Text

Response to Request for Additional Information Concerning Technical Specification Change Request on Reactor Water Clean-Up High Energy Line Break Detection and Isolation
	ML061230203
Person / Time
Site:	Oyster Creek
Issue date:	04/21/2006
From:	Cowan P; AmerGen Energy Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	2130-06-20323
	Download: ML061230203 (140)
	v • d • e

AmerGenm AmerGen Energy Company, LLC 200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com An Exelon Company 2130-06-20323 April 21, 2006 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Oyster Creek Generating Station Facility Operating License No. DPR-16 NRC Docket No. 50-219

Subject:

Response to Request for Additional Information Concerning Technical Specification Change Request on Reactor Water Clean-up High Energy Line Break Detection and Isolation

References:

1)

USNRC letter from G. E. Miller to Christopher M. Crane, dated March 9, 2006, "Oyster Creek Nuclear Generating Station - Request for Additional Information RE: Technical Specification Change Request - Reactor Water Clean-up High Energy Line Break Detection and Isolation (TAC No.

MC6046).

2)

AmerGen letter 2130-05-20029 dated February 2, 2005, Technical Specification Change Request No. 280 - Reactor Water Clean-up High Energy Line Break Detection and Isolation.

This letter provides additional information as requested by the NRC staff in Reference 1. The request for information is in regard to AmerGen Energy Company's Technical Specification Change Request (TSCR) No. 280 (Reference 2) to include the setpoint for the Reactor Water Clean-up High Energy Line Break detection and isolation instrumentation in the Technical Specifications. Enclosure 1 to this letter provides the AmerGen responses to the request for additional information. Enclosure 2 provides calculation C-1302-215-E610-060, as requested by the NRC. No changes to the original license amendment request are required due to submittal of these responses to the NRC RAI.

If any additional information is needed, please contact Mr. Dave Robillard at (610) 765-5952.

AC

U. S. Nuclear Regulatory Commission April 21, 2006 Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Respectfully, Lit -4 ° (

Executed On L 3 /I.

gil Pamela B. Cowan Director - Licensing & Regulatory Affairs AmerGen Energy Company, LLC

Enclosure:

cc:

S. J. Collins, Administrator, USNRC Region 1 G. E. Miller, USNRC Project Manager, Oyster Creek M. S. Ferdas, USNRC Senior Resident Inspector, Oyster Creek File No. 04036

ENCLOSURE 1 OYSTER CREEK GENERATING STATION TECHNICAL SPECIFICATION CHANGE REQUEST 280 REGARDING REACTOR WATER CLEAN-UP HIGH ENERGY LINE BREAK RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION 2130-06-20323 Page 1 of 8 NRC Request 1 Describe HELB analysis utilized in postulating an RWCU system HELB downstream of the system isolation valves (e.g., computer codes used, location of the postulated break, reactor coolant mass and energy discharge, predicted temperature response, etc.).

Response

The HELB analysis evaluates the thermal hydraulic response of reactor building cleanup system compartments to a RWCU line break (Figure 1). The results of the evaluation are used to provide input for establishing an appropriate setpoint for the temperature monitoring instrumentation that will isolate the cleanup system. The analysis evaluates the ability to detect (as well as the time to detect) a small break using an area temperature of 1800F as the indication of a break. To evaluate this condition a conservative representation of the smallest line size required to be considered within the licensing basis HELB is evaluated. This size line break will be the most difficult to detect and is therefore, appropriate for consideration in this evaluation of break detection.

The analysis is performed using GOTHIC version 5.0e. The Cleanup Heat Exchanger and Pump Rooms are modeled as separate subdivided volumes connected via flow paths. The postulated break is located in the Heat Exchanger room which maximizes the distance to the area designated as the detection location. The subdivided modeling of the rooms was implemented to account for the transport time from when steam enters the Heat Exchanger room to when the detector location reaches 1800F. The Pump room is connected to the adjoining reactor building compartments by an open entrance, which is modeled as flow paths connecting to a constant pressure boundary condition.

The influence of the ventilation system was included in the modeling to ensure that the time to detection was completely understood. The ventilation draws air (exhausts) from the two rooms.

These were modeled as flow boundary conditions not shown in Figure 1.

The break is modeled as a constant pressure boundary condition with a flow path that connects the boundary condition to the subdivided GOTHIC volume representing the Heat Exchanger room. The boundary condition is established to provide Reactor Coolant (RC) from the recirculation loop B to the Heat Exchanger room. The boundary condition is established based on a reactor steam dome pressure of 1035 psia, reactor water level of 16Z' TAF, and a liquid enthalpy of 525 BTU/lbm. The boundary condition pressure accounts for the water level above the elevation of the RWCU line connection to the recirculation loop for a total source pressure of approximately 1040.3 psia.

The length of the GOTHIC break flow path and associated component losses are established to be consistent with that documented in the calculation C-1302-153-5450-070 Rev. 1 "OC RELAP5 Analysis of Cleanup Line Break," and depicted in Figure 2. The flow path area is conservatively modeled as a continuous 0.75 inch diameter line. This assumption will minimize the leakage flow and make for a more difficult detection condition. The conservatism is found in the smaller line size than that documented in the licensing basis for HELB evaluation (1 inch).

In addition, the resulting pressure losses associated with the small line are exaggerated further by assuming the size applies to the full length of the flow path (the actual nominal line size is 6 2130-06-20323 Page 2 of 8 inch). The flow path direction is established to discharge into one of the Heat Exchanger room side walls to minimize the transport of steam to the pump room area where the area designated for detection is located. The break assumes the flow is compressible and uses the homogeneous equilibrium critical flow model with a discharge coefficient of 1.

The modeling of the Pump and Heat Exchanger rooms also includes the influence of heat transfer to structures within the room. A total of 42 heat conductors are included to represent the walls, floors and ceilings of the rooms. The heat structures will remove some of the break energy and add to the delay in detection that would not be recognized if they were not included.

The heat transfer includes the use of the ADD condensate/convection option, which combines the condensate and convection heat transfer. The MAX option is used for the condensation, which provides the maximum value of Uchida and Gido/Koestel. Natural and forced convection are included as part of the modeling while radiation heat transfer is not included.

The detector is not explicitly modeled, but is represented as the temperature in the sub-volumes of the Pump room located adjacent to the Reactor Building. These sub-volumes are designated as 2s3 and 2s6 in Figure 1.

The break flow rate predicted by the model is 13 Ibm/sec. The location 2s6 reaches the 1 800F temperature 40 seconds after break initiation without ventilation (Figure 3) and 30 seconds after break initiation with ventilation (Figure 4). The location 2s3 reaches the 1800F temperature 55 seconds after break initiation without ventilation and 15 seconds after break initiation with ventilation.

NRC Request 2 Section 5 of Enclosure 1 to your submittal states the following:

This safety grade break detection/isolation equipment monitors RWCU pump room temperature and initiates a[n] RWCU system isolation when ambient temperature exceeds a preset limit, below the process safety limit of 1 800F. The system is designed to detect a line failure as small as a one-inch diameter pipe and as large as a full guillotine rupture of the largest system pipe (six-inch diameter). The small line break is the most difficult to detect, and such, is used to establish the location and actuation limit of the temperature monitor.

Define the terms preset limit, process safety limit, and temperature monitor actuation limit.

Explain the HELB analysis utilized to determine the preset limit and how this limit relates to the process safety limit (1 800F) and the temperature monitor actuation limit. Address the radiological impact of an RWCU system HELB for a small pipe. In particular, consider a pipe break where the release of reactor coolant mass is very small in magnitude over a prolonged period of time (e.g., slow leak), making detection and timely closure of the RWCU isolation valves even more difficult.

2130-06-20323 Page 3 of 8

Response

Definition of Terms Preset Limit - is used to represent the nominal value assigned to the instrumentation that actuates the isolation signal. This limit is established as a nominal setpoint that will not exceed the value used in the analysis when error and instrument drift are considered. It is also evaluated to ensure that it will not cause a spurious isolation of the RWCU system.

Process Safety Limit - is used in this context to represent the value of the measured variable used by the HELB analysis to initiate the valve isolation. Specifically, the analysis assumes an area temperature of 1800F to isolate the valves.

Temperature Monitor Actuation Limit - is used in this context to represent the upper limit of the detection device. This accounts for setpoint drift and error. The establishment of a setpoint must ensure that the actuation signal for valve closure occurs at or before the temperature in the sensor's location exceeds 1800F. The Temperature Monitor Actuation Limit must be s 1800F.

HELB Analysis The HELB analysis is utilized to evaluate the use of the 1800F area temperature as an acceptable analysis limit for detection of the small break. The details of that analysis are described in response to Question 1. The Preset Limit is established to ensure that instrument error and drift does not result in its actuation at a value in excess of the analysis temperature value of 1800F. Therefore, it is established via calculation to be 1600F.

Radiological Impact The 1-inch nominal diameter size is evaluated as part of the detection assessment. This size was selected to be consistent with the current accident analysis documented in Amendment 75 to the Facility Description and Safety Analysis Report (FDSAR) (section 4.1.1), which states the following.

Excerpt from Amendment 75 to FDSAR 4.1 Criteria and Assumotions The following criteria and assumptions form the basis for the analysis presented in this section.

4.1.1 Type of Postulated Breaks

a.

Circumferential breaks in piping runs and branch runs exceeding 1-inch nominal pipe size

b.

Longitudinal breaks in piping runs and branch runs 4-inch nominal pipe size and larger This information is also consistent with that presented in Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants, Section 3.6.1, Appendix B, Branch Technical Position SPLB 3-1. Therefore, for HELB evaluations at Oyster Creek the small line size is defined by this criteria as 1-inch nominal pipe size. The radiological consequences 2130-06-20323 Page 4 of 8 were evaluated in support of the modification effort. Two specific evaluations were conducted.

For each of these evaluations it was assessed that the large break (with a conservatively established isolation time of 2 minutes) produced the limiting radiological consequence when compared with the 1 -inch nominal pipe size. As such the large break size was used with the conservatively established isolation time to assess the consequences. The first of these analyses assessed the offsite dose consequences summarized below.

When evaluating the isolation time of the proposed modification an assessment of the impact on off site release was conducted and documented in calculation C-1302-215-E610-061, Rev. 1, URB EQ Profiles Cleanup Line Modified Break Detection." The requirements of SRP 15.6.2 are applied as follows for the mass release to be used in the dose calculation:

The fraction of the iodine assumed to become airborne and available for release to the atmosphere, without credit for plateout, is equal to the fraction of the coolant flashing into steam in the depressurization process. The flash fraction is determined by assuming the discharge to be a constant enthalpy process.

The portion of the break-flow that flashes to steam under the constant enthalpy expansion process will be used as the release term in the dose analysis. It is this mass release that can be compared to the FSAR mass release for the Main Steam Line Break (MSLB) break analysis.

The dose analysis utilizes the methodology identified in Regulatory Guide 1.5 and the reactor coolant activity will be based upon the current OC Tech Spec limit. The calculation results indicate that the total steam released is less than that assumed for the Main Steam Line Break dose calculation in Chapter 15 of the OC FSAR. Therefore, radiological impact of an RWCU system HELB for a small pipe is bounded by the MSLB accident.

The second of the radiological analyses was associated with evaluating the exposure of equipment located in the RWCU Pump and Heat Exchanger room area. This analysis showed that the exposure associated with the break analysis is well within the capability of the qualified equipment within the area.

NRC Request 3 Section 5 of Enclosure 1 to this submittal states the following:

Calculation C-1302-21 5-E610-060... determined that a detector located at the RWCU pump room exit will detect the failure of an instrument tube size break in one minute.

This calculation established an actuation setpoint of (1800F) for the RWCU HELB detectors to be consistent with the Emergency Operating Procedures (EOPs) at the time of the modification... This is a conservative value that considers the maximum allowable environmental temperature for the equipment and instrumentation.

Summarize how the actuation setpoint of 1 800F is a conservative value when compared to the maximum allowable environmental temperature for equipment and instrumentation installed in the affected area, system operational values, and system interactions. State how use of the 1 800F setpoint facilitates effective and timely detection and isolation of the RWCU system HELB described above (e.g., setpoint is high enough to prevent system isolation due to spurious actuation). Compare the predicted maximum temperature for the RWCU pump room with the 2130-06-20323 Page 5 of 8 bounding temperature profiles used for equipment qualification. Consider the HELB results compared to the profiles of other equipment qualification parameters (e.g., steam, pressure, radiation).

Provide Calculation C-1 302-215-E610-060, which supports the safety evaluation for the modification.

Response

The 1800F analysis temperature value is established to detect a break condition within the RWCU area. Therefore, it is provided to ensure that the environmental temperatures that result from a break are maintained at or below those evaluated for equipment and instrumentation required to mitigate the break. The 1800F analysis temperature value is used to establish a basis for those conditions.

