GO2-04-170, Calculation, Secondary Containment Drawdown
| ML042930802 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/30/2004 |
| From: | Maley D Energy Northwest |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| GO2-04-170 NE-02-01-05, Rev 1 | |
| Download: ML042930802 (337) | |
Text
{{#Wiki_filter:BDC/PDC Page X ENERGY CALCULATION PDC 2406
/NORTHWEST People -Vision -Solutions ORIGI NAL COVER SHEET Equipment Piece No. Project Page Cont'd on Page Columbia 1.0 1.1 Discipline Calculation No.
Secondary Containment NE.02-01-05 Nuclear Quality Class 39.0 Standby Gas Treatment System i Remarks TITLE/SUBJECT/PURPOSE Tite/Subject Secondary Containment Drawdown Purpose The purpose of this calculation is to determine the time required to reach 0.25" W.G. Vacuum ("drawdown") in secondary containment during post-Loss Of Coolant Accident (LOCA) conditions with a Loss Of Offsite Power (LOOP) under the design weather conditions using a single train of Standby. Gas Treatment System (SGTS). CALCULATION REVISION RECORD REV STATUS/ REVISION DESCRIPTION INITIATING TRANSMITTAL NO. F,P, OR S DOCUMENTS NO. 0 F Initial Issue PER 297-1003 ItfCfCA ltt'sIzq-C1^,< -Moa f PERFORMANCE/VERIFICATION RECORD REV VERIFIED BYIDATE NO. PERFORMED BY/DATE APPROVED BYIDATE 0 D. Maley/ 00 4 LS 6/ k h /'k-/2-1 Study Calculations shall be used only for the purpose of evaluating alternate design options or assisting the engineer in performing assessments. 409CAR Or
"" ENERGY Page No. Cont'd on page (People 2 )NORTHWEST
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Calculation Index 1.1 - Verification Checklist for Calculations and CMR's 1.2 - Calculation Reference List 1.3 - 1.301 Calculation Output Interface Documents Revision Index 1.4 - Calculation Output Summary 2.0 - 2.1 Calculation Method 3.0 - 3.4 Sketches 4.0 - 4.1 Manual Calculation 5.0 - APPENDICES: Appendix A Pages Appendix B Pages Appendix C Pages Enercon Report WS129-PR-02 ri Appendix D 141 Pages - A t- rc A)' Enercon Cal NO. WS129-CALC-001 r2 Appendix E 660 Pages - /A -t )-'6 (P)s. I -150) Enercon Cal NO. WS129-CALC-002 rO Appendix IF 54 Pagesvr /9rr c' Sensitivity Evaluations & comments Appendix G 38 Pages. Attexckte.& /,*-o) 1,971. I -So> Vendor correspondence Appendix H 4 Pages (0m0 4rr6c Enercon Report WS129-PR-01 rO Appendix I 129 Pages(/vfr-fury WR77R PR
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~~ENERGY 1.2 1.3 A NORTHWEST People
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- Solutions VERIFICATION CHECKLIST1 Calculation No. NE-02-01-05 Revision No. 1 CalculationICMR NE-02-01-05 Revision I was verified using the following methods:
3 Checklist Below Z Alternate Calculation(s) Verifier Initials Checklist Item Clear statement of purpose of analysis .................................................................... Methodology is clearly stated, sufficiently detailed, and appropriate for the proposed application.......................................................................................... Does the analysis/calculation methodology (including criteria and assumptions) differ from that described in the Plant or ISFSI FSAR or NRC Safety Evaluation Report, or are the results of the analysis/calculation as described in the Plant or ISFSI FSAR or NRC Safety Evaluation Report affected? 0D Yes n1 No ............................................................................................ If Yes, ensure that the requirements of 10 CFR 50.59 and/or 10 CFR 72.48 have been processed in accordance with SWP-LIC-02.................................... Does the analysis/calculation result require revising any existing output interface - v document as identified in DES-4-1, Attachment 7.3? 0 Yes [i No ................................................................................................ If Yes, ensure that the appropriate actions are taken to revise the output - interface documents per DES-4-1, section 3.1.8 (i.e., document change is initiated in accordance with applicable procedures).......................................... Logical consistency of analysis ................................................................................
- Completeness of documenting references ........................................................
- Completeness of input .......................................................................................
- Accuracy of input data........................................................................................
- Consistency of input data with approved criteria ...............................................
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- Completeness in stating assumptions ...............................................................
- Validity of assumptions ......................................................................................
- Calculation sufficiently detailed ..........................................................................
- Arithmetical accuracy .........................................................................................
- Physical units specified and correctly used .......................................................
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- Reasonableness of output conclusion .............................................................. XNA Supervisor independency check (if acting as Verifier) .-----.-. --------.---.-.-.
- Did not specify analysis approach
- Did not rule out specific analysis options 4A
- Did not establish analysis inputs........................................................................
If a computer program was used:.............................................................................
- Is the program appropriate for the proposed application?
- Have the program error notices been reviewed to determine if they pose any limitations for this application?
- Is the program name, revision number, and date of run inscribed on the output?
- Is the program identified on the Calculation Method Form?
If so, is it listed in Chapter 10 of the Engineering Standards Manual? .............. Other elements considered: NE-02-03-10 GOTHIC software V&V record If separate Verifiers were used for validating these functions or a portion of these functions, each sign and initial below. Based on the foregoing, the Calculation/CMR is adequate for the purpose intended. Verifier Signature(s)/Date Verifier Initials LS Woosley( -2, A/ L~'
Ad' LPage No. Cont'd on page EERGY CALCULATION 1.3130 People
)NORTWESTREFERENCE
*VisIon* olutions Li, T Calculation No. NE-02-01-05 Prepared by I Date: D ay 0644 Verified by/Date:ftg ~ , Revision No. 0 ISSUE DATE/
NO AUTHOR EDITION OR TITLE DOCUMENT NO. REV. EWD for miscellaneous equipment 1 Energy Northwest S Division 1/Division A lighting quenching EWD-108E-013 EWD for miscellaneous equipment 2 Energy Northwest 6 Division 2/Division B lighting quenching EWD-108E-015 Setting range for the DG time delay E/1-02-94-1352 Energy Northwest 3 relays 4 Energy Northwest Setting range determination for SGT E/1-02-91 -1066 Energ Nortwestvoltage signal limiter IAI 5 Energy Northwest 0 SGT annubar flow meter correction NE-02-92-06 factors 6 Energy Northwest 1 Sizing of DG 1A/B water reservoir tanks ME-02-91-50 7 Energy Northwest 0 Setting range determination for E/1-02-91-1094 Instrument loop SW pressure switch I B 8 Energy Northwest 11 Standby service water operability OSP-SW/IST- _ _ __ _ _ __ __ _ ___ _ _ _ _ _ _ _ _ _ _ _Q 70 1 9 Energy Northwest 1 Calculation for SW motor operated C1 06-92-03.04 EneryNothwet I valve design basis review Setpoint & allowable value 10 Energy Northwest 0 determination for instrument loops SW E/1-02-91-1137 relay 62/P1IA, 62/PI1B, TDS/P1IA, and TDS/P1 B 1 Design specification for Division 300 DIVISION 300 _1 Energy Northwest Section 318A Reactor building SECTION 318A 12 Energy Northwest 4 Summary of equipment qualification TM-2019 environmental profiles Alternative radiological source terms for 13 NRC 0 Evaluating design basis accidents at R.G. 1.183 nuclear power plants 14 NRC 2 Standard review plan - secondary containment functional design 6.2.3 15 Energy Northwest N/A CCR form for GOTHIC 7.1 Installation 2003-0127 16 Energy Northwest 1 Secondary Containment Drawdown NE-02-94-19 I__ __ _ _ _ _ _ _ _ _ _ _ _ _ _ A nalysis I _ _ _ __ _ _ FM7R1R2
NOENERGY CALCULATION 1.301 1.4 K-'NORTHWEST REFERENCE LIST People -Vision - Solutions Calculation No. NE-02-01-05 Prepared by / Date: D. __ Verified by/Date: Sfa,,/ Revision No. I ISSUE DATE/ NO AUTHOR EDITION OR TITLE DOCUMENT NO. _ __ _ _ _ __ _ _ _ _ _ _R E V. Setpoint and Allowable Value 17 Energy Northwest 2 determination for Instrument loops SGT- E/1-02-92-1024 RLY-1TRIAl, SGT-RLY-lTRIA2, SGT-RLY-1 TR/B 1, SGT-RLY-1 TR/B2 Setpoint and Allowable Value 18 Energy Northwest 2 determination for Instrument loops SGT- E/1-02-92-1 026 RLY-2TR/Al, SGT-RLY-2TR/A2, SGT-RLY-2TR/B1, SGT-RLY-2TR/B2 19 Energy Northwest 4Instrument Master Data Sheets for 19NorhwetEerg 4SGT-TS-EHIAIAll, etc 20 Energy Northwest 0 SGT FAN INFO FROM BUFFALO 28-00,99 FORGE 21 Energy Northwest 0 SGT FAN MOTOR DATA 28-00,100
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-t t I 4 I -t i + t
ENERGY CALCULATION OUTPUT Page No. Cont'd on page CNORTHWEST INTERFACE DOCUMENT REVISION INDEX 1.4 2.0 Calculation No. NE-02-01-05 PeoplesVision*Solutions Prepared by A/a-te:MoKAy7-06-04 Verified by/DatT ~ 'r Revision No. 0 The below listed output interface calculations and/or documents are impacf d by the current revision of the subject calculation. The listed output interfaces require revision as a result of this calculation. The documents have been revised, or the revision deferred with Manager approval, as indicated below. CHANGED BY CHANGED DEFERRED DEPT. AFFECTED DOCUMENT NO. (e.g., BDC, SCN, CMR,Rev.) (e.g., RFTS, LETTER NO.) MANAGER* ME-02-92-43 PDC 2406 ME-02-99-20 PDC 2406
- Required for deferred changes only.
Page No. Contd on page ENERGY CALCULATION OUTPUT 2.021 NORTHWEST People.Vision'Soluti ns
SUMMARY
Calculation No. NE-02-01-05 Prepared by / Date: . Mare07-06-04 Verified by/Date: AX& 1Revision No. 0
'REV BAR.
Discussion of Results The Technical Specification 3.6.4.1.3 and 3.6.4.3 Bases assume a secondary containment drawdown time of twenty (20) minutes. The base case analysis demonstrating compliance with this requirement is contained in Appendix D. This analysis shows that the secondary containment will return to a negative pressure after 972 seconds (- 16 minutes) when the Fuel Pool Cooling system will not be manually re-aligned to the Standby Service Water system (SW) until 12 hours into the event. The secondary containment will be maintained within the required specifications for the analytical period. The 12 hour delay in the manual re-alignment of the SW system to the fuel pool cooling was selected as a point in the event that is beyond the minimum time for operator action during an accident, but is within the maximum re-start time for the drawdown analysis. Procedures are in place to require manual alignment of the SW system to the fuel pool cooling based on temperature requirements that would take place prior to this drawdown requirement. The calculations and analysis in Appendix D, E, and F have been reviewed and approved as separate vendor documents. All of these documents have been transmitted to files under DIC 1822.3. The design case analysis for this calculation is documented in Appendix D. The basic calculation method is documented in Appendix E. The following is a summary of the results of methods used in this calculation:
- The leakage model in the GOTHIC analysis verifies that the Secondary Containment leakage limit is met based on the volume of secondary containment, Reference 3.1 of Appendix E, leakage modeling techniques, Reference 1.24 of Appendix E, and the secondary containment leakage test data, Reference 1.20 of Appendix E. This leakage limit is 2430 cubic feet per minute. The model provides a conservative result with respect to the periodic secondary containment drawdown tests.
- The modifications to the basic GOTHIC model presented in Appendix E show the design case initial secondary containment conditions and use an extended evaluation period to demonstrate containment stability.
In Appendix D an analytical run was performed to test the case of operating the Secondary Containment with the initial differential pressure >0.0" WG. This condition was run to test the drawdown for a change in Technical Specification SR 3.6.4.1.1 limits. The input assumptions for this analysis are located in Appendix D. The GOTHIC model and calculations are located in Appendix E. This analysis is the design case analysis for the Secondary Containment Drawdown. This appendix D analysis is a QA approved document by Enercon and has been reviewed and approved by Energy Northwest under separate cover.
- Additional analytical runs were performed to benchmark the margin in the assumptions used in the GOTHIC model. The 70%/30% assumption of the split of the secondary containment leakage was verified to be a reasonable choice. Appendix G provides the details on the Independent Verification computer runs performed on the GOTHIC model. These runs verified that the model performs as required.
Conclusions:
The Secondary Containment Analysis will establish that the conditions of less than or equal to 0.25" WG Vacuum will be reached in 972 seconds (16.2 minutes). The required conditions will be maintained for the analytical period of 30 days.
Page No. Cont'd on page ()ENERGY CALCULATION OUTPUT 2.1 3.0 x&NORTHWEST
SUMMARY
People -Vision-iSolutions Calculation No. NE-02-01-05 Prepared by / DatAealey / 07-06-04 Verified by/Date: / Revision No. 0
>1 REV BAR.
Discussion of Results (cont.) The Secondary Containment Drawdown analysis results fully support the design assumptions. The drawdown in the analysis is within the allowed time assumed for the AST and includes margin that can be used to maintain that condition if future changes to the plant require additional analysis. The AST assumes that the Secondary Containment will be drawn down to equal or below -0.25 inches of Water Gauge in less than 20 minutes. Using the restoration of the SW cooling flow to the Fuel Pool cooling system at 12 hours the Standby Gas Treatment System will maintain the secondary containment at equal or below the -0.25 inches of Water Gauge for 720 hour duration of the analysis. The selection of the 12 hours for the restoration of cooling flow to the fuel pool was made to not require the operators to perform this action during the initial stages of the accident and still leave margin in the time until a limiting condition for this analysis required the flow. Due to the slow heat-up of the secondary containment and the attendant decrease in differential pressure (DIP), the analysis was run for a longer period to verify the fidelity of the GOTHIC model. The longer run verified that the conditions stabilize in the secondary containment in approximately 46 days, Appendix I, Page 14. The results are that the temperature and DIP stability are demonstrated to meet all requirements.
EPage No. Cont'd on page ENORTHWEST People Vision-Bolutions CALCULATION METHOD . . CalculationNo. NE-0241-05 Prepared by / Datet. IaleO07-06-04 Verified by/Date: A / 1 Revision No. 0 7 REV BAR. Analysis Method (Check appropriate boxes) al Manual (As required, document source of equations in Reference List) 3 Computer LI Main Frame l Personal El In-House Program El Computer Service Bureau Program a BCS n CDC LI PCC n OTHER s Verified Program: Code name/Revision GOTHIC Version 7.1 El Unverified Program: Approach/Methodology The implementation of this calculation at Energy Northwest, Columbia Generating Station requires prior NRC approval. No revised interfacing documents will be issued until the NRC approval process is completed. This calculation was performed using GOTHIC, Version 7.1 (QA), which is a thermal-hydraulics analysis tool. GOTHIC is under the Appendix B, Quality Control of the vendor (Numerical Applications, Inc.). GOTHIC, Version 7.1 is maintained as a verified internal production code in accordance with SWP-CSW-04, Indirect Nuclear Safety and Regulatory Software Quality Assurance, Reference 15. This drawdown calculation is an extension of the vendor calculation attached as Appendixes D, E and I. The conclusions, data and assumptions of the main body of the calculation need to be taken as part of the overall calculation along with the conclusions, data and assumptions in Appendixes D and E. Appendices E and I includes history of the model development. Appendix D contains the current results. This GOTHIC model was developed using the Energy Northwest GOTHIC program under the QA program of Enercon Services, INC. Energy Northwest verified the GOTHIC model and the case studies in this calculation were run using that model. Appendix F consists of the flow paths and loss coefficient inputs for the Reactor Building to be used as inputs to the secondary containment drawdown calculations. The results of Appendix F are used as inputs to Appendix E, results from E were used to develop Appendix I, and the result of I was used to create the license bases case Appendix D. The methodology of this calculation is discussed and developed in Appendix E. The basic method consists of the following:
- Develop the boundary conditions surrounding the Secondary Containment. The boundary conditions use the Certified Vendor Information for the CGS five percent and ninety five percent Wind Speed and Temperature Values, Appendix E, Reference 1.12. This data is used to develop the dynamic and static pressures on the leakage points for the Secondary Containment. The development of the data is shown using equations I through 3 in Appendix E, pages 21 through 27.
Page No. Cont'd on page NORTH WEST CALCULATION METHOD .1 3.2 PeoplaeVislon.Solutions , Calculation No. NE-02-01-05 Prepared by/ Date: . al' 06-044 Verified by/Date: Revision No. 0
/ REV BAR.
- Develop the initial input conditions of the Secondary Containment. The control pressure for secondary containment Standby Gas Treatment System (SGTS) and for each of the volumes modeled in the GOTHIC analysis is calculated. This value is calculated for both the 5 % and 95 % temperature conditions and is used to ensure that the required differential pressure is obtained in all location for all design conditions. The developments of these values are shown in Appendix E, pages 28 through 33,
- Develop the leakage model for the Secondary Containment from the surrounding environment. The leakage is based on the volume of secondary containment, Reference 3.1 of Appendix E, leakage modeling techniques, Reference 1.24 of Appendix E, and the secondary containment leakage test data, Reference 1.20 of Appendix E. The development of this data uses equations in Appendix E, pages 34 through 37.
- Develop the wind pressure coefficients and leakage flows. The boundary conditions and the leakage model discussed above are used to develop the wind pressure coefficients. The wind pressure coefficients are evaluated to provide the effect of the wind on the test data. The wind pressure and the leakage model are used to develop the leakage flow coefficients. This development is documented in Appendix E, pages 38 through 48.
- Develop the internal pressure values at the leakage points. The pressure at the internal side of the leakage points is determined to provide a bounding review of the pressure differential across the building walls. This data is developed in Appendix E, pages 49 and 50.
- Develop the leakage flow path input values. The leakage flow path areas and hydraulic diameters are developed for input into the GOTHIC model. These values are developed in Appendix E, pages 51 and 52.
- Develop the GOTHIC flow paths. The flow paths into, through, and out of the Secondary Containment are developed in Appendix F and shown in Appendix E pages 52 and 53. These flow paths are used in the GOTHIC model to model the air flow for drawdown.
- Develop the GOTHIC volume inputs and thermal inputs. Data is extracted from various references to compile the volume and thermal inputs for the GOTHIC model. See Appendix E, pages 54 through 93 for input data.
- Develop the thermal conductor boundary temperatures. The temperature profiles for the Wetwell and Drywell are developed from plant references. See Appendix E, pages 94 and 95.
- Develop GOTHIC heat transfer coefficients. The GOTHIC model heat transfer coefficients are developed on pages 96 through 98 of Appendix E.
- Develop heat loads and fan cooler unit data. The development of the heat input and the equation for the decay of the heat load after the LOOP are presented in Appendix E, pages 99 through 111.
- Develop the model for the Fuel Pool Heat Exchanger. The calculations for the model are developed in Appendix E, pages 112 through 114.
- Develop the model for the SGTS fan performance. The calculations for the SGTS fan performance to show the input path, flows, and output paths are developed in Appendix E, pages 115 through 124.
