ML20134D394
| ML20134D394 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 12/27/1996 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20134D254 | List: |
| References | |
| 96-0284, 96-284, NUDOCS 9702050123 | |
| Download: ML20134D394 (43) | |
Text
,
f NUCLEAR , .,WER 4USINESS-UNTT - - --
,4 CALCULATION REgW.AND AP/ROVAL culation #
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LLr of Pages 7 + ( eW*he + ry Title of Calculation: .
(/nced A5cocMul P M M54rvmeJ*hh vfed sh IT-(2_ k IT-13
$r CC.O 1% fC p Original Calculation Qk QA-Scope O Revised Calculation. Revision #
D Superseding Calculation. Supersedes Calculation #
Modification #
Description:
Other
References:
Prepared By: Date:
, , D'fI ~5 f9 (o
' Ibis Calculation has been re/ viewed in accordance with NP 7.2.4. The review was accomplished by one or a combination of the following (as checked):
A review of a representative sample of repetitive A detailed review of the original calculation.
calculations.
A review of the calculation against a similar A review by an alternate, simplified, or calculation previously performed. approximate method of calculation.
Comments:
r 9702050123 970122 PDR ADOCK 05000301 '
P PDR Date: Aporoved Bv: Date:
Reviewed Bv: .
(f*k 4l% Wld1/90 t g r< _. .m. _____. 1 li -
ear-im q j DEC 3 0 Revision 1 02/27/95 ( l9 *""' Reference (s): NP 7.2.4 i
w
TITLE: Uncarttinty Associstad with. CALCULATION # : 96-0284 Instrumsntztion Ussd in Prepared By: EJM IT-12 & IT-13 for CCW Pumps Date:12/23/96 Page 7 of R
- b. Uncertainty associated with PI-692A (see Section F.3)
U692 = 1.10 psi . /
c . Uncertainty associated with PI-617A (see Section F.4)
U617 = i2.24 psi /
The uncertainties associated with 1-PI-692A and 1-PI-617A, in psi, must be converted to an equivalent uncertainty in gpm in order to combine the pressure uncertainty with the uncertainty associated with the flow instrument. Therefore, the pump curve at the test point (3400 gpm) was used to approximate an associated change in gallons per minute due to an uncertainty in psi. Selecting this point to take the slope maximizes the error contribution of the pressure indicators. (assumption 2) A tangential line to the pump curve was drawn at the testing point from which a slope (ft/gpm) was obtained to convert the uncertainty in psi to an uncertainty in gpm. This method has been determined to be an acceptable approach and has been evaluated independently by Duke Engineering Services. (reference 10)
The two points taken off the tangential line to develop the slope were 275 feet at 1900 gpm, and 150 feet at 5950 gpm. The conversion factor used to convert ft to psi (2.336) assumes a water temperature of 125 F which is the upper temperature for the CCW system from the draft CCW Design l
Basis Document.
/ /
275 ft- 150 ft psi 1.32E - 2 psi / gpm #-
m = = 3.09E - 2 ft / gprn x =
1900 gpm - 5950 gpm 2.336 f t v /
U692 = i 1.10 psi x 9 P"' r- 2 83 gpm /
1.32E - 2 psi U617 = 12.24 psi x 9P* = 1170 gpm /
1.32E - 2 psi Now that the units of the individual uncertainties are consistent, the total uncertainty associated with the instruments used to test the CCW pumps can be calculated via the SRSS method.
- d. Combining the uncertainties from these three instruments gives the following for total uncertainty:
TITLE: U',cirttinty Associited with CALCULATION # : 96-0284 4
instrumsntstion Uszd in Prepared By: EJM IT-12 & IT-13 for CCW Pumps Date:12/23/96 Page Kol'N utotai =
/(~U692)' + (U617)' + (U619)2 4
Utotal = h3 gpm)' + (170 gpm)2 + (529 gpm)'
Utotal = 562 gpm ,/
H. Results The totalinstrument uncertainty, expressed in gpm, associated with the inservice test procedure for the component cooling water pumps is 562 gpm.
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9Y' OPERABILITYDETERhflNATION
/
Noter Prompt Operability Determinations should be made as soon as possible commensurate uith the safety importance of the SSC affected, and, in most cases, within 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> (can be extended up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> per DCS discretion) (See NP 5.3. 7). l
- 1. Potentially degraded or nonconforming structure, system or component (SSC):
Component Cooling Water Pumps 2 Structure, system or component's safety function:
The Safety-Related (SR) heat loads of the Component Cooling (CC) system are: The residual heat removal (RHR) heat exchangers during the recirculation phase of safety injection (SI); the seal water coolers of the RHR, SI and containment spray (CS) pumps during the recirculation phase of SI; the reactor coolant pump (RCP) thermal barriers during heatup, cooldown, hot shutdown and power operation.
The CC pumps circulate cooling water through the CC system, transferring heat from the SR loads (and non-SR loads) to the service water (SW) system.
- 3. Under what circumstances (Including postulated accidents) would the problem exist; Identify failure mechanism if possible:
The IST program does not reflect design basis requirements. As a result Section XI criteria may not be conservative in ensuring design basis requirements are met.
- 4. Applicable Technical Specification or Current Licensing Basis requirement or commitment and why the requirement or commitment may be met.
The required flow through the RHR heat exchanger is established by FSAR section 9.3. The FSAR defines RHR heat exchanger shell side (the CC side) flow to be 1.375x10' lb/hr. By performing urut conversions the resultant required flow is 2780 gpm This basis was further evaluated by SER 96 055.
The required flows through the seal water coole., of the RHR pumps and of the CS pumps are 10 gpm, per unit. The required flow through the seal water coolers of the SI pumps are 20 gpm, per unit.
These flow requirements come from the respective pump component instruction manuals (CIMs) and system design basis documents (DBDs).
The required flow through the RCP thermal barners is 50 gpm, per unit. This requirement is listed in the RCP CIM.
The flows required during the recirculation phase of SI, per the CC draft DBD and WCAP-13938, are the recirculation phase flows listed in #2 above, 2820 gpm, as well as 75 gpm to the sample system heat exchangers. Total component coohng flow required for the recirculation phase loads is 2895 gpm.
The flow required during plant heatup is 2420 gpm, per the CC draft DBD and WCAP-13938. The plant heatup flow is bounded by the recirculation phase flow requirement of 2895 gpm.
The flow required during power operation is 2290 gpm for unit one and 2627 gpm for unit two. Unit two is higher due to the radwaste CC loads. These flow requirements are per the CC draft DBD and WCAP-13938. The power operation flows are bounded by the recirculation phase flow requirement of 2895 gpm.
PDF 1553 NP537 Revmon 1 I1/27.96
l l The CC draft DBD and WCAP-13938 list two plant operational modes, plant cooldown and refueling, as requiring flows greater than 2895 gpm. However, these flowrates are to achieve maximum allowed cooldown or heat removal rate. One pump can accommodate the heat removal load on one unit either following a loss-of-coolant (LOCA) accident or during normal plant shutdown, per FSAR section 9.3 and Tech Specs 15.3.3. To accomplish this, flow to a RHR heat exchanger would be adjusted and/or flow to non-essential loads would be throttled or secured. The sump recire flow requirement is therefore considered to be limiting.
- 5. How was degradation /nonconformance discovered?
This generic concern was first identified in June 1996 as a specific concern for safety injection pump acceptance criteria from ASME Section XI versus design requirements Condition Report 96-416.
The flow required during the recirculation phase of SI is 2895 gpm. Calculation 96-0284 (attached) determined that uncertainty associated with the instrumentation used in IT-12 & IT-13 is +/- 562 gpm, for the flow range considered. Therefore design basis (DB) required flow is 3457 gpm.
The CC pumps are operable as long as they are capable of providing the DB required flow of 3457 gpm.
1 During IT-12 & IT-13, each CC pump is operated at 3600 gpm flow, though the exact flow and pressure is not recorded This flow is greater than the DB total of 3457 gpm. Thus, the quarterly ITs verify that the CC pumps can meet their DB flow requirements.
The RHR heat exchanger throttle valves, w hich define CC flow requirements, were set during performance of WMTP 12.1I in 1990 and 1989, for umts I and 2 respectively. These tests er,sured that the throttic valves were set to obtain at least 2780 gpm through the RHR heat exchangers. These tests also defined pump performance at a number of pomts along the pump curves. As shown on the attached pump curves, subsequent inservice tests show that the pumps are operating at essentially the same performance curve as demonstrated dunng the WMTPs.
d Recommendations:
- 1) IT-12 & IT-13 should be revised, so that pump performance data is taken at the DB required flow, 3457 gpm, or higher.
- 2) WMTP 12.11 should be made into a test uhich is performed on a regularly scheduled basis to better determine system loads and performance.
- 7. Does initial Operability Determination need more conclusive evidence for support (such as additional testing, research, or analysis)? If yes, list proposed action (s) which will need to be accomplished in the In-Depth Operability Analysis:
No.