As part of the evaluation of the 1800F analysis temperature value for isolation, the impact on Equipment Qualification (EQ) was considered. The aforementioned HELB analysis model was used to assess the time to reach the 1800F analysis temperature value for a range of break sizes. The analysis results show that the smallest break (13 Ibm/sec) is detected in 60 seconds while the largest break (850 Ibm/sec) is detected in 2 seconds. A number of intermediate breaks were also evaluated. These analytical detection timing results were further evaluated in calculation C-1302-215-E610-061, Rev. 1, "RB EQ Profiles Cleanup Line Modified Break Detection" to determine which would be applied in the evaluation of EQ program equipment. An integrated energy approach was used to assess which break would provide the greatest amount of energy into the Reactor Building. The evaluation concludes that the conservative result is obtained using the largest break assuming that the detection time is 10 seconds, which is an additional 8 seconds beyond that established in the calculation C-1 302-215-E610-060 Rev. 1, "Cleanup System Break Detection Requirements Evaluation." Therefore, the EQ profiles for the RWCU line break are conservatively established using the large break size assuming detection in 10 seconds. Since the detection time for the 1800F analytical temperature value is earlier than 10 seconds, this 1800F value is conservatively established for assessing the maximum allowable environmental temperature for equipment and instrumentation installed in the affected area, systems operational values, and system interactions.

The 1800F analytical temperature value is used to provide a basis for determining the nominal setpoint of the instrument that is installed in the plant. The establishment of the setpoint is critical to ensure that the response is both timely and effective. This means that the signal must occur prior to the analytical temperature value of 1800F, but not spuriously. The HELB analysis performed in support of this modification has been directed at providing the necessary criteria to ensure that the analytical detection value provides an appropriate value. It has been shown that the value is sufficient to detect all break sizes within the plant's licensing basis for the evaluation of HELBs. As such, the Radiological and Equipment Qualification issues are satisfactorily addressed by the value selected. Therefore, for the purpose of mitigation this value is effective and timely. The setpoint error calculation establishes a setpoint of 1600F that establishes an acceptable as-found value of 1720F, leaving 80F margin. In terms of the spurious actuation, the 1800F analytical temperature value is only related to this concern through the nominal setpoint and its error calculation since early isolation during an accident is not a safety concern. The setpoint error calculation establishes a lower as-left value for the setpoint at 156 0F. The normal 2130-06-20323 Page 6 of 8 April 21, 2006 average temperature for the area (documented in the error calculation) is 81OF. Thus, there is significant margin between the instrument actuation limit and the normal operating conditions within the plant, such that spurious actuations are not expected.

As described previously, the 1 800F analysis temperature value is used to provide the basis for the EQ profiles. The pressure and temperature profiles are developed in calculation C-1302-215-E610-061, Rev. 1, "RB EQ Profiles Cleanup Line Modified Break Detection". The radiation levels are assessed in calculation C-1302-215-E820-066, Rev. 0, "RWCU Area HELB TID". Each of these assessments are conservatively based on the 1800F analytical temperature value. The results of these evaluations are used to establish environmental profiles for equipment used to mitigate a RWCU HELB.

Calculation C-1302-215-E610-060 is provided as Enclosure 2 to this submittal.

NRC Request 4 Section 5.4.8.2 of the final safety analysis report states that for the RWCU system, the supply line has a motor operated isolation valve inside the drywell and two parallel motor operated isolation valves outside the drywell, and the return line has one motor operated isolation valve outside the drywell. Section 5.4.8.2 refers to Table 6.2-12, "Containment Isolation Valves/Mechanical Integrity," for isolation signals for each valve, however; Table 6.2-12, which lists the four RWCU system isolation valves (V-1 6-061, V-1 6-001, V-1 6-014 and V-1 6-002) does not show valve V-16-061 receiving a signal to isolate on RWCU HELB. Please explain this apparent discrepancy.

Response

As stated on page 5.4-14 of the Updated Final Safety Analysis Report, V-16-61 closes only on low-low reactor water level, high drywell pressure or High area temperature (RWCU HELB isolation signal). The omission (on page 4 of Table 6.2-12) of the signal indicator (e.g., 10) to annotate that V-16-61 will close on a RWCU HELB isolation signal was an oversight when the UFSAR was revised in April 2003. The marked up copy of Table 6.2-12 supporting the April 2003 UFSAR update correctly identified the signal indicator, however it was omitted when the page was retyped. This omission has been entered in the corrective action program and will be corrected in the next UFSAR update.

2130-06-20323 Page 7 of 8 Figure 2 GOTHIC Flow Path Model 6 -,

pe00rot *tI on t1. a.

Srt~

a oc *t i an 2130-06-20323 Page 8 of 8 VaporTemperature Pump Room Exit No Ventilation 220 -

__}Iemp e

r a tur 2 0 20___

40___

60 0

00 12 1

_lO 140

-Temperatur 120

-Temperatur 100 0

20 40 80 so 100 120 140 1

Time Jsac)

Figure 3 Vapor Temperature Pump Roow With Ventilation 220 -________

200-

=

=_

140 T

120 100 10 180 200 n Exit 20 40 so 80 100 120 140 160 180 200 Time sace)

Figure 4

ENCLOSURE 2 OYSTER CREEK GENERATING STATION TECHNICAL SPECIFICATION CHANGE REQUEST 280 REGARDING REACTOR WATER CLEAN-UP HIGH ENERGY LINE BREAK CALCULATION C-1302-215-E610-060, Revision 1 (128 pages)

04/18/06 10:00:09 NUCLEAR CALCULATION COVER SHEET Calculation Number.

Rev. # System Number(s) l C-1302-215-E610-060 l

1 215 ISheet 1 of Calculation

Subject:

Cleanup System Break Detection Requirements Evaluation Yes No Is this calculation within the OQA Plan Scope?

(If Yes, a verification is required)

Does this calculation contain assumptions / design input that requires onfirmation?

0 (If Yes, provide EDTTS No.(s))

Is this calculation performed as a design basis calculation?

i 0

(if Yes, identify design basis parameters (section 3.3))

Reference Source Documents (Calculations, Safety Evaluations) (Section 4.3.1.3)

DOCUMENT NO.

REV. NO.

Refer to section 3.0 of this calculation APPROVALS:

Originator

/

Date Paul N Hansen P Verification Engineer I Reviewer

,}

Date Francs P Kenny

r.

ae 3 -

Section Manager Date Nick Tinkouros, 90 oF 7 Z1 C11

04/18/06 10:00:09 (GPU NUCLEAR CALCULATION SHEET

Subject:

Cleanup Systen Break Detection Requirements Caic. No.

Rev. No.

Sheet No.

Evaluation C-1302-215-E610-060 2 of 1.0 PROBLEM STATEMNT:..

3 2.0

SUMMARY

OF RESULT:......................

3

3.0 REFERENCES

6

4.0 ASSUMPTIONS

6 5.0 DESIGN INPUT:.7.........

6.0 CALCULATION

7 6.1 GOlTHIC Input Calculations....................

8 6.2 G T ICIpu GOuatos C.....ANALYTICAL.......................RESULTS.................

25...

6.2 GOl HIC ANALYTICAL RESULTS............................................................................................................................................

25 Appendix I GOTHIC Output Figures.26 Case 1 No Ventilation.27 Case 2 Ventilation Functional.28 Appendix II GOTIC Input Deck.

29 Case ti No Ventilation30 Case 2 Ventilation Functional.31 Appendix III Detection Time for Larger Break Sizes.32 Case 3 Large Break - 850#J/sc.33 Case 4 Large Break - 450#/sec.34 Case S Large Break - 142#/sec.35

-~~

I I 04 8..

10:00:09 fGPU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Calc. No.

Rev. No.

Sheet No.

Evaluation C-1302-21S-E610-060 l

3 of 1.0 PROBLEM STATEMENT:

The Oyster Creek Nuclear Generating Station cleanup system will be modified to provide additional break detection. This modification is provided in response to SIL-604, which identified plant conditions were a failure of the cleanup system piping inside the reactor building could go undetected by the current automatic isolation system. To address this concern GPUN will install temperature sensors at the exit to the cleanup system pump room to monitor for elevated temperatures. Upon detection of elevated temperatures the cleanup system will receive an automatic isolation signal. This calculation evaluates the thermal hydraulic response of reactor building cleanup system compartments to a line break. The results of the evaluation are used to establish an appropriate setpoint for the temperature monitoring instrumentation that will isolate the cleanup system.

2.0

SUMMARY

OF RESULT:

A detector located at the cleanup system pump room exit will detect the failure of an instrument tube size break (Temp. >

1 80IF) within the Heat Exchanger Room in approximately I minute. The sensor should be located at or near the ceiling of the pump room entrance (refer to plan view below). This conclusion is true with as well as without ventilation as can be seen in the figures below. Although not evaluated in this calculation, this conclusion holds true for a break in the pump room as well since the sensor location is in the pump room.

Vapor Temperature Pump Room Exit No VonUtilaton 2W jaw

t.

II-:I 0

160 Ito 200 0

20 40 W

so teO 120 140 Tke b)

04/18/06 10:00:09 (GPU NUCLEAR CALCULATION SHEET Subjec: Cleanup System Break Detection Requirements Calc. No.

Evaluation C-1302-215-E610-060 Rev. No.

Sheet No.

1 4of VaporTampemturs Pump Room Exit With Vantdaton 220 10 E

II 10

-Tept 2==

3

.T menu W

140 120 0o 20 40 w

so i0 noke (ee) 120 140 lo0 ISO 200

a /lA/06 10:00:09 MGPU NUCLEAR Pump Room

.W Scnsor in either location lo HX Room Sensor Location Figure I Break detection sensitivity studies were performed for use in establishing an EQ environment. Tbese sensitivity studies are documented in Appendix I & HI and summarized in the table below.

I BREAK SIZE DETECTION TIME SENSITIVITY I

Case #

Break Flow Ventilation Detection Time I

13#Isec NO 60 seconds 2

13#/sec YES 30 seconds 3

850#Isec NO 2 seconds 4

450#/sec NO 3 seconds 5

142#/sec NO II seconds

04/18/06 10:OD:09 (MPU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Calc. No.

Rev. No.

Sheet No.

Evaluation C-1302-215-E610-060 I

6 of

3.0 REFERENCES

1.

General Arrangement Reactor Building Sections C-C, D-D & E-E Dwg. No. 3E-15302-009 Rev. 4

2.

General Arrangement Reactor Building Sections A-A Dwg. No. 3E-1 53-02-007 Rev. 4

3.

General ArrangementReactorBuilding Plan Floor Elevation 51'-3" Dwg. No. 3E-153-02-003 Rev. 6

4.

Reactor Building Conduit Plan El. 5I'-3" Dwg. No. 3138

5.

RELAPS Analysis of Cleanup Line Break C-1302-153-5450-070 Rev. 1

6.

GOTHIC Version 5.Oe Date: 11/23/96 Time: 12:35 PM Size 1300616

7.

H&V Plans Reactor Building BR2169-3

4.0 ASSUMPTIONS

1.

The assumed break size will be that equivalent to a 1" diameter line. The selection of a relatively small pipe size ensures the evaluation considers the minimum detectable line failure. The failure of a larger pipe will result in a more easily detectable temperature response. Therefore, for detection purposes the small break size bounds a large break. The 1" diameter size is also selected to be consistent with the current accident analysis documented in Amendment 75 to the FDSAR (section 4.1.1), which states the following.

Type of Postulated Breaks

a.

Circumferential breaks in piping runs and branch runs exceeding 1-inch nominal pipe size

b.

Longitudinal brcaks in piping runs and branch runs 4-inch nominal pipe size and larger Since minimizing the break flow is conservative for this calculation the GOTHIC model will be developed for a line break that is 0.75" diameter. The size selected for calculation purposes is conservatively established less than 1" diameter.

Furthermore, this size will be applied to the entire length of pipe to the reactor adding additional conservatism. It will be demonstrated in the calculation that these size assumptions will conservatively bound any possible break location.

2.

The reactor pressure is assumed to be at normal operating conditions.

Pressure - 1035psia, Enthalpy - 52SBTU/lb, Level = 162" TAF This assumption is consistent with previous current high energy line break evaluations of the cleanup system documented in reference S.

3.

The evaluation is done with and without room ventilation. Reference 7 shows that there is room ventilation that will influence the flow of fluid within the area of the break. To ensure that the design is correctly evaluated it is important to evaluate both of these scenarios.

4.

The break detection temperature is assumed to be 180rF. This value is selected to be consistent with the current Emergency Operating Procedures (EOPs).

5.

The slabs and walls used in this calculation are arbitrarily assumed to be 6" thick. This is acceptable since the duration of this evaluation is very short (2 minutes). Therefore, the heat will not penetrate more than a few inches.

This will be confrmed in the calculation.

04/18/06 10:00:09 (GPU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Calc. No.

Evaluation C-1 302-215-E610-060 Rev. No.

Sheet No.

7 of 6.0 DESIGN INPUT:

5.1 All design-input information is obtained from drawings listed in references I through 4 and 7. The figure that is provided below illustrates reactor building information used to size the volumes used in the calculation (references I to 4).

v-W3 J

W4 I*-

H2 1-1 Bt At AB I

H3 1I B-B T

HiIf JA A-A Where WI - 12.473ft, W2 = 4.595R, W3 = 21.664ft, W4 = 10.&32ft LI = 28.557R, L2 - 31347ft, L3 - 19.695ft Hi = 20.35 IfR. H2

= 20.023ft, 13 - 9.84711 5.2 The cleanup line information is obtained from reference 5 figure 2. The length is sufficient as descnbed in assumption 1.

5.3 The ventilation information is obtained from reference 7.

04/18/06 10:00:09 (GPU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Cslc. No.

Evaluation C-1302-21 5-E610-060

_Rcv. No.

Sheet No.

