Text

Rev 0 to RSA-D-92-07, LPCI Room Temperature Response Due to Loss of Room Cooler at Dresden Station
	ML20126G102
Person / Time
Site:	Dresden, Quad Cities
Issue date:	12/17/1992
From:	Kong P, Tsai R; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML17179A652	List: ML20126G102;
References
	RSA-D-92-07, RSA-D-92-07-R00, RSA-D-92-7, RSA-D-92-7-R, NUDOCS 9301040063
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} Document Number RSA D 92 07 1 December 14,1992 I i Pedro L. Kong " Robert \V. Tsal i

                                                                                                    ' Nuclear f uel servkes Department Commonwealth Editon Company Chicago, Illinois I
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RSA D 92 07 Rev.0 Statement of Disclaimer This report was prepared by the Nuclear Fuel Services Department for use internal to Commonwealth Edison Company as applicable to the Dresden Nuclear Generating Station, it is being made available to others upon the express understanding that neither Commonwealth Edison Company nor any of its officers, directors, agents, or employees makes any warranty, representation, or assumes any obligation, responsibility with respect to the contents of this report, its accuracy, or . completeness pertaining to any usage other than,the originally stated purpose. Disclaimer ll

RSA D 92 07 Rev.0 Abstract This calenote documents analysis performed to demonstrate the operability of the LPCI system is not compromised by the loss of heat removal capability of the room coolers. This condition could occur if the normal service water is lost due to a loss of offsite power. The temperature response in the LPCI room due to a loss of room cooler concurrent with a LOCA was calculated conservatively. It shows that the EQ temperature is not exceeded during extended LPCI system operation without the room coolers. The analysis incorporates methods discussed with the NRC reviewers in recent meetings. This calcnote provides final documentation in support of room cooler operation as related to LPCI system operability and is intended to supersede the results of previous analyses. 4 4 Disclaimer lll -

RSA D 92 07 Rev.0 Table of Contents Table of Contents _ - _. -Iv 1.0 Introduction- . __ _ _ - -I 2.0 Method of Analysis. _.. .2 2.1 D e s c rip ti o n o f Tra n sie n t .................. ... . . ... ........................ .............. ......... ... ... 2 2.2 ComputerCode.............................................................................................2 2.3 A n al y t i c al M o d e l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.4 I n p ut As s u m p tio n s and Param e t e r s .......'....................................................... 3 3.0 Resuits -- 7 4.0 Conclusion- .- -. 8 5.0 Refsrsnces _. 9 Listing Of Computer Runs. x=

                                                                                                                                                                                                                                    -15 Appendix.                                            _
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1 RSA D 92 07 Rev.0 List of Tables Table I: Heat Slab Parameters. ~~~~~~ .,,,,,,,,,,,_,,,,,,, __g 1

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RSA D 92 07 Rev.0 l

i List of Illustrations ! Figure 1: RELAP4 Mode l Schematic -

                                                                                                                                                                            ---                 12 4

j Figure 2: Torus Watar Temperature _ . 13 i Figure 3: LPCI room temperature response due ta loss of room cooler. 14 . 4 1 it i 4 1 I i f i 1 i .l 4 4 1 1-I b l 4 l l e l. 0 4

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RSA D 92 07 Rev.0 1.0 Introduction The purpose of this calculation is to document the thermal response of the LPCI room to events in which the heat removal capability of the room cooler subsystem is unavailable. This candition could occur if the normal service water cooling path is lost due to a loss of offsite power. Assuming a loss of cooling function concurrent with maximum estimated heat load to the LPCI toom, the LPCI room would experience increasing temperatures, moderated only by heat and mass transfer out of the room in the unlikely event of a LOCA, the room heatup must not exceed the EQ (equipment qualification) temperature of the essential mechanical, electrical and structural components located within the room for an extenJed period of time. This analysis conservatively calculates the temperature response and demonstrates that the EQ temperature is not exceeded. This report is intended to be the analysis of record for this event, and supersedes the results of previous LPCI room heatup calculations (References 1,2 and 3), it is based on changes and improvements in methodology developed in the process of regulatory review, introduction 1

~ I RSA D 92 07 Rev.0 i 2.0 Method of Analysis 2 The LPCl room temperature response was calculated by a RELAP4 system model. The following sections describe the transient, computer code, model and the assumptions used in the analysis.

2.1 Description of Transient .

The analysis assumes a LOCA concurrent with the loss of heat removal capability of the room coolers. This condition could occur if the normal service water path is lost due to a loss of offsite power. The normal ventilation to the LPCI pump room is also lust. Upon the initiation of the LPCI system to mitigate the consequences of the LOCA, the pump room temperature would start to increase due to the heat generated by the running pump. The pump is assumed to run continuously. 2.2 Computer Code The RELAP4/ MOD 6 (Reference 4) computer code was used in this analysis. RELAP4 is a computer code written to model system fluid conditions including flow, pressure, temperature, mass inventory, fluid quality, and heat transfer, it is primarily applied in the study of system transient response to postulated perturbations. This version of -

          . the code contains an equation of state for air and has the ability to transport air between nodes. The code was installed in the CECO computer system in accordance with approted Company procedures and requirements for design application computer codes. The name of the current CECO load module is M2720 with site ID of RELAP/lO6 02/23/78 (Reference 5).