Prepared by: _ _ Date/ Time: 12/3c/4 (e, . IMD Active SRO: _
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!) C li APPROVAL Daie Daie _,
E S Cognaant Group Head AppewaJ Supt-Operstions Approvst (it Required)
- 5 s l N APPROVAL Date Date l
N PRIOR Group Head Approval Manager . PBNP Approval (if Required) s TO USE R Date Date l Other Approval (if Required) Other Appetwal (!! Required) '
' DSS for Operations procedures and Group Head or Supervisor, as spectied, for other group procedures See other side for summiary of P8NP 2.t.1 approval equinaments. j Mti . . .;<,n i 4 .. l l
. . .__ ..m.. _. _ __ . __ _ .. _
l l WMTP 12.11 COMPONENT COOLING SYSTEM FLOW TEST 4AJOR
'.evision 1 11-02-89 d
1.0 PURPOSE (' h ' i 7 "l' C O L. "
To demonstrate that the performance of the component cooling water system
, has not degraded significantly since the initial functional test. Specific 2
items covered are:
4 1.1 Flow balance i
1.2 Pump performance 1.3 Throttle valve position
2.0 REFERENCES
2.1 Component Cooling System Description TRHB 10.9.
2.2 Final Facility Description and Safety Analysis Report, Volume 3, Chapter 9.
2.3 Westinghouse Flow Diagram 110E018 Sheet 1 Westinghouse Flow Diagram 110E018 Sheet 2 Westinghouse Flow Diagram 110E018 Sheet 3 2.4 Component "ooling System Functional Tests.
WMTP H-2.3, Revision 1, January 8, 1971 WMTP H-2.3, Revision 3, June 25, 1970 WMTP H-2.3A, supplement "A", March 10, 1971 2.5 Operating Procedure OP-6A, Operation of Component Cooling System.
3.0 DISCUSSION This test will try to verify normal operating flows of the component cooling water system. If the flow appears to be incorrect, valves 824A and 824B will be manipulated to try to establish the correct flow.
4.0 PRECAUTIONS AND LIMITATIONS All precautions in operating procedure OP-6A must be observed during this test.
5.0 INITIAL CONDITIONS Initials Date 5.1 The component cooling water system is aligned for normal plant operation. 6C/9sP' c-2/ #ft?
5.2 The RHR heat exchangers are not receiving CCW flow. &C kbtV & 21 YO Page 1 of 6
- : l
\
j l e WMTP 12.11 i
e COMPONENT COOLING SYSTEM FLOW TEST MAJOR Revision 1
. 11-02-89 Initials Date 5.3 CCW pump PllA is operating. CCW pump PilB is secured. ([24/9' ,
5.4 The following equipment is not required for operation.
5.4.1 Boric acid evaporator 4
- 5.4.2 Excess letdown heat exchanger l
, 5.4.3 Waste evaporator (Unit 1 test only) ,
, 5.4.4 Blowdown evaporator bottoms cooler (Unit 2 test only) 3
, 5.4.5 Unit 2 letdown gas stripper system (Unit 2 test only) N.. Y 6 Al '/O 5.5 Install temporary instruments to allow current measurements to be taken for both CCW pumps. #0lV 6-22 '/O 5.6 Unit 1 letdown flow is about 40 gpm (Unit 2 test only).
NA 6 - 2/ '/O 5.7 The non-regenerative heat exchanger CCW flow is less than 300 gpm. $6M 6 2 8-W 6.0 PROCEDURE 6.1 Record the data sptcified in Table 6-1. 6-" '7#
6.2 Secure component cooling water flow to one of the CCW heat exchangers.
8 Y CCW heat exchan,er secured. c. . < ~
6.3 secure the following systems if they are !
receiving CCW flow: i
.f d . -- C?.'.-2 00: PIL!EF "?.L"" 7'i .".f.Y L!n '""'!? SECURING--
p~ ""
C.5.Cr00 IE,70^'4: :".'.".T EXO S255".
" . IF
- :.!NC , C:".'"' "?.LV" 700 TO STOP n'"
- 0:000".C5.
'f. /.' l 5 6.3.1 The excess letdown heat exchanger by v
- , 'il closing valve -Mb 76 L, . Y ( 24
f, Page 2 of 6
WMTP 12.11 ,
COMPONENT COOLING SYSTEM FLOW TEST MAJOR l Revision 1 11-02-89 1
d Initials Date 1
6.3.2 (Unit I test only). The waste evapora-
- tor condenser by closing inlet and outlet valves 776A and 776B. /*'/9 # 4 -27 fo 6.3.3 The boric acid evaporator condenser and distillate cooler by closing inlet #
valves 744A and 748A and outlet d!
, valve 744B. C' di '
6.3.4 (Unit 2 test only) The blowdown evaporator bottoms cooler by securing gf g the bottoms cooler circ pump, P136. IA A 6.4 (Unit 2 test only) Divert Unit 2 letdown from l l the gas stripper system. 14 NI A 4 6.5 Record data specified in Table 6-1. ' ' E3 #'
- /9# ,
6.6 (Unit 2 test only). Determine the flow to the radvaste system by subtracting all measured CCW loads from the total CCW flow.
Radwaste system flow 0 gpm. 4 0 4 6 . ~/ Establish flow to "A" RHR heat exchanger
! by opening Valve 738A. '94 4 - 2 L -4 o i 6.8 Record the data specified in Table 6-1. *d/ 6~ #
6.9 Determine flow to RHR heat exchar.ger by subtracting the total flow of the other users (including radwaste system) from the indicated i flow at FT619. Record this number in Table 6-1 ,$$/ ,"c,io under the Heading 6.8 or 6.14 as appropriate.
L, CAUTION: THE FOLLOWING STEP MAY CAUSE UNDESIRABLE FLOW CHANGES IN OTHER CCW FLOW PATHS. THE VALVE MANIPULATION SHOULD BE DONE SLOWLY TO ALLOW THE OPERATOR TIME TO EVALUATE THE EFFECTS ON OTHER SYSTEMS.
6.10 If the RHR heat exchanger flow is not equal to or a little more than the design value (2780 gpm), o then adjust Valve 824A (824B) to obtain the desired fhv. M ge Page 3 of 6
WMTP 13.11 i COMPONENT COOLING SYSTEM FLOW TEST MAJOR Revision 1 11-02-89 l
i Initials Date 6.11 Record the data specified in Table 6-1. , et/ (, l ' #
- 6.12 Isolate "A" RHR heat exchanger by closing !
Valve 738A. (.2L 7* I 6.13 Supply CCW flow to "B" RHR hea*. exchanger by !
"'"[
opening Valve 7388. ,6 ' y . ,, , j l 6.14 Repeat Steps 6.8, 6.9 and 6.10. WA (,-&M d i
6.15 Record the data specified in Table 5-1, 4/r#- 0
- 9 w.<r ns,Terusceaue vuf
- 3 6.16 Secure-component-cooling.npump P11A- and_ allow 4
( i. , cm-nt cooling-pump-P118-to-star-t. Restart Pila if PHB-does e t-ete 4 cr-if'ifischarge 4
b.
1 check valve sticks open, r/f 4 (,[ze 5
6.17 Record the data specified in Table 6-1. 'Y 6/bt 6.18 Isolate 'B" RHR heat exchanger by closing Valve 738B. <* /* l' N ~'
i 6.19 Record the data specified in Table 6-1. A# 6 [2 L 6.20 Supply CCW flow to "A" RHR heat exchanger by opening Valve 738A. M (k 6.2I Record the data specified in Table 6-1. e'/h (AL I
6.22 Start component cooling water purrp Pila and l l
leave both Ccw pumps operating. m# C /c c.
CALTTION : MINIMIZE THE TIME THAT TWO CCW PUMPS ARE '
SUPPLYING CNE CCW HEAT EXCHANGER.
6.23 vent and establish flow to the component cooling ,
water heat exchanger secured in Step 6.2. s'# 6 /t t-6.24 Reestablish flow to "B" RHR heat exchanger by opening Valve 738B. M// 8/c'd 6.25 Do not change any throttle valve positions and record the data specified in Table 6-1. Y #
.p ..
- ,7 p 6.26 Isolate flow to-ben RHR heat exchanger)( by
.( closing Valveg ??"" W 738A. "
t' 2 t
.y Page 4 of 6
wMTP 12.11 CJMPONENT COOLING SYSTEM FLOW TEST MAJOR Revision 1 11-02-89 Initials Date 6.27 Secure component cooling water pump PllA. # 6/J --
l 6.28 Reestablish flow to any of the following systems that are desired for normal operation.
6.28.1 The excess letdown heat exchanger by opening Valves 766 (if shut in Step 6.3) and 769. M///-- 6/ja 6,28.2 (Unit 1 test only) The waste evaporator condenser by opening inlet and outlet Valves 776A and 776B. Y- _
Mcc 6.28.3 The boric acid evaporator condenser and distillate cooler by opening inlet and l
outlet Valves 744A, 748A and 744B. ,.g g~
6.28.4 (Unit 2 test only) The blowdown evaporator bottoms cooler by starting g y I
the bottoms cooler cire pump, P136 A b 6.29 (Unit 2 test only) Reestablish Unit 2 letdown flow to the gas stripper system if desired, b tA p E
, 6.30 Record the data specified in Table 6-1. #h# c > L '/e 7.0 RESULTS
, 7.1 Acceptance Criteria Verify that flow to each RHR heat exchanger is at least 2780 gpm {
under accident conditions. '
7.2 Review Criteria 7.2.1 Review flow data to assure all flows seem consistent with i the system lineups. i 7.2.2 Evaluate pump head curves and pump current to show that the pump is operating as expected.