I S of I_ o I

6.0 CALCULATION

The following sections document the calculations used to provide inputs to the GOTHIC computer code as well as the results of the computer analysis.

6.1 GOTHIC Input Calculations The free volume is calculated for each of the rooms as follows.

VHjMI -(WI-LI-W2-L2)-H1 VHpX.m-IOlO.799e 3 PMrr -(W3-W4) L3.H2-W4.L3H13 VpMm= 63723274e 4-H1 -WI (HI - WI )

4HI* W2 2-(HI

W2Ž)

2 DH HXrm DHI X1tm = 11.482

-ft 4 113 13 DH mnn

=

D Vpi 2-(H3 - L3)

DH PMnn - 13.13 oft The hydraulic diameter is calculated for the sub-nodes in the model as well.

04/18/06 10:00:09 GU NUCLEAR LI

-I-I I

I I I I

I I

J I-L I

I I

T L2 At J A I

_ii

'WI 1 W2 I Plan View Of Heat Exchanger Room 1<

WI 1I W2k A-A Heat Exchanger Room Elevation View

04/18/06 10:00:09 CGPU NUCLEAR 14 W3 AL3 BL 1

_____,_r M I.=

-~I r -----

I I_

JB Pump Room Plan View 1<

W3

-I eW4 H2 I

4 H1 H3 7i B-B Pump Room Elevation View

04/f 1

0:A0n09 10: 00:09 (GPU NUCLEAR Ll L2

04/18/06 10:00:09 CPU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Caic-No.

Evaluation C-1302-21 5-E610-060

[Rev. No.

Sheet No.

1 12 of I Hydraulic Diameters in the LI Direction 4-WI,H1 DHL1M I -

3 2: j

\\3 21 DHLI HxI = 11.80j7ft 4 W1 HI DHLI~m~--3

(/WI Hl\\

\\ 3 2/

DHLI HX3 = 11.80Rt DHLIHX5 =DHLIHUI 4,WI HI DH HX2 --

3 2

\\ 3 'i DHLI },2 = 40.7021ft 4 W2 DHL1HX 4 =

2 W2 -Hi DHLI HX4 = 7.49-ft DHLI HX 6

- DHL1 HX2 DHLI.5

= 11.80711 DHLI HX6 a 40.7021ft

-04/18/06 10:00:09 (GP NUCLEAR Subject Cleaup System B DHLI 2

(W2-HI)

DHLIHX7 DHLIHX3 DHLILHX 7 = 11.807ft DHL1 H 9 = DHL1HX1 DHLIHCg= 11.907ft DHL1 HXI I =DHLI MOC DHLI HXI1 I1 I1.807fl DHLIHX13 =DHL 1HXI DHLIHX13= 11-807fl DHLIHXl 5 DHLIHX 3 DHLIHX1 5= 11f807ft DHLI HX8 = 7.498Rft DHLIHXI0 =DHLIHX2 DHLI HXI0 = 40.70211 DHLIHXI 2 - DHL1 X4 DHLIHX1 2 7-498f DHLI HX14 - DHLI HX DHLI HX1 4 - 40.702fl DLIHX16 - DHL1IHX4 DHLI HX1 6 = 7.49& ft

04/18/06 10:00:09 (CŽU NUCLEAR CALCULATION SHEET

Subject:

Cltanup System Break Detection Requirements Calc. No.

Evaluation C-l1302-21l5-E6 10-060 Rev No.

Sheet No.1 I

14 of Hydraulic Diameters in the L2 direction Li Hi 4.---.-

DHL2HXI 4

2L

-H D~i~pjj:LI HI I\\4 2/

DH12HX1 = 16.782 DHL23 -DHL2Hx 1 DH12.HX3 = 16.78241 Ll Hi DHL2X 4

2 LI 42 DHL2Hx 5 = 40.702i DHL2HX7 --DBU2HX5 DHL2HX7= 40.702Rf DHL2Hxp DHL2Hx 5 DHL2HX9 =40.702ft DHL2HXlp1 - DHL2H,,

DL2HXI I = 40.702t DHL2HX13 =DHL2HX1 DHL2HX1 3= 16.78T2h 4.LI Hl DHL2 H2 -

H2

\\4 2,

DHL2 1 i=

16.782-4 4-L2 Hi DHL2 4

4 2 1.2 4

DHL2 HX,4 = 40.7021 DHL2HX6 - DHL2HX5 DHL2 H 6 = 40.70Th DHL2Hxg DHL2HX4 DHL2HX =40.702t DHL2HX 0 -DHL2p-1 5 DHL2HX1 0z 40.702t DHL2H 1 2 - DHL2HX4 DHL2HX1 2= 40.702t DHL2HX1 4 :DHIL2HX1 DHL2HX1 4= 16.782R

04/18/06 10:00:09 GU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Calc. No.

Evaluation C-1302-215-E610-060 Rcv. No.

Sheet No.

j 15 of Door from channel 15 to 16 L215_16 '6-Length L21 5 1= 1-969 DHL2 15 - DHL2 1 4 DHL2Hx I5 a 16.782Ift The vertical direction also contains a hydraulic diameter LI WI' 4-DHVHXI l

4 DHV I = I0 S1'ft

'4 3

4Ll WI DHVHX2 =

,4

'3 DHVHpi= 2L.557it

\\3 /

/LI WlO 4.--

\\,%4 3 I' DHVHX LI W I DHV 3= 10.5 1>

\\4 3 !

4-W2 DHVH4

/

L' DHVHx4 =9.l9Ift 4;

LI WI 4-DHVHXS =4 3_

Li 4

DHVHm = 16.63 tft DHVHX6 =10ft DHVHX7

- DHVHX5 DHVHX7 = 16.63tft

04/18/06 10:00:09 GU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Calc. No.

Evaluation C-1302-215-E610-060 Rev. No.

Sheet No.

l 16 of

[2 4---*W2 D4V 4

2 L2 4

DHVHX9 - DHVHX5 DHVHXIO -DHVHX6 DHVHX 1 -DHVH 7

DHVHX] 2 =DHVHX8 DHVHX13 rDHVHXI DHVHX1 4 --DHVWU WI Li 4-....-.

3 4 DHVHD15

- I-Li 4 W2-L2 4

DHVHX1 6 11.5-1;2-W2 DHVHf>g8 9.191ft DHV"Xg= 16.631ft DHVHI 1 O= 100ft DHVHxV I = 16.63?fR DHVHX1 2= 9.191-f DHVHX13= 10.51 f DHVHX1 4= 28.55T7 DHVHX1 5= 33.262ft DHVHX 16= 2.791ft

04/18/06 0 10:00:09 GU NUCLEAR CALCULATION SHEET Subjecti Cleanup System Break Detection Requirements CaIc. No.

Evaluation t-1302-215-E610060 Rev. No.

Sheet No.

jI 17 of Pump Room To Remainder of the reactor building - Junction Information L3H1-3 2

4-13-1-3 H3 = 96.97-ft

= 13.13aft W3 = 21.664ft 2

2-(L3* H3)

Heat Exchanger Room To Pump room junction information 4W2H1 W2H=46.76P'ft 2

W2 H_=4_

= 7.4983ft W2-Hi The inertial Length between the volumes Is calculated as follows 12_ W3 r 8420f 4

Cleanup Line is a 6 OD pipe OD =6in ID OA.8fl Ares =X-a 4

Area = 0.181

.1. 11. 1.4 i 10:00:09 CGPU NUCLEAR CALCULATION SHEET Subject; Cleanup System Break Detection Requirements Calc. No.

Evaluation C-1302-21 5-E610-060 Rev No.

Sheet No.

I v 18 of Heat Conductor Information Heat Exchanger Room There are 32 heat conductors included in the model. One is provided for each of the sub volumes in the heat exchanger roorm. These represent the floor ceiling and wails of the room. The heat conductors are numbered I through 16 for the corresponding channels on the first elevation, and 17 through 32 on the second elevation. Each is assumed to be 6" of concrete with an insulated outter boundary condition. The significance of this boundary condition assumption will be evaluated with the calculational results.

HCl iH 'WI Ll, LI WI 2

3 4i 4

3 HCI = 144.63"2 HC2 -Hl1W1 _ LlWI 2

3 4

3 HC2-71.991-ft2 HC3 -HCI HC3= 144.638ft2 L2 L2 Hi HC4 = L2 W2 2-.

2 4

4 2

HI Ll LI WI HCS =

2 4 4 3 HC6 LI WI 4

3 LI WI LI HI HC7 =Z..

4 3

4 2 HC8=L-W2-2-L2H 4

4 2 HC9 HCS HCl0 HC6 HCI I HC7 HC4 = 195.50211 HC5= 102.33ft2 HC6= 29.681ft2 HC7= 102.33ft2 1iCs-195.502fi2 HC9= 102.33ft2 HCI0= 29.684112 HCl I= 102.33f112 HCl2 -HC8 HCl2 195.5020

t4i l

8/0 9

10:00:09 (GP NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Calc. No.

Evaluation C-1302-215-E610-060 Rev. No.

Sheet No.

19 of 1 HC13 -HCI HC14 = HC2 HC15 =HCII L215 16 2 HC16 =HC12-L21 I Hi HC13u 144.638f!2 HC14-71.99?e 2 HCIS 82.291t2 HC16-175.462ft2 Heat Conductor Information Pump Room There are 10 heat conductors included in the model. One is provided for each of the sub volumes in the pump room. These represent the floor ceiling and walls of the room. The heat conductors are numbered I through 6 for the corresponding channels on the first elevation, and 7 through 10 on the second elevation. Each is assumed to be 6" of concrete with an insulated outter boundary condition. The significance of this boundary condition assumption will be evaluated with the calcutational results.

HCPI W3 - W4 11-12 L3, H2 L3 2

i2 2J 2 2 HCP2 W3-W4..H2 W3' 2

2 2I HCP3 - W4' tlH3-L3.

.k 21 HCP4 - HCP I HCPI= 206.14202 HCP2= 107.556ft2 HCP3= 320.001112 HCP4-206.142ft2 HCP5 = HCP2 HCPS-107.55602 HCP6 - W4 !2-W'

\\

2; HCP6-213.334ft2 HCP7 =HCPI HCP7-206.142f 2 HCP8 = HCP2 _

2.3 2 2 HCP9 = HCP4 HCP8= 206.142 e HCP9-206.142fl2 HCPIO =HCP8 HCPIO= 206.142fe2

04/18/06 10:00:09 CGMU NUCLEAR W3 = 21.664fk W4 = 10.832ft H2 = 20.02f H3 = 9.84?ft L3 = 19.693fi Vertical Channel Parameters Al pup~-.

LW-W; Al 53.33ft pumproom 2

pumproom HD]

=o

_ purmproom HDI 13.977?ft puprom W

4 pwnproom 2

2 1

L3 W3--W4\\

533f 2

23 '

2 2

pumproom HD2 4-A2 pumproo9n pumproom I W3 - W41 HD2pumproom = 39.3ni 2;

L3

/3

=166f 2

A3punproom = y(W4)

A3pumproom 106.66 Ifl3pumo 4 A3 pumproorn

=39389 H3puniproom (W4)

H3pumproom'339f

-- 04/18/06 i 10:00:09 NUC NU(:LEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Calc. No.

Evaluation C-1302-21S-E6 10-060 Rev. No.

Sheet No.

1 21 of The lower elevation of the pump room has the followkV volume Information. The area of channels 1,2,4 and 5 ar as follows.

W3-W4 L3 Area 2 5 - -

2 Arc 2a = 53.333,12 The area of channels 3 & 6 are as foIlows AreA 2,1 -W4.L32 Area 2,1 = 106.667ft2 The hydraulic diameters in the vertical direction are calculated as follows. Note that the values In the channels 3 and 6 are not irportant since there Is no low in that direction since the cells are null on the second elevation. The hydraulic diameters in level 2 of channels 2 and 5 are different from that of level 1.

4-Alma 25 HI~ertcal2, W3

-A..

a

W3-W4' L3 2

2

~verica22, '-Arca H~ verd al225 W 3 - W 4~

2; 4-AMa 2s1 HhveftiEU3 2 5 HDvcrtica4, HDvctica 2

HDvetic5 2 5 - HDvcrtic&122,

HDvcrdcalI 2 = 13.977ft HDvericar22s = 39389R HDveticyd3 2 5 = 39.39Rft HDvcftical425 = 13.977 ft KDverticalS2,= 39.389ft MDvertica6 2 lOoft Level 2 channel 2 and 5 hydraulIc diameters are calculated as follows.

Mvenica!1222,-

HMvertical I 2s HDverica222 13.977fl HDverticaI522, - HDvctical42s Mvdtca52%

- 13.977Rt

04/18/06 10:00:09 (7PU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Caic. No.

Evaluation C-1302-215-E610-060 Rev. No.

Sheet No.

j 22 of The horizontal and hydraulic diameter dimensions used to represent the pump room cells Is as follows For channels 1.2,4 & 5 the foliowing is used W3 - W4 Ll 1 2s 5

2 L212 L3 12s LI 12s= 5.416-R L2 12s = 9.847,ft For Channel I and 4 elevation 1 and 2 the horizontal hydraulic diameter in the LI and L2 direction is 4W3-W4 H2'.

