Tsnk.
- 2. NSSS. Temperature'is greater than 532 F.
- 3. The regenerative heat exchsnger drains (CvC-193, CVC-19h, CVC-318, and CVC-319) are shut.
- h. The safety injection leakage isolation valve (SI-661) is-shut'.
. .s- 5. - ' Draining from the Teactor CooJ ant System is not in progress.
- 6. Draining of the quench tank is not in pro 6ress.
7 Reactor Coolant Pamp controlled bleed-off is aligned to the VCT - s and the RCP controlled bleed-off relief (CVC-199-RV) is shut. -8., The following reliefs have not lifted: A. RCP 11A Cceponent Cooling' Water Relief (CC-3835) L-
- 3. ECP.113 Cocponent' Cooling Water Relief (CC-3336)
. C. ? RCP 12A Component Cooling Water Relief (CC-3837) ~ D. ECP 123 Ccaponern Cooling Water Felief (CC-3533) - NOTE - The major sources of leakage to the reactor coolant drain tank is from valve ste= leakoff - and the reactor coolsnt pump vapor sesis.
- 3. ,?rocedure
^* 1. - Chserve the R.C. drain tank level for a period of six (6) hours.
- 2. Frcs the change in level and Table 2 compute the volume chsnse
. in the. Reactor Coolant drain tank. <3. To'ottain the valve ste: leak rste in G.P.M. divide the value - from Step 2.by 360 s=- S e'.* . 1 Table k-8 a.- g...:=. , Reactor Coolant Piping Para =eters .!Tumber.of loops 2 . Flow per loop, Ib/hr 61 x 10 ~ Pipe ~ Size -Reactor outlet, ID, in, ' h2 Reactor inlet, ID , in. 30 Surge line, nominal,.in.; 12- -Design Pressure, psia.- 2500' Design Temperature, *FL , 650 ~ Velocity! Hot leg, ft/see h2 Velocity: Cold leg, ft/sec. 37 - The reactor coolant' piping is designed and fabricated in accordance with the rules and procedures of ANSI B31.7, Class I. Ihe anticipated transients ' listed:in Section h.2.1 for= the'bssis -for the required fatigue analysis to insure an adequate useage factor. The reactor. coolant piping is fabricated' from~ SA516-GR70 carbon steel mill J,spn. -clad internally with type 304L stainless steel. A minimum clad thickness 2 p %gjgE1 ~ of 1/8. inch is maintained. The 12-inch surge line is . fabricated fram ASTH . A351 Gr CF8M -alloy steel. - \. Thermal sleeves are installed in the' surge no::le, charging no::les and shut- . down cooling inlet no::le to reduce thermal shock effects from auxiliary systems. Clad sections of piping are fitted, where necessary, with safe ends
- for field welding to stainless-steel components.
The piping .is shop fabr'cated .and shop velded into subasse=blies to the greatest. extent ~ practicable to-=inimize the amount of field velding. F abri-cation of1 piping and. subassemblies is done by shop personnel experienced in -=aking large heavy wall velds. Welding procedures and operations meet the requirements of Section IX of the' ASNE Boiler ~ and Pressure Vessel. Code. . All ' velds are LOO percent ~ radiographed and liquid-penetrant tested and all reactor coolant piping penetrations are attached in accordance with the require =ents of: ANSI B317. ~ Cleanliness standards consistent with nuclear service are-maintained during fabrication and erection. h.3 5 PRESSURIZER The pressurizer maintains reactor coolant syste= operating pressure and compensates for _ changes in coolant. volume durins load changes. Table h-9 4;? gives design parameters for the pressuriser. ~The pressurizer is shown in Figure h-8. 2W ==3r E R'ev. 9-10-71 h-17~ u.- . Table k-9
- p. Pressurizer Parameters Design Pressure, psia 2,500 Design Temperature. *F 700 Normal Opera' t ing Pressure, psia 2250 Normal' 0perating Temperature, *F 653 3
Internal Free Volu=e, ft 1500 2 - Normal Operating-Water Volume, ft' / 600-800 Normal Steam Volume, Full Power, ft 700-900 Installed Heater Capacity, kw 1500 Spray Flovi Maxi =um, spm 375 Spray Flow, Continuous, sp:' 15 -: Nozzles ... ; Surge Line (1 ea) nominal, in. 12 Safety and Relief Valves-{2) ID, in. L "" Spray (1 ea) no=inal, in. - k - ^ Heaters (120 ea) OD, in.- 0.875 Instrument,' Level (k ea) nominal, in. 1 Temperature (1 ea) nominal, in. 1 Pressure (2 ea) nominal, in. 1 ' Matericls Vessel A-533, or 3, class 1 Cladding .~ Stainless Steel
- and y , Ni-Cr-Fe Alley
' Dimensions - Overall Length, in. Lhi 3/8 Outside-Diameter, in. 106 1/2 .Inside Diameter, in. 95 9/16 Cladding Thickness,'in. (mini =us) 1/8 Dry Weight, Including Heaters, lb 206,000 Flooded Veight, Including Heaters, lb 300,000-L *Ueld deposited type 306-309 stainless steel composition with type 308 in r-contact with coolant. '.;.g:p,c h-18 y Y ' 54: :. - .. :.:L' REACTOR CCOLANT SYSTEM ; REACTOR'C00LANT SYSTEM LEAKAGE LIMITING CONDITION FOR OPERATION .. 3.4.6.2 Reactor Coolant System leakage shall be limited to: , # 'a. No PRESSURE BOUNDARY LEAKAGE , - ~
- b. ,o..GPM .l UNIDENTIFIED LEAKAGE,' l
- c. 1 GPM total piimary-to-secondary leakage through steam generators, M
~ + and.
