ML20245F290
| ML20245F290 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/30/1984 |
| From: | Billig P, Rogers A GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20245F260 | List: |
| References | |
| AE-59-0584, AE-59-584, NUDOCS 8908140225 | |
| Download: ML20245F290 (45) | |
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arra cume.N T* la l ^ AE-59-0584 l' DU E31-00028 June 1984 l
QUAD CITIES 1 AND 2
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HFCI/RCIC ROON LEAK DETECTION PEASE II AND III
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Frepared by: M F.F. 81111 y Plant Performance Engineering Approved byr d
'A.T. Edge' fs. Manager
- Plaat Performance Engineering '
Prepared for Commonwealth Edises Company by General Electric Company Nuclear Services Operations GENER AL $ ELECTRIC neug88: n8886 P PNV
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F- 7 LEGAL NOTICE
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z r-i y' Except as otherwise agreed to in writing, neither the General ,
Electric Company nor any of the contributors to this document makes any warranty or representation (express or. implied) with respect to the accuracy, completeness, or usefulness of the information contained in this document or that the use of such information may not infringe privately owned rights, nor do they assure any responsibility for liability or damage of any kind which may result from the use of any of the information contained in this document .
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. A3STRACT L' Each HPCI and RCIC pump room at the Quad Cities Station Unita 1 and 2 contains sixteen temperature switches to detect steam leaks. An
. analysis has been performed to justify reducing the number of sensor to four in each roce. The thermal hydraulic computer code RELAP4 MOD 5 is used to predict the cesperature response to various leak races.
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TABLE OF CONTENTS l fj
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I811 ABSTRACT 11 1.- INTRODUCTION g.g
1.1 Background
g.g 1.2 Method '
g.g 2 .' AS$tHPTIONS 4 2-1
- 3. RESULTS 3.g f*
4 DISCUSSION 0p 41 4.1 Assumptions 41 4.2 Temperature Setpoints 4.g 4.3 Temperature Switch Arrangement 42 4.4 Fire Protection 43
- 5. . CONCLUSION & UC000(ENDATIONS 5.L 9
- 6. REFERENCH 6-1
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LIST OF TABLES I 'g)
Table g
3.1 Initial Conditions and Thermodynamic Properties 3-2 3.2 Temperature Response in HPCI/RCIC Pump Rooma 3-3 Tor Small Steam Leeks S
O LIST OF FIGURES Timure g
3.1 HPCI Pump Room Temperature Response 3-4 3.2 RCIC Pump Room Temperature Response 3-5 4.1 One-cut-0f-Two Twice Logic Teg erature 4-4 Switch Configuration
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4 1.
INTRODUCTION
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1.1 BACRCROUND
,v Each High Pressure Coolant Injection (EPCI) and Reactor Core Isolation Cooling (RCIC) room at Quad Cities Station Units 1 and 2 currently contains sixteen temperature switches to detect significant leaks in the EPCI/RCIC steam piping sad to initiate isolation of the ,
steam lines.
Commonwealth Edison Company (Ceco) has requested the General Electric Cospany (CE) to provide justification to reduce the number of temperature sensors in each room from sixteen to four. A reduction of temperature switches would lessen the likelihood of unnecessary system italacions ,due to faire signals. Additionally, the calibration " burden and potential for the issurnes of a Licensee Event Report would also be reduced significantly since the 64 (16 in
- each room in both units) existing switches require calibration once each operating cycle.
O The Phase I report (Reference 1) showed qualitatively that a
( reduction in the number of sensors was feasible.
This report represents Phase II and III in the effort to reduce the number of temperature switchdh in the EPCI and RCIC rooms, respectively. This report supports the Phase I judgement with a quantitative analysis.
1.2 METHOD The offset that small steam leaks have on the ambient temperature in the IPCI and RCIC pump rooms is studied. The leaks 2nalyzed are for 5. 10 and 25 sps flow rates.
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. Apprrpricto clars tceparcture setp31nts can be determined from
~ curves relating temperature behavior and leak rats.
These cutvos are generated using the thermal hydraulic computer code RELAp6/ MOD 5 l .(Reference'3).
This Idaho National Engineering Laboratory (INEL) code is suitable for use in transient analyses of nuclear power reactors and its related systems.
RELAp6 providss transient response to systen perturbations such as coolant loop rupture, circulation pump fzilure, and power 9xcursions. ilovover, verassility of its options permits analysis of small leaks in sulcon grements such as the EpCI/RCIC pump rooms.