HDL11 42 s -- i 2

2/

1H2 W3-W4 2

2 L3 1H2 4---

HDL2142s L3 122 23_ H2 2

2 HDL11 42 s= 14.059ft HDL2 14 2s= 19.857f*

For Channel 2 and 5 elevation I the horizontal diameter in the LI and L2 direction is HDLIE125 2 s W3 - W4 H2 4.._

2 2

!W3-W4'.

2 'i HDLI E12 52, = 40.046 ft HDL2El 2 52, H2 L3 112 L3 2

2 HDL2E12 52s = 19.S57*ft For the elevation 2 the L2 value of the hydraulic diameter is the same. However, the Li value is somewhat different and is calculated as follows.

W3-W4 H2 HDL1E2252 3..2 2

2 W3 -- W4\\ H2 2

1' 2

HDLIE22 52s 14.059"f

04/18/06 10:00:09 GU NUCLEAR

Subject:

Cleanup System I Evaluation For channels 3 & 6 the following is used LI 32s W4 L232s 3

2 Ll 32s = 10.832ft L232s = 9.847ft 4.W4 H3 HDLI3 6 2 s = I W4 i3 2-W4 L3 HDL23 6 2s 2

L3 2

11DLI 3 62s= 19.692ft HDL2 3 62s= 13.13ft The GOTHIC code is used to estimate the full line break flow. The frictional and Inertial information of the piping associated with the cleanup line break is obtained from the RELAP5 calculation (reference 5). The following is that information.

frictional length - I ft - 11.25fc - 6.75Sf - 4ft - 2 fl ft - 3 ft - 4.75 ft - 9.75Sfl i 2.5 ft frictional length=49 fl inrtial length - frictional Icngth pipe = 1.0- O.5S 0.9 2-03 3 t 6.0.2 1+ 0.9 0.33 K pipe =5.55

.11AI.K 10:00:09 (GPU NUCLEAR CALCULATION SHEET Subjed: Cleanup System Break Detection Requirements Cak. No.

Rev. No.

Sheet No.

Evaluation C-1302-215-E610-060 24 of In assumption 4 it is stated that the pipe line size selected Is selected to provide a conservative result. Conservative in this evaluation Is to minimize the break flow rate into the reactor building. Minimizing the break flow will chalenge the detection capabiiity of the modification. With tis in mind. the 0.75 diameter assumption for the entire length the Clearup line modeled is sufliciently conservabve that it Is not necessary to provide a detailed representation of the actual pipe length ior a specific break location. The following portion of the calculation will demonstrate this assumption to be va8id.

Assumptions are made that allow the comparison of the low through a 6' diameter line and the 0.75' diameter lne used h the model. Note that the term actul is used to represent the system and assumed is used la represent how it was modeled.

The Inside diameters used hr comparison purposes are as ollows.

ID, tuai 5.76l-in IDsummcd =0.7Sin The corresponding flow areas are calculated as folows.

2 ax2 2

FA 1

am

IDgcka FA asmd~

]~

4 4

FA MW - 0. I&I-e FA ssume

= 0-003ft2 The head loss relationship used In the comparison Is as follows.

AP =1P.K.V2 2

K f L D

For the sake of making a comparison assume that the mass flow rate is I Osec for the assumed condition.

m - 10 b-sec If the velocity for the assumed and actual conditions are calculated it can be seen that the assumed velocity is approidmately 60 times greater than that which would flow thrugh the actual line length. From he pressure drop relationship It Is easily deduced that the relative pressure drops will be substantially dkfferencL f3 m-Yfrsat(525).-

v -- tuaa tualb f3 M-VffSat( 525)-'

assumed V A umed Vactual-1.163*-..

30C assumei.

59ft V,,md-68.593'-. -

JIM Vassumned2 v--.-,2

04/18/06 10:00:09 (Gm, NUCLEAR

Subject:

Cleanup System I Evaluation The next step Is to estimate the pressure drop along the modeled line (for the assuned flow rate) and determine the required loss coefficient associated with the actual system to produce an equivalent tow. Note that the system Is choked at tO break location and the phenomena is not modeled hI this evaluation since the pressure drop model used here is only interested hI e flow through the line (ie., what Is the pressure and the choke point). It wil be shown tfat to obtain the same low pressue at the choke point the losses in the 6" diameter pipe would need to be quite large.

f assune 0.024 K'fi a ~ssu

~4-05

49.11 2

.. assumed '

K foriiasumcdi.Vnn

- 551.72*4 in 2.g-vfrsat(525).

lb fasmumed _49.R

_ K-frm~ assumed = 22-866 assumed The Ioss coefficent to obtain the equivalent response would need to be as follows.

fMl

=0 015 K9-ft 2,

assumed'

(K f 0m p

)ed asue

-- etuivalem-Vactu K equivalent, 79604.322 ff tt Is assumed ta the form loss is the same (it is not ) an estimate of the length required can be obtained as follows.

Lequivmallet

- 'Kequivalent - K formisumedj ur

_sudlfactual Lequi" lnt 5 2.548lo( *fl This vahie Is oertaihly extreme and should be viewed as the approximate comparison that Is and not as anything more. However. it Wustrates the conservatism associated with assuming that the entire length of pipe is 0.75" in diameter. Thus assumption 4 Is In fact conservative and the length selection can be made quite liberally as is done hi this calculation.

nan ntig 10:OO:09 10:00:09 OGPU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements alc. No.

Rev. No.

Sheet No.

Evaluation C-1302-21S-E61060 26 of The boundary condition pressure is based upon the system pressure and the elevation of the break.

P - 1035psi Elbrk -66&ft 5 i.

TAF - 39fR - 9*in -- 353 -

..in I

16; TAF = 69.193-fi RPV1vi - TAF - 160 in RPV1v1 = 82.526'ft 3'-

ft~

Pb =P- (RPVv1-Elbrk), vfPsat( 1035) l g

PbC = 1040.2"4psi The smallest break to be detected in the evaluation is that equivalent to a 0.75" diameter instrument line.

Brdia 0.75 -in Brarca =x -Brdia 2 4

Brarca = 0.003 -ft2 6.2 GOTHIC ANALYTICAL RESULTS The GOTHIC analysis is performed in two parts the first assumes that the building ventilation system is not operational.

The room response for this case is illustrated in figures I to 15. As can be seen from the results provided in figure 5, the setpoint is reached in approximately 60 seconds. With a valve stroke time of 60 seconds the break would be detected and isolated in approximately 2 minutes. Figure 8 shows that the slab and wall thickness (assumption 5) is acceptable since the heat does not affect more than 2" of the sab or wall. It is judged that walls and slabs exceed 2" in thickness.

For the second case (figures 16 to 30) the time to reach the setpoint is shorted by the ventilation in the pump room.

This can be seen in figure 21. Note that figure 23 demonstrates the validity of assumption 5 with ventilation operational.

04/18/06 10:00:09 GU NUCLEAR CALCULATION SHEET Siujt: Cleanup System BWek lciection Requirenwnts Calc. No.

Evaluation C-l1302-21 5-E6 10-060 Rcv. No.

Sheet No.

l 26 of I

Appendix I GOTHIC Output Figures

04/18/06 10:00:09

(ŽPU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Calc. No.

Evaluation C-1302-215-E610-060 Rev. No.

Sheet No' 1

27 of Case I No Ventilation

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:49:38 1997

-GOTHIC Version 5.0(QA)-e -

October 1996 1

Heat Exchanger Roon Tenperatures TULs1 TUls2 TUVs3 TUVs17 TULs L1

-n (91 N

v S.

zLS Fe

.w

~-----------s"_

S

-?....

4 1

7 1 X _...

F.....

2 35 Mai+n

_*ti

/

X=Break Location u4 In N

'*1 lo I 20 48 60 88 100 120 TiHe (sec)

GOTHIC 5.0(QIA)-e l2Xol4,'97 l9:26:25

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:49:39 1997

GOTHIC Version 5.0(QA)-e - October 1996 2

Heat Exchanger Roon Tehperatures TUls5 TUIsG TUIls7 TUls2l TUls22 6.............................

t-Y64 -------

l-M l.22.

WI%

Tisne (sec)>

COTHIC 5.OCQA)-e 12104,'97 l9:26:25

'4/18/06 6 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:49:40 1997

-GOTHIC Version 5.0(QA)-e - October 1996 a

Heat Sink Tenp Prof S TP2t600 TPUt688 0

N _

I50sec TP3t688 TP4t6B8 TP 14 Relative Distance GOTHIC 5.e(QA)-e 12/04/97 19:26:25

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:49:41 1997

.GOTHIC Version 5.0(QA)-e - October 1996 g3 Break Flow Rate FD4 op 04 W

2a

~Ik I

I I 111 I t4 I II ml a t I I IShl S11 I

I 51a551#

I I

I SI IS MI I

I I u1N

-I 0.e010e.eL e.1 1

is 1IS 186 Tinue (sec)>

GOTHIC 5.0CQA)-e )1204/97 19:26:25

'04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 3 2 Thu Dec 04 20:49:42 1997

.GOTHIC Version 5.O(QA)-e - October 1996 La HX Roaun Hallway Tenperatures TUls2S TULI24 TU1s28 TULs32 C.

EL:

.0 CO I4 1W S.

S.

61 K

S Ii4 C

'4

,~~

V a

f '/

.16£

J.,...

j Ii,

.. W.......

0t4 2

a I M

(12 I

I 28 40 6s 80 Le0 120 Tine Csec)

GOTHIC 5.0(QA)-e 12/04,97 19:26:25

04/18/06 i 10:00:09 Cleanup Line Break in the Heat Exchanger Room 33 Thu Dec 04 20:49:43 1997

.GOTHIC Version 5.0(QA)-e - October 1996 ii HX Root Hallway Temperatures ruJLs16 TUls12 TULSO TUIs4

£A~.._..................................... A

-I4 Time (sec)

GOTHIC 5.SCQAI-e 12jA4,'q7 19 v2r; !2

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:49:44 1997

.GOTHIC Version S.0(QA)-e - October 1996 34 12 114 I

.v S.

z FeS.

o4 PuMp RoozM Temps TU2s1 TU2s2 Elevation I TU2s3 F,M M

120 Tine (sec)

GOTHIC 5.0CQA)-e 12/84/97 19:26:25

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:49:45 1997

.GOTHIC Version 5.O(QA)-e - October 1996 13 Pump Rooa Teseps Etevation I TU2s4 TV2s5 TU2s6 l

.........,............. +...

..........................R

s.

i4 IF1F1RD 14 S-I 141 1

8 28 48 60 Tine Csec)

GOTHIC 5..0(QA)-e 12/04/97 193:26:25

04/18/06 10:00:09' Cleanup Line Break in the Heat Exchanger Room 34 Thu Dec 04 20:49:46 1997

-GOTHIC Version 5.0O(QA)-e - October 1996 14 W

01k S

9.

IC S

S v6 L

IV X.

Punp RoOa Terps TU2s7 TU2s8 co

._4.

GD

_I Elevation 2 TU2sIS TU2sI a _

<1 Tinie Csec)

GOTHIC 5.SCQA)-e 12/04/97 19:26:25

'04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 3 7 Thu Dec 04 20:49:47 1997 GOTHIC Version 5.0(QA)-e - October 1996 j L Heat Exchanger Rooa Elevation I i

S.

aI Urzax = LeaCft/s )

Scaltng Power = 0.25 Tine = 121.583

/

Volune

Channels

Le we ls /

/

1:

1:-16 : 1-1 /

idGOTH IC 5.. B QIc, -t7e LPf44mC9:2.:2Z5,

1

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 38 Thu Dec 04 20:49:46 1997

.GOTHIC Version 5.0(QA)-e -

October 1996 Heat Exchanger Roon Elevation 2 no a

unax = lrCf t/s )

Scaling Power = e.25 Tine = 121.583

/

Uolune

Channels : Le vels /

/

1:

1-16:

2-2 /

"GOTHIC 5.0CQA)-e M4o?

Is:26:25 I

^

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 3i Thu Dec 04 20:49:49 1997

GOTHIC Version 5.0(QA)-e - October 1996 Pump Roon Elevation 1.

i S.

V UnAx = 10 Cft/s )

Scaling Pouer = 0.25 Tine = l21.583

/

Uolune

Channels : Levels /

/

2

1-6 : 1-1 /

GOTHIC 5. eCQA ) -e 1N,44/ "X9:26:25 4

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:49:50 1997

GOTHIC Version 5.0(QA)-e - October 1996 Pursp Roon Elevation 2 i

I Null Cell 4

5 K

\\Null Cell i

A

S.

Unax = l C f t/s

)

Scaling Power = e6.25 Tine = 121.583

/

Volune : Channels

Levets /

/ 2 :

14-G: 2-2 /

GOTHIC 5_. 0(Q)-X I.V,44 "9

26:25 urn

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:49:52 1997

-GOTHIC Version 5.0(QA)-e - October 1996 j L PiFp Roon Elevation Utew i

S.a V

Unax = 10 Cft/s) -

Scaling Power = 0.25 Tine = 121.583

/

Uolgurne

Channels : Levels /

2 1-3:

1-2 /

GOTHIC S.8 CQA)-e 1064,4"JI :26:25 1.

I.-

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:49:53 1997

-GOTHIC Version 5.0(QA)-e -

October 1996 42 Punp Roon Elevation Uiew i

Unax = la Cft/s)C:

Scaling Power = 8.25 Tite = 121.583

/

Uoluune

Channels

Levels /

/ 2 : 4-6 : 1-2 /

leGOTHIC 5..Q)-,

i-

,-I.-

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 4 3 Thu Dec 04 20:49:54 1997

-GOTHIC Version 5.0(QA)-e -

October 1996 I.