7.2.3 Verify that flow to any RHR heat exchanger is not likely to I exceed 1.5 times the design flow, or about 4100 gpm, during accident or any other conditions.
, zj7 .E, , t,u t e ' I. ' ' ts 0 RK /w.sf w hunger ,
,.I
( p'.
c ic . n s*h' 7 5 b 0. "h '
f r' age 5 of 6
CL WMTP 12.
..cNT COOLING SYSTEM FLOW TEST .
MAJOR
- Revision 1 11-02-89 + '
TABLE (-I l DESCRIPTION COMPONENT COOLING DATA STEP NUMBER 6.1 6.5 6.8 6.11 6.14 6.15 6.17 6.19 6.21 6.25 6.30 Boric Acid & Dist. Cooler Flow FI-642 d o o o o () o o <> d 0 Total RCP Flow Flo13 22i 2.2/. /r/ IN o't /7f e/o J 2 r, nc / 7o 3.rc FI609 223 221 tri tyr / /3' N? !Sla 22co RHR Pump Flow FI640
/72 svr 22}
2 2 a' _27.i f9 284 19 Ji 9 J 2. .tJ.s 22 2s.r J7.c Waste Gas Compressor KIA Flow ;
(Unit 1 only) F1643 ## #i I% Jo 19 30 J o. C J Y. 3 28 5 Je 2/ i Waste Cas Compressor K1B Flow !
(Unit 1 only) FI645 2i JYS // /1 /I '11 ' 9-i 2! /T l
Ii 2J 2- !
Excess Letdown HXE Flow FI607 o o
/'t o o a o O d o //<l Waste Evap. Cond. Flow FI647 (Unit 1 only) O O O o O O O c) 0 0 C Seal Water Heat Exchanger Flow FI605 '32 33 <? f 109 Tr /or lof, /3/.y /oc /o</ 131 Non-Regenerative Heat Exchanger FI601 5 f g Containment Spray Pump HXE FI649 C_ f <~ C r f f C 3G 32 19 2i s ?.f 25 5' Safety Injection Pump HXE FI650 21 2g 21. r 20.2 27 i 4L gz_ 23 I z_ 21 3, 3sS Y85 y I. '2- 18 'fz.
Sample Heat Exchanger FI603 94 c,3 Sc 73 c7 93 'ts- 1G 7f- 74 ??
J Total CCW Flow FT619 Ifrom PPCS) /OW 975 VJ75 382f fMO gge g/0 Sco 3gg (,5 g fgff Residual Heat Exchanger Flow CCW Pump Discharge Pressure PSIG k Yf k -h
-- M.,1'y
((dk. e Sb -
/3/ 9 '/ f6 ,7 1 19 Sf in 14 2 ta f /66 (3i /dG #33' CCW Pump Suction Temperature TI616 /*C 'f '? <f t 9 '1 91
> CCW Pump Current
'l l r2 'il 9 .L 93 72 I?2 /4 8 262 Jio 2. i 'i 150 Valve 824A Position (0-90)
Z (> 3 //,[ 2V8 N /c1 Yo y:o ye Js~ 33- 33' 3r 3r 33' SF 3r Valve 824B Position (0-90 ) Yo Y<J </6 fo 4O 3 :,
/
35 53 3i 3r 33 Page 6 of 6
i ? W- - pj T D..' ..
//- M 4
WM , .., ., . ,.
~ ,COMPONEN* C0 CLING SYS*IM FLOW TEST MAJOR A -.. Revision 1 l
m , '* f. ;
21-02-89
'7
_kO C_
I d'Db , , _
.t? A M _ _ __ _~.
3 1.0 PURPOSE e
To demonstrate that the performance of the compenent cooling water system has not degraded significantly since the initial functional test. Specific items covered are:
1.1 Flow balance 1
1.2 Pump performance 1.3 Tnrottle valve posi-ion
2.0 REFERENCES
2.1 Component Cooling System Description Tru310.9.
3 0.2 Final Fac:.lity Description and Safety Analysis Report, Vclume 2, Chapter 9.
2.2 Westinghouse Flow Diagram 110E018 Shee: 1
- Westinghouse Flow Diagram 110E018 Shee
- 2 4
Westinghouse Flow D:.agram 110E01E Shee: 3 2.4 Component Cooling System Functional Tests.
e
, WM ? H-2.3, Rev:.sion 1. January 8, 1971 WP"."? H-2. 3, Rev:.sion 2, June 25, 1970
- WM ? H-2.2A, Supplemen " A'", Ma rch 10, 1971 1,
0.5 Operating Procedure OP-6A, Operation cf Component Cool:::g System.
2 2.0 ::SCUSS:0N This tes will try to verify normal operating flows cf the component cool:.ng water sys em. If the flow appears to be incorrect, valves 824A and S243 vill be manipulated te try to establish the correct flow.
1 4.0 PRECAU* IONS AND LIM:TATIONS All precautions in operating procedure OP-6A must be observed during this tes*.
5.0 INIT:AL CONDITIONS Initials Date i
5.1 The component cooling water system is aligned A for normal plant, operation. /y) /;-f ff 5.2 The RHR heat exchangers are not receiving CCW .A s ,f flow. /$ $ -f -//
Page 1 of 6
W"? 12.11
, . a 25,,eoNgg- COOLING SYS m F*.0W ~EST MAJOR
. Revision 1
- 3. 11-02-89 E, .'
k . . -. ... ..
@ Initials Date 7
~
5.3 CCW pump P11A is operating. CCW pump PllB is secured. b M # /9 5.4 The followine ecuiement is not recuired for coeration.
5.4.1 Beric acid evaporator
- 5.4.2 Excess letdown heat exchanger 5.4.3 Waste evaporator (Uni 1 test only) r- -
5.4.4 Blowdown evaporator bottoms cooler (Un:.: 2 test only) 5.4.5 Ur.i: 2 le down gas stripper sys.em (Unit 2 tes: only) 3 /2lTf 5.5 Install temcorarv :.nstruments to allow curren:
A . e measurements to be taken for M tn C74 pu=ps. R/ ~9
-Gre un;. : ; le:cown flow :.s amou*. 40 gpm (Unit 2 ^
test only), h /d -T *If 5.7 The non-regenerat:.ve hea: exchanger c'd fiev '-
M, / E o m is less than 200 gpm. j $, <
~
c.. e.,0 :. A r :.
A 6.1 Record the data spe::.fied :.n Table 6-1. 8 / ? 'IE8 6.2 Secure component cooling water flow to one of the CCW heat exchangers.
{
C CCW beat exchanger secured. /J -I ff 6.3 Secure t.be follevine svstems if thev are rece:. vine Crd flow:
(
CAUTION: RELIEF VA:.VE 768 MAY LIF"' WHEN SECURING l THE EXCESS LE'"DOWN HEAT EXNOIR. IF IT LIF"*S, SHUT VALVE 766 TO STOP THE ;
DISCHARGE.
l 6.2.1 .f The excess letdow heat ex hanger by I h
I ~
closing valve 769. A /?-T'If S)# J Tc M ec '
85VWE Page 2 cf 6
~
, J .
1 WMT? 12.1; i COMPONENT COOLING SYS T. FLOW TEST MAJOR Revisien 1--- - - - -
- 11-02-89 1
4 i
d Initials Date 6.3.2 (Unit 1 test only). The waste evapora-ter condenser by closing inlet and /
outlet valves 776A and 776B. A/ S M/b g 6.3.3 The boric acid evaporator condenser and distillate cooler by closing inlet valves 744A and 748A and outlet g
\ v;1ve 744B. /y /7 F -9 f
\{ 6.3.4 (Unit 2 test only) The blowdown
(* evaporator bottoms cooler ty securing the bottoms cooler c:rc pump, P136. R g
C # /9
\ . 6.4 (Unit 2 test only) Divert Uni 2 le:down from h
{\-:6 s _. the gas stripper system. & /2 -f -If 6.5 Record data spec fied :.n Table 6-1. A) /'2 -F W j r 6.6 s (Uni 2 test only). Determine the flow to the ;
/ radwaste system by suttracting all measured C:4 !
,h, leads from the total CCW flow. l 9
l Radwaste system flow 3 b/ Y gpm. /A-87f .
1 6.7 Establish flow to "A" RHR heat exchanger I by opening valve 73SA. /d - f "N j 6.5 Record the data spec:.f:.ed :n Table 6-1. b M 'I O 1 6.9 Determine flow to RHR heat exchanger by subtracting the total flow of the c:her users
(:nclut.ng radvaste system) from the indicated flow at FT619. Record this number in Table 6-1
"*fer the Heading 6.8 or 6.14 as appropriate.