- d. '10:GPh IDENTIFIED LEAKAGE from the Rec tor Coolant System. Et APPLICABILITY: MODES 1, 2, 3 and 4. k:
ACTION: . .. *'~C. 'a. 'With any PRESSURE BOUNDARY LEAKAGE, be 14 at least HOT STANDBY f=== . . .R: within 6 hours and in COLD SHUTDOWN within the.following 30 ~ hours. .y b'. .With any Reactor Coolant System leakage greater that sny one of the above limits, excluding PRESSURE BCuNDARY LEAKAv., reduce r the leakage rate to within limits.within 4 hours or be in at. T least HOT STANDBY within the next 6 hours and in CULD SHUTDOWN in M within the following 30 hours. {-!
- s. _f(
SURVEILLANCE-REQUIREMENTS - ~ 4.4.6'.2 ' Reactor Coolant System leakages ~ shall be damonstrated to be , within each of the above limits by: .. 'a . Monitoring'.the containment atmosphere particulate radioactivity in at-least once per 12 hours, s-
- =.
- b. Monitoring.the containment sump discharge frequency at least M once per 12 hours, E .. -
- c. Performance of a Reactor Coolant System water Sventory balance E=.
- at least once per 72 hours-during steady state operation . -i=- T' texcept when operating in the shutdown cooling mode, and ist::- [.g..
p CAL'iERT CLIFFS-UNIT 2- 3/4 4-14 i%::. , .~7 ::2 :L. . d . 4...,..... . . . . . . . . . . . . . . . , .. , t -k.2. DESIGN BASIS'
- W h.2.1 LDESIGN PARAMETERS
.The reacter ecolant system vill cperate initially at a power level of 2570 Met but:it is anticipated that the conservatively designed rystem vill be capable of attaining higher power levels. For this reasen, the major systems and components which bear'significantly-on the acceptability of the site have been evaluated for operation at a power level of 2700 MWt. The principal design parameters for the reactor. coolant . system are listed in
- Table ' k-1. The design parameters for each of the major ecmponents are given
'in Section k.3 for each individual component. The reactor coolant system is- designated a Class 1 system for seismic design and is designed to the -criteria' for'icad combinations and stresses which are presented in Table h-2. l . kable . k-1 s Principal Design Parameters Of Reacter Coolant System g.* Design Themal Power, Mwt 2570 Y Btu /hr 8.73 x 10 9 ~ j LDesign Pressure, psia 2500 ~ Design Temperature (Except Pressu'cizer), 'T 650 .N- 6 g;; Coolant Flow Rate, Ib/hr 122 x 10 Cold Leg Temperature, Operating, *F. Shk.5 Average Temperature, Maxi =um, 'T 572.5 Hot Leg Temperature, Maximum, 'T. 599.4 Nomal Operating Pressure, psia 2250 System. Volume,' ft3 (Wi,thout Pressurizer) 0601 Pressurizer Water Volume, ft 3 800 Pressurizer Steam Volume, ft 3 700 The system design . temperature and pressure are conservatively established and exceed the combined normal operating value and the change due to anticipated operating transients. " hey include the effects of instrument ; error and the response characteristics of the control system. The change due to the ' anticipated transients. also considers the effect of reactor - core themal lag, coolant transport time, system pressure drop and the characteristics of the safety and relief valves. .3 ;2= ^ =, e h-3 - 4 4 .1.,. }s } ' L i. '. - . drN .. .. .t. ... .t. q sf ,.f . ... .a. . . : . .}.... . ..Q 4". ., . . V /C.t . (/J l/.Of. fp) g.".J.. ... .- ... .J' ' . . ... . ' . ' . . _.~ .u_l:... . . ' t. .i. . . ~ ..3, ..r .. . . . . . .t . .s ... .. v . .. .. . ... .. / .. ... . . . . . . . . . .. .. . .. 1 .g. .t. ) .L p. ..... .. . . . ._. . 1 . . .. ..,... 3(y .... .... ... . . .... s. ..I.. . . .. . p. ..~ s. . ..J......w..... .... .. ... .. . ...,.4 . . , f..... .. . ._. . . ... .. ..\. s 7, d . .t. . .. . 1..... ...... .. . !. . .... . . .. . ... ..l..... . . . . . ,....... .. . . .... . _ . . - .. .... . ....h.... .. _. .. .l . . ... ~... .. ..~ ~ ". . ..... ' ~' ~ .!~ . . ~ ' a..c. ... . .... .. .. .. ... . . . .$.= *. ..$..6. e... )Zd ~ . . . '~~' ~'~~ ' . . . .*. ..*.j- . . M.... ..... =. ,. . . .... . . .... ..J..** .. .Iu .. .l . .p ... ,,.a e ..4 -C .. . ... . . . ..... ... .~.. . . w. . .~ . ... ._. _. s ., . 2.$- ,g. , g,J . ... ... -. r.... ..J. . ...t.J- -*1 .. . , . ,... . .... . . . . , .. . .. .. .4 . . . ..i. . f .. . ...4 ... . _ . Z. . ... . . ,1. .. . .... ..._. . .....<., ... . . .... . . . . 2 ., .... . $~. . . .......4,
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