Heat Exchanger RoOM Halluas Elevation Uiew i

S.

Unax = 10 Cft/s 3 Scaling Power = e8.25 Tine = 121.583

/

Uolune : Channels

Levels /

/

1 : 4-16 : 1-2 /

COTHIC 5-.BCQA)-e 1W4/ 'P'<9:26:25 I

04/18/06 10:00:09

(ŽGPU NUCLEAR CALCULATION SHEET Subjct: Cleanup System BTcak Detection Requirements Ca1ic. No.

Evaluation C-1302-215-E610-060 IRev. No.

Sheet No.

44of Case 2 Ventilation Functional

04118/06 10-00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

.Thu Dec 04 22:02:35 1997 GOTHIC Version 5.0(QA)-e - October 1996 1

Heat Exchanger TUlsI TULs2 Roon Temperatures TUls3 TU~s 17 TUls 18 nN

&W S.I.

'4 S

is I

-. ilX=reak Location SIn W4 20 48 6s 8s lee 128 Tine (sec)

GOTHIC 5.SCQA)-e 12/04497 21:51:27

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

.Thu Dec 04 22:02:36 1997 GOTHIC Version 5.0(QA)-e -

October 1996 2

Heat Exchanger TULs5 TULs6 Roon Temperatures TUis7 TULs21 TUls22 Iti LI A.

9

£ F4

.4 ID

.4 1,

NWI a0 _

to_

Tine (sec)

GOTHIC 5.8(QA30-e 12/04/97 21:51:27

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

Thu Dec 04 22:02:37 1997 GOTHIC Version 5.0(QA)-e -

October 1996 do 8

Heat Sink Tenp Prof TP2t6DB TPlt688 N _

e 150sec TP3t68 TP4t688 TP VI.

09 IV 5.4 Relative Distance GOTHIC 5.i&QA)-e L2/04/97 21:51:27

04/18/06 10?00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

-Thu Dec 04 22:02:38 1997 GOTHIC Version 5.O(QA)-e - October 1996 9

Break Flow rD4 AL Rate

£ 2

C iW GOTH IC N'4 a.

8108 Tiume (sec) 5.OCQA)-e 12/04/97 21:51:27

04/18106 10:00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

Thu Dec 04 22:02:39 1997 GOTHIC Version 5.O(QA)-e - October 1996 10 HX Roon Hallwag Tenperatures TUls2S TUIs24 TUls28 6