N [24 ' N C.AUTION: THE FOLLOWING STEP MAY CAUSE UNDESIRABI.E E,0W CHANGES IN 0"HER CC"d FLOW PATHS. ':'rE VALVE MANIPUI.ATION SHOULD BE DONE SLOWLY TO ALLOW THE OPERATOR TIME TO EVALUATE THE EFFECTS ON OTHER SYSTEMS.
6.10 If the RHR heat exchanger flow is not equal to or a little more than the design value (2780 gpm),
ther. adjust Valve 824A (824B) to obtain the /
desired flow. M// /',-f si s .
g Page 3 of 6
_ _- _ -m_ .._. _ _ . _ . . _ . _ _ _ _ _ _ _ . _ _ ._ - . _ . _ _ _ _ _ . _ _
I WM"'? 12.1; !
COMPONENT COOLING SYS~EM F*OW *EST MAJOR
- --Rev.s ten i 11-02-89 Initials Date .
6.11 Record the data specified in Table 6-1. /i/[4 C f fi 6.12 Isolate "A" RHR heat exchanger bv ~ closing g Valve 738A. /W /1 'I N }
6.13 Supply CCW flow to "B" RHR heat exchanger by g opening Valve 738B. & /2 -f ff 6.14 Repeat Steps 6.8, 6.9 and 6.10. d /244f 6.15 Record the data specified in Table 6-1. d// /J V U i 6.16 Secure component cooling pump Pila and allow component coeling pump PilS to start. Restart P11A if P.3. does net start er .f d.:.schar e ' A -
check valve stteks open. /J /J -8 8'2 I 6.17 Record the data spe::.f:.ed in Table 6-1. d /T -6 fi 6.15 :sclate "B" F.S heat ex:nanger by :*.esing g ,
Valve 7385. ;G ,d . f- F 7 6.19 Record the data spe: fied in Tanle 6-1. b M'l O ,
I i
6.20 Supply CCW flow to "A" FRR heat exchanger by cpening Valve 736A. h /? . P . F9 6.21 Record the data specified in Tahle 6-1. /2 'I"8f 6.22 Start component cooling water pump Pila and g leave both CCW pumps cperating. du /.~ -8 aEi CA""': ON : MINIM :*E ~HE T:MI "'#.AT "'WC C:~4 ?UM?S AFI SUPPLTING ONE CCW :~.~: AT EX7. ANGER.
6.22 Vent and establish flow to the comocnent cooling .
/2' water heat exchanger secured in 5tep 6.2.
I 6.24 Reestablish flow to "B" RHR heat exchanger bv~ g opening Valve 738B. L) [2 'I ~ @
6.25 De not change any throttle valve positions and l t
record the data specified in Table 6-1. b /d -fN 6.26 Isolate flow to both RER heat exchangers bv l
/3 f N
~
I . closing Valves 738B and 738A. ,
1 '
g Page 4 cf 6
= Y. . ,.. .....
, COOLING SYSTEM FtOW TEST MAJOR Revisten 1 11 02 39
. - . . . . ~. . -- - - - - - - - - - - - - - ~ - - - - - - - - -
\
Initials Date 6.27 Secure component cocling water pu=p Pila. /h / chi-d'i 1
6.28 Reestablish flow to any of the following systems that ure desired for normal eperatien.
6.28.1 The excess le down heat exchanger by opening Valves 766 (if shut in p Step 6.3) and 769. f]h. /2 ~#~ d'f 1 1
1 6.2S.2 (Uni: 1 tes only) The waste evaporator tendenser by opening inle and cutle 4ff Valves 776A and 776S. /ed /d -f i/7 6.2S.3 The bcr : a:id evapora:Or :endenser and distilla:e cooler by openin: nle: and
. ,, a. ..s . ..., s , ,. ,. e,
. s ,.ca
. . L 3.. , ,. ,. . .
/ 9=~ . f. fL, i 6.25.4 (Un:: 2 tes: cnly) The blewdown evacerat:r bc : ms 'ar bv s ar:;ng
- ne'be:::=s :: ler ::r: pump. F136. ^! /I I' /2- I 27
, 6.29 (Un;: 2 tes: only) Rees ab1:sh Un;; 2 le:dewn flew :: :ne gas str:pper syste: if des: red. 46/ / /4 -r #f
~= * *;-
i.2: Re:Ord the data spe- # " --
/) /2187
.1 A::e :ance Cr; e.-ia Ve-ify tha* flow ea:n RHR heat exchanger is at least 2780 gpm unter ac:::en ::nni ::ns.
- .2 Review Criteria l l
7.2.1 Review flow data := assure all flows seem consistent w;th l the system lineups.
i 7.2.2 Evaluate pump head curves and pump current to show that tne i pump is :perating as expe::ed.
7.2.3 Verify that flow to anv RER heat exchanger is not likelv. to 1
l ex:eed 1.5 times the design flow, or about 1100 gpm, during a :: dent er any other tend::: ens.
s :.
Page 5 cf 6 t
r i .
WilTP 12. .
Collis..cNT C001.ING SYSTEll IJI.nW TEST HAJOH Hevision I !
i1-02-89 TAlli.E 6- 1 i CollP0llEllT C001.ING DATA ,
l DESCRIPTION STEP HUlHIER 6.I _6.5 6.8 6.I1 6.14 6.15 6.17 6.19 6.21 6.25 6.30 ;
Boric Acid & Dist. Cooler Flow F1-642 (' O O _Al[A_ O A'/J O O O O O Tolal RCP Flow Fl613 .235 .1.a f X'1 /58 /f1 .2 A'l
_t@ (/( A f//_ jd .23 o l F1609 22 3 } a y_ /73 tu/A 3Xf /64 JA]
/7f _f!f)_ /77 /7/ I Hilli Pump Flow FI640 J L (- JM /1.2 #[J /1,i _Nb / 9.6 .1 ~7. L. If,5 /t). O 2 7. /-
Waste Gas Compressor KIA Flow gp j{/[j gjj/ y g[J j A/fA (lin i t I only) FI643 i
(inIt IoIiShF645 #[3 M!I / f!/ /$/ d'! _
- V #/ W! N! W A ,
Excess i.ettlown llXE Flow F1607 '/1 O O rJ/4 ri M/J O O O g /f,a 1
Waste Evap. Colul. Flow F1647 (lin i t I otily) g gg g gp g/j ,gfjj/ Q jg/f jfjg/
Seal Water lleat Exclianger Flow F1605 h '/ f j/_ Vf 4 97 /3f 'If 77 /3f ;
Non-Hegenerative lleat Exclianger FI601 Jo ro j{
11 O fo _//f/_ /0 /o /o /g ja Containment Spray Pump IlXE F1649 il ~l l d.). 5 /M J '/ _AlA_ clf/ 33 ){/ ,2 $/ JJ./
Safety Injection Pump flXE FI650 _ff_
TV _ 3/,5 N/d 3d _A/k 3) '/'/ J1 .71 JM !
~
Sample Ileat Exchanger FI603 '/.! ')) ef _ft/j_ ( 5- f(/(( (,4 9/. F 4if /fA 'JJ Total CCW Flow FT619 (from PPCS) IDA //46 Jr/o .377f '
N/[ JPW _/V(( //46 34'(o 73 ;10 13ff6 Residual lleat Exchanger Flow
_Nk [/L J.92L'l Mh_ Jfg /t/k 39J01 A//A 3eo2.f (,374,6 jj CCW Pump Discliarge Pressus e PSIG(fI e n} / I'l /Vo 1t/_ Jj 'j ') j(/k _/p/_ jr/L /so /0 (, /VO CCW Pump suction Temperattne T1616 / 3 10/_ 9J _A!p _ 'J4 /\///_ ft, 97
/d3 95 /0V crW Pump Current /J5'"rs /F5 270 /90 A70 g If6 A//[ _44,g A/!/ 270 Valve 024A rosit ion (0-90") W" Vv ' Vo ' /// Vv' A/ / M?' yo jv ' V0 " Vd '
valve n240 Position (0-90") V" ' V#* # gj_ /# Alf[/ W '/O ' V0 ' f/ /0 ' I
't 8k I $I I
._ .= . - - -
Pump Reference
- PRESSURE TEST ** Values and Limits Pump #: IP11A IT-012 Date Established: 6/10/93 Entered By: 1eh Reference Values
- Reference Pressure: 103.40 psig Flow: 2602.00 gpm Reference Vibration Motor End Pump End Point C: .166 ips Point A: .143 ips Point D: .116 ips Point B: .146 ips Point E: .301 ips Acceptable Range Pressure: 96.16 psig to 105.47 psig Vibration Motor End Pump End Point C: s .325 ips Point A: s .325 ips Point D: s .290 ips Point B: s .325 ips Point E: s .325 ips Alert Rango Low Pressure: 93.06 psig to 96.16 psig High Pressure: 105.47 psig to 106.50 psig j Vibration Motor End Pump End Point C: .325 ips to .700 ips Point A:
Point D: .325 ips to .700 ips
.290 ips to .696 ips Point B:
Point E: .325 ips to .700 ips
.325 ips to .700 ips Required Action Range Low Pressure: 93.06 psig High Pressure: 106.50 psig Vibration Motor End Pump End Point C: > .700 ips Point A: >
Point D: > .700 ips
.696 ips Point B: > .700 ips Point E: > .700 ips Comment: Reference values changed as a result of 06/10/93 evaluation.