2.3 Analytical Model The Ilmiting case that would result in the highest LPCI toom temperature is when both ECCS trains are running because both pump rooms share the same heat sinks in the reactor building and the torus room. For this case, both pump room temperature responses are identical or symmetrical. Therefore, only one pump room and one half Method of Analysis 2

RSA D 92 07 Rev.0 of the volume and heat sink areas in the reactor building and torus room are used in the analytical model. The analytical model is shown in Figure 1. It consists of three volume nodes representing the 1.PCI pump room, the reactor building floors above Elevation 517, and the torus room. Five additional nodes are used to model the outdoor air, soll adjacent to the building walls, soll underneath the floors, the turbine building and the reactor building of the sister unit. A time dependent volume is used to prescribe the post LOCA torus water temperature. , Heat transfer to walls, ceilings and floors is modelled with fouiteen heat slabs. The heat load in the pump room is modelled by a heat slab with constant power generation. The heat slab dimensions are listed in Table 1. As the room heats up, the room would act like a chimney by drawing air from the torus room through openings in the wall and discharging the air to the reactor building. After passing through the reactor building, the air is returned to the torus room through openings between the reactor building and the torus room. Thus an air circulation path is formed that would contribute to the heat removal in the pump room. This alt circulation path is modelled by three flow Junctions. Since the amount of air circulated affects the room temperature, LPCI room 2A which has the smallest opening was modelled. The results of References I and 2 confirm this selection. 2.4 Input Assumptions and Parameters The following input assumptions and parameters were used in the analysis.

1. The pump room air temperature is assumed to be uniform and no significant stratification exist within the room. Data from the Quad Cities test (Reference 6) shows all sensor readings fall within a 2 degree band around the average room temperature during a 90 minute run of the RHR pumps without room coolers.

This is due to the thorough mixing of air caused by the ECCS pump motor fan and the room cooler fans. Measured data from Dresden shows that the exhaust air flow from each of the three pump motors is approximately 48,000 cfm l Method of Analysis 3 l I

l l RSA D 92 07 Rev.0 (Reference 7). Since the room volume is approximately 25,000 cu ft, thorough mixing of air can be assumed.

2. The initial pump room and torus room conditions are 14.7 psia,104 deg F and 95% relative humidity. The torus water temperature history is taken from the LOCA analysis which assumed the operation of one RHR cooling loop with one RHR pump, two RHR service water pumps and one RHR heat exchanger. This -

5 assumption resulted in higher torus water temperature as compared to two RHR loop operation. The temperature history is given in Figure 5.2.19 (Case d) of the Quad Cities UFSAR and is reproduced in Figure 2.

3. The initial reactor building conditions are 14.7 psia,104 deg F and 95% relative-humidity. This is the conditions that would exis; followliig a LOCA as listed in the EQ zone maps (Reference 8). The temperature of the turbine building and the reactor building of the sister unit is assumed to be constant at 104 deg F throughout the transient.

4. Normal pump room ventilation is assumed to be off throughout the transient.

5. The heat load in the LPCI room was taken from Reference 9. It consists of two components, a fixed component and a variable component. The heat load from room lighting, two LPCI pumps, one CS pump and fan motors is fixed at 431,022 Btu /hr. The heat load from piping and LPCI heat exchanger shell is variable, depending on the surface and rvom temperatures and was calculated in Reference 9 by assuming surf te temperatures of 170 and 165 deg F, respectively. It varies from 81,446 Btu /hr to zero for room temperatures of 120 and 170 deg F, respectively.

The operation of the LPCi/CS system is assumed continuous. The piping and the shell side of the LPCI heat exchanger contain water from the suppression pool. Therefore, the heat load from these sources becomes zero when the room temperature equals the torus water temperature._Although the piping and heat exchanger become heat sinks when the room temperature exceeds the torus water temperature, they are not modelled as heat sinks. Since a temperature dependent heat load can not be modelled with the RELAP4 code, the maximum heat load of 512,500 Btu /hr was assumed in the analysis for room temperature Method of Analysis 4

RSA D 92-07 Rev.0 below 170 deg F. After the room temperature reached 170 deg F, the fixed heat load value of 431,500 Btu /hr was used. 1

6. All steel structures are not considered as heat sinks for conservatism.

7. The mechanism of heat transfer between air and the heat sinks in the pump room is a combination of natural, forced and radiative heat transfer. Based on the test data obtained in the Quad Cities RHR2B room in 1986, the combined heat transfer coefficient was determined to be 6.5 Btu /hr sq ft-F (Reference 6). A value of 5.0 Btu /hr sq ft-F was used in the analysis.

I

8. The mechanism of heat transfer between air and the her # t in the other rooms is assumed to be a combination of natural and radiative heat transfer. The RELAP4 code has a default heat transfer coefficient of 5 Btu /hr sq ft-F, which requires the adjustment of the heat slab surface area to yield the correct heat transfer rate. The actual and adjusted heat slab areas are listed in Table 1. The natural convection heat transfer coefficients were calculated using correlations found in heat transfer textbooks such as Kreith (Reference 10) or McAdams (Reference 11). The radiative heat transfer coefficient is derived by considering the heat transfer between air and the gray walls, it is defined as the heat transfer rate per unit area divided by the temperature difference. The heat transfer rate is calculated using gas emissivity value given by Hottel(Reference 11) or Leckner (Reference 12) and gas absorptivity value calculated by Hottel's method (Reference 11). The methodology of calculating the radiative heat transfer 4 coefficient is identical to the one used in the CONTEMPT 4 code (Reference 12).

9. The thermal conductivity of concrete is assumed to be 1.05 Btu /hr ft-F and the volumetric heat capacity is 30.24 Btu /hr-cu ft-F.