A subcompartment cesputer model was developed by benchmarking RELAtle predictions to measured test results (Rieference 2). These h
tests simulated the temperature response in a turbine roca to steam leaks with several heat removal mechanisms in operation such as air e.coling and forced ventilation.
4 The model was then revised to
. reflect the normal operating conditions in the RPCI and RCIC pump AP 1 ro ws at Quad Citias. Where room parameters varied between Units 1 and 2, the most limiting case was used to bound the results for both units.
fg' Section 2.0 lists the assurgtions used in the analysis.
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- 2. ASSLHPTIONS
,m The following assumptions are used in the analysis to determine the room temperatures for postulated steam leaks. They are discussed in Section 4 ..1 1.
The heat transfer coefficient between the vall and the air /
steam mixture in the room is assumed to be a linear function of,the humidity ratio.
- 2.
Constant leak rates are assumed.
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Thermal stratifiestion effects caused by small leaks are neglected.
, 4 Air cooling is neglected.
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Normal ambient conditions in the pump rooms are assumed.
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The thermodynamic properties for steam correspond to normal full power operating conditions.
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. p. '3. RESULTS
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.( ) Table 3.1 gives the initial conditions and thermodynmaic properties which were used in the analysis.
They are consistent with assumptions given in Section 2.0.
Figure 3.1 shows the temperature response in the NPCI pump reca for 5. 10 and 25 spa sesaa leaks.
The temperature response in the RCIC pump room for these three leak rates is'given in Figure ..
32 The room temperatures at 200, 400 and 600 r,econds are also tabulated in Table 3.2.
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J" . g TABLE 3.1 lf*h m 1 INITIAL CONDITIONS AND THERMODYNAMIC PROPER y ., ,
_ Pump Room Parameters.
~* Temperature 85*F
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- Pressure 14.69 psia i '
- Relative Humidity 60%
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- Volume .
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- $1034 fta RCIC 25401 fts
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'EnthalPT 1191.6 Stu/lb II
Reference:
D.G. Clark. Ihermal Engineer. Quad Cities Nuclear Power Station. Letter April 30, 1984 and Telecon May 10. 1984 -
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. S j-se Hi i TEMPERATURE RESPONSE IN HFCI/RCIC PIMP A00M5 P p.
Leak Rate Temperature ('F)
' Room (CPM)
. 200 sec 400 sec. 600 see l EPCI 5 103 115 121 l' 10 118 t
132 140 1 25 142 l 158 167 RCIC' ,5- , 117 130 137 10 134 14g g37
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- 4. DISCUSSION
< ,m 4.1 ASSUMPTIONS Assumptions used in this analysis are the same as those Referencu n used i 2 to model previous leak tests.
That report concluded that
" benchmarking RELAP4 predictions against test result s indicate the computer code is capable of producing good agreement." k An accuracy of 10% is espected for rooms of the size evaluated.
It further concluded that "the predicted temperature l temperature." will be below actual This is mainly due to tha conservative reistionship assused between the heat transfer coefficient and the humidity ratio of the air in the pump roossi Assuming a uniform roca temperature during a esall leak is siso conservative.
Theresi stratification would make the actual i temperature higher'near the ceiling. For temperature sensors above 4+
.the' leak location, a high temperature signal would occur earlier than indicated by this analysis.
O Air cooling is neglected in this analysis because it is assumed that most of the system's capacity is being used to maintain the roca temperature during normal operating conditions. Under accident conditions it is assumed that the coolers are not sufficient to maintain the temperature.
In addition, the ventilation system will isolate on a high radiation (2 mR) signal which may occur during this sccident.
4.2 TEMPERATURE SETPOINTS The setpoints for the temperature sensors for the MFCI and RCIC rocas depend upon the size of staan~1eak and the alarm time. Figure 3.1 and'3.2 or Table 3.2 should be consulted in asking this decision.
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x Currently the temperature sensors are set to actuate at 185'F.
This is too high to cause an alarm based on the results shown in Table 3.2. A setpoint of 140'T seems reasonable.
nis will also cause isolation before the fire suppression system starts. Before lowering this serpoint a temperature survey of the rocas should be made to determine the temperature range near the sensors during normal operations.
If thermal stratification. exists, then the temperature near the switches may be higher than the average ambient temperature.
Falso signals may occur if the setpoints are made too low.
4.3 TEMPERATURE SWITCH AARANGDENT GE reconnends that the four switches be arranged as shown in Figure 4.1.
This layout contains a one-out-of-two twice logic to initiate steam line isolation.