'215M RI
Page No. Cont'd on page ENORTHWEST People *Vision1* Gatutlns CALCULATION METHOD 3.2 3.3 Calculation No. NE-02-01-05 Prepared by / Date: 6t .616yo 07-06-04 Verified by/Date: 6 g/ 2 / Revision No. 0 REV BAR.
- Develop the modifications to the basic GOTHIC model presented in Appendix E to show the initial secondary containment pressure and the extended evaluation period to demonstrate containment stability in Appendix I.
InAppendix I an analytical run was performed to test the case of operating the Secondary Containment with the differential pressure 0.0" WG. This condition was run to test the drawdown for a change in Technical Specification SR 3.6.4.1.1 limits. However, it was determined that the SGT inlet heaters were not modeled correctly, and so that deficiency needed to be corrected.
- Develop the modifications to Appendix I to add the inlet heaters in SGT system. In Appendix D this analytical run was performed to test the case of operating the Secondary Containment with the differential pressure 0.0" WG. This condition was run to test the drawdown for a change in Technical Specification SR 3.6.4.1.1 limits. The input assumptions for this analysis are located in Appendix D. The GOTHIC model and calculations are located in Appendix E. This analysis is the design case for the Secondary Containment Drawdown Analysis.
The methodology of this analysis is consistent with the current methodology as discussed in Section 6.2.3.3.1.2 Calculation Approach of the FSAR. The use of the GOTHIC 7.1 model provides a current method of analysis of the thermal hydraulic conditions in Secondary Containment during a LOCA/LOOP.
.1.
ENERGY Page No. Cont'd on page ENEORTHWEST People. Visloni Solutions CALCULATION METHOD 3.3 3.4 Calculation No. NE-02-01-05 Prepared by I DateD ley 07-06-04 Verified by/Date: AW 0/Revision No. 0 6/ RE-V BAR. Assumptions The Assumptions for this calculation are listed In Appendix D and E. The discussion listed here Is additional clarifying information.
- 1. The Normal Emergency Lighting for the Reactor Building is energized at the start of the accident and is lost for 15 seconds during the time the Emergency Diesel Generators (EDG) start and re-power the buses.
References:
1, 2&3.
- 2. The Standby Gas Treatment System (SGTS) is assumed to operate at 4800 ACFM during the accident. This flow is based on the following for fan SGT-FN-IAl and applies to all fans:
- a. Initial position of the Vortex Damper SGT-AD-lAI will be fully open due to the low differential pressure between the Secondary Containment and the outside air.
- b. Following SGT fan start, the vortex damper will throttle as necessary to limit flow to the flow limiter SGT-LMTR-lAl value of 5378 ICFM and to maintain the differential pressure setpoint on SGT-DPlC-IAl. Reference 4.
- c. The 5378 ICFM is 434 ICFM below the analytical limit of 5812 ICFM. Reference 4.
- d. Applying the 434 ICFM uncertainty to the limiter setpoint as a reduction sets the flow at 4944 ICFM.
The rounding of the flow to 4800 ICFM is a conservative assumption.
- e. Additional margin is realized by using Actual CFM instead of ICFM with no correction for the sensor inaccuracy. Reference 5.
- 3. The Standby Service Water (SW) is assumed to be off at the initiation of the accident. The SW is assumed to be supplying full flow to the ECCS room coolers at 300 Seconds based on the following:
- a. At T= 15 Seconds the EDG is loaded and the SW start sequence is initiated. Reference 1.
- b. The timing sequence for the starting of the SW pumps is determined from Reference 10. This value is 108 seconds.
- c. Five seconds is allowed for the SW pump to develop the 52 PSIG discharge pressure required for SW-PS-lA/B to actuate. This is based on Appendix 3, Reference 6. This data shows that at 10 seconds after a SW pump start, flow of at least 300 GPM is indicated at SW-FIS-15 located at the discharge of the DG heat exchanger. Pressure switch, SW-PS-IA/B, is the control sensor for the pump discharge valve opening and is required to be actuated prior to the flow starting in the DG heat exchanger, thus the 5 second assumption is a conservative number. The 52 PSIG for SW-PS-lA/B is based on Reference 7.
- d. Stroke times for the SW valves are the Action Hi values as listed in Reference 8. This procedure is the timing value in Reference 9. The Action Hi values are those stroke times beyond which the valve shall be immediately declared inoperable. This value is currently 140 seconds.
NOTE: This value of 140 seconds is based on the trend test data and could be revised in the future. The time for SW-V-2A to be fully open and provide full SW flow includes 32 seconds margin to allow for any future changes in the Action Hi setpoint. This margin will also bound any setting variations in the control relays.
- e. The opening of the discharge valve is stopped at 20% for 48 seconds. The settings of the associated control relays, SW-RLY-V/2A3 & SW-RLY-V/2A4 and the B loop relays are based on field testing as discussed in page C-5 of Reference 10. As the Reference 10 states there is no allowable values on these relays.
Page No. Cont'd on page ENRY3.4 4.0 NORTHWEST People.Vislon*Solutions CALCULATION METHOD Calculation No. NE-02-01-05 Prepared by/ Date: D. a 07-406-4 Verified by/Date: I Re- sion No. 0 91.1 REV BAR.
- 4. The initial temperature of the reactor building is assumed to be an average of 750F. This temperature was derived by taking the day and night recordings of temperature in the Reactor Building from the Operator OPS2 rounds for January 5t 2004. These values were averaged to get an overall building temperature. This was the coldest day of the month with the local/regional outside temperatures in the range of 11 to 14 degrees below zero. This is well below the 5% value of 28 0F, Reference 1.12, Appendix E, used in the analysis.
- 5. The secondary containment drawdown analysis, Appendix E assumes that the SGT system will be operating within 120 seconds. This time is developed in References 17 and 18 of this calculation.
Page No. Cont'd on page ENERGY 4.0 4.1
)NORTHWEST People- Vislon* 6olutIons SKETCHES Calculation No. NE-02-01-05 Prepared by I Date: D. aIen 04 Verified by/Date: ;Vvlay Revision No. 0 (I/ REV BAR.
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)ENERGY SKETCHES 4.1 5.0
\YNORTHWEST People -Vision Solutions Calculation No. NE-02-01-05 P d D Verii-e ale /L Prepared by / Date: D. f-'Iffie4 2Z Verified by/Date: LS Woo0sley eiin 1/4 No. 1 REV BAR.
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t ENERGY Page No. Cont'd on page ENORTHWEST MANUAL CALCULATION 5.0 People* Vislon- Solutions Calculation No. NE-02-01-05 Prepared by J')at: K ey 07-06-04 Verified by/Date: / Revision No. 0 REV BAR. The test data for the leakage into secondary containment, Reference 1.20 of Appendix E, indicates that the majority of the leakage is at the upper location, Figure 1. This location consists of thousands of feet of lap between the metal sheeting of the upper section of the refuel floor volume. A review of the data indicates that the leakage from this area is at least 90% of the total leakage. However the D/P is higher at the lower leakage location, which is the railroad bay door, Figure 1. Due to this condition the leakage is conservatively adjusted to have an increase in the leakage at the lower location (highest D/P). A series of sensitivity studies were run to determine the effect of varying the leakage between the two locations. It was determined that the 70% upper/30 % lower split is an acceptable conservative condition. Plant Procedure TSP-RB-B501 verifies that the leakage is within the Technical Specification limits for an SGT fan to be in service and for verification of leakage rate. The secondary containment has only one leakage limit of 2430 CFM. For a discussion of the basis of the leakage value see page 34 of Appendix E. The split of the leakage is not a concern during operation and testing as long as the total leakage is within the specifications. This secondary containment drawdown analysis is for a duration of 30 days as required by R. G. 1.183, Reference 13, Table 6. The evaluation of the results of Appendix E determined that the temperatures in the reactor building do not reach a stable condition prior to the end of the required duration. To verify that the model reaches a stable or decreasing temperature in the secondary containment the length of the analysis was extended to show the point of stability. The longer duration of the temperature increase is in part due to the conservative temperature assumed in the primary containment wetwell.
Background
The approach used in this calculation was to have Enercon Services, Inc develop the GOTHIC model based on previous models developed by Energy Northwest. The development of the model started with the assumptions and framework used in calculation NE-02-94-19, Reference 16. This model was then simplified from a multinode representation of secondary containment to a single node model. This model was used to run various sensitivity studies and to develop the three-node model. The three-node model was used to run additional sensitivity studies and to establish and test the assumptions. Figure 2 shows the three node GOTHIC model used to perform the analysis. The final assumptions and input parameters were documented in the QA INPUTSRlOa.doc. The information contained in QA INPUTSRlOa.doc was incorporated into the body of Enercon calculation WS129-CALC-O01. Both Enercon Services, Inc and Energy Northwest ran case studies. Enercon test cases are documented in Appendix D and E and 1. Energy Northwest test cases are documented in the Appendix G of this calculation. The configuration of the GOTHIC model, Figure 2 on page 4.1, is used for all Energy Northwest test cases except those to test the Refuel Floor circulation where additional flow paths are added to the floor. The results of those studies are included in this calculation.
kE- / Y - P<R tz/ C-1R4 33PI No. WSIZ9-PR-02 C9 z PROJECT REPORT b COVER SHEET REV. 1 ENERCON SERVICES, INC. _ PAGE NO. 1of 44 PROJECT REPORT For
.Long Term Drawdown Analysis Sensitivity On Modeling Location Of SGTS Heater Independent Review Required: Yes Prepared by: Paul N Hansen a Date: 7/28'10 Reviewed by: NA Date:
Reviewer Reviewed by: Bivins Calhoun MH Date: 24 f Independent Reviewer Approved by: Ralph Schwar bekk2, t:9j / 7 Project Manager or Des gnee
NO. WS129-PR-02 PROJECT REPORT - REV. I ENERCON SERVICES, ENC. S___ _ _C___ __ _ _PAGE NO. 2 of 44 PROJECT REPORT REVISION STATUS REVISION DATE DESCRIPTION 0 September 6, 2004 Initial Release September 28, 2004 Revision PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION All 1 APPENDIX REVISION STATUS APPENDIX NO. PAGE NO. REVISION NO. APPENDIX NO. PAGE NO. REVISION NO All All 1
NO. WS129-PR-02 E HQ PROJECT REPORT I REV. 1 ENERCON SERVICES, INC. I __I_ _PAGE NO. 3 of 44
Purpose:
....... 4........4
References:
....... 5 Methodology: . ............. . . . . 5 Assumptions: ....... 5 Evaluation: .....
Modeling Inputs....8 Case Description ............................................................................................................................................. 22 Results ..... 23
Conclusions:
.......... 25 Appendices: ....... 44
NO. WS129-PR-02 lam PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I I I PAGE NO. 4 of 44
Purpose:
Energy Northwest has requested that ENERCON evaluate the drawdown response with the SGTS heater elements located within the SGTS inlet volume. In addition, changes to the SGTS fan flow modeling is presented. The revised modeling incorporates an additional volume to the discharge side of the SGTS fan to allow for the inclusion of the fan efficiency heating of the fluid and to better represent the fluid momentum response of the system. The calculation documented in References 1 and 2 evaluates the response with the SGTS heater incorporated into the GOTHIC volumetric fan model.
NO. WS129-PR-02 PROJECT REPORT ENERCON SERVICES, INC. I _ __I_ _ IPAGE NO. 5 of 44
References:
- 1. Calculation WS129-CALC-001 Revision I "Columbia Station GOTHIC Secondary Containment Drawdown Model"
- 2. WS129-PR-0I Revision 0 "Long Term Drawdown Analysis Demonstrating Steady State Condition is Reached From a Starting Condition based on 0.0" Water Gauge"
- 3. SGT-TS-EHlA1 I Revision 4 "Instrument Master Data Sheet For SGTS-EHC-lA-1 First Stage Thermal Control"
- 4. Specification SPC 28-00,99 (Provided in Appendix 2)
- 5. Specification SPC 28-00, 100 (Provided in Appendix 2)
- 6. E/I-02-92-1024
- 7. Heating Ventilating and Air Conditioning Analysis and Design Second Edition By Faye C. McQuiston and Jerald D. Parker ISBN 0-471-08259-7
- 8. E/I-02-91-1066 Methodology:
The analysis is performed using the GOTHIC Version 7.1 computer code (Energy Northwest license). All input changes are calculated using the methods documented and the GOTHIC model developed in Reference 1. Assumptions:
- 1. The volume initial pressures are established based on the worst case building pressure differential pressure being a 0.0" water gauge difference between the inside and the outside of the building. This specific assumption is provided to establish a basis to change the TS SR 3.6.4.1.1 from >0.25" WG vacuum to >0.0" WG vacuum as requested by the plant.
- 2. The outside temperature conditions are based on the cold outside air data documented in Reference 1. The cold outside air conditions were shown to be bounding in the Reference 1 evaluations. The continued use of the bounding conditions is appropriate for this evaluation.
This assumption is consistent with that used in Reference 2.
- 3. An Easterly Wind Direction is assumed in this analysis. The bounding evaluation in the Reference 1 analysis assumed an Easterly Wind Direction. The continued use of the bounding conditions is appropriate for this evaluation. This assumption is consistent with that used in Reference 2.
- 4. A 700/o/30% Leakage Split as defined in Reference I produced the bounding response. This new analysis continues to use this bounding approach. This assumption is consistent with that used in Reference 2.
- 5. The Fuel Pool Cooling Start Time is assumed to be 12 hours. This value was requested by Energy Northwest as a conservative upper bound for an operator response to manually restart
L PROJECT REPORT NO. WS129-PR-02 IREV. 1 ENERCON SERVICES, INC. I __I I_PAGE NO. 6 of44I the system within the control room following a LOCA. This assumption is consistent with that used for Reference 2.
- 6. The SGTS heater is assumed to start 13 seconds before the fan starts (Reference 6). The heater will continue to run provided air temperatures in the SGTS inlet volume are less than 225 0F and the fan is running. The temperature value is selected based on the nominal value documented in Reference 3.
- 7. The SGTS heater is assumed to stop for air temperatures in the SGTS inlet volume that exceed 245 0F. This value is arbitrarily selected and is not expected to have any impact on the analysis. It is provided as a place holder for future analysis and will be demonstrated to be inactive for the analysis by the results presented in this calculation.
- 8. The SGTS fan motor provides a heat source to the main reactor building volume equivent to that associated with a 25hp motor operating at 89% efficiency. The motor horsepower is established in Reference 5 as 25hp while the motor efficiency is established in Reference 4 to be 89% with flow at 75%. The flow assumed in the analysis is greater than 75%, however, Reference 4 provides higher efficiency at higher flow rates. Since the lower efficiency results in a greater heat load to the building this value is conservative. The fan is centrifugal and the motor for this type of fan is outside the flow stream and therefore provides a heat source to the building rather than the process fluid. Therefore, locating the heat source in the Main Reactor Building Volume is appropriate.
- 9. The SGTS fan adds heat to the process fluid. A portion of the shaft horse power adds heat to the fluid moved by the fan. Specifically, the fan imparts on the fluid a total power that raises the total pressure of the fluid and produces a flow. The total power imparted to the fluid is less than the shaft horsepower delivered by the motor. The ratio of these two values is the total fan efficiency. The portion of the shaft horsepower that does not result in flow and pressure rise adds heat to the fluid.
- 10. The SGTS fan flow is modeled assuming the VIV (Variable Inlet Vane) is 0% closed when building vacuum in the worst case location is less than 0.26 inwg (this value explained below).
The original analysis documented in Reference I assumed that the VIV was 25% closed throughout. The actual control system for fan flow modulates the position of the VIV to control fan flow to establish the minumum required vacuum conditons within the building. This fan flow control loop utilizes one of two signal inputs - a building differential pressure signal provided by the reactor building pressure control system, which utilizes a controller setpoint value of -1.7 inwg and a maximum/minimum flow signal provided by an electonic limiter circuit, having a maximum setpoint of 5378 ICFM and a minimum setpoint value of 1560 ICFM. When there is a loss of vacuum in the building - as is the case for this analysis - the VIV is positioned to maximize flow, utilizing the limiter signal of 5378 ICFM. The maximum fan flow is restricted to prevent a motor thermal over load trip during low source voltage conditions and to ensure maximum residence time through the carbon filters (Reference 8). This maximum flow value of 5378 ICFM is maintained until the building pressure control setpoint of -1.7 inwg is reached, at which time the VIV will throttle as necessary, based on actual building inleakage rates, in an attempt to maintain this -1.7 inwg
NO. WS129-PR-02 PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I___I_ PAGE NO. 7 of44 setpoint value. Therefore, although the VIV will actually open to maximize flow up to the SGT fan flow limiter setpoint value of 5378 ICFM, for the purposes of this analysis, only a maximum flow rate of 4800 ACFM is used. This is accounted for in the modeling by limiting the fan curves to a maximum flow of 4800 ACFM. Recent modeling changes that better simulate the fluid momentum response on the discharge side of the fan produce pressure drop conditions that result in flows below 4800 ACFM on the 25% closed fan curve while building vacuum remains below the analytical setpoint value. The modeling of the pressure drops in the system inlet are established to provide the maximum pressure drop associated with dirty filters. Therefore, the inability to establish the 4800 ACFM for the 25% closed VIV postion is not completely unreasonable and the opening of the VIV to establish the 4800 ACFM is to be expected under such conditons. As described above, the fan will position the VIV to full open if necessary to establish the maximum allowed flow when Building Vacuum is below the setpoint. Therefore, applying the 0% closed fan curve with a limit of 4800 ACFM is appropriate for the initial drawdown analysis evaluation. Once the analytical vacuum criteria for the building is established the fan control will be switched back to the 25% closed position. If the analytical vacuum criteria is no longer met the fan control will return to the 0% curve. This is a very simplified approach since the actual fan controls would modulate through the 0% to 25% range prior to reaching a 25% position. This simple modeling of fan response could result in an artificial decrease in building vacuum below the minimum criteria. To address this a lag is introduced in the form of a slightly increased vacuum value that will be used to switch the fan flow curve. The vacuum value selected is 0.01 inwg greater than the minimum vacuum criteria of 0.25 inwg. Therefore, the fan curve will switch at 0.26 inwg of vacuum in the worst building location.
NO. WS1Z9-PR-02 Fwl PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I_ PAGE NO. 8 of 44 I__ Evaluation: Modeling Inputs The modeling inputs are based on those documented in Reference 2 except were modified below. The changes to the model includes the modification of the heat source included in the GOTHIC volumetric fan. This is accomplished by applying a forcing function to represent the heat input provided by the fan . In addition, the fan flow control is altered to allow the use of the 0% curve as described above in assumption 10. This is accomplished by applying a forcing function to drive the flow using a control variable as shown in Table 1 and described below. Better representation of the fluid momentum response is provided by adding an additional volume associated with the SGTS modeling and rearranging the SGTS heater location relative to the inlet pressure drop. Finally, the SGTS fan motor heat is included in the reactor building volume. Fan Heat The fan heat forcing function (FF#46 Table I) provides the heat input to the fluid by the fan using the fan efficiency. The fan efficiency is based on the shaft horse power delivered to the fluid. The shaft horse power is defined using the motor horse power and motor efficiency as shown in the equations following Table 1. Table 1 -Modified GOTHIC Input Volumetric Fan Table 2 Volumetric Fan - Table 2 Vol Flow Flow I Heat Heat Fan Flow Rate Rate Heat Rate Rate Dlsch
# Option (CFM) FF Option (Btuls) FF Vol 1Q DP 1 48 Flow 1 46 6 ShaftHp = 0.89(25hp)~
f0.70679 B1t7 J9sea ShaftHp = 15 .72 6 BTU/ The fan efficiency and resulting fan heat is calculated using the shaft horse power as follows (Reference 7).