10. The soll temperatures are assumed to be 55 and 65 deg F for soll under the floor and adjacent to walls, respectively, in the Chicago area, the ground water temperature at depths of 30 to 60 feet is relatively constant at 52 deg year rour.d (Reference 13). The soll temperature under the floor is assumed to be equal to the ground water temperature and a value of 55 deg F is used for conservatism. The soll temperature adjacent to the wall is assumed to be equal to the mean of the temperatures at depths of 4 inches and 30 feet. The Method of Analysis s

h RSA D-92 07 Rev.0 maximum-annual soll temperature at a depth of 4 inches is estimated to be about 77 deg F using data given in Reference 1_4 (page 25.6).

11. Heat transfer between concrete and soll is modelled by using an effective heat transfer coefficient which is defined by the soll thermal conductivity divided by a heat diffusion length. The diffusion length is determined from semiinfinite heat slab solution methods. The detailed procedure is described in the Appendix.

i i a Method of Analysis 6

RSA D-92 07 Rev.0 3.0 Results The LPCI room temperature response as a result of a loss of room cooler heat removal capabliity concurrent with a LOCA is shown in Figure 3. The room temperature at the end of 11.7 days is 178.0 deg F. Because the RELAP4 code has a transient time limitation of 11.7 days (IE+6 sec), the temperature at the end of 30 days was estimated. After 11 days, the room temperature is increasing, but the rate of increase is decreasing.- The torus water which acts as a heat sink is cooling down resulting in lower torus room temperature. Thus, cooler air will circulate through the LPCI room it is estimated that the temperature would reach a peak of 178.6 deg F in four more days and beyond that time it would be less than or equal to 178.6 deg F. The calculated LPCI room temperature response shows an abrupt change after it has reached 170 deg F. This is the result of the change in heat load-as explained in item 5 of the input assumptions, if the heat load were allowed to vary with room temperature, the temperature response would be smooth. The temperature response shown as a dotted line in Figure 3 was obtained with a constant heat load equal to the fixed heat load of 431,500 Btu /hr. Therefore, it represents th'e lower bound of the temperature response while the solid curve represents the upper bound. ! The dotted curve in Figure 3 provides an insight to the mechanisms of heat removal for the LPCI room. The temperature increased 54.5 deg from 104- to approximately 165 deg F during the first 12 hours but added only 6 degrees in the next 12 hours.. During the first 12. hours, the major contributor to heat removal is heat transfer i through the LPCI room surfaces. As the room air and surface temperatures increase, the heat removal through the walls decreases but the " chimney _ effect" air circulation-increases; The increased air circulation carries a major portion of the heat load out of the LPCI room which slows down the temperature increase. At the end of 6 days the room temperature added another 10.6 deg-to 175.2 deg F. From this point on, the room temperature starts to level off and would reach a temperature of 177.9 deg F after 11.7 days. Results 7

I RSA D 92 07 > Rev.0 l 4.0 Conclusion The temperature response in- the LPCI room- as. a result of loss of room cooler a functior. concurrent with a LOCA has been determined. The results show that the EQ' temperature limit of 185 deg F is not-exceeded for an extended period of-time. Therefore, operation of the LPCI system without room coolers does not compromise-the operability of the LPCI system. The temperature response;shows that it takes'6 ' days for the. temperature to reach 175_deg.'This would allow enough time to restore the room coolers. The calculations have been performed in a conservative manner by assuming both ECCS trains are running to maximize the room heat load. The torus - area temperature was maximized by using the torus _ water temperature for LOCA with one ECCS train as the forcing function. i References 3

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RSA D 92 07 Rev.O 5.0 References l

1. "ECCS Pump Room Transient Response to Loss of Room Cooler for Dresden l l

Station Units 2 and 3," RSA Calcnote RSA-D-89-01, August 15,1989.

2. "ECCS Pump Room Transient Response to Loss of Room Cooler for Dresden Station Units 2 and 3," RSA Calcnote RSA D-90-01, April 12,1990.

3. "An Alternate Method of ECCS Pump Room Transient Response for Dresden and Quad Cities Stations," RSA Calcnote RSA D 92-02, August 6,1992.

. 4. "RELAP4/ MOD 6 - A Computer Program for Transient Thermal Hydraulic Analysis of Nuclear Reactor and Related Systems," EG&G Idaho inc., CDAP TR 003, January 1978.

5. "RELAP4/ MOD 6 Certification," RSA Calcnote RSA-M-85-01, February 28,1985.

6. " Study of Thermodynamic Characteristics of Quad Cities ECCS Pump Rooms," RSA Calcnote RSA-Q 86 01, October 14,'1986.

7. " Air Flow Measurements on LPCI and Core Spray Pumps", Documentation of Telephone Conversation between K. Ramsden and S. Rhee, October 30,1992.

8. " Response to IE Bulletin 79-01 B Procedure for Use of Environmental Zone Maps for DNPS Units 2 and 3," Rev. 3, October 21,1988.

9. "Dresden Maximum Corner Pump Room (CS/LPCI) Temperatures," Bechtel Calc DR 721-M-001, October 19,1992.

10. Kreith, F., Principles of Heat Transfer, Second Edition, International Textbook Company,1965.

11. McAdams, W. H., Heat Transmission, Third edition, McGraw-Hill Book Company, 1954.

References 9

RSA D 92-07 Rev.0 -

12. " CONTEMPT 4/ MOD 4 A Multicompartment System Analysis Program," NUREG/CR- -

3716, page 69.

13. Todd, D. K., Ground Water Hydrology, page 195, John Wiley & Sons, Inc.,1959.-

14. ASHRAE Handbook 1981 Fundamentals, American Society of Heating, Refrigerating and Air-Conditioning Engineers, Inc.,1981.

