ML20199K611
| ML20199K611 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 11/13/1997 |
| From: | Chen H, Czyszczewski M, Vega M COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20199K523 | List: |
| References | |
| CON-10246-002, CON-10246-2 L-001324, L-001324-R01, L-1324, L-1324-R1, NUDOCS 9712010164 | |
| Download: ML20199K611 (108) | |
Text
r 1 2 ATTACHMENT G CALCULATION NO. L-001324, Rev.1, Nov.13,1997 AREA AMBIENT AND DIFFERENTIAL TEMPERATURE DESIGN BASIS O CALCULATIONS FOR REACTOR COOLANT LEAK DETECTION (Note that the " Mezzanine Area" as referred to in the attached calculations is the same as the holdup pipe area for RWCU) 9 97120to PDR A g [ M 73 i PDR P ,
l COS1510NWEALTIl EDISON COSIPANY CALCULATION TITLE PAGE O
CALCULAllON NO.: L-vol324 PAGE NO.: 1
@ SAFETY RELATED C REGULATORY REIATED C NON.SAITTY RELATED CALCULATION lilLFn Area Ambient and Differential Temperature Design Basis Calculations for Reactor Coolant Leak Detection STATION / UNIT: SYSTEM ABBREVIATION:
LaSalle Units I and 2 RT, RI, Ril, MS EQUIPMENT NO.: N/A PROJECT NO.: 10246 002
%EV: D ST8fUS': App 7 rover----QA SEKlAT30. GKtIIRTNRE--- BATE-----
PREPARED BY: Michael F. Czysrczewski /#ffed DATE: /o////97 '
09 00
/'
REVISION
SUMMARY
- Revision 0 InitialIssue k nis calculation is being issued to identify plant areas which contain reactor coolant pipelines outside of the containment; identify which of the identified areas require LD ambient and differential temperature monitoring; and for those plant areas that require LD temperature monitoring, perform calculations to determine the theoretical room area temperature rise and rate of change for various design pipe leak rates.
ELECTRONIC CALCULATION DATA FILES CREATED:
(Name ext / size /date/ hour: min / verification method / remarks)
The follomng source files wre verified tiuough an attnbute comparison.
1001324. DOC /175616/1017 97/l:28:18pm/Microsoft Word 6.0 File Report SYSTEMS.XLS/140288/ID 16-97/ll:21:02am/ Excel 5.0 Electronic Spreadsheet Tables RCIC.XLS/92672/10-16-97/4.03.22pm/ Excel 5.0 Electronic Spreadsheet Calculation DO ANY ASSUMPTIONS IN TIIIS CALCUIATION REQUIRE LATER VERIFICATION YES@NOC Vettfv that no ptping enodtfications which affect <fie I D calculatichs (prept for the RWCU pipint) have occured since the RaC No 24 NDIT.
REVIEWED BY: H.Ch / [rr// b / h b ' 7 DATE: /0 // 7 /9 ?
o e /
REVIEW METHOD: Detailed Design Review / COMMENTS (C, NC OR CI): CI._
j APPROVED BY: M. Veen,N/4,fMkW
, DATE: //,!/,/M,7 MJ Bautem 4
Exhibit C
. NEP.12 02 Revision 4 COMSIONWEALTil EDISON COMPANY '
CALCULATION REVISION PAGE CALCULATION NO.: L.001324 PAGE NO.:2 REV:1 STATUS: Unverified QA SERIAL NO. OR CllRON NO. DATE:
PREPARED BY: Michael F. CrysrgznnM N4d4'- - dg,.p9M DATE: //[/3/M i <
i REVISION
SUMMARY
The revision was required t0:
. Incorporate the results from calculation L.001281, Rev. 01
- Add a LD calculation for the RWCU Pipe Tunnel 798'.0" , issued on 117 97
. Add a comparison of the calculated temperatures to the Technical Specification setpoints.
All of the pages in the report have been renumbered in order to incorporate the above changes. All changes are identified in the calculation by revision marks (Rev. 01). The revision status ofpages which do not show test or table changes from Rev. O are marked Rev. 0 (even though this rnaterial may have appeared on another page in Rev. 0). His was done in order to make a more readable ad@ clear document.
Tilyn O
ELECTRONIC CALCULATION DATA FILES REVISED:
(Name ext / size /date/ hour; min / verification method / remarks) ne following source files were verified through an attribute comparison.
1234.RI. DOC /208384/11 12 97/l:52:56pm/Microfoft Word 6.0 File Report SYST RI.XLS/140800/11 12 97/7:01:16an/ Excel 5.0 Electronic spreadsheet - Tables RCIC31.XLS/120320/1112 97/11:15:08am l
DO ANY ASSUMPTIONS IN Tills CALCULATION REQUIRE LATER VERIFICATION YES@ NOC Verify that no piping modifications which affect the LD calculations (except for the RWCU piping) have occured since the Ref. No. 24 NDIT.
- i
/' , -
REVIEWED BY: 11. Chen
& *~
8
,/
DATE: / 3![ 7 REVIEW METilOD: IMaikd 4/ COMMENTS (C, NC OR Cl): Cl The reviewer's signature indicates compliance with S&L standard GES 320.10 and the verification of the following minimum items: correctness of math for hand nepared calculations, appropriateness ofinput data, O
! appropriateness of assumptions, and appropriateness of t2e calculation method.
V APPROVED BY: M. Vega
[l[diuu A DATE: ////M97 M .
/ /
Eshibit C
- NEP.12 02 Revision 4 O COhlhlONWEALTil EDISON COhlPAN .
CALCULATION TABLE OF CONTENTS CALCULATION NO L-001246 PROJECT NO. PAGE NO. 3 10246-02 SECTION PAGE NO. SUB PAGE NO.
1 TITLE PAGE REVISION SUI.F4ARY 2 TABLE OF CONTENTS 3 PURPOSE / OBJECTIVE 4 METHODOLOGY AND ACCEPTANCE CRITERIA 6 ASSUMPTIONS / ENGINEERING JUDGMENTS 7 O DESIGN INPlTT 11 C
REFERENCES 16 CALCULATIONS 18
SUMMARY
AND CONCLUSIONS 42 ATTACHMENTS 48 A. Area De(mition Cross Referece Al A2 B: Areas Contatrung Reactor Coolant Pipelines Bi B13 Outside of Containment C: Excerpt from 1991 S&L Letter / Attachment - Cl C9 Tanperature Based LD System Evaluation D: Excerpt from 1995 S&L NDIT Temperature Cl D6 Based LD Evaluation E: Summary Table of Temperature Based LD S3sem El E17 Pipelines Evaluauons y F: Spreadsheet Calculations of Ambimt Air Temp. F1 F9 and Differmtial Temp. for a LD S>sem in the RCIC hpe Chase i
a G: Spreadsheet Cell Formulas used in Attachment F Gl G3
\
COMMONWEALTH E[DISON COMPANY PROJECT NO. 10246-002 PAGE NO. 4 CALCULATION NO. L 001324 l l 1,.0 PURPOSELORJEQIlyg The LaSalle Power Station has a Leak Detection (LD) system for pipelines containing reactor coolant that are outside of the primary containment. The LD system uses redundant detection methodologies such as temperature, radiation, or sump level monitoring in each piping room araa.
The purpose of this safety-related calculation is to define and document the methodology and calculations used in determining inputs for the LD temperature sensors. These inputs consist of a determination of the theoretical room area ambient temperature rise and rate of temperature change due to pipe leaks of various size. Specifically, this calculation will:
. Identify those plant areas which contain reactor coolant pipelines outside of the containment
. Identify which of the above identified areas require LD ambient and differential temperature monitoring.
. For those plant areas that require LD temperature monitoring, perform 9 calculations to determine the theoretical room area temperature rise and rate of change for various design pipe leak rates.
This calculation is issued in response to Problem identification Forms (PlF) 96-0202, L1997-04896 and L1997-05315, which address concerns about the technical i adequacy of the original temperature based LD design basis calculations. The ,
7 objective of this calculation is to consolidate the previous calculations into one l j document, correct errors in the original calculations, and more clearly define the ;
! basis of the temperature based LD setpoints. This calculation will supersede and replace those found in the following documents:
. Ll-01, Rev. O, Calculation for Temperature Sensor Set Points for Main Steam Tunnel Leak Detection.
. Ll-02, Rev. O, Calculation for Temperature Sensor Set Points for RCIC Steam i Tunnel Leak Detection. 1
. LI 03, Rev. O, Temperature Sensor Set Point Verification for Main Steam Tunnel.
. Ll-04, Rev.1, Set Point Verification for Main Steam Tunnel, p Ll-05, Rev.1. Set Point Verification for RWCU Equipment Rooms.
V ,
P.EVISION. NO.
00
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COMMONWEALTH EDISON COMPANY CALCULATION NO. L 001324 PROJECT NO. 10246-002 PAGE NO. 5
. Ll 06, Rev. O, Set Point Verification for RHR Pump Rooms
- LI-07, Rev. O, Set Point Verificadon for RCIC Equipment Rooms
. Ll-08, Rev. O, Set Point Verification for RCIC Pipe Tunnel The scope of this calculation is limited to the temperature based components of the LD system. Othe-leak detection methodologies will be used where temperature based LD setpoints are not appropriate. The scope c,1 this calculaUon does not include developing inputs for these other methodologies. In addiUon, calculadons will not be performed for plant areas that are not found to require a temperature based LD system, or for which valid approved calculations already exist.
Existing approved LD temperature calculaUons are not repeated here, however, for completeness, their inputs and results are listed here. In summary, this calculation does not replace the following:
. S&L Calculation, L-001281, "RWCU Pump and Heat Exchanger Rooms c Temperature Response Due to High Energy RWCU Fluid Leakage, (Reference j 9 No. 9) c
. S&L Calculation, 3C7-1184-001, "ECCS Room Leak Detection Setpoints" l (Reference No. 21)
. CECO Calculation, BSA-L-95-05, "LaSalle MS Tunnel Temperature Response Due to Steam Leakage with Ventilation System in Operation" (Reference No.
15)
Revision 01 of this calculation is being issued in ordei to:
. Indorporate the results from calculation L-001281, Rev. 01, issued on 11 97.
. Add a LD calculation for the RWCU Pipc Tunnel 798'-0" p
. Add a comparison of the calculated temperatures to the current Technical l Specification setpoints.
This calculation revision does not change the results or cenclusions previously issued in the original calculation issue. Only additional information which was g missing from the previous issue is being provided.
REVISION. NO.
01
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COMMONWEALTH EplSON COMPANY CALCULATION NO. L401324 PROJECT NO. 10246 4 02 PAGE NO. 6 12.0 METHODOLOGY AND ACCEPTANCE CRITERIA 2.1 Methodology An assessment of the LD requirements for each room and pipeline is based upon the findings, conclusions, and recommendaUons. contained in the 1990 Cygna study (Reference No.10), the 1991 S&L LD evaluation (Reference No. 25) and the 1994 S&L NDIT (Reference No. 24). A new evaluauon of the rooms and pipelines la not conducted in this calculation. The evaluations contained in these references are assumed to be valid since S&L has determined that the approved referenced results/ conclusions are appropriate as design !nput to this calculation. This calculation assumed that no significant room, piping, or instrumentation changes have occurred since the 1995 assesan.ent (Reference No. 24), with the exception of changes evaluated in the new RWCU calculation (Reference No. 9). This 5 assumption should be verified. If any changes are found to have occurred since the g 1995 evaluation, they should be incorporated in Revision 2 of this calculation. &
The plant areas which require LD air temperature calculations will be determined l l as follows:
. Use the 1990 Cygna study to determine which reactor coolant piping systems are routed outside containment.
. Use the 1990 Cygna study along with the if 35 S&L LD evaluation issued in an NDIT and 1991 letterlattachment as the basis for determining temperature based LD system compliance.
. Based upon the review of the above described documents, identify the areas /p.pelines that require ambient temperature and differential temperature calculadons for the temperature based LD system.
Existing LaSalle temperature based LD calculations will be reviewed to determine if they are acceptable, if new area temperature based l9 calculations are required, they will be performed as follows:
. The calculation will model the various cubicles, rooms and tunnels as a control volume. An energy balance is performed on this volume to predict the exhaust air temperatures that the ventilation ductwork will experience.
. A pipe leak inside the control volume will provide heat to the air, and this I
value is added to the heat normally present in the area. The amount of heat REVISION. NO.
01 eunws - mm cc 4
l COMMONWEALTH EDISON COMPANY :
i PROJECT No. 10244 002 PAGE NO. 7 CALCULATION No. L 001324 l 1 L gain is dependent on the enthalpy and mass of the leak which flashes to steam. The heat gain contributed by the portion of the pipe leak in the liquid phase is neglected. The outlet mir temperatures resulting from a design 5 l gpm and 25 gpm leak rate will be determined. l
- The steady state room exhaust air temperature is predicted by adding the inlet air temperature to the rise in temperature of the air due to the heat gain ,
from the equipment and the pipe leak in the control volume.
. The area differential temperature is determined by subtracting the normal operating inlet ambient air temperature from the predicted outlet mir i temperature.
The calculation methodology described above is consistent with the General Electric (GE) LD design guidelines (Reference No. 20). These guidelines recommend that a simple energy balance be performed, based on a steady state model that assumes heat transfer through the area walls and elabs is zero.
1 p L2 Assentance Critada v The LD system is required by the UFSAR (Reference No.14) to detect pipe leak rates (mass equivalent at standard conditions) for the following two conditions:
. A pipe leak rate of 5 gpm should be detectable. This control room alarm value will allow time for corrective action before the pipe's process barrier could be significantly compromised.
. A leak rate of 25 gpm should initiate a system isolation.
General Design Criteria 54 of 10CFR 60 Appendix A (Reference No. 22) requires that piping systems penetrating primary containment shall be provided wita redundant leak detection capabilities. This means a temperature based LD is not required fer a pipeline if at least two other LD methodologies are present.
3.0 ASSUMPTIONS /ENQ1NEERING JUDGMENTS The following assumptions are inherent in the methodology used to :erform the heat balance calculations:
O .
REVISION. NO.
00 s%.--.m c
COMMONWEALTH EDISON
- COMPANY l
PROJECT NO. 10246-002 PAGE NO. 8 CALCULATION NO. L 001324
( > i
. Inlet Air Tempelafures_
e pre Constant The ventilaUon air. inlet temperature is assumed constant during the steam leak. This assumption is reasonable since the pipe leak time period for the design leak rates is small (less than a few hours).
. Process FluLd_I_lquJd. Phase Heat Input is NeJI ected
~
The heat gain contribution of fluid leaking from the pipe that is in the liquid phase is conservatively neglected. This is acceptable since neglecting this, heat load causes the area thermal alarm setpoints to be reached sooner, thereby causing an alarm before the criticalleak rate is actually reached.
. Effectpf Room Inlet Air Humidity Durina a Pipe Leak is Negligible A sensitivity study is included in Reference No.12 that investigates the effect of room inlet air humidity on the heat balance calculations. The results show that inlet air relauve humidity for both a 5 and 25 gpm pipe leak rate has a negligible effect on the room air temperature response. The sensitivity study showed that the room air temperature decreased roughly 1 'F, when the G relative humidity was varied between 10% and 90%
. tLept Transfer Throuah Area Walls is Neallaible Heat transfer through room walls is assumed low at steady state conditions due to the thickness of the concrete and its low thermal conductivity. When a pipe leak occurs, area humidity will rise resulting in a condensed film of hot water on walls and components. This film of hot condensate will create addiUonal thermal resistance to heat flow, in addition, this assumption is required for the simple control volume model described in the GE methodology recommendations (Reference No. 20).
. Equ_ipment Heat Loads Are Constant During.a Pipe Leak Heat loads from equipment or piping in the room area are assumed constant whatever the ambient air temperature. This assumption can lead to unconservative results because the heat gain contribution of piping and equipment is reduced when a pipe leak occurs and the area heats up.
A sensiUvity study is included in Reference No.12 that investigates how changes in heat load affects the heat t;alance calculatiom. For a 25 gpm leak pV rate, the results showed an air tomperature rise of roughly 1 'F for every 50 BTU / min of heat load incrcinent. For the 5 gpm leak rate, the results showed REVISION. NO.
00
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COMMONWEALTH EDISON COMPANY PROJECT NO. 10244 002 PAGE NO. 9 CALCULATION NO L 001324 9 .
i a temperature rise of roughly 1.5 'F fo every 50 BTU / min heat loaci increment. Baceuse the observed che nges are small, heat loads can be ,
considered constant during a pipe lesk. '
- Changes in the Exhane.tjystem's Perf. DuriD91SL9_Am_Lenk are Neallgih[t The heat balance calculsdons assume that increases in air moisture during a pipe leak will have a negligible effect on the performance of the venulation system exhaust fans. The density of steam is of the same order of magnitude as the density of air, therefore, during the ateam leek, the fluid density change experienced by the fans will be negligible.
- P_tenamiEatipn of the Room Ares purina a Ploetken_k_ is Neglisibit i The heat balance calculations are based on the mesumption that the pipe leak will not pressurize the areas beyond normal (14.7 pela) levels. This assumption is jusufied as follows:
' - The room areas have many air passages that would allow venting on 3 any attempt to pressurize them. These passages includc wire-type ventiladon doors and ceiling / wall gaps.
- Before the room area pressure could build, it would have to equalize with the reactor truilding (a relatively much larger volume) which is maintained at a slight hogative pressure. When a pipe leak occurs, the change in exhaust air volume through the exhaust fans is negligible.
The leaking steam volume will vent out of the room into other areas of the reactor building, rather than cause the room to pressurize.
- For pipe leak rates on the order of 5 and 25 gpm, the mass and energy '
releases era small compared with the room volume. Compared to a high energy line break, the transient and steady state pressures developed are approximately three orders of magnitude smaller.
Therefore, unlike high energy line break calculations, area pressurizauon effects may be neglected.
- Room inlet Air Flow Rate will be Reduced Durina a Pine Leah The heat balance calculations are based on the assumpUon that a pipe leak will cause the room's inlet air flow to decrease in proportion to the amount of steam entering the room from a pipe leak. This assumption will lead to higher .
0 temperature sensor set points since the room temperatura will rise as the O inlet air flow is reduced. This assumption is jusufied as follows:
REVISION. NO.
00 man.wom minu=
g Essesama 4
_ , _ . ~ . _ _ _ _ . . . , _ . _ . _ , . . _ . . - _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _
COMMONWEALTH EDISON COMPANY cat.CULATION NO. L 001314 PROJECT NO. 10246 002 PAGE NO.10 l I
- The outlet air flow rate remains constant because changes in the '
exhaust air volume through the exhaust fans during a pipe leak are negligible.
- During normal operating conditions, the reactor building'o exhaust ventilation network induces a small negauve pressure difference between the fan's inlet and other areau of the building. This pressure differential (in the order of 1/16 to 1/8 inch w.g. relative to the pipe rooms) draws air through the rooms. A slight positive room pressure from a pipe leak will, therefore, drive air and steam out of the rooms through various openings. This would have the effect of blocking the normal flow of air into the area.
- A,talyses are included in Reference No.12 which invenUgates v.,w inlet air flow changes affect the heat balance calculaUons. The results show that room air temperature rises as inlet air flow is reduced.
The technical assumptions listed above were used to perform the temperature i
based LD calculations presented here. Other referenced temperature LD I I calculations may have used a different set of assumptions because different I
analytical techniques were used, or different room characterisucs needed to be accounted for. These reference calculations should be consulted for a detailed description of their assumpUons.
The assessment of the LD requirements for each room and pipeline is based upon the findings, conclusions, and recommendations contained in the 1990 Cygna study (Reference No.10), the 1991 S&L LD evaluation (Reference No. 25) and the 1995 S&L NDIT (Reference No. 24). A new evaluation of the rooms and pipelines will not be conducted in this calculation. The evaluaUons contained in these references are assumed to be valid. This calculation assumes that no significant room, piping, or instrumentaUon changes have occurred since the 1995 assessment (Reference No.
24), with the excepuon of changes evaluated in the new RWCU calculation i (Reference No. 9). This assumption should be verified, if any changes are found to lg .
have occurred nince the 1995 cvaluation, they should be incorporated in Revision 2 E of this calculation.
l REVISION. NO.
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COMMONWEALTH EDISON COMPANY
\
PAGE NO.11 i CALCULATON NO. L401324 PROJECT NO. 10244 4 02 i
4.0 DESIGN INPUTS The calculations were prepared using the followilig design inputs.
. Area EauiAment and Piojna Heat Loeds:
PLANT AREA REF. . HEAT No. LOAD (Stuimin)
MS P6pe Tunnel . 16 332.6 Upper / Lower RCIC Estulpment 21 336.0 Room 473'.4" RWCU Pipe Tidinel Tliis 0 798'-0" Calc.
RWCU Heat 9 862/38 Exchanter Roome un 7es.. "
p 862/38
' V RWCU Valve Roome 9 NB 786' 8" RWCU Pump Roome 9 664192 NC 781' 0" RWCU Pump Room 8 9 299 i
(
761'-0" RWCU Domin. Room 9 200 i
NS/C 120'-8" RWCU Loop Hold-Up 9 293 Pipe Room 774'-0" RCIC Pipe Chase This 0 710' 4"Hi Calc.
(1) The area only containe insulated piping. The heat load will, therefore, be conservatively taken as zero.
O REVISDN. NO.
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COMMONWEALTH EDISON COMPANY PROJECT NO. 10246-002 PAGE NO.12 CALCULATION NO. L 001324
- Area Inlet Air Flow Ratesj PLANT AREA REF, INLET AIR NO. FLOW RATE (scru)
MS Pipe Tunnel . 15 24,000 Upper (g 95 *F)
MS Pipe Tunnel. 15 40,000 Lower (O 95 'F)
RCIC Equipment 21 3,718 Room 673'-4" RWCU Pipe Tunnel 26 7,660 798' 0" RWCU Ht Esch. 9 2603 Roome NB 786' 6
RWCU Valve Roome 9 2603 NB 786' 6" r 1694 C l RWCU Pump Roome 9 NO* 761' 0" .
i 916 C RWCU Pump Roome 9 8 761' 0" RWCU Domin. Room 9 549 NB/C 87^' 6" AWCU Loop Hold Up 9 916 Pipe Room 774' 0" RClc Pipe Chase 13.2 300 l 710' 6" l
i 1
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REVISION. NO.
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COMMONWEALTH EDISON COMPANY CALCULATION NO. L-001324 PROJECT NO. 10246-002 PAGE NO.13
. Inlet Air Temperatures _;
The calculations should be performed so that the tamperature based LD system is responsive to a leak any time of year. The i.0 setpoints should be low enough to ensure that the leak is detected, but high enough to avoid spurious isolations and alarms. Therefore, a reasonable maximum summer and a reasonable minimum winter ventilation air temperature were used in the calculations. The summer air temperatur a is conservative for the ambient air temperature calculations, while both winter and sur, mer values are nended to calculate the differential temperature. The following area inlet air temperatures were used in the calculations:
PLANT AREA REF (WINTER) (SUMMER)
. MIN. MAX. INLET AIR No. INLET AIR TE MP. (*F)
TEMP.
('F)
MS Pipe Tunnel . 16 66 110 Upper / Lower RCIC Equipment Room 21 70 104
{ 673' 4" RWCU Pipe Tunnelm 798'-0" 9 80 121.6 RWCU Heat Exchanger. 9 80 104 Roome NB 786'-6" RWCU Valve Rooms NB 9 80 104 786'-6" ,.
O RWCU Pump Rooms NC 9 80 104 .
781'-0" $,
a:
RWCU Pump Rooms B 761'. 9 80 104 0"
RWCU Domin. Room NB/C 9 80 104 820' 6" RWCU Loop Hold Up Pipe 9 80 104 Room 774' 0" RCIC Pipe Chasem 710' 6" 27 66 118 l
l (1) A reference temperatur9 of 80 F (winter) and 104 (summer) ,
r pfg gused for the basis of the diftarentialtemperature sensors (as per Reference No. 9).
{l Al 1)
(2) An NOIT containing the desi,)n input data has not yet been c1 received. The values shown are expected to envelope the O
i possible room temperatures.
REVISION. NO.
01 l 1
LetatPwetfuettentN4 a&JoC mC l NEP1141 l Revesten 4
COMMONWEALTH EDISON ,
COMPANY PROJECT NO. 10246-002 PAGE NO.14 CALCULATION NO. L 001324
- 6Les Inlet Air Humidity Levels:
PLANT AREA REF. SUMMER WINTER NO. RELATIVE RELATIVE HUMIDITY HUMIDITY
(%) (%)
MS Pipe Tunnel- 16 30 30 Upper / Lower ,
RCIC Equipment 21 38.7 16 8 Room 673'-4" RWCU Pipe Tunnel 9 35 23 798' 0" RWCU Ht Exch 9 35 23 Roome N8 786' 6" RWrU Valve 9 36 11 Roome NB 786' 6" RWCU Pump 9 35 23 e Roome NC 761'-0" C RWCU Pump 9 36 23 k Er Roome 8 761'-0" . ,
RWCU Domin. 9 36 23 i
I Room NB/C 82C' 6" l RWCU Loop Hold. 9 35 23 Up Pipe Roon.
774'-0" RCIC Pipe Chase 27 30m 30m 710'-6" l
(1) An NDIT containing the design input data has not yet been received. The values shown are gxpected to envelope the possible humidity values.
I i
e REVISION. NO.
01 c*aw w - =uw ti e NEP-t&43 aw.
COMMONWEALTH EDISON COMPANY PAGE NO.15
. CALCULATION NO. L 001324 PROJECT NO. 10246-002 I l
. Eipeline Process Flow!%nditions The maximum design pipeline flow Conditions are shown below for each area:
PLANT AREA REF. PRESSURE TEMPERATURE No. (pala) (*F)
MS Pipe Tunnel . 16 1050 660 Upper / Lower ,
RCIC Equipment 21 1000 646 Room 673'-4" RWCU Pipe Tunnel 31 1300 676 796' 0" 14RWCU Ht Exch 9 1020 437 Roome NB 766'.6" tuRWCU Valve Roome 9 1020 437 NB 766'.6" C 1020 633 IURWCU Pump.Rootets NC 761'.0" 9
j G
IURWCU Pump Room 9 1020 633 l B 761' 0" j
mRWCU Domin. Room 9 1020 437 NBIC 620' 6" WRWCU Loop Hold. 9 1020 633 Up Pipe Room 774' 0" RCIC Pipe Chase 31 1250 676 710' 6" '
e c
(1) The temperaturse are from the normal opereting mode E
. Atmospheric pressure is 14.7 psia. (
Reference:
standard engineering data) e Water density is 62.4 lb/ft" (Ref.: standard engineering data for a standard temperature of 70 *F and a standard pressure of 14.7 psia.)
. The steam rates are expressed in gallons per minute. One gpm of steam leakape is equivalent to the mass flow rate of 1 gpm of water with a density of 62.4 lbtft'.
e
. Air at standard conditions (14.7 psia and 70*F) has a density equal to 0.075 Ibtft'. (Reference No. 32) lCi O 0
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REVISION. NO.
01
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COMMONWEALTH E,DISON COMPANY PROJECT NO. 10246 002 PAGE NO.16 CALCULATION NO. L 001324 5.0 REEEEENCES This calculation was preparend using the following references:
- 1. Ll-01, " Calculation for Temperature Sensor Set Points for Main Steam Tunnel Leak Detecuon," Rev. O, dated 3-24-81
- 2. LI-02, " Calculation for Temperature Sensor Set Points for RCIC Steam Tunnel Leak Detection," Rev. O, dated 3 23-81.
- 3. LI-03, " Temperature Sensor Set Points fr. the RWCU Pump a- Hest Exchanger Cubicles," Rev. O, dated 3 23-81
- 4. Ll-04, " Set Point Verification for Main Steam Tunnel," Rev.1, dated 04-1184.
- 5. Ll-05, " Set Point Verification for RWCU Equipment Rooms," Rev.1, dated 06-11-84 '
- 6. LI-06, " Set Point Verification for RHR Pump Ro7ms," Rev. O, dated 09-26-83.
- 7. LI 07, " Set Point Verification for RClO Equipment Rooms," Rev. 0, dated 10-10-83.
- 8. Ll-08, " Set Point Vcrification for RCIC Pipe Tunnet," Rev. O, dated 10-10-83.
C
Temperature Response Due to High Energy RWCU Fluid Leakage, Rev. 01, g Er dated 11/07/97.
- 10. " Study of Temperature and DifferenUal Temperature Leak Detection Provisions for Reactor Coolant Pressure Boundary Piping Outside Primary Containment, " CYGNA, LaSalle Project No. 90071, Dated 5-30-90.
- 11. S&L Steam Functions for Excel, Stmfunc.xla, (S&L's verined and validated program) Program No. 03.7.598-1.0.
- 12. S&t. Calculation, L-001298, " Leak Detection Evaluation Based on Area Ambient and Differential Temperatures for Basis of Licensing Event Report to USNRC," Rev. O, Dated 9-17 97.
O REVISION. NO. -
01 En.- - - .ua me 71"l
COMMONWEALTH EDISON COMPANY CALCULATION NO. L 001324 PROJECT NO. 10246-002 PAGE NO.17
- 13. S&L Piping and Instrumentation Drawings 13.1 M 1461, HVAC P&lD, " Liquid Radwaste Ventiladon System," Sheet 2 of 4, Rev. J, dated 3 22 90.
13.2 M 1461, HVAC I'?.'D, " Liquid Radwaste Ventilation System," Sheet 2 of 4, Rev. F, dated 1-16-96.
13.3 M-104, Mech. P&lD, " Reactor Building Floor Drains," Sheet 1, Rev. P.
(Shows sump drains in RWCU Hold up Pipe Room)
- 14. LSCS-UFSAR, SecUons 5.2.5.1.2, 7.3.2.2.3.10, and 7.6.2.2.5.