TEST DATA FOR ONE PUMP 12/C2/96 Page 1 Pump: IP11A Test: 012 Pressure Test Vibrations (Aps!
Vert Herz Vert Horz Test Date Diff P Inbd 2nbd Axial Outbd Outbd Int Remarks 6/13/91 101 .130 .090 .300 200 .130 BAT ROUTINE SURVEILLANCE e/22/91 103 .160 .130 .150 1.050 .320 LEH POST MAINTAINANCE OP 9/15/91 100 .150 .130 .330 .150 .150 BAT ROUTINE SURVEILLANCE 12/16/91 102 .210 .140 .360 .250 140 LEH ROUTINE SURVEILLANCE 3/02/92 101 .260 .140 .310 .250 .130 BAT ROUTINE SURVEILLANCE
{ 6/09/92 100 .190 .170 .300 .270 .260 JH ROUTINE SURVEILLANCE 6/09/92 100 .190 .170 .300 .270 .160 JH ROUTINE SURVEILLANCE 6/09/92 100 .190 .270 .300 .170 .260 JH ROUTINE SURVEILLANCE
( 7/31/92 102 .310 .340 .370 .160 .150 JH MWR 923363 9/01/92 101 .157 .132 .342 .173 .150 9/01/92 101 .160 .330 .340 .270 .150 LEM ROUTINE SURVEILLANCE 10/15/92 102 .233 .144 .321 .227 .137 10/15/92 102 .230 .340 .320 .230 ,140 RAT INCREASED FREQUENCY 12/Ca/92 100 .207 .154 .308 146 .156 12/01/92 ICC .210 .350 .310 .250 .160 1.EH ROUTINE SURVEILLANCE 3/01/93 103 .183 .127 .199 .141 .311 3/23/93 116 .267 .115 .310 .185 ,144 6/10/93 103 .266 .116 .301 .143 146 g/ 7/12/93 103 .218 .270 .363 140 .145
, 9/01/93 103 .193 .134 .333 .155 154 A
12/23/93 103 .195 139 .320 .381 .127 2/28/94 103 .196 .345 .367 159 .156 6/01/94 103 .144 121 .366 .352 154 9/02/94 103 .155 .124 .363 12e .133 LEN ROUTINE SURVEILLANCE 12/09/94 103 .241 .118 .309 .139 190 BAT ROUTINE SURVEILLANCE 2/17/95 103 .20C .114 .298 .199 120 LEN ROWINE SURVEII. LANCE 3/02/95 103 .242 .085 .364 .347
.109 LEN ROUTINE SURVEILLAN:t 6/01/95 104 .330 .126 345 1 91
- 11. IJ.D ROUTINE SURVEILLANCE 7/16/95- 104 366 .342 .300 264 113 LRD SPECIAL TEST. a 9507 9/01/95 104 .150 097 .273 .299 i 113 BAT ROUTINE SURVE!LLANCE !
12/05/95 104 .213 156 .276 .212 !
.224 BAT ROUTINE SURVEILLANCE 3/01/96 105 .? 80 107 .346 .211
.127 LEH ROUTINE SURVEILLANCE 3/26/96 104 .220 342 .296 .186
.129 LEH INCREASED FREC. IP11 6/01/96 104 .241 252 .371 .284
.263 LRD ROUTINE SURVEILLANCE '
9/03/96 104 .252 .146 .125 .199
. 315 ZEN ROUTINE SURVEILLANCE 11/29/96 104 .281 .133 .357 .187
.118 LEH ROUTINE SURVEILLANCE l
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Pump Reference
- PRESSURE TEST ** Values and Limits Pump #: 1P11B Date Established: 6/10/93 i IT-012 Entered By: LEH '
Reference Values
' Reference Pressure: 107.20 psig Flow: 2583.00 gpm i
j Reference Vibration Motor End Pump End Point C: .142 ips Point A: .143 ips Point D: .149 ips' Point B: .114 ips Point.E: .251 ips Acceptable Range i
! Pressure: 99.70 psig to 109.34 psig Vibration Motor End Pump End !
Point C: s .325 ips Point A: s 325 ips '
Point D: s .325 ips Point B: s .285 ips Point E: s .325 ips Alert Range
. Low Pressure: 96.48 psig to 99.70 psig High Pressure: 109.34 psig to l 110.42 psig ;
Vibration Motor End Pump End '
Point C: .325 ips to .700 ips Point A:
Point D: .325 ips to .700 ips
.325 ips to .700 ips Point B: .285 ips to Point E: .325 ips to .684 ips i
.700 ips Required Action Range :
Low Pressure: 96.48 psig High Pressure: l
,110.42 psig Vibration Motor End Pump End Point C: > .700 ips Point A: >
Point D: > .700 ips
.700 ips Point B: > .684 ips Point E: > .700 ips '
Comment:
Reference 925782, values established due to post maintenance MWR 921603, 932609. -
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TEST DATA FOR ONE PUMP 12/C2/96 Page 1 Pump IP11B Test: 012 Pressure Test Vibrations ( Aps)
Vert Horz Vert Horz Test Cate Diff P Inbd Inbd Axlal Outbd Outbd Int Rema ras 6/13/91 106 .110 .100 .270 .130 .110 BAT ROUTINE SURVEILLANCE 1/23/91 107 .130 .110 .260 .150 .120 BAT POST MAINT. AFTER CI l 9/15/91 105 .240 .110 .200 .150 .130 EAT ROUTINE SURVEILLANCE 12/16/91 107 .140 .120 .130 .150 120 LEH ROUTINE SURVEILLANCE 1/06/92 106 .070 .100 .250 .150 .110 LEH INCREASED FREQUENCY 1/16/92 107 .000 .090 .250 .130 .110 LEH POST MAINTENANCE IP1 3/03/92 106 .120 .100 .210 .150 .100 BAT ROtTTINE SURVEILLANCE 6/09/92 106 .130 .200 .250 .130 .130 JH ROUTINE SURVEILLANCE 6/09/92 106 130 .200 .25C .130 .130 JH ROUTINE SURVEII. LANCE 6/09/92 106 .13C .200 .250 .130 .130 JH ROUTINE SURVEILLANCE 9/c2/92 107 .342 .226 .276 .144 .160 9/C2/92 107 .140 .230 .280 .140 .160 LEH ROUTINE SURVEILLANCE 10/15/92 105 .208 .314 .234 123 .236 10/15/92 105 .21C 31C .230 ,12C
.24C BAT INOREASEO TRICUENCY 12/01/92 106 .140 ,265 .278 132 .202 12/C1/92 106 140 .270 .280 13C .20C LEM ROUTINE SURVEILLANCE 1/15/93 107 .146 .260 .128 .191 .304 3/C2/93 107 .165 .247 .127 164 .266 3/05/93 107 .204 .261 .167 .138 269 3/23/93 107 .149 .266 .235 .130 16; 5/31/93 107 .146 217 .252 128 .14C 6/10/93 107 .142 .349 .251 143 .14 9/01/93 107 131 .2C2 .252 133 14C 12/23'93 1C7 .123 .218 .225 133 141 12/30/93 1C1 .013 .184 245 .330 122 3/01/94 107 ,119 .197 .28C 135 12C 6/01/94 ,
1C5 123 264 .242 137 .168 6/03/94 1C5 .125 .270 247 .145 2C3 i' 9/C2/94 106 .109 150 .230 .134 I 144 LEN ROUTINE SURVEILLANCE '
12/09/94 106 .304 ,285 .220 129 191 BAT ROUTINE SURVEILLAN2E 3/C3/95 106 .116 .305 .255 130 .346 LEN ROUTINE SURVEILLANCE
- 6/01/95 107 .202 .249 256 .346 .195 LRC ROUTINE SURVEILLANCE 9/01/95 107 .347 .243 .230 .134 I
.265 BAT ROUTINE SURVEILIANCE 12/05/95 107 .124 .224 .227 128 .10C BAT ROUT!NE SURVEILLANCE 3/01/96 107 .136 .271 .265 .125 i
.349 LEN ROUTINE SURVEILLANCE 1 3/26/96 LEN INORIASEO FREQ. IP11 6/01/96 107 .313 .289 .278 .117 .203 LRD ROUTINE SURVE!LLANCE 9/03/96 105 .180 .259 .106 .267 .383 LEN ROUTINE SURVEILLANCE 11/29/96 107 .141 .252 .229 .343 .147 LEH ROIT!!NE SURVEILLANCE I
I l <
l Pump Reference
- PRESSURE TEST ** Values and Limits 3/16/96 Pump #: 2P11A Date Established:
! IT-013 Entered By: LEH Reference Values i
Reference Pressure: 105.80 psig Flow: 2628.00 gpm 1
! Reference Vibration Motor End Pump End Point C: .102 ips Point A: .100 ips t Point D: .065 ips Point B: .105 ips '
Point E: .190 ips Acceptable Range Pressure: 98.40 psig to 107.90 psig Vibration Motor End Pump End Point C: s .254 ips Point A: s .250 ips Point D: s .164 ips Point B: s .262 ips Point E: s .325 ips Alert Range Low Pressure: 95.20 psig to 98.40 psig I 3 High Pressure: 107.90 psig to 109.00 psig !