L 3 PROJECT REPORT NO. WS129-PR-02 ReV. 1 ENERCON SERVICES, INC. PAGE NO. 9 of 44 r = F7iafi) FanHeat= (I - , XShawtp) The fan heat is entered into the volumetric fan heat input using the forcing function controlled by a control variable based on the aforementioned Fan Heat relationship. The fan heat is calculated with two control variables. The first of these (#59) establishes the efficiency and the second (#60) gives the Fan heat. The GOTHIC inputs associated with these control variables and fimctions are outlined below. Control Variables CV Func. Initial Coeff. Coeff. Upd. Int. Description Form Value G a8 Min Max Mult. 59 Fan Efficiency mult I 0 0.0116883 0 -1E+32 I E+32 0 60 Fan Heat sum 0 15.73 0 -1E+32 1E+32 0 Function Components Control Variable 59 Fan Efficiency mult Y=G*(alX1*a2X2*... anXn) Gothicq s Variable Coef. Name location a Vfanf cf1Q I 2 Dpjnc cJAl 1 Function Components Control Variable 60 Fan Heat sum Y=G*(aO+alXl+a2X2 ...+anXn) Gothics Variable Coef. Name location j a One cm 1 2 1 CWal I cv59 I -1 I 31 FF# 46 l I Description SGTS Fan Heat Functions I Ind. Var. I I cv6O I Dep. Var. Dep. Var. I Points i Lii d Function
' 48 1 1 1 SGTS Flow Select Ind. Var.:
Dep. Var.:
Am NO. WS129-PR-02 qu PROJECT REPORT REV. I ENERCON SERVICES, INC. I_ _ _ _I_ I__ PAGE NO. 10 of 44 Ind. Var. l Dep. Var. Ind. Var. Dep. Var. l 0I 0 1000000l 10000001 Fan Flow The fan flow is established using control variables 58 to assess the controlling building vacuum This control variable evaluates the building vacuum and compares it with the established value of 0.26 inwg (Assumption 10). Based on the comparison the control variable selects the appropriate fan curve as defined in Assumption 10. The GOTHIC inputs associated with these control variables and functions are outlined below. Control Varlables CV Func. Initial Coeff. Coeff. I Upd. Int.
# Description Form Value G aO Mli Max Mult.
55 DP sum 0 1 0 -1E+32 1E+32 0 56 0%/OVIV Flow tfunc 0 1 0 -IE+32 1E+32 0 57 25%VIV Flow ffunc 0 1 0 -1E+32 1E+32 0 58 Selector If 0 1 -0.26 -1E+32 1E+32 0 Function Components Control Variable 55 DP sum Y G*(aOl+1X1+a2X2+...+anXn) Gothic s Variable Coef. X Name location a _P cV6 1 2P cV2s1 _1 Function Components Control Variable 56 0%VIV Flow ffunc Y-G*interp(XptableX Gothic p Variable CoO. Name location a 1 Cvval cv55 _ 2- DC47 I Function Components Control Variable 57
Lo"P NO. WS129-PR-02 PROJ.ECT EPORT PAE 1 E2NERCON SERVICES, INC. I I PAGE NO. l l of 44 25%VIV Flow ffunc Y=G*interp(XI.tableX2) Gothlcms Variable Coef.
# Name location a 1 Cvval cv55 _
2- DC12 Function Components Control Variable 58 Selector Hf(a1X1+aO< alXl+aO=O alXl+aO>O) Y=Ga2X2 YtGa3X3 Y=Ga4X4 Gothic-s Variable Coef. _ Name location a I Cwal cv9 1 2 Cvval cv56 1 3 Cvval cv57 1 4 Cvval cv57 1 Function 12 SGT Flow vs DP Ind. Var.: Dep. Var.: ___ Ind. Var. Dep. Var. Ind. Var. Dep. Var.
-1 4800 0 4800 0.1444 4800 0.2707 4800 0.3609 4800 0.4421 4800 0.5007 4800 0.5503 4800 0.556 4800 0.5774 4000 0.5955 3000 0.6 2000 0.61 0 5 0 Function 47 SGTS 0%
Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var.
-1 4800 0 4800 0.144 4800 0.208 4800 0.266 4800 0.316 4800 0.37 4800 0.415 4800 0.456 4800 0.496 4800
p NO. WS129-PR-02 E' PROJECT REPORT REV. 1 ENERCON SERVICES, INC. PAGE NO. 12 of 44 0.5321 48001 0.5591 4800 0.595 4800 0.613 4800 0.623 48001 0.632 4800 0.633 0 5 0 Function 48 SGTS Flow Select Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 1000000 1000000
PM NO. WS129-PR-02
. PROJEC REPORT 16d-REV. __
ENERCON SERVICES, INC. III__ __ PAGE NO. 13 of 44 Flow Paths and Volumes The Revision 1 Fan Model configuration is illustrated the Figure below. Changes from Revision 0 include the division of the inlet volume, the addition of the discharge duct volume, and a connecting flow path. ELEVATED RELEASE SOTS INLE;T VOLUME (#2s) FAN DISCHARGE Ducr \-~ L VOLUME (#)
*t- BEAT SOURCE
The heat source that represents the SGTS heaters is relocated within the Volume 2 to simulate heating of the air before it reaches the SGTS Fan Inlet. To accommodate the relocation of the volumetric fan assumed heat source changes to the model are required. A review of the references listed in Reference 1 that form the basis for the models, indicate that two heaters are located in series just down stream of the inlet and Moisture Separators as outlined in Table 2 below. From Table 2 it can be seen that the pressure drop on the suction side of the fan can be logically divided between the region before the heaters and that after the heaters. Table 2 - SGTS Fan Suction Information Fan Suction Losses Pressure Drop Heat Input Flow Reference (inches WG) (km (ACFM Moisture Separators Loaded 2 4457 #1.9 para. 3.5.2 _(pg. 15A-12) Two Electric Heating Coils 0.2 21 4457 #1.9 para. 3.5A (pg. 15A-14) Pre-Filters Cleanup loaded 1.0 4457 #1.9 para.3.5.3 DP_(pg. 15A-13) Two HEPA Filters loaded 4 4457 #1.9 para. 3.5.5 to 900grams dust __ (pg. 15A-17) Two Charcoal Absorber 6 4457 #1.9 para. 3.5.6 Filters (pg. ISA-19) Electric Strip Heaters 4457 1.9 Total DP 13.2 Total DP (psi) OA88 Area Assumed 1.767 f 2 Velocity 42.039 ft/sec The model currently documented in References 1 and 2 places the entire pressure drop in the flow path that connects the main reactor building volume with the SGTS inlet volume. Therefore, as currently modeled the entire suction pressure drop would occur prior to heating the air. To properly model the pressure drop, it is necessary to separate the pressure drop calculation between the two regions as the velocity of the heated air will increase as it expands. This is accomplished by separating the SGTS fan Inlet Volume (GOTHIC Volume 2) into two sub-volumes. The area between the sub-volumes is assigned a loss coefficient that accounts for the losses listed in Table 2 after the heaters. The losses prior to the heaters and including the heaters will be assigned to the flow path number 4. To ensure a conservative result, a total DP value of 13.5inwg will be assumed in this analysis. Using the pressure drop value of 13.5inwg, an equivalent pressure loss coefficient is developed
POETRPNO. WS129-PR-02 FlyRO^=C %,F REPORT. REV. 1 ENERCON SERVICES, INC. I __I I__ PAGE NO. 15 of 44 for the assumed area. The flow rate listed in Table 2 is less than that assumed in the analysis, but it provides the basis for the pressure drops. The flow information provided in the table is provided as Indicated CFM (ICFM. However, to add conservatism to the calculation of the pressure loss coefficient that follows, the flow rate is treated as if it is Actual CFM (ACFM. This is the same approach used in References 1 and 2. As described earlier the pressure drop is divided between the region before the heater and the region after the heater. Therefore, a loss coefficient is assigned to represent each of these regions. The pressure drop before the heaters will include the heaters totaling 2.2in water gauge. The remainder of the 13.5inwg is assigned to the downstream region beyond the heaters. Using the same approach outlined in Reference 1 the loss coefficients are calculated. Tempo 68Fahr P:= 29.38-0.4912psi Before Heaters After Heaters
*PWGbh:= 2.2in APWGah:= 13 .5in - 2.2in P = 14.431 psi Temp = 68Fahr Flow= 4457cfin Aa := 1.767ft 2 vfTat(68Fabr)- ff= 0.016 -
lb lb Velocity:=F Velocity= 42.039- pg.a(PTemp,'air') = 0.074 lb3 Area sec f APWGbh.g APbh - AXtah- APWGah g 3 vfrsat(68Fahr)- lb vfrsat(68Fahr)-l lb lb APbh = 0.079 psi APah = 0.408 PSI 2APbh Kinletbh:= nletah:=
=ah Pgas (P,Temp, "air')-Vclocity p,(P.Temp, air').Velocity2 Before Heaters After Heaters Kinletbh = 5.644 Kinletah = 28.989
9OR NO. WS129-PR-02 PROJECT REPORT ENERCON SERVICES, INC. RE. 6 I ~PAGE NO. 16 of4 I Therefore the inlet flow path will have a loss coefficient of 5.644 as calculated above with an area of 1.767ft2 . The remainder of the pressure drop is applied within the Fan Inlet Volume. The hydraulic diameter associated with this area is 1.5ft (18inch). In addition, a flow path #11 is added to the model to provide the volumetric fan connection between the SGTS inlet and the exhaust ductwork Since the flow path is associated with a volumetric fan the hydraulics of the flow path are unimportant other than the inertial length which is maintained as 10 ft. which was established in Reference 1. The revised GOTHIC Input Flow Path Tables 1 through 3 are provided below in Table 3 Table 3 Flow Paths - Table I F.P. Vol Elev Ht Vol Elev Ht Description A (ft) (f) B (ft) f0) 1 Ground Leakage 1 468.5 0.5 1F 468.5 0.5 2 Elevated Leakage 5 667 0.1 2F 667 0.1 3 SGTS 6 577 1.5 3P 671.17 1.5 4 SGTS Inlet 1 577 1.5 2s2 577 1.5 5 FP Cooling In 5 604.4 1 4F 568.124 1 6 FP Cooling Outlet 3 568.125 1 _C 568.125 1 7 _FPHX 3 568.125 1 5 604.4 1 8 Pump Room to Maln Building 4 466 0.1 1 471 0.1 9 Pump Room to Main Building 4 422.25 16.7 1 441 0.0104 10 Main Building to Fuel Floor 1 572 0.1 5 607 0.1 I1I SGTS Fan 2sl 577 1.5 6 577 1.5 _ Flow Paths - Table 2 Flow Flow Hyd. Inertia Friction Relative Dep Mom Strat Path Area Diam. Length Length Rough- Bend Tm Flow (fW2) f})l (ft) ness (deg) Opt Opt 1 0.36 0.68 136 1 . NONE 2 0.85 1.04 130 1 - NONE 3 1.767 1.5 0.1 157.81 - NONE 4 1.767 1.5 10 1 - NONE 5 0.216 1 1 1 - NONE 6 0.216 1 1 1 - NONE 7 0.216 1 1 1 _ - NONE 8 191.41 1.77 105.31 2 - NONE 9 16.83 1A 105.31 2 - NONE 10 409.61 11.89 112.33 2 NONE 11 1.767 1.5 10 0.01 NONE Flow Paths - Table 3 Flow Fwd. I Rev. I I Critical Exit Drop
NO. WS129-PR-02 PROJECT REPORT REV._ ENERCON SERVICES, INC. PAGE NO. 17 of 44 Path Loss Loss Comp. Flow Loss Breakup Coeff. Coeff. Opt Model Coeff. Model 1 IE+18 I OFF OFF 0 OFF 2 1E+18 I OFF OFF 0 OFF 3 4 4 OFF OFF 0 OFF 4 5.644 5.644 OFF OFF 0 OFF 5 _ OFF OFF 0 OFF 6 OFF OFF 0 OFF 7 OFF OFF 0 OFF 8 1.52 1.52 OFF OFF 0 OFF 9 1.5 1.5 OFF OFF 0 OFF _ _ 10 1.5 1.5 OFF OFF 0 OFF 11 OFF OFF 0 OFF = To accommodate this change the fan inlet volume is converted into a two node subdivided volume. Since the purpose of this change is to establish a pressure drop within the volume the subdivision is evenly split between the two sub volumes and the critical parameters are the area, hydraulic diameter and loss coefficient between these sub volumes. The volume changes to accommodate this are provided in Tables 4 and 5. Table 4 identifies that the volume 2 is subdivided by assigning a 2s value to the number designation. The Volume 6 is added to provide a downstream volume for the volumetric fan used to simulate the SGTS. This volume size is arbitrarily established at 270 ft3 which approximates the discharge ductwork volume. Table 5 provides the geometry input for the model with the x direction representing the flow direction. The volume dimensions are arbitrary and the flow pressure drop behavior is established by the X-Direction Cell Face Variations table inputs. The Area Porosity input is used to establish the flow area, which is associated with the loss coefficient documented by Table 2. The Area Porosity is simply the fraction of the area defined by the geometry that allows flow. This value is thus calculated as follows. AreaPorosity = 1.767ft2 _0.0456 (1.5ftX25.8199.f) The hydraulic diameter is set to be consistent with the area assumed in Table 2 and the loss coefficient is established to account for the difference between the total loss coefficient developed from Table 2 and that assigned to the flow path discussed above. This value is 28.989 and is listed in Table 5.
NO. WS129-PR-02 g--vffiw PROJECT REPORT qj ENERCON SERVICES, INC. Ad REV. 'I I___ _PAGE __ __ __ _ NO. 18 of 44 Table 4 Control Volume s Vol Vol Elev Ht Hyd. D. LIV 1A Bum Description () ' f) (ft)(ft) l (ft2) .Opt 1 Reactor Building 1804568.96 441 163.875 28.9 DEFAULT NONE 2s SGTS Fan Inlet 1000 577 1.5 1.5 DEFAULT NONE 3 Fuel Pool Piping 10 568.125 1 1 DEFAULT NONE 4 Pump Rooms 345121.1 422.25 46.75 69.07 DEFAULT NONE 5 Fuel Pool Floor 1321336.77 604.367 63.303 31.34 1360 NONE 6 Fan Discharge Duct 577 270 1.5 1e6 DEFAULT NONE Table 5 X-Direction Noding l l___l Volume 2s __ _ Cell Distance Width Plane (ft1_(ftL 1 0 12.91 2 12.91 12.9099 Y-Dlrection Noding Volume 2s Cell Distance Depth Plane (ftL ( _t _ 1 0 25.8199 Z-D1lrection Nodin__ Volume 2s Cell Distance Helht Plane A!t L A(L _ _ It 0 1.5 = X-Directlon Cell Face Variations Volume 2s Cell Blockage Area Hyd. Dia. Loss Drop De-ent. No. No. Porosity (ft) Coeff. Factor def 0 1 1000000 0 0 2s 0 0.0456 1.5 28.989 0 2s2 0 0.0456 1.5 28.989 0
LO PROJECT REPORT NO. WS129-PR-02 REV. 1 ENERCON SERVICES, INC. I _I_ __ rPAGE NO. 19 of 44 Heaters As described above the heater was relocated to the inlet volume. To model this a new heater 27 was introduced as documented in Table 6. This heater is located in the inlet side of the volume 2s, designated as 2s2. This heater uses two trips to control the heat input to the volume. To allow for this two new trips were added to the model, trip 27 and 28 documented in Table 7. The fan motor heat source is also modeled with a new heater located in volume 1. This heater
#28 is documented in Table 6. The heater starts with trip 2, which starts the volumetric fan model to represent the SGTS. The heater has a heat load assigned that is based on a 25hp motor operating at 89% efficiency. The heat load input is calculated below for this heater.
Qmotor = (1-0.89X29 0 2 9 u/ I 1.944B-1bp see
Table 6
._ Cooler/Heater Heater On Off Flow Flow Heat Heat Cooler Vol. Trip Trip Rate Rate Rate Rate Phs Ctrlr # Description # # # (CFM) FF (Btufs) FF Opt Loc 1H Main Building Heat 1 5 = 43.24 WTI 3 2H Decay Heat S _ _ 2720.56 LTI 5 3C RRA-CC-1 __ 41_ 1 1 37 VTE 4 4C _RRA-CC_4 4 1 1 38 WE 4 5C RRA-CC-5 4 1 1 39YTE 4 6C RRA-CG_6 4 1 0 5 VTE 4 7C RRAC-1I 1 22 _ 1 41 VTE 1 C RRA-CC-12 1 22 1 42 VTE 1
_C RRA-CC-13 1 22 1 43 VTE 1 10C RRA2C15,17 22 2 44 VTE I 11C RRA-CC-19,20 22 2 45 TE 1 12H Aux Heat 522 1 6 i 7 190 VTE 1 13H Aux Heat 548 1 - _ 100 VTE 14H Aux Heat 572 10 11 50 VTE 1 15H Aux Heat 548 1 1_ 13_ 100 WIE I 16H Aux Heat 572 _4_ 1 1 16 50 VTE 17H Aux Heat 522 1 16 1 190 VTE 3 18H Aux Heat 501 _ 18 19 200 VTE I 19H Aux Heat 471 1 20 21 200 VTE 1 20H Emergency Lighting 1 25 1 43.4 1 VTI 1 21H Auxiliary Heat 1 2i 10.95 1 VTI 1 22H Dry Cask 5 = 21.8 VTI 5 23H Pump Heat 24 244.5 VTI 4 24H Fuel Pool HX Rm _ 3 4.37 VTI 1 25H Pump Room Fans 4 1 12.1 VTI 4 26H Normal LUghing I 26 0 1 27 VTl I 27H SGTS Heater 2s2 2 28 19.9 Y V77 12s2 28H SGTS Fan Motor 1 a _.9424 VT7 1
NO. WS129-PR-02 DEW 1 PROJECT REPORT ENERCON EC. .SERVICES, I I IPAGE NO. 21 of 44 The trip number 27 is used to start the heater in volume 2s2 if the air temperature in the discharge volume 2sl is less than 225F (Assumption 6) and the SGTS fan has received a start signal established by Trip 2. To address the turning off of the heater an additional trip number 28 is provided to turn off the heater if the temperature in the discharge volume 2sl exceeds 2450 F (Assumption 7). Table 7 Component Trips Trip Sense Sensor Sensor Var. Set Delay Rset Cond Cond __ Description Var. I LoC. 2 Loc. Limit Point Time Trip Trip T I Start Pump Room Coolers TIME UPPER 300 0 AND 2 Start SGTS TIME UPPER 120 0 AND 3 Start FP Cooler TIME UPPER 43200 0 AND 4 HVAC Isolation TIME UPPER 15 0 O AND 5 Heat Load Starts TIME UPPER 0.1 0 AND 6 AH12H On GASTEMP 1 LOWER 68 1E+60 7 _ AND 71AH12H Off GAS TEMP 1 UPPER 70 0 6 AND 8 AH13H On GAS TEMP I LOWER 74 1E+60 9 _ AND 9 AH13H Off GASTEMP I . UPPER 77 0 8 = AND 1a AH14H On GASTEMP I . LOWER 71 1E+60 11 _ AND 11 AH14H.Off GAS TEMP I. UPPER 73 0 10 AND 12 AH15H On GASTEMP 1 LOWER 70 1E+60 13 AND 13 AH15H Off GAS TEMP 1 UPPER 73 0 12 1AND 14 AH16H On GASTEMP 1 LOWER 62 1E+60 15 AND 15 AH16H Off GAS TEMP I UPPER 64 Of 14 AND 16 AH17H On GAS TEMP 1 LOWER 70 1E+60 1X7 AND 17 AH17H Off GAS TEMP I _ UPPER 73 0 16 AND 1_AH18H On TEMP IAS I1 LOWER 71 1E+60 19 AND 191AH18H Off GASTEMP 1 UPPER 73 0 18 _ AND 201AH19H On GAS TEMP I ILOWER 73 1E+60 21 1AND 21 AH19H Off GAS TEMP 1 _ UPPER 75 0 20 AND 22 Main Building Coolers TIME _UPPER 300 0 _ AND 23 OPEN REAIROA TIME _UPPER 1000000 1E+60 AND 24 Pump Heat TIME UPPER 30 0 _ AND 25 Emergency Lighting TIME UPPER 0.1 0 AND 26 Ensure OFF TIME UPPER 3600 0 AND 27 SGTS Heater On GAS TEMP 2sl LOWER 225 0 28 2 AND 28 SGTS Heater Off GAS TEMP 2s1 _ UPPER 245 0 27 AND
NO. WS129-PR-02 PROJECT REPORT ENERCON SERVICES, INC. . . I_ I__ PAGENO. 22f44I Case Description The model used to perform the analysis is described in full detail in References 1 and 2. The modifications made to address this sensitivity case are outlined in the previously presented Modeling Inputs section of this analysis. The analysis presented here assumes a different location for the SGTS heater input than documented in either Reference I or 2, and includes a heat load for the fan motor. All initial conditions and external wind and temperature conditions are identical with that assumed in Reference 2.