15. "HPCI Room Thermal Response with L'oss of HPCI Room Cooler at Dresden Station," RSA Calcnote RSA D 92 06. ,

References - 10

RSA-D-92 07 Rev.O

                                                 'La_ble 1: Hea.t_Sjab Parameter _s_

Slab Description Volume Number Area, sq ft Heat Transfer Coeff Temp Diff, F 11] . Adjusted Area, sq f t . Thick, f tVoi, cu ft Btu /hr sq ft F Left Right Left Right Left Right Left Right i Pump room outside wall 1 4 1480 5 0.106 1480 31 3 4440 2 Pump 0 1 100 0 100 100 3 Pump room outside wall 1 4 1480 5 0.106 1480 31 3 4440 4 Pump room inside wall 1 3 2080 5 c.68 10 2080 283 3.5 7280 5 Pump room ceiling i 2 640 5 0.37 5 640 47 2 1280 6 Pump room floor 1 7 685 5 0.106 685 15 4 2740 7 Torus room floor 3 7 6515 0.43 0.106 20 560 138 4 26060 8 Torus room ceiling 3 2 6515 0.74 0.37 10 5 964 482 2 13030 9 Torus room outside wall 3 4 2280 0.79 0.106 20 360 48 3 6840 10 Rx bldg outside wall 2 6 11367 0.58 4 5 12] 1319 9094 3 34101 11 Rx bldg interior floors 2 2 19348 0.64 0.37 5 5 2477 1432 2 38696 12 Torus shell 5 3 16137 5 1.46 13] 16137 4712 0.042 673 13 Rx bldg roof 2 6 7770 0.74 4 10 l2] 1150 6216 0.29 2266 14 Wall bet U2/U3 Rx bldg 2 8 11367 0.58 0.58 5 5 1319 1319 3 34101 15 Wall bet torus rm & turb bldg 3 8 2280 0.79 0.79 20 20 360 360 3 6840 Notes:

1. Temperature difference assumed in calculating the combined natural convection and radiation heat transfer coefficient.

2. Heat transfer coefficient for wind velocity of 7.5 mph (Reference 14, page 23.12).

3. Heat transfer coefficient for non-reflective vertical surface (Reference 14, page 23.12)

Tables

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                                                                                             - RSA D 92 07 Rev.0-Torus Water Temperature am 190 - -

180 - -

                                           - 170 - -

100 - - E o lii e 150 - .- o. E. H 140 -- 130 -- 120 - - 110 - - O 2 4 6 8 10 .12 . Days Figure 2: Torus Water Temperature Figures 13

RSA D 92 07 Rev.0 Dresden LPCI 2A Room Temperature a .i 200

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EQ Temperature 180 -- LPCI Room _ 170 -. 160 -- l 8 'l 3 . e 150 -- ' O. E e t-140 - 130 - - BuHding Torus Room 120 - - 110 - - Initial Temperature

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O 2 4 6 8- 10 12 Days Figure 3: LPCI room temperature response due to loss of room cooler. Figures 14

H RSA D 92 07 j Rev,0 ; 1 i Listing Of Computer Runs jobID Description NFSPKB00789) Change from total heat load to fixed heat load at t - 69000 sec. NFSPKCU1846) Fixed heat load only. NFSPKF09608) Change interior floo: thickness to 1 ft. I i-i i a l-i l ? i e i i-l r I-i i 1 l l t-r^ ! Listing of Computer Runs -15 I-l

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4 i RSA D 92 07 Rev.0 i ! Appendix i

Contents i

1. Calculation of Combined Heat Transfer Coefficient 4 pages i

l 2. Determination of Soll Effective Heat Transfer Coefficient 3 pages ! 3. Heat Slab Dimensions 15 pages i i

4. Volume of Model Volumes 2-pages 4
5. Estimation of LPCI Room Temperature at 30 days 2 pages l-i t

l 4 i l I i 3 i .. i i i s. 4 l I i

o

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                                                                                                                                                       - RSA-D-92 07 Rev 0 Corg Heat Transfer Coefficient
                          ! Prepared tg: L:A Kot1DBecked by:                                                1 Reviewed by: 4'4(4 i