- 15. Ceco Calculadon, BSA-L-95-05, "LaSalle MS Tunnel Temperature Response Due to Steam Leakage with Venulation System in Operation", Rev. O, dated 1-13-96.
- 16. Problem idenUfi[ation Form (PIF) L1997-04896, " Leak Detection OP Eval, incomplete," 8-6-97.
I 17. Problem IdenUfication Form (PlF) L1997-05315, "LD System T and detta T,"
dated 8/22/97.
- 18. Problem Identification Form (PlF) 96-0202, " Revise T.S. Leakage Detection Cales. for Temp. & Diff. Temp," 8-06-97
- 19. Letter from USNRC to Ceco, "Isauance of Amendment for the Setpoint Change to the Primary Containment isolauon on Main Steam Tunnel Differential Temperature - High", dated 4-4-96.
- 20. ' General Electric Leak Detection System Design Specification 22A2870,"
Rev.8,
- 21. S&L CalculaUon 3C7-1184-001, "ECCS Room Leak DetecUon Setpoints, Rev.
1, dated 5/7/86.
- 22. Code of Federal Reguladons,10 CFR 50, Appendix A, General Design Criterion (GDC) 54, " Piping Systems Penetrating Containment."
- 23. Letter from JoAnn Shields (Ceco) to Dr. T. E. Murley (USNRC), "DeleUon of the Steam Condensing Mode of the Residual Heat Removal (RHR) System,"
dated 10-20-92.
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COMMONWEALTH EDISON COMPANY
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j CALCULATION NO. L-001324 PROJECT NO. 10246-002 PAGE NO.18 9
- 24. Nuclear Design Information Transmittal (NDIT) LAS-NDIT-0072-00, " Leak Detection Evaluation", LaSalle 1 & 2, lasued by Sargent & Lundy, dated 9 95.
- 25. Letter / Attachment SCM-0534, " Review of tho Leak Detection System, LaSalle 1 & 2, E. P. Ricohermoso (S&L) to R. H. Mirochana (CECO), dated 121-91.
- 26. S&L HVAC Physical Drawing, Mo M-1357, Sheet 2 of 2, LaSalle Unit 1, c
" Reactor Building Vent. System - El. 786'-6" West," Rev T, dated 3-25-C9. j c
27 NDIY Containing input data (Inlet air humidity and summer / winter temperatures) for the RCIC Pipe Chase ( in progress).
- 28. Microsoft Excel Spre;Jsheet Program, Version 5.0c,1995-1994, Product ID:
OEM43-D21 2537164.
- 29. S&L Steam Functions for Microsoft Excel, Stmfunc.xla, (S&L's verified and validated program) Program No. 03.7.598-1.0.
- 30. GOTHIC Computer Program, Version 4.1, NAl 8907-02, Rev 5, Numerical i
h Applications, incorporated, September 1994.
- 31. Piping Line List, LaSalle County 1/2, Rev BM, dated 8&-94.
l 32. ASHRAE Handbook Fundamentals,1993 Edition.
c
- 33. LaSalle Unit 2 Technical Specification for Leak Detection isolation, j
Amendment No.100, Table 3.3.2-2.
6.0 CALCULATIONS The temperaturn based LD system is intended to alarm on S gpm and isolate on 25 l
gpm. This system is effectJve for detecting and locating pipe leakage because of it's sensitivity and immediate response, however, it does not accurately quantify the amount of leakage. Th's method is influenced by many variables such as the temperature and humidity of the entering air, pressure and temperature of leaking reactor coolant, room air flow rates, HVAC flow paths, and changes in process pipe operating modes.
An essassment must be made of the room and pipeline specifications to determine i if a temperature based LD system is applicable for a room and will func'Jon reliably.
G This assessment is contained in the sections that follow. Temperatura calculations REVISION. NO.
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COMMONWEALTH EDISON COMPANY PROJECT NO. 10246-002 PAGE NO.19 CALCULATION NO. L-001324 are performed for those room areas where a temperature based LD system was found appropriate.
6.1 Definitions
. CAM: Continuous Airborne Monitors. This is an in-duct isokinetic probe. Air collected from the CAM is passed through a fixed particulate filter for continuous monitoring and then through a charcoal canister for iodine sampling. CAMS are equipped with adjustable high and low radiation alarm setpoints.
. ECN: Engin 'ering Change Notice.
. Flashing: When pressurized water enters an area at atmospheric pressure, the drop in pressure causes the water to suddenly change states and " flash" into steam.
Pipeline flow rates more than a predetermined
. Flow monitoring:
amount can be an indication of a pipe leak.
. FW: Feedwater.
. Heat Load: The heat in Blu/ min emitted by equipment and piping into a room.
. HVAC: Heating Ventilation and Air Conditioning.
. LD: Leak Detection.
. MS: Main Steam.
. P&lD: Piping and Instrumentation Diagram.
! . Radiation monitoring: An increase in area radiation levels can be an I
indication of a reactor coolant pipe leak. Pipe leak i radiation monitoring can be performed by fixed air l sampling, fixed area radiation monitoring, or CAMS.
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COMMONWEALTH EDISON COMP ANY l PROJECT NO. 10246-002 PAGF NO. 20 CALCUL.tTION NO. L-001324
. RCIC: Reacter Core isolation Cooling.
. RCP8: Reactor Coolant Pressure Boundary. All those pressure-containing con.ponents such as pressure vessels, piping, pumps, and valves that aire part of the reactor coolant system or connected to the rea 'or coolant system, up to and including any or all of n - following: -
- The outermost containment isolation valve in system piping which penetrates primary reactor containment
- The second of two valves normally closed during reactor operation in system piping which does not p% strate primary reactor containment
- Tho reactor coolant system and safety and relief valves. The reactor coolant system I extends to and includes the outermost j containment isolation in the MS and FW piping.
. RHR: Residual Heat Removal.
. RWCU: ,
. Sump monitoring: Increases in sump pump-out time, or a pump rest.ari g before a preset timing interval can indicate that n pipe leak has occurred in a room area.
l
. UFSAR: Updated Final Safety Analysis Report l
. Visual /A"dible monit. Accessible areas are inspected periodically. 1 Temperature and flow indicators are monitored l regularly. Any instrument indication of abnormal leakage will be investigated.
l 9
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COMMONWEALTH EDISON COMPANY PROJECT NO. 10246-002 PAGE NO. 21 CALCULATION NO. L-001324 l I 6a2 Units A descrip'. ion of the nomenclature and units used in the calculations follow:
. p, Atmospherb prescoure psia
. T, Room supply breperatus e (*F) e mi Humidity rc.tle of supply air (Ib,,, Abe,)
. h., Enthalpy of dry entering air (BTUllb)
. h,3 Enthalpy of water vapor at T 3 (BTU /lb)
. hi Combined enthalpy of entering mixture (BTU /lb) 8
. vi Specific volume of supply air (ft 'Ib)
. v4 Specific volume of air at steady state (ft*'Ib) 8
. Q, Volumetric flow rate of supply air (ft / min) 3
. Q4 Volumetric flow rate at steady state (ft / min) j
. mi Wass flow rate of supply air (Ib/ min)
. hr Enthalpy of saturated liquid at room pressure (BTUAb)
. h, Enthalpy of saturated steam at room pressure (BTU /lb)
. h4 Enthalpy of exit air at room pressure (BTUnb e HL Total heatload (BTU / min)
. To Terr.perature at leakage point (*F)
. pt t8 ressure atleakage point (psia)
. he Enthalpy atleakage point (BTunb) n . F Steam flashing rate (%)
f u
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COMMONWEALTH E,DISON COMPANY CALCULATION NO. L-001324 PROJECT NO. 10246-002 PAGE NO. 22
. pt Water density (Ibtft')
. Qt Total volumetric flow rate of leakage (gal / min)
. muot Total mais flow rate of leakage (Ib/ min)
. mt, Mass flow rate of flash steam (Ib/ min) e v, Specific volume of flash steam (ft*'Ib) e mu Mass flow rete of condensate (Ib/ min)
. co4 Humidity ratio at steady state (Ib/lb)
. T4 Temperature at steady state (*F) h.4 Enthalpy of. dry air at T4 (BTUllb)
. h,4 Enthalpy of water vapor at T4 (BTUllb)
I l
. Atm., Temperature diff'erence across room ('F) o
. tw Reference temperature for determining At (*F) s e
6.3 Cyana Study - Reauired Plant Areas and Pipelinen for a Temperature based LD System A detailed study was conducted by Cygna in 1990 (Referenco No.10) to review the temperature based LD requirements for RCPB piping outside containment. This study identified the room areas out.=3de the containment, and identified the applicable pipe lines in each area. The results (provided here as Attachment B) list the reactor coolant pipe line numbers, the room areas in which they are routed, and the temperature sensors (if any) which are provided. Note that the scope of the Cygna study did not include performing a detailed evaluation of the station's compliance to the LD system requirements.
A summary of the methodology used by Cygna to create this list follows:
I
. The LSCS-USFAR (Reference No.14) sections concerning RCPB leak detection outside containment was reviewed to determine the extent of the
{ } commitments regarding temperature and diff'erential temperature detectors.
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COMMONWEALTH EDISON COMPANY PROJECT NO. 10246-002 PAGE NO. 23 CALCULATION NO. L-001324 Section 5.2.5.1 of the UFSAR states that the LD system will detect, annunciate and isolate (in certain cases) leakages in the following systems:
- Reactor Core isolation Cooling .
- Feedwater Table 5.2.8 of the UFSAR states that the MS, RHR, RCIC (steam), RWCU (hot),
and FW systems are to be monitored with equipment area ambient temperature and differential temperature sensors. The resulting action is to alarm and isolate all appropriate lines, except FW. An alarm alone is required for the FW lines in the MS Tunnel.
. General Electric's Design Specification for tha LD system (Reference No. 20) clarifies the equipment areas specifically required to be monitored with i
differential temperature sensors as follows:
l l l l - RCIC equipment area
- RG;C steam pipe routing area
- RHR equipment rooms
- RWCU equipmer.1 rooms MS line tunnel (to isolate the four MS lines)
- Pipe area between the MS tunnel exit and turbine inlet
. The monitoring commitments of the USFAR and the GE clarifications were translated to P&lDs. The drawings were highlighted to identify the scope of the piping to be monitored for each particular system. Dead-end piping legs to valves normally closed for the operating modes were also included to completely define the pressure boundary. Piping equal to or less than nominal one inch diameter was excluded from the scope of the review to be consistent with the high and moderate energy line break criteria.
. The identified pipelines were highlighted on physical drawings to identify the areas through which they were routed. Since the LD sensors are mostly located in inlet and outlet ventilation ducts, HVAC P&lD ventilation area descriptions were used for identification purposes where ever possible.
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i COMMONWEALTH EDISON COMPANY PROJECT NO. 10246-002 PAGE NO. 24 CALCULATION NO. L-001324 l I 6.4 Temperature Based LD System Scope Exclusions A temperature based LD syetem is technically inappropriate for some reactor coolant pipelines that are outside containment, and can therefore be excluded.
Although not explicitly within their scope, the Cygna study summary (included as Attachment B to this calculation) identifies the appropriateness of a temperature based LD system in the " Leak Detect Iso. Logic." column. Various pipolinesirooms were eliminated from the scope of this calculation based on this assessment.
In ifM1, Sargent & Lundy conducted a study (Reference No. 25) to evaluate what. v* tha 6.0 system in each area was sufficient to satisfy the requirements of the USFAR. The Cygna study was used as the basis for this study. The S&L study identified several areas that did not have an adequate temperature based LD system. However, the conclusion of the study noted that the absence of temperature based LD did not represent a safety hazard but merely an inconsistency with the UFSAR commitment Therefore, recommendations were given to revise and update plant operating procedures and the UFSAR to eliminate these discrepancies.
l ,
Temperature based LD instrumentation may be present in an area but can be l l l interlocked to isolate only one specific pipeline. In 1995, S&L issued LAS-NDIT-l 0072-00 (Reference No. 24) to provide a detailed evaluation of the station's leak detection capt.bility for those plant areas that contain multiple reactor coolant pipelines These areas were checked to ensure that ambient temperature and differential temperature LD monitors with icolation capability were provided for all pipelines in each area.
In conclusion, the thiee studies found that additional plant areas containing reactor coolant pipelines outside containment could be eliminated from the scope of the temperature based LD system. A discussion and summary of these scope
. exclusions follow:
l
. Eipina in Laroe General Areas l
Ambient temperature and differential temperature sensors are intended to be used in " equipment areas" as stated in the UFSAR Table 5.2.8 (Reference No.
14). However, temperature sensors in a large open area such as a plant general area do not provide the same leak detection sensitivity as those in smaller equipment cubicles that are dedicated to the system being monitored. This is because wall heat sink effects, potentially large distances beiween small leaks and the sensors, and the dilution effect of the larger air
( volume and area exhaust will reduce the area temperature rise due to a leak.
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l' I
COMMONWEALTH llDISON COMPANY CALCULATION NO. L 001324 PROJECT NO. 10246-002 PAGE NO 25 l l Consequently the temperature setpoints would need to be set low, leading to undesirst:le spurious alarms and system isolations.
Additionally, when more than one system is located in an area, all systems need to be isolated when only one system is actually leaking sufficiently to warrant an isolation. This is undesirable from an operations viewpoint and would need to be addressed if isolation interlocks were to be added.
Because of inherent problems with thermal LD in large volume areas, the following areas must be eliminated from the temperature based LD system
- scope
- Reactor Building, Elev. 710'-6" & 740'-0" (Reference No. 24)
The reactor building area containing the RHR piping is a wide open space. Temperature based leak detection is not practical.
Both sump monitoring and exhaust radiation monitoring is provided for these areas, therefore, additional temperature I
based LD is not required.
l I - Area Between Primary Containment & CSCS Cubicle, Elev. 673'-
l 4" (Reference No. 24)
Several RHR and RCIC lines are routed in this area that is a wide open space. Temperature based leak detection is not practical.
Both sump monitoring and exhaust radiation monitoring is provided, therefore, additional ternperature based LD is not required.
l
- Turbine Building, Elevation 692'-6" (Reference No. 25)
Several MS lines are routed within the basement of the turbine building. Because this part of the building at elevation 692'-6" and column row S-12 is a wide open space, temperature based i D is not practical. The turbine building contains both sump and visuallaudible system monitoring, therefore, temperature based LD is not required.
- Area Between MS Pipe Tunnel Exit & Turbine Inlets
' ~
The four MS pipes leads exit the MS Pipe Tunnel before 4 connecting ' with the steam turbine. Although not separately identified in the Cygna report (Reference No.10), this pipe area REVISION. NO.
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COMMONWEALTH EDISON COMPANY PROJECT NO. 10246 002 PAGE NO. 26 CALCULATION NO. L-001324 is par 1 of the Turbine Building. The Turbine Building is a large volume space that is inappropriate for a temperature based LD system. Because this area contains both sump and visual / audible system monitoring, additional temperature based LD is not rer, . ired.
e Cold Pipina Systems -
Ambient temperature and differential temperature sensors are only effective when the reactor coolant water temperature within the pipe is above 212 'F.
Sufficient flashing must occur so that the change in area ambient air temperature is great enough to be detected by the temperature sensors.
Pipelines below 212 'F are identified as " COLD" in Attachment B, and are eliminated from the scope of this calculation.
Some additional cold piping exclusions are discussed below:
- RHR Pump / Heat-Exchanger Rooms A & B/C, Elev. 673'-4" l These rooms antain both RHR and RCIC piping. RCIC line No 1R141BA-10 te 1Rl41BB-10 are routed in these rooms. The rooms contain tempecare based LD monitors for isolating the RHR lines, but not the RCIC lines.
The process diagram of the RHR system is shown in Figure 5.4-5 of the UFSAR (Reference No.14). Eight modes of operation are shown.
Process fluid conditions along the various flow paths are also shown.
Based on this diagram, the table below summarizes the process fluid's maximum and rainimuri, temperatures.
MAXIMUd & MINIMUM RHR PROCESS FLUlO CONDITIONS IN THE RHR PUMP / HEAT.
EXCHANGER ROOMS MOO HIN. MAX. MODE DESCRIPTION E TEMP. TEMP.
(T) (T)
A1 40 170 Reactor 30 70 psig.
Pump discharge line to RPV nozzle flooding w/o HX.
A-2 90 180 Reactor at 0 psig.
Pump discharge to RPV nozzle flooding going through HX.
8 212 212 Reactor at 0 psig.
G Pump discharge to containment and suppression pool head ers.
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l COMMONWEALTH EDISON COMPANY PROJECT NO. 10246-002 PAGE NO. 27 q
CALCULATION NO. L-001324 MAXIMUM & MINIMUM RHR PROCESS FLulO CONDITIONS IN THE RHR PUMP / HEAT.
EXCHANGER ROOMS MOD MIN. MAX. MODE DESCRIPTION E TEMP. TEMP.
(*F) (*F) _
D 344 344 Reactor at 110 poig: Mode lasts 20 hrs.
RPV to pump suction for shutdown. Testline to pump suction for shutdown. Pump discharge to head sprey.
E 108.8 120 Reactor at 0 poig.
Pump discharge to RPVs LPCI nonles and Recirc.
Pump's discharge (to jet pumps).
F 40 120 Pump discharge to suppression pool through test line and minimum flow bypass.
G 40 125 Nonctor at 0 poig.
Pump discharge to suppression pool via minimum byr aos line (suction from suppression pool).
344 344 Reactor at 110 psig.
Pump discharge to suppression pool via minimum bypesa line (suction from recirc. loop piping).
8 40 90 Reactor at 1000 poig.
Hot standby.
As shown in the table, there are only two modes (G & D) where process fluid temperatureo are above 212 'F.
- a. Mode G is for the opening of the minimum flow bypass line. When the pumps start, the bypass lina opens until sufficient flow is developed in the system. This mode lasts for only a few (approximately 5) seconds, it is a transitory mode, not a normal operating mode,
- b. Mode D is the Reactor Shutdown Cooling Mode. This mode is used to remove residual heat consisting of decay and sensible heat from the nuclear boiler system after a normal shutdown and cooldown. The auction piping in the pump rooms has a theoretical maximum temperature of 344 'F, at the start of the mode, and a minimum temperature of 125 'F within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> after control rod insertion. Based on the actual performance of the heat exchanger, the temperature would not go beyond 252.5 *F.
The period during which the piping is hot represents only about 0.23% of (8760 Hralyr) of the total operating time.
The Steam Condensing Mode is no longer used (Reference No. 23).
This mode allowfcd cecling of the reactor during shutdown operation O when reactor pressure was below approximately 50 psia, cooling the REVISION. NO.
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COMMONWEALTH EDISON COMPANY PROJECT NO. 10246 402 PAGE NO. 28 CALCULATION NO. L-001324 L
reactor's water to 125 *F for refueling and servicing operations, and diverting part of the shutdown flow for vessel head cooling, in conclusion, the great majority of the time that reactor coolant flows through the RHR piping, fluid temperatures are below the threshold where a temperature based LD system is practical. For most of the modes, fluid temperatures are between 40 and 212 *F. In this temperature range, the flashing percentage of the pipe fluid is very small.
The RCIC pipeline from the MS supply to RHR may be used during Mode D for alternate shutdown cooling. In this mode, the maximum water temperature in the RCIC lines is limited to 200 'F (per Reference No.
< 24) which is below the threshold temperature for using a temperature based LD system.
These rooms contain both sump and exhaust radiation monitors (Reference' No. 24), therefore, a temperature based LD system is not required.
I - Reactor Building, Elev 710'-6" and 740' (Reference No.10)
RHR pipelines in the Reactor Building are part of the Reactor Shutdown Cooling Mode and are downstraam of the RHR heat exchangers.
- According to the UFSAR, the maximum temperature of the lines is 252.5 "F Because cf the low temperature and the rapid (20 hr) cooling of the fluid, a temperature based LD system would not be practical.
These pipelines that are identified in Attachment B by Note 13, were eliminated from the temperature based LD scope, i
- RCIC Pipe Chase, Elevation 710'-6" (Reference No. 25)
This area contains both RHR and RCIC piping. The area is monitored i by RCIC temperature based LD sensors that isolate only the RCIC lines.
An assessment of the ambient and differential temperature LD requirements for the RCIC piping is required and will be provided.
The RHR lines within this RCIC pipe routing area are part of the Reactor Shutdown Cooling Mode. The maximum temperature of the RHR pipelines in this mode is 252.5 *F and occurs only for a short (20 hr) period, therefore, a temperature based LD system for these lines is
[ not practical. Leaks in the RHR piping ares presently detected by I
radiation monitors and CAM.
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l l
- Holding Pumps Cubicle, Elevation, 820'4" (Reference No. 24) ,
1 No hot piping of the RWCU or other systems is routed in this cubicle.
The hot piping identified in the Cygna study (Reference No.10) for this ,
cubicle is routed in the RWCU Ht-Exch. Rooms elevation 786'-6" and the RWCU Pipe Tunnel, elevation 798'-0".
Since this cubicle contains only the cold portion of the RWCU system, installation of a temperature based LD system is not effective and not recommended. The existing LD high differential flow, sump level, and gas monitoring detection systems for this cubicle are sufficient.
- RWCU Heat Exchanger Rooms A & B Elev. 786'-6",and RWCU Valve Rooms A & B Elev. 786'-6", and RWCU Pump Rooms A, B, & C Elev. 761'-0", and RWCU Domin. Room A, B, &C Elev. 820'-6", and RWCU Loop Hold-Up Pipe Room Elev 774'-0" A temperature based LD system was provided in these rooms, O however, it was deleted when the RWCU system design was changed to locate the pumps downstream of the system heat exchangers so that the pumps would not be subjected to high temperature water. This modification was intended to prevent problems with the pump seal design. This system change made temperature monitoring of the now i colder portion of the RWCU system ineffective and prone to spurious l
isolations. Redundant LD was available in these areas through the use ,
of high differential flow, sump level, and exhaust radiation monitoring (per Reference No. 25)
The piping in these rooms has race r tly been revised to reintroduce hot suction to the pumps. This modification was made poesible by utilizing an improved pump seal design. Because instrumentation is already in place, a temperature based LD system can again be used to increase the reliability of the overall LD system. A new design basis calculation (Reference No. 9) determines the new room temperatures during a pipe leak for these rooms.
. Pipelines with Sufficient Redundant LD Systems l
l According to General Design Criteria 54 of 10CFR 50 Appendix A (Reference No. 22), the reactor coolant piping systems outside containment must use O redundant leak detection methodologies. A temperature based LD system is REVISION. NO.
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COMMONWEALTH EDISON COMPANY l CALCULATION NO. L-001324 PROJECT NO. 10246-002 PAGE NO. 30 not required if other redundant LD systems are used. Therefore, the following pipelines are acceptable without a temperature based LD system:
- Area Between Primary Containment & CSCS Cubicle (Reference No.
10)
Redundant LD provisions exist for the RCIC system lines. These pipelines are idenUfied in Attachment B by Note 14. A temperature based LD system is not required.
- RHR Pump / Heat-Exchanger Rooms A & B/C, Elevation 673'-4" (Reference No.10)
Redundant leak detection provisions exist in these rooms for the RCIC system lines 1Rl418A-10 and 1Rl41BB-10. These pipelines are ,
identified in Attachment B by Note 14. An additional temperature c based LD system is not required. j Q
- Radwaste Pipe Hatch (F<eference Nn. 24 and 25) h RWCU line No.1RT06A-4 runs vertically within this shaft from elevation 786'-6" to elevation 749'-0". No temperature leak detection is provided. e C
The current means of leak detection ivr this line is to use sump level, and CAM monitoring, therefore, a temperature based LD system is not i c
required.
in conclusion, based upon a review of the Cygna Report (Reference No.11), the S&L LD system evaluations issued in an NDIT (Reference No. 24), the S&L evaluations issued in a letter / attachment (Reference No. 25), and some new assessments in this calculation, the following plant areas require temperature based LD inonitoring:
. MS Pipe Tunnel- Lower / Upper
. RCIC Equipment Room 673'-4" E,
. l
. RWCU Pipe Tunnel 798'-0" I l
l
. RCIC Pipe Chase 710'-6" l The following rooms utilize LD methodologies other than T and AT, therefore, a E Temperature based LD system is not required. However, because the O t 4 i
REVISION. NO. !
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COMMONWEALTH EDISON COMPANY j PROJECT NO. 10246-002 PAGE NO. 31 CALCULATION NO. L-001324 instrumentation is already in place, temperature based LD is recommended for these areas in order to enhance the overall reliability of the LD system.
. RWCU Heat Exchanger Room A Elev. 786'-6"
. RWCU Heat Exchanger Room B Elev. 786'-6"
. RWCU Valve Room A Elev. 786'-6
. RWCU Valve Room B Elev. 786'-6
. RWCU Pump Room A Elev. 761'-0" o i
. RWCU Pump Room B Elev. 761'-0" $
. RWCU Pump Room C Elev. 761'-0"
. RWCU Domin. Room A Elev. 820'-6"
. RWCU Demin. Room B Elev. 820'-6"
. RWCU Domin. Room C Elev. 820'-6" l
. RWCU Loop Hold-Up Pipe Room Elev 774'-0" 6,5 Reauired LD Temp, Monitorina Areas that Are Evaluated Elsewhere Plant areas identified as requiring a temperature based LD system are eva!usted in the following approved calculations:
. MS Pioe Tunnel - Lower / Upper (Reference No.15)
CECO's Safety Analysis Group in Nuclear Fuel Services developed the justification for the temperature based LD setpoints in a 1996 calculation. ;
This calculation used the GOTHIC computer code. This code was developed by Numerical Applications, Inc., for the Electric Power Research Institute.
GOTHIC is a general purpose thermal-hydraulics computer program for ;
design, licensing, safety and operating analysis of nuclear power plant containment and other confinement buildings. l i
O \
REVISION. NO. !
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Reststum 4
COMMONWEALTH EDISON COMPANY CALCULATION NO. L-001324 PROJECT NO. 10246-002 PAGE NO. 32 I I The MS Pipe Tunnels have a new temperature based LD setpoint that has been approved by the USNRC. Reference No.19 provides the license amendment and revised Technical Specifications as well as the Safety Evaluation to Ceco. The new MS tunnel setpoint requirements for differential temperature, and the deleted setpoint for ambient temperature specified a 100 ppm leakage flow rate (rather than the previous 5 and 25 gpm flow rates).
The winter room air temperature during a pipe leak was calculated to be 151.3 'F. This is the temperature the MS Pipe Tunnels could attain when the ventilation system is out of service. Therefore, the analysis concluded that a single year-round ambient temperature setpoint could not be established based on the 100 gpm leak rate.
The AT calculated for winter and summer is 86.3 'F and 72.5 'F respectively.
The highest AT for the no-leak condition is expected to be 28.2 *F, therefore there is sufficient margin available for temperature differential LD instrumentation.
. RCIC Equipment Room (Reference No. 21) l I The RCIC Equipment Room is evaluated in a 1986 S&L Calculation. The l
analysis was performed both with and without the room coolers in operation, and evaluated the effect of both summer and winter inlet air temperatures. A steady-state mass and energy balance was used to perform the calculation.
No computer programs were used.
1 The input data from this calculation was used to perform additional analyses I which are documented in this calculation. The new analyses are required to investigate the effect of the ambient inlet air flow rate. These analyses are discussed in Section 6.5.
. RWCU Heat Exchanaer Rooms A & B Elev 786'-6".and RWCU Valve Rooms A & B Elev. 786'-6". and i RWCU Pump Rooms A. B. & C Elev 761'-0" and BWCU Domin. Room A. B. &C Elev. 820'-6" and RWCU Loop Hold-Up Pipe Room Elev 774'-0"(Reference No. 9_) g l
The RWCU piping in these areas has been recently revised. The design i change resulted in a potential for high energy leakage into areas that previously contained only subcooled, nonflashing lines. The piping is analyzed in a S&L Calculation (Reference No. 9). This calculation uses q essentially the same methodology and spreadsheet which is documented in REVISION. NO.
01 a.-u -u-c mc 4
i
i COMMONWEALTH EDISON COMPANY CALCULATION NO. L 001324 PROJECT NO. 10246-002 PAGE NO. 33 this calculation. Ambient temperature, and differential te6nperatures for a temperature based LD system , are calculated.
The HVAC. supply air for all the rooms except for the RWCU Heat Exchanger i Rooms A/B is shut off by a leakage rate of 25 gpm. Once this occurs, the !
room environment will be 100% saturated steam. The analytical limit is therefore 212 'F, regardless of the normal supply air temperatures considered. Some conservatism is offered by this limit, since heat input from _
the piping and equipment within the room is neglected.
- RWCU Heat Exchanger Rooms A & B Elev. 786'-6" The 5 gpm pipe leakage alarm limit is based on a summer differential ,
temperature response of 24.6 'F and an ambient temperature of 128.6
'F. This limit will be reached by AT measurement with a 4.3 gpm leakage rate in the winter. In the event the leak occurs in a non-operating heat exchanger room, this limit will be reached by. AT measurement with leakage rates of 17.0 gpm and 13.6 gpm for the summer and winter. The limit is not lowered based on a consideration i
of these cases because the probability of false alarms when the i
exchanger is in operation would be increased ; J
- RWCU Valve Rooms A & B Elev. 786'-6"
. The 5 gpm pipe leakage alarm limit is based on a summer differential temperature response of 24.6 'F and an ambient temperature of 128.6
' F. This limit will be reached by AT measurement with a 4.3 gpm leakage rate in the winter, in the event the leak occurs in a non-operating heat exchanger room, this limit will be reached by AT measurement with leakage rates of 17.0 gpm and 13.6 gpm for the summer and winter. The limit is not lowered based on a consideration of these cases because the probability of false alarms when the exchanger is in operation would be increased RWCU Pump Rooms A, & C Elev. 761'-0" The alarm limit is based on a summer differential temperature response of 32.4 'F and an ambient temperature of 136.4 'F, which provides the l bounding case for 5 gpm leakage in an operating pump room. This limit l will be reached by AT measurement with a 4.1 gpm leakage rate in the winter, in the event the leak occurs in a non-operating pump room, this limit will be reached by AT measurement with leakage rates of 10.2 REVISION. NO.-
01 am. _ _ a m.oc g4 Revistam e
4 CCMMONWEALTH GDISON COMPANY CALCULATION NO. L-001324 PROJECT NO. 10246-002 PAGE NO. 34 gpm and 8.0 gpm for the summer and winter, respectively. The limit is not lowered based on a consideration of these cases because the probability of false alarms when the pump is in operation would be increased.