TUVs32 w I m

C p4 S.s V

H~

V At a

!S i:

~~~....

4 It

.2 8....4..

I

1 V

.4 9a II.

I I

28 40 6G 8e 126 Tine (sec)

GOTHIC 5.0CQA)-e 12/04/97 21:51:27

-04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room so Ventilation is Available

.Thu Dec 04 22:02:40 1997 GOTHIC Version 5.0(QA)-e - October 1996 Il HX Roon Halluau Tenperatures TUls16 TUls12 TUis8 TU1s4 co I..............

.44 I,.~

l*

~--------W----8

'4*

Tine Csec)o GOTHIC 5.OCQA)-e L2/04/97 21:51:27

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room-St Ventilation is Available

-Thu Dec 04 22:02:41 1997 GOTHIC Version 5.0(QA)-e -

October 1996 12 1unp Ron Tenps TU2sV TU252 Pn Elevation I TU2s3 m I IN 9P I.

U 0.

Ii ft.

, C Ct rC

:J

-J C

C C

I X

0 tIn WWI M

m9 W4 CC

.' t I

I I

1 2

3 RB I.....1..

1 20 48 68 80 Lee 120 Tine esec)

GOTHIC 5.0CQA)o-e 12/04/97 21:51:27

04/18/06 10:00?09 Cleanup Line Break in the Heat Exchanger Room 52 Ventilation is Available

Thu Dec 04 22:02:42 1997 GOTHIC Version 5.0(QA)-e - October 1996 13 Punp Roon Tenips Elevation I TU2s4 TU2s5 TV2s6 X,

~~

VWI N

lk rv go

.... j 5..

O In of in

.4 4

5 RB 6

__.==....

J

+/-

i 120 28 40 60 80 lee Tiine (sec)

GOTHIC 5.SCQA)-e 12/04/97 21:51:27

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 53 Ventilation is Available

-Thu Dec 04 22:02:43 1997 GOTHIC Version 5.0(QA)-e - October 1996 14 Punp Roon Teunps Elevation 2 Tr2s7 TU2s8 TU2siS TU2s11 CD

.I 7

8 ut

-............. I eI *I a

I 8

I I

e Ii 4

so Be lee 12 Tine (sec)

GOTHIC 5.e<QA)-e lZ/04/97 Z1:51:Z7

04/18106 10:00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

Thu Dec 04 22:02:44 1997 GOTHIC Version 5.0(QA)-e - October 1996 54 I

Heat Exchanger Room Elevation I A3 3

\\

A

__I1 13!

LI 1 6 i

a.

Unaix = 1rtls)

Scaling Power = 0.25 Tine = 121.991 Voluae : Channels

Levels /

/ O1:

1-16: 1-5

/

-GOTH IC 5,. 0 QA)e LNY4F41N 5i:51: 27 I.r

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

Thu Dec 04 22:02:46 1997 GOTHIC Version 5.O(QA)-e - October 1996 Heat Exchanger Roan Elevation 2 I

3

/

I 5

7 1i 12ii 4 7 i

Unax = RP0< i t /s )

Scaling Power = 0.25 Tine = 121.991

/

Voluae : Channels : Levels /

/

L : 1-16 : 2-2 /

dGOTHIC 5-.(QA)-e 1NY&IN 19i: 51: 2?

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room SCo Ventilation is Available

Thu Dec 04 22:02:47 1997 GOTHIC Version 5.O(QA)-e - October 1996 Pump Roon Elevation 1 I4 L

3 i

a.

Go 4

1 UnaWx

= la cft/si Scating Power = 0.25 Tine = 12L.991

/

Uolune

Clhannels

.,/ 2 1-6 :

1-1 /

Levels /

'GOTHIC 5.OCQA)-e 11,6/"g1:51

Z7

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room

$ 7 Ventilation is Available

.Thu Dec 04 22:02:48 1997 GOTHIC Version 5.0(QA)-e -

October 1996 i

Punp Roon Elevatton 2 i

gJ Unax = l0 Cft/pS) P Scalting Pouer = 0.25 TiUne = 121.991

/

Volmune: Channels : Level s,

/ 2 : 1-6 : 2-2 /

i GOTHIC 5 8Q e 1A) 41 9:5.:i 4 b

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

.Thu Dec 04 22:02:49 1997 GOTHIC Version 5.0(QA)-e -

October 1996 Ss Pui Roon Elevation Utew I

Nut I Cel I 1

2 3

V

-11r-Unax 1_ Cft/s)

C Scaling Power = 0.25 Tine = 121.991

/

Uolune : Channels : Levels /

/ 2 : 1-3:

1-2 /

14 GOTHIC 5OCQA)-e 1;24411L:sL:27 1h L..

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

.Thu Dec 04 22:02:50 1997 GOTHIC Version 5.0(QA)-e -

October 1996 5S PU 4 Roon Elevation Uiew 4

Ce I I 4V 6

.S.

V UMax = La (f t st )

o Scaling Power = 0.25 Tine = 121.991

,/ tolurne : Channels

Levels /

/

2 : 4-6:

1-2 /

.4GOTHIC 5,.OCQA)-e 1 m 4_/

"R41'j:5L;27 1

04/18/06 10:00:09

/D

(,O

L Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

.Thu Dec 04 22:02:51 1997 GOTHIC Version 5.O(QA)-e - October 1996 Heat Exchanger Roon Hallsw&s Ele vation Uiew I

i-0 I.

L4 Unax = 18e (f t S Scaltng Power = 0.25 Tine = 121.991

/

Volurne

Channels

Levels /

/

1 : 4-L6 : 1-2 /

GOTHIC 5.0CQA)-e 1INT4/84"P1:51:27 1

-V

04/18/06 10:00:09 Appendix 11 GOTHIC Input Deck

04/18/06 10:00:09 Case I No Ventlation

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 21:34:13 1997

-GOTHIC Version 5.O(QA)-e - October 1996

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room (4

Thu Dec 04 20;50:04 1997 GOTHIC Version 5.O(QA)-e -

October 1996 Control Volumes Vol Vol Elev Ht Hyd. D.

L/V IA Burn Description (ft3)

(ft)

(ft2)

Opt Is Heat Exchanger 10181.

51.25 20.35 11.5 DEFAULT NONE 2s Pump Room 6372.33 51.25 20.35 13.2 DEFAULT NONE 3D Volumes -

Volume is Nominal Values -

Vertical Chan.

Area Ver. Flow Hyd. D.

Loss De-ent. Vari.

(ft2)

Ar. (ft2)

(ft)

Coeff.

Factor Table 1

29.682 29.682 10.51

0.

NO 2

29.682 29.682 28.557

0.

NO 3

29.682 29.682 10.51

0.

NO 4

36.01 36.01 9.19

0.

NO 5

29.682 29.682 16.631

0.

NO 6

29.682 29.682 100.

0.

NO 7

29.682 29.682 16.631

0.

NO 8

36.01 36.01 9.191

0.

NO 9

29.682 29.682 16.631

0.

NO 10 29.682 29.682 100.

0.

NO 11 29.682 29.682 16.631

0.

NO 12 36.01 36.01 9.191

0.

NO 13 29.682 29.682 10.51

0.

NO 14 29.682 29.682 28.557

0.

NO 15 29.682 29.682 33.262

0.

NO 16 36.01 36.01 2.791

0.

NO 3D Volumes - Volume Is Nominal Values -

Horizontal Chan.

Width Hyd. D Loss Dent. Vari.

Dir.

(ft)

Coeff. Factor Table 1 Li 4.1577 11.807

0.

NO 1 L2 7.1393 16.782

0.

NO 2 Li 4.1577 40.702

0.

NO 2

L2 7.1393 16.782

0.

NO 3

LI 4.1577 11.807

0.

YES 3 L2 7.1393 16.782

0.

0. YES 4 Li 4.595 7.498

0.

NO

04/18/06 10:00:09 (6S 3D Volumes -

Volume Is Nominal Values - Horizontal Chan.

Width Hyd.

D Loss Dent. Vari.

Dir.

(ft)

Coeff. Factor Table 4

L2 7.8368 40.702

0.

NO 5

Li 4.1577 11.807

0.

NO 5

L2 7.1393 40.702

0.

NO 6

Li 4.1577 40.702

0.

NO 6

L2 7.1393 40.702

0.

NO 7

LI 4.1577 11.807

0.

YES 7

L2 7.1393 40.702

0.

YES 8

Li 4.595 7.498

0.

NO 8

L2 7.8368 40.702

0.

NO 9

LI 4.1577 11.807

0.

NO 9

L2 7.1393 40.702

0.

NO 10 Li 4.1577 40.702

0.

NO 10 L2 7.1393 40.702

0.

NO 11 Li 4.1577 11.807

0.

YES 11 L2 7.1393 40.702

0.

YES 12 Li 4.595 7.498

0.

NO 12 L2 7.8368 40.702

0.

NO 13 LI 4.1577 11.807

0.

NO 13 L2 7.1393 16.782

0.

NO 14 Li 4.1577 40.702

0.

NO 14 L2 7.1393 16.782

0.

NO 15 Li 4.1577 11.807

0.

NO 15 L2 1.969 16.782 1.5

0.

NO 16 Li 4.595 7.498

0.

NO 16 L2 7.8368 3.591

0.

NO

n 4/18A/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e - October 1996 3D Volumes -

Volume is Vertical Noding Bottom Height Level El. (ft)

(ft) 1 51.25 9.6353 2

61.0853 10.5147 3D Volumes -

Volume Is Horizontal Variation -

Channel 3 Width Hyd. D Loss Dent.

Level Dir.

(ft)

Coeff. Factor 1 L1

0. 11.807

0.

1 L2

0. 16.782

0.

2 Li

0. 11.807

0.

2 L2

0. 16.782

0.

3D Volumes - Volume Is Horizontal Variation -

Channel 7 Width Hyd. D Loss Dent.

Level Dir.

(ft)

Coeff. Factor 1

LI 4.1577 11.607

0.

1 L2

0. 40.702

0.

2 Li 4.1577 11.807

0.

2 L2

0. 40.702

0.

3D Volumes - Volume is Horizontal Variation - Channel 11 Width Hyd. D Loss Dent.

Level Dir.

(ft)

Coeff. Factor 1

Li 4.1577 11.807

0.

0 L2 O. 40.702

0.

2 Li 4.1577 11.807

0.

2 L2

0. 40.702

0.

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room

'7 Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e - October 1996 3D Volumes -

Volume 2s Nominal Values -

Vertical Chan.

Area Ver. Flow Hyd. D. Loss De-ent. Vari.

(ft2)

Ar.

(ft2)

(ft)

Coeff.

Factor Table 1

53.333 53.333 13.977

0.

NO 2

53.333 53.333 39.389

0.

0. YES 3 106.667 106.667 39.389

0.

0. YES 4

53.333 53.333 13.977

0.

NO 5

53.333 53.333 39.389

0.

0. YES 6 106.667 106.667 100.

0.

0. YES 3D Volumes -

Volume 2s Nominal Values -

Horizontal Chan.

Width Hyd. D Loss Dent. Vari.

Dir.

(ft)

Coeff. Factor Table 1 Li 5.416 14.059

0.

NO 1 L2 9.847 19.857

0.

NO 2 Li 5.416 40.046

0.

NO 2 L2 9.847 19.857

0.

NO 3 Li 10.832 19.695

0.

NO 3 L2 9.847 13.13

0.

NO 4 Li 5.416 14.059

0.

NO 4 L2 9.847 19.857

0.

NO 5 Ll 5.416 40.046

0.

NO 5 L2 9.847 19.857

0.

NO 6 Li 10.832 19.695

0.

NO 6 L2 9.847 13.13

0.

NO 3D Volumes -

Volume 2s Vertical Noding Bottom Height Level El. (ft)

(ft) 1 51.25 9.8353 2

61.0853. 10.5147

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 0

Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e - October 1996 3D Volumes -

Volume 2s Vertical Variation -

Channel 2 Area Ver. Flow Hyd. D. Loss De-ent.

Level (ft2)

Ar. (ft2)

(ft)

Coeff.

Factor 1

53.333 53.3331 39.3891 0.l 0.

2' 53.333 53.333 13.9771

0.

3D Volumes -

Volume 2s Vertical Variation -

Channel 3 Area Ver. Flow Hyd. D. Loss De-ent.

Level (ft2)

Ar. (ft2)

(ft)

Coeff.

Factor 1

106.667l 106.6671 39389

o.

°-

3D Volumes -

Volume 2s Vertical Variation -

Channel 5 Area Ver. Flow Hyd. D. Loss De-ent.

Level (ft2)

Ar. (ft2)

(ft)

Coeff.

Factor 1

53.333 53.333 39.389

0.

2 53.333 53.333 13.977

0.

3D Volumes -

Volume 2s Vertical Variation -

Channel 6 Area Ver. Flow Hyd. D. Loss De-ent.

Level (ft2)

Ar. (ft2)

(ft)

Coeff.

Factor 1I 106.6671 106.6671 39.389!

0 0.

2t

°.

0.

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e - October 1996

&i Turbulence Parameters Liquid Vapor Liquid Vapor Vol Molec Turb. Mix.L.

Mix.L Pr/Sc Pr/Sc Phase I

Diff. Model (ft)

(ft)

No.

Option isl NO NO

1.

1. VAPOR 2s NO NO

1.

1. VAPOR Turbulence Sources Vol Kinetic Energy Dissipation

Type Phase (ft2/s2)[*lbm/s] FF lft2/s3)[*lbm/s] FF I

I I

T Il Fluid Boundary Conditions - Table 1 Press.

Temp.

Flow ON OFF BC#

Description (psia) FF (F)

FF (lbm/s) FF Trip Trip IP RB/ATM B0.

2P Break Boundary 1

t-E525.

0. 0 3P RB/ATM 95.

1',1,t Et~nx Fluid Boundary Conditions - Table 2 Liq. V Stm.

Drop D Cpld Flow Heat Outlet 3C#

Prac. FF P.R.

FF (in)

FF BC# Frac. FF (Btu/s) FF Quality FF

.p

1.

NONE DEFAULT 2P

1.

0.0047 DEFAULT 3P

1.

NONE DEFAULT Tke t 1h-vorS

'-fe (Cf(Qce

,A;louA cta8t 4 k resAXt jke,,eAve)

VLe t~tCU10 v-e^&r,,

ct P

S

e~4F

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 70 Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e -

October 1996 Fluid Boundary Conditions - Table 3 Gas Pressure Ratios Air BC# Gas 1 FF Gas 2 FF Gas 3 FF Gas 4 FF 12i~

1.

1

[22 32 1.

Fluid Boundary Conditions -

Table 4 Gas Pressure Ratios BC# Gas S FF Gas 6 FF Gas 7 FF Gas 8 FF

'P 22 32 Flow Paths -

Table 1 F.P.

Vol Elev Ht Vol Elev St Description A

(ft)

B (ft)

(ft) 1 Opening To RB 2s6 51.25

9.

1P 51.25 9.

2 Opening Between 1s4 51.25 4.5 2s6 51.25 4.5 3 Opening Between 1s4 55.5 4.5 2s6 55.5 4.5 4

Break Junction 1s19

62.

0.48 2P

62.

0.48 5 Upper Open To R 2s3 51.25

9.

3P 51.25 9.

Flow Paths -

Table 2 Flow Flow Hyd.

Inertia Friction De-Mom Path Area Diam.

Length Length Entrmt Trn (ft2)

(ft)

Frac. Opt 1

96.97 13.13 21.664 21.664 2

46.761 7.498 8.842 8.842 3

46.761 7.498 8.842 8.842 4

0.003 0.0625

49.

5 96.97 13.131 21.664 21.6641

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room

'7l Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e -

October 1996 Flow Paths -

Table 3 Flow Fwd.

Rev.

Critical Exit Path Loss Loss Comp.

Flow Loss Coeff.

Coeff.

opt.

Model Coeff.

1 1.5 1.5 ON TABLES 0.0 2

1.

ON TABLES 0.0 3

1.

ON TABLES 0.0 4

5.55 5.55 ON HEM 1.0 5

1.5 1.5 ON TABLES 0.0 Thermal Conductors -

Table 1 Cond Vol HT Vol HT Cond S. A.

Init.

Description A

Co B

Co Type (ft2)

T.(F) Or 1 cond 1 isl 1

lsl 2

1 144.638

80.

I 2 cond 2 1s2 1

1s2 2

1 71.991

80.

I 3 cond 3 ls3 1

1s3 2

1 144.638

80.

I 4 cond 4 ls4 1

1s4 2

1 195.502

80.

I 5 cond 5 lsS 1

ls5 2

1 102.33

80.

1 6 cond 6.

ls6 1

ls6 2

1 29.684

80.

I 7 cond 7 1s7 1

187 2

1 102.33

80.

I 8

cond 8 ls8 1

Is8 2

1 195.502

80.

I 9 cond 9 1s9 1

1s9 2

1 102.33

80.

I 10 cond 10 ls10 1 lslO 2

1 29.684

80.

I 11 cond 11 1sll 1 isll 2

1 102.33

80.

I 12 cond 12 1s12 1 1s12 2

1 195.502

80.

I 13 cond 13 ls13 1 ls13 2

1 144.638

80.

I 14 cond 14 1s14 1 1s14 2

1 71.991

80.

I 15 cond 15 ls15 1 iS15 2

1 82.29

80.

I 16 cond 16 1s16 1 ls16 2

1 175.462

80.

I 17 cond 17 1sl7 1 ls17 2

1 144.638

80.

I 18 cond 18 Is18 1 1618 2

1 71.991

80.

I 19 cond 19 1819 1 119 2

1 144.638

80.

I 20 cond 20 1s20 1 ls20 2

1 195.502

80.

I 21 cond 21 ls21 1 ls21 2

1 102.33

80.

I 22 cond 22 ls22 1 ls22 2

1 29.684

80.

I 23 cond 23 1s23 1 ls23 2

1 102.33

80.

I 24 cond 24 1s24 1 ls24 2

1 195.502 B0.

I 25 cond 25 1s25 1 ls25 2

1 102.33

80.

I 26 cond 26 ls26 1 ls26 2

1 29.684

80.

I 27 cond 27 ls27 1 ls27 2

1 102.33

80.

I 28 cond 28 ls2B 1 1s28 2

1 195.502

80.

I 29 cond 29 1s29 1

ls29 2

1 144.638

80.

I

04/18/06 10:00:09 72 Thermal Conductors -

Table 1 Cond Vol HT Vol HT Cond S. A.