NO. WS129-PR-02 1 W hPROJECT REPORT REV. 1 ENERCON SERVICES, INC. I _PAGE NO. 23 of 44 Results: The results of this analysis are documented in Figures I through 18. Table 8 documents the GOTHIC Input deck name and the time to restore building differential pressure. Table 8 - Timing Response GOTHIC Deck Tne to Reach Tim to Reach 072S"Wo 4O.W TNMleeaterR6.CrTH 972A seconds 462.43 seconds The DP criteria illustrated in Figure 1 shows that the differential pressure criteria stabilizes at approximately 4 million seconds (46 days 7 hours) after the event. Once a vacuum of >0.25" WG is established it does not drop below this value throughout the 10 million seconds (>115 days) analysis time. NOTE: Figure 1 shows inches of WG Vacuum so a larger number, i.e. 0.5, indicates a lower pressure inside the secondary containment The pressure response of each of the three building volumes (Refueling Floor Volume, Main Building Volume, and Pump Rooms Volume) are illustrated in Figure 2. The impact that room air cooler water temperature as well as Fuel Pool Cooling start time have on the building pressure response can be seen in Figures 1 and 2. The increase in cooling water temperature causes a slight increase in building pressure. This is to be expected as temperature increases within the building illustrated in Figure 3. The start of fuel pool cooling (Figure 4) leads to a reduction in both fuel pool water temperature as well as refueling floor vapor temperature (Figure 3). This leads to a pressure reduction illustrated in Figure 2 and an increase in differential pressure illustrated in Figure 1. The mass flow into and out of the building are illustrated in Figure 5. As can be seen by the flows provided on this figure the steady condition is reached at approximately 4 million seconds. Figure 6 provides a comparison of the upper and lower leakage flow rates as a function of differential pressure. Figure 7 through 10 illustrate the heat loads and cooler response. Figures 11 through 13 illustrate the response of conductors heated by primary containment conditions. Finally, Figures 14 and 15 provide the relative humidity of the volumes and steam mass ratios respectively. The impact of fuel pool cooling on the building humidity can be seen in these same figures. As water evaporates from the fuel pool the steam mass ratio and relative humidity rise rapidly on the refueling floor. The remaining building volumes lag behind, but soon follow with increases in both relative humidity and steam mass ratio. Once fuel pool cooling is started the steam mass ratio on the refueling floor begins to decrease. The pump room and main building volumes lag behind, but also show a decrease. The relative humidity stays high on the refueling
dNO. WS129-PR-02 ki -PROJECT REPORT ENERCON SERVICES, INC. II I_FPAGE NO. 24 of 44 floor, but decreases in the other volumes. This is to be expected since as Figure 3 illustrates the water temperature on the refueling floor is superheated relative to the vapor temperature. Figure 16 shows the SGTS heater comes on just prior to the fan start as expected. The temperature rise within the system never reaches the set point to trip the heater off which validates the Assumption 7. Figure 17 and 18 show the fan volumetric flow as a function of time. As can be seen once the vacuum criteria are met the fan flow drops off to that associated with the 25% closed curve described in Assumption 10. For the remainder of the run the fan remains on this curve since the building vacuum criteria is maintained throughout. The fan heat, SGTS heater and fan motor heat input is illustrated in Figure 18. This figure shows that these heaters behave as specified in the inputs.
. PNO. WS129-PR-02 PROJE REPORTV. 1 ENERCON SERVICES, INC.
- I I PAGE NO. 25 of 44
Conclusions:
This evaluation demonstrates that with the SGTS heater located in the suction side volume of the model and with building conditions based on 0.0" Water Gauge (Reference 2) the SGTS response to a LOOP/LOCA is sufficient to establish 025" water gauge vacuum in less than 20 minutes. Moreover, the building conditions are maintained with a building vacuum of !0.25" WG throughout the analysis and a steady state pressure condition is achieved.
RNO. WS129-PR-02
= s PROJECT REEPORT q; REV. 1 EN:RCON SERVICES, MC.
I __ ___ __ _ _ I I__PAGE NO. 26of44 FuelftoICooll2tr Long Twrm Mlnlmwmn DP Crfttrl Evalualion I i -11II51 11 , . 1.0 10 100.0 1,w.0 10.0 100.000.0 1.0w00.IW.0 10,000.000.0 now (sam) FIgure 1
NO. WS129-PR-02 19 PROJECT REPORTEV. 1 ENERCON SERVICES, INC. _ _ _ _ _ _ _ _ I __ rPAGE NO. 27 of44 Valmne Prawn's Resporue I I I '14.8 0.1 1.0 ' 0. 10o
- 0. lW000A 1~000. 1.00.ODO 1.0m.000.0 10.mO.00.0=
Tn. (see) Figure 2
. PNO. WS129-PR-02 F"L.H PROJEC REPORTEV 1REV. I FANERCON SERVICES, INC.
I.I I PAGE NO. 28 of44 Fuelftoloclcl2hr Rewctor EJIWIng Teshpwratwum 1I 100 Rimp RRidVaT A'C I 11111H I I 11111 li, 111H1lpm Moinfloill
- ~11rmmi1 I II IlIII 111111 I I I111111 II I a I 10.000 100I00 1. 0.0 00 i 0.0 0, 00 Tro (G")
Figure 3
BMNO. WS129-PR-02 El ~PROJE CT REPORT ULd REV. 1 ENERCON SERVICES, INC. I _ __I_ _ I__PAGE NO. 29 of44 FuelPaolCooll2hr Fuel Pool Hea Balance 1i1 1 1 1 1 I I ed I~o If I II mm 4000
-0w 4600C IA 10.0 100.0 l.imoa 1s.0o.o 100. 0 . 1 0oo0. 0 10 i0.0 00.
m ("a) Figure 4
NO. WS129-PR-02 I PROJECT REPORT ENERCON SERVICES, INC. I __I I__ PAGE NO. 30 of 44 FusIPoolCooll2hr Flows Into and Out of Reactor Building II 1111111 I 1 111 4-W u 11111 I I 1fiiiiii I I11111111 i1I frII111 I El2 RmSW I 1.0 10.0 100.0 1.eDD.0 10o00.0 100,000.0 1.000000.0 10.000000.0 rm. ("a0) Figure 5
low PROJECT REPORT NO.WS129-PR-02 ENERCON SERVICES, INC. I I I I PAGE NO. 31of 44 FuUP'CoColl2hr Leakage Flow Versus DP 02 0. *A OA 0.6 pm. 4l._. (InH2O) Figure 6
NO. WS129-PR-02 PROJECT REPORT miREV. _ EiNERCON SERVICES, INC. SERVICES,__MC. ___PAGE NO. 32of44 ruelPoolCoonhm Maln And R.Ieune Floor Heat Loads I I I K I-- M ;; E y 1.0 10A 1M.0 U=
"AM. Ige..)m "m 0 "U m Figure 7
NO. WS129-PR-Z2 PROJECT REPORT EV. I ENERCON SERVICES, INC. I _ _ _ _I_ I__ PAGE NO. 33 of44 FueIPoolCoofl2h, Pwq Room Heat Loads 500 -
- - : - - = - - -i1riill1illl llll IO 1 00 - ----- --
1.0 10 100t0 1pOO 10000.0 100W.0 1.0000. 10.0PO.0. 10O0DOO Wn.(s"m Figure 8
NO. WS129-PR-02 "I PROJECT REPORT PEV. R 1 ENERCON SERVICES, INC. I_ _ _I_ _PAGE NO. 34of44 ftetI~oolCoot12Iw Punip Room Coolemr I IN I I I coottv W*Wm ob"puh~ I I OCFIII os"NMT 1.0 10.0 Mo.0 tome. l04.0 1,000,00X0 I0.000.00
.thoo.)
Figure 9
U.NO WS129-PR-02 M PROJECT REPORT ENERCON SERVICES, INC. PAGE NO. 35 of 44 FuelPaooCaoo!2hr hain Eudlli Volume Cooler HeawRemo~va
.40 ~~N~A~VZ= A 14O I
l RR1CIU2Ocll I I IOo. t.aMo r.0.0O 10a.M.00 10,0o.0.0 d eAd) Figure 10
NO. WS129-PR-02 PROJECT REPORT Li ENERCON SERVICES, INC
. REV. 1 I.I I PAGE NO. 36of44 FuelPoolCaoollhr WW To Pump Roam Heat Sgnwtu I I11 c
FI 1.0 10.0 o00.0 1.0.0 ¶0.0100 M M0.* 1 = 0 =.0
. ¶0.000.000.
TW. (am.) Figure 11
NO. WS129-PR-02 r-m-ff -ifPROJECT REPORT
% o REV.
ENERCON SERVICES, EqC. I PAGE NO. 37 of44 FluelPooCoI19r Drywall To RB Heat tructur E 1-_ 200 A11 A 1X~ ~0
-Wet To MakhRBTA33 iiil _1lll 11111ll~
71 0.1 1. HIM 1 10.0 100.0 1,oooo HI 10,000.D0 10000o 11111 tlC .0 10,CCO.O Thu ( Figure 12
NO. WS129-PR-02 3 PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I__ I_FPAGE NO. 38of44 FusIPool~ooMl2ti Fuel Pool to DW NWaStructure 110fo A oD W I II> A1 E 1200 100 1.0 10.0 1000 1000.0 1l.ox"O 100,000.0 1000,0O 10.000.0m. Thm ('.4 Figure 13
ILImPROJECT REPORT NO. WS129-PR-02 REV. 1 ENERCON SERVICES, INC. I___ I__PAGE NO. 39of44 Fuel Pool Cooling 121wLong Twnn Relatly Humidity 05 If
-I"-PurnpRDon RsW"HmftM44 RfflM
-R"ro R= ftathn HwMtj M-15
- MaInIMIVolumeftsin M" F 111111 I H ill I I I I Jil 11111 11111 I IIL1000 IX 11111N, I 4 4 J.IIIII Pi Ill I FUIRROM 1.0 10.0 100.0 t0o 10o,0.0" 1co0,0.D 1.0 000 10.00000.0 o t(o)
Figure 14
FNNO. WS129-PR-02 FwI6 PROJECT REPORT REV. 1 ENERCON SERVICES, INC. II __ rPAGE NO. 40 of 44 Steam Mass Ratio 4 E06-m" Roorn Steam MansRmWtSWO RPafudft Floor Slaam MkanFtft SMS
- 0. 4M atfl B d ww~i tawn Pbs PRao 8& 1
.I I
0.01 E'IHl 1.0 10.0 100. 1,X00.0 10,00.o 100.O00D 1.000.0X 10.000.0c0.0 rug (s.) Figure 15
WS129-PR-02 aPROJECT N"NO. REPORT ________ CREV. _ ENERCON SERVICES, INC. I_ PAGE NO. 41 of 44 SG13 Heater Input &d Tenperature Response 1-11
- -li sc II DI E
Lag XX a01 o a .0 I o0 eoo loom lewd TeneEma) FIgure 16
NO. WS129-PR-02 Ed ft PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I_ I_PAGE NO. 42 of 44 SGTS FAN Flow 5000-4000 f__,_ ,_ 0 -1 I0- - - 1I 100 --- 2 0 - - 111 1 100 1,000 10.000 00,000 1.000,00 10,000.000 Tim. {sac) Figure 17 -Volumetric Fan Flow
PM NO. WS129-P1R-02 PROJECT REPORT NO. 1 SERVICES, INC.V. EON1 INERCON PAGE NO. 43 of44 SGTS Fen And Heater Loads SOTGTS Fen I l _ :F0 -
- I I I 11 __
1Ii - '--' ' 1-- 100 1.0m0 10.000 100,000 100m00 10,000,000 Tw j"ic) Figure 18 - SGTS Associated Heat Loads
0 _ NO. W5129-PR-02 E 1v PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I PAGE NO. 44 of 44
. Appendices:
- 1. GOThIC INPUT DECK 90 Pages
- 2. Design Verification 2 Pages
- 3. Fan Motor Specification 5 Pages
MNO. WS129-PR-02 W NWE PROJECT REPORT ENERCON SERVICES, INC. I__PAGE NO. I of 90 APPENDIX I GOTHIC INPUT DECK
NO. WS129-PR-02 Pt PROJECT REPORT L ENERCN SERVICES, INC. REV. 1 PAGE NO. 2of90 Control Volumes Vol Vol Elev Ht Hyd. D. LI IA Bum
# Description (ft3) (ft) (ft) (ft) (ff2) Opt I Reactor Building 1804568.96 441 163.875 28.9 DEFAULT NONE 2s SGTS Fan Inlet 1000 577 1.5 1.5 DEFAULT NONE 3 Fuel Pool Piping 10 568.125 1 1 DEFAULT NONE 4 Pump Rooms 345121.1 422.251 46.75 69.07 DEFAULT NONE 5 Fuel Pool Floor 1321336.77 604.367 63.303 31.34 1360 NONE 6 Fan Duct 270 577 1.5 1000000 DEFAULT NONE Laminar Leakage Lk Rate Ref Ref Ref Sink Leak Vol Factor Press Temp Humid ISrc Model Rep Subvol Area
_ (°hr) (psla) (F) ) BC Option Wall Option (ft2) 1 0 CNST T UNIFORM DEFAULT 2 0 CNST T UNIFORM DEFAULT 3 0 CNST T UNIFORM DEFAULT 4 0 CNST T UNIFORM DEFAULT 5 0 . CNST T UNIFORM DEFAULT 6 0 _CNST T UNIFORM DEFAULT Turbulent Leakage Lk Rate Ref Ref Ref Sink l ____l Leak Vol Factor Press Temp Humid /Src Model Rep Subvol Area
# (%/hr) (psla) (F) (YO) BC Option Wall Option (ft2) fLJID 1 0 _ lCNST T l lUNIFORM DEFAULT 2 0 _ l lCNST T l lUNIFORM DEFAULT 3 0 _ l CNSTT _ JUNIFORM DEFAULT 4 0 _ l lCNSTT l UNIFORM DEFAULT 5 0 I _CNSTT I I UNIFORM DEFAULT 5 0 I I ICNSTT l UNIFORM DEFAULT X-Dlrectbon Noding I Volume 2s Cell l Distance Width Plane (ft) (ft) 11 0 12.91 2 12.91 12.9099 Y1Dlrectlon Noding Volume 2s
0L NO. WS129-PR-02 E tPROJECT REPORT REV. 1 ENERCON SERVICES, INC. PAGE NO. 3 of 90 Cell Distance Depth Plane (K) (ft) 1 0 25.8199 Z-Direction Noding Volume 2s Cell Distance Height Plane (ft) (ft) 1 01 1.5 Cell Blockages - Table I Volume 2s Blockage _ _ No. Description Type = = = = __ ___ =e____ ___=_ Cell Blockages - Table 2 Volume 2s Blockage (ft) Curb Coordinates Dimensions No. Xi Y1 ZI X2 Y2 Z2 X3 Y3 - L Height X-Dlrection Cell Face Variations - ____ Volume 2s I Cell Blockage Area Hyd. Dia. Loss Drop De-ent. No. No. Porosity (ft) Coeff. Factor def 0 1 1000000 0 0 2s1 0 0.0456 1.5 28.989 0 2s2 0 0.0456 1.5 28.989 0 II I tI- I Y-Direction Cell Face Variations =_==_ Volume 2s _ i Cell Blockage Area Hyd. Dia. Loss T Drop De-ent. = No. j No. Porosity (ft) Coeff. J Factor def 0 1 1000000 01 0 _ Z-Dlrectlon Cell Face Variations Volume 2s
NO. WS129-PR-02 PROJECT REPORT REV. 1
.NERCON SERVICS, INC.
__ PAGE NO. 4 of 90 Cell Blockage Area Hyd. Dia. Loss Drop De-ent. Curb Ht No. No. Porosity (ft) Coeff. Factor (ft) - def 0 1 1000000 0 0 _ I _ _ Volume Variations ___ Volume 2s Cell Blockge IVolume I Hyd. Dia. _ No. No. Porosity I ft) def a 11 I =1000000 _ Fluid Boundary Conditions - Table I
= Press. Temp. Flow l J ON OFF Elev.
BC# Description (psia) FF (F) FF (Ibmts) FF P 0 Trip Trip (ft) IF Ground Leakage 14.68294 28 VO.O17 22 NO NO l 468.5 2F Roof Leakage 14.56511 28 vO.017 21 NO NO l 667 3P Elevated Release 14.568321 28 INO NO _ _ 671.17 4F Fuel Pool Cooling 14.71 I- 120 -78.958 19iNO NO 3 l 568.124 5C Fuel Pool Cooling 14.7 1 1201 0 lNO lNO l l l 568.125 _ Fluid Boundary Conditlons - Table 2 l Llq. V. __ l_Stm. l_ l_Drop D. Cpld Flow l Heat Outlet
@C# Frac. FF P.R. FF (In) FF BC# Frac.lFF Btus FF Quality FF iF 0 0 NONE l _ DEFAULT l_l 2F 0 0 NONE _ DEFAULT _
3P I l _ l 0 NONE l l DEFAULT l_ l4F l 1l I1 NONE I 1 l DEFAULTI _ l5C l 11 _1_1 INONE I 14F I 1l I I lDEFAULT 7 Fluid Boundary Conditions - Table 3 l _ _ Gas Pressure Ratios Air t2sG BC# Gasi1 FF Gas 2 FF Gas 3 FF Gas 4 FF 3P I _ _ _ __ _ _ _ _ _ 1 F I01 ii _ _ 5 01 I_ I _-
. NO. WS129-PR-02 ram PROJECT REPORT Un REV. 1 ENERCON SERVICES, INC.