- RWCU Pump Room B Elev. 761'-0" The 5 gpm pipe leakage alarm limit is based on a summer differential temperature response of 41.0 *F and an ambient temperature of 145.0
'F. This limit will be reached by AT measurement with a 3.9 gpm leakage rate in the winter.
- RWCU Demin. Room A, B, &C Elev. 820'-6" The 5 gpm pipe leakage alarm limit is based on a summer differential temperature response of 44.5 'F and an ambient temperature response of 148.5 'F. This limit will be reached by AT measurement with a 3.8 gpm leakage rate in the winter.
l l
- RWCU Loop Hold Up Pipe Room Elev 774*-0" C
The 5 gpm pipe leal: age alarm limit is based on a summer temperature response of 40.8 'F and an ambient temperature of 144.8 'F. This limit i 8
will be reached by AT measuremont with a 3.9 gpm leakage rate in the winter.
The calculatio'n details are not repeated here, however, for completeness, their results are summarized below:
LEAK DETECTION ISOLATION PLANT AREA RCF.
NO.
AMBIENT T DIFFEREN. AMBIENT T DIFFEREN.
('F) TIAL T (*F) (*F) TIAL T ('F)
Ms Pipe Tunnel- 15 Deleted 72.5 Deleted Deleted Upper / Lower RWCU Heat 0 128.6 24.6 159.8 41.8 Exchanger Rooms A/B 786'-6" RWCU valve Rooms 9 128.6 24.6 159.8 41,8 A/B 786' 6" REVISION. NO.
01 ca.-mone tan
. 4=.
COMMONWEALTH.RDISON COMPANY l
PROJECT NO. 10246-002 PAGE NO. 35 i CALCULATION NO. L.001324 LEAK DETECTION ISOLATION PLANT AREA REF.
NO.
AMBIEN T T DIFFEREN. AMBIENT T DIFFEREN-('F) TIAL T ('F) (*F) TIAL T ('F) -
3U Pump Rooms 9 136.4 32.4 212.0 94.0 A/C 761' 0" O RWCU Pump Room B 9 145.0 41.0' 212.0 94.0 -
761'0 $
cc RWCU Domin Room 9 148.5 44.6 212.0 94.0 A/B/C 820'-6" RWCU Loop Hold Up 9 144.8 40.8 212.0 94 Pipe Room 774'-0""
6.5 LD Monitorino Areas that Must Be Evaluated in This Calculation Temperature calculatio a will be performed for RCIC Equipment Room (elevation 673'-4"), the RCIC Pipe Chase (elevation 710'-6") and the RWCU Pipe Tunnel
{ (elevation 798'-0"). A discussion of the calculations follows.
i
. Steady State Control Volume Room / Area Model The following diagram shows the room model used for this calculation. The model is based on the assumption that the exhaust air flow (Q 4) remains constant (i.e., the same flow occurs during a pipe leak as when no pipe leak is occurring). The heat loads of the internal piping is conservatively taken as Zero.
NO LEAKAGE:
Oi, Ti, mi, mi, vi , hi Q4, T4, m4, m4, v4.h4 Heat Load (HL), Btu / min l
j O REVISION. NO.
01 euc-== a --- g Resummm 4 l
COMMONWEALTH EDISON COMPANY CALCULATION NO, L-001324 PROJECT NO, 10246-002 PAGE NO. 36 l l l LEAKAGE:
Qi = Qi- FQu iv N, g O,V mee hc f Qi = Q.
m/ = m.
mi = (Qi- FQtvi/v,)/vi
- T/,et,v/,h/
Ti. mi, vi h,
- Heat Load (HL), Blu/ min :
~
,, HEAT IN = HEAT OUT Condensate and unflashed liquid (assume heat loss = 0)
. Heat Balance for Steam Leakaae For steam leakage, a energy heat balance is performed for the control volume as follows:
Ere Neloy in (per minute) = Enthalpy out (per minute)
Vi g,. 9 Vi g,_ G h , + m s, h a + HL -
y, h.
r s , s From this equation, exhaust enthalpy can be calculated by:
- h. = h, +
'A'^'+E A 0, Ot M Where A- I is reduced inlet air mass flow rate, q ,
M REVISION. NO.
00 e.--- _a--- .c 4
l l
COMMONWEALTH E,DISON COMPANY l PROJECT NO. 10246-002 PAGE NO. 37 CALCULATION NO. L 001324
. Heat Balance for Liauld Leakaan An energy balance for liquid leakage is performed as follows:
Enthalpy in (per minute) = Enthalpy out (per minute)
/7,+ # ' I' + = h.
A A v,
G, FQe Whero ,t .
V/ : is reduced inlet air mass flow rate, v,
and F is the flash steam percentage defined as:
F=hi h i h,- hi
{ l If the calculated F is less than zero, the spreadsheet program sets F equal to zero. This means that no flashing occurs and all of the leakage is liquid, if l
the calculated F is greater than 1, the spreadsheet sets F equal to 1. This
- means that the pipe leakage is purely steam.
. Exhaust AlfTemperature (T) Calculation.
Using exhaust air enthalpy (h4 ), the exhaust air temperature (T4 ) can be determined from the following expression:
Total Enthalpy = Dry Air Enthalpy + Vapor Enthalpy
- h. = h., + o.24(T. - T) + h,.m. (from reference No. 32) 1 = T, + h. - h,i h, m.
on f
where, g,= A l
O REVISION NO. -
00
..am - -
.~.
i
! COMMONWEALTH EDISON COMPANY PROJECT NO. 10246-002 PAGE NO. 38 d CALCULATION NO. L.001324
. Room Differential Temperature (AT) Calculation The differentir.1 room temperature is found by subtracting the initial ambient air temperature of the room from the calculated final room temperature after the pipe leak occurs.
AT = T4 - Ti .
' . RCIC Pipe Chase. Elevation 710'-6" i
The calculations were performed using the Excel Spreadsheets included in Attachment F. The cell formulas used by the spreadsheet are shown in Attachmrt G.
The RCIC Pipe Chase inlet and exhaust ventilation air flow rate is 300 SCFM.
The RCIC pipelines contain saturated steam (P = 1264 psia, T = 575 'F). If eithei design leak rate occurs (5 or 25 gpm), the inlet air flow rate would be reduced to zero at steady state conditions because the rate of venting steam would exceed the flow rate of air out of the pipe chase. For this case, the j g steady state room temperatute is simply found from the enthalpy of the venting steam. The pressusized steam would auperheat as it expands and heats the room air to 280 'F (based upon the steam's 1183 Btullb enthalpy).
The current Technical Specification (Reference No. 33) ambient tamperature analytical (allowable) setpoint for isolation is 206 'F. The spreadsheet shows that this will result in a pipe letk rate of 1.33 gpm which is below the ,
allowable leak rate of 25 gpm. The current Technical Specification c differential temperature analytical setpoint for isolation is 123 'F. The g spreadsheet shows that this will result in a pipe leak rate of 1.12 gpm which is a below the allowable leak rate of 25 gpm. Therefore, the current Technical Specification analytical setpoints for system isolation in the event of a pipe leak, do not need to be revised.
A reasonable "detectinn" temperature v'ould be 145 'F. This value is 27 'F cbove the summer inlet air temperature. This temperature would have sufficiant margin wita the no-leak room temperatures for determining T and AT setpoints. Note that this temperature setting will detect a very small 0.27 gpm leak (based on summer inlet air temperatures).
In summary, the following temperatures are recommended for LD design in the RCIC Pipe Chase (elevation 710'-6"):
REVISION. NO.
01
= --mm .oec yc Rasemam e
1 l
COMMONWEALTH E.DISON COMPANY PROJECT NO. 10246-002 PAGE NO. 39 CALCULATION NO. L-001324 l l LEAK DETECTION ISOLATioh PLANT AREA AMBIENT T DIFFEREN. AMBIENT T DIFFEREN.
('F) TI AL T (*F) ('F) TIAL 1 ('F)
RCIC Pipe Chase 145 l 27 20608 188ni l E' i
(1) CurrentTechnical specrcauon Temperature Setpoint $
. R_CIC Eauipment Room. Elevation 673'-4" The RCIC Equipment Room was analyzed in a 1966 S&L Calculation (Reference No. 21). The analysis was pesformed both wi'.h and without the room coolers in operation, and evaluated the effect of botn summer and winter inlet mir temperatures.
l The room coolers are designed to operate when the room pumps are operating. This is a very short perrod of time. The normal operating condition is with the room coolers off. According to the GE LD design guidelines (Reference No. 20), the LD setpoints should be based upon normal operating l
I G conditions. Therefore, the mode with room coolers on will be ignored.
l The design air ventilation flow into the RCIC Equipment room is 3718 scfm (Refarence No. 21). In actuality, the ventilation air flow through this space is negligible since the flow goes to the room above at 694'-0". In addition, when a pipe leak occurs, the inlet air flow would be reduced proportionately (as i described in Section 3.0). Therefore, the results from the 1986 calculation will not be used since the analysis assumed that the inlet and outlet e!r flows into the room remain at a constant 3718 scfm.
New calculations were performed to examine the effect of different inlet air flows. The calculations were performed using the Excel spreadsheets ,
included in Attachment F. The cell formulas used by tue spreadsheet are i l shown in Attachment G. One set of analyses reduces the inlet air flow I
proportionately with the size of the pipe leak. The second set of ans. lyses looks at the case where the inlet air flow to the room is zero. haducing the I inlet air flow results in higher room temperatures when a pipe lea'< occurs. , ;
The more conservative case is the one with higher inlet air flows since this t '
will result in the implementation of luwer temperatur3 LD setpoints.
Therefore, the analyses with the inlet air flow reduced to zero are s.. ewn for i information only, and will not be used to determine the temperature base ' LD setpoints.
REVISION. NO.
01 ,
am - - no-s.=4 Ramesamm e
l COMMONWEALTH EDISON COMPANY PAGE NO. 40
' CALCULATION NO. L 001324 PROJECT NO. 10246-002 I I The current Technical Specification (Reference No. 33) ambient temperature analytical (allowable) setpoint for isolation is 206 'F. The spreadsheet shows that this will result in a pipe leak rate of 13.33 gpm (winter case) which is below the allowable leak rate of 25 gpm. The current Technical Specification differential temperature analytical cetpcint for isolation is 126 'F. The spreadsheet shows that this will result in a pipe leak rate of 14.57 gpm ,-
(summer case) which is below the aliowable leak rate of 25 gpm. Therefore, the current Technical Specification analytical setpoints for system isolation in the event of a pipe leak, do not need to be revised. E a:
The reco nmended "oetection" setpoint foi a 5 gpm leak rate based on ambient air temperature is 131.5 'F (winter case). The spreadsheet determined that the " detection" differential temperature should be 52.5 'F (summer case). These temperatures would have sufficient margin with the no-leak room temperatures foi determining T and AT setpoints.
The results of the different analyses are summarized below:
LEAK ['ETEcTION ISOLATION
- ANALYSIS CASE LEAK RATE.
(gpm) AMDIENT DIFFEREN- AMBIEir OlFFEREN T ('F) TI AL T (*F) T('F) -TI AL T
(*F)
Without Room WINTER 131 61 294 224 Coolers Qin Reduced SUMMER 166 62 300 196 Without Room WINTER 304 234 344 234 Coolers Q1= 0 SUMMER 304 200 304 200 (for info only)
As shown above, the most conservative calculation results for determining the setpoints, is the case with reduced inlet air flow. Therefore, the following design temperatures are recommended:
9 REVISION. NO.
01 'l E shMr C 84MMMP4 M 3 W 4
1 COMMONWEALTH EDISON COMPANY j l
PROJECT NO. 10246 002 PAGE NO. 41 CALCULATION NO. L-001324 1 LEAK DETECTION ISOLATION PLANT AREA AMalENT T DIFFEREN- f.MSIENT T DIFFEREN.
(*F) TIAL T ('F) ('F) TIAL T (*F)
RCIC Equipment 131 62 206m 126m O Room (6 73'-4") g m
(1) current Technical spectrication Temperature setpoint
. RWQU Pine Tunnel. Elevation 798'-0" Currently, there is no temperature based LD instrumentation dedicated to the RWCU Pipe Tunnel, however, the room contains a sump level monitorinc system for leak detection.
Temperature based LD sensors which are used for protecting the RWCU Heat Exchanger Roomis A/B (elev. 786'-6") are located in the RWCU Pipe Tunnel l (per Reference No. 25). These sensors use a reference temperature outside the RWCU pipe area to calculate differential ventilation air temperature.
I I I These sensors will alac provide prc,tection for the RWCU Pipe Tunne!.
The RWCU Pipe Tunnel inlet and exhaust ventilation air flow rate is a high 7650 SCFM. The existing temperature LD sensors are not located at the room ventilation discharge. Therefore, when a pipe leak occurs in the tunnel ,
the sensors will not become effective until the pipe leak rate reaches a level o which 4 huts off the ventilation air flow, and steam completely fills the tunnel. S Calculations were performed using the Excel Spreadsheets included in E Attachment F to determine the " shut off" ventilation flow rate. The cell formulas used by the spreadsheets are shown in Attachment G. The spreadsheets determined that a pipe leak rate of 166 gpm is necessary before the ventilation air flow will be shut off.
I Until the pipe leak rate reaches 166 gpm, the LD system in the RWCU Pipe Tunnel is believed to be adequate for the following reasons:
- The steam will be exhausted by the room ventilation system out of the ventilation stack. Therefore, it is not released to any general plant areas. The radiation monitors in the ventilation stack would identify a pipe leak below 166 gpm in the RWCU Pipe Tunnel.
- Redundant LD is required in " equipment areas. There is no safety I related equipment in the RWCU Pipe Tunnel." This area only contains
! REVISION. NO.
01 l
- = = - g Res: mum 4
COMMONWEALTH EjDISON COMPANY PAGE NO. 42 CALCULATION NO. L-001324 PROJECT NO. 10246-002 piping. Therefore, a pipe leak will have no significant eMect on plant operation or safe shutdown.
- The piping ciontains water from downstream of the domineralizers which is being returnnd to the feedwater system. Therefore, any e C
radiation released due to a pipe leak is minor due to the reduced radiation activity level of the fluid at this locati m, and should not affect !
8 oN site doses. .
- The room contains a sump monitoring LD system which will detect leak rates below 166 gpm.
. Marains The calculations of temperature and differential temperature are to be used for c etermining the LD thermcl instrumentation setpoints. Suitabit: margins should be applied depending upon the uncertainty, sensitivity and accuracy of the instrumentation, in determining the setpoints. The calculation of the margin between the calculated T and AT and the actual instrumentation A setpoints is not in the scope of this calculation.
g if measurement uncertainties are greater than the differenca between the calculated winter leak air temperature and the summer no-leak air tamperature, then a temperature based LD system cannot be used.
l l
l l 7,0
SUMMARY
AND CONCLUSIONS l
The assessment of the LD requirements for each room and pipeline is based upon the findings, conclusions, and recommendations contained in the 1990 Cygne study (Reference No.10), the 1991 S&L LD evaluation (Reference No. 25) and the 1995 S&L NDIT (Reference No. 24). A new evaluation of the rooms and pipelines was not conducted in this calculation. The evaluations contained in these references are assumed to be valid since S&L hcs determined that the approved referenced I results/ conclusions are appropriate as design input to this calculation. This calculation assumed that no significant room, pipi ig, or instrumentation changes l have occurred since the 1995 assessment (Reference fJo. 24), with the ' exception of changes evaluated in the new RWCU calculation (Reference No. 9). This -
assumption should be verified. If any changes are found to have occurred since the 1995 evaluation, they should be incorporated in Revision 2 of this calculation.
An NDIT containing some RCIC Pipe Chase input data has not yet been received.
- This calculation was prepared using values for inlet air humidity and winter and REVISION. NO.
01
--u .mc san.4
. . . ~ _ . , , . - _ _ . . _ . _ _ ._ . _.. . , , .
GOMMONWEALTH EDISON COMPANY CALCULATION NO. L-001324 PROJECT NO. 10246-002 PAGE NO. 43 summer inlet air temperatures which are believed to be reasonable and which should envelope those reported in the NDIT. If the NDIT values are found to differ ,.-
greatly from those used in this calculation, the spreadsheets included in o Attachment F will be rev ued, f a:
7.1 Plaint Areas Containina RC Pipelines Outside Containment Attachment B from the Cygna report (Reference No.11) is a complete listing of all pipelines containing reactor coolant that are routed outsHe the containment The plant areas containing the piping was identified. Based upon this listing, the following 30 unique plant areas were identified. These identifiers are consistent with the descriptions used in References 10, 24, and 25, and therefore minimize potential ambiguity due to renaming plant areas. A cross reference for the room names found in the reference documents is included as Attachment A.
. Reactor Building - North 710'-6"
~
. Reactor Building - South 710'-6"
. Reactor Building - East 740'-0"
. Reactor Building - West 740'-0"
. React.v Building - East 761'-0"
. Reactor Building - West 761'-0"
. RWCU Loop Hold-Up Room 774'-0"
. RWCU Phase Sep. Tank Cubicle
. Holding Pumps Cubicle 807'-0"
. Area Between Primary Containment & CSCS Cubicle
. Precoat Tank Room 820'-6"
. RWCU Heat Exchanger Room A 786'-6" l
- . RWCU Heat Exchanger Room B 786'-6" 1
. RWCU Valve Room A 786'-6" REVISION. NO.
01 l a mm-s aa.a
, - _ _ - .. - = - - - .-
COMMONWEALTH EDISON COMPANY PROJECT NO. 10246-002 PAGE NO. 44 CALCULATION NO. L-001324
. RWCU Valve Room E 786'-6"
. MS Pipe Tunnel- Lower / Upper
. RCIC Equipment Room 673'-4"
- RCIC Pipe Chase 710'-6" -
. RHR Pump / Heat & changer Room A 673'-4"
. RHR Pump / Heat Exchanger Room B 673'-4"
. Radwaste Pipe Hatch 735'-0"
. RWCU Domineralizer Room A 820'-6"
. RWCU Domineralizer b'm B 820'-6" l
g . RWCU Domineralizer Room C 820' 4"
. Turbine Buildin2
. RWCU Pump Room A 761'-0"
. RWCU Pump Room B 761'-0"
. RWCU Pump Room C 761'-0"
. Pipe Area Between the MS Tunnel Exit & Turbine inlet
. RWCU Pipe Tunnel 798'-0" l
l 7.2 Plant Areas Which Reauire LD Honitorina Based upon a review of the Cygna Report (Reference No.11), the S&L LD system evaluations issued in an NDIT (Reference No. 24), the S&L evaluations issued in a l
letter / attachment (Reference No. 25), and some new assessments in this l
calculation, the following plant areas require LD monitoring:
C l REVISION. NO.
l e c =-- un.uoc ge Essessen e
COMMONWEALTH EDISON COMPANY
\
PROJECT NO. 10246-002 PAGE NO. 45 :
CALCULATION NO. L 001324 l
(.
l
- MS Pipe Tunnel- Lower / Upper
.- RCIC Equipment Room 673'-4"
. . RWCU Pipe Tunnel 798'-0"
. RCIC Pipe Chase 710'-6" The following rooms utilize LD methodologies other than T and AT, therefore, a Temperature based LD system is not required. However, because the e instrumentation is already in place, temperature t.ased LD is recommended for these arsas in order to enhance the overall reliability of the LD system. * {:
i
. RWCU Heat Exchanger Room A Elev 786'-6"
. RWCU Heat Exchanger Room B Elev. 786'-6"
. RWCU Valve Rooin A Elev. 786'-6 g . RWCU Valve Room B Elev. 786'-6
. RWCU Pump Room A Elev. 761'-0"
. RWOU Pump Room B Elev 761'-0" l
. RWCU Pump Room C Elev. 761'-0" l
. RWCU Domin. Room A Elev. 820'-6"
. RWCU Domin. Room B Elev. 820'-6" {
. RWCU Domin. Room C Elev. 820'-6" )
. RWCU Loop Hold-Up Pipe Room Elev 774'-0" 7.3 Room PiDe Leak Temoerature Calculations j l
Calculations have previously been performed for some of the areas that require a temperature based LD system. The results of these temperature calculations are l
j s summarized here:
(
j REVISION. NO.
01
. \
l auswarnow^ = e v_~
.~.
COMMONWEALTH EDISON COMPANY PROJECT NO. 10246-002 PAGE NO. 46 CALCULATION NO. L-001324 PLANT REF, LEAK OETECTION ISOt ATioN (1) TECH. SPEC.
ISOLATION (CURRENT SETPolNTS)
AREA NO. AMBIENT DIFFER. AMBIENT DIFFER.
ENTIAL T T ('F)
DIFFER.
ENTIAL l AMBIENT T ('F) ENTIAL T T ('F)
('F) T('F) ('F) 72.5 Deleted Deleted Deleted 70 MS Pipe Tunnel is Deleted j
. Upper / Lower RWCU Heat 9 128.6 24.6 '159.8 41.8 187 91 Exchanter Rooms NB 786'.
4" RWCU Valve 9 128.6 24.6 153.8 41.8 None Nona Rooms NB 786'.
4" RWCU Pump 9 136.4 32.4 212.0 M.0 None None Rooms NC 761'.
0" RWCU Pump 9 145.0 41.0 212.0 M0 None None l
Room B 761'-0" l RWCU Domin. 9 148.5 44.5 212.0 M.0 None None Room NB/C 820'-0" [
O RWCU Loop Hold Up Pipe Room 774'-0" 9 144.8 40.8 212.0 M.0 None None C
i (1) Technical Spectricauon Setpoints shown are " analytical" or "aliowable" values As shown in the above table, the following changes to the LaSalle Technical Specification (Reference No. 33) are recommended:
e Revise the RWCU Heat Exchanger Room A/B ambient temperature setpoints for system isolation to 160 'F.
. Revise RWCU Heat Exchanger Room A/B differential temperature setpoints for system isolation to 42 'F.
e Add new ambient temperature (42 *F) and differential temperature setpoints (160 'F )for the RWCU Valve Rooms A/B (786'-6"), RWCU Pump Rooms AlC (761'-0"), RWCU Demineralizer Rooms A/B/C (820'-6") and the RWCU Loop Hold-Up Pipe Room (774'-0")
New calculations were performed for the RCIC Pipe Chase 710'-6" and the RCIC l p Equipment Room 673'-4". The results are:
V REVISION. NO.
01 l
t nemmmmmum
- _nas.3 e.
l
COMMONWEALTH EDISON COMPANY CALCULATION NO, L-001324 PROJECT NO. 102464 02 PAGE NO. 47 G
PLANT LEAK DETECTION ISOLATION WTECH. SPEC.
ISOLATION (CURRENT SETPolNTS)
AREA AMBIENT DIFFEREN. AMBIENT DIFFEREN. AMBIENT DIFFEREN.
T (*F) TIAL T ('F) T ('F) TIA,L T (*F) T (*F) TtAL T ('F)
RCIC Pipe 146 27 206 *86 206 186 Chase 710'.4" RCIC 131 52 206 126 206 126 Equipment Poom 673' 4" (1) Technical Specification Setpoints shown are "analytJeaf" or " allowable" valuss As shown in the above table, no changes to the Techniul S. 'cifics*Lan are required for the RCIC Pipe Chase or the RCIC Equipment Roon.. l Operating mode changes have occured with the RHR piping. Therefore, the following changes are recommended to the Technical Specification:
. The Steam Condensing Mode is no longer used. Delete the isolation setpoints 9 for ambient temperature and chfferential temperature for the RHR Steam Condensing Mode.
. During the Shutdown Cooling Mode, the reactor coolant fluiu temperature is below the threshold temperature for using a temperature based LD system. )
Delete the isolation setpoints for ambient temperature and differential temperature for the RHR Shutdown Cooling Mooe.
The calculations of temperature and differential temperature are to be used for determining the LD thermal instrumentation setpoints. Suitable margins should be applied deponding upon the sensitivity and accuracy of the instrumentation, in determining the setpoints. The calculation of the margin between the calculated T and AT and the actual instrumentation setpoints is not in the scope of this !
calculation. l The following documents are superseded by this calculation:
. LI-01, Rev. O, Calcuiat on for Temperature Sensor Set Points for Main Steam 1 Tunnel Leak Detection.
. LI-02, Rev. O, Calculation for Temperature Sensor Set Points for RCIC Steam l p
V Tunnel Leak Detection. l I
REVISION NO, 01
. -u.u=c rm c Esseseen 4 i
COMMONWEALTH EDISON COMPANY CALCULATION NO. L 001324 PROJECT NO. 10246-002 PAGE NO. 48 FINAL
. Ll 03, Rev. O, Temperature Sensor Set Point Verification for Main Slesm Tunnel.
. LI-04, Rev.1, Set Point Verificadon for Main Steam Tunnel.
. LI-05, Rev.1, Set Point Ver'ficadon for RWCU Equipment Rooms.
. Ll 06, Rev. O, Set Point Verification for RHR Pump Rooms
. Ll.07, Rev. O, Set Point Verification for RCIC Equipment Rooms
. Ll.08, Rev. O, Set Point Verification for RCIC Pipe Tunnel 0.0 ATTACHM.ENIS Total No.
- of Paaes A. Area Definition Cross Reference 2 l
B. Areas Containing Reactor Coolant Pipelines outside of 13 Containment (From Reference No.10)
C. Excerpt from 1991 S&L Letter / Attachment - 9 o Temperature Based LD System Evaluation (Ref. No. 25) g' a:
D. Excerpt'from 1995 S&L NDIT -Temperature Based LD 6 Evaluation (Reference No. 24)
E. Summary Table of Temperaiure Based LD System 17 Pipelines / Area Evaluations F. Spreadsheet Calculations of Ambient Air Temperature 9 sad Differential Temperatures for a LD System G. Spreadsheet Cell Formulas used in Attachment F. 3 l
I 9 l i
REVISION. NO.
l 00 s.a - - ,.m, -
l _ _,_ ., - - _ . . - ~
- -- ^
l 1
, Calc. No.: L 001324 Proj. No: 10246 002 l Rev.: 00 l Page A1 ,
p f
ATTACHMENT A Area Definition Cross Reference l
O
b, v l
I !
I J
ATTACHMENT A 1 AREA DEFINITION CROSS REFERENCE i i
PURPOSE; THE THREE REFERENCE DOCUMENTS USED N THis c M.CULATION USED SUGHTLY DIFFERENT TITLES FOR THE AREAS BENG EVALUATED TMS IND CONFUSION AS TO WHICH AREA *S BENG DtSCUSSED UtstT-1 GEleERAL AREA COORD IDElsTIFIEft M TletS CALC 1pLA79088 ELEV. MVAC PSIO DESCRIPTIOct ROWS (REFEftEIBCE leo.teg (stEFEREleCEleO.S 24 & 251 ,
Reactor enM 4. R ^= k_^^ g -North 710E {
71UE D-14 71GE RB NORTH Reeder * ^ , N este D-1G 710E RB SOUTH Reedor 5_P g S sute Reedor tue, v 4_ Reactw 5 Sandre 710C 21(7 M Roerfor h44.,- East 7C&
Reedor '_^*=ig E ease Reedor EJ ., e ; _ ,
747& B-12 747F RB EAST Reactor tnaheng - West 747&
747& H-10 MTV RB WEST Reedor P_ ^ ^ 4 W skee Resc$a 5_-.^ ,v. - el. -
Reedor tusserg E suse Reedor 5 - ' g re areas Reedor NA- , - Eew 761*&
^
i 761* & B-14 TSr# RB EAST Reedor k+esig W suse Reedor knadeng gentw . Reedor b_-^ ,-Wut 76TE j 76TV G-10 76rV RB WEST RWCU loop hoidaJp ppo room - 7T4&
774 & H-13 774& RWCU RM Cloen up loop he"w ppe -.. Cloenup loop f*? ppe -.. I Clos A Wy ppe room t i RWCU g.; sep ter* cutade ,
j 80T& H-10 80TV RWCU SEP TN Cloen g pheme sep ter* ch*= '
Hektrig p mn murto Hopeng purgs cut scle - GOTE i 837E G-12 637E RD PP CUB Hokr-;;;; .mcutado B-13 AREA BTWN PC&CSCS Area tismusen .. y cort & CRCS cuh Aree tishmeen ,...-1 cortseimert & CSCS (cutscle) Aree bahneenr..-r cortesimert & CSCS cutacle [
) (JJ# Procost ter* room - 837E 837E G-11 FD PRECOAT TK RM Reedor' M useetsute Roodor InJ.,^ g w iel s l' Non reg & reg host each SW RWCU heat ends toern A - 78EE 786'E G-11 HXaRM Non reg & reg heat entit NW RCWU heet ends room 3 - 785E l
' 78 6-6" G-13 HX B RM Upper & tommer steem peo tunnel (Upper & loser) MS ppo tunnel MS ppe tunriet -lonerA,v ;
VTJ# L-12 MS PIPE TUNNEL LPCS east sute RCIC - , .._ rooms RCIC og.v . ^ room - 675-4" t.75 # B-14 NCIC EQ RM Ppo chose . ^^. suse Pye diese rierth suse i RCIO ppe T; aree RCIC ppe chose - 710-6" 710E C-13 RCIC PIPE RA i RHR PP A RM RHR host ese:h cutado N sute RHR hast A ;- (ciescle) RHR p.. A 4M .-.. A - 6TJ#
tOTJ E H-14 RHR pn. ,.^ ;4mch .-.. BC - 675-4" I
L77# B-10 RHR PP BJC RM RHR host ed ne=rm S suse RHR best b, ;-. . (c'tude) ,
Re:Semele ppe herch - 737& f T.f?& S11 RWASTE PIPE HATCH Aust wrtscal shaft unt-1 N pape hatch (or sh&O RWCU DEMIN RM A RWCU flRer ciescio el 837-8* RWCUha -^.~. RWCU demsn voorn A - 837F 637 s H-11 l RWCU DEMIN RM B RWCU Ilber cutucto et 837E RWCU v=mert rooms RWCU demri room B - 837&
837E H-12 RWCU DEMIN RM C RWCU flRer ne=rh el 837-6" RWCU ==-- --- t . .,, . RWCU domes room C - 837 &
837M H-13 Vehe room SW sette el 79&M RWCU iehe .-. RWCU who room A/B - 786E 78FM H 11/12 RWCU nVRM Tartene R ^ g Turtune 5-- ^ g Turtune tm4.r g l 892 & S-12 TURB BLDG Clean up recyc pJg ctesche W sute RWCU purg room RWCU pianp room A - 761*& l 761* & G-12 8 RWCU PP A RM Cleon g recirc purg cutmete W su$e RWCU purry .-.. RWCU y ., room B - 761*&
761*& G-13 RWCU PP B RM RWCU% voam RWCU purg reorn C - 761*& gy j 761*& G-14 RWCU PP C RM C3een up redrc ,.r, cutade W srto
. . Pipe eres behusen the MS timanal est & turtene ardet Pipe eres behusen the MS tunnel eut & brtune ettet !