Init.

X Description A

Co B

Co Type (ft2)

T.(F) Or 30 cond 30 1s30 1

1s30 2

1 71.991

80.

I 31 cond 31 1s31 1 1s31 2

1 82.29

80.

I 32 cond 32 1s32 1 1s32 2

1 175.462

80.

I 33 cond 33 2s1 1

2s1 2

1 206.142

80.

I 34 cond 34 2s2 1

2s2 2

1 107.556

80.

I 35 cond 35 2s3 1

2s3 2

1 320.001

80.

I 36 cond 36 2s4 1

2s4 2

1 206.142

80.

I 37 cond 37 2s5 1

2s5 2

1 107.556

80.

I 38 cond 38 2s6 1

2s6 2

1 213.334

80.

I 39 cond 39 2s7 1

2s7 2

1 206.142

80.

I 40 cond 40 2s8 1

2s8 2

1 206.142

80.

I 41 cond 42 2s10 1 2s10 2

1 206.142

80.

I 42 cond 43 2s11 1

2s11 2

1 206.142

80.

I

04/19/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 73 Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e -

October 1996 Thermal Conductors -

Table 2 Cond Therm. Rad.

Emiss.

Therm. Rad.

Emiss.

Side A Side A Side B Side B 1

No 0.9 No 2

No 0.9 No 3

No 0.9 No 4

No 0.9 No 5

No 0.9 No 6

No 0.9 No 7

No 0.9 No 8

No 0.9 No 9

No 0.9 No 10 No 0.9 No 11 No 0.9 No 12 No 0.9 No 13 No 0.9 No 14 No 0.9 No 15 No 0.9 No 16 No 0.9 No 17 No 0.9 No 18 No 0.9 No 19 No 0.9 No 20 No 0.9 No 21 No 0.9 No 22 No 0.9 No 23 No 0.9 No 24 No 0.9 No 25 No 0.9 No 26 No 0.9 No 27 No 0.9 No 28 No 0.9 No 29 No 0.9 No 30 No 0.9 No 31 No 0.9 No 32 No 0.9 No 33 No No 34 No No 35 No No 36 No No

37.

No No 38 No No 39 No No 40 No No 41 No No 42 No No

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 74 Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e - October 1996 Heat Transfer Coefficient Types -

Table 1 Heat Cnd Sp Nat For Type Transfer Nominal Cnv Cnd Cnv Cnv Cnv Rad Option Value FF Opt Opt HTC Opt Opt Opt 1 Direct ADD MAX VERT SURF C*Re**n OFF 2 Sp Conv

0.

l OFF Heat Transfer Coefficient Types -

Table 2 Min Max Convect Condensa Type Phase Liq Liq Bulk T Bulk T Opt Fract Fract Model FF Model FF 1 VAP Tg-Tf Tb-Tw 2 VAP Tg-Tw Heat Transfer Coefficient Types - Table 3 Char.

Nat For Nom Minimum Type Length Coef Exp Coef Exp Vel Vel Conv HTC (ft)

FF FF FF FF (ft/s)

FF (B/h-f2-F) 1 2

3

-1.

2-HTC Types -

Table 4 Total Peak Initial Post-BD Type Heat Time Value Direct (Btu)

(sec) (B/h-f2-F)

FF I I I

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e -

October 1996

'75 Thermal Conductor Types Type Thick.

O.D.

Heat Heat Description Geom (in)

(in)

Regions (Btu/ft3-s)

FF 1 TWall WLL I 6.1 o.1 is

0.

I Thermal Conductor Type 1

Wall Mat.

Bdry.

Thick Sub-Heat Region (in)

(in) regs.-Factor 1

1

0. 1.2e-004 1

0.

2 1

1.2e-004 2.4e-004 1

0.

3 1

3.6e-004 4.8e-004 1

0.

4 1

8.4e-004 9.6e-004 1

0.

5 1

0.0018 0.00192 1

0.

6 1

0.00372 0.00384 1

0.

7 1

0.00756 0.00768 1

0.

8 1

0.01524 0.01536 1

0.

9 1

0.0306 0.03072 1

0.

10 1

0.06132 0.06144 1

0.

11 1

0.12276 0.12288 1

0.

12 1

0.24564 0.24576 1

0.

13 1

0.4914 0.49152 1

0.

14 1

0.98292 0.98304 1

0.

15 1

1.96596 2.01702 1

0.

16 1

3.98298 2.01702 1

0.

Materials Type #

Description 1

lconcrete

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 74i Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e - October 1996 Material Type 1

concrete Temp.

Density Cond.

Sp. Heat (F)

(lbm/ft3) (Btu/hr-ft-F) (Btu/lbm-F)

0.

140.

1.

0.2 1000.

140.

1.

0.2 Valves & Doors Flow Open Close Valve Valve Path Trip Trip Type Disch.

it Description I

Vol.

IV lBreak Location l 4 t 1 I l 1 1s19 Valve/Door Types Valve Stem Loss Flow Type valve Travel Coeff.

Area Option Curve Curve (ft2) 1 I QUICK OPENlI 0 [

0 l 0.003 Component Trips Trip Sense Sensor Sensor Var.

Set Delay Rset Cond Cond Var. 1 Loc. 2 Loc. Limit Point Time Trip Trip Type I I TIMEI I

IUPPERI 1.I 0. I I

I AND Functions FF#

Description Ind. Var.

Dep. Var. Points 0 Constant 0

1 Break Flow Ind. Var.

Dep. Var.

6 2 Nusselt I coef Ind. Var. Dep. Var.

3

04/l18/06 10:00:09 Functions FF#

Description Ind. Var.

Dep. Var. Points 3 TNUSselt # exp I Ind. Varl Dep. Var.

2

-04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 7 a Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e - October 1996 Function 1

Break Flow Ind. Var.:

Dep. Var.:

Ind. Var.

Dep. Var.

Ind. Var.

Dep. Var.

0.

1.

0.

2.

0.3 600.

0.3 660.

0.

1000000.

0.

Function 2

Nusselt # coef Ind. Var.:

Dep. Var.:

Ind. Var.

Dep. Var.

Ind. Var.

Dep. Var.

0.

0.664 500000.

0.664 100000000.

0.664 Function 3

Nusselt # exp Ind. Var.:

Dep. Var.:

Ind. Var.

Dep. Var.

Ind. Var.

Dep. Var.

.0.1 0.51100000000.1 0.5 Fourcej Corwec.ior, 14e&N TIr^.ske, It-ExterncAl Flou, (Flat Pttes I/

MU kG-;4P. "Apr^3 e~cludiolg S-7.

&c~Atr cj IveAn'tv-~c Fra4 k Krei+4 Wi14*

I e pRIach~

Volume Initial Conditions Vapor Liquid Relative Liquid Ice Ice Vol Pressure Temp.

Temp.

Humidity Volume Volume Surf.A.

(psia)

(F)

F (e)

Fractio Fract.

(ft2) def l 14.7 j eol.

80.1 60.1

o.

ol.1

'04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:50:04 1997 GOTHIC Version S.O(QA)-e - October 1996 Initial Gas Pressure Ratios Vol Air Gas l Gas 2 Gas 3 Gas 4 Gas S Gas 6 Gas 7 Gas 8 def I O 1.1 O.I 0.I o.I o

.I O0.

o.

Run Control Parameters (Seconds)

Time DT DT DT End Print Graph Max Dump Int Min Max Ratio Time Int Int CPU Int 1

le-004 0.25

1.

200.

50.

2. 10000.

0.

Run Parameters Menu Parameter Value Restart Time (sec) 0 Restart Time Step #

0 Restart Time Control NEW Revap. Fraction 0

Hetero. Nucleation?

YES Min. NC HT Coeff. (Btu/ft2-hr-F) 0 Reference Pressure (psia) 0 Forced Ent. Drop Dia. (ft) 0.00833 Vaper Phase Head Cor.?

NO Solution Method DIRECT Include Kinetic Energy?

NO Ice Condenser Parameters Initial Bulk Surface Area Heat Temp.

Density Multiplier Transfer (F)

(ibm/ft3)

Function Option 15.l 33.431 UCHIDA

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Thu Dec 04 20:50:04 1997 GOTHIC Version 5.0(QA)-e -

October 1996 Graphs Graph Curve Number Title Mon 1

2 3

4 5

1 Heat Exchanger TV1s1 TVls2 TVls3 TV1s17 TV1s18 2

Heat Exchanger TV1s5 TV1s6 TV1s7 TV1s21 TVls22 3

Heat Sink Temp TP2t600 TPlt600 TP3t6OO TP4t600 TP5t600 4

Break Flow Rate FD4 5

HX Room Hallway TVls20 TV1s24 TVls28 TVls32 6

HX Room Hallway TV1s16 TV1s12 TVls8 TV1s4 7

Pump Room Temps TV2sl TV2s2 TV2s3 8

Pump-Room Temps TV2s4 TV2s5 TV2s6 9

Pump Room Temps TV2s7 TV2s8 TV2s10 TV2sll 10 1 Wi l-1 11 lsVV17-12 2sVV1 -6 13 2sVV7-1 14 2sVV1-9 15 2sVV4-1 16 1sVV16-Noncondensing Gases Gas Description Symbol Type Mol.

Lennard-Jones Parameters No.

Weight Diameter e/K (Ang)

(K) 1 Air Air IPOLY1 28.971 3.6171 97.

Noncondensing Gases - Cp/Visc. Equations Gas Cp Equation (Required)

Visc. Equation (Optional)

No.

Tmin Tmax Cp Tmin Tmax Viscosity (R)

(R)

(Btu/lbm-R)

(R)

(lbm/ft-hr) 11 360.1 2280.10.238534-6.20061 1

1

04/18/06 10:00:09 NUCLEAR CALCULATM

Subject:

Cleanup System Break Detection Requirements I

Case 2 Ventilation Functional

AIA0 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Oct 31 22:57:16 1997 GOTHIC Version 5.O(QA)-e - October 1996

'd;i'A ve^4Id(Jon

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Ventilation is Available

.Thu Dec 04 22:04:19 1997 GOTHIC Version 5.O(QA)-e -

October 1996 Vol une Is Level 2 Top Ulew (RII I

I I

- -1ff--164-I I

I I

I i:F m1A -IS 115 I16 I

I I

t LI L L2 a-17.1 ft a

In I~

Elevation

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Oct 31 22:57:44 1997

GOTHIC Version 5.O(OA)-e - October 1996 Uolume 2s Level 2 Top Uiew o

T LII a

I DL2 2ZI.664 ft i________-___

a Elevation p

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Oct 31 22:57:52 1997 GOTHIC Version 5.O(QA)-e - October 1996 Fluid Boundary Conditions - Table 1 Press.

Temp.

Flow ON OFF BC#

Description (psia) FF (F)

FF (lbm/s) FF Trip Trip 1P RB/ATM 14.7 80.

2P Break Boundary 1061.

E525.

0.

0 3P RB/ATM 1.4.7 95.

4F Heat Exch Rm Ve 14.7

80.

v-50.-

SF Pump Room Vent 14.7

80.

v-78.7 6F Pump Room Vent 14.7

80.

v-78.7 I-.

'I

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Oct 31 22:57:55 1997 GOTHIC Version 5.0(QA)-e -

October 1996 Fluid Boundary Conditions -

Table 2 Liq. V Stm.

Drop D Cpld Flow Heat Outlet BC# Frac. FF P.R.

FF (in)

FF BC#

Frac. FF (Btu/s) FF Quality FF 1P

1.

NONE DEFAULT 2P

1.

0.0007 DEFAULT 3P

1.

NONE DEFAULT 4F

1.

NONE DEFAULT 5F

1.

NONE DEFAULT 6F I_1.

NONE DEFAULT

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 87 Fri Oct 31 22:57:58 1997 GOTHIC Version 5.O(QA)-e - October 1996 Fluid Boundary Conditions - Table 3 Gas Pressure Ratios Air BC# Gas 1 FF Gas 2 FF Gas 3 FF Gas 4 FF IF 1.

2P 31' 1.

4F 1.

SF 1.

6F 1.

04/18/06 10:00:09 8 8 Cleanup Line Break in the Heat Exchanger RoomB Fri Oct 31 22:57:47 1997 GOTHIC Version 5.O(QA)-e -

October 1996 Flow Paths -

Table 1 F.P.

Vol Elev Ht Vol Elev Ht Description A

(ft)

B (ft)

(ft) 1 Opening To RB 2s6 51.25

9.

1P 51.25 9.

2 Opening Between 1.4 51.2S 4.5 2s6 51.25 4.5 3 Opening Between 1s4 55.5 4.5 2s6 55.5 4.5 4 Break Junction 1819

62.

0.46 2P

62.

0.48 S Upper Open To R 283 51.25

9.

3P 51.25 9.

6 HX Room Vent 1s17 69.1

2.

4F 69.1 2.

7 Pump Room Vent 2.7 69.25

1.

5F 69.25 1.

8 Pump Room Vent 2s10 69.25

1.

6F 69.25 1.

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Oct 31 22:58:11 1997 GOTHIC Version 5.O(QA)-e - October 1996 Flow Paths -

Table 2 Flow Flow Hyd.

Inertia Friction De-Mom Path Area Diam.

Length Length Entrmt Trn (ft2)

(ft)

Frac. Opt 1

96.97 13.13 21.664 21.664 2

46.761 7.498 17.684 17.684 3

46.761 7.498 17.684 17.684 4

0.003 0.0062

49.

5 96.97 13.13 21.664 21.664 6

7.667

1.

8

8.

1.

04/18/06 10:00:09 1q0 Cleanup Line Break in the Heat Exchanger Room Fri Oct 31 22:58:15 1997 GOTHIC Version 5.O(QA)-e - October 1996 Flow Paths - Table 3 Flow Fwd.

Rev.

Critical Exit Path Loss Lose Comp.

Flow Loss Coeff.

Coeff.

Opt.

Model Coeff.

1 1.5 1.5 ON TABLES O.1&

2

1.

. ON TABLES I-,

o 3

1.

ON TABLES e4 e 4

5.55 5.55 ON HEM 1.0 5

1.5 1.5 ON TABLES Qua 10 6

OFF OFF 0.0 7

OFF OFF 0.0 8

OFF OFF 0.0 Ak 3a "e+

cts c~feea.-'S O.A pane (O

04/18/06 10:00:09 GU NUCLEAR CALCULATION SHEET

Subject:

Cleanup System Break Detection Requirements Caic. No.

Rev. No.

Sheet No.

Evaluation C-1302-215-E610-060 1

W of 9'

Appendix III Detection Time for Larger Break Sizes As part of this analysis the detection time for larger break sizes is evaluated. The model used is virtually identical with that documented in this calculation. The changes that have been made are to the break-input model. The GOTHIC input tables associated with the changes are included under each section. The valve in the failed line has been removed and the break boundary condition was changed from a pressure boundary condition to a flow boundary condition. These changes allow the break flow to be specified by the analyst Three cases are evaluated, the first (case 3) represents a conservative estimate of the break flow from a full line failure based on break flows calculated in reference 5. The second and third cases (cases 4 and 5) are representative of smaller than full line failure.

The results of the evaluation are documented in the figures provided for each break. As would be expected the large break quickly detected when compared with the small I" diameter break used for determining the detector actuation limit and location.

04/18/06 10:00:09 CM"U Case 3 Large Break - 850#/sec

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:16:53 1998 GOTHIC Version 5.O(QA)-e - October 1996 12 Pump RoOM Tenps ETe Vation I TU2sl TU252 TU2s3 e

_~

WI w

6J S.

S.

IV' r

/

X--

a a

CD M4

~0 W4 WI I

f I1

.I

/

..... f,.

I

'I 1 I 2

3 RD I

I......

I a

a I

I I

a 1T I

2 3

4 4

Tite (esc)

GOTHIC 5.BCQA)-e 02/06/98 14:48:24

10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:16:54 1998 GOTHIC Version 5.O(QA)-e - October 1996 13 W

V vI" 4

0 X1I.

I" PUnp Rooms Tenpps TU2s4 TU2s5 Elevation 1 TU2s6 Tine (sec)

GOTHIC 5 8 (QA)

-e 82/86/98 14 48 :24

0 /18A/

00 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:16:55 1998 GOTHIC Version 5.0(QA)-e -

October 1996 14 Punp RoOn Tenrs Elevation 2 TUZs7 TU2s8 TU2s18 TUs 11 ml I

th I.

10 0~

A 5.4

.4 at 7

8:

nutl l

L e l

o 0 1 ID 04e k

5 10 15 20 25 30 rine (Sec)

GOTHIC 5.B(QA)-e 02/06/98 14:48:24

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:16:47 1998 GOTHIC Version 5.0(QA)-e - October 1996 1

Heat Exchanger Roon Tenperatures TUIsI TU1s2 TU1s3 TUls17 TUlSl8 IU,

_4

[-

N viL I.

V A.K v

I" 117118 2

3 X=Dreak Location

.i

,,,,Ie

,t Imm,i,m i

,li ii, I v

I)

-4 IN

-I

'El I

5 le 15 28 25 38 Tine (sec)

GOTHIC 5.0(QA)-e 02/86/98 14:48:24

11 I..