I PAGE NO. 5 of 90 Fluid Boundary Conditions - Table 4 Gas Pressure Rattos SC# Gas 5 FF Gas 6 FF Gas 7 FF Gas 8 FF Flow Paths - Table 1 F.P. Vol Elev Ht Vol Elev Ht
# Description A (ft) (ft) B (ff) (ft)
I Ground Leakage 1 468.5 0.5 1F 468.5 0.5 2 Elevated Leakage 5 667 0.1 2F 667 0.1 3 SGTS 2s1 577 1.5 3P 671.17 .1.5 4 SGTS Inlet 1 577 1.5 2s2 577 1.5 5 FP Cooling In 5 604.4 1 4F 568.124 1 6 FP Cooling Outlet 3 568.125 1 5C 568.125 1 71FPH3 3 568.125 1 5 604.4 1 8 Pump Room to Main Building 4 466 0.1 1 471 0.1 9 Pump Room to Main Building 4 422.25 16.7 1 441 0.0104 10 Main Building to Fuel Floor 1 572 0.1 5 607 0.1 1_1 SGTS Fan 2s1 677 1.5 6 577 1.5
_ Flow Paths - Table 2 Flow Flow Hyd. Inertia Friction Relative Dep Mom Strat Path Area Diam. Length Length Rough- Bend Tm Flow
# (ft) (ft) (.ness (ft) (deg) Opt Opt 1 0.36 0.68 136 1 - NONE 2 0.85 1.04 130 1 - NONE 3_ 1.767 1.5 10 157.81 - NONE 4 1.767 1 1 1 - 1 NONE 5 0.216 1 1 1 - NONE 6 0.216 1 1 1 _ NONE 7 0.216 1 1 1 NONE 8 191.41 1.77 105.31 2 - NONE 16.83 1A 105.31 2 _ NONE 10 409.61 11.89 112.33 2 - NONE 11 1.767 1.5 10 0.01 _ NONE Flow Paths - Table 3 Flow Fwd. Rev. _ Critical Exit Drop Path Loss Loss Comp. Flow Loss Breakup
# Coeff. Coeff. Opt. Model Coeff. Model I 1E+18 1 OFF OFF 0 OFF 2 IE+18 1 OFF OFF 0 OFF 3 4 4 OFF OFF 0 OFF 4 5.644 5.644 OFF OFF 0 OFF 5 OFF OFF 0 OFF 6 OFF OFF 0 OFF 7 OFF OFF 0 OFF 8 1.52 1.52 OFF OFF 0 OFF 9 1.5 1.5 OFF OFF 0 OFF 10 1.5 1.5 OFF OFF 0 OFF 11 I, OFF OFF 0 OFF
NO. WS129-PR-02I I r- PROJECT REPORT wSREV. 1 ENERCON SERVICES, INC. PAGE NO. 7 of 90 Thermal Conductors - Table I Cond Vol HT Vol HT Cond S. A. Init.
# Description A Co B Co Type (ft2) T.(F) Or I ECCS Unin Pipe 4 7 4 4 1 2307.56 751 2 ECCS Ins Pipe 4 7 4 5 2 642.19 751 3 FP Unin Plpe 1 8 1 6 3 406.34 751 4 Pump Rm ExWall 4 9 4 3 15 1958.06 751 5 Pump Rm Ex Wall 4 9 4 3 18 4359.37 751 6 Pump Rm ExWall 4 9 4 3 21 714 751 7 Pump Rm ExWall 4 9 4 3 25 133 751 8 Pump Rm CoorWall 4 9 4 3 15 1405.68 751 9Pump Rm CoorWall 4 9 4 3 18 1026.37 751 IO Pump Rm CoorWall 4 9 4 3 25 208.25 751 11 Pump Rm Ceiling 4 11 1 10 5 2908 75 X 12 Pump Rm Ceilng 4 11 1 10 9 3117 75 X 13 PumpRm RBWall 4 9 I 9 14 5630.62 75 X 14 Pump Rm RB Wall 4 9 1 9 18 121.87 75 X 15 Pump Rm RBWall 4 9 1 9 19 706.87 75 X 16 Pump Rm Int Well 4 9 4 9 31 4743.45 751 17 Pump Rm Int Wall 4 9 4 9 21 97.5 751 18 Pump Rm IntWall 4 9 4 9 24 5975 751 19 Pump Rm WW Wall 4 9 4 7 28 5676.25 75 1 20 Aux Rm Floor 4 11 1 10 9 92 75 X 21 Aux Rm Ex Wall I 9 1 3 13 1324 751 22 Aux Rm Int Wall _ 9 1 9 4 4995.25 751 23 Aux Rm Int Wall 1 9 I 9 5 444.5 751 24 Aux Rm IntWall 1 9 1 9 7 1241.5 751 25 Aux Rm Int Wall 1 9 1 9 15 322 751 26 Aux Rm Int Wall 1 9 1 9 17 264.5 751
NO. WS129-PR-02
; ; . PROJECT REPORT r REV. 1 ENERCON SERVICES, INC.
I _I _PAGE NO. 8 of 90 Thermal Conductors - Table I Cond Vol HT Vol HT Cond S. A. mitn _ Descriptlon A Co B Co Type (ft2) T.(F) Or 27 Aux Rm Int Wall 1 9 1 9 25 450.85 751 28 Aux Rm Int Wall I 9 1 9 27 40.25 751 29 Aux Rm Int Wall 1 9 1 9 4 1149.36 751 30 Aux Rm Int Wall 1 9 1 9 5 814.31 751 31 Aux Rm Int Wall 1 9 I 9 9 150 751 32 Aux Rm Int Wall _ 9 1 9 12 101.66 751 33 Aux Rm DW Wall 1 9 1 1 20 289 751 34 Aux Rm FP Wall 1 9 1 12 23 422.875 751 35 Misc Wall 1 9 1 9 4 9789.87 751 36 Misc Wall 1 9 1 9 6 5445.41 751 371Mlsc Wall 1 9 I 9 10 1704 751 381MiscWall 1 9 1 9 16 2334.49 751 39 Main Ex Wall I 9 1 3 8 24402.43 751 40IMaln Ex Wall 1 9 1 3 11 44567.01 751 41 Foor 11 1 10 9 55700.9 751 42 DW Wall 1 9 I 1 22 9443.95 751 43 DW Wall I 9 1 1 26 13332.51 75 1 44 FP to DW Wall 5 12 5 1 20 1743.75 751 45 FP to Main Build 1 12 5 9 21 4378.75 75 X 46 Ex Wall 5 9 5 3 29 34800.06 751 47 Roof 5 11 5 3 30 20194.28 75 1 48 Fioor _ 1 11 5 10 9 16205.5 75X
l_0 NO. WS129-PR-02 PROJECT REPORT PGN.9o0 RC SRiCES. 1
'~iRONSERVICES, INC.
I I PAGE NO. 9 of 90 Thermal Conductors - Table 2 Cond Therm. Rad. Emiss. Therm. Rad. Emiss. Side A Side A Side B Slde B I No No 2 No No _ 3No No 4 No No 5 No _No 6 No No 7 No No 8 No No 9 No No 10 No No 11 No No 12INo .No 13INo No 14 No No 21 No No 16 No .No 17 No No 18 No No 27 No No 20 No No 21 No No 22 No No 231No No 324 No No 25 No No 26 No No 27 No No 3No No 29 No No 30 No No 31 No No 32 No No 33 No No 34 No No 435 No No
LI PROJECT REPORTO.1 NO. WS1Z9-PR-02 ENERCON SERVICES, INC. I __I_ _ I PAGE NO. 10 of9o Thermal Conductors - Table 2 Cond Therm. Rad. Emiss. Therm. Rad. Emniss.
# Side A Side A Side B Side B 44 No _ No 45 No No 46 No No 47 No ___ No _
48 No I___ No I
NO. WS129-PR-02 F-Am PROJECT REPORT ENERCON SERVICES, INC. I______. __ __PAGE NO. 11 of 90 Heat Transfer Coefficient Types - Table I Heat Cndl Sp Nat For Type Transfer Nominal Cnv Cnd Cnv Cnv Cnv Rad
# Option Value FF Opt Opt HTC Opt Opt Opt I Sp Ambient and HTC 1 14 2 ___ _
2 Sp Conv HTC 1 18 _ OFF 3 Sp Heat Fux 0 _ . . 4 Direct ADD UCHIDA HORZ CYL OFF ON 5 Direct ADD UCHIDA HORZ CYL OFF ON 6 Direct ADD UCHIDA HORZ CYL OFF ON 71Sp Temp 1 26 8ISp Temp 1 25 9 DIrect ADD UCHIDA VERT SURF OFF ON 10 Direct _ ADD UCHIDA FACE UP OFF ON 11 Direct ADD UCHIDA FACE DOWN OFF ON 12 Correlation Set . _ ; VERT SURF OFF OFF
NO. WS129-PR-102 PROJECT REPORT REV. ENERCON SERVICES, NC._ PAGE NO. 12 of 90 Heat Transfer Coefficient Types - Table 2 ___ Ml Mn_ Max Convection __ _ Condensation __ _ Type Phase Liq Liq Bulk Temp Bulk Temp Opt Fract Fract Model FF Model FF 231VAP __ _ _ _ _ _ _ T- w _ _ _ _ _ _ 4 VAP Tg-Tf Tb-Tw 5 VAP Tg-Tf Tb-Tw 6 VAP - Tg-Tf Tb-Tw 9 VAP Tg-Tf Tb-Tw 9 VAP Tg-Tf Tb-Tw 11 VAP Tg-Tf Tb-Tw _ 12 LIQ Tg-Tw Heat Transfer Coefficient Types Table 3 Char. Nat Conv For Conv Nom . Minimum Char. Type Length Coof Exp Coef Exp Vel Vel Conv HTC Height 1 ( t) FF FF FF FF (ftfs) FF (Blh-f2-F) (ft) 2 31. 4 1.75 DEFAULT 59I 1.83 __DEFAULT 6 0.X61.DEAL 7_ 9, DEFAULT _
4 NO. WS129-R-Z02 Li PROJECT REPORT . EV. I ENERCON SERVICES, INC. I_.I I PAGE NO. 13 of 90 10 DEFAULT 11 I I I I I I IDEFAULT. 12 DEFAULT HTC Types - Table 4 Total Peak Initial BD Post-BD Post-BD Type ConstHeat Time Exp Value Exp Exp Direct 1 CT (Btu) (sec) XT (Blh-2-F) yt xt FF 2 7 12 ____________ ______ _______ ______ ____ ________ _______ _____
I.NO. WS129-PR-02 E. PROJECT REPORT ENERCON SERVICES, INC. /V PAGE NO. 6of 90 Inteionally Left Blank 7A41v
NO. WS129-PR-02 E PROJECr REPORT RV AtE. 1 ENERCON SERVICES, INC. PAGENO. 15of90 Thermal Conductor Types Type ThickL O.D. Heat Heat
# Description Geom (in) (in) Regions (Btutft3-s) FF I ECCS Uninsulated TUBE 0.38 21.02 2 0 2 ECCS Insulated TUBE 2.38 22 29 0 3 FUEL POOL UNIN TUBE 0.29 7.31 1 _
4 Concrete 12" WALL 12 0 13 0 5 Concrete 18" WALL 18 0 2_ 0 6 Concrete 23.16 WALL 23.16 0 21_ _ 7 Concrete 23.36" WALL 23.36 0 21 0 8 Concrete 23.83" WALL 23_83 0 11 0 9 Concrete 24" WALL 24 0 1_ 0 10 Concrete 27.79" WALL 27.79 0 22 _ X 0 11 Concrete 28.41" WALL 28.41 0 12 0 12 Concrete 32" WALL 32 0 22 0 Concrere 33.98" WAL 33.S 1: 14 Concrete 35.12 WALL 35.12 0 22 0 15 Concrete 36" WALL 36 0 22 0 16 Concrete 37.04" WALL 37.04 0 22 0 17 Concrete 44.26" WALL 44.26 0 23 0 18 Concrete 48" WALL 48 0 23 0 19 Concrete 58.14" WALL 58.14 0 24 0 20 DW Composite 60" WALL 60 0 34 0 21 Concrete 60" WALL 60 0 24 0 22 DW ComposIte 61.37" WALL 61.37 0 34 0 23 Concrete 62.55" WALL 62.55 0 X_24 24 WW Composite 64.06" WALL 64.06 0 46 0 25 Concrete 72" WALL 72 0 24 0 26 Composite 72" WALL 72.09 0 34 0 27 Concrete 102" WALL 102 _ 25_ 28 Composite 154.86" WALL 154.86 0 49_ _ 0 29 RefuelFIWall WALL 1.598 _ 32 0 30 RefuelFIRoof WALL 0.049 0 1 0 31 Concrete 35.1 WALL 35.1 0 24 __ 0
C . NO. WS129-PR-02 PE PROJECITREPORT RV 19 REV. I ENERCON SERVICES, INC. PAGE NO. 16 of 90 Thermal Conductor Type ECCS Uninsulatedd Mat. Bdry. Thick Sub- Heat Region # (in) (in) regs. Factor 1 1 0 0.10 1 0 2 1 0.19 0.19 1 0 Thermal Conductor Type ECCS Insulated Mat. Bdry. Thick Sub- Heat Region # (in) (in) regs. Factor 1 1 0 0.19 1 0 2 1 0.19 0.19 1 0 3 5 0.38 5.27778E-05 1 0 4 5 0.38005278 0.000105556 1 0 51 5 0.38015834 0.000211111 1 0 61 5 0.38036945 0.000422222 1 0 71 5 0.38079167 0.00844441 0 81 5 0.38163611 0.001688889 1 0 91 5 0.383325 0.003377778 1 0 101 5 0.38670278 0.006755556 1 0 11 5 0.39345834 0.013511111 1 0 12 5 0.40696945 0.027022222 1 0 13 5 0.43399167 0.054044444 1 0 14 5 0.48803611 0.10808889 1 0 15 5 0.596125 0.21617778 1 0 16 _ 5 0.81230278 0.43235556 1_ 0 17 5 1.2446583 0.28383542 1 0 18 5 1.5284937 0.28383548 1 0 19 5 1.8123292 0.16886042 1 0 20 5 1.9811896 0.16886037 1 0 211 5 2.15005 0.11519995 1 0 22 5 2.26525 0.05759995 1 0 231 5 2.32285 0.02879995 1 0 241 5 2.35165 0.01440005 1 0 25 1 5 2.3660501 0.00719995 1 0 26 5 2.37325 0.00359995 1 0 27 5 2.37685 0.00180005 1 0 28 5 2.3786501 0.00089995 1 0 29 5 2.37955 0.00044995 1 0
LNO. WS129-PR-02 Et 1 PROJECT REPORT Ad REV. 1 ENERCON SERVICES, INC I _I _PAGE NO. 17 of 90 Thermal Conductor Tvye 3 FUEL POOL UNIN Mat Bdry. Thick I Sub- Heat Region (In) (in) I regs. Factor 1 1 01 0.291 1 0 Thermal Conductor Type 4 1 I I _ I Concrete 12" Mat Bdry. Thick Sub- Heat Region # (in) (In) regs. Factor 1 2 0 0.126 1 0 2 2 0.126 0.252 1 0 3 2 0.378 0.504 1 0 4 2 0.882 1.008 1 0 5 2 1.89 2.016 1 0 6 2 3.906 2.0235 1 0 7 2 5.9295 2.0235 1 0 8 2 7.953 1.0785 1 0 9 2 9.0315 1.0785 1 0 10 2 10.11 1.008 1 0 11 2 11.118 0.504 1 0 12 2 11.622 0.252 1 0 13 2 11.874 0.126 1 0 Thermal Conductor Ty _ _ _ _ 1 _ _ 1_ 1 Concrete 18" Mat. Bdry. Thick Sub- Heat Region # (In) (in) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 C 6 2 0.3906 0.4032 1 C 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 9 2 3.21 3 3.2256 1 C 10 2 6.4386 2.89035 1 0 11 2 9.32895 2.89035 1 0 12 2 12.2193 2.09025 1 C 13 2 14.30955 2.09025 I 0 14 2 16.3998 0.8064 _ C 15_ 2 17.2062 0.4032 1 0 16 2 17.6094 0.2016 17_ 2 17.811 0.1008 _
_NO. WS129-PR-02 idPROJECT REPORT PEV. RI 1 ENERCON SERVICES, ECAE O 1o9 Thermal Conductor Type 5 Concrete 18" Mat. Bdry. Thick Sub- Heat Region* _ (In) (in) regs. Factor 18 2 17.9118 0.05041 1 0 19 2 17.9622 0.0252 1 0 20 2 17.9874 0.01261 1 0 Thermal Conductor Type 6 1 I e I I Concrete 23.16 Mat. l Bdry. Thick Sub- Heat Region (in) (in) regs. Factor 1 2 O 0.0126 1 O 2 2 0.0126 0.0252 1_ _ 3 2 0.0378 0.0504 1 O 41 2 0.0882 0.1008 I_ 0O 5_ 2 0.189 0.2016 1 O 6 2 0.3906 0.4032 I O 7 2 0.7938 0.8064 0O 8 2 1.6002 1.6128 0O 9 2 3.213 3.2256 1 O 10 2 6.4386 4.18035 1 O 11_l_ 2 10.61895 4.18035 1 0 12 2 14.7993 2.57385 1 O 13 2 17.37315 2.57385 1 O 14 2 19.947 1.6128 1 O 15 2 21.5598 0.8064 1 O 16 2 22.3662 OA032 I 0 17 2 22.7694 0.2016 1 0
=18 _ 2 22.971 0.1008 1 0 19 2 23.0718 0.0504 1 0 20 2 23.1222 0.0252 1 O 21 2 23.1474 0.0126 1 O Thermal Conductor Type T _I I Concrete 23.36"
[ _ __ _ _- Mat. Bdry. Thick Sub- Heat Region j (in) (in) regs. Factor I 2 O 0.0126 1 O 21 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0
0 NO. WS129-PR-02 LE",PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I__PAGE NO. 19 of 90 Thermal Conductor Type 7 I I I I I
. Concrete 23.36" 7 Mat. Bdry. Thick Sub- Heat Region (in) (in) regs. Factor 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 9 2 3.213 3.2256 1 0 10 2 6.4386 4.23035 1 0 11 2 10.66895 4.23035 1 0 12 2 14.8993 2.62385 1 0 13 2 17.52315 2.62385 1 0 14 2 20.147 1.6128 1 0 15 2 21.7598 0.8064 1 0 16 2 22.5662 0.4032 1 0 17 2 22.9694 0.2016 1 0 18 2 23.171 0.1008 1 0 19 2 23.2718 0.0504 1 0 20 2 23.3222 0.0252 1 0 21 2 23.3474 0.0126 1 0 Thermal Conductor Type Concrete 23.83" Mat. Bdry. Thick Sub- Heat Region (iIn) (In) regs. Factor - 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 3 2 0.0378 0.0504 _1 C 41 2 0.0882 0.1008 a0 5 2 0.189 0.2016 1 a 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 a 9 2 3.213 3.2256 1 10 2 6.4386 8.6957 1 0 11 2 15.1343 8.6957 C 0_
Thermal Conductor Type _____ I . I I __ Concrete 24" Mat. Bdry. Thick Sub- Heat Region 2 (In) (in) regs. Factor 1 2 0 0.126j 0 2 2 0.126 0.252 1 0 3 2 0.378 0.5041 1 0
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ENERCON SERVICES, INC. I I ___I _PAGE NO. 20 of 90 41 2 0.882 1.008 0 5 2 1.89 2.016 1 6 2 3.906 4.032 0 7 2 7.938 4.0155 0 8 2 11.9535 4.0155 0 9 2 15.969 2.0625 1 0 10 2 18.0315 2.0625 0 11 2 20.094 2.016 1 _ 12 2_ 22.11 1.008 1 0 13 2 23.1181 0.5041 1_ 0_ 14 __2_23.6221 0.2521_ 0 15 2 23.874 0.126 1 0 Thermal Conductor Type 10 I I II I Concrete 27.79" Mat. Bdry. Thick Sub- Heat Region # (in) (in) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 _2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 _ 0 7 2 0.7938 0.8064 1 0 8 _ 2 1.6002 1.6128 1 9 2 3.213 32256 1 10 2 6.4386 6.4512 0 11 2 12.8898 3.72505 1 0 12 2 16.61485 3.72505 1 a 13 2 20.3399 2.11855 1 0 141 2 22.45845 2.11855 1 0 15 2 24.577 1.6128 1 0 16 2 26.1898 0.8064 1 0 17 2 26.9962 0.4032 1 0 18 2 27.3994 0.2016 0a 19 2 27.601 0.1008 1 a 20 2 27.7018 0.0504 ___ 21 2 27.7522 0.0252 1 0 22 2 27.7774 0.0126 1 a Thermal Conductor Type 11 Concrete 28.41" Mat. Bdry. l Thick I Sub- Heat Region (in) (In) regs. Factor
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I_ I PAGE NO. 21 of 90 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 X X 0 5 2 0.189 0.2016 1 _ 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 9 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 2 12.8898 7.7601 1 0 12 2 20.6499 7.7601 1 0 Thermal Conductor Type 12 1 l l l l Concrete 32" Mat. Bdry. Thick Sub- Heat Region (in) (in) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 I 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 91 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 2 12.8898 4.77755 1 0 12 2 17.66735 4.77755 1 0 13 2 22.4449 3.17105 1 0 14 2 25.61595 3.17105 1 0 15 2 28.787 1.6128 1 0 16 2 30.3998 0.8064 1 0 17 2 31.2062 0.4032 1 0 18 2 31.6094 0.2016 1 0 19 2 31.811 0.1008 1 0 201 2 31.9118 0.0504 1 0 21 2 31.9622 0.0252 1 0 22 2 31.9874 0.0126 1 0 Thermal Conductor Type 1 3 ( _ _ _ _ _ 1 _ _ I I_ I Concrere 33.98" I Mat. Bdry. Thick Sub- Heat Region (in) (in) regs. Factor 1 2 0 0.0126 1 0