79 5 & H.11/13 Pyetunnel Pye tunnel RWCU pee tunned - 79Er& l-l RWCU Vsfue Room 80T& RWCU Vehe Room - 80T& i O' l 80TV 412 - -
Calc. No.: L-OO1324 Proj. No: 10246-002 Rev.: 01 j
i Page A2 Final l
_ _ - . .J
l Calc. No.: L-001324 Proj. No: 10246 @ 2 ,
Rev.: 00 i Page B1 .
O .
i
. 1 1
f :
O
^TracHusar a Areas Containing Reactor Coolant Pipelines Outside of Containment (from Reference No. 25)
O
. . - ~ , . . . , . . _ . . . . _ _ _ . . , . _ . . _ _ . , _ _ _ _ . . . _ , _ . _ . _ _ . . , . _ . . . _ _ _ . - _ _ _ . - , _ . _ . _ _ _ , _ _ _ _ _ _ _ _ . . . . _ . _ . _ _ _ _ . _ . . _ _ _ _ . _ . . - . _ _ , _ _ _ _. -
Calc. No.: L 001324 Proj, No: 10246 @ 2 ATTACHMENT 3 SORT SY AREA /ROCM PAGE i Rev.: 00 Page B2
(] AREA / LINE LEAK DETECT.
't) ROOM NUMBER ISO. icGIC 710-6 RB NORTH 1RH03BA-12 NONE, NOTE 13 710-6 RB NORTH 1RH03BB-12 No!!E , NOTE 13 710-6 RB NORTH 1RH03CA-12 NONE, NOTE 13 710-6 RB NORTH 1RH34A-6 No!!E , NOTE 13 710-6 RB NORTH 1RH39AA-4 NONE, NOTE 13 710-6 RB NORTH 1RH40AA-12 NONE, NOTE 13 710-6 RB NORTH 1RH40CA-16 NONE, NOTE 13 710-6 RB NORTH 1RH41AA-3 NONE, NOTE 13 710-6 RB NORTH 1RH41AB-3 NONE, NOTE 13 710-6 RB NORTH 1RH59AA-16 NONE, NOTE 13 710-6 RB NORTH 1RH70A-3 NONE, NOTE 13 710-6 RB SOUTH 1RH03CB-12 NONE, NOTE 13 710-6 RB SOUTH 1RH33A-16 NONE, NOTE 13 710-6 RB SOUTH 1RH39AB-4 NOME, NOTE 13 710-6 RB SOUTH 1RH40CB-16 NONE, NOTE 13 740-0 RB EAST 1RH33A-16 NONE, NOTE 13 740-0 RB EAST 1RH40CB-16 NONE, NOTE 13 740-0 RB EAST 1RH41AA-3 NONE, NOTE 13 740-0 RB EAST 1RH59AA-16 NONE, NOTE 13 7 4 0-0 RB EAST / 1RH70A-3 NONE,* NOTE 13 740-0 RB WEST 1RH40AB-12 NONE, NOTE 13 761-0 RB EAST 1RH59AA-16 NONE, NOTE 13 761-0 RB WEST 1RH40AB-12 NONE, NOTE 13 761-0 RB WEST 1RH59AB-16 NONE, NOTE 13 774-0 RWCU RM 1RT01DA-3 COLD 774-0 RWCU RM 1RT01DB-3 COLD .
774-0 RWCU RM 1RT01DC-3 COLD 774-0 RWCU RM 1RT02AA-3 COLD 774-0 RWCU RM 1RT02AB-3 COLD 774-0 RWCU RM 1RT02AC-3 COLD 774-0 RWCU RM 1RT02BA-4 . NONE -
774-0 RWCU RM 1RT028-4 COLD 774-0 RWCU RM 1RT04BS-4 00LD 774-0 RWCU RM 1RT04BC-4 COLD 774-0 RWCU RM LRT09A-4 COLD 774-0 RWCU RM 1RT09C-4 COLD 774-0 RWCU RM 1RT11A-4 COLD 774-0 RWCU RM 1RT12A-4 COLD 774-0 RWCU RM 1RT66A-2 COLD 774-0 RWCU RM 1RT67AA-2 NONE 774-0 RWCU RM 1RT97A-2 COLD B07-0 RWCU SEP TN 1RT34B-4 COLD 807-0 RWCU SEP TN 1RT35A-2 COLD 807-0 RWCU SEP TN 1RT37A-1 1/2 COLD gogr&vI4 RWC0 807-0 RWCU SEP TN 1RT45A-3 COLD popp.vP C620-6-HLDFFTUB-8 2 0-6 -MLC ?? CUS-1RT013-6 1RT01C-4 NONE NONE (ReF 24)Pl/6 N r
8 20-6 4GD-PP-CdF 'IRT02BR-4 NONE H tt00rlf/d 8WCg d 2 0-6 m*-PP-eUB- 1RT02BB04 NON U HT-6TQ Y4kYd' C]
l 820-6 CLD PP CUB 1RT028-4 COLD R00M A% ([R.6-F LASALLE RCPB LEAX DETECTION STUDY 90071 l
l
--- - ._. ._- . _= . . _ - - . - _ - - . - - . _ -
Calc, No.: L 001324 Proj. No: 10246-002 ATTACIOfENT 2 SCRT BY AREA /ROct! FAGE 2 Rev.: 00 Page B3 O AREA R00H LINE HUMBER LEAK OETECT.
750. 100IC
~~~~-------
l 820-6 HLD PP CUB 1RT04BA-4 COLD 820-6 HLD PP CUB 1RT04BC-4 COLD 820-6 HLD PP CUB 1RT04B-4 COLD 820-6 HLD PP CUB 1RT04CA-3 COLD 820-6 HLD PP CUB 1RT04CB-3 COLD 820-6 HLD PP CUB 1RT04CC-3 COLD 820-6 HLD PP CUB 1RT04DA-4 COLD 820-6 HLD PP CUB 1RT04DB-4 COLD 820-6 HLD PP CUB 1RT04DC-4 COLD 820-6 HLD PP CUB 1RT05AA-4 COLD 820-6 HLD PP COB 1RT05AB-4 COLD 820-6 MLD PP CUB 1RT05AC-4 COLD 820-6 HLD PP CUB .RT05BA-3 COLD 820-6 HLD PP CUB 1RT05BB-3 COLD 820-6 HLD PP CUB 1RT05BC-3 COLD 820-6 HLD PP CUB 1RT05CA-4 COLD 820-6 MLD PP CUB 1RT05CB-4 COLD Rourtr0 /t) OCY 24) 820-6 HLD PP CUB --1RT05C-4 30LD_ FI FP WA'M Q20~6_n* T@lf
~
1RT06kA-4 NONT ppt 60 Ild gp)ct) HTWl I
f N O - 6 d.D "" '"* - IRTO6AB-4 NONEJ gg pg (RM A4) 1RT06A-4 t _NONE/
Wi@W i 6 -6 "___ ""CUB MLD~PP C"a; 1RT12A-4 COLD q 820-6 HLD PP CUB 1RT128-2 COLD g 820+-6 MLD PP CUB 820-6 MLD PP CUB 1RT12C-4 COLD 1RT20AA-3 COLD
, 820-6 MLD PP CUB 1RT20AB-3 COLD 820-6 MLD PP CUB 1RT20AC-3 COLD 820-6 MLD PP CUB 1RT21AA -2 COLD P20-6 MLD PP CUB 1RT21AB-2 COLD 820-6 HLD PP CUB 1RT21AC-2 COLD 820-6 MLD PP CUB 1RT21BA-2 COLD 820-6 HLD PP CUB 1RT21BB-2 COLD 820-6 HLD PP CUB 1RT21BC-2 COLD 820-6 MLD PP CUB 1RT22A-1 1/2 COLD 820-6 MLD PP CUB 1RT23AA-2 COLD 820-6 MLD PP CUB 1RT23AB-2 COLD 820-6 MLD PP CUB 1RT23AC-2 COLD 820~6 MLD PP CUB 1RT23BA-2 COLD 820-6 HLD PP CUB 1RT23BB-2 COLD 820-6 HLD PP CUB 1RT23BC-2 COLD 820-6 MLD PP CUB 1RT23B-2 COLD 820-6-HLD PP CUB 1RT26AA-2 COLD 820-6 HLD PP CUB 1RT26AB-2 COLD 820-6 HLD PP CUB 1RT26BA-2 COLD 820-6 HLD PP CUB 1RT26BB-2 COLD 820-6 HLD PP CUB 1RT26BC-2 COLD 820-6 IfLD PP CUB 1RT29AA-4 COLD
'20-6 HLD PP CUB 1RT29AB-4 COLD O 820-6 HLD PP CUB 1RT29AC-4 COLD M 820-6 HLD PP CUB 1RT298\-4 COLD LASALLE RCPB LEAX DETECTION STUDY 90071 l
{
Calc. No.: L-001324 Proj. No: 10246 @ 2 ATTACHMENT 2 SORT SY ARIA /P.CtM PACI p 3 O
(d AREA /
ROOM
"~
LINE NUMBER
~~~~~~
LEAX OETICT.
ISO. LOGIC
~~~~~ ~ "~~
820-6 i!d PP CUB 820-6 HLD PP CUB 1RT29BB-4 bb 1RT29BC-4 COLD 820-6 HLD PP CUB 1RT29B-4 COLD 820-6 HLD PP CUB 1RT30AA-1 1/2 COLD 820-6 HLD PP CUB 1RT30AB-1 1/2 COLD B20-6 HLD PP CUB 1RT30AC-1 1/2 COLD 820-6 HLD PP CUB 1RT31BA-1 1/2 COLD 820-6 HLD PP CUB 1RT31BB-1 1/2
- COLD 820-6 HLD PP CUB 1RT31BC-1 1/2 COLD 820-6 HLD PP CUB 1RT32AA-2 COLD 820-6 HLD PP CUB 1RT32AB-2 COLD 820-6 HLD PP CUB 1RT32AC-2 COLD 820-6 HLD PP CUB 1RT33AA-1 1/2 COLD 820-6 HLD PP CUB 1RT33AB-1 1/2 COLD 820-6 HLD PP CUB 1RT33AC-1 1/2 COLD 820-6 HLD PP CUB 1RT34AA-4 COLD 820-6 HLD PP CUB 1RT34AB-4 COLD 820-6 HLD PP CUB 1RT34AC-4 COLD 820-6 HLD PP CUB 1RT34bA-4 COLD 820-6 HLD PP CUB' 1RT34BB-4 COLD 820-6 HLD PP CUB 1RT34B-4 COLD
, 820-6 HLD PP CUB 1RT36A-2 COLD l n 820-6 HLD PP CUB 1RT39B-4 COLD
) Q -
820-6 HLD PP CUB 820-6 HLD PP CUB 1RT41A-2 1RT48A-2 1/2 COLD COLD 820-6 HLD PP CUB 1RT48B-2 1/2 COLD 820-6 HLD PP CUB 1RT66A-2 COLD 820-6 HLD PP CUB 1RT75A-2 COLD AREA BTWN PC&CSCS 1RH01AA-24 NONE' AREA BTWN PC&CSCS 1RH01AB-24 NONE AREA BTWN PC&CSCS 1RH04C-20 NONE AREA BTWN PC&CSCS 1RH04DA-18 NONE AREA BTWN PC&CSCS 1RH04DB-18 NONE AREA BTWN PC&CSCS 1RH06AA-3 NONE ARFA ETWW PC&CSCS 1RH06AB-3 NONE .
AREA BTWN PC&CSCS 1RH50A-20 NONE AREA BTWN PC&CSCS 1RH56B-18 NONE AREA BTWN PC&CSCS 1RH57A-24 NONE ARIA BTWH PC&CSCS 1RIO2A-10 NONE, NOTE 14 AREA BTWN PC&CSCS 1RI41A-10 NONE NOTE 14 AREA BTWN PC&CSCS 1RI41BA-10 NONE, NOTE 14 AREA BTWN PC&CSCS 1RI41BB-10 NONE, NOTE 14 AREA BTWH PC&CSCS 1RI65A-2 NONE, NOTE 14 AREA BTWN PC&CSCS 1RI68A , NONE, NOTE 14 FD PREC0AT TK RM 1RT29B-4 COLD FD PREC0AT TK RM 1RT34B-4 COLD TD PREC0AT TK RH 1RT37A-1 1/2 COLD FD PREC0AT TK RH 1RT38A-3 COLD FD PREC0AT TK RM 1RT40A-2 COLD i
FD PREC0AT TK RM 1RT44A-6 COLD i
LASALLE RCPB LEAK DETECTION STUDY 90071 l
Calc No.: L.001324 Proj. No: 102464X)2 AT ACHMENT 2 SORT BY ARIA /R$CM FACE 4 O
l AREA / LINE LEAK DETECT.
ROOM NUMBER ISO. LOGIC TD PREC0AT TK RM 1RT45A-3 COLD TD PREC0AT TK RM 1RT46A-2 COLD
. TD PREC0AT TK PR 1RT47A-2 t/2 COLD TD PREC0AT TX RM 1RT478-2 2/2 COLD HX A RM 1RT02BA-4 NOTE 1 XX A RM 1RT03AA-4 NOTE 1 KX A PR 1RT04AA-4 COLD RX A RM 1RTO4BA-d , COLD MX A RM 1RT05CA-4 COLD L HX A RM 1RT05DA-4 COLD MX A RM 1PT06AA-4 NOTE 1 HX B RM 1RT02BB-4 NOTE 2 MX B RM 1RT028-4 COLD MX B RM 1RT03AB-4 ** NOTE 2 MX B RM 1RT04AB-4 COLD HX B RM 1RT04BA-4 COLD MX B RM 1RT04BB-4 COLD NX B RM 1RT05CA-4 COLD MX B RM 1RT05CB-4 COLD
~MX B RM / 1RT05DB-4 COLD MX B RM 1RT06AA-4 NOTE 2 MX B RM 1RT06AB-4 NOTE 2 MX B RM O
- MX 5 RM MX B RM 1RT09A-4 1RT66A-2 1RT67AB-2 COLD COLD NOTE 2 MS PIPE TUNNEL 1FWC2BA-24 NOTE 12 MS PIPE TUNNEL 1FWO2BB-24 NOTE 12 MS PIPE TUNNEL 1FWo2FA-24 NOTE 12 MS PIPE TUNNEL 1FWO2FB-24 NOTE 12 MS PIPE TUNNEL 17WO2HA-24 NOTE 12
.MS PIPE TUNNEL 1FN02HB-24 NOTE 12 MS PIPE TUNNEL 1FW11AA-4 NOTE 12 MS PIPE TUNNEL 17W11AB-4 NOTE 12 MS PIPF TUNNEL 1FW11A-4 NOTE 12 MS PIPE WNNEL 1MS01BA-26 NOTE 9 MS PIPE TUNNEL 1MS01BB-26 NOTE 9 MS PIPE TUNNEL 1MS01BC-26 NOTE 9 MS PIPE TUNNEL 1MS01BD-26 NOTE 9 MS PIPE TUNNEL 1M501EA-26 NOTE 9 MS PIPE TUNNEL 1MS01EB-26 NOTE 9 MS PIPE TUNNEL 1M501EC-26 NOTE 9 MS PIPE TUNNEL 1MS01ED-26 NOTE 9 MS PIPE TUNNEL 1M5148-3 NOTE 9 MS PIPE TUNNEL 1MS14C-12 NOTE 9 MS PIPE TUNNEL iMS14D-3 NOTE 9 MS PIPE TUNNEL 1MS14E-3 NOTE 9 MS PIPE TUNNEL 1MS16A-3 NOTE 9 MS PIPE TUNNEL 1MS19A-3 NOTE 9 i O MS PIPE TUNNEL MS PIPE TUNNEL 1MS19BA-2
-1MS19BB-2 NOTE 9 NOTE 9 IASALLE RCPB LEAX DETECTION STUDY 90071
Calc. No.: L-001324 Proj. No: 10246 @ 2 ATTACFD1ENT 2 SORT BY AREA /Rodtt PAGE ! Rev.:00 Page B6
't (d AREA /
ROOM LINE NUMBER LEAK DETECT.
ISO. LOGIC -
MS PIPE TUNNEL 1MS1SBC-2 NOTE 9 MS PIPE TUNNEL 1MS19BD-2 NOTE 9 MS PIPE "UNNEL 1MS193-3 NOTE 9 MS PIPE TUlmEL 1MS20AA-2 NOTE 9 MS PIPE TUNNEL 1MS20AB-2 NOTE 9 MS PIPE TUNNEL 1MS20AC-2 NOTE 9 MS PIPE TUNNEL 1MS20AD-2 NOTE 9 MS PIPE TUNNEL 1MS20BA-1 1/2 , NOTE 9 MS PIPE TUNNEL 1MS20BB-1 1/2 NOTE 9 MS PIPE TUNNEL 1MS20BC-1 1/2 NOTE 9 MS PIPE TUNNEL 1RS20BD-1 1/2 NOTE 9 MS PIPE TUNNEL 1MS20CA-1 1/2 NOTE 9 MS PIPE TUNNEL 1MS20CB-1 1/2 NOTE 9 MS PIPE TUNNEL 1MS20CC-1 1/2 ' NOTE 9 MS PIPE TUlmEL 1MS20CD-1 1/2 NOTE 9 MS PIPE TUNNEL 1MS200-1 1/2 NOTE 9 MS PIPE TUNNEL 1MS25AA-2 NOTE 9 MS. PIPE TUNNEL 1MS25AB-2 NOTE 9 MS PIPE TUlmEL 1MS25AC-2 NOTE 9 MS PIPE TUNNEL / 1MS25AD-2 NOTE 9 MS PIPE TUNNEL 1MS25A-12 NOTE 9 l MS PIPE TUNNEL 1MSB8AA-1 1/2 NOTE 9 Q
V MS PIPE TUNNEL MS PIPE TUNNEL 1MSB8AB-1 1/2 NOTE 9 1MSB8AC-1 1/2 NOTE 9 MS PIPE TUNNEL 1MSBCAD-1 1/2 NOTE 9 MS PIPE TUNNEL 1MSC1AA-1 1/2 NOTE 9 MS PIPE TUNNEL 1MSC1AB-1 1/2 NOTE 9 MS PIPE TUNNEL 1MSC1AC-1 1/2 NOTE 9 MS PIPE TUNNEL 1MSC1AD-1 1/2 NOTE 9 MS PIPE TUNNEL 1MSC1A-2 1/2 NOTE 9
, MS PIPE TUNNEL 1MSC3A-2 NOTE 9 MS PIPE TUNNEL 1RT06A-4 NONE MS PIPE TUNNEL 1RT06B-4 NONE RCIC EQ RM 1RIO1D-4 NOTE 3 RCIC EQ RM 1RIO1F-10 NOTE 3 RCIC EQ RM 1RIO2A-10 NOTE 3 RCIC EQ RM 1RIO2B-18 NOTE 3 RCIC EQ RM 1RIO2C-10 NOTE 3 RCIC EQ RM 1RIO7A-2 NOTE 3 RCIC EQ RM 1RI12A-6 NOTE 3 RCIC PIPE RA 1RH04B-20 NONE RCIC PIPE RA 1RH04C-20 NONE RCIC PIPE RA 1RH04F-20 NONE RCIC PIPE RA 1RH04G-20 NONE RCIC PIPE RA 1RH41AA-3 NONE, NOTE 13 RCIC PIPE RA 1RH48A-3 NONE RCIC PIPE RA 1RH70A-3 NONE, NOTE 13 RCIC PIPE RA lq Ly RCIC PIPE RA 1RHG9A-1 1/2 1RIO1A-10 NONE NOTE 4 I
RCIC PIPE RA 1RIO1B-4 NOTE 4 l LASALLE RCPB LEAK DETECTION STUDY 90071 l
l
_ _ _ _ ~ . _ _ _ _ _ _ _ . _ _ _ . _ _ . . _ _ . . _ . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _
ATTACHMENT 2 SORT BY AREA / ROC (4 PAGE 6 g j, ho: 102 6 2 Rev.: 00 AREA / LINE LEAK DETICT. 8' O i
Os ROCH NUMBER ISO, LOGIC RCIC PIPE RA 1RI01C-4 -NOTE 5 RCIC PIPE RA 1RI41A-10 NOTE 4 :
RCIC PIPE PA 1RI81A-1 1/2 NOTE 4 !
RHR PP A RM 1RH01AA-24 NOTE 10 RNR PP A RM 1RH02AA-18 NOTE 10 RNR PP A PM 1RH03AA-18 NOTE 10 RNR PP A RM 1RM03BA-12 NOTE 10 PJUt PP A RM 1RH04DA-18 NOTE 10 RHR PP A RM- 1RH05BA-3 . NOTE 10 RNR PP A RM 1RH12AA-8' NOTE 10 RHR PP A RM 1RH13AA-18 NOTE 10 RNR PP A RM 1RH18AA-18 NOTE 10 RMR PP A RM 1RH19AA-18 NOTE 10 RHR PP A RM 1RH19BA-18
- NOTE 10 RNR PP A RM 1RH19CA-10 NOTE 10 RHR PP A RM 1RH190A-10 NOTE 10 RHR PP A RM 1RM23BA-4 NOTE 10 RHR PP A RM 1RM24AA-1 1/2 NOTE 10 RNR PP A RM 1RH26AA-4 NOTE 10 RHR PP A RM ', 1RH29AA-3 NOTE 10 RNR PP A RM 1RH39AA-4 NOTE 10 RNR PP A RM 1RH40CA NOTE 10 l RNR PP A RM 1RH74A-1 1/2 NOTE 10
- RNR PP A RM 1RHG3AA-2 NOTE 10 l RHR PP A RM 1RHG7AA-2 NOTE 10 RNR PP A RM 1RI41BA-10 NONE, NOTE 14 RNR PP B/C RM 1RH01AB-24 NOTE 11 RNR PP B/C RM 1RH02AB-18 NOTE 11 RHR PP B/C RM 1RH03AB-18 NOTE 11 RNR PP B/C RM 1RH04DA-18 NOTE 11 RHR PP B/C RM 1RH04DB-18 NOTE 11 RHR PP B/C RM 1RH04EA-18 NOTE 11-RHR PP 8/C RM 1RH04EB-18 NOTE 11 RNR PP B/C RM 1RH05BB-3 NOTE 11 '
RHR PP B/C RM 1RH12AB-8 NOTE 11 RMR PP B/C RM 1RH13AB-18 NOTE 11 RNR PP B/C RM 1RH18AB-18 NOTE 11 RNR PP B/C RM 1RH19AB-18 NOTE 11 RMR PP B/C RM 1RH19BB-18 NOTE 11 RHR PP B/C RM 1RH19CB-10 NOTE 11 RHR PP B/C RM 1RH19DB-10 NOTE 11 RHR PP B/C RM 1RH23BB-4 NOTE 11 RNR PP B/C RM 1RH24AB-1 1/2 NOTE 11 RHR PP B/C RM 1RH26AB-4 NOTE 11 RHR PP B/C RM 1RH29AB-3 NOTE 11 RER PP B/C RM 1RH30A-4 NOTE 11 RHR PP B/C RM 1RH39AB-4' NOTE 11 RHR PP -5/C RM 1RH40CB-16 NOTE 11 RHR PP B/C RM 1RH56B-18 O RNR PP B/C RM - 1RM765-1 1/2 NOTE 11 NOTE 11 IASALLE RCPB u'AK DETECTION STUDY 90071
. . . .. _. _ _ _ . _ . _ - _ ,__ _ _ ~ - - __ _ . _ _ ___. . _ _ _.__ _ .. _ ._...__ _ _ _ _ _ ____ _ _
Calc. No.: L.001324 Proj. No: 10246 002 ATTACHMENT 2 SORT BY AREA /RocH FACE 7 Reb: 00 t Page B8 AREA / LINE LEAK DETECT.
t ROOM NUMBER ISO. LOOIC RHR PP B/C RM 1 RHO 3AB-2 NOTE 11 RMR PP B/C RM 1 RHO 7BA-2 NOTE 11 RER PP B/C RM 1RHH2BA-1 1/2 NOTE 11 RHR PP B/C RM 1RI41BB-10 NONE, NOTE 14 RWASTE PIPE HATCH 1RT06A-4 NONI RWCU DEMIN RM A 1RT04DA-4 COLD RWCU DEM7.N RM A 1RT05AA-4 COLD RWCU DEMIN RM A 1RT20AA-3 COLD RWCU DEMIN RM A 1RT20BA-3
- COLD RWCU DEMIN RM A 1RT20BC-4 COLD RWCU DEMIN RM A 1RT26AA-2 COLD RWCU DEMIN RM A 1RT26BA-2 COLD RWCU DEMIN RM A 1RTA2AA-1 1/2 COLD RWCU DEMIN RM B 1RT04B-4 COLD RWCU DEMIN RM B 1RT04DB-4 COLD RWCU DEMIN RM B 1RT05AB-4 COLD RWCU DEMIN RM B 1RT20AB-3 COLD RWCU DEMIN RM B 1RT20BB-3 COLD RWCU DEMIN RM B 1RT20BC-4 COLD RWCU DEMIN RM B/ 1RT21AB-2 COLD RWCU DEMIN RM B 1RT26AB-2 COLD RWCU DEMIN RM B 1RTA2AB-1 1/2 COLD RWCU DEMIN RM C 1RT04DC-4 COLD O RWCU DEMIN RM C RWCU DEMIN RM C 1RT05AC-4 1RT05C-4 COLD COLD RWCU DEMIN RM C 1RT09A-4 COLD RWCU DEMIN RM C 1RT20AC-3 COLD RWCU DEMIN RM C 1RT21AC-2 COLD RWCU DEMIN RM C 1RT26AC-2 COLD RWCU DEMIN RM C 1RTA2AC-1 1/2. COLD RWCU PP A RM 1RT01DA-3 COLD RWCU PP A RM 1RT02AA-3 COLD RWCU PP A RM 1RTC6AA-3 COLD RWCU PP A RM 1RTC7AA-3 COLD RWCU PP B RM ITlJ1DB-3 COLD RWCU PP B RM 1RT02AB-3 COLD RWCU PP B RM 1RTC6AB-3 COLD RWCU PP B RM 1RTC7AB-3 COLD RWCU PP C RM 1RT01DC-3 COLD RWCU PP C RM 1RT02AC-3 COLD RWCU PP c RM 1RTC6AC-3 COLD RWCU PP C RM 1RTC7AC-3 COLD RWCU VLV RM 1RT02BB-4 NONE RWCU VLV RM 1RT025-4 COLD RWCU VLV RM 1RT04AB-4 COLD RWCU VLV RM 1RT04BA-4 COLD RWCU VLV RM 1RT04BB-4 COLD RWCU VLV RM 1RT04B-4 COLD RWCU VLV RM 1RT05CB-4 COLD RWCU VLV RM 1RT05C-4 COLD l
l l LASALLE RCFB LEAK DETECTION STUDY 90071 l . . _ . . - . -- . .
. _ _ _ - - . . _ . _ _ _ . _ _ ~ __ _ _ _ - _ _ _ _ _ _ _ _ _ . ..__ _. . . . _ _ . _ _ .
Calc. No.: L-001324 Proj. No: 10246 002 ATTACF. MENT 2 SORT SY AREA /P[00M PAGE 8 Pa B O. IJtIA/
ROOM LINE NUMBER LEAX DETECT.
ISO. icGIC '
RWCU VLV RM 1RT06AB-4 NONE RWCU VLV RM 1RT06AC-4 NONE RWCU VLV RM 1RT06A-4 NONE RWCU VLV RM 1RT09A-4 COLD RWCU VLV RM 1RT09C-4 COLD :
RWCU VLV RM 1RT11A-4 COLD RWCU VLV RM 1RT20BC-4 COLD RWCU VLV RM 1RT21AA-2 .