[ 180i -125j 115! 110 tg. F 1801- 170l j i 150i 4 tw.F 1201 130i 140! 150! 1051 105! 105 Dt 3 01 30! 3 01 30i 2 01 1 01 5 i Tg,K 338.7056 344.26111 349.81671 355.3722i 324.8167) 319.26111 316.4833 I Tw.K I 322.0389: 327.5944i 333.15l 338.70561 313.7056l 313.70561 313.7056 j L. ft i 17l -- 17) - 11 1 71 17 1 71 17) L. cm i 518.16! 518.161 518.161- 518.16! 518.16 518.16i 518.16 trot 120i 1201 1201 120! 1051 -105l 105 l psat, ref p: 1.69331 1.6933l 1.6933I 1.69331 1.1016 1.10161 1.1010 3 Rel hum i 0.9 51 0.9 51 - - 0.9 51 0.9 51 0.95 0.9 51 0.95 pv 1.6918881 1.719639 1.7473891 1.77514j 1.083587 1.065053I 1.055787 f ! pv,bar 0.1166521 0.1185651 0.120478j 0.1E'392i 0.074711 0.0734331 0.072794 j pt 14.7i 1 4.71 14.7l , 14.7l 14.7} - 14.7) 14.7 l pt, bar - 1.013529 1.013529i 1.013529! 1.013529 1.013529 1.013529l 1.013529 j Calculate emmisMty l l l 4 tau I 0.338706 0.344261, 0.3498171 0.3553721 0.324817l 0.319261, 0.316483 beta i 1.7813541 1.788421 1.7953731 1.802216 1.5878461 1.5803541 1.576559 40 i 2.613721 2.620251 2.626771 2.63329l 2.59741 2.590871- 2.5876 i al i 1.0067331 1.0064421 1.0060621 1.0055941 1.0070721 1.0070521 1.007009 a2 1 0.161221 -0.1621 -0.16278! 0.163551 -0.15926 -0.158471 -0.15808 l eps.t.ref I 0.263955 0.2622511 0.2604881 0.258671) 0.246631 0.247794 0.248354 i pe i 1.5266941 - 1.530885j 1.535043l 1.539168i 1.3491441 1.346261 1.344811 beta. max I 0.180219 . 0.194351 0.208255l 0.2219411 0.143851l 0.128885 0.121276 j cw 1.0832981 1.083944) 1.084581 1.085207) 1.064139l 1.0635851 1.063308 eps 0.2859461 0.2842651 0.28252) 0.280712i 0.262449 0.263551 0.264076 l j. d Calculate absorptMtY l l l l taul - I 0.32203S 0.3275941 0.33315 0.338706 0.3137061 0.3137061 0.313706 l betal 1.759441 1.7668691 1.774172 1.781354l 1.57273' 1.57273 1.57273 j a0 -2.594141 -2.600671 2.6072 -2.613721 -2.58434 -2.58434 -2.58434 at- 1.0070731 1.0070491 1.006935 1.0067331 1.006943 1.006043 1.006943 } a2 -0.15887} 0.159651--0.160441 0.161221 0.157681 0.157681 -0.15768 ~ eps.t,ref 0.2687311 0.2672I 0.265605 0.2639581 0.24801 0.24891 0.2489 i pe i 1.5398051 1.5438831 1.5479291 1.551945I 1.3550361 1.3491951 1.346274 beta. max i 0.136391I 0.151247 0.165854i 0.180219l 0.113618I ~ 0.1136181 0.113618 cw i 1.082951 1.08361 . 1.084261 1.08491 1.063943 1.0634861 1.063256 j alpha j 0.297706 0.296079l 0.2943851 0.2926261 0.268995 0.2668 0 N m j Calculate Radiation coeft l eps.w 0.9 51 0.9 51 0.95 0.95 0.95: 0.95 0.95 h T 9.74th 10.112871 10.48611 10.859681 5.4884581 2.6754871 1.320063 I hr 0.324688 0.717096 0.349537) 0.3619801 0.274423 0I 575491 0.264133 Calculate combined heat transfer coeff - wall l hc 0.590374- 0.5903741 0.590374 0.5903741 0.5157391 0.409343 0.324895 4 h = hr + h 0.915062i 0.92747) 0,.9390111 0.952364 0.7901621 0.676891 0.589028 . ceiling - l- l hc 0.683591 0.683591 0.683591 0.683591 0.5971721 0.473975 0.376195 h = hr + h 1.008279 1.0206871 1.033128! 1.045581 0.8715951 0.741524 0.640327 + floor l

                                                   }                     l               l-L                            8.44l           8.4 44             8.44)                   8. 4 41            8.44              8.44                      8.44 i                hc                        0.17851         0.17851            0.17851-              0.17851 0.161293                    0.135631             0.114051 i                h = hr + h l 0.5031881 0.5155961 0.5280371 0.5404891 0.435716 0.403179i 0.378184 Page 1                                                                                         HRAD.XLS

C0lMONWEALTH EDISON COMPANY NUCLEAR FUEL SERVICES DEP ARTMENT PROJECT DATE CALCULATION NUMBER

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i. %rAL I -P Rn OJs,h. aldL A - se.es s2 = 3 ft

6= 3 ft V = 4389 ft" Ref: %g B - 127 Ma 56 2. P Y 2. 2.

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~~63 - see - 1. $ 22.ofe kw f .i bveericA sw ? 4b45) e 2(ll'/,I)- 59-3o Q = - l~~
- i 1606o.0 M* / l % = 64h(ii7.s3- f(so? -(ssi - p3)( V -as) ,
I
~~= 1uz +.os 4c /~~
~~Q=l062A.nsW(2t)=2 nits.ua 49~~
~~/ \~~
~~l l J~~
~~.. .- --, - .. . - . , . - - , - - . , ~ . , , , - . -~~
COWONSEALTH EDISON COMPANY NUCLEAR FUEL SERVICES DEPARTMENT PROJECT DDEM OAlt 9 " O' CALCULAfloN NUM0tp rl(g LC/ C. !M .s pagg gr SUBJECT !AM/ DJI!'MA Wf TW Lit /r' 2 etr*7% ( / N 7"P+F 7f u% A6.se64 PREPAttp gy _ *
~~CHECKED BY REVitet0 BY gr.c -~~
~~6 3 ,' . , - (w /.. e .e e..r) _NW CIAlo t (p 14) \ l~~
~~! d 4 *a. __~~
~~f !$' O ' _ 3 7g.g --- j -l g.;~~
~~PL. I l~~
~~, ,, @4l -~~
i
*11 6 . .
I
~~. .. I' (~~
~~47P 6 g_ j scenon e-s, M7~~
~
OlMEBSior4s G i s ,o' uNen ', [10I, hvc Fe7sa.'tiA %MA) i M - 0a7 m,Y (vzi)+ 2(zsodj( 6s7 -614) lSiO*)SO.cr @ m mees centorn. ow w Amet. / 7,opA , W m(H I L V W 'y ( or452#v h yt'. , ! FAODIei6 /n.L t,q-(t c e y w 7- W 7trUS-4.co m \ l \ Sit 95o G i b (Avet. u3 7 2. a5 s so I-evet. 176 S 7 7 670 fNG
- .23f669 S45 u