10:00:09 17 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:16:48 1998 GOTHIC Version 5.0(QA)-e - October 1996 2

Heat Exchanger Rooi Tereperatures TUls5 TUls6 TUIs7 TUIs2I TUIs22 NN S.

'I S.

I..

U, Ir if N

-I

...............I

.2 2..

I WII a 6

12 18 24 30 Time (sec)

GOTHIC S.S(QA)-e 02/08698 14:48:24

04/18/06 10:00:09 78 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:16:49 1998 GOTHIC Version 5.0(QA)-e - October 1996 9

Break Fl ow Rate FD4 v

O C

I NX Ad OM.

Pd 11 ma I1 u mi as I

I I I m

mII I I

I I

H a

Im 5

10 15 20 25 30 Tine Csec)

GOTHIC 5.BCQA)-e 02e86/98 14:48:24

04/18/06 10:00:09 79 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:16:50 1998 GOTHIC Version 5.0(QA)-e - October 1996 la HX Roon Halluav Tenperatures TUls26 TUUs24 TUVs28 TU1s32 6w a_

I r

.1 61 I.

S.

v 96 E

A i*

6

- -I.

A.

32 28 24a 21 6

-4

=- I p4 6

12 18 24 30 Tine (sec)

GOTHIC 5.0(QA)-e 02ve6/98 14:48:24

04/18/06 10:00:09 106 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:16:51 1998 GOTHIC Version 5.0(QA)-e -

October 1996 Li HX Rooan Halluwag Teaperatures TUIsI6 TUlsIZ TUlsa T

a Vuls4 W.,

M 114 IiL X

N

'4 mo It 4 _

1L6 I

I I

I a I I a i.I I.

I a I I a i I

a I I I I I a 5

1i 15 20 30 Tine Csec)p GOTHIC 5.8(QA)-e 02/06/98 14:48:24

04/16/06 10:00:09 lot Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 14:47:23 1998 GOTHIC Version 5.0(QA)-e - October 1996

04118/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 02 Fri Feb 06 14:46:57 1998 GOTHIC Version 5.0(QA)-e -

October 1996 Fluid Boundary Conditions -

Table 1 Press.

Temp.

Flow ON OFF BC#

Description (psia) FF (F)

FF (lbm/s) FF Trip Trip IP RB/ATM 14.7 80.

2F Break Boundary 1061.

E525.

850 0

3P RB/ATM 14.7 95.

04/18/06 10:00:09 (03 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 14:47:06 1998 GOTHIC Version 5.0(QA)-e -

October 1996 Function I

Break Flow Ind. Var.:

Dep. Var.:

Ind. Var.

Dep. Var.

Ind. Var.

Dep. Var.

0.

1.

0.

2.

1.

600.

1.

660.

0.

1000000.

0.

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 14:47:28 1998 GOTHIC Version 5.O(QA)-e - October 1996 Valves & Doors Flow Open Close Valve Valve Path Trip Trip Type Disch.

Description Vol.

I I I I 1

I

04/18/06 10:00:09

[AS Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 14:47:58 1998 GOTHIC Version 5.0(QA)-e - October 1996 Run Control Parameters (Seconds)

Time DT DT DT End Print Graph Max Dump Int Min Max Ratio Time Int Int CPU Int 1 lle-0041 0.251 1.l 30.1 30.1 1.l10000.l 0.

-04/18/06 10:00:09 Case 4 Large Break - 450#/sec

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:38:48 1998 GOTHIC Version 5.0(QA)-e - October 1996 12 Punp Rooni Tenps Elevation 1 TU2s 1 TU2s2 TU2s3 INI m

S X...............

I L

2 3:

e*RD

.0 A

-4 Ti ne (sec)

GOTHIC 5.SCQA1)-e 02/06/98 15:22:11

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:38:49 1998 GOTHIC Version 5.0(QA)-e -

October 1996 13 Punp Roon Tenps TU2s4 TUZs5 2z L.

Elevation I TU2s6 IN I..

S.

A.

Tinie Csec)

GOTHIC 5.0(QA)-e 62/06/98 15:22:11

04/18/06 10:00:09 O09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:38:50 1998 GOTHIC Version 5.O{QA)-e -

October 1996 14 IVi U

I.

4 a.

I*4 Punp Roon Tenps TUZs7 TU2s8 4

Elevation 2 TUZsl0 TU2sll 0 [

04a_

Tine Cseca)

GOTHIC 5.SCQA)l-e 02/06/98 15:22:11

04/18/06 10:00:09 Ito Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:38:43 1998 GOTHIC Version 5.0(QA)-e -

October 1996 i

Heat Exchanger Roon Tenperatures TUlsl TUls2 TUls3 TU1s17 TUIsiS nNN I

S It S.

S%

C S

34 V.1 nU, U.'

we-

-D

................................................ ]....

A......................................

X=Dreak Location I

I Ils sl I

l

I I

I I

a a 1

a I

in N-I U.

a 5

1e 15 26 25 30 Tine (sec)

GOTHIC 5.S0CQA)-e 02/06/98 15:22:11

-04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:38;44 1998 GOTHIC Version 5.O(QA)-e -

October 1996 2

Heat Exchanger Roon Teunperatureis TUIs5 TULsS TUIs7 TUIs2l TULs22 n

IN SS I.

6,S.

o 61 S

UI In

-I An..........................................................

t.............................................................................

,,,...............................2

11

''I

'I '

3 6

12 18 24 38 Tine (sec)

GOTHIC 5.8CQA1-e 82/06/98 15:22:11

04/18/06 10:00:09 Ill7 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:38:45 1998 GOTHIC Version 5.0(QA)-e - October 1996 9

Break Flow Rate FD4 w.

in.

C 0

N tC 3

a II.

.I I I

I I

I II I

I II aa GOTHIC 0 1 0

ve I 5

le 15 20 25 30 Tine (sec) 5.0CQA)-e 02/06/98 15:22:11

04/18/06 10:00:09 113 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:38:46 1998 GOTHIC Version 5.0(QA)-e - October 1996 10 iHX RooM Hallwas Tenperatures rUis28 TU1s24 TU1s28 TU1s32 IC..

-(3 28 24:

P' 4

r J Tine (sec)

GOTHIC 5.0CQA)-e e2M86/98 15:22:11

04/18/06 10:00:09 114 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:38:47 1998 GOTHIC Version 5.0(QA)-e -

October 1996 11 HX Roon Hallway Tehperatures TUIsI6 TUIsl2 TUIs8 TUI%4 L W~-------

L

£0_

f...

....... --------- I----...

'44

.................. -- - -- - -,---4-_------

a e;

SA*

O aaA Time Csec)

GOTHIC 5.O(QA)-e 02/06/98 15:22:1L

04/18/06 10:00:09 luS Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:17:52 1998 GOTHIC Version 5.0(QA)-e -

October 1996 Fluid Boundary Conditions -

Table 1 Press.

Temp.

Flow ON OFF BC#

Description (psia) FF (F)

FF (lbm/s) FF Trip Trip IP RB/ATM 14.7 80.

2F Break Boundary 1061.

E525.

450 0

3P RB/ATM 14.7 95.

04/18/06 10:00:09 (GPU Case 6 Large Break - 142#/sec

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 117 Fri Feb 06 15:50:39 1998 GOTHIC Version 5.0(QA)-e - October 1996 12 Punp Roon Tenps TU2s 1 TU2s2 D

_~ _

Elevation I TU2s3 It0

'4 IN, SI.

9 S.

To CU 3.a S

_~~~~~

....................f..

I S

5 S

S.............

C4 N

I

'SI

.I I

I I

f......

l 2Z I

2 3

3 RD /

I W I l

10 28 38 Tine Csec)

GOTHIC 5.0(QA)-e 02486/98 15:41:51

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 118 Fri Feb 06 15:50:41 1998 GOTHIC Version 5.0(QA)-e - October 1996 13 Puntp Roon Tehsis TU2s4 TU2s5 XL Elevation 1 TU2s6 4S.

V V

H Tine (sec)>

GOTHIC 5.BCQA)-e 02/06/98 15:41:51

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:50:42 1998 GOTHIC Version 5.0(QA)-e - October 1996 14 Punp Roon Tenps Ele vation 2 TU2s7 TU2s8 7M2s 10 TU~sLL 0 t gm 7

a a

8

.l t

w 1

"4 w

L Off

£0 Pq C

S Af 1--a I

a.

....L...L..... L..... L.. L. L.. JI.L.... L L L i 1s 15 21 25 38 Tine (sec)

GOTHIC 5.OCQA)-e 02806/98 15:41:51

04/18/06 10:00:09 I o Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:50:34 1998 GOTHIC Version 5.O(QA)-e -

October 1996 I

Heat Exchanger TUI6s1 TUis2 A)

~

Rooh Tenperatures TU1s3 TUIsJ.7 TUIsLO wN9 rg gm a

S.

Fz Ob 4

S.

t S

11 17 18!X

.L..............................

l

~X=Break Locati on IC In "I

n)

M P4 5

la 15 28 38 Ttne Csec)

GOTHIC 5.6CQA),-

02/i8698 15:41:51

-04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:50:35 1998 GOTHIC Version 5.0(QA)-e - October 1996 2

Heat Exchanger Roon Tenperatures TUls5 TUis6 TUls7 TUrlsZl TULs22 I-.._...--.

M I.

S.

I' 14 H,

t-

'4

-I-.

H 4E4

W---........

- j I.,.I.

O I

6 12 18 24 38 Tine (sec)

GOTHIC 5.0CQA)-e 02/06/98 15:41:51

04/18/06 10:00:09 1Z2 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:50:36 1998 GOTHIC Version 5.0(QA)-e - October 1996 9

Break Flow Rate FD4 v o t'If S%D

'4 to 3C SN-I I

II a

I. I I I I

I I I 1.

I I

I I I t

I I

5 10 15 28 38 Tine (sec)

GOTHIC 5.OCQA)-e 02/86/98 15:41:51

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room Fri Feb 06 15:50:37 1998 GOTHIC Version 5.O(QA)-e -

October 1996 e0 HX Roon Halluwam Tenperatures TUls28 TIUs24 TUls28 TUls32

.t..

32.

24, 20 Tine (sec)

GOTHIC 5.0CQA)-e 02/06/98 15:41:51

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 124 Fri Feb 06 15:50:38 1998 GOTHIC Version 5.0{QA)-e -

October 1996 11 HX Roon Hallwag Tenperatures TUlsl6 TUlsl2 TUls8 TUls4 a,

S

~-~

e S

sA 1141

5 is 15 25 25 30 Tine (sec)

GOTHIC 5.(CQA)-e 02/06/98 15:41:51

04/18/06 10:00:09 Cleanup Line Break in the Heat Exchanger Room 125 Fri Feb 06 15:23:29 1998 GOTHIC Version 5.0(QA)-e - October 1996 Fluid Boundary Conditions - Table 1 Press.

Temp.

Flow ON OFF BC#

Description (psia) FF (F)

FF (lbm/s) FF Trip Trip 1P RB/ATM 14.7 80.

2F Break Boundary 1061.

E525.

142 0

3P RB/ATM 14.7 95.

04/18/06 10:00:09 CG U NUCLEAR VERIFICATION PLAN)

SUMMARY

SHEET (EP.006)

Sheet 126 of 127 C-1302-215-E610-060 R.I I-I Scope of Verfication Review the calculation.

Item No.

MethodtDepth of Verification Required Reqd Compl. Date Review the problem statement, input, assumptions, calculations and results to verify they are 03)27/1998 correct, reasonable, and they address the stated problem.

Assigned Verification Engineer FP Kenny Oualified per 4.4.1.3 b E Yes 0 Waived Justification for Waiver g

Sesction Manager SM)(sign)

Dat ev tg> LIs Summary of vedffication scope, methods, results and conclusions.

A review of Cleanup System Break Detection Requirements Evaluation', Calculation C-1302-215-E610-060 Rev.1 has been completed. The assumptions were found to be valid and the input was checked against the references an found to be correct AM the calculated input parameters were checked by hand calculations and found to be correct The input tables to the GOTHIC model were checked and found to be correct The GOTHIC modeling approach wa determined to be appropriate for this analysis. The results appear to be reasonable and consistent, and satisfy th stated objective.

It is concluded that the use of the break boundary pressure of 1061 vs. the calculated value of 1040 psi has a negligibl Inpact on this problem. Cases 3,4and 5 are constant flow boundary conditions, so this pressure difference will no affect the low, and cases 1 and 2 have a demonstrated conservative resistance.

The slight difference in the blowdown drop diameter used and the recommended value has a negligible impact sinc the droplet agglomeration/breakup model in Version 5.Oe of Gothic is relatively insensitive to the user-specified dro diameter.

The discharge coefficient of 0 for the junctions 1.2,3 and 5 has no inpact since flow does not choke i these junctions. These conclusions were verified by a sample run.

Based on this evaluation, the calculation is verified to be acceptable.

VerificationEngineew(pnt)

FP Kenny (sgn)I Ao#/?

Date 3 D7e Use addItional sheets If necessary

(./

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04/18/06 10:00:09 QPU CALCULATION VERIFICATION CHECKLIST Sheet) 7 f

(G itUCLEAR ITt EP-0061 C-C k. Titb Calc. No.

Rev.

Verificatbo by: P nt Name)

Section Date Place a check mart hi the applicable box (Yes, No, NWA) for each tern.

'NO' nay Indicate the design or verification Is Incomplete requirg a task requen be assigned by the responsie Section Manager.

The Section Manager halt review each 'NO' rponse to detamdne If Task Requst needs to be prepared.

INIA' (ot Applicablel does not requfre any further ecdon by the Verification Enginer.

The Verification Summary (V) (Exti 7A) may b. used to outline the Verification Enineer's work or for comments deened wvroprlot by the Verifiation Engineer.

13Ims Review Check Yes No N/A Design Input & Data - Were the inputs correctly selected, referenced (latest revision) and incorporated into the calculation?

Assumptions - Are assumptions necessary to perform the calculation adequately described and reasonable?

Regulatory Requirements - Are the applicable codes and standards and regulatory requirements, including issue and addenda, properly identified and ue their requirements met?

/

Consuuction/Opemting Experience - Has applicable construction and operating experience been considered? 7 Interfaces - Have the design interface requirements been satisfied?

7 Methods - Was an oppropriate calculation method used?

V_

Outnwi - Is the output reasonable conpared to Inputs?

Acceptance Critea - Are the acceptance criteria Incorporated In the calculation sufficient to allow verification that the design requirements have been satisfactorily accomplished?

Radiation Exposure - Has the calculation properly considered radiation exposure to the public and plant personnel?

v Comments:

N5830 17197)

v t e Letter Sequence Response to RAI
TAC:MC6046, (Approved, Closed)
Initiation Request Acceptance... Administration Questions 18 October 2005 1 February 2006 9 March 2006 20 March 2006 Answers 21 April 2006 Results Approval Other: ML062370475
MONTHYEAR2006-03-09 [Table View]

ML061230203

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