COLD RWCU VLV DM 1RT398-4 COLD RWCU VLV RM 1RT488-2 1/2 COLD RWCU VLV RM 1RT66A-2 COLD RWCU VLV RM 1RT67AB-2 NONE RWCU VLV RM 1RTCSAA-2 NONE RWCU VLV RM 1RTC5AB-2 TURB BLDG NONE 1MS01CA-28 NONE TURB BLDG 1M501CB-28 TURB BLDG NONE 1M501CC-28 HONE TURB BLDG -1M501CD-28 TURB BLDG NONE 1MS25B-3 NONE TURB BLDG 1MS28AA-2 TURB BLDG NONE 1MS28AB-2 NONE TURB BLDG 1MS28AC-2 TURB BLDG NONE 1MS28AD-2 NONE TURE BLDG 11:328A-12 t
TURB BLDG NONE 1MS28B-3 NONE TURB BLDG 1MS32A-36 TURE BLDG NONE '
1MS328A-18 HONE TURB BLDG 1MS32BB-18 TURB BIDG NONE 1MS38AA-16 NONE TURB, BLDG 1MS38AB-18 NCNE '
k Q
LASALLE RCPB LEAK DETECTION STUDY 90071
Calc. No.: L 001324 ATTACHMENT 4 NOTES FROM ATTACHMENTS
- 2 AND 3 PAGE 1 ,
Page BIO O REIATED LEAX DETEC SWITCH EQ. TYPE RELATED-ISOL VALVE
- NOTE 1 1E31-N6000 TDS 1G33-F004 1E31-N600H TDS 1G33-F001 1E31-N601G TS 1G33-F004 1E31-N601H TS 1G33-F001 ,
NOTE 2 1E31-N600J TDS 1G33-F004 1E31-H600K TDS 1G33-F001 1E31-N601J TS 1G33-F004 1E31-N601K TS 1G33-F001 NOTE 3 1E31-N602A TS 1E51-F008 1E31-N602B TS IC51-F076 1E31-N602B TS 1E51-F063 1E31-N603A TDS 1E51-F008 '
1E31-H603B 'i DS 1E51-F076 1E31-H603B TDS 1E51-F063 NOTE 4 1E31-N6128 TS 1E51bF063 1E31,-N6125 TS 1E51-F076 1E31-N613B TDS 1E51-F063 1E31-N613B TDS 1E51-F076
() NOTE 5 1E31-N612A 1E31-N6125 TS TS 1E51-F008 1E51-F063 1E31-N6128 TS 1E51-F076 1E31-N613A TDS 1E51-F008 1E31-N610B TDs 1E51-F063 1E31-N6135 TDS 1E51-F076 NOTE 6 1E31-H600A TDS 1G33-F004 1E31-N6005 TDS 1G33-F001 1E31-N600B TDS 1E51-F076*
1E31-N601A TS 1G33-F004 -
1E31-N6018 TS 1G33-F001 NOTE 7 1E31-N6000 TDS 1G33-F004 1E31-N600D TDS 1E51-F076*
1E31-N6000 TDS 1G33-F001 1E31-N601C TS 1G33-F004 1E31-N601D TS 1G33-F001 LASALLE RCPS LEAK DETECTION STUDY 90071
Calc. No.: L.001324
, Proj. No: 10246 @ 2 Re ATTACHMINT 4 NOTES FROM ATTACILS.ENTS 2 AND 3 PAGE 2 p O xEuTED LEAX DETEC EQ. TYPE xEmm ISOL
- SWITCH VALVE NOTE 8 1E31-N600E TDS 1G33-F004 1E31-N600F TDS 1G33-F001 1E31-H601E TS 1G33-F004 1E31-N601F TS 1E51-F076*
1E31-N601F TS 1G33-F001 NOTE 9 1E31-N604A TS tWIV 1E31-N604B TS MSIV 1E31-N604C TS MSIV 1E31-N604D TS MSIV 1E31-N615A TDS MSIV 1E31-N615B TDS MSIV 1E31-N615C TDS MSIV 1E31-N6150 TDS MSIV NOTE 10 1E31-N608A TS 1E12-F023 1E31-N608A TS 1E12-F053A i 1E31-N608A TS 1E51-F064*
1E31-N608A TS 1E12-F008 1E31-N608A TS 1E12-F0533 1E31-N608B TS 1E51-F063*
1E31-N608B TS 1E12-F0995 O 1E31-N608B TS 1E51-F076*
1E31-N608B TS 1E12-F009 1E31-N608B TS II12-F099A 1E31-N614A TDS 1E51-F064*
1E31-N614A TDS 1E12-F053B 1E31-N614A TDS 1E12-F023 1E31-N614A TDS 1E12-F008 1E31-N614A TDS 1E12aF053A 1E31-N614B TDS 1E51 F076*
1E31-N614B TDS 1E12-F099A 1E31-N614B TDS 1E12-F099B 1E31-N614B TDS 1E51-F063*
1E31-N6148 TDS 1E12-F009 O LASALLE RCPB LEAK DETECTION STUDY 90071
Calc. No.: L 001324 Proj No: 10246 402 ATTAC)CiE!!T 4 !!OTIS TROM ATTAC}C4EllTS 2 AND 3 FAGE 3 Rev.: 00 t Page B12 RILATED RELATED LEAK DETEC EQ TYPE ISCL -
SWITCH VALVE Il0TE 11 1E31-H608C TS 1E12-T008 i 1E31-N608C TS 1E12-T023 1E31-N608C TS 1E12-T053A 1E31-N608C TS 1E12-T053B 1E31-N608C TS 1E51-T064*
1E31-N608D TS 1E12-T099A 1E31-N608D TS 1E51-T063*
1E31-N608D TS 1E51-T076*
1E31-N608D TS 1E12-T009 '
1E31-N608D TS 1E12-T099B 1E31-N614C TDS 1E51-T064*
1E31-N614C TDS l'E12-T008 1E31-N614C T'JS 1E12-T053B 1E31-N614C TDS 1E12-T053A ,
1E31-N614C TDS 1E12-T023 1E31-N614D TDS 1E51-T076*
1E31-N614D TDS 1E12-T009 1E31-N614D TDS 1E12-T099A 1E31-N6140 TDS 1E51-T063*
1E31-N614D TDS 1E12-T099B valves marked with
- receive an isolation signal to isolate RER piping in the Steam condensing Mode.
I O LASALLE RCPB LEAK DETECTION STUDY 90071
- _.._ _._._. _ __ _ .. _ ~
i Cale. No.: L401324
. Proj, No: 10246 002 i ATTACHMENT 4 NOTES FROM ATTACHMENTS 2 AND 3 PAGE 4 Rev.: 00 i Page Bl3 Final _ l O RELATED LEAX DETEC EQ. TYPE RELATED ISOL -
f SWITCH VALVI l
________ ________ _____ t i
1E31-N604A No isolation legic required. ;
MOTE 12 TS 1E31-N604B TS Detection of FW leak vill !
1E31-N604C TS result in alarm in control rocm.
1E31-N604D TS l 1E31-N615A TDS !
1E31-N6158 TDS - i 1F.31-N615C TDS :
l 1E31-N615D TDS
[
- NOTE 13 These-RNR lines are part'of the Reactor Shutdown ;
Cocling Mode and are downstream of the RER heat-exchangers. Per the FSAR, the maximum temperatura l of the lines is 252.5 F. Although not specifically excluded from any documentation identifying the scoping of the temperature based leak detection ,
consitaents, the low temperature and the rapid (20 hr) i
- cooling of the reactor coolant suggests temperature '
based leak detection is_less practical than the other methods available. Those methods includet l
i 1. RKR heat exchanger steam supply flow - high
- 2. Reactor vessel water level - low, level 3 ,
- 3. Reactor vessel (RKR cut-in permissive) pressure - '
high
- 4. RKR pump suction flow - high Additional leak detection measures in the Reactor Building includet
- 1. Reactor Building floor drain sumps
- 2. Reactor Building radiation monitoring NOTE 14 Redundant leak detection provisions exist for the RCIC i systen lines including: '
- 1. RCIC steam line flow - high
- 2. RCIC steam supply pressure - low
- 3. RCIC turbine exhaust diaphragm pressure - high Additional leak detection measures in the Reacter Building include:
- 1. Reactor Building floor drain su=ps-
-2. Reactor Building radiation monitoring LASALLE RCPB LIAK DETECTION . STUDY 90071
.r--.- ,+----w,',ry.,y -mr-,,.m.,-w, ,,,mw,-wm_,,,,w-.ew- ,+,,,.w....,,,,. r ,_.,,,,_.mr -m.,-.yyu.-sy,., -y.-~,.w.,..,,q.
,,%., , ~ . ,,,, -,_m_y,s. e-m,,,,,, .,<,c4
i
)
Calc. No.: L 001324 :
- Proj. No: 10246-002 '
Rev.: 00 :
Page Cl O .
I t
I M g lQ ATTACHMENT C Excerpt from 1991 S&L Letter / Attachment - Temperature Besed LD System Evaluation (Reference No. 25) l l
l l
l O
Calc. No.: L-001324
, Proj. No: 10246-002 Rev.: OG ATTACHMENT A Page C2 asARcDfT & LUNDY EVALUATION OF GSAf ? E LEAX DETPNTOW SYSTEMA *
- 1. - BACKGRCt,'ND INr0RMATION OF TEMPERAT'JE LEAK DETECT:en ogszcg a.
, Temeerature Leak Setection system 5 i
The ambient and differential temperature based leak ;
detection system is intended to detect unidentified leakage from the reactor coolant pressure boundary and to alarm on 5 gpm and isolate on 25 gpm. This type of ledk detection is effective for detecting and locating the leakage because of its sensitivity and immediate response, however, it is not accurate for leakage quantification. This method is influenced by many '
variables such as temperature and humidity of entering air, pressure /tempersture of leaking reactor coolant, O air flow rates, HVAC 1 low paths, changes in process pipe operating modes, and entering cooling water temperature (in the case for RHR and RCIC Equipment Rooms).
In an attempt to optimize the intended functions of the existing system, set points are selected to consider all these f actors so that the temperature based leak detection system will'be responsive to any leakage at anytime of the year. For example, the alarm setpoints for both the ambient temperature and switches and diff erential teaperature swit:hes were set ':w enough .
to detect any leakage <25 gym during surmer or winter.
This alarm will alert the operator of potential leakage and allow investigation betera the isolation setpoint is reached. Whereas, isolation fer both ambient and dif f erential temperatures will be set high enough to -
q avoid spurious isolation and yet icw enougn to avoid exceeding radioactive release limit and the environment 1
Prh. No: 10246-Ob2 I Rev.: 00 ;
, Page C3 to which the safety-related equipment in that l i
particular area was qualified.
- b. ESCU Ecuiemeat and Pleine Temperature sensors were provided in the Pump Rooms and ,
Heat Exchanger Rooms as a backup to the High Differential Flow and Sump Pump High Level Leak Detection Systems. Howe.ver, alarm and isolation functions have been deleted for these instruments when the RWCU System design was changed to locate these I pumps downstream of the system heat exchangers so that pumps would not be subjected to high temperature water.
This sy, tem change made the temperature monitoring of the now colder portion of the RWCU System ineffective and potentially cause unnecessery isolations. Due to this< design change und spurious isolations experience from the temperature portion of the leak detection system, the RWCU System has now depends on the high differential flow, sump high level and air particulate sampling for leak detection.
- c. MS. RMR and RCIC Pleine and Eculement Temperature monitoring for leak detection was provided within the confined areas with equipment and piping to the extent possible wnere ventilation boundaries, ~'
airflow and flow directions are constant.
Temperature monitoring in an open areas-like the Tucbine Building and't'he areas between the containment and the CSCS cubicle were not provided because it would not be very effective. Thus, leak detection in these areas needs to rely en the other variables.
N
Calc. No.: L 001324 Proj. No: 10246 002 Rev.: 00 Page C4
- 2. '
EVALUATION or CYCNA'S FINDINGS a.
Holdinu Punen cubicle. Elevation 920'-4" .
No hot piping of RWCU or other systems is routed in this cubicle. The hot piping identified in the Cygna Report for this cubicle are routed in the RWCU Valve Room, Elevation 807'-0" and in the Pipe Tunnel, !
Elevation 798'-0". I Since this cubicle contains only the cold portion of the RWCU System, installation of temperature based leak detection is not effective and not recommended. The existing high differential flow, sump leuel and gas monitoring detection systems for this cubicle meet the FSAR/UFSAR comr.itment.
- b. RWCU Valve Room. Elevation 807'-0" (Refer to Figure 1)
RWCU Lines Nos. 1RT06A-4 and 1RT06AC-4 are part of the hot portion of RWCU System that are routed in this room. Although this room is not presently provided with temperature based leak detection system, the existing RWCU high differential flow instrumentation should detect the leakage line in this room.
This room is a confined area with established air flows and ventilation bnundaries. Thus, provision for ,
temperature based leak detection can be pursued to fully comply with FSAR/UFSAR commitment and enhance the leak detection capabilities. The temperature sensors may be located accordi~ng to Figure 1.
- c. Pirinc Tunnel Elevation 708'-0" and RNct' Valve Poem.
rievation 786'-4" (Refer to Figure 2)
These areas are adjacent to each other and also to the Heat Exchanger Rooms.
The current temperature based 3
_ __ __- _. ._. _ .~ _ _ _
Cale. No.: L401324 1 Proj. No: 10246 4)2 Rev.: 00 Page C5 l
g_ leak detections are strategically located to commonly l
( serve the Valve Rooms, Heat Exchanger Rooms and the '
Pipe Tunnel.
The ventilation coundaries, air flow
- direction boundaries, air tiew directions and temperature leak detection sensors are shown in Figure 2.
No further change nor clarification to the UTSAR is required.
- d. Cleanue Looe Holdue piee Room. Elevstien 774'-o" (Refer to Figure 3) -
The leakage from the RWCU lines, 1RT02BA-4 and 1RT67AA-2 that are within thir6 room should be detected by the dif ferential temperature sensors mounted in the commen exhaust duct.
This exhaust duct serves both the Holdup Room and the Cleanup Recirculation Pump Room.
Currently, the alarm and isolation functions of these instruments are deleted by ECN ED-266. This was done as a' result of RWCU System design c!.ange which lef t only a small amount of hot piping in this room.
f)
these RWCU lines now depends on high differential flow, Thus, sump high level and air particular sampling for leak detection.
Since this room is a confined space with some hot RWCU piping, the temperature monitoring should be provided to meet the 75AR/USTAR commitment. The existing ambient temperature and differor.ial temperature sensors can be re-used to serve this room. The arrangement of the temperature sensors are shown in Figure 3.
e.
Endvaste (Refer to Figure Piee Shaft
- 4) (Auviliarv 9uildine Pire ihsft The RWCU Line No. 1RT06A-4 runs vertically witnin this shaft from Elevation 786'-6" to Elevation 749'-O'. No temperature leak detection is previded in this snaft.
O
\ /
4
Cde. No.: L-001324 Proj. No: 10246 002 Rev.: 00
- Page C6 The current means of leak detection f:r this line are
( high differential flow and air particulate sampling. '
Since the pipe snatt is a confined space and has established and flow / directions and boundaries, temperature differential sensors can be added in this shaft for leak detection enhancement. Addition of temperature based leak detection system in this shaft should fulfill TSAR /UTS6R cor.mitments. The suggested arrangement of the sensors are shown in Figure 4. I
- f. RCIC Pine Routine Area The RFR lines within this RCIC Pipe Routing area are part of the Reactor Shutdown cooling mode. The maximum tarperature of the pipe in this mode is about 250*r and occurs only for a very short period of time during the Reactor Shutdown Cooling Mode. A temperature based s leak detection system for this area is not practical
(~'l
\s- and not recommended.
A cl*rification of the UFSAR to clearly identify this deviation is recommended.
- g. Aren Between Primarv Containment and CSCS Cubiele.
Elevation 673'-4" Several RHE and RCIC lines are routed in this area between Primary Containment and CSCS Cubicle.
These areas are wide'cpen spaces. Temperature based leak detection is not practical nor recommended.
The UTSAR should be clarified to point out that L
temperature cased ?ut detection applies only to equip =ent/ pipe ::ca. .ad tunnels and no to large : pen f\ areas of the Reacter Building. ;
5
Calc No.: L-001324 Proj. No: 10246-002
- Rev.: 00 Pa:e C7 h.
RMR Meat Exchanear cubicle. rievatie- 694'-og
{
The RCIC Line Nos. 1R411A-10 and 1RI41BB-10 are routed in the RHR Heat Exchanger Cubicles. '
Temperature baced leak detection is provided in this cubicle in addition to the available methods such as sump drain and high differential flow rate. However, the existing. temperature based leak detection isolates only the RHR lines.
Leakage from the RCIC line routed in the RHR heat exchanger cubicle will be detected by the temperature sensors which will provide an alarm to the Control Room.
This high temperature alarm in conjunction with the other redundant leak detection (high flow, low pressbre and high pressure in RCIC Turbine Exhaust Diaphragm) for the RCIC System identify indicate j ,
leakage in this subject line.
No further enhancement of leak detection is recommended in the RHR Heat Exchanger Cubicles to encompass RCIC tine isolation. The UFSAR should be clarified to describe the actual situation.
i.
Uneer and Lower Main Steam Tunnel rievation 673'-4? .
RWCU Line Nos. 1RT06A-4 and 1RT068-4 are routed in the i
Main Steam Tunnel.
There is adequate leak detection instrumentation in the pipe tunnel which isolates the main steam system in case of a leak in the tunnel. However, the existing temperature based leak detection has no isolation signal for the RWCU lines that are within the tunnel.
L p/
(m-Isolation signal to the RWCU isolatien valves (1033-F001 and 1G33-F004) can be added to the temperature 6
. _ - - ~1 -. ,- . _ . - _ . . . . _ - , - - _ . - _ - . __ _ _ _ .
Cale. No.: L@l324 Proj. No: 10246 @ 2 I Rev.: C0 Page C8 leak detection system to meet the intent or tne tdAx.
) However, this may not be necessary if the LaSalle
\_/
Station Precedure is updated to instruct cpe:ator to -
monitor the RWCU flew and Filter Deninerali:er AP at ler.st hourly
- af ter receipt of hign temperature alarm from the Main Steam Tunnel Leak Detection System. The l procedure should also instruct operators to isolate RWCU on a Filter Domineralizer high AP.
j.
Turbine Buildine. Elevation 692'-6" Several main steam lines are routed within the basement of the Turbine Building, Elevation 692'-6".
This part of the Turbine Building at Elevation 692'-6" '
at column row S-12 in a wide open space and the use of temperature based leak detection system are not practical nor are they recommended. The UFSAR should be clarified to point out this actual situation.
- 3. CONCLUSIONS The absence of temperature leak detection devices in some pipe routing areas does not represent safety hazard but is inconsistent with the FSAR/UTSAR commitments. The inconsistencies can be corrected by implementing the following actions:
- a. Clarify the applicable sections of the UFSAR.
O,f t..
- Based en Leak Before Break (LSB) criteria, a one hour reading interval is sufficiently conservative to prevent a leak from becoming a pipe break while still undetected. 7
. , L-wl324. - - - . _
Leas. .No.
Proj. No: 10246 002 Rev.:00
.* Page C9 Final
- b. Update the applicable LaSalle Station Operating Procedure to instruct operator to monitor the RNCU Tiow and Tilter Domineralizer AP at least hourly
- af ter .
receipt of high ambient and/or differential temperatures from the Main Steam Tunnel, RWCU Valve Room, Cleanup Holdup Room and Radwaste_ Pipe Shaft. The procedure should also instruct the operators to isolate RWCU System on Filter Domineralizer high AP. ,
- c. Improve the reliability ot the Leak Detection System by i adding temperature >e . sors to provide an alarm when there is leakaar la t2.4 following areas:
. RWCU Valve 6 coa. E'evation 807'-0" 4
. . Cleanup Holdup Pipe Room, Elevation 774'-0"
. Radwaste Pipe Shaft O
- Based on Leak Before Break (LBB) criteria, a one hour reading interval is sufficiently-conservative to prevent a leak from becoming a pipe break while still undetected. 8 l
- Calc. No.: L@l324
' Proj. No: 10246-002 Rev.: 00 Page DI i
D i
, 1 l
f ATTACHMENT D l Excerpt from 1995 S&L NDIT - Tempemture Based LD Evaluation of Temperature based LD (Reference No. 24) !
4 L O l
l
NDIT No. LAS NDIT-0072-00 Page 14 cf 18 '
Attachment 1 -
Revision 0 September 29.1995 Leak Detection Evaluation For Areas Outside of Primary Containment 4.0 AREA ASEESSMENT OF AVAILABLE LEAK DETECTION METHODS ,
The areas which are assessed are discussed in the background section of this letter.
They are areas identified in the Cygna report as having hot reacter coolant piping which is not isolated by ambient temperature or area differential temperature monitors. >
These areas are evaluated to determine what alternate leak detection methods are available in an area in place of the ambient and differential temperature monitors. The alternate leak detectica methods must be able to detect a 5 GPM unidentified leak in sufficient time to allow the leaking system to be isolated before the total reactor coolant leakage limit c,f 25 GPM is exceeded.
A summary table of laak detection methods is attached as Table 1.
!O l
4.1 Reactor Building General Areas 710'-6" and 740' 0" (ltem Nos.1-4 in section 2.0]
These areas contain RHR shutdown cooling mode piping. Since the pipes have a maximum line temperature of 252 *F, cooldown requires only 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> and the areas are large open spaces, T and AT sensors are not recommended. T and AT sensors would require low setpoints which could result in spurious alarms or isolation. These detectors would only be functional for.a.short period of time during the shutdown cooling rpede and other methods would still bee- -
required for the remaining time period when water temperature drops below the detection capability of the T and aT sensors.
Leak detecticn methods fer this area include the Rsacter bu:! ding exhaust radiation monitor and the CAM monitar. The general area f!cer drains are ciced to the reactor building sumps which are monitored. A high raciation moniter is available on the west side cf elevation 740'-0". Tne RHR shutdown cooling high flow switch will also isolate any of these lines following a line creak.
Calc. No.: L-001324 - '
Proj. No: 10246-002 Rev.:00 Page D2 1
N _. _ _ _ _ . _ _ _ _ _ , _ . _ , , _ , _ __ _ .- .
I
NDIT No. LAS.NDIT-0072-00 Page 15 of 18 C
Attachment 1 -
' Revision 0 !
September 29,1995 Leak Detection Evaluation .
For Areas Outside of Primary Containment 1 4.2 Cleanup Loop Holdup Pipe Room - EL. 774'-0" (ltem No. 5 in section 2.0)
This area contains RWCU piping coming from the reactor to the regenerative heat exchanger. Leak detection methods available for this area are high radiation in the reactor building exhaust duct, reactor building sump alarms and RWCU high differential flow. The RWCU high differential flow setpoint is above the 25 GPM totalleakage limit and provides automatic isolation of the RWCU system. Leak detection methods including the reactor building ventilation exhaust high radiation monitor, CAM monitor and sump monitors are alarm only. -
4.3 Holding Pumps Cubicle EL. 820'-6"
( (liem No. 6 in section 2.0)
A review of the Cygna report in SCM-0534 found the Cygna report inaccurately showed hot piping in this area. All RWCU piping in this area is cold and not detectable by T and AT sensors. Alternate means of leak detection are reactor building sump monitoring, reactor building exhaust high radiation, CAM monitors and RWCU high differential flow.
4.4 Area Between Primary Corsainment and CSCS - EL. 674'-0" (Item No. 7 in section 2.0)
This area contains both RHR and RCIC piping. Since this is an open area and contains piping from 2 systems, isolatien based on T or AT would require both systems to be isolated simultanecusly which may not be desirable. In addition, tnis is a large general area and T artd.aT sensers wculd require Icw setpoints wnien can lead to sourious alarms and isolatiens.
A reactor building sump is located in the area to provide a leak detection alarm. Reacter building exhaust high radiation and CAM alarms are also available, f]
V Calc. No.: L-001324 Proj. No: 10246-002 Rev.: 00 Page D3
NDIT No. LAS NDIT-0072 00 Page 16 cf 18 V
Attachment 1 -
Revision 0 September 29,1995 Leak Detection Evaluation For Areas Outside of Primary Containment 4.5 Main Steara Pipe Tunnel .
{ltem No. 8 in section 2.0)
This area contains both MS and RWCU piping. The sensors located in this area are for MS isolation only. Leaks in this area can be detected by the reactor building exhaust high radiation monitor or CAM monitors. The RWCU line inside the pipe tunnelis after the last flow element s that RWCU high differential flow isolation is not possible. High temperature alarms from the MS temperature sensors can be used to warn of a possible RWCU leak.
4.6 Pipe Chase North Side - EL. 710'-6" i
(ltom No. 9 in section 2.0)
(]
This area contains both RHR and RCIC piping. The area is monitored by the RCIC T and AT sensors which isolate only the RC!C lines. The RHR lines in this area are associated with shutdown cooling which ha: a limited duration tnd maximum water temperatures of 252 'F. Isolation of the RHR piping by T and AT sensors are not recommended for this area due to the chott duration of the shutdown cooling mode, ineffectiveness of the instruments after water temperature drops below 212 'F and the fact that a RCIC leak would isolate both RCIC and RHR which may be undesirable.
Leaks in this area can be detected by the reacter building high radiation monitor and CAM.
4.7 RHR Heat Exchanger Rooms - EL. 710'-6" and 694'-6" (ltem Nos.10-11 in section 2.0}
The RHR Heat Exchanger recms contain both RHR and RCIC piping. The reem contains T and AT sensors which isolate the RHR lines but not the RCIC lin The RCIC !!ne located in the RHR area is part cf the steam cendensing mcde whien has ceen deleted. Hcwever the line remains available fer use during mode 4 as a!temate shutdown cooling. Water temcerature is limited to 200 'F during mece 4 so that T and .1T sensors could not be usec to detect the
,9, leakage.
t t J
Calc. No.: L-001324 i
Proj No: 102464)02 Rev.: 00 Page D4
NDIT No. LAS NDIT-0072 00 Page 17. of 13 Attachment 1 Revision 0 September 29,1995 Leak Detection Evaluation For Areas Outside of Primary Containment The other detection methods available for the RHR heat exchanger areas are reactor building sump n.onitoring, Reactor building ventilation exhaust high radiation and CAM monitors 3;h radiation monitors are also located in the heat exchanger rooms. He en ~, these monitors have been noted as having high background radiation exag RHR operation which rr.ay limit their effectiveness at distinguishing a leak from normal room conditions.
4.8 Radwaste Pipe Hatch
[ Item No.12 in section 2.0]
This area contains RWCU line 1RT06A-4 which is a return line from the regenerative heat exchanger and is located downstream of the final RWCU system flow element. Therefore, a leak in this line is not detectable by the RWCU differential flow monitoring instrumentation. The Radwaste pipe hatch area is not exhausted by the reactor building ventilation system so the exhaust plenum radiation monitor is not available. Die Radwaste building CAM monitor is the only radiation monitor available for detecting a leak in this line, it is believed that there is a sump in this area. However we have not been able to verify from design drawings.
4.9 RW '.U Valve Room - EL. 807'-0"
[ Item No.13 in section 2.0)
This area contains RWCU foing which is after the second flow element in the -
differential flow monitoring instrumentation. Other RWCU.olping is detectable by the RWCU differential flow isolation. Other detection methods other than visual and audible inspection is the reactor building exhaust radiation monitor, CAM monitor and reactor building sump monitoring.
m, Calc. No.: L-001324 Proj. No: 10246-002 Rev.:00 Page D5
NDIT No. i.AS NDIT-0072-00 Page 18 of 18 (O
) Attachment 1 Revision 0 .
September 29,1995 Leak Detection Evaluation For Areas Outside of Primary Jontainment 4.10 Turbine Building
[ Item No.14 in section 2.0)
The turbine building contains some MS piping not located in the steam tunnel.
Because the piping is located in open areas of the Turbine building, the T and AT setpoints would probably be low and cause spurious isolations.
These leaks could be detected by visual and audible inspection, CAM monitors or possibly sump activity monitoring (needs verification). High main steam flow is also available but would not detect below the 25 GPM totalleakage limit.
O 9
Calc. No.: L-001324 Proj. No: 10246-002 Rev.: 00 -
Page D6 Final
l- Calc. No.: L-001324 Proj. No: 10246-002 i
Rev.: 00 -
PageEl O -
i i l
l 1
l J
/
)
I C ATTACHMENT E Summary Table of Temperature based LD System Pipeline / Area Evaluations 0
i O
____________________i
rm em U U ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINE / AREA EVALUATIONS N R REASON TEMP MONITORING NOT REQUIRED TEMP CALC?EF.
ROOM DESCRIPTION UNENO. Nf A e 10 m and rapid M q make tem WS unpradd Reador taaldng-North 710E 1RHQ3BA 12 No Wde open area, temp LDS rrgradcal Redundant LDS oved S&L Ref 24 CYGNA Ref.10 Cmb am of W T and rapd wv;.9 make temo LDS sgradcal 1RWMS-12 g Reador tamMng - North 710-6* S&L Ref. 24 Wde open aree, temp LDS rrgradcal Redandarit LDS eved 1RW 3CA-12 A .10 No
'" 'W *****P *"E'"
Reader b Mng - North 710E S&L Ref. 24 Wde open aree, temp LDS regradcal Redandert LDS avsd A 10 ' "" '*E' * '"# * '"E * *#
Reactor bang-North 710E 1 RH34A-6 No Wde % , eree, temp LDS impractcal Red;ndert LDS avad S&L Ref 24 A 10 ""d # "'"#*'** **
Reedor buddng - tJorth 710E 1RH3GAA-4 No Wide open area temp LDS empredcal Redundert LD$ aved S&L Ref. 24
.10 * " *"d "#*I""E
- Rondor SMng-Ncuth 710E 1RH40AA-12 No Wde open eres temp LDS ergredcal Red;ndert LDS avad S&L Ref. 24 A 10 " *" ** *'*"E **
Reador hMng-North 710E 1RH40CA-16 No Wde open aree, temp LDS wrgradcal Redtsdart LDS avad S&L Ref 24
- I " N Reactor tusMng-North 710& 1RH41AAG No Wde oper.r:an. temp LDS snpractcal Redandwt LDS eved S&L Ref 24 A .O he d low T and rW W mde tanp WS wnpradcal g,
Reador heng-tiorth 710E 1RH41 ABO S&L Ref. 24 Wde open area, temp LDS impradcal Redurdort LDS avad 10 " '"**"" *"E' .