NO. WS129-PR-02 E a PROJECT REPORT pi REV. 1 ENERCON SERVICES, INC. PAGE NO. 22 of 90 21 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 4 2 0.0882 0.1008 1 0 5_ 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 9 ____ _2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 _2 12.8898 10.5451 1 0 121 2 23.4349 10.5451 _1 0 Thermal Conductor Type 14 1 1 YP Concrete 35.12 Mat. Bdry. Thick Sub- Heat Region (in) (in) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 9 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 2 12.8898 5.55755 1 0 12 2 18.44735 5.55755 1 0 13 2 24.0049 3.95105 1 0 14 2 27.95595 3.95105 1 0 15 2 31.907 1.6128 1 0 16 2 33.5198 0.8064 1 0 17 2 34.3262 0.4032 1 0 18 2 34.7294 0.2016 1 0 19 2 34.931 0.1008 1 0 20 2 35.0318 0.0504 1 0 21 2 35.0822 0.0252 1 22 2 35.1074 0.0126 1 0 Thermal Conductor Type Concrete 36" Mat. Bdry. Thick Sub- Heat Region (in) (in) regs. Factor 1 a 0 0.01261 1 0 2 2a 0.0126 0.0252 1 0
NO. WS129-PR-02 PROJECT REPORT II ENERCON SERVICES, INC. REV. 1 PAGE NO. 23 of 90 Thermal Conductor Type Concrete 36" _Mat. Bdry. Thick Sub- Heat Region _ (in) (in) regs. Factor 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 9 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 2 - 12.8898 5.77755 1 0 12 2 18.66735 5.77755 1 0 13 2 24.4449 4.17105 1 0 14 2 28.61595 4.17105 1 0 15 2 32.787 1.6128 1 0 16 2 34.3998 0.8064 I 0 17 2 35.2062 0.4032 1 0 18 2 35.6094 0.2016 1 0 19 2 35.811 0.1008 -1 0 20 2 35.9118 0.0504 1 0 21 2 35.9622 0.0252 1 0 22 2 35.9874 0.0126 1 0 Thermal Conductor Type 16 I I IlIl Concrete 37.04" Mat. Bdry. Thick Sub- Heat Region (in) in) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 X 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 9 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 2 12.8898 6.03755 1 0 12 2 18.92735 6.03755 1 0 13 2 24.9649 4.43105 1 0 14 2 29.39595 4.43105 1 0 15 2 33.827 1.6128 1 0 16 2 35.4398 0.8064 1 0
NO. WS129-PR-02 F5L6 PROJECT REPORT REV.__ ENERCON SERVICES, INC. I _ __I_ _ PAGE NO. 24 of 90 I__ 17 2 36.2462 0.4032 1 0 18 2 36.6494 0.2016 I 0 19 2_ 36.851 0.1008 1 0 20 2 36.9518 0.0504 1 0 21 2. 37.0022 0.0252 1 0 22 21 37.0274 0.0126 1 0 Thermal Conductor Type Concrete 44.26" _mat. Bdry. Thick Sub. Heat Region # (in) (In) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 41 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 - 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 9 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 2 12.8898 7.84255 1 0 12 2 20.73235 7.84255 1 0 13 2 28.5749 4.62325 0C 14 2 33.19815 4.62325 1 0 15 2 37.8214 3.2256 1 C 16 2 41.047 1.6128 1 C 17 2 42.6598 0.8064 1 C 18 2 43.4662 0.4032 1 C 19 2 43.8694 0.2016 1 t 20 2 44.071 0.1008 1 C 21 2 44.1718 0.0504 _ _ C 22 2 44.2222 0.0252 1 0 23 2 44.2474 0.0126 1 C__ Thermal Conductor Type 18 1 1 1 , I Concrete 48" m at Bdry. Thick Sub- Heat Region (In) (In) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0
NO. WS129-PR-02 a PROJECT REPORT . 1 ENERCON SERVICES, INC. I _ __I I__ rPAGE NO. 25 of 90 Thernal Conductor Type 18 Concrete 48" Mat. Bdry. Thick Sub- Heat Region (In) (in)__ regs. Factor 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 91 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 2 12.8898 8.77755 1 0 12 2 21.66735 8.77755 1 0 13 2 30.4449 5.55825 _ 0 14 2 36.00315 5.55825 1 0 15 2 41.5614 3.2256 1 0 16 2 44.787 1.6128 1 0 17 2 46.3998 0.8064 1 0 18 2 47.2062 0.4032 1 t 19 2 47.6094 0.2016 1 0 20 2 47.811 0.1008 _ __ 21 2 47.9118 0.0504 22 2 47.9622 0.0252 1 0 23 2 47.9874 0.01261 0 Thennal Conductor Type Concrete 58.14" Mat. Bdry. Thick Sub- Heat Region # (in) (In) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 _2 1.6002 1.6128 1 0 91 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11i 2 12.8898 12.9024 1 0 12 2 25.7922 8.08695 1 0 13 2 33.87915 8.08695 1 0 14 2 41.9661 4.86765 1 0 15 2 46.83375 4.86765 1 0 16 2 51.7014 3.2256 1 0 17 2 54.927 1.6128 1 0 18 2 56.5398 0.8064 1 0
NO. WS129-PR-02 &K-1 PROJECT REPORT ENERCON SERVICES, INC. PAGE NO. 26of 90 Thermal Conductor Tvye Concrete 58.14" Mat. Bdry. Thick Sub- Heat Region (In) (in) regs. Factor 19 2 57.3462 0.4032 1 0 20 2 57.7494 0.2016 1 0 21 2 57.951 0.1008 1 0 22 2 58.0518 0.0504 1 0 23 2 58.1022 0.0252 1 0 24 2 58.1274 0.0126 1 0 Thermal Conductor Type DW Composite 60" Mat. Bdry. Thick Sub- Heat Region # (In) (In) regs. Factor 1 1 0 0.00324 1 0 2 1 0.00324 0.00648 1 0 3 1 0.00972 0.01296 1 0 4 1 0.02268 0.02592 1 0 5 1 0.0486 0.05184 1 0 6 1 0.10044 0.10368 1 0 7 1 0.20412 0.20736 1 0 8 1 0.41148 0.54426 1 0 9 1 0.95574 0.54426 1 0 10 2 1.5 0.005833333 1 0 11 2 1.5058333 0.011666667 1 0 12 2 1.5175 0.023333333 1 0 13 2 1.5408333 0.046666667 1 0 14 2 1.5875 0.093333333 1 0 15 2 1.6808333 0.18666667 1 0 16 2 1.8675 0.37333333 1 0 172 2.2408333 0.74666667 1 0 18 2.9875 1.4933333 1 0 19 2 4.4808333 2.9866667 1 0 202 7.4675 5.9733333 1 0 21 2 13.440833 11.946667 1 0 22 2 25.3875 8.653125 1 0 231 2 34.040625 8.653125 1 0 241 2 42.69375 5.433825 1 0 25 2 48.127575 5.433825 1 0 26 2 53.5614 3.2256 1 0 27 2 56.787 1.6128 1 0 28 2 58.3998 0.8064 1 0 29 2 59.2062 0.4032 1 0 1 301 2 59.6094 0.2016 1 0
NO. WS129-PR-02 I§, PROJECT REPORT B:1 REV. __ ENERCON SERVICES, INC. _____I__ PAGE NO. 27 of 90 Thermal Conductor Type 20 DW Composite 60" Mat Bdry. Thick Sub- Heat Region (in) (in) regs. Factor 31 2 59.811 0.1008 1 0 32 2 59.9118 0.0504 1 0 33 2 59.9622 0.0252 1 0 34 2 59.9874 0.0126 1 0 Thermal Conductor Type 21 l - l l _ Concrete 60" Mat Bdry. Thick Sub- Heat Region # (In) (in) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 I 0 8 2 1.6002 1.6128 1 0 9 2 3.213 3.2256 1 0 10 2 6.4386 6A.512 1 11 2 12.8898 12.9024 _ 0 12 2 25.7922 8.55195 1 0 13 2 34.34415 8.55195 1 O 14 2 42.8961 5.33265 1 0 15 2 48.22875 5.33265 1 0 16 2 53.5614 3.2256 1 0 17 2 56.787 1.6128 1 0 18 2 58.3998 0.8064 1 0 19 2 59.2062 0.4032 1 0 20 2 59.6094 0.2016 1 0 21 2 59.811 0.1008 1 0 22 2 59.9118 0.0504 1 0 23 2 59.9622 0.02521 1 0 24 2 59.9874 0.0126 _ 0 Thermal Conductor Type 22 1] I__ I______ OW~~Com posite 61.37" _ _ _ __ _ _ _ Mat. Bdry. Thick Sub- Heat Region# (in) (04) regs. Factor 11 01 0.00320 1 0
NO. WS129-PR-02 11 1 wPROJECT REPORT REV. ENERCON SERVICES, INC. II_ I_PAGE NO. 28 of 90 Thermal Conductor Tvoe 22 _ W Composite 61.37" Mat. Bdry. Thick Sub- Heat Region (In) (in) mos. Factor 21 1 0.00324 0.00648 1 0 3 1 0.00972 0.01296 1 0 4 1 0.02268 0.02592 1 0 5 1 0.0486 0.05184 1 0 6 _1 0.10044 0.10368 X 1 0 71 1 0.20412 0.20736 1 0 8 1 0.41148 0.54426 1 0 9 1 0.95574 0.54426 1 l 10 2 1.5 0.005833333 0t 11 2 1.5058333 0.011666667 1 0 12 2 1.5175 0.023333333 1 0 13 2 1.5408333 0.046666667 1 l 14 2 1.5875 0.093333333 1 0 15 2 1.6808333 0.18666667 1 l 16 2 1.8675 0.37333333 1 0 17 2 2.2408333 0.74666667 1 l 18 2 2.9875 1.4933333 1 0 19 2 4.4808333 2.9866667 _1 20 2 7.4675 5.9733333 1 0 21 2 13.440833 11.946667 1 l 221 2 25.3875 8.995625 1 0 23 2 34.383125 8.995625 0l 24 2 43.37875 5.776325 1 0 25 2 49.155075 5.776325 1 l 26 2 54.9314 3.2256 1 l 27 2 58.157 1.6128 1 0 28 2 59.7698 0.8064 1 0 29 2 60.5762 0.4032 1 0 30 2 60.9794 0.2016 1 0 31 2 61.181 0.1008 I1 0 32 2 61.2818 0.0504 1 C 33 2 61.3322 0.0252 _1 341 2 61.3574 0.0126 ___ C Thermal Conductor Type l 23 L[T I I_ _ Concrete 62.55" l_ _ Mat Bdry. Thick Sub- Heat Region l (in) (in) regs. Factor 1_ 2 0 0.0126 1 0 2_ 2 0.0126 0.0252 1 0 3_ 2 0.0378 0.0504 1 0
NO. WS129-PR-02 E 1 PROJECT REPORT 4SS REV. 1 ENERCON SERVICES, INC. I __I I__ PAGE NO. 29 of 90 Thermal Conductor Type 23 1 l l l Concrete 62.55" Mat. Bdry. Thick Sub- Heat Region (in) (In) regs. Factor 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 9 2 3.213 3.2256 1 0 10 2 6A386 6.4512 1 0 11 2 12.8898 12.9024 1 0 12 2 25.7922 9.18945 1 0 13 2 34.98165 9.18945 1 0 14 2 44.1711 5.97015 1 0 15 2 50.14125 5.97015 1 0 16 2 56.1114 3.2256 1 0 17 2 59.337 1.6128 1 0 18 2 60.9498 0.8064 1 O0 19 2 61.7562 0.4032 1 0 20 2 62.1594 0.2016 1 0 21 2 62.361 0.1008 1 0 22 2 62.4618 0.0504 1 0 23 2 62.5122 0.0252 0 24 2 62.5374 0.0126 1 0
NO. WS129-PR-02 PROJECT REPORT. lwREV. 1 ENERCON SERVICES, INC. I__ _PAGE NO. 30 of 90 Thermal Conductor Type 24 1 l I WW Composite 64.06" l Mat. Bdry. Thick Sub- Heat Region (in) (in) fogs. Factor 1 1 0 0.00324 1 0 2 1 0.00324 0.00648 1 0 3 1 0.00972 0.01296 1 0 4 1 0.02268 0.02592 1 0 5 1 0.0486 0.05184 1 0 6 1 0.10044 0.10368 1 0 7 1 0.20412 0.20736 1 0 8 __ 1 41148 0I. 0.54426 1 0 91 1 0.95574 0.54426 1 0 10 6 1.5 0.000483333 1 0 11 6 1.5004833 0.000966667 1 0 12 6 1.50145 0.001933333 1 0 13 6 1.5033833 0.003866667 1 0 14 6 1.50725 0.007733333 1 0 151 6 1.5149833 0.015466667 1 0 161 6 1.53045 0.030933333 1 0 171 6 1.5613833 0.061866667 1 0 18 6 1.62325 0.12373333 1 0 19 6 1.7469833 0.24746667 1 0 20 6 1.99445 0.49493333 1 0 21 6 2.4893833 0.31515417 1 0 22 6 2.8045375 0.31515423 1 0 23 6 3.1196917 0.26827917 1 0 24 6 3.3879709 0.26827922 1 0 25 6 3.6562501 0.09374995 1 0 26 7 3.75 0.075 1 0 27 7 3.825 0.11875 1 0 28 7 3.94375 0.059375 1 0 29 7 4.003125 0.059375 1 0 30 2 4.0625 1.1314655 1 0 31 2 5.1939655 2.262931 1 0 32 2 7.4568965 4.5258621 1 0 33 2 11.982759 9.0517241 1 0 34 2 21.034483 10.75638 1 0 35 2 31.790863 10.756379 1 0 36 2 42.547242 7.537079 1 0 37 2 50.084321 7.537079 1 0 38 2 57.6214 3.2256 1 0 39 2 60.847 1.6128 1 0 40 2 62.4598 0.8064 1 0 41 2 63.2662 0.4032 1 0 42 2 63.6694 0.2016 1 0
NO. WS129-PR-02 Ed ft PROJECT REPORT REV. ENERCON SERVICES, INCR I I PAGE NO. 31 of 90 Thermal Conductor Type 24 111 , WW Composite 64.06" Mat. Bdry. Thick Sub- Heat Region _ (in) (in) regs. Factor 43 2 63.871 0.1008 1 0 44 2 63.9718 0.0504 1 0 45 2-64.0222 0.0252 1 0 46 2 64.0474 0.0126 1 0 Thermal Conductor Type 25 1 1 1I 1 Concrete 72" Mat. Bdry. Thick Sub- Heat Region # (in) (in) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0 4 2 0.0882 0.1008 1 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0
. 2 1.6002 1.6128 1 0 el 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 2 12.8898 12.9024 1 0 12 2 25.7922 11.55195' 0 13 2 37.34415 11.55195 1 _
14 2 48.8961 8.33265 1 0 15 2 57.22875 8.33265 1 0 16 2 65.5614 3.2256 1 0 17 2 68.787 1.6128 1 0 18 2 70.3998 0.8064 _ _ 19 2 71.2062 0.4032 1 0 20 2 71.6094 0.2016C 0 21 2 71.811 0.1008 1 0 22 2 71.9118 0.0504 1 C 23 2 71.9622 0.0252 1 0 24 2 71.98741 0.0126 1 0 Thermal Conductor Type 26 _ - _ _ _ _r I Composite 72" Mat Bdry. Thick Sub- Heat Regson (in) (in) regs. Factor 1 1 l0 0.003240 1 C1
AM NO. WS129-PR-02 q.n PROJECT REPORT htREV. _ _ _ ENERCON SERVICES, INC. II _PAGE NO. 32 of 90 Thermal Conductor Type 26 Composite 72_ Mat. Bdry. Thick Sub- Heat Region # (in) (in) regs. Factor 2 1 0.00324 0.00648 1 0 3 1 0.00972 0.01296 1 0 4 1 0.02268 0.02592 1 0 5 1 0.0486 0.05184 1 0 6 1 0.10044 0.10368 1 0 7 1 0.20412 0.20736 1 0 8 1 0.41148 0.54426 1 0 9 1 0.95574 0.54426 1 0 10 2 1.5 0.005833333 1 0 11 2 1.5058333 0.011666667 1 0 12 2 1.5175 0.023333333 1 0 13 2 1.5408333 0.046666667 1 0 141 2 1.5875 0.093333333 1 0 15 2 1.6808333 0.18666667 1 0 16 2 1.8675 0.37333333 1 0 17 2 2.2408333 0.74666667 1 0 18 2 2.9875 1.4933333 1 0 19 2 4.4808333 2.9866667 1 C 201 2 7.4675 5.9733333 1 C 21 2 13.440833 11.946667 1 C 22 - 2 25.3875 11.675625 C 0 23 2 37.063125 11.675625 1 0 24 2 48.73875 8.456325 1 0 25 2 57.195075 8.456325 C 0 26 2 65.6514 3.2256 1 C 27 2 68.877 1.6128 1 0 28 2 70.4898 0.8064 1 0 29 2 71.2962 0.4032 1 0 30 2 71.6994 0.2016 1 0 31 2 71.901 0.1008 1 0 32 2 72.0018 0.0504 1 0 33 2 72.0522 0.02521 1 0 34 2 72.0774 0.0126 1 0 Thermal Conductor Type 27 1_ 1 I I Concrete 102" Mat. Bdry. Thick Sub- Heat Region # (in) (In) regs. Factor 1 2 0 0.0126 1 0 2 2 0.0126 0.0252 1 0 3 2 0.0378 0.0504 1 0
I; NO. WS129-PR-02 Fug PROJECT REPORT REV. 1 FNERCON SERVICES, INC. _ _ __ PAGE NO. 33 of 90 Thermal Conductor Type 27
-_ Concrete 102" Mat. Bdry. Thick Sub- Heat Region (In) (in) regs. Factor 4 2 0.0882 0.1008 I 0 5 2 0.189 0.2016 1 0 6 2 0.3906 0.4032 1 0 7 2 0.7938 0.8064 1 0 8 2 1.6002 1.6128 1 0 9 2 3.213 3.2256 1 0 10 2 6.4386 6.4512 1 0 11 2 12.8898 12.9024 1 0 12 2 25.7922 19.05195 1 0 13 2 44.84415 19.05195 1 0 14 2 63.8961 12.60705 1 0 15 2 76.50315 12.60705 1 0 16 2 89.1102 6.4512 1 0 17 2 95.5614 3.2256 1 0 18 2 98.787 1.6128 1 0 19 2 100.3998 0.8064 1 0 20 2 101.2062 0.4032 1 0 21 2 101.6094 0.2016 1 0 22 2 101.811 0.1008 1 0 23 2 101.9118 0.0504 1 0 24 2 101.9622 0.0252 1 0 25 2 101.9874 0.0126 1 0
I -Y NO. WS129-PR-02 l PROJECT REPORT I W REV. I ENERCON SERVICES, INC. I___PAGE NO. 34 of 90 Thermal Conductor Type 28 l 28___ _Composite 154.86" Mat B Thick Sub- Heat Region (in) (in) regs. Factor 1 1 0 0.00324 1 0 2 1 0.00324 0.00648 1 0 3 1 0.00972 0.01296 C0 4 1 0.02268 0.02592 0 5 1 0.0486 0.05184 1 0 6 1 0.10044 0.10368 1 0 7 1 0.20412 0.20736 1 0 8 1 0.41148 0.54426 1 0 9 1 0.95574 0.54426 1 0 10 6 1.5 0.000483333 1 0 11 6 1.6004833 0.000966667 1 0 12 6 1.50145 0.001933333 1 0 13 6 1.5033833 0.003866667 1 0 14 6 1.50725 0.007733333 1 0 15 6 1.5149833 0.015466667 1 0 16 6 1.53045 0.030933333 1 0 17 6 1.5613833 0.061866667 1 C 18 6 1.62325 0.12373333 1 0 19 6 1.7469833 0.24746667 1 0 20 6 1.99445 0.49493333 1 0 21 6 2.4893833 0.31515417 1 0 22 6 2.8045375 0.31515423 1 0 23 6 3.1196917 0.26827917 1 0 24 6 3.3879709 0.26827922 1 0 25 6 3.6562501 0.09374995 1 0 26 7 3.75 0.075 1 0 27 7 3.825 0.11875 1 0 28 7 3.94375 0.11875 1 0 29 2 4.0625 1.1314655 1 0 30 2 5.1939655 2.262931 1 0 31 2 7.4568965 4.5258621 1 0 32 2 11.982759 9.0517241 1 0 33 2 21.034483 18.103448 1 _ 0 34 2 39.137931 18.103448 0 35 2 57.241379 18.103449 1 0 36 2 75.344828 19.878793 1 0 37 2 95.223621 19.878789 10 38 2 115.10241 13.433893 0 391 2 128.5363 13.433897 1 0 40 2 141.9702 6.451204 1 0 41 2 148A214 3.225604 1 0 42 2 151.647 1.612804 1 0
NO. WS129-PR-02 OW.H PROJECT REPORT 61: -REV. 1 ENERCON SERVICES, INC. I I_PAGE NO. 35 of 90 Thermal Conductor Type 28 1 1 1 l Composite 154.86" Mat. Bdry. Thick Sub- Heat Region (in) (in) regs. Factor 43 2 153.2598 0.806404 1 0 44 2 154.0662 0.403204 1 0 45 2 154.4694 0.201604 1 0 46 2 154.671 0.100804 1 0 47 2 154.7718 0.050404 1 0 48 2 154.8222 0.025204 1 0 49 2 154.8474 0.012604 1 0
ATgB NO. WS129-PR-02 19i 111 PROJECT REPORT
~REV. 1 ENEDRCON SERVICES, INC.