Vibration Motor End l Pump End Point C: .254 ips to .610 ips Point A: .250 ips tt .599 ips Point D: .164 ips to .392 ips Point B: .262 ips to .629 ips Point E: .325 ips to .700 ips Required Action Range Low Pressure: 95.20 psig High Pressure: 109.00 psig Vibration Motor End Pump End Point C: > .610 ips Point A: >
Point D: > .599 ips
.392 ips Point B: > .629 ips Point E: > .700 ips Comment:
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l TEST OATA TOR CNC PUMF 12/12/96 Fage .
Pump: 2 P11 A 7 Test: 013 Fressure Tes:
Vibrat;ons taps! ,
r Vert Horz Vert Herz Test Date C2 f f P 2 nbd Indd Axia; Dutbd Outbd 2n Rema rks TESTING *PUMFPRNT*
.800 ROUTINE SURVEILLANCE 6/15/91 2C7 240 120 .;?C .08C ,160 LEH INITIAL RDUTINE SURV 9/25/9; 103 .130 .100 380 .110 08C BAT ROUTINE SURVEILLANCE
~2/15/9; 205 .;2C .110 220 .34C .D9C LEH ROUTINE SURVEILLANCE 3/04/92 102 34C .090 240 .12C
.08C BAT ROUTINE SURVEILL;ECE 6/03/92 101 j
.13C .130 .240 .120 .09C JH - ROUTINE SURVEILLANCE !
f/C1/91 1C1 .330 .130 .24C 120 ,090 JH ROUTIFE SURVEILLANJE '
9/C2/92 1 04 .158 .13; .230 .145 .12f t 9/02/92 204 <16C 130 J23 c t
- 4c ' ,;30 ;gH ROUTINE SURVEILLANCE i 9/C3#92 103 34C .34C 23C .24C .21: LEH C:L CHANGE 11/3C/92 104 34C .25C .25C 12C .cet LEN ROUTING SgRVE:LLANcg 3/12'93 103 156
.103 .114 .081 .226 I
6 ';; '93 105 4e :04 .23, ,;- .;;9 i i
9/0* '93 1C5 ;2C 104 2:9 109 .c93 '
12/23/93 :CE 127 .;7 .26; .26 09:
I 3 / C2 / 94 105 '09 083 .21; ;C; e9; i ':3 '94 .0! .. 094 .243 ::s Oft t 9/C6/64 105 349 .108 ;52 ;15 C l LIA ROUT;NE SunVE LLAN E '
12/C9/94 101 .14 091 .295 Ice C6: EA! R;gT:Ng Sgavg Aseg ,_ I 3/04 95 .;' .C31 C42 .204 ..;
. cit ;Er A;;;;Ng 3;gyg;;;gN;g f/01/95 Itf .19 _C9: ;c3 c97 {
ggg ;g; 3;77;gg gggyg;;;4g7g - I 9 #02 /95 2 04 .37 .3C .205 ;C; 0'( EA? ROUT NI SURVg:LLAN;E 12 '04,'95 ; 05 ;24 .cg4 .23; 1;4 * ,
. 7; BAT R 77;NI SURVE*L ANet !
2/34/96 1C7 ;2: .093 242 it! 09f LEp R07;;Ng simg7;;;Ag;g
' U 2 # 9 f 10( .li .C93 16; 101
, 09:. LR: Rgg7 gr S;pyg.;;AN;g 4 /29 e bi ICE ;44 120 ;99 ;ft C93 LEh ROUT;NE SgpVE:LLAN;g 12!11/94 105 156 169 ;77 ;23 :sf LEp Reg;;Ng Sgpyg;;;AN;g l
. , - . m- . . - - m,. ., ,
e Pump Reference l
l
- PRESSURE TEST ** Values and Limits Pump #: 2P11B Date Established: 8/29/96 IT-013 Entered By: LEH Reference Values Reference Pressure: 104.00 psig Flow: 2600.00 gpm l Reference Vibration Motor End Pump End i
' Point C. .173 ips Point A: .168 ips Point D: .217 ips Point B: .152 ips Point E: .174 ips Acceptable Range Pressure: 96.70 psig to 106.10 psig Vibration Motor End Pump End Point C: s .325 ips Point A: s .325 ips Point D: s .325~ips Point B: s .325 ips Point E: s .325 ips Alert Range g- Low Pressure: 93.60 psig to 96.70 psig q High Pressure: 106.10 psig to 107.10 psig Vibration Motor End Pump End Point C: .325 ips to .700 ips Point A:
Point D: .325 ips to .700 ips
.325 ips to .700 ips Point B: .325 ips to Point E: .325 ips to .700 ips
.700 ips Required Action Range Low Pressure: 93.60 psig High Pressure: 107.10 psig Vibration Motor End Pump End Point C: > .700 ips Point A: > .700 ips Point D: > .700 ips Point B: > .700 ips Point E: > .700 ips Comment: New reference value for DP provided as result of PPE evaluation for 08/29/96. Vibration data retained from 02/14/96 data.
. . - . . _ . _ _ - _ . . . . _ _.. _ _._ ..m _. .-._ _ _____ _ -. . _ . _ . _ . . _ . . m . . . .____ ..~
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- l. TEET DATA FOR ONE PUMP 12/12/96 Page i i
Pump: 2P11E Test C;3 Pressure Tes:
Vibrations lapsi Vert Horz Vert Herz Tes: Date Daff P Inbd Inbd Ax2a! Dutbd Outed 2n: E ema rks 6/14/91 it? 19C .16C ;7C .15C 4
l 180 LEN INITIAL ROUTINE SURV i 9/15/91 103 .190 350 31C .170 130 BAT ROUTINE FURVEILLANCE 9/25/91 106 .200 .170 .290 .21C 150 BAT INOREASED FREQUENCY 12/15/91 102 .210 .160 .20C .28C .160 LEH ROUTINE SURVE LLANCE 3/05/92 1 04 170 .140 ,250 .160 14C LEN ROUTINE SURVEILLANCE 6/01/92 101 ,17C .130 .290 .170 .150 JH ROUTINE SURVEILLANCE '
6/01/92 101 .170 130 .29C .170 .250 JH ROUTINE 3URVEILLANCE 9/C2/92 102 .178 .135 .262 .382 .134 9/C2/92 102 .180 .13C .260 180 .130 LEN ROUTINE SURVEILLANCE 9/04/91 103 .187 .173- 287 .156 .145 9/04/92 103 190 . lit 290 16C 25: LEN ROUTINE SURVE!LLANCE 11/30/9; 2C2 .180 280 .280 ;7C 150 LEH ROUTINE SURVEILLANCE 3/C3/93 104 194 .237 329 275 ;6; 3rC3'93 104 294 .23' 329 275 ,le; 4/14/93 104 .192 13f 334 ;71 143 6/11/93 104 .224 .227 .282 19: 16 1/09/93 103 .197 .360 28C .206 229 9/C;/93 104 .304 .205 .274 ISC ;E' 12/C3/93 103 .264 .173 261 15' ;7f
)
3/c2/94 l03 .201 .351 .279 153 14; l f/C3/94 C4 .200 .356 263 159 ;6-l 9/06/94 .04 .210 256 156 ;tt .;r LEW ROUTNE SUNVE!LLANOE l 12/09/94 1C5 176 339 ;39 ;36 ;'t SAT ROUT!NE SURVE*LLANCE 1
1 6/C;/95 205 ITC 244 .26C ;56 .;! LA: SOUT!NE SURVE!LLANCE 9/C2/95 1C5 166 .244 266 ;7:
355 BAT EOUT:NE SURVEILLANCE 10/04/95 105 .226 .316 22C ;34 ;29 BAT EOUTINE SURVE*LLANCE 2/ 4/96 ;02 173 .2;7 ;74 ;66 15; LZh AOUTINE SURVE;LLANCE 6/c2/96 ICI .255 .233 .C95 12C 15e LA: AOUT!NE SURVEILLANOE 6/29/96 104 .171 15; .34' 13; 449 LEF ROUTINE SURVE LLANCE 12/1;/96 104 .205 17: ;31 161 ;5: LE's RDUTINE SURVE* LLANO!
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00.b, di-so rril 1013 n16Luftsth ti.cVir.1L hrDU rnA itV. 414ccidVlu r.11 NUCLEAR POWER BUSINT.,55 UNIT CALCULATION REVIEW AND APPROVAL
'd"****#qs-op.ey g N"mW of Pages ;
7 + ( Ah + ry Title of Calculation: .
vnte. 4s A scacs> Aid u.% 1ms4r-ameA+!'am vred t n' *rT-t1 t tT- 5 hv- C C.Q && ftS p Onginal Calculation @ QA-Scope O Revised Calculatina. Revision #
D Superseding Calculation. Supersedes Calculation #
Modification #
Description:
Other
References:
Prepared By: Date:
Ifl. 3 f4(o This Caleujation has been Wewed in accordance with NP 7.2.4. The review was accomplished by oce or a combinaden of the following (as che:ked):
A review of a representative cample of repetitive A detailed review of the original calculation.
ca1cuo .