v6L
~~_+ 275 '7 % ' Si7 Levth 2 455 #40 f6' v h'LUMtter, S% .v 'toL.ve? s warment at oncerrtm Poe consceutmsn~~
% * '7 4'Is Iao veo ' M[O ,9s) = L 552.xte ' 46' T4h% "towha os (in.s)( I45) = 17am.cW, P>a lh&me /0, coo W Poe. cesecuttnse ZVOQ* I,5 = 14) /h -id = %T 4 6S7 - S47.5 +DrEN3 I eLw r so.s-es.s$?r*%
~~C0tMONWEALTH EDISON COMPANY~~
'4U C L E A R FUEL SERVICES DEPARTMENT PROJECT UMOOOI DATE 4'"72"@7 CALCOLATION NUW9tR flLe d NE PAGE OF SU8JtCg I gy,, puppns A M $TP#H LINC @$ erg !N W IndvA &
g PREPARED BY m l . ni, F cHtexto sv Revitato ev NM > M Sl<6c (p. I5) VocumG ReTcntL524ff$ $ [Q peesow r=s Are .pwee I, sewd S , P. s.z.s-3 , [2.] preotw ngc.ww. gewg_ sramos vuir 2. , p t,Tp
~~++t-grs > ] Oecscos noctem p>~a. srknam. Un or 7., f 4, I c> m- 71~~
[4] % e w se- v~ .r 2 , aOo m.4s [5] Ca.esceu new he sw un sr z , j2 4,10 M-+ 0.] oees e nucc a n - at stanm vuns : 4, Is ri i c> m7 o pnesom ewa.ew a. pe srenuN UN875 E ,5 , [4 IP M~3 [7} [.03 (Rc , wen ma*vemenew ver s , t r,'" minou c4/ /ta 5 *., , n o ea w v ,sett, 4 {9] OEc50CN wma twee vrrnm a m n 2 t,5 / 5 ' o M t. ocesoca neu. cwt wem. sren.,4 u w rs 2.i,s p c' I .2 m-6 [fo] 4 Gm8'= **.. 9 4
~~, - - , - - .,_,._.,cr,.. , ,.-.._,..,..,,....,,o-, . - > - - . - 4... m ,, y , - . .~~
~~. - . _ - . _ - . ._ .-. . ~ _ - . ~ . - . ~ . - _ _ . . . .~~
T ! COWONWEALTH EDISON COMPANY j NUCLEAR FUEL SERVICES DEPARTWENT PROJECT DATE CALCULATION NUWSER FlLE PAGE OF j SUBJECT PREPARED BY CHECKED BY REVIEWED BY i j hk ofMahlVks 1
~~l. hwI -~~
LPCI i Di m ,,,,,e a,a ter g w s y a f/ w 37 5 > Sls j .tsytr 37ft. ' V f (31.sx ass)" 52 ' 27,4 31 ft j Ass m ~t of ocy*J- % ga~r i I V,s
~~o.1 V 24,688 ft '~~
Vs = 2 +,6 f2. ft' wu au) a.s f . . i 2 VM 2- Rx B19 Go. gio- 14 of %r %4 D,.-,..,,, ," ) i Elu - VM i . SI7 '6 " 273226
~~545'6 " 251bb1 570 /74577 521' 23i 7z8~~
~~' G I3' 759490 _ . _ .~~
~~#GL~~
~~I,615,190 fpt Ik, M g cue 4 As s m' - /62, o c .~~
~~M Npd Va~~
0. 5 = 0.t S < 14f fl10