I FAGE NO. 36 of 90 Thermal Conductor Tvoe 29 RefuelFIWall Mat. Bdry. Thick Sub- Heat Region (In) (In) regs. Factor 1 1 0 0.049 1 0 2 7 0.049 0.0000348 1 0 3 7 0.0490348 0.0000696 1 0 4 7 0.0491044 0.0001392 1 0 5 7 0.0492436 0.0002784 1 0 6 7 0.049522 0.0005568 1 0 7 7 0.0500788 0.0011136 1 0 8 7 0.0511924 0.0022272 1 0 9 7 0.0534196 0.0044544 1 0 10 7 0.057874 0.0089088 1 0 11 7 0.0667828 0.0178176 1 0 12 7 0.0846004 0.0356352 1 0 13 7 0.1202356 0.0712704 1 0 14 7 0.191506 0.1425408 1 0 15 7 0.3340468 0.2850816 1 0 16 7 0.6191284 0.2324679 1 0 17 7 0.8515963 0.2324679 0 18 7 1.0840642 0.1612149 1 0 19 7 1.2452791 0.1612149 1 0 20 7 1.406494 0.0712704 10 21 7 1.4777644 0.0356352 1 0 22 7 1.5133996 0.0178176 1 0 23 7 1.5312172 0.0089088 1 0 24 7 1.540126 0.0044544 1 0 25 7 1.5445804 0.0022272 1 0 26 7 1.5468076 0.0011136 1 0 27 7 1.5479212 0.0005568 1 0 28 7 1.548478 0.0002784 1 0 29 7 1.5487564 0.0001392 1 0 30 7 1.5488956 0.0000696 1 0 31 7 1.5489652 0.0000348 1 0 32 1 1.549 _0.04_ 1- C
PJ RNO. WS129-PR-02 WS PROJEC REPORT I_______ REV. _ ENERCON SERVICES, INC. _ _ _ _ _ _ _ _ _I PAGENO. 37of90 Thermal Conductor Type 30IIII RefuelFIRoof Mat. Bdry. Thick Sub- Heat Region (in) (In) regs. Factor 1 1 0 0.049 1 0 Thermal Conductor Type 31 l Concrete 35.1 Mat. Bdry. Thick Sub- Heat Region (In) (In) regs. Factor 1 2 0 0.00648 1 0 2 2 0.00648 0.01296 1 0 3 2 0.01944 0.02592 1 0 4 2 0.04536 0.05184 1 0 5 2 0.0972 0.10368 1 0 6 2 0.20088 0.20736 1 0 7 2 0.40824 0.41472 1 0 8 2 0.82296 0.82944 1 0 9 2 1.6524 1.65888 1 0 10 2 3.31128 3.31776 1 0 11i 2 6.62904 6.63552 1 0 12 2 13.26456 5.45886 1 0 13 2 18.72342 5.45886 1 0 14 2 24.18228 3.80322 1 0 15 2 27.9855 3.80322 1 0 16 2 31.78872 1.65888 1 0 17 2 33.4476 0.82944 1 0 181 2 34.27704 0.41472 0 191 2 34.69176 0.20736 10 20 2 34.89912 0.10368 0 211 2 35.0028 0.05184 1 0 22 _ 2 35.05464 0.02592 1 0 23 2 35.08056 0.01296 1 0 24 2 35.09352 0.00648 1 0
*, PROJECT REPORT REV. 1 RNERCON SERVICES, INC.
PAGENO. 38of90 CoolerlHeater Heater On Off Flow Flow Heat Heat Cooler Vol. Trip Trip Rate Rate Rate Rate Phs Ctrlr Description # # (CFM) FF (Btu/s) FF Opt Loc IH Main Building Heat 1 5 _ _ 43.24 VTI W I 2H Decay Heat 5 5 2720.56 LTI 5 3C RRA-CC-1 4 1 1 37 VTE 4 4C RRA-CC-4 4 1 1 38 VTE 4 5C RRA-CC-5 4 1 1 39 VTE 4 6C RRA-CC-6 4 1 0 5 VTE 4 7C RRA-CC-1 1 22 41 WVTE 1 8C RRA-CC-12 1 22 1 42 VTE 1 90 RRA-CC-13 1 22 . 1 43 VTE. 1 10C RRACC-1 5,17 1 22 2 44 VTE 1 11C RRA-CC-19,20 1 22 2 45 VTE I 12H Aux Heat 522 1 6 7 190 VTE I 13H Aux Heat 548 1 8 9 100 VTE 1 14H Aux Heat 572 1 10 11 50 VTE I 15H AuxHeat 548 1 12 13 100 VTE I 16H Aux Heat 572 1 14 15 50 VTE 1 17H Aux Heat 522 1 16 17 190 VTE I 18H Aux Heat 501 1 18 19 200 WV1E I 19H Aux Heat 471 1 20 21 200 VTE 1 20H Emergency Lighting 1 25 43.4 1 VTI 1 21 H Auxiliary Heat 1 22 10.95 1 VTI 1 22H Dry Cask 5 5 _ 21.8 VTI 5 23H Pump Heat 4 24 _ 244.5 _VTI 4 24H Fuel Pool HX Rm 1 3_ 4.37 _VTI 1
NO. WS129-PR-02 E B PROJECT REPORT %aREV. 1 ENERCON SERVICES, INC. PAGE NO. 39 of 90 Cooler/Heater Heater On Off Flow Flow Heat Heat Cooler Vol. Trip Trip Rate Rate Rate Rate Phs Ctrlr Description _ # (CFM) FF (Btuls) FF Opt Loc 25H Pump Room Fans 4 1 12.1 VTI 4 26H Normal Lighing 1 26 0 1 27 VTI I 27H SGTS Heater 2s2 27 28 19.9_ Vrl 2s2 28H SGTS Fan Motor 1 .2 _ 1.9441 VI 1
j NO. WS129-PR-02 PROJECT REPORT ENI_ 0 SERVICES, INC. RE GEN PAGE NO. 40 of 90 Volumetric Fan - Table I
- Vol I Flow On Off Min Max Fan Path Trip Trip DP DP Description # # # (psi) (psi) 1Q SGTS Fan 11 2 DEFAULT DEFAULT Volumetric Fan -Table 2 Vol Flow Flow Heat Heat Fan Flow Rate Rate Heat Rate Rate Disch
# Option (CFM) FF Option (Btuls) FF Vol a
a DP 1 48 Flow 1 46 6 Heat Exchangers - Table I Heat HX PrIm Scnd Cpid Drain Ex. Type Flow Flow HX Vol
# Description # Path Path #
1H Fuel Pool Cooler 1 7 SPEC - _ DISCARD Heat Exchangers - Table 2 Heat Scnd lScnd Scnd Scndt Ext. Ext. Ext. l Ext. lOp. Op. 1H [ Ex. l Flow (Ibmns) 79.503 Flow Temp Temp l FF l (F) l FF 1 46 Flow (Ibmisb ) Flow FF Heat l (Btuls) l Heat FF Pres Pres (psla) FF Heat Exchanger Types - Tablel HX l lPassesl Tube l Thick l Wall Type or Mat. nessl Area I I Option IZones I I (In) I (ft2) I TUBE-SHELL 2 4 0.051 582.
IJ P NO. WS129-PR-02 I PROJECI REDPORT REV. 1 ENERCON SERVICES, INC. I_ PAGE NO. 41 of 90 Heat Exchanger Types - Table 2 HX Flow Hyd. Tot. S. H.T. H.T. Foullng Type Fin Area Diam. Area Coef Coef Resistance
# Side Type (ft2) (In) (ft2) Curv Type (h-f2-F/B) 1 primary NONE 0.377 0.75 625 17 NUSSELT 0.0002487 SECONDARY NONE 0.216 0.649 540.493 16 NUSSELT C_
Heat Exchanger Types - Table 3 Fin Parameters HX Fin Pin Thick- Surf. Film Type Mat. Diam. Length ness Area Thick Side Type # (in) (in) (in) (ft2) Mult. I PRIMARY C0 01 0 0 0 1 secondary 0 0 0 0 0 1 Volume Initial Conditions Total _ Vapor lLquid Relative Liquid Ice Ice Vol Pressure Temp. Temp. Humidity Volume Volume Surf.A.
# (psla) (F) F ( Fract. Fract. (f2) def 14.7 75 104 60 0 0 0 1 14.63549 75 75 60 0 0 0 2 14.60724 75 75 60 0 0 0 3 30 104 104 100 1 0 0 4 14.67533 75 75 60 0 0 0 5 14.57722 75 125 60 0.03541 0 0
PR C ENO. WS129-PR-02
. -Ul PROJECT RE3PORT "Ma REV. 1 ENERCON SEIRVCES, INC.
PAGE NO. 42 of 90 Initial Gas Pressure Ratios l Vo Air
# Gas I Gas 2 Gas 3 Gas 4 Gas 5 Gas 6 Gas 7 Gas 8 De 1 0 0 0 0 0 0 0 f
1 O 0 0 0 0O 0 2 1 0 0 0 0 0 0 0
-3 0 0 0 0 0. 0 0 0 4 1 0 0 0 0 0 0 0 5 1 0 0 0 0 0 0 0 Noncondensing Gases Gas l Descriptlon l Symbol Type Mol. Lennard-Jones Parameters No. Weight Diameter elK (Ang) _ (K)
I Alr Air POLY 28.97 3.617 97 Noncondensing Gases - CpMsc. Equatlons Gas Cp Equatlon (Required) Visc. Equation (Optional) No. Tmin Tmax Cp Tmin Tmax Viscosity (R) (R) (Btuflbm-R) (R) (R) (Ib7/ft-hr) 1 360 2880 0.238534-6.20064e-*T+2.1 3043E-8--2-4.2o247E-1 2T= -
Materials Type # Decription Gap 1 CARBON STEEL NO 2 CONCRETE NO 3 FIBERBOARD NO 4 COPPER TUBE NO 5 CALCIUM SILICATE NO 6Poly Urthne NO 7 FIBERGLASS NO
C) NO. WS129-PRR-2 E' u PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I PAGE NO. 44of90 Material Type
~CARBON STEEL Temp. Density Cond. Sp. Heat (F) (Ibmft3) (Btuthr-ft-F) (Btullbm-F) 75 490 26 0.11 Material Type 2 71 _l 1 CONCRETE Temp. Density Cond. Sp. Heat (Ibmfft3) (Btulhr-ft-F) (Btunlbm-F) 75 144 0.541 0.2 Material Type FIBERBOARD Temp. Density Cond. Sp. Heat (F l (Ibm~ft3) (Btu/hr-ft-F) (Btutlbm-F) 75 3.25 0.0221 0.2 Materlal Type 4 ] 1 COPPER TUBE Temp. Density Cond. Sp. Heat (F) (bmlt3) (Btuthr ft-F) (BtunIbm-F) 32 488 8 0.11 212 488 9.4 0.11 572 488 10.9 0.11 932 488 12.4 0.11
N"I NO. WS129-PR-02 I PROJECT REPORT qz. REV. 1 ENERCON SERVICES, INC. PAGE NO. 45of90 Material Type
._ CALCIUM SILICATE Temp. Density Cond. Sp. Heat (F) (Ibmfft3) (Btulhr-ft-F) (Btullbm-F) 0 15 0.0375 0.201 200 15 0.0375 0.201 300 15 0.0417 0.201 400 15 0.0458 0.201 500 15 0.05 0.201 600 15 0.055 0.201 Material Type Poly Urithane Temp. Density Cond. Sp. Heat (F) (Ibmlft3) (Btulhr-ft-F) (Btullbm-F) 32 75 0.11 0.48 Material Type 7 1 ' ~ I FIBERGLASS Temp. Density Cond. Sp.Heat (F) (Ibmtft3) (Btulhr ft-F) (Btu/lbm-F) 321 0.0291 0.21 Ice Condenser Parameters Initial Bulk Surface Area l Heat Temp. Density Multiplier 1 Transfer (F) (Ibm/ft3) Function Option 15 33.43 UCHIDA
NO. WS129-PR-02 PROJECT REPORT REV. 1 ENERCON SERVICES, INC. PAGE NO. 46 of 90 Intentionally Left Blank
NO. WS129-PR-O2 PROJECT REPORT 69REV. _ _ _ ENERCON SERVICES, INC. II I_PAGE NO. 47 of 90 Comoonent Trips Trip Sense Sensor Sensor Var. Set Delay Reet I Cond Cond Description Var. I Loc. 2 Loc. Limit Point Time Trip Trip Type I Start Pump Room Coolers TIME UPPER 300 0 AND 2 Start SGTS TIME UPPER 120 0 - AND 3 Start FP Cooler TIME UPPER 43200 0 AND 4 HVAC Isolation TIME UPPER 15 0 AND 5 Heat Load Starts TIME UPPER 0.1 0 AND 6 AH12H On GAS TEMP I LOWER 68 1E+60 7 AND 7 AH12H Off GAS TEMP I UPPER 70 0 6 AND 8 AH13H On GAS TEMP 1 LOWER 74 1E+60 9 AND 9AH13H Off GASTEMP I UPPER 77 0 8 AND 10 AH14H On GASTEMP I LOWER 71 1E+60 11 -AND 11 AH14H Off GASTEMP _ 1 UPPER 73 0 10 AND 12 AHI5H On GASTEMP 1 LOWER 70 1E460 13 AND 13 AHM5H Off GASTEMP 1 UPPER 73 0 12 AND 14 AH16H On GASTEMP . 1 LOWER 62 IE+60 15 AND 15 AH16H Off GASTEMP 1 UPPER 64 0 14 AND 16 AH17H On GASTEMP _ _ LOWER 70 IE+60 17 AND 17 AH17H Off GAS TEMP 1 UPPER 73 0 16 AND 18 AH18H On GAS TEMP I LOWER 711 IE+60 19 AND 19 AH18H Off GAS TEMP 1 UPPER 73 0 18 AND 20 AH19H On GAS TEMP 1 LOWER 73 1E+60 21 AND 21 AH19H Off GAS TEMP I UPPER 75 0 20 AND 22 Main Building Coolers TIME UPPER 300 0 AND 23 OPEN REAIROA TIME UPPER 1000000 I E+60 _ AND 24 Pump Heat TIME UPPER 30 0 AND 25 Emergency Lighting TIME UPPER 0.1 0 . AND 26 Ensure OFF TIME . UPPER 3600 0 AND 27 SGTS Heater On GAS TEMP 2s1 LOWER 225 0 28 2 AND 28 SGTS Heater Off GAS TEMP 2s1 _UPPER 245 0 27 -AND
F= 2PROJECT REPORT NO. WS129-PR-02 REV. 1 ENERCON SERVICES, INC. I__ I___ PAGE NO. 48 of 90 Functions FF# Description Ind. Var. Dep. Var. Points 0 Constant 0 1 Normal Heat Load Ind. Var. Dep. Var. 3 2 RRA-FC-1,2,3 T vs Ht Rate Ind. Var. Dep. Var. 42 3 RRA-FC-4 T vs Ht Rate Ind. Var. Dep. Var. 42 4 RRA-FC-5 T vs Ht Rate Ind. Var. Dep. Var. 42 5 RRA-FC-6 T vs Ht Rate Ind. Var. Dep. Var. 27 6 RRA-FC-8,9 T vs Heat Rate Ind. Var. Dep. Var. 26 7 RRA-FC-10,11 T vs Heat Rate Ind. Var. Dep. Var. 42 8 RRA-FC-12 T vs Heat Rate Ind. Var. Dep. Var. 42 9 RRA-FC-13,14 T vs Heat Rate Ind. Var. Dep. Var. 42 10 RRA-FC-15,17 T vs Heat Rate Ind. Var. Dep. Var. 42 11 RRA-FC-1 9,20 T vs Heat Rate Ind. Var. Dep. Var. 42 12 SGT Flow vs DP Ind. Var. Dep. Var. 14 13 SGT Heat Rate Ind. Var. Dep. Var. 11 14 PC Temperature Ind. Var. Dep. Var. 131 15 Coeff Ind. Var. Dep. Var. 4 16 Nu Tube Side Ind. Var. Dep. Var. 28 17 Nu Shell Side Ind. Var. Dep. Var. 29 18 Cont Heat Transfer cv4 Dep. Var. 2 19 Fuel Pool Flow Ind. Var. Dep. Var. 4 20 Upper Leak Flow cv12 Dep. Var. 2 21 Lower Leak Flow cv15 Dep. Var. 2 22 Wetwell Pool Temp Ind. Var. Dep. Var. ___ 23 Fuel Pool Temp cv17 Dep. Var. 2 24 ECCS Pipe Temp cv19 Dep. Var. 2 25 Norm Pwr Decay cv27 Dep. Var. 2 26 RRAFC123 87F Ind. Var. Dep. Var. 42 27 RRAFC4 87F Ind. Var. Dep. Var. 42 28 RRAFC5 87F Ind. Var. Dep. Var. 42 29 RRAFC8, 9 84F Ind. Var. Dep. Var. 26 30 RRAFC10,11 87F Ind. Var. Dep. Var. 42 31 RRAFC1 2 87F Ind. Var. Dep. Var. 42 32 RRAFC13,14 87F Ind. Var. Dep. Var. 4 33 RRAFC15,17 87F Ind. Var. Dep Var. 42 34 RRAFC1 9, 20 87F Ind. Var. Dep. Var. 42 35 RRAFC123Cont cv28 Dep. Var. 2 36 RRAFC4Cont cv31 Dep. V2r. 2 37 RRAFC5Cont cv34 Dep. Var. 2 38 RRAFC89Cont cv37 Dep. Var. 2 39 RRAFC1 011 Cont cv40 Dep. Var. 2 40 RRAFC12Cont cv43 Dep. Var. 2 41 RRAFC1314Cont cv46 Dep. Var. 2 42 RRAFC1517Cont cv49 Dep. Var. 2 43 RRAFC192OCont cv52 Dep. Var. 2
NO. WS129-PR-02 E w PROJECT REPORT
.u REV. 1 ENERCON SERVICES, INC.