Reador h eng - North 710F 1RtfBAA-16 No Wde open ares, temp LDS rrgractcal Redandent LDS ewed S&L Ref. 24
- *"E' Reador hMng-North 710-6* 1RH70A-3 No Wde open area, temp LDS imoracteal Redtrdert LDS avad S&L Ref 24 CYGNA Ref.10 C-b am of low T and rapd cooieng make term tpS ugradcal 1RHDCB-12 g Reactor buddng - South 710& S&L Ref 24 Wide open area, temp LDS wnpradcal Redundard LDS avad
- m e@ v mee temp WS wnpradd Reador buddng - Sotah 710F 1RKDA-16 No Wde open area.tempLDS rn:radcal Redundert LDS avad S&L Ref. 24 1Rt03AB-4
^ No
- m and rspid M y rnake tanp WS anpradcal Reador tnnung-SotAh 710F S&L Ref. 24 Wde open area. temp LDS wnpradcal Redundart LDS avad 10 m T and rW @g make tanp WS wnprade Reador tasang-South 710E 1RH40CB-16 No S&L Ref 24 Wde open area, temp LDS wrvradcal Redtmdard LDS avad e 10 u m an raped eg rnde tenp WS unpradd Reador buddng - East 740# 1RK13A-16 No Wde open area, tempLDS unpredcal Redundert LDS avad S&L Ref. 24
^ "" m an rapid My mee tanp WS unpradd Reactor buiung - East 740& 1RH41 AA-3 No Wde open area, temp LDS wnprodcal Redandart LDS avad S&L Ref 24
- " * *E'd '"#* ""P 3 N*d Reactor buddng - East 740F 1RKBAA-16 No Wide open area, temp LDS impradcal hed ndert LDS avad TATr S&LRef 24
" *" '*P * *#* ""P N*##*'
- Readur buddng - East 740F 1RH70A-3 No Wde oren area, temp LDS impredical Redundert LDS evad S&L Ref. 24
^ = 2 Iw and rapd ng m8 e tenPWS rnpradcal 8 h Reador buildng -West 740& 1 RH4MB-12 S&L Ref. 24 No Wde open aree. temp LDS entradcal Redundert LDS eved ,-
Reador Wng - East 761*& 1 RH5BAA-16 CYGNA Ref.10 No Cmu aeon of low T and repd cov6 g make temp LDS rnpredcol 3 t, No Combsnation of low T and rapd e y make temp LDS impractcal n(
Reador 5 hy -West 761*& 1RH40AB-12 CYGNA Ref.10 #I 1RH50AB-16 CYGNA Ref.10 No Cma anon of low T and raped wv6 g mabe temp LDS rnpradcat
- Reacter tanidng-West 761*& e 1RTO1DA-3 CYGNA Ref 10 No Cold kne RWCU toop hold-up pipe rcom - 774'&
,S (m)
Q/
(., %'
(Q s ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS REASON TEMP MONITORING NOT REQUIRED TEMP, CALC. REF. '
ROOM DESCRIPTION LfME NO.
RWCU loop hokke ppe i-e - 774& 1RTD1DBG CYGNA Ret.10 No Coki kne RWCU bop hokkp ppe room - 774& 1RTD1DCJ CYGNA Ref.10 No Cold kne RWCU loop holdup ppe room - 774& 1RT02AA-3 CYGNA Ref.10 *ii Coki kne RWCU loop hokkp ppe r wwn- 774& 1 RT02AB-3 CYGNA Ref.10 No Coki kne RWCUloop hakkp ppo room - 774F 1RT02AC-3 CYGNA Ref.10 No Cold kne RWCU bop hokkp ppe room - 774& 1'4TO2BA-4 S&L Ref. 25 No Redandert LD eved. Therme! LD edsed to encrease rehabmy l Rev 01 RWCU loop hokkp ppe room - 774& 1RTC2B-4 CYGNA Ref.10 No Cokikne RWCU loop hokkp ppe n- 774F 1RT0488-4 CYGNA Ref.10 No Coki kne RWCU loop hokkp ppo room- 774& 1RTD4BC4 CYGNA Ref.10 No Cold hne -
RWCU loop hokkp mpo i 774& 1RTOBA-4 CYGNA Ref.10 No Cold kne RWCU loop hokkp ppe room - 774F 1RT09C4 CYGNA Ref.10 No Cold kne RWCU loop holdup ppe room - 774& 1RT11 A-4 CYGNA Ref.10 No Cold 6ne RWCU toop hokkp ppe room - 774& 1RT12A-4 CYGNA Ref.10 No Cold kne RWCUloophoidupppei n-774& 1RT86A-2 CYGNA Ref.10 No Cold kne RWCU loop hokkp ppe i-n - 774& 1RT67AA-2 S&L Ref. 25 No Redundert tD eved Thermal LD ed 2nd to sicreeee rehstalty l Rev. 01 RWCU loop hakkp ppo room- 774& 1RT97A-2 CYGNA Ref.10 No Cold tre RWCUloop holdup ppe room- 774& 1RTO1B4 S&L Ref. 25 No Red;ndert LD eved Thermal LD erdod to encreese rehetmity- Rev. 01 RWCU loop hokkp ppe room - 774& 1RTO1C-4 S&L Ref 25 No Rodjndent LD eved Thermal LD edded to increase rehabmy RWCU phase sep tank cubecle 1RT348-4 CYGNA Ref.10 No Cold brie .
RWCU M-w sep. tank cubcle IRT35A-2 CYGNA Ref.10 No Cold kne RWCU phase sep tank a deia 1RT37A-1 1/2 CYGNA Ref.10 No Cold kne RWCU d a sep tank a*h 1RT45A-3 CYGNA Ref.10 No Cold kne CYGNA Ref.10 '
Mh Hoking pumpe cubcle - 807& 1RTD1DA-3 S&L Ref.25 & N R h LDsvet.
24 Holdng pumps cutacle - BOTE 1RTD18-6 S&L Ref. 24 - Actuety en RWCU toop hokkp ppe room Holdng pumps cutacle - 80TE 1RTO1C-4 S&L Ref. 24 - Aduesy en RWCU loop hok>up ppe room Holdng pumps a
- eta - 807& 1RT02BA-4 S&L Ref. 24 - Aduesy en RWCU heat exchanger room A/B Hokang pumpe a dele - 807& 1RT02BBA S&L Ref. 24 - ActusBy en RNU heat enchanger room A/B CYGNA Ref.10 Cold kne Holding pumpe cubcle -807& 1RT02B4 S&L Ret 24 Redundert LD eved.
CYGNA Ref.10 Cold kne Hoking pumpe cubcle - 807C IN4 S&L Ref. 24 Redundert LD eved CYGNA Ref.10 Cold kne Holding pumps cubicle -807& 1RTD40C-4 No ggt pg 74 Redundert LD evel CYGNA Ref.10 Cold kne 2 Holding pumps cubcle -807& 1RTD48-4 S&L Rd 24 No Redundert LD sved. 2 [S hp '
O <
CYGNA Ref.10 Cold kne Holdng pumps cubicle -807& IN N m 2 sat pet. 24 Redundert LD evoi. .'
W .O. _o g~
CYGNA Ref.10 N
Cold kne :
Hoking pumps cubcle - 807& 1RTD4CBG Redundert LD eveil.
S&L Rd 24 O-CYGNA Ref.10 Cold kne Hoking pumps cubcle-807& 1RTD4CCG S&L Ref 24
" Redundert LD eved
$ C'3, m
ow
- ON N A
/N
\
N p
{G \vh ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PlPELINEIAREA EVALUATIONS Coh ;LUSeON REQ.
ROOM DESCRIPTION UNENO. REASON TEMP MONITORING NOT REQUIRED TEMP. CALC. REF.
REFERENCE T7 CYGNA Ref.10 Cold kne Holdng pumps cutscle -807g 1RTD4DA-4 "
S&L Ref. 24 Re&ndert LDS eved CYGNA Ref.10 Cold hne Holdng pumps cubcle -807a 1N S&L Rd. 24 Re&ndert LDS ewed-CYGNA Ref.10 Cold hne Holdng purge cutsc6s -807g 1RTDdDC-4 No S&L Rd 24 RN LDS eved CYGNA Ref.10 Cold hne Hofig pumps cubcle -807g 1RTMAA4 Redundert LDS eved S&L Ref 24 CYGNA Ref.10 Cold kne Holding pumps cubicle -807g 1N ggt p.g.24 No Re&ndert LDS eved CYGNA Ref.10 Cold kne Holdng purms cubicle-807g 1RT05AC-4 "
S&L Ref 24 Re&ndert LDS ewed CYGNA Ref.10 Cold kne Holdng pumps cubele -807g 1RTEBA 3 No S&L Rd 24 Re&ndert LDS eved CYGNA Ref.10 Cold hne Holdng purnos cubcle-807a 1RTEBBG Re&ndert LDS eves S&L Ref. 24 CYGNA Ref.10 Cold kne Holdng pumps cubcle 807g 1MM S&L Ref. 24 N
Re&ndert LDS eved i
CYGNA Ref.10 Cold kne .
Holdng pumps cubecle-807g 1R N S&L Ret 24 Redundert LDS eved CYG*4A Ref.10 Cold kne Holding pumps cubecle -807c 1RTTCB-4 Redsdard LDS evaa S&L Ref. 24 CYfv4A Ref.10 Cold kne .
Holding pumps cubecle -807g 1RTTC-4 Re&ndert LDS eved S&L Ref. 24 Holdng purque o_A-ia - 807g 1RT06AA-4 S&L Ref. 24 - Muesy in RWCU ppe tunnel Holdng pumpe r* *w4a -807g 1RTOSABA S&L Ref. 24 - Muesy an RWCU heat exchanger room A,6 Holdng pumpe cubcle - 807g 1RTOSA-4 S&L Ref. 24 - Aduesy in RWCU pape tunnel ,
^ ' N Holdng pumps ettacle -807g 1RT12A-4 Rd R LDSeved CYGNA Ref.10 Cold kne Holdng purnps cubcle - 807g 1RT128-2 S&L Rd 24 Re&ndert LDS eved.
CYGNA Ref.10 Cold kne Holding pumps cuticle -807c 1RT12C4 N S&L Ref 24 Re&ndert LDS eved CYGNA Ref.10 Cold hne 2 E O 's Holdng pumps cubcle -807c 1RT20AA-3 "
S&L Ref. 24 Redundert LDS sved E f, @ I CYGNA Ref.10 Cold kne Holding panps cubscle -807a 1RT20 ABO S&L Rd 24 No Redundert LDS eved fT)
- 8 0Z;.
CYGNA Ref.10 Cold kne -
Holdng pumps cubcle- 807c 1RTMC-3 S&L Rd 24 Redundert LDS eved CYGNA Ref.10 Cold hne <
Holdng pumps cubicie -807g 1RT21AA-2 Re&ndent LDS eved S&L Rd 24 CYGNA Ref.10 Cold kne {
Holding pumps cubscle -807g 1RT21AB-2 w S&L Rd 24 Redundmet LDS eved
( O 3 ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS REASON TEMP MONITORING NOT REQtMRED TEMP. CALC. RtEF.
ROOM DESCRIPTION UNE NO. ,
CYGNA Ref.10 Cold kne Hoking rumpe cabele -807c 1RT21 AC-2 Redundert LDS eved S&L Ref 24 CYGNA Rc".10 Cold kne Hoktng pumps cshcle - 807s 1RT2h2 S&L Ref. 24 Redsndert LDS eyed CYGNA Ref.10 Cold kne Hoking pumps a m -807g 1RT21BB-2 N S&L RW 24 Recbndert LDS ewed CYGNA Ref.10 Cold kne Hoking pumpe ethcle - 807g 1RT21BC-2 Redundant LDS eved S&L Ref. 24 CYGNA Ref.10 Coid bne Holctng pumps cabcie -807e 1N1 M " Redundert LDS eved S&L Ref. 24 CYGNA Ref.10 Cold kne Hoking pumps ctdncle -807g 1N2 S&L Ref,24 Redundert LDS eved ;
CYGNA Ref.10 Cold kne l Hoktng pumpe ethcie -807g 1RT2E2 S&L Rd 24 Redundert LDS eved CYGNA Ref.10 Cold kne 1RT23AC-2 f Hoking pumpe cubicle - 80Te S&L Ref. 24 Redundert LDS oved '
CYGNA Ref.10 Cold kne Hoking pumpe cutsele -807a 1RT230A-2 Redundert LDS eveil S&L Ref. 24 CYGNA Ref.10 Cold kne Hoking pumps cutscle - 807c 1RT23BB-2 Redundert LDS eved S&L Ref. 24 CYGNA Ref.10 Cold kne Hoking pumps cubecle - 807e 1RT23BC-2 "
S&L Ret 24 Redundert LDS eved CYGNA Ref.10 Cold kne Hoking pumps cabele-807g 1RT238-2 Recbndert LDS eved S&L Ref. 24 CYGNA Ref.10 Cold kne Hoking p.smpo cutacle - 807g 1N2 SEL Ret 24 Redundert LDS eved CYGNA Ref.10 Cold kne Hoking pumps cutncle -807c 1RT26AB-2 Redundert LDS sved S&L Ref. 24 CYGNA Ref.10 Cold kne Hoking pumps cubcle - 807g 1RT N 2 " Recbndert LDS ewed S&L Ref 24 CYGNA Ref.10 Cold kne Hoking pumps cubele -807g 1RT2mB-2 Redundert LDS ewed S&L Ref. 24 CYGNA Ref.10 Cold kne Hoking pumpe ethcie-807a 1RT2tBC-2 N S&L Rd 24 Redsndert LDS oved.
CYGNA Ref.10 Cold kne 1N Holding pumps cM -807g 1 rim 4 S&L Ref. 24 CYGNA Ref.10 W
Redsndert LDS eved Cold kne [f 'h >
" :. - F Hoking pumps cutncle -807g ggt p,g 74 CYGNA Ref.10 Redundert LDS eved Cold kne
[ g 7.
99 7'
1RT29AC4 Hoking pumpe cubicle -807c S&L Ref. 24 Redunctut LDS eved.
Cold kne g '[
M CYGNA Ref.10 Hoking pumps cubicle -807e 1RT29BA4 S&L Ref. 24 Redundant LDS owed Mg '
CYGNA Ref.10 Cold kne **
Hoking pumps cutacie - Borg 1RT29BB-4 S&L Rd 24 N
Rodridert LDS eved w' h *_I
,em.
(,~4 \
t
%)
\
%-) +O ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS REASON TEMP MONITORING NOT REQUIRED TEMP. CALC. REF.
ROOM DESCRfPTION UNENO.
ER CfGNA Ref.10 Coldine Holdng pumpe e_*h - 807c 1RT29BC4 " Redinde-t LDS eveil S&L Rsf. 24 CYGNA Ref.10 ColdIne Holdng pumpe e_*h - 807g 1RT/9EM No m Rd. 24 Re&ndert LDS eve 3 CYGNA Ref.10 ColdIne Holdng pumps a *h - 807g 1 N 110 N Re&ndert LDS eveil S&L Rd 24 CYGNA Ref.10 Coldine Holdng pumpe e.*h - 807g 1RTJOAB-11G No S&L Rd 24 Re&ndert LDS ave 4 -
CYGNA Ref.10 Cokikne Holdng pumps cubcle - 807e 1RT30AC-11G Redardert LDS aved S&L Rd 24 CVGNA Ref.10 Cold kne Holdng pumps a *h - 807s 1RT31BA-11G S&L Ref. 24 " Redindert LDS eved CYGNA Ref.10 Cold kne Holdng pumps a *h - 807g 1RT31BB-11G S&L Ref. 24 " Redandert LDS aved CYGNA Ref.10 Cold kne Holdng pumpe a *h - 807s 1RT31BC-11/2 S&L Ref 24 N Redundert LDS eyed CYGNA Ref.10 Cold kne I Holdng pumps a*h - 807g 1RT32AA-2 " "
S&L Ref 24 Redundert LDS evail.
CYGNA Ref.10 Cold kne Holdng pumps a ** - 807c 1RT32AB-2 " Redundert LDS emil
- S&L Ref. 24 CYGNA Ref.10 Cold kne Holdng pumpe a *h - 807s 1RT32AC-2 No S&L Rd 24 Re&ndert LDS eved.
CYGNA Ref.10 Cold kne Holdng pumpe a *h - 807g 1RT31AA-11G N '
S&L Rd 24 Reendert LDS evaa CYGNA Ror.10 Cold kne Haidng pumpe a *h - 807s 1RT33AB-1112 " Re&ndert LDS eved S&L Ref. 24 CYGNA Re4.10 Cold ine Holdng pumps cubicle - 807c 1RT33AC-1112 N S&L Rd 24 Red.,d_ert LDS eved .
CYGNA Ref.10 Cold brw Holdng pumps cubcle - 807c 1N4 N RedunM LDS eved S&L Ref. 24 CYGNA Ref.10 Cold kne Holdng pumps cubicle - 807g 1N sat p.g.-24 N
Redunda t LDS aved CYGNA Ref.10 Cold kne 1RTMCA "
Holdng pumps cubicle - 807g S&L Rd 24 Redundert LDS oved. 2%2 Holdng pumpe a *h - 807c 1RT34BA-4 CYGNA Ref.10 No ColdIne % .4 @
~~ f S&L Rd 24 Redundert LDS eve 3-CYGNA Ref.10 Coldline mb
- Zy R9 Holdng pumpe a.*h - 807c 1RT34BB-4 No ~'
S&L Rd 24 Redundert LDS evoi.
Holdng pumps a *h - 807g 1N CYGNA Ref.10 No Coldline 85 S&L Ref.24 Redundert LDS eved.
ColdIne
$E Holdng pumpe a eh -807g 1RT36A-2 CYGNA Ref.10 S&L Rd 24 N Redundert LDS avea.
gE y$
CYGNA Ref.10 Cold kne .
Holdng pumpe a *h - 807c 1N-4 No '
satp.g.24 Redundert LDS eved
(v/
~
( ! \ f v m_J ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS ROOM DESCRIPTION LINE NO. REASON TEMP tAOMITORING NOT REQUIRED T EMP. CALC. REF.
CYG4A Ref.10 Cold bne Hofdng ptsnps ethcie - 807& 1RT41 A-2 N Rd N R h Wavad CYGNA Ref.10 Cold Irve Hafdng pumps cutacle - 807c 1RTM21/2 N S&L Rd 24 Redindert LD avad CYGdA Ref.10 t old hne Holdng pumps ethcle - 807& 1RT488-21/2 N S&L Rd N Redandant LD avad CYGNA Ref.10 Cold hne Holdng pumps cthcle - 807F 1RT66A-2 N S&L Rd N Redundert LD avad 10 Holdng pumps cutacle - 807& 1RT75A-2 N 3g R LD avad Area between pwnery cortarvnert & CSCS cutacle IRHO1 AA-24 S&L Ref. 24 No Wide open area, temp LD unpractcal Redindert LD avad Area between prrnary cortainmort & CSCS cutacle IRFO1 AB-24 S&L Ref. 24 No Wide open area, temp LD unpradcal. Redundart I.D avad Area between pnmary cortsenmert & CSCS cutacle I RHO 4C-20 S&L Ref. 24 No Wide open area, temp LD unpractcal Redundert LD avad Area be..xa prrnary cortainmort & CSCS cutzcle 1 RHO 4DA-18 S&L Ref. 24 No Wide open area, temp LD rnpradeel Redundert LD avad Area tmtc:;a pnmary cortainmort & CSCS a_heia 1 RH04DB-18 S&L Ref. 24 No Wide open area. temp LD rnpadcal Redundart LD avad Area bere prenary cordainmort & CSCS cutacle IRHOEWL3 S&L Ret 24 No Wide open area, temp LO empadcal Redundard LD avad Area tutween prnary cortarvnent & CSCS cutzcto 1RH06AB-3 S&L Ref. 24 No Wide open area, temp LD rnprodcol Redundert LD eved Area La;.na prwnary cortaintnert & CSCS a% 1RH50A-20 S&L Ref. 24 No Wide open area, temp LD empractcal Redundart LD avad Area between prrnary cortarvnert & CSCS cubicle 1RH568-18 S&L Ref. 24 No Wide open area, temp LD wnpradcal Redundart LD evad ,
Area between prenary cortainmert & CSCS cutzcle 1RH57A-24 S&L Ref. 24 No Wide open area, temp LD rnpaccal Redundait LD avad
"^ N Area between pnmary cortainment & CSCS cutacle 1RIO2A-10 R W area t LD inpractical Red;ndart LD avad Area between primary cortainmort & CSCS cubicle 1R141 A-10 N D impradcal Redundart LD avad R Ade a es t Y R 10 "
Area tetween primary cordainmert & CSCS cutacle IR141BA-10 gg N D impradcal Redundart LD aval
- a. t 10 Area between pnmary cortarvnert & CSCS cutacle 1R141BB-10 N W area t D impractcal Redandart LD avad Area tWween pnmary cortainmert & CSCS cubcle 1RiO5A-2 N D empradcal Redur dart LD aved R a at 1RIC8A-4
^ No LD Area between pnmary corsainmert & CSCS cutacle Rf g ,,ea t D rnpradcal Redundart LD avad
'*P"""'** #"E ""P' "
Precoat tank room- 820s 1RT298-4 CYGNA Ref.10 No svadable
"* 'd* @*" "'** '**P ""F"** * ""d*'#
ommn Precoat tank room - 820-6" 1RT348-4 CYGNA Ref.10 No avadable o, e g c, h
Precoat tank room - 820F 1RT37A-11/2 CYGNARef 10 No avaaable P"""'**** * ""F moZ 7 Precoat tank room - 820s 1RT38A-3 CYGNA Ref.10 No
""*' P*" "'** ***P " **I
9 O available - -
No
""'****P N di Precoat tank room-820s 1RT40A-2 CYGNA Ref.10 available AO Precoat tank room - 820F 1RT44A-6 CYGNA Ref.10 No available P"" *** "P " *"F O[
to 4-
V '
V ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINE /Ahr'A EVALUATIONS
" L i TEMP. CALC. REF.
ROOM DESCRIPTION LINE NO. REASON TEMP MONITORING NOT REQUIRED ERE E T 1RT45AG CYGNA Ref.10 No
"*' P'" "**I N *"#
Precoat tenk room - 820& evetable 3 " " * *
- N Precost tank room - 820-6" 1RT46A-2 CYGNA Ref.10 No 4> evad=N.
- Cold M open mee temp W e gWd Rh W Precoat tank room 820 6" 1RT47A-21/2 CYGNA Ref.10 No
- pen wee tg LD e enped Rh W Precoat tank room - 820-6" 1RT478-21/2 CYGNA Ref.10 No eve 4eth S&L Ref. 25 Redundert LD provided S&L, Ref. No 9 RWCU heat exch room A-786r 1RT02BA4 N h* Temperature 1.D recor imended to increase renabilty of LD syst S&L Ref. 25 Reduridert LD provided S&L, Ref. No 9 RWCU heet exch room A-786g 1RTU3AAA " Temperdure LD recommended to increase rehebey of LD syst This cele.
CYGNA Ref.10 Cold kne RWCU heat exch room A -786E 1RTD4AA4 N S&L Rd 25 Redundert LD povided CYGNA Ref.10 Coldirm RWCU heat exch room A -786g 1RTD4BA-4 N Redsnda t LD povided S&L Rd 25 CYGNA Ref.10 C etkne RWCU heat exch room A - 7 Bgg 1RTOSCA-4 N Redundert LD povided S&L Rd 25 CYGNA Ref.10 Cold kne RWCU hed exch room A - 786-6" 1RTDEDA-4 N
- S&L Ret 25 Redsndert LD povided RWCU heat auch room A-786& 1RTO6AA-4 N '
Tm Wr .. M to encrease rehabMy of LD syst No F "
RCWU hem exch. room B - MIF 1RT02BB-4 , , ,,of LD syst CYGNA Ref. ' Cold kne RCWU heat exch. room B - 786s 1RTU28-4 S&L Ref. 25 Redunif LD provided RCWU heat exch room B - 786-6" 1RTQ3AB-4 N '
Temper e D ecommendedto increase rebebaty of LD syst CYGNA Ref.10 Cold kne RCWU heat exch room B - 786E 1RTD4AB-4 N S&L Rd 25 RMM W pW CYGNA Ref.10 Cold hns RCWJ heat exch room B - 78gg 1RTD4BA-4 " Redundert LD provided S&L Ref. 25 CYGNA Ref.10 Cold bne RCWU heat exch. room B - 786-6= 1 M B4 Redundant LO provided S&L Ref. 25 RCWU heat exch. room B -786E 1RTD5CA-4 gg N LD povided A
RCWU heat exch room B - 786& 1RT05CB4 N LD providerf C
R ,
10 RCWU heat exch room B - 786& 1RTD5DB-4 No W pm R
25 "'
Et tCWU heat exch. room B - 786-6* '1RTOSAA-4 N ,"
empor e LD recommended to increase reEatAty of LD syst.
RCWU heat exch room B - 786-6" 1RTD6AB-4 N S&L, Ref. No. 9 Te Dr h he mdWW bW O PO 90 4
ATTACHMENT E
SUMMARY
TABLE OF THERMAL LO PIPELINEIAREA EVALUATIONS ROOM DESCRIPTION UNENO.
fERENCE T7 RCWU heat orch room B - 786'-6* 1RTWA-4 N R LO provided C A 10 RCWU heet exch. room B - 786'-6" 1RT66A-2 g No gp R 25 *"
RCWU heat orch roorn B - 786-6' 1RT67AB-2 N emperature D W to increase rehetmity of LD syst MS ppe tunnel -lower / upper 1FWO2BA-24 CYGNA Ref.10 Yes Ceco, Ref 15 MS ppe tunnel-lowerA;pper IF WO2PB-24 CYGNA Ref 10 Yes Ceco.Ref 15 MS ppe tunnel . lower / upper 1FWO2FA-24 CYGNA Ref.10 Yes CECO, Ref.15 MS ppe tunnel- lower / upper 1FWO2FB-24 CYGNA Rsf.10 Yes CECO,Ref 15 M S ppe tunnel . lowerturper 1FWO2HA-24 CYGNA Ref.10 Yes CECO. Ret 15 MS ppe tunnel . lowerlupper 1FWO2HB-24 CYGNA Ref.10 Yes Ceco. Ref 15 MS ppe tunnel- lower / upper 1FW11 AA-4 CVGNA Ref.10 Yes CECO, Ref.15 MS ppe tunnel -lowerfbpper 1FW11 AB-4 CYGNA Ref.10 Yes CECO, Ref 15 MS pp turmel -lowerfupper 1FW11 A-4 CYGNA Ref.10 Yes CECO. Ref 15 MS ppe tunnel . lower / upper 1MSO1BA-26 CYGNA Ref 10 Yes CECO, Ref 15 MS ppe tunnel-lower / upper 1MSO1BB 26 CYGNA Ref.10 Yes CECO. Ref.15 MS ppe tunnel- lower / upper 1MSO1BC-26 CYGNA Ref.10 Yes CECO Ref 15 MS ppe tunnel -lowerfupper 1MSO1BD-26 CYGNA Ref.10 Yes CECO, Ref 15 ,
MS ppe tunnel . lowerrupper 1MSO1EA-26 CYGNA Ref.10 Yes CECO. Ret 15 MS ppe tunnel - lowerfurper IMSO1EB-26 CYGNA Ref.10 Yes CECO. Ref 15 MS ppe tunnel -lowerturper 1 MSO1EC-26 CYGNA Ref.10 Yes CECO, Ref 15 MS ppe tunnel . lower / upper 1MSO1 ED-26 CYGNA Ref.10 Yes . CECO, Ref 15 MS ppe tunnel -lower / upper 1MS148G CYGNA Ref.10 Yes Ceco, Ref.15 MS ppe tunnel -lower / upper 1MS14C-12 CYGNA Ref.10 Yes CECO. Ref.15 MS ppe tunnel - lower / upper 1MS14DG CYGNA Ref.10 Yes CECO Ret 15 MS ppe tunnel . lower / upper 1 MS14E-3 CYGNA Ref.10 Yes Ceco, Ret 15 MS pro tunnel - 10werAJpper 1MS16AG CYGNA Ref 10 Yes CECO, Ret 15 MS ppe tunnel . lower / upper IMS19AG CYGNA Ref.10 Yes CECO Ref.15 MS ppe tunnel-Im . Ay,et I MS19BA-2 CYGNA Ref.10 Yes CECO, Ref 15 MS ppe tunnel-lows peer 1 MS1GBB-2 CYGNA Ref.10 Yes CECO, Ref.15 MS ppe tunnel -lowowpper 1MS19BC-2 CYGNA Ref.10 Yes CECO, Ref.15 MS ppe tunnet - town. Asper 1MS190D-2 CYGNA Ref.10 Yes ____
CECO, Ret 15 MS ppe tunnel -lowertupper 1MS198G CYGNA Ref.10 Yes CECO. Ret 15 MS ppe tunnel -lower / upper 1MS20AA-2 CYGNA Ref.10 Yes CECO Ref 15 MS ppe tunnel-lowertupper '. MS20AB-2 CYGNA Ref.10 Yes CECO. Ret 15 7 JD U O
, $ $ $, E-MS ppe tunnel - lower / upper 1MS20AC-2 CYGNA Ref.10 Yes CECO.Ref 15 MS ppe tunnel -lowerAspper 1MS20AD-2 CYGNA Ref.10 Yes Ceco Ref.15 *L* E MS pre tunnel -lower / upper MS ppe tunnel -lower / upper 1MS20BA-1 1/2 1MS20BB-1 112 CYGNA Ref.10 CYGNA Ref.10 Yes Yes CECO, Ref.15 CECO. Ret 15
@OhZ**
MS ppe tunnel - lowerrupper 1MS20BC 11/2 CYGNA Ref.10 Yes CECO, Ref 15 y ~, '.