720,45%.
~~Va = 615, o00 ft' wns und rs tyx .~~
~~,e,..,,,,, .---n . . . - - - . - , , -~~
~~, - . . . . - . . . _ ~ . . - . ..__ ._--- . ._..~ .- .-. . . - _ _ _ - _ - ...__ - , _ . . ..-~~
~~l C0WONWEALTH EDISON COMPANY GUCLEAR FUEL SERVICES DEPARTMENT PROJECT DATE~~
~*
C ALCUL ATION NUMBER FILE PAGE OF .; SUBJECT PREPARED BY P. L KONG Q.K - p/<f/C j h
~~, Vo% of V M *,G.L Vo % s (v G f~~
[. 3 Vo k 3 To m s R-Dwr> *) ( Ja p1 o c IWsM, V 2 + 2, is f ft ' ' 1 Fa & % h 1 case l \/d
~~o. 5 V = 12 +, 068 ft v' L~~
l 4. %k + &d i % V ' 9 x t o' k'
~~s. VL 5- 7u.s "~~
o c & % L, D ,* m s, w s ) l (su. f 9 u V 2,+2 no' l Vrk 5 is TD V , - V a's 4 mA . l 6. V L 6i O d s. s. A ir . J h V= fxtO' ft )
~~7. A7 bl uu V= 1910 1~~
~~pc' /~~
~~
~~8. Ve% 8. < Tad.u (bly Rx SIG ,~~
~~s 604 V 7xt0' ft' .... g~~
*
~~ice e~~
~~, g -----.,y---r-rt p,y p ,_y-g y y- - , -.~~
~~RSA D-92 07 Rev 0 Prepared by: Q% j Checked by: Reviewed by: %Ah 1~~
P.1.40NG l l ESTIMATION OF LPCI ROOM TEMPERATURE AT 30 DAYS I I I l The temperature after 11.5 days is estimated by first examining j the change in temperature every two hours for 32 hours preceding t = 276 hours.
~~day hour delta time Temp detta Temp 3 41 177.511 32I 177.545 0.034 3 01 177.578) 0.033 2 81 177.611~~
~~0.033I 2 61 177.643 0.032~~
> 2 41 177.674 0.031 d 22i 177.705 0.031 20I 177.735] 0.03l ' 0.029; 18i 177.764l i 16! 177.793 0.029! 4 14 177.821 0.0281
~~12. 177.849 0.028i 10l 177.876: 0.027j~~
~~-8l 177.903l 0.027) 61 177.929 i 0.0261 -4 177.954 0.025]~~
2 177.979 0.025l 11.5 276 0 178.003 0.024 l l The rate of change of delta Temperature is about 0.0005 deg per 2 hours. Estimate temp assuming this rate. 0 178.003 0.0240 2 178.027 0.0235 4j 178.050 0.0230 6l 178.072 0.0225
~
81 178.094 0.0220 10 178.1161 0.0215 12 178.137 0.0210 14l 178.157, 0.0205 1 61 178.177, 0.0200 18 178.1971 0.0195 20 178.216 0.01901 22 178.234 0.0185 24 178.252 0.0100 26 178.270 0.0175 2 81 178.287 0.0170 30 178.303 0.0165 32 178.319 0.0160 34 178.335 0.0155 Page1 LORCEST.XLS
=
l 1 i RSA-D-9247 Rev 0 l l l Prepared by: OhiChecked by: lRewowed by: dtl ; W P. L KQNG 3G 178.3501 0.01501 38} 178.364) 0.01451 l 40l 178.378l 0.01401 j 42i 178.392 0.01351 ! 44l 178.405 0.01301 4 4 61 178.417l 0.0125! i 48l 178.429l 0.0120l 50 178.441 0.01151 __ 1 52. 178.452 0.0110 54- 178.462l 0.0105 -l 56l 178.472l 0.0100 i 5 81 178.4821 0.0096 ! 00l 178.491l 0.0000 I ! 62 178.499! 0.0005 I . 64 178.507I 0.00801 l 1 6 61 178.515 0.00751 i 6 81 178.5221 0.0070l l 7 01 178.5281 0.00651 7 21 178.534 0.00001 4 74 178.540 0.0055l l 76 178.545 0.0050 78 178.549 0.0045 8 01 178.553 0.0040 0.0035
82. 178.557 l 84 178.580 0.0030 8 64 178.562. 0.0025 8 81 178.564l 0.0020 9 01 178.5881 0.0015 l 92 178.567 0.0010 1 94 178.567 0.0005 15.5 372l 9 61 178.567 0.0000 -