A review of the calculation against a similar A review by an alternate, siznplified, or calculation previous 1y performed. approxunate method of calculation.
Comments:
1 Reviewed Bv: . Date: Approved By: Date: ]
i1/ulet IAlo1)9o l i
I PDF.1608 !
l Revision 1 02/27/95 Rcranos (s) NP 7.2.4
DEC-2i-96FR114:19 WISCONSih blECikiC NPBU rAA NO. 414aidulu r. t o TITLE: Uncertainty Associated with CALCULATION # . 96 02A4 Mstrumentation Used in Pre,aared By: EJM 17-12 & IT 13 for CCW Pumps cated 2f131$6 Page Iof8 A. Purpose The purpose of thic calculation is to determine the uncertainty associated with the instrumentation used in inservice test procedures IT-12 &,13. for l the component cooling water pumps, (reference 2). The final uncertainty l value must include a combination of the uncertainties (by a square root '
sum of the squares [SRSS) method) for all the instrumentation used in the test that will have an impact on the ability to measure the IST acceptance value during the test performance for comparison to the design basis acceptance value.
B. Method Instrument uncertainties will be calculated for the instruments used in the component cooling water (CCW) pump Inservice Test procedures IT-12 and IT 13, (reference 2). These inservice tests determine the developed head across the CCW pumps (1&2P 11 A&B) by adjusting the pump flow to approximately 2600 gpm within approximately 30 gom by throttling valves 1CC-824A and 1CC 748A. Once the correct flow value is achieved, the suction pressure instrument is valved in and the suction and discharge pressures are measured and the total developed head across the pump is determined. This value is compared to the CCW pump acceptance criteria.
A change to the IST test will be made to open up these throttle valves further to establish a flowrate that is greater than the design basis required CCW flow, plus instrument uncertainties. Based on this calculation, and reference 1, this value is expected to fall between 3400 gpm and 4000 j gpm. This calculation is supporting this additional flow criteria that is being !
added to the IST test. These uncertainties do not apply to the portion of the IST test that is only verifying that ASME Section XI criteria are being l satisfied.
While the IST procedures recommend using the computer point for total CCW flow (FT619), this calculation evaluated the control room indication.
F1-619. Due to the readability error of FI 619, the overall loop error should exceed that of the computer point (FT619), and thus this calculation would be conservative.
This calculation is written referencing Unit 1 train A instrumentation. The results are also applicable to Unit 1 B train, and Unit 2 trains A and B.
C. References
- 1. Component Cooling Water Pump operability determination, 10/3/1996.
- 2. PBNP inservice Test, IT 12 and IT-13, Component Cooling Water Pumps and Valves"; Unit 1, Hevision 11, August 29,1996; and Unit 2, Revision 12, August 29,1996.
- 3. Foxboro Component Instruction Manual for E13DM Series Differential Pressure Transmitter, Section 10, June 1979.
I UcV-fidoTr,1 1010 wioVVholit CL:'.uir.4v itrou rnA itu. ,awccicviv r. .c l TITLE: Uncertainty Ass ciated with CALCULATION d : 96 o284 Instrumentation Used in Prepared oy: EJM IT 12 & IT-13 for CCW Pumps Dated 2I23196 l Page 2 of 8
- 5. PBNP instrumentation and Control Procedures, ICP-06.15, " Auxiliary Coolant System (Non-Outage)", Rev 19, August 20,1996.
- 6. PBNP Instrumentation and Control Procedures, llCP-06.068, " Component Cooling Water Flow Calibration", Rev 1, October 24,1995. ;
- 7. DG 101 " Instrument Setpoint Methodology", Revision 1, September 12.
1995.
- 8. Perma-Cal direct drive test and process gauge, component manual, dated 2/94.
- 9. VECTRA Calc No. PBNP-IC-07, " Westinghouse 252 Indicator Drift Calculation", Rev O, 6/9/1995
- 10. Duke Engineering & Services letter to WE, "Si Pump IST Flow Test Uncertainty Evaluation", September 25,1996.
- 11. WE Calculation 96 0191, " Minimum Allowable IST Acceptance Criteria for l Si Pump Performance", dated 9/25/1996. l
- 12. Process Measurement and Analysis, instrument Engineers' Handbook, Third l Edition, Chilton Book Company. i
- 13. Flowmeters, a basic guide and sourcebook for users, Alan T.J. Hayward, l John Wiley & Sons,19/9.
14 Ingersoll-Rand Component Instruction Manual #76, Component Cooling l Water Pumps, rev 12, dated 10/15/96. j 1
8 D. Assumptions )
/ 1. The temperature effect on the instrumentation will be assumed to be negligible as the transmitters are calibrated and used in ecsontially the same temperature environment.
/2. The CCW pump flowrate used in the IST test will be changed to a value that ensures the IST decign basis criteria, plus instrument uncertainties, is satisfied. This value is expecteo to be between 3400 gpm and 4000 gpm.
The method to convert an error from psi to gpm, as accepted by Duke Engineering (reference 1m, requires determining the slope of the pump curve at the point of interest. The pump curve for the CCW pump (from reference 14) is attached. As can be seen from the curve, the slope of the pump curve is more negative at higher flowrates, and using the slope at the lower end of this band, 3400 gpm, will ensure a maximum gallon per minute change for a given head change in addition, when using the transfer function for calculating the error of a square root converter, (see Eq.1.) the lower the representative flowrate, the greater the resulting error.
For this case a flowrate of 3400 gpm will also be used. This calculation will be accurate for all CCW IST test revisions in which the pump flowrate that is used to satisfy the design basis requirement is greater than 3400 gpm. This calculatiun does not apply to the IST criteria that ensures that ASME Section XI criteria are satisfied, and that CCW test criteria could be done at any flowrate desired by the IST engineer and system erigineer.
/3. The pressure indicators,1&2 PI-692 A&B and 1&2 PI 617 A&B were verified to be at the same elevation,64~ above the 8' elevation of the PAB,
i)t.C ci-96 Fill 14:19 W1500hSih tt.tuiniu krou rra tw. wiccicuiu r cu l
l TITLE Uncittrinty AssicictId with uALuVLAlluN # : 96 o284
! Instrumentation Used in Prepared By: EJM i 17-12 & IT 13 for CCW Pumps Date:12123/96 !
Page 3 of R l
and there is no need to consider the effects of elevation differences between the instruments and pipe centerlines i
l
/4. The velocity head developed by the pump is ignored.
l
/ 5. The delta pressure measurement for Fl 619 is taken off a 90 degree elbow ;
in the pipe. It is assumed that this device has an inaccuracy of 10%
l based on references 12 & 13, which both state an accuracy of between !
2 5.0% and 210% for this type of flow measuring device.
/6. If manuf acturer's data was not located, uncertainties associated with drif t of an instrument have been assumed to be the smaller of either 0.5% of full scale, or the instrument calibration tolerance. This value (0.5%) is based on engineering judgment of the maximum expected drift between calibrations for the instrumentation involved. Alternatively, the calibration accuracy is used if smaller, because instrumentation found regularly out of !
calibration are typically either repaired or replaced. l
/. 7 The M&TE error is assumed to be the smaller of either 0.5% of the instrument range, or the calibration tulerance, for all IST instruments. This value (0.5%) is conservative based on the research performed for l Calculation 96-0191, " Minimum Allowable IST Acceptance Criteria for Si Pump Performance" (reference 11). The calibration accuracy is used if smaller because it is the practice of l&C to use a calibration instrument which is at least as accurate as the instrument being calibrated.
E. Inputs for this calculation, the total uncertainty associated with the instrumentation used to perform the IST test must be considered. Contributors to this total uncertainty include:
. Instrument (transmitter & indicator) accuracy
- indicator readability
. Tolerance
- Drift F. Instrument Uncertainty Determinations
- 1. Instrumerr ~ 4 certainties for 1 FT-619, HX-12A/B CC HX Outlet Flow Transmitt xboro model N-E13DM, input range 0.0 to 94.33 in H2 0, output range.10.0 to 50.0 mAdc. The calibrated range is 0.0 to 94 in H2 O (reference 6)
- a. Instrument accuracy: z0.5% of range (reference 3)
Accuracy =
20.5 %
- 94.33" =
0.502 % /
19 4.0 " 0.0")
Oh.0-bl-b0 rrd 14:20 WidCOhdih cLtWr,1b hrDU rr1A hv. *19ccicutu r. c 4 TITLE: Uncertainty Associated with CALCULATION e . 9G 0284 Instrumentation Used in Prepared Br EJM IT-12 & 1713 for CCW Pumps Dated 2123196 Page 4 or S
- b. Calibration Setting Tolerance: The calibration setting tolerance is 0.2 mAdc. This represents = 0.5% of the range, or on error of =0.502% v (see a. above) (reference 6)
- c. Drift (transmIIter stability); Assumed to be 0.5% (Assumption 6) /
- d. M&TE (Instrumentation uncertainty due to calibration); M&TE tolerance must be 0.47 in H 20, which represents 0.5% of the calibrated input range ( O.47 in H2O /94 in H 2O) (reference 6) y
- e. Flow Element: This flow measurement is done using a delta P measurement off an elbow flow element. It is assumed that this type of device is about 10% accurate (Assumption 5). This occuracy is assumed to be as a function of the flowrate. Since the flow value for the test is always less than 4000 gpm (Assumption 2), and the calibrated range is 1131.4 gom to 7838.4.0 gom, the assumed accuracy as a function of the cahorated range is:
U,cc,, = = 10 % - 9P"
= = 5.96% /
(7838.4 - 1131.41 gpm Urn . , = (0.00502)' . (0.00502)2 (0.005)' (0.005)' . (0.0596f U,m s = 0.0604 = - 6.04 % /
- 2. Instrument Uncertainties for 1.Fl.619. HC-12A/R CC HX return Finw Indicator, Westinghouse Mcdel 252 indicator.