MS ppe tunnel lowerAJpper 1MS20BD-1 1/2 CYGNA Ref.10 Yes Ceco. Ret 15 N6 MS ppe tunnel . lowerfupper MS ppe tunnel-lowerAsrper 1 MS20CA-1 112 1MS20CB-1 1/2 CYGNA Ref.10 CYGNA Ref.10 Yes Yes CECO Ref 15 CECO, Ret 15
$O gg
, ON f0 A
) -f- }
0 ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS L REASON TEMP MONITOR!NG NOT REQUIRED TEMP. CALC. REF.
ROOM DESCRIPTION LINE NO.
ERE E 1MS20CC-1 1/2 CYGtaRet 10 Yes CECO. Ref 15 M S ppe tunnel - lowerA-=r Ceco, Ref 15 MS ppe tunnel-IcwerA==r 1MS20CD-1 1/2 CYGNA Ref.10 Yes Yes CECO, Ret 15 M 1 ppe tunnel -lowerAger 1MswD-1 1/2 CYGNA Ref.10 1MS25AA-2 CYGNA Ref.10 Yes CECO. Ref 15 M3 ppe tunnel-lowerA==r CECO, Ref 15 MS ppe tunnel-lower / upper 1MS25AB-2 CYGNA Ref.10 Yes CYGNA Ref 10 Yes CECO, Ref 15 MS poo tunnel-lowerA-=r 1MS25AC-2 Yes CECO, Ref 15 MS ppe tunnel -lowerAspper I MS25AD-2 CYGNA Re(,',9 CECO, Ref 15 MS ppe tunnel-lowertumor 1MS25A-12 CYGNAIs' L1 Yes Yes CECO, Ret 15 MS ppe tunnel-lowerA-=r 1 MS88AA-1 1/2 CYGNA Ref.10 Yes CECO, Ret 15 MS ppe tunnel -lowerA--r 1MSB8AB-11/2 CYGNA Ref 10 Yes CECO, Ref 15 MS ppe tunnet -lowerAn=< 1MSB8AC-11/2 CYGNA Ref.10 Yes Ceco, Ref 15 MS ppe tunnel-lowerAwar 1MS88AD-1 1/2 CYGNA Ref.10 1MSC1 AA-1 1/2 CYGNA Ref.10 Yes Ceco. Ret 15 MS ppe tunnet -lowerA rar CECO, Ref 15 M S ppe tunnel - lowerA_==r 1MSC1 AB-1 1/2 CYGNA Ref.10 Yes CYGNA Ref.10 Yes Ceco, Ref 15 MS ppetunnel-tri sti==r 1MSC1 AC-1 1/2 1MSC1 AD-1 1/2 CYGNARef 10 Yes CECO. Ref 15 MS ppe tunnel - lower / upper Ceco, Ref.15 MS ppe tunnel-lower / upper 1MSC1 A-21/2 CYGNA Ref.10 Yes Yes CECO, Ref 15 MS ppe tunnel-lowerAwar 1MSC3A-2 CYGNA Ref.10 Yes CECO, Ref 15 MS ppe tunnel-lowerA==r 1RT06A-4 CYGNA Ref.10 ,
CYGNA Ref.10 Yes CECO, Ref 15 MS ppe tunnel -lowerAr-r 1RTOEE-4 CYGNA Ref.10 Yes Thes calc.
RCIC e- -Te1 room - 6U-4" - 1RTO1D-4 CYGNA Ref.10 Yes Tras calc.
RCIC eq%se-a room - 6U-4* 1RIO1F-10 CYGNA Ref.10 Yes Thes calc RCIC equpret room - 6U-4" 1RIO2A-10 .
1RIO2B-18 CYGNA Ref.10 Yes Ttus calc.
RCIC equipmert room - 6U-4" 1RIO2C-10 CYGNA Ref.10 Yes Tfus calc RCIC equp e1 room - SU-4" 1RIO7A-2 CYGNA Ref.10 Yes Itus calc.
RCIC equipmert room - SU-4" 1R112A-6 CYGNA Ref 10 Yes Ttus colc RCIC eqwife 4 room - 673-4" Rem cooling sMh e m M temp. as low, hefwe, temp RCIC pipe chase - 710-6" 1RH048-20 S&L Ref. 25 No LD imprwecal
" " # "P " - "**'**P' RCIC pipe chase - 710E 1 RHO 4C-20 S&L Ref.25 No LD impratical
" " " # I"*P' " *"*'"***P RCIC pipe chase - 710-6" 1 RHO 4F-20 S&L Ref. 25 No LDimpratical
" " " '""P~ "*'"**'"P' RCIC pipe chase - 710E 1 RHO 4G-20 S&L Ref 25 No LD impratical 0 " * **P "**'**P RCIC pipe chase - 710-6" 1RH41AA4 No LD impratical . . --- o i S&L Ref. 25
" '" '"* *'"P~ "***"P $ Z RCIC pipe chase - 71GE 1RH48A.3 S&L Ref.25 No a *-
CYGNA Ref.10 Reactor wv; 4 shutdown mode is short, temp. m low,therefwe, temp.
RCic pipr chase - 710E 1RH70AJ S&L Rd 25 N LD impratical OC
"* * * ""P' * "**'""P O RCIC ppe chase - 710E 1RHG9A-11/2 S&L Ref. 25 No LD imprwicai 9m
.ou o to -
f0 A
ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS
" TEMP. CALC. REF.
ROOM DESCRIPTION LINE NO- REASON TEMP MONITORING NOT REQUIRED FER sedM C ng shtadmn modo es short, temp a km,Omrefore, temp RCIC ppe chose -710F 1RHGEM-1 1/2 . S&L Ref. 25 No LD irwrdeal RCC ppe chose - 710& 1RO1 A-10 The calc. Yes The cale RCIC ppo chose - 710E 1RO18-4 Thes cele. Yee Thrs caic.
RCIC ppe chose - 710& 1 RO1C-4 Thrs ceic. Yes This calc 1Rl41 A-10 Thrs ceic Yes TNs case RCIC ppe chose - 710E RCIC ppe chose - 710& 1 RIB 1 A-1 1/2 TNs cale. Yes Thrs cale Reactor cochng shddown mode is short, temp a kw,threfore, temp RHR pumpthod.exch. room A - 6U# 1RH32AA-24 h R&g No- LD knpractical Redundert LD is available Reettor coohng shtadown modo rs short, temp es km,therefore, temp.
g RHR pumphes-exch. room A-6U-4* 1RHQ2AA-18 No. LD imprecical Rd N Redunde/t LD is avedable Reactor cochng shutdown mode is short, temp es low, therefore, temp 1RFf1MA-18 No LD impractcal RMR pumpthed4xch room A-6U-4* SE Rb Redmdart LD is avadable Reettor cochng shtidown mode es short, temp es low, therefore, temp g
R@ pump /heetexch room A-673# No. LD impractcal 1RHU3BA-12 S& Rb Redundert LD is evadetWe >
Reedor cochng shtidcwn mode es short, temp es low, therefore, temp.
RHR pumpheat-exch. room A-6U# 1Rt040A-18 gg pg No LD impadcol.
Re&ndert LD is avsamble N8 W Mh 6 m M temp as km,therefore, temp This cafe.
RHR purap/ heat-exch. toom A - 6U# 1RHG5BA-3 Na LD knpredcal S&L Ret 24 Redundert LD is eveileth g Reador cochng shut @wn modo es short, temp es km,therefore, temp RHR pumpheat-exch room A-GU-4" 1RH12AA-8 S&L Rg No. LD anpradcol Redundert LD is evadable Reedor coohng shtidown mode es short, temp s low, therefore, temp TNd RHR pumpheat-exch room A-6U-4* 1RH13AA-18 p No. LD impedcal.
Redundert LD to evadable g Reedor cochng shLidown mode es short, temp is km,therefore, temp RHR pumpheatexch. room A - 6U 1RH18AA-18 S& Rg No LD improdcal Redundert LD is avadable Reedor coohng shLadown mode is s%t, temp is low,therefore, temp gg RHR pumpthea* cch room A- 6U-4* 1RH19AA-18 ,
mRG No. LD irgractcal. g g "U Q Redundert LD is evadable to ,< S. g 7g Reedor cochng shtadown rnode is short, temp es low, therefore, temp "2' m o og RHR pumptheatexch room A-6U-4" 1RH19BA-18 gg pg No. LD knprodcal.
Re&ndert LD is evodeble Reedor coohng shtidown mode es short, temp is low, therefore, temp or RHR pumpthest4xch. room A- 6U-4" 1RH19CA-10 yg g pg~ 24 No. LD imorsdcat. goO Redundert LD is evadable m bW OM '
, N A
m (pgU) k) v ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS ON "
REASON TEMP MONITORINGiMT REQUIRED TEheP. CALC. REF, ROOM DESCRIPTION LINE NO, gp E Reedor coohng shutdown mode is short, temp a tow, therefore, temp.
g RHR pump /heetexch room A - 6D-4" 1RH19DA-to gpg Ho_ LDirnpredcol Redmdert LD is availetdo Reedor M g shtAdown mode is short, temp es low,therefore, temp PHR purnpthestexch room A 6U-4" 1RH230A-4 No. LD impedcot Rd 24 Redmderd LD is evedeble Reedor cochng shutdown rnodo es short, temp is low, therefore, temp g
No. LDimpredcat RHR pumphestexcit room A - 6U-4" 1RH24AA 11/2 M Rd] Redmdert LD is evedable Reedor og shutdown mode is Joi, temp es low, therefore, temp g
RHR pumptheet-exch rcom A - GU-4* 1RH26AA-4 Rg No. LD impractcal Redundert LD is evadable Reedor n y shtadown mode es short, temp as low, therefore, temp g
No. LD improdcol RHR pumptheet-exch room A-6U-4" 1RH29AA3 S Rdh Redmdart LD is evadable Reedor n y shurcbwn mode is short, temp is low, therefore, temp RHR p ==4 wet-exch. room A - 6U-4" 1RH39AA-4 gg No. LD imprecical Redmdert LD is avedable Reedor M y shticbwn mode es short, temp *s low, therefore, temp ,
RHR pumptheaterch. room A - SU-4" 1RH40CA-16 No. LD enproacet m Rd 24 Rediedert LD is eveilable Reedor M y shtAdown modo es short, temp as bw therefore, temp RHR pump /heateuch room A-6U-4" 1RH76A-1112 No. LD improdcei M @d S& R 24 Redindert LD is evadable Reedor cochng shutdown rnodo es eu;, temp es low, therefore, temp gg RHR pump /heet-exch. toom A - 6U-4" 1RHG3AA-2 MRg No. LD impedcot Redundert LD is evadable Rondor coohng shtadown modo es short, temp ts low, therefore, temp gg RHR pump /hooterch. toom A - 6U-4" 1RHG7AA-2 S&L Rek 24
- N*#
Redundert LDis evadable RHR pump /heaterch. room A - 6U-4" 1R141BA-10 No Redundert LD is avadable R 2 Reactor cochng shtidown rnode is short, temp es low, therefcre, temp gg RHR pump /heet-exch room B/C - 6U-4" 1RH01AB-24 pg No. LD improdcat Redundert LD is evadable Reedor coohng shttdown modo es short, temp is low, therefore, terro y,y g
RHR pump /heet-exch roorn B/C - 6U-4* 1Rt02AB-18 pg g No. LD impredical g a g a, Redundert LD is evadable e. ?o Reedor M g shtAdown mode is short, temp rs low,therefore, temp rn 2 ,o2
--O. R g'
RHR pumpheetexch room B/C - 6U-4" 1RHG3AB-18 % p*g No. LD improdcol Redundert LD is evadsbie - --
O r"-
Reedor e y shutdown mode is short, temp to low, therefore, temp.
g O RHR pump /heet-exch room B/C - 6U-4" 1RH04DA-18 h &gp g No. LD impredicat Redundert LD is available ?-
OW
, OM NA
ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS LINE T10, C REASON TEMP MONITORING NOT REQUIRED T EM P. cal $ . REF.
ROOM DESCRIPTION E Reedor coohng shutdown modo es short, temp es low, therefMe, ter@
RHR purrp/ heat-exch roorn BC - SU# 1RHMOB-18 g pgf No. LD impreocal Re&ndert LD is evedoble Reactor i.uv;.,9 shttdown mode a short, temp es now, therefore, ter@
g RHR purnp/hed-exch. room BC - SU-4* 1RHMEA-18 g pg] No. LD impradeel Re&ndert LD is evadetde Reactor cochng shtAdown mode es short, temp es low, ttwofore, temp g
RHR purnph3-exch room BC - SU-4* 1RtO4EB-18 No LD imprarbcal.
m Rdh4 Redundert LD is avedable Reedor suu;.is shiAdown modo is short, temp as low, therefore, temp RHR pumptheat-exch. room BC 6U-4" 1RHIiBB-3 g pglg No LD impractest Redmdert LD is evedable ;
Reactor M 9 stodown mode is short, temp is low,therefore, temp.
h& No. LDimpactcal 1RH12AB4 RHR pump 4 met 4xch. room BC - SU-4" m Rdh Redundert LD is avedeble Reedor coohng shutdown mode is short, temp es low, therefore, ter@
g RHR pump /heet-exch room BC -SU# 1RH13AB-18 No LD impredral.
g pgy Redundert LD is evadable Reedor M g siddown rr. ode is short, temp is low, therefore, temp. ,
No. LD irnprodcal RHR pump / heat-exch. room BC - SU-( 1RH18AB-18 m Rd] Redundert LD is evadetne Reedor coohng studown mode oc t.hort, temp is low,therefore, temp g
RHR pump / heat-exch room BC - 6U-4" thM19AB-18 g pgf No. LD impradca! .
Re&ndert LD is evedeble Reedor coohng stodown mode es stxwt, temp es low, therefore, temp g
No LD impredcal RHR pump /heet-exch room BC - GU-4" 1RH 9BB-18 m Rdh Rededert LD se evadable Reedor coohng shutdown rnode es short, temp os low, therefore, temp g
Nc. LD impredical RHR pumptheet-exch roorn BC - 6U-4" 1RH19CB-10 m Rd] Redundert LD is evadable Reedor cochng shutdown rnode es short, temp as low, therofore, temp gg 1RH1908-10 e. LD impractent.
RHR pumptbest exch. room BC -GU-4" m Rdh Redunderit LD is evedeble Reedor coohng studown mode is short, temp is low,therefore, temp TnUO gg g a g al RHR pump / hest-exch room BC - 6P-4" 1RH23BB4 No. LD impractcal Rd N Redundert LD is evedoble *:.* P g Reedor cochng <udown mode is short, temp es low, therefore, temp $Oh2 u"-O RHR pumptheat-exch room BC 6U-4* 1RH24AB-1 il2 g ggl3 No. LD impredical Re&ndert LD is e o ,_
g Reactor coohng stM&wn rnodo es short, temp es low, therefore, temp u6 RHR pump /heet exch room BC- 6U-4* 1RH26AB-4 Rd N No. LD improdcol $o Redundert LD is evadeHe 6w ON Mb
O O C ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS REASON TEMP MONITORING NOT REQUIRED TEMP, CALC. REF-ROOM DESCRIPTION LINE NO.
RHR pumphed-exch. room BC - 6U-4" 1RH2!MB-3
[ Reedor coohng sMdown mcr% is short, temp n low, therefore, temp No. LD impredcol m Rd N Redundant LD is avad=Na Reeds e q eMcbwn mode es short, temp is low, therefore,ter@
g RHR pumpheatexcit room BC - SUV 1RH3CW4 Ne- LD impredcol.
Rd N Redundert LD is evelable Reactor coohng shddown mode n short, temp es low, therefore, temp.
h& No. LD improdcol.
RHR pumpMeat-exch room BE - 6U-4* 1RH39AB-4 gg Redundert LD is evodeble Reactor M, shddown ne es short, temp es low, therefore, temp FtHRpsnpheat-exch room B/C-6U4" 1RH40CB-16 No. LD improdcol m Rd 24 Redundert LD is evadable Reedor u,v; y shutdown mode es short, temp es low,6; ore, temp RHR pumpfhed-exch. room BE - 6U4* 1RH56818 ggg No. LD improdcol Redundert LD is evadable Reector coohng shddown mode es short, temp es low therefore, temp.
RHR pumpMeateach room B/C - SU-4" 1RH708-11/2 mRg No. LD impractical Redunde t LD s evadable Reactor coobra shd:bwn mode es short, temp es low, therefore, temp ,
RHR pumpheaterch. room B/C - 6U-4" 1RHG3AB-2 m Rd 24 No. LD W .im.a Redimdert LD is eveileNo Reector coohng shddtmn modo rs short, temp ts low, therefore, temp RHR pumptheat4xch room BE - 6U-4" 1RHG7BA-2 mRg No. LD impedcol ,
Recundert LD is available -
Reactor cochng shddown mode e short, temp is low, therefore, temp RHR pumptheat-exch. room B/C - 6U-4" 1Rm2BA-11/2 mRb4 No. LD e' nprodcol RedJndert LD is avedable CYGt4A Ret 10 RHR pumpthest4xch. room B/C - 6U 4* 1Rl41BB-10 Rh m m Ro&vas*e ppe hatch - TJf& 1RT06A-4 S&L Ref. 24 No Redundant LD se evadable RWCU demn room A-820s 1RTO4DA4 CYGNA Ref.10 No Cold kne RWCU domm room A - 837-6" 1RTO5AA4 CYGNA Ref.10 No Cold kne RWCU domm rocen A -820s 1RT20AA,3 CYGNA Ref.10 No Cold kne RWCU demn room A - 820-6* 1RT20BAJ CYGNA Ref. TO No Cold kne RWCU domin room A - 820-6* 1RT20BC-4 CYGNA Ref.10 No Cold kne y yg RWCU demn room A-820-6" 1RT26AA-2 CYGNA Ref.10 No Cold kne ga3g' 1RT2fBA-2 CYGNA Ref.10 No Cold hne e ;, r p RWCU domm ivu..e A - 820-6" RWCU a. , room B - 620F 1RTA2AA-1 1/2 CYGNA Ref.10 No Cold kne m o Z 7 l
RWCU demn room B - 820-6" 1RTO48-4 CYGNA Ref.10 No Cold kne ya3o -* " t RWCU domm room B -820s 1RTD4DBA CYGNA Ref.10 No Cold kne O
i RWCU domm room B - 820 1RT05AB-4 CYGNARef 10 No Cold kne RWCU domm room B - 820s 1RT20AB-3 CYGNA Ref.10 No Cold kne Ao RWCU demo room B - 820s IRT20BB-3 CYGNA Ref.10 No Cold kne 9""
RWCU demn room B - 820-6" 1RT20BC4 CYGNA Ref.10 No Cold kne ON
~+
I
m O., O,.
ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINE / AREA EVALUATIONS L T EMP. CALC. REF.
ROOM DESCRIPTION LINE NO. REASON TEMP MONITORING NOT REQUNtED ERE RWCU denn room B - 820E 1RT21 A8-2 CYGNA Ref.10 No Cold kne RWCU damn room B - 82G& 1RT26AB-2 CYGNA Ref.10 No Cdd kne RWCU deman room B -820E 1RTA2AB-1 1/2 CYGNA Ref.10 No C(4d kne RWt U denn room C - 820-6* 1RTD4DC-4 CYGNA Ref.10 No Cok$kne RWCU demen room C - 820& 1RTUSAC-4 CYGNA Ref.10 No Cod kne RWCU denn room C - 820E 1RTC6C-4 CYGNARef 10 No Cold kne RWCU denn room C - 820E 1RTNA-4 CYGNA Ret 10 No Cold kne RWCU deman room C -82UE 1RT2 CMC-3 CYGNA Ref.10 No Cold kne CYGNA Ref.10 No Cold kne ,
RWCU demn room C - 820-6" 1R T21 AC-2 RWCU denn room C - 820E 1RT26AC-2 CYGNA Rel.10 No Cold kne RWCU 6 .-uws. C - 820E -
1RTA2AC-1 1/2 CYGNA Ref.10 No Cold kne S&L Ref.No 25 Redandert LD prwated S&L, Ref. No. 9 RWCU pump room A- 761*g 1RT01DAG Temporwure LD recommended to meresse rebetzity of LD syst h&
S&L Ref No. 25 Redundert LD prwided S&L,Ref No 9 RWCU pump room A - 761*g 1RTD2AAG p,, g W TemperWure LD recommended to increes, rehmbaty of LD syst S&L Ref. No. 25 RedJndert LD prwujed S&L. Ref No 9 RWCU pump room A- 761*g 1RTC6AA-3 No
- h calc. TemperWure LD r-..- .J d to increese rehabilty of LD syst S&L Ref. No. 25 Redandert LD provided S&L,Ref No 9 RWCU pump room A- 761*g 1RTC7AA 3 No h& Temperdure LD r- .- J.d to increase reliebdty of LD syst S&L Ref. No. 25 Rodandert LD prwided S&L.Ref No 9 RWCU pump room B - 761*& - 1RTD1DBJ N h cele. Temperature LD t_..- d d to increase reliebday of LD syst S&L Ref. No. 25 Redandort LD prwided S&a_, Ref No 9 RWCU pump room B - 761 g 1RT02AB,3 N h calc. Temperature LD recommended to increase retsbitty of LD syst.
No S&L, Ref No 9 RWCU pump room B - 761*g 1RTCGAB-3 p E', g RWCU pump room B - 761*& 1RTC7AB-3 No TW hhemy of W W S&L.Ref No 9 UgOg S [. 5 No S&L. Ref. No 9 f" o o2 2 '
RWCU pump room C - 761*g 1RTD1DCJ M calc. Temperature LD r-..- .J.d to increese rehebaty of W syst ga o !
RWCU pump room C - 761*-0* 1RT02AC-3 No emperature LD recommended to ir=reese rehabday of LD syst.
ms 1RTC6AC-3 No "
RWCU pump room C - 761*g emperature LD ocommended to increase rehebiity of LD syst.
l I
9 m ,q w
ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS LINE NO. REASON TEMP MONITORINO NOT REQUIRED TEMP. CALL. REF.
ROOM DESC'dPTKHi ER 1RTC7AC,3
" No S&L,Ref No 9 RWCU pump room C -761*& TNs cale. Temperature LD iw..-
to sicreese rebebMy of LD syst.
1RTD2BB4 No S&L.Ref No 9 RWCU veno room A/B - 786-6" This calc. Temperature LD recommended to sicreese rebatnity of LD syst RWCU velve room A/B - 786& 1RTU2B4 CYGNARef 10 No Cold kne RWCU valve room AS - 786& 1RTO4AB-4 CYGNA Ref.10 No Cold kne _
RWCU valve room A/B - 786-6" 1RTO4BA4 CYGNA Ref.10 No Cold hne RWCU vetve room A/B - 786& 1RTO4BB4 CYGNA Ref.10 No Cold kne RWCU veno room A/B - 786-6" 1RTO48 4 CYGNA Ref.10 No Cold kne RWCU valve room A/B - 786-6" 1RT06CB4 CYGNA Ref.10 No Cold kne RWCU valve room A/B - 786-6' 1RTaiC-4 CYGNA Ref.10 No Cold hne
" No E' S&L, Ref. No. 9 RWCU valve room A/B - 786E 1RTOGAB4 W . toincrease rehabey d LD sg RWCU vaNo room A/B - 786& 1RTDSAC4 S&L Ref. 24 No e D ecommended to increase rehabMy of LD syst.
i emper 1RTD6A-4 S&L Ref. 24 No S&L Ref No 9 o RWCU veno room A/B - 786-6" Temperature LD r ...- , ,to sicrease rehebay of LD syst RWCU valve room A>B - 786-6' 1RTOEM-4 CYGNA Ref.10 No Cold kne RWCU valve room A/B - 786& 1RTO9C 4 CYGNA Ref 10 No Cold hne a
RWCU valve iuv... A/B - 786& 1RT11 A-4 CYGNA Ret 10 No Cold hne RWCU da room A/B - 786-6* 1RT20BC4 CYGNA Ref.10 No Cold kne RWCU vatvo room A/B - 786-6" 1RT21 AB-2 CYGNA Ref.10 No Cold kne RWCU valve room A/B - 786-6' 1RT388-4 CYGNA Ref.10 No Cold hne RWCU valve room A/B - 7864' IfIT488-21/:e CYGNA fi W.10 No Cold hne RWCU valve room A/B - 786& 1RT66A-2 CYGNA Re' 10 No Cold hne
" S&L, Wei No 9 .
RWCU vane room A/B - 715'J-6* 1RT67AB-2 No ,
6 '
S&L.Ref No 9 RWCU valve room A/B - 786-6" 1RTCSAA-2 No g ,g g 8' "" S&L, Ref. No 9 RWCU valve room A/B - 786-6' 1RTCSAB-2 No g rn O 2-RWCU volve room A/B - 786& 1RTD6AB-4 8 " N dWW S&L, Ref. No 9 b"
- Or Turtane buskkng IMSO1CA-23 S&L Ref. 25 No. Wde open aree, temp LD improdcal. Re<Ondert LD avad Mf Turtxne tuidwig 1MSO1CB-28 S&L Ref. 25 No. Wute open eroe, temp LD improdcat. Redundert LD eved yC.
.Turtxne t</ iw 1MSO1CC-28 S&L Ref. 25 No. Wde open aree, temp LD improdcol. Redundant LD evad g{
1MSO1CD-28 S&L Ref. 75 No. Wde open eres, temp LD y--V.31. Redundert LD avad oN lTurtsne budchng w4
o o
\v)
ATTACHMENT E
SUMMARY
TABLE OF THERMAL LD PIPELINEIAREA EVALUATIONS C' REASON TEMP M00HTORMcG WOT REQUIRED TEMP. CALC. REF.
ROOM DESCRIPTION UNE No.
RE Turtune k21s 1MS25BG S&L Ref. 25 No. VWces open aree, temp LD enpredical Redundert LD eved Turtune h 2 ^ ,i, IMS2BAA-2 S&L Ref. 25 No. Wide open eree, temp LD sgrescal Ro&ndert LD eved.
1M328AB-2 S&L Ref. 25 No, VVkse open area, temp LD enpraecal Re&ndert LD eved Turtune h.%
Turtune h 2'- s 1MS28AC-2 S&L Ref. 25 No. VWde open eree, temp LD enpractical Redmdart LD eved Turtune k2* w 1MS28AD-2 S&L Ref. 25 No VWde open eres, temp LD empredical Re&ndert LD eved Turtano 5% 1MS2BA-12 S&L Ref. 25 No. VWde open eres,torg LD impredical Redundert LD eved.
Turtane 5_% 1MS28BG S&L Ref. 25 No. VWes open aree, temp LD impredical Re&ndert LD eved Turtune h2^-g 1MS32A-36 S&L Ref. 25 No VWde open eres, temp LD trgredical Re&ndere LD eved Turtune h-
^
v 1 M<roRA.18 S&L Ref. 25 No VWes open eres, tory LD sgredical Redmdart LD eved Turtune b% 1MS32BB-18 S&L Ref. 25 No. VWde open area, temp LD nmprescal Redundert LD evet Turtano 52As 1MS3BAA-18 S&L Ref.25 No. VVkie open eres, temp LD impredical Re&ndert LD sved Turtune k 2 ^-g IMSEAB-18 S&L Ref.25 No. VWde open eree, torg LD impraecal. Redurdert LD eved.
Pp eres between the MS tunnel ed & turtune inist 1MS01CA-28 This calc. No. VWde open eroe, temp LD impredical Re&ndert LD eved.
Pipe area between the MS tunnel est & turtune intet 1MSO1CA-2B This calc. No. VWds open area, torg LD impredical. Re&ndert LD eved Pipe area kneween the MS tunnel ext & turtune inest 1MSO1CB-28 This case. No. VWde open eres, tesg LD impreecal Rededwt LD ewed. ;
Pipe area between the MS tunnel out & turtune inist 1MSO1CC-28 TNs calc. No. VWde open eree, temp LD .y aa Redundert LD eved.
RWCU Pipe Tunnel 1RT06A-4 CYGNA Ref.10 Yes Redundert LD eved. This ceae.
lU RWCU Pipe Tunnel 1RT06AA-4 CYGNA Ref.10 Yes Re&ndert LD eved. Thrs cele
(* 1RT06A-4 S&L Ref. 24,25 No. Redmdurt LD eved. .
RWCU Velve Room .80T&
N!Lt 8 /elve Room -807& 1RT06AC-4 S&L Ref. 24,26 No Redundert LD ewed.
] t 22-ir S SOgz >
q * . . ,O a ..
m c r-5' QL .
N6 O
?O Ow OM Mb
Calc. No.: L-001324 Pro]. No: 10246@2 O Rev.: 00 Page F1 ,
I f
- 1 I
ATTACHMENT F Spreadsheet Csiculations of Ambient Air Temperature and Differential Temperatures for a LD System .