1 I Therefore, the maximum temperature is 178.6 dog F.
The temperature at 30 days would be less than or equal to 178.6 deQ F. l E { 1 i j Page 2 LORCEST.XLS
ENCLOSURE 3 CECO Calculation DSE-O 004 Evaluation of the impact of LOCA Combined with a Loss of Room Coolers on Performance of General Electric RHR Pump Motors, , Dresden 2&3/QUnd Cities 1&2 ! i i 1 k
Exhibit B 2 NUCLEAR ENGINEERING DEPAR M ENT ENC-QE-51.D Revision 2 CALCU1ATION TITLE PAGE Page 2 of 2 PAGE.: OF
~~; STATION / UNIT I hr/ht+1, O l' '~~
gggggy l[ RE1ATED CALCULATION TITLEt } gyggdjery W& $w Mf /.0% l_ l REG. RE M D G m [7, d y & dedit hM bb NON-SATETY
~~i g p,/ g/,,,(-fe. l-l RELATE I~~
~~ANg~~
~~##g'~~
~~Fu "/' lEl ENVIRONMEN QUALIFICATION l~_lASME 1 srcrion tri l r~~
~~CALC NUMBER SYSTEM GROUP } EUIPNUMBER(S)Atle9N-)~~
~~-/ Tota-D,(~~
~~i j 24.ieo/A-a fz im.s D.SE-f-Gc'/ APPROVER DATE DATE REVIEWER DATE REV. CHRON # PREPARER~~
~~& Sb 1~~
~~00 Yuff& 'O i i i [ l 4 l t I w QE-51.D (20)_ i~~
~~116 2 g-20. -~~
t
Exhibit C NUCLEAR ENGINEERENG DEPARWENT TABLE OF CONTENTS ENC-QE-51.D Revision 2 i Page 2 of 2 REV.O PAGE 8 0F CALCULATION NO: gjg, ,,gg y PAGES a DESCRIPTION SECTIONS .__ 1 CALCULATION TITLE PAGE z 2 TABLE OF CONTENTS - , 4 3 llISTORICAL DATA (REQUIRED ONLY FOR REVISIONS) I 4 CALCU1ATION
~~SUMMARY~~
~~SilEET~~
~~/ $ CALCULATION S!!EET(S) 6 CALCU1ATION REVIEW CIIECKLIST 7 COMPUTER APPLICATION REVIEW CllECKLIST O~~
~~4 ATTAC!!MENTS~~
~~.Y QE- 51.D (22) 1162g-22 \~~
' Exhibit E NUCLEAR D4GINEERING DEPARMENT ENC-QE-51.D ,
~~CALCULATION~~
~~SUMMARY~~
SHEET Ravision 2 Page 2 of 3 1 4 l CALCULATION NO: d36*- $-SSV REV. O PAGE [ OF t PURPOSE /0BJECTIVE OF CALCULATION SVeltte& % fdeh OY Mb Wlk l% Gdos n y<$nu<auco l n 4is y pd '- qG ENR Pn noAus ae/ n v'ts. ,s u s k fund / d h c. J ASSUMPTIONS / DESIGN INPUTS h f lO REFERDiCES
~~/, Sf $~nl4 r* h# WA~~
. .t. 5 4' & w fu - 64'-*CR ./c $ M/apu:S bkd f-ZYfg wir4f J. Memo & 3 Sedeye. a k/ i 4 cded/</rmu c4D -o et fen-~ Bao/, dati./ 4.zy-ge I CONCLUSIONS
~~& h0 fwaf <&to O!Y f *d i~~
w4d pek Amy soym 4 xa'ree Jos/ap g' ga/ Loe,4/2 ofe aeeMeuv4 PREPARER DATE 1 REMARKS- _ h h f l#*N'YL REVIEWER DATE 1 QE -51.D (26) 1162g-26
~~. .- . - - - - , - - ~~~
~~Exhibit F NUCLEAR ENGINEERING DEPARTMDfT ENC-QE-51.D CALCULATION SHEET R0 vision 2 i~~
. Page 2 of 2 CALC. NOs A16"(**GC H PAGE N01 OT '
Q / sua k gg.c,,,a 7L r.au#s f& ,d, &&<uas /{E., are. .dDn a f f*uf 7k- durv.e
~~/~,y 2 * / dda cf'#j ust %~~
j'Af& 80. duo k coau d &v dAe&S M & "' ""~ '
"* "'"" **g/ Me'e l o p & > M y a*<'az-'& '""
~~1"/ a f./Itp*e +~~
~~~4t<- , d y & '- W 12e aed*<u"* UO tiuol* e u)rudruj6 ad C B / ' / h , 7 * / F C f~~
~~t o / 7 ), .~~
~~so*c w f r -i.c < Y **" f 0 fe's jo/ 6pl lg,se, (1402*262f[ot+/G*e)~~
~~~jhe. /?/t2 rpo<a -t q'm&* Prui4'/4 "'l"M t- 0M eeu<dha.d urr1% / ass o/ -~~
~~arc.- neu// f 4fc. - dl*G*< *+ peps ci.3 &cm A %/M dieu %f -% l j $ sud 1/ E6~~
~~/f0*P l }$ A d a a u de~~
~~-ha,u.rskre nd w b g'repu+-aeeidaf.~~
a e ltso dop (38,2 %) Ju.cing /7 9%< la*/ rik-l fer N. //e, %d Fl.'ipap d l k As
~~-f.ouprakro-So e .~~
~~gor- % =A.< y M pum,o jusfe/4, aceihk , suearey utu k y~~
~~.A fr 2 <ao h rs 44up. ochre f c(k.~~
~~6 22.5 *e + .Co 2 + /e'e .:::. ./qr,.g y 4 REVISION~~
~~- - BY/DATE CHECKED /DATE QE .51.D (29) 4 1162g-29~~
~~Exhibit F NUCLEAR UfGINEERING DEPARTMENT ENC-QE-51.D CALCULATION SHEET Rsvision 2~~
. Page 2 of 2 CALC. NO3 MS *~ "MN PAGE NO: [ OF [ -gg.a.,
Gru 4, ao) t(of}/4'th/c A intalalhe o cL ftabhe.) 4tacoua/2 adou l- n.c, 000 L*" - af M 2.e *c e m S t claralru< a eis 4t< Pe< Q<u<s 4, e ge- wJ.v, + ai,erabroua' s 6et cqc.eauV atI 4e.- suBjuk ewyb b y o.aA w F b a tt,2so a ak twe W waku) M d I M ' d M Q u a d 8 J b' d NE / A7Af6 pay CI0 Q Ce=g % 4 -h pa ryr.aueul6 z,, m u aktw c) w auah & ( -ax af 14Ct) sW li.% Ale ( 6900o % w ill daf- +Le, BhDpp 4 p .r g m it- raged eq ,tu.utb dung so & + 0,aal4 d epeA 4 uoeA M/t oes a ee;dw'- ad are. I:&. fM Ch thaswa\ assfiee-REVISION
~~-- BY/DATE CHECKED /DATE QE-51.5(29) 1162g - - - - - - - -~~
~~Exhibit-G NUCLEAR ENGINEERING DEPARTMENT ENC-QE-51.D CALCULATION REVIEW CHECKLIST R vision 2~~
~~- Page 2 of 2 CALCULATION Not MG l -0B4 REv 6 PAGE f Or REVIEWED BY: DATE:~~
~~YES NO REMARKS~~
1. IS THE OBJECTIVE OF THE ANALYSIS CLEARLY STATED 7

2. ARE ASSUMPTIONS AND ENGINEERING JUDGEMENTS VALID AND DOCUMENTED 7

3. ARE ANY ASSUMPTIONS THAT NEED REVERIFICATION IDENTIFIED 7

4. ARE THE REFERENCES (1.E. DRAWINGS, CODES, STANDARDS.) LISTED BY REVISION EDITION, DATE, ETC.7

5. IS THE DESIGN METHOD CORRECT AND e APPROPRIATE FOR THIS ANALYSIS 7
~~_, 6. IS THE CALCULATION IN COMPLIANCE WITH DESIGN CRITERIA CODES STANDARDS, {sh AND REG. GUIDES 7~~
7. ARE THE UNITS CLEARLY IDENTIFIED, AND EQUATIONS PROPERLY DERIVED AND APPLIED 7

8. ARE THE DESIGN INPUTS AND THEIR SOURCES IDENTIFIED AND IN
- COMPLIANCE WITH UFSAR, TECH SPECS 7 li 9. ARE THE RESULTS COMPATIBLE WITH THE INPUTS AND RECOMMENDATIONS MADE7 l 10.WAS A DETAILED REVIEW PERFORMED 7 IF "N0" PROVIDE JUSTIFICATION FOR YOUR REVIEW METHOD.
~
~~l" QE- 51.D (31)~~
~~~(162c-31}}~~

ML20126G102

Text

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