- a. Indicator readability: This is a log scale. Minor divisions at 200 gom.
Assuming the instrument can be read to 1/2 a division, the readability as a function of calibrated range would represent an error of:
100 gpm g'**"'"_ ,
~ (7838.4 - 1131.41 spm - '
M9% /
- b. Instrument accuracy: e 1.028% (reference 9) /
This error also includes M&TE error and drift, based on telecon on 12/17/1996 with Karen Depodesta, Duke Engineering & Services.
- c. Calibration Tolerance: 2% of 8000 gpm = 160 gpm. (reference 6)
Since the calibrated span is 1131.4 gom to 7838.4 gom:
9P Calibration Tolerance - .0239 a 2. 2.39% /
(7838.4 - 1131.4) gpm
( I)hC 27-96 Fiti 14:20 Scut <5iti ti.tuniv nrou rna itu. *iwccicuiu r.cc TITLE: Uncertfnty Associated with CALCULATION * : 96 0284 Instrumentation Used in Prepared By: EJM 17.12 & 17 13 br CCW Pumps Date:12/23196 l pa ,. s nr x 1
Since the bellows in the indicator effectively acts as the square root converter, it is necessary to tr:et this instrument as a square root converter. All the above errors with the exception of the indicator readability, are treated as input errors.
Input errors:
a = h(Une )# ,- (Ur,si,f l
/
a = d(0.0004)* ,-(0.01028)2 + (0.0239)2 a- 0.0658 - 6.58 % /
Using the transfer function from reference 7 for a scuare root converter:
Eq.1 b =h(a / 28)# -e 2 Where b -Output error from non -linear device a = Input error to non -linear device B = Point of Interest (0 - 100% of span = 0 to 1) e = Device Uncertainty from non -linear device By reviewing Equation 1 it can be seen that the smaller the value of B. the point of interest
- the greater the error. Based on Inas, and assumption #2, a point of interest of 3400 gpm will be used.
R =
Instrument range
= 9" 8000 gpm
=.425 #
Evaluating Ecuation 1.
b = h(.0558 / 2*0.425)# + (0.0149)# #
b = 0.0788 = 7.88% of calibrated span /
b= 7.88% = (7838.4 com 1131.4 gom) = 529 grm /
- 3. Instrument Uncertainties for 1-PI 692A, P-11 A CCW Pump Suction Pressurc Indicator, Perma Cal model #101TTMO3A21, range 0-60 psig.
(reference 5)
- a. Indicator readability: minor divisions at 0.2 psi. Assuming the meter can be read to half a division, the meter can be read to 20.1 psi. This represents 0.1 gpm/60 gpm or 20.17% uncertainty indicator #
readability was determined by plant walkdown by Ed Mercier 12/21/96.
- b. Instrument accuracy,20.25% of full scale, (reference 8) /
OcC-di do rK1 14;dU WidbChdih f.LcVir.1V hrDU rnA i*V. avi5cticv1U r. 40 flTLE: Uncertainty AssocPted with CALCULATION * : 96-0284 Instrumentation t) sed in Prepared Ev: EJM IT-12 A. IT-13 for CCw Pumps onted 2/22/96 r4 9e 6 cf S
- c. Calibration Tolerance The as-left tolerance for the instrument is 21.0 psi. This represents an uncertainty of 1 psi /60 psi, or e 1.67%(reference
- 5) /
- d. Drift: assumed in be +0.5%. (assumption 6) /
- e. M&TE (instrumentation uncertainty due to calibration); assumed to be 0.5%, (assumption 7) v Total Uncertainty associated with PI-692:
U692 =
[(0.0017)2 + (0.0025)* t (0.0167)2 +- (0.005)2 + (0.005)# /
U692 = = 0.0184 = = 1.84% /
U692 = 1.84% + 60 psi = 11.10 psi /~
4 Instrument Uncertainties for 1 PI-617A,1P 11 A CCW Pump Discharge j Pressure Indicator. Acheroft model #1379SS, range 0-200 psig (reference l 5).
- a. Indicator readability: Based on plant walkdown, the smallest division is 2 psi. Ascuming the meter con be read to half a division, the indicator readability would be :1.0 psi, which represents an uncertainty of 1/200 or zO.5% / !
- b. Instrument accuracy, 2 0.5% of full scale, (reference 4) # l
- c. Calibration Tolerance; The as left tolerance for the instrument is :1.0 psi, which represents an uncertainty of = 0.5% (reference 5) v ' I
- d. Drift; assumed to be =0.5%, tassumption 6) -
- e. M&TE (Instrumentation uncertainty due to calibration); assumed to be 0.5%, (assumption 7) y Total uncertainty associated witn PI-617A:
U617 = j(0.005)# +(0.005)# +(0 005)# + (0.005)* -(0.005)# /
U617 = 0.0112 = = 1.12% v U617 = = 1.12% = 200 psi = 2.24 psi -
G. Calculatinn The uncertainties of the inservice test instrumentation have been determined above, and will be combined using a systematic method established in reference 7 and reference 10. This best estimate or realistic l approach combines uncertainties using the statistical square root sum of l squares (SRSS) method. This uncertainty value will be added to the design l basis CCW pump flow requirement and this will become the IST design basis limit, and will be used as an acceptance value for the CCW pumps.
I
- a. Uncertainty associated with F1-619 (see Section F.1 & F.2)
U619 = x 529 gom /
iv.,-21-90 rru 14:21 W16thl45th CLtvnuv hrou rnA iv. w,ccicvAv r. c ,
TITLE Uncerldnty Associ!!;d with CALCULATION * : 96-0284 inrtrumentat'on Used in Precared Sv: EJM 17-12 & IT 13 for CCW Pumps Date:12/22196 Page 7 o!' 8
- b. Uncertainty associated with PI-692A (see Section F.3)
U692 - :: 1.1C psi /
C. Uncertainty associated with PI-617A (see Section F.4)
U617 = = 2.2d psi /
The uncertainties associated with 1-Pi-692A and 1-PI 617A. in psi. must be converted to an equivalent uncertainty in gpm in order to combine the pressure uncertainty with the uncertainty associated with the flow instrument. Therefore, the pump curve at the test point (3400 gpm) was used to approximate an associated change in gallons per minute due to an uncertainty in psi. Selecting this point to take the slope maximizes the error contribution of the pressure indicators. (assumption 2) A tangential line to the pump curve was drawn at the testing point from which a slope (ft/gpm) was obtained to convert the uncertainty in psi to an uncertainty in gpm. This inethod has been determined to be an acceptable approach and has been evaluated independently by Duke Engineering Services. (reference 10)
The two points taken off the fangentialline to develop the slope were 275 feet at 1900 ppm, and 150 feet at 5950 gpm. The conversion factor used to convert ft to psi (2.336) assumes a water temperature of 125 "F which )
is the upper temperature for the CCW system from the draft CCW Design i Basis Document. I
./ /
m -
275 ft 150 ft i
= 3.09E - 2 ft / gom x psi
= 1.32E - 2 osi / gom #
1900 Opm - 5950 gpml 2.336 ft ,
v / l U692 - 1.10 psi x 9P* = = 83 gpm /
1.32E 2 osi UP*
U617 = 2.24 psi x 1.32E 2 pst
= z 170 gpm /
Now that the units of the individual uncertainties are consistent, the total uncertainty associated with the instruments used to test the CCW pumps can be calculated via the SRSS method.
- d. Combining the uncertainties from these three instruments gives the.
fellowing for total uncertainty:
-- . . . _ . . _ . . . _ - _ _ . _ . - __-..-__-.._____-__.m_..___-._ -
- , _ _ ~
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TITLE: Uncertainty AssIciated with CALCULATION a . 96-0254 Instrumentation Used in Prepared By: EJM 1712 & IT-13 for CCW Pumps Date:12f23196 Page R of M j
Utotal = I (U692)* v (US17)* - (U619)2
~
Utotal = z d(83 gom)* t (170 gpm)* t (529 gpm)* !
Utotal -- i 562 apm /
H. . Results
)
t he total instrument uncertainty, expressed in gom, associated with the inservice test procedure for the component cooling water pumps is e 562.
gpm.
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