I I
l l
I O
1 1
AREA AMBIENT AND DIFFERENTIAL TEMPERATURE CALCULATION FOR REACTOR COOLANT LEAK DETECTION t
RCIC PIPE CHASE (710'-6") - WINTER INLET AIR CONDITIONS (Flow = 300 SCFM)
Outende Air c:-f._.::: o
- Pressure . , (pe.e > . iu. ,
Setocart Reference Temperature (T,) (*F) 4 .08.0 i g Notes: CC Mien 6ditv Retie 1, Grey come are inpJe to the spreedsheet Humiday Rate . e,l (ttw / lb.) l
- 8.8046W l 2. Ceee 0: No leek l 3. Ceee 1:Deteden flow rate Enter 6ne NVAC Air Conditlens 4. Case 2: loo 6 sten fkw rate Room Supply Temperature (T ) . OS - 5. Case 3. *Reesonable* detection (emp.
(*F)
- 6. Caos 4: Currert toch spec notpoort for Ertheipy of Dry Entenng Ar (h..) (BTUAt3 d 'E ?
Ertheepy of Water Vapor at T, (h,,) (BTUAb) 108092 g 7
Comtaned Erthalpy of Ertenng Moture (hi) (BTUAb) 24.36 etwwtist T (123 F)
Specific Volume (vi) (e3'Ib) 13.227 298 0 0 225 151 174 Volumstnc Fkw Rate (Q,) CFM (symm) 23 0 0 17 11 13 Mens Fkm Rate (m.)
" _ " _ - "-- - Peremesera Erthelpy of Saturned Lkned at Room Pressure (h.) (BTUAb) 180 18 Erthalpy of Saturated Steam at Room Pressure (h.) (BTUAb) 1150.48
~*
Total Heat instA (HL) (BTU /mm) 14llSSMdJ"48 M 2P(1583~ 6 - Jd Per-- e for 8 ==h ima F ' - - -"
l Temperature et Leekage Post (Tt) (*F) WW
)
Preneure et Leekage Poire (pt) (peas) [ 9L Erthalpy at Lenkage Poirt (ht) (BTU 4) 1183.46 Seem Flashm0 Rate (F) (%) 1.000 Weer Doneay (pt) (IbMt*) WE Rev. 01 Erthelpy Corneneaa 1183.46 Cees e Ceee 1 Cees 2 Cees a Cees 4 Case s kAAkaALhAOllIXfsAISulAMWI Twel Volumetnc Fkm Rede (Q.) (Ge4/mm) [ ;- ' '[ ] 3 5l C ' D -_- d 0 42 200 6 11 9 Total Mees Fkm Ree (mue) (Ib/mm) 0 42 200 6 11 9 Mens Fkm Rate of Flash 8 team (mt.) (RWmm) 8 0.00 30.46 30.46 30.46 30.46 30 46
%* Voulme of Flesh steem (V.) (8 'ib)
Volumeerte Fkw Ree of Fieen Steam CFM 0 1271 6353 168 337 284 CFM 0 552 2758 73 146 123 Volumstric Flow of Flesh 8 teem (air coneion)
(tWmm) 0 0 0 0 0 0 Mens Flow Rate of Condeneste (mts) 0_ ' ^ - f Reem C r "" - Atto' * : Oceure 0.329 0.971 0.710 Humidity Rate (m.) (ItWIb) 0.004 g
'7e ~7L CU ' - iT Temperwure T. (Modify Urtil Check e 0.0) (*F) $.u-Erthelpy of Dry Air et T. (h ) (BTudo) 20.0 71.8 71.8 30.2 53.8 49.5 Estheavy of Water Veser et T. (h ) (BTUAb) 1089.9 1174 0 1174.0 1124.0 1148.2 1141.3 (9tr AthLvLglingt.gy.Be!am to selve for T, Rigtt Sede of Equaien - 24.4 400.5 1168.9 859.3 Left Sade of Eaustion - 24.4 400.5 1168.9 850.3 Cheek - 0.0 0.0 0.0 0.0 0 1emtw.tu,e o,,e,_. Across Room . m c,) - mo mo 0 om m0 Cedc. No.:L401324 Proj. No.:10248-002 pay,. 01 Pee- ROC ,Rt.XL5, Teo: P Chase W Dene 11r1347,Tkne:1121 AM p,,,:p; 1
AREA AMBIENT AND DIFFERENTIAL TEMP"ERATURE CALCULATION FOR REACTOR COOLANT LEAK DETECTION
(
RCIC PIPE CHASE (710'.6")- SUMMER INLET AIR CONDITIONS (Flow = 3ee SCFM)
S_4 @ h C : . ._? _ ~_ a g
Atmosphenc Pressure p, (pse) J .14.7 - .
Satpout Rderence Temperature (T,) (*F) 17118A 1 Notes: h
- 1. Grey celle er. inputs to the spreadshed W.
." _._ N Ratie
- 2. Case 0: No leek Humesty Ratio.e,l % iib.) l *i3.33'13'{l 3. Case 1: Detection flow rWe l 4. Ceee 2: teoission flow rue Enterina WVAC Mr 01 ^" ~r L Case 3. " Reasonable
- detecten temp.
Room Suppry Temperstwo (T,) f%1986 '6. Case 4:Currert toch spec seaport for
(*F)
Erthelpy of Dry EMenne Air (h.,) (BTUAbt 6892 W embeert T A O I* " * * #
Ertheapy of Water Veoor at T. (h..) (BTUAb) 1112.74 ,'**
Comtuned Erthalpy of Ertenno Moewe th,) (BTUAb) 75 27 ,
Specie Volume (v,) (n*1b) 14962 328 0 0 294 202 139 Volumeenc Fkm Rate (Qi) CFM 0 0 20 14 10 Moss Flow Rate (mi) (Ltr.) 23
?tz:_ '- _ _: Parameters ,
EMheepy of Saturated 8_" at Room Pressure (hr) (BTUAb) 180.18 Erthelpy of Saturned 8 team at Room Preneure (hy (BTUAb) i1$0.48 Teel Heat inpia (H.) (BTUtmm) M*IT .SAIM E i E b 7 - - - U*
/
Per_.__ E for i "A " C ' -- "
Tempermure at Leeka0e Pont (Tt ) (*F) M Preneure af Leaha0e Posrt (pt) (pese) N Erthalpy e I W PonW N (BTUAb) 1183.46 Steam Fhehen0 Rate (F) (%) 1.000 Rev 01 weerc = , w (me -
Erthalpy Compennen 1183.46 i Ones e Onee 1 Caos 2 Caos 3 Caos 4 Onee E
~
Total Vo6umetne F)ow Rate (Qt) (peWrnan) _ _ _ .
1 .
_d_ _ , , _ , ,_
0 42 200 2 9 13 Total Mene Flow Rate (mum) (Wmm) 0 42 200 2 9 13 Meen Fww Rate of Flash Steam (my F.J: c.)
0.00 30 46 30.46 30.46 30.46 30.46 Spectic Voulme of Flash steem (V,) (ft*M 0 1771 8353 70 2B2 304 voeummerte Flow Rate of Flash Steam CFM 0 807 3037 33 125 180 Volumsine Flow of Flash steem (eer condshin) CFM 0 0 0 0 0 0 Maes Flen Rate of Condeneste (nu) (Ltc .)
0 r_ _ ^ d Reem C - --- After 8 --a' Oneure Hamedty Ratio (e ) (IMb) 0.021 ",, ,," 0.134 0.642 1.3 77 Temperature.Ta % Urte Check e 0.0) (*F) .. N 3 . S 3 .. M -
'?.
51.9 91.0 91.0 58.4 73.0 81.4 Erthalpy of Dry Air et T4 (tu) (BTUAb) 1112.7 1174.0 1174.0 1124.0 1148.2 1180.9 Ent4 et weer vener st T. (h ) (BTunb)
Rganen of Emerav " "- te 25: ter T.
. 71L3 200 1 800.7 1679.7 R40ft Side of Eeussen
. 75.3 209.1 800.7 1679.7 Left same of Eeustion 0.0 0.0 11 0 0.0 Cheek .
Temperature Dffaence Across Room . 4 (*F) 8.8 182.8 182.5 27.0 38.8 l 121.0 Cats. No.: LM1324 Piel. No.:1024sm2 Ror.: 01 Fle: ROC.R1.XLA.Tet: P Chene 4 Page : F3 Date.11/12R7.The:1QSe AM
AREA AMBIENT AND DIFFERENTIAL TEMPERATURE CALCULATION FOR REACTOR COOLANT LEAK DETECTION O = -
RCIC EQUlPMENT ROOM (673'-4")-WINTER INLET AIR CONDITIONS .
(Flow = ma scrM)
Gbg!gide_ Air Qonaltions Atmosohenc Pressure . p, (peia) 4 14,7 * + e= l Settert Reference Temporwure (T,) (*F) .. 70.0 2 Notes:
- 1. Grey cells are inputs to the spreadsheet l0g, ,
. g ,,,g 2. Case 0: No leak a: ,
l Humedty Raho . e,l (ityIlb,.) l_?0.0028*l 3. Case 1: Detecton flow rate Enterina tfVAC Air Conditlogg 4. Case 2:Isoladon flow rate Room Supply Temperature (T ) "*'- 70 '. . - - 5. Case 3: Curent tech spec setpoint for
(*F)
EMhelpy of Dry Ertenng Ar (h.,) (BTUAb) 1.% 14.3 - ambient T (206 F)
Enheioy of water vapor at T. (h,,) 10920g L1. Case 4: Current tech spec. setpoint for (BTuAb)
Combened EMhelpy of Ertenng Mndure (hi) (BTUAb) 2264 dfferential T (126 F)
Spec:6c Volume (v,) (It*m) 13:E3 Vo6umatnc Fkw Rate (Q,) CFM 37 3 3187 ,
939 2:39 2378 M.se Fkw Rate (m,) (t/mm) 2's9 237 70 188 178 Miscellaneous Parameters Erthelny of Saturmed Lktund at Room Preneure (h.) (BTUAb) 18018 Erthupy of Saturated Steem at Room Pressure (h,) (BTUAb) 1150 e Total Heat inptA (HL) (BTU /mm) g,- y ag@ggg,pg Paramatare for i "aa Cdrt Temperature at Leek.ve Poert (TJ (*F) h Q Preneure at Leekage Powt (m)
Erthalpy at Leekage Point (h)
(pean)
(BTUAb) 1194 82 l Steam Fleshen0 Rate (F) (%) i 3 10 f
Water Densay (n) (hat *)
Ehelpy Componeon Rev. 01
! 1194 82 l ,
Cees O Cees 1 Case 2 Case 3 Case 4 U6 'l . _ __. .. . . . . _ _ _ . .
Twel Volumatnc Flow Rate (Ot ) (gei/mm) _$: ?_,_ .. , i'. . tj] %g l
Tatel Mese Flow Rate (try) (t/mm) 0 42 2B 111 1 01 i
Mese Flow Rate of Flesh Steam (trQ (b/mm) 0 42 2B 111 1 01 SpecsAc Voulme of Flesh steem (V,) (It*1b) 0 00 30 48 30 48 3De 2 48 Volumstnc Fnow Rate of Flesh Steam CFM 0 1271 8353 3387 3075 Volumatnc Finw of Flesh Steam (air condibon) CFM 0 557 2795 1e5 1348 Mese Flow Rate of Condenente (mu) (htnim) 0 0 0 0 0 Calculated Room Conditions After Leek Occurs Humdty Ratio (m.) (IbAb) 0 033 0.178 2.989 0.888 0.570 Temperature . T. (Modify Uria Check = 0.0) (*F) . 3$. 1 JQ 7@ - .=' . ' -)
Erthelpy of Dry Ar at T. (h ) (BTUAb) 21.0 34.5 73.8 52.4 SD.0 Enhelpy of Water Vepor at T. (h ) (BTUAb) 1094.3 1118.4 11780 114.2 11444 Iteration gf Enerav Balance to Solve for T.
Right Side of Eaustion - 218 234 2 3570 8 8189 702.2 Left Side of Ecuaten - 218 234.1 lE70 8 8170 7J?.3 l 0.0 0.0 Check - 0.0 0.0 0.0 Temperature Defference Acrose Room . 42 (*F) 8.0 81.8 214.1 138,0 128,0 l
i l
b l
Catc. Nc.: L-001324 Pre 6. No.: 1024s 002 Pite: RQC.R1.XLS,Tatt tasap Rm W Rev.: 01 l
Onen: 11/1247. Time.8 40 AM Page:F4 l
e
~ AREA AMBIENT ANO DIFFERENTIAL TEMPERATURE CALCULATION FOR REACTOR COOLANT LEAK DETECTION i
\
v l
RCIC EQUIPMENT ROOM (673'-4")- SUMMER INLET AIR CONDITIONS (Flow = 3718 SCFM)
Outende Air 0:rf -
Atmosphenc Proteure . p. (peas) 1&7 g Setoont Reference Temperwure (T,) (*e. 104.0 Notes: f
% mietty Ratie
- 1. Grey cells are inputs to the spreadsheet j l Humedity Ratio . m. J (Itwi lb,.) l50A182 l 3. Case 1: Detection flow rate Enterine MVAC Air c:: r.__: . 4. Case 2: Isolation flow rate Room Supply Temperature (Ti) (*F) M:194 - 5. Case 3: Current tech spec setpoint for Erthelpy of Dry Ettery,g Aa (M) (BTUAb) #
- 45 3 ' ambient T (206 F)
Eitheapy of Water Veoor at T (h,,) (BTUAb) 1106.78 6. Case 4: Current tech. Spec, setpoint for Comtened Erthalpy of Ernenng Mrdure (h.) (BTUAb) 65 14 differential T (126 F)
Specific Volume (v.) (ft*1b) 14 210 Volumetne Flow Rate (Q,) CFM 3962 3370 999 2632 2235 279 237 70 185 157 Mees Flow Rate (m ) (ItWmm) g__..-__p,__ __3 Esthalpy of Saturned L6 quid at Room Prosaure (h.) (BTUib) 180.18 Erthalpy of Saturated Steam et Room Preesure (h.) (BTUAb) 1150 48 Total Heat ingxi (HL) (BTU /mm) "f'300.0 TM 335.4 M l**e*230EA P'85l C *30EB M m - *M Perrcro fer l =^hl== " ' -^-
Temperature et Leeeege Powt (Tt ) (*F) 2I3440 $
(pois) M Q Preneure at Leele0s Poort (pt)
Erthelpy at Leekage Post (ht) (BTUAb) 11N.82 seem FleJung Rate (F) (%) 1.000 Weer contey (pa, (esit*> NH Rev.01 Erthelpy Compartoonl 11M 62 i..h m.-- ity e r a Case O Case 1 Case 2 Case 2 Case 2 Tatal Volumetne Flow Rate (Qt) (9st/mm) C. t"4Nl N at !Aete.'--- es7 5 (itsmm) 0 42 200 94 122 Tatei Mese Flow Rete (mus) 0 42 200 94 122 Mese Flow Rate of Flash seem (mt.) (ItWman) 0,00 30 46 30.46 30 46 Specsec Voutme of Flesh ataam (V,) (ft*lb) 3a 46_
CFM 0 1271 6113 2851 3702 Volumsene Flow Ree of Flesh seem CFM 0 503 2963~ 1330 1727 Volumetric Flow of Flesh seem (en condit6on) 0 0 0 0 0 Mens Flow Rose of Condeneste (mu) (RWmm) calculated Reem C . "^^ - After n==* Occure Humidly Ratio (m.) 0.018 0.194 2.964 0.523 0.791 (ItWIb) ~
Temperature T. (Moefy UreLCheck e QO) (*F) TWE .
Erthalpy of Dry An at T. (N) (BTUAb) 46.2 57.6 92.2 69 5 75.2 Erthalpy of Water Vapor at T. (h,.) (BTUAb) 1108.8 1128.8 1179.9 1148.2 1157.1 leeration of Enerav talanes to Selve for T.
Riget Side of Eaust on . 86.3 276.7 3613.3 670.5 900.2 Left Sade of Eaustion - 66.3 276.7 _ 3613.3 670.5 900.2 Check . 00 Gr' O.0 0.0 0.0 Temperature Difference Acrose Room . at (*F) AS 52.5 194.5 102.0 128.0 0_
calc. Mr.: L 001324 Prog. No.: 102484102 P9e: ROC.Rt.XLS, Tate temy Rm .8 Ret:01 Does: 11/12/57. Time: 8 42 AM Pess:F5
AREA AM LENT AND DIFFERENTIAL TEMPERATURE CALCULATION FOR REACTOR COOLANT LEAK DETECTION O RCIC EQUIPMENT ROOM (673'-4")-WINTER INLET AIR CONDITIONS (Flows o ScrM)
Outside Air Conditions Atmosthenc Pressure . p, (pose) m14.7 e r.
Setsort Reference Temperature (T,) (*F) e s + 70A J ' ' , l*
Humidity Ratio to the spreadsheet y
.- . .. 2. Case O No leek I
Humidsty Rato.e,I (ttwIlb ) I "J' CA028 * '.I 3. Case 1:Detecten
. flow rate Enterina HVAC Air Conditions #
Room Supply Tempe sture (T.) (*F) Je%.70 eC ,
Erthalpy of Dry Eritenng Ar (h..) (BTUAb) L:M 19A ' T 5 This spreadsheet is Erthalpy of Water Vacor at T,(h,,) (BTUAb) 1CB2m for enformaron only.
Not for determaneng Comtaned Erthalpy of Ertenng Mature (h,) (BTUAb) 22.64 13.363 Spectre Volume (v.) (Plb)
Volumetnc Flow Rate (0,) CFM O O O Mese Fkw Rate (m,) (It* nan) O O O Miscellaneous Parameters Erthalpy of Saturated Lioun$ at Room Pressure (h) (BTUAb) 18018 _
Erthalpy of Saturatad Steam at Room Pressure (h ) (BTUAb) 1150 48 Total Host input (HL) . (BTU / min) h= h MN f ,
Parameters for leakine Condefisate O' Tempermure at Leekage Poirt (TJ Pressure at Leekage Port (pt)
(*F)
(poie) h Two M
Erthalpy at Leckage Poirt (ht) (BTUAb) 1194 62 Stsom Fleshing Rate (F) (%) 1.000 Water Donety (p0 (Ibitt') M Erthelpy Compenson 1194 62 Case O Case 1 Case 2 N_
Tr*el Volumetne Flew Rate (Qd (pelAnn)
Taal Mese Flow Rate (mt ) (Ib/ min) O 42 2D9 l Mese Flow Rate of Flesh Steem (mt.) (Ib/ min) O 42 200 l Mc Voulme of Flesh steem (V,) (PIb) 0.00 30 46 30.46 l Volumstne Flow Rate of Flesh Steam CFM O 1271 M3 l Volumame Flow of Fleen Steam (e'r condten)
. CFM O E57 2785 l Mese Flow Rate of Condensate (mt,) (Ib/ min) O O O l Calculated Room Conditions After leak Og'rs, SH steem, rc er SH steem no at SH steem, no er R%d M to ths room to the room to the room 5emperature .T. (Modfy Urtd Check = 0.0) (*F)
Ershelpy of Dry Air at T. (h ) (BTUAb) 198 78 0 78.0 Erthelpy of Water Veoor at T. (h,.) (BTUAb) 1002.1 1180.9 1180%
leeratton of Enerny Balance to Solve for T.
Rigtt Side of Equebon -
Left Side of Equebon -
\
Check .
Temperature DiffererEAs oss Room . A (*F) 0.0 234.2 234.2
-- Caic, No.: L401324 Proi. No.: 10246-002
% ROC.R1 XLS, Tab: Equip Rm -W(2) Rev.:01 Deen 11tt2/97, Time 6 a5 AM PuSe:F6
AREA AMBIENT AND DIFFERENTIAL. TEMPERATURE CALCULATION FOR REACTOR COOLANT LEAK DETECTION RCIC EQUIPMENT ROOM (673'-4")- SUMMER INLET AIR CONDITIONS (Flow = 0 SCTM)
Outside AirCondulons Atmoschenc Pressure p. (poie) --H14.7*
8 Settnert Reference Tempermure (T,) (*F) '**144.8 a
- g, g Humidwy Ratio to the speedehoot y
- 2. Case O. Noleek l Humdty Rate es,l (ttylib.) l " 9.0182 ~El 3. Case 1: Detoden Enterina HVAC Air CondMione 4 Room Sucply Temperature (T,) ("F) " f.k184~ n gg rg,,
Erthelpy of Dry Ertenng Air N) (BTUAb) des L % 5. TNs spreedsheet la 1106.78 for informaten only.
Ertholoy of Water Vapor at T. N) (BTUAb)
Nd for detonamng Comtuned Erthelpy of Ertenng Mature (h,) (BTUAb) fE.14 Specife Volume (v,) (ft%) 14 210 Volumstne Fkw Rate (Q,) CFM O O O Meet Fkm Rate (m,) (It9mm) O O O M!5-: " nzr? Parameters Erthalpy of Saturmed Lead at Room Preneure (h,) (BTUAb) 180.18 Erthelpy of Saturated Steam at Room Pr-e (h.) (BTUAb) 1150 48 F M **STle sina SW Total Heat ined (H.) (BTutmm) il .n s- s Pers ....:. for Leakine C-z n#1 Temperwure at Leekaga Port C ') (*F) MM Preneure at Leekage Port (pd ,,, ,; gene) MidiWI Erthalpy at Leekage Port (hd '. N 2) 1194 62 Steem Thehmg Ree (F) (%) 1.000 Water C. :p (A) (itert') . __ -
Erthalpy Componeon 1194 62 Leekane CaseO Case 1 Case 2 (geumm)
. _._ _. ___ __ ____ Td.J Volumstne Fkm Rate (QJ . _ _ _ _ . .
Total Ms.es Flow Rate (rQ (tWmm) O 42 200 Mene Fkm Rate of Flash Steam (m) (ItWmen) O 42 l 200 l Specsfic Vouir, e of Fleen steem (V,) (ft%) 0.00 30.48 l 30.46 l Volumetne Fkw Rate of Flash Steam CFM O 1271 l END l Volumetne Fkw of Flash Steam (or condion) CFM O SD l 291D l Mene Flow Rate of Condensde (mu) (tWmen) O O l 0 l C&_W Room Condttions ARer Leak Occurs 0.018
- "***"** OH "***' "* ""
Humdty Rabo (e.) (ItWIb) to the room to the room EN Temeerature T. (":-#p Unte Check = 0,0) (*F)
$_ Z --
Erthaipy of Dry Air at T. (h.J (BTUAb) 4FLO 50 0 50.0 Erthetoy of Water Veoor at T. (h ) (BTUAb) 1106E 1180.9 1180.9 Iteration of Enerny Balance to Solve for T.
Rgnt Sech of Ecuanon - IE1 O Left Sdo of Eauenon Check fE 1 0.0 Temperature Difference Acre e 9eom % ("F) 0.0 4 200.2 200.2 Calc. No.: L-001324 Prol. No.: 1024tWC2 Fae- RCIC_R1M.S. Tab: Equip Rm -S (2) Rev.:01 Dele 1t/12107. Time:6.47 Ahl Page:F7
i j
. AREA AMBIENT AND DIFFERENTIAL TEMPERATURE CALCULATION FOR REACTOR COOLANT LEAK DETECTION
' RWCU PIPE TUNNEL (798'-0") -WINTER INLET AIR CONDITIONS _ -
(Flow = 7650 scrM)
Outside Air Conditions Atmoschenc Presaure . p, (pete) 14.7 Satpoirt Reference Temperature (T,) ("F) '80A~~ Notes:
)
- 1. Grey cel6e are inputs ,
I to the spreadsheet.
HumidRV Retto 2. Case 'l No leek )
- 3. Case 1: Leek rete l Humedty Rato e.,l (%ih.) l ~*..t10050 e enut oeftn.
Enterine HVAC Air Conditions toorn inlet ear fk.
Room Supply Temperature (T,) ("F) MM~M Erthelpy of Dry Ertenng Air (h. ) (BTUAb) *h e.9 :" YI-Er* helpy of Werer Vapos et T, (h,4) (BTUAb) 1CB6 44 Comtzned Erthelpy of Ertenng Mrsture (h,) (BTUAb) 22.29 We Volume (v,) (ft*1b) 13805 Volumetne FW Rate (Q,) CFM 7806 O Mees FW Rate (m,1 (R*mn) 574 0 Misc:"- sr. Peremeters 1 180.18 )
Erthalpy of Saturated I w taRoom Pressure (h)
- (BTUAb)
Estheipy of Saturated Steem at Room Preneure (h.) (BTUAb) 1150 48 ,
Total Heat input (HL) 6MAdes'auw M C ,
(BTUhan) s e
l l
Parameters for i dw Cc..i..:P E i
Temperature et Leekage Poert (TJ ("F) MS MM l
Pr-e et Leekage Port (pd (poe)
Dthalpy at Leekage Poirt (hd (BTUAb) 582.21 Steam Flashing Rate (F) (%) 0.414 i
Water Donety (pd (bft') _-
Erthalpy Compenson 1150.48 Case O Case 1 h
l TcselVolumstne Fh Rate (Oy (gelhan)
(( ~SY I Tctel Maes Flow Rate (mt ,1 (Itsnsn) 0 1'J85 Mese Flow Rate of F)meh Steam (mt.) (itsmn) O 574 M Voulme of Flesh steem (V,) (ft*1b) 0.00 2tL80 !
l Volumatnc Fh Rate of Fisen Steam CFM O 15376 Volumetne Fh of Flash Steam (or condtion) CFM O 7808 Maes Fh Rate of Cordsneate (mt,) (Itemn) O 811 Calculated Pm C-rf"':ee After Leek Occurs Hurmdty Rabo (e.) (Ith) 0.033 45047.450 Temperature . T. (Modfy t)td Check = 0.0) ("F) M Mt'ag Erthelpy of Dry Air at T. (h ) (BTUAb) 19.0 50,7 Enthalpy of Water Vepor et T. (h ) (BTUAb) 1096.4 11S0.5 leeretion of Enerav Belence to solve for T.
Right Sede of Ecuehan . 22.3 51826299 9 51826299 9 (D Left Side of Eaustion - 22.3 Check . O.0 0.0 _ f Temperature Difference Acrose Room.h ("F) 0.0 132.0 casc h:L401324 Prt4 No.:1G246402 File: ROC.R1.XLS, Tab: RWCU TM Rev.:01 Dune: 111t247, Time: 11:12 AM Page:F8
AREA AMBIENT AND DIFFERENTIAL TEMPERATURE CALCULATION FOR m REACTOR COOLANT LEAK DETECTION U -
RWCU PIPE TUNNEL (798'-0")- SUMMER INLET AIR CONDITIONS (Flow = 7650 SCF'M)
Outs 6de Air Conditiong Atmospheric Pressute . p. (peas) 14J '
Notee:
Getpoent Reference Temperature (T,) (*O '104.0 " 1. Grey cone are hpute to the spraedsheet.
Hum 6d6tv Ra60 2. Coeo 0. No leek
[ Hunway Ratsod'(tw/ b ) l OAtt0"'l 3. Caos 1:Look rate
, which shuts off the Enterina HVAC Air condisons
~
room inlet air flow.
Room Supply Temperature (T ) (*O " ' 121 A ' -
Enthelpy of Dry Erstormg Air (h..) (BTU /Ib) 48 7 ***"*
Enthalpy of Water Vapor et T (h,,) (BTU /lb) 1114 26 Combbed Erithelpy of Erstering Mbeture (hi) (BTU 4) 88.00 haeine Volume (A) (ft'b) 14 853 VokJmetric Flow Rate (O ) CFM 8407 0 Mees Flow Rate (mi) (Wmin) 1 574 0 Mite &.me Parerneters Enthalpy of Saturated Liquid at Room Praeeure (h,) (BTU 2) 180.18 Enthalpy of Saturated Steam et Room Preemure (h) (BTU 2) 1150.48 .
Tatel Heat input (HL) (BTU / min) WM MAW.M Q Parameters for leakins Condentp i f__
Temperature at Leekage Point (Td (*F) _
^~^ -^ ~^
Preneure et Leekage Point h) (pois) _ _
Enthalpy at Lookege Pokst (itd (BTU 2) 882.21 Steam Finehbg Rate (O (%) 0.414 Water Deneey (pd (Wfth M Erwhelpy Comportaan 1190.46
= .
LekMe Quachty t'e8-a_detkm CaseO Case 3 Total Vokamattto flow Rate (Qd (geFmin) NC Total Maes Flow Rate (trun) (Wmin) 0 1385 (Wmin) O M74 Mene Flow Rate of Flesh Steem (mt.)
emic Voutmo of Fineh steem (V,) (ft*b) 0.0') 26.80 Vokametric Flow Rate cf Flash 8 team CFM 0 15376 Vuksmetric Fksw of Flash 8tsa.n (air condition) CFM 0 8407 Mene Flow Rate of Condeneste (ng,) (Wmin) 0 811 gggleted Room Cond6tions After Leak (% curs Humedty Rateo (e.) (Wb) 0 018 45047.474 Tempetiture . T. (Modify Unte Ct ack = 0.0) (*F) uTM MW Erithetsrr of Dry Air at T. (h..) (BTU 2) 48.0 (El.7 Enthalpy of Water Vene r a T. (h ) (BTU 2) 1114.3 1150.5 i leera60n of Eb.arav "% to Sdve for T.
Raght Side of Egustion . flB.1 ,S 3 1045.7
\ Left Side of Equation - 08.1 J tigD45.7 Check . 0.0 (
_ , 1.0 Temperature Difference Across Room . 41,w (*F) 17.8 W8.0 Calc. No.:L@1324 i Pn4 No.:10246M2 Rev.: 01 ,
F66e RCIC.Rt.XLS. Tob: RWCU Tunne64 Final l Desa 11/12,97, Time 11:13 AM PeGe : FW
_ _ _ ~ _
1 J Cale. No.: L@l324 i
Proj. No: 10246 002 Rev.: 00 Page Gl ;
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