"9 This analysis assumed a uniform temperature within each roca.
4 Therefore, the setpoint, based on the remits of this analpis, will be reached by all four sensors simultaneoudy. The predicte0 delay in receiving an isolation signal due to the need to trip more than one temperature sensor will be negligible.
This layout also ensures that there will not be a false signal due to the failure of one switch, since two evitches aust be actuated to caura isolation. -
CE also r9cossends that, the four individual sensors be located in the sans respective area whore each group of"four is now located.
These locations are above potential scesa leak sources. In the HPCI room the four locations are above the EPCI steam inlet line, above the turbine rupture disk, and at both ends of the turbine near the bearings.
In the RCIC room the four locations are above the RCIC turbine at'the rupture disk, near the stess supply to the turbine.
gg and at both ends of the turbine at the shaft. These locations will minimize the Isak detection time.
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&* 4.4 FIRE FROTECTION 17
([ Currently.the EPCI pump rooms have a fire protection system with detectors set at 175'F. There is no need to change the fire protection system setpoint if the leak detection sensors are set below 175'F.
The lesk detsetion sensors are now set higher than those for the fire protection system. This could tapair the operation of the Isak detection system because the fire protection system would, prevent automatic isolation.
There is no fire protection system in the RCIC pump rooms.
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FIGURE 4.1r One-Out-of-Two Twice Logic Temperature Switch pg Configuration I
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CONCLUSloWS & RECCNMDfDATIONS e
The present arrangement of sixteen temperature switches ach in e HPCI and RCIC pump room at quad Cities can be reduced to fou switches in each roca.
l e A reasonable setpoint for the temperature sensors is 240'F e
A one-out-of-two twics logic configuration (Figure 4.1) to initiate isolation is recommended.
e The four switches in each room should be located in the respective area as each group of four switches is now situated.
e The fire protection system setpoints in the MPCI room should remain at current settings.
.. e The new setpoints shoald be verified by a temperature survey of the room to ensure that they would not result in falso trips due to isolated hot spots in the room.
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- 6. REFERDICES A
- 1. i F.F. Billig, " Quad Cities 1 and 2 HPCI/RCIC Roonon:Leak Date Phase I Report" AE-05-0184 January 1984 ,
2.
8.G. Atras, T. Leong, " Analysis of Reactor Coolant Laakage Versus Area Ambient Temperature Rise" N E E-25252
, January 1980.
3.
"RELAF4/M00 5. A Computer Program For Transient Thermal-Hydr.sulte Analysis of Nuclear Reactors and Related Systems User's M.tnual," II(EL ANCR-NUREC-1335, Septemb*e 1 O
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4 gM [ N M,5 t{'o ,,c June 21, 1985 '1 . -E IN(( 'g(f Y s J. Hausman D
'J#N " x/b SNED 35 FN West a , *'
Subject:
HPCI/RCIC Area High Temperature Isolation System Leak Detection 4- I g5 1, '
Quad-Cities Station has been concerned with the recommended 140'F setpoint for our HPCI/RCIC Area High Temperature Switches. We have taken L]pt/
E, temperature surveys in these areas,and believe that, although temperatures d, recorded were below 140*F, temperatures could actually reach 140'F. The reason our test temperatures were low was that the tests were conducted gl, during cold months. A temperature survey in July and August would give us kf E a more accurate picture. In the past we have had spurious trips of EFCI .
due to area high tersperature. We feel that, with a much lower setpoint such as 140'F, these trips would continue. The Station would lika to -
f) retain the old setpoint or work with SUED and General Electric to determine a safe and effective setpoint somewhere between the old setpoint and the newly proposad setpoint of 140'F.
Respectfully.
.}. t t H. G. Libou Technical Staff Supervisor Quad-Cities Station HCL:NPD/bb l
O 1
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August 22, 1989
() Note : Don Lanham IRM/DCB
(). From : Thierry Ross NRR/PD32 (3L Subject : Page Replacement in CECc Document Dated -
August 3, 1989 for Guad Cities Station ,
(Accession No. 8908140217 890803) l O.
The letter described above was inadvertently submitted to us
() with,a bogus page (specifically page 14 of 23 in Attachment I've attached to this note a copy of the original l
l No. 7).
RIDS sheet and the appropriate page'that thould be used to
[() replace the bogus one. Please update the docket file for this document using'the correct page. Thanks.
O O ,.
//~
() Thierry Ross Project Manager l
C).
(1 C)
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