I_ __I_ _ _ PAGE NO. 49 of 90 Functions FF# Description jnd. Var. Dep. Var. Points 44 Pool Temp Simple Time (sec) Temperature (F) 4 45 SGTS Start Time Ind. Var. Dep. Var. 6 46 SGTS Fan Heat cv6O Dep. Var. 2 47 SGTS 0% Ind. Var. Dep. Var. -18 48 SGTS Flow Select 1cv58 Dep. Var. 2 Function II Normal Heat Load Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 1 3600 1 10000000 Function 2 T RRA-FC-1,2,3 T vs Ht Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 78 0 80 2.07 82 4.14 84 6.19 86 8.25 88 10.31 90 12.36 92 14.42 94 16.47 96 18.5 98 20.56 100 22.61 102 24.64 104 26.67 106 28.61 108 30.83 110 32.78 112 34.72 114 36.94 116 38.89 118 40.83 120 42.78 122 45 124 46.94 126 48.89 128 50.83 130 52.78 132 55 134 56.94 136 58.89 138 60.83 140 62.78 142 64.72 144 66.94 146 68.89 148 70.83 150 72.78 152 74.72 154 76.67 156 78.61 158 80.56
NO. WS129-PR-02 4 - PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I_ PAGE NO. 50 of 90 Function 3 RRA-FC-4 T vs Ht Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 78 0 80 4 82 7.97 84 11.94 86 15.89 88 19.83 90 23.78 92 27.72 94 31.67 96 35.56 98 39.44 100 43.33 102 47.22 104 51.11 106 55 108 58.89 110 62.5 112 66.39 114 70.28 116 74.17 118 77.78 120 81.67 122 85.56 124 89.17 126 93.06 128 96.67 130 100.56 132 104.17 134 107.78 136 111.67 138 115.28 140 118.89 142 122.78 144 126.39 146 130 148 133.61 150 137.22 152 140.83 154 144.44 156 148.06 158 151.67 Function 4 1~ 1A I RRA-FC-5 T vs Ht Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 78 0 80 2.86 82 5.72 84 8.58 86 11.A2 88 14.25 90 17.11 92 19.94 94 22.75 96 25.58 98 28.33 100 31.11 102 33.89 104 36.94 106 39.72 108 42.5 110 45.28 112 48.06 114 50.83 116 53.61 118 56.39 120 59.17 122 61.67
L ENERCON SERVICES, INC PROJECT REPORT jEV. NO. WS129-PR-02 9 IPAGE NO. 51 of 90 Function 4 RRA-FC.5 T vs Ht Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 124 64.44 126 67.22 128 70 130 72.78 132 75.56 134 78.33 136 80.83 138 83.61 140 86.39 142 89.17 144 91.67 146 94.44 148 97.22 150 99.72 152 102.5 154 105.28 156 107.78 158 110.56
"911!LNOQ WS129-PR-O2 .- 1% PROJECT REPORT %aREV. I ENERCON SERVICES, INC.
I___ I___PAGE NO. 52 of 90 Function 5. RRA-FC-6 T vs Ht Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 78 0 90 8.030555556 95 11.36388889 100 14.69166667 105 18.01111111 110 21.32222222 115 24.63055556 120 27.91666667 125 31.2222222 130 34.5 135 37.77777778 140 41.05555556 145 44.30555556 150 47.58333333 155 50.83333333 160 54.05555556 165 57.30555556 170 60.52777778 175 63.75 180 66.97222222 185 70.16666667 190 73.38888889 195 76.58333333 200 79.77777778 205 82.94444444 210 86.111111111 1 Function 6 RRA-FC-8,9 T vs Heat Rate Ind. Var.: Dep. Var.:. Ind. Var. Dep. Var. Ind. Var. Dep. Var. O O 84 O 8_ 1.074166667 90 6.433333333 95 11.775 100 17.1 105 22.40555556 110 27.69166667 115 32.97222222 120 38.22222222 125 43.44444444 130 48.66666667 135 53.86111111 140 59.02717778 145 64.19444444 150 69.33333333 155 74.47222222 160 79.58333333 165 84.66666667 170 89.75 175 94.80555556 180 99.83333333 185 104.8611111 190 109.8611111 195 114.8611111 200 119.8333333
ZL k! PROJECT REPORT NO. WS129-PR-02 REV. ENERCON SERVICES, INC. I _ __I_ _PAGE NO. 53 of 90 Function 7 I I RRA-FC-10,11 T vs Heat Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 78 0 80 2.15 82 4.3 84 6.45 86 8.59 88 10.73 90 12.87 92 15 94 17.13 96 19.26 98 21.39 100 23.51 102 25.63 104 27.75 106 29.86 108 31.97 110 34.08 112 36.19 114 38.29 116 40.39 118 42.49 120 44.58 122 46.67 124 48.76 126 50.85 128 52.93 130 55.01 132 57.09 134 59.16 136 61.23 138 63.3 140 65.36 142 67.43 144 69.49 146 71.54 148 73.6 150 75.65 152 77.7 154 79.74 156 81.79 158 83.83 Function 8 RRA-FC412 T vs Heat Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 78 0 80 2.24 82 4.47 84 6.7 86 8.93 88 11.15 90 13.37 92 15.59 94 17.8 96 20.01 98 22.22 100 24.43 102 26.63 104 28.83 106 31.02 108 33.21 110 35.4 112 37.59 114 39.77 116 41.95 118 44.13 120 46.3 122 48.47 124 50.64 126 52.81
E - PROJECT REPORT
.~ NO. WS129-PR-02 m
ENERCON SERVICES, INC. w-REV. 1 PAGE NO. 54 of 90 Function 8 RRA-FC-12 T vs Heat Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 128 54.97 130 57.13 132 59.28 134 61.43 136 63.58 138 65.73 140 67.87 142 70.01 144 72.15 146 74.28 148 76.41 150 78.54 152 80.67 154 82.79 156 84.91 158 87.02 Function 9 § I RRA-FC-13, 14 T vs Heat Rate Ind. Var.: Dep. Var.: Var. ld. Dep. Var. Ind. Var. Dep. Var. 0 0 78 0 80 1.91 82 3.81 84 5.72 86 7.61 8 9.5 90 11.39 92 13.28 94 15.17 96 17.06 98 18.94 100 20.83 102 22.72 104 24.58 106 26.47 108 28.33 110 30.28 112 32.22 114 33.89 116 35.83 118 37.78 120 39.44 122 41.39 124 43.33 126 45 128 46.94 130 48.89 132 50.56 134 52.5 136 54.44 138 56.11 140 58.06 142 59.72 144 61.67 146 63.61 148 65.28 150t 67.22 152 68.89 154 70.83 156 72.5 158t 74.44
NO. WS129-PR-02 LI Wa PROJECT REPORT REV. 1 I ENERCON SERVICES, INC. _ __ __ _ _ _ _ _ _ _ _ _ _ PAGE NO. 55 of 90 Function 10 - I I I RRA-FC.15,17 T vs Heat Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Yar. Dep. Var. 0 0 78 0 80 1.66 82 3.33 84 4.97 86 6.64 88 8.28 90 9.94 92 11.58 94 13.25 96 14.89 98 16.53 100 18.19 102 19.83 104 21.47 106 23.11 108 24.75 110 26.39 112 28.06 114 29.72 116 31.39 118 32.78 120 34.44 122 36.11 124 37.78 126 39.44 128 41.11 130 42.78 132 44.17 134 45.83 136 47.5 138 49.17 140 50.83 142 52.22 144 53.89 146 55.56 148 57.22 150 58.61 152 60.28 154 61.94 156 63.61 158 65 Function 11 i RRA-FC-19,20 T vs Heat Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 78 0 80 2.93 82 5.86 84 8.78 86 11.7 88 14.61 90 17.52 92 20.42 94 23.31 96 26.2 98 29.09 100 31.97 102 34.84 104 37.71 106 40.57 108 43.43 110 46.28 112 49.13 114 51.97 116 54.81 118 57.64 120 60.46 122 63.28 124 66.1 126 68.91
SNO. WS129-PR-02 k, P PROJECT REPORT REV. 1 E.NERCON SERVICES, INC. I PAGE NO. 56 of 90 Function 11 RRA-FC-19,20 T vs Heat Rate Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 128 71.71 130 74.51 132 77.3 134 80.09 136 82.88 138 85.65 140 88.43 142 91.19 144 93.96 146 96.71 148 99.46 15C 102.21 152 104.95 154 107.69 156 110.42 158 113.14 Function 12 SGT Flow vs DP Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var.
-1 4800 0 4800 0.1444 4800 0.2707 4800 0.3609 4800 0.4421 4800 0.5007 4800 0.5503 4800 0.556 4800 0.5774 4000 0.5955 3000 0.6 2000 0.61 0 5 0 Function SGT Heat Rate Ind. Var.:
Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. _ 0.2 0.' 0.081 0.2 0.05 0.3 0.09_ 0.4 0.16 0.' 0.25 0.6 0.37 0.7 _ 0.5 0.8 0.65 0.9 0.81 _1 1
NO. WS129-PR-02 Fu< PROJECT REPORT ENERCON SERVICES, INC. I I , rPAGE NO. 57of 90 Function 14 PC Temperature Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 135 0.1 150 0.7 328 1 290 4 285 10 280 1000 280 2000 285 10000 280 86400 250 1000000 165 10000000 110 100000000 110 Function 15 111 Coeff Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var.
-1000000 0 0 0.1 0.1 1000 1000000 1000 Function 16 Nu Tube Side Ind. Var.:
Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 45350 299.64 49030 307.96 52830 316.13 56740 324.18 60760 332.11 64890 339.91 69120 347.6 73460 355.18 77890 362.65 82410 370.02 87030 377.29 91740 384.47 96540 391.55 101400 398.55 106400 405.46 111400 412.3 116600 419.051 121800 425.74 127000 432.361 132400 438.91 137800 445.4 143300 451.83 148900 458.21 154500 464.53 160200 470.8 165900 477.03 171700 483.21
NO. WS129-PR-02 O PROJECT REPORT R
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I _I___ _ _ PAGE NO. 58 of 90 Function 17 l Nu Shell Side Ind. Var.: Dep. Var.: Ind.Var. Dep. Var. Ind. Var. Dep. Var. 0 0 15090 163.86 16310 167.23 17570 170.51 18860 173.7 20190 176.82 21550 179.85 22940 182.82 24350 185.71 25800 188.54 27270 191.29 28770 193.99 30300 196.62 31850 199.2 33420 201.72 35010 204.19 36620 206.61 38260 208.97 39910 211.29 41580 213.56 43270 215.79 44970 217.98 46680 220.13 48420 222.24 50160 224.31 51920 226.34 53690 228.34 55460 230.31 1000000 230.311 Function 18 Cont Heat Transfer Ind. Var.: Dep. Var.: Ind. Var. l Dep. Var. I nd.Var. l Dep. Var. 0- 0° 1000000001 100000000 Function 19 111 Fuel Pool Flow Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 1 0 1.1 1 100000000 1
L NO. WS129-PR-02 U ENIERCON SERVICES, INC. I I PROJECT REPORT REV. 1 II__PAGE NO. 59 of 90 Function 20 Upper Leak Flow Ind. Var.: Dep. Var.: Ind. Yar. Dep. Var. lnd. Var. Dep. Var. 0° o0 100000000l 100000000 Function 21 Lower Leak Flow Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 100000000 100000000 Function 22 I I Wetwell Pool Temp Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 95 101 105 100 150 1000 160 10000 200 35000 204 50000 200 100000000 200 Function 23 I I Fuel Pool Temp Ind. Var.: Dep_Var.: Ind. Var. l Dep. Var. Ind. Var. l Dep. Var. 0° 0l 10000000l 10000000
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I _ _I__ I_PAGE NO. 60 of 90 Function 24 ECCS Pipe Temp Ind. Var.: Dep. Var.: Ind. Var. L Dep. Var. l Ind. Var. Dep. Var. 01 -0 100000001 10000000 Function 25II Norn Pwr Decay Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. r. Dep. Var. o 0° 1000000001 100000000 Function 26 RRAFC123 87F Ind. Var.: Dep. Var.: Ind.Var. Dep. Var. Ind. Var. Dep. Var. 0 0 87 0 89 2.06 91 4.11 93 6.17 95 8.22 97 10.28 99 12.33 101 14.39 103 16.42 105 18.47 107 20.5 109 2.53 ill 24.56 113 26.58 115 28.61 117 30.56 119 32.78 121 34.72 123 36.67 125 38.61 127_ 40.83 129 42.78 _131 _ 44.72 133 46.67 135 48.61 137 50.83 139 52.78 141 54.72 - - 143 56-.67 145 58.61 147 60.56 149 62.78 151 64.72 153 66.67 155 68.61 157 70.56 15' T2.5 161 74.44 163 76.39 165 78.33 167 80.28
NO. WS129-PR-02 all PROJECT REPORT LIE REV. 1 ENERCON SERVICES, INC. _ _ _ _ __ _PAGE NO. 61 of 90 Function 27 RRAFC4 87F Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 87 0 89 3.97 91 7.92 93 11.86 95 15.81 97 19.72 99 23.64 101 27.56 103 31.39 105 35.28 107 39.17 109 43.06 111 46.94 113 50.83 115 54.72 117 58.33 119 62.22 121 66.11 123 69.72 125 73.61 127 77.5 129 81.11 131 85 133 88.61 135 92.5 137 96.11 139 100 141 103.61 143 107.22 145 110.83 147 114.72 149 118.33 151 121.94 153 125.56 155 129.17 157 132.78 159 136.39 161 140 1631 143.61 165 147.22 16 150.83 Function 28 RRAFC5 87F Ind. Var.: Dep. Var.: Ind. Var. DEp. Var. Ind. Var. Dep. Var. 0 0 87 0 89 2.86 91 5.69 93 8.53 95 11.36 97 14.19 99 17.03 101 19.86 103 22.67 105 25.47 107 28.33 109 31.11 111 33.89 113 36.67 115 39.44 117 42.22 119 45 121 47.78 123 50.56 125 53.33 127 56.11 129 58.89 131 61.67 133 64.17 135 66.94
NO. WS129-PR-02 E PROJECT REPORT REV. 1 ENERCONSERVICES, INC. _ _ _ _ _ _ _ _ I__ _ _ _ _ __ _ _ _ _ _ _ I__PAGE NO. 62 of90 Function 28 RRAFC5 87F Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 137 69.72 139 72.5 141 75.28 143 77.78 145 80.56 147 83.33 149 86.11 151 88.61 153 91.39 155 94.17 157 96.67 159 99.44 161 102.22 163 104.72 165 107.5 167 110 Function 29 RRAFC8, 9 84F Ind. Var.: Dep. Var.: _ _ _ _ _ Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 *84 0 85 0.669722222 90 4.013888889 95 7.352777778 100 10.68333333 105 14.00833333 110 17.325 115 20.63611111 120 23.93888889 125 27.23333333 130 30.52777778 135 33.80555556 140 37.0833333 145 40.36111111 150 43.61111111 155 46.86111111 160 50.11111111 165 53.3611l11 170 56.58333333 175 59.80555556 180 63.02777778 185 66.25 190 69.44444444 195 72.63888889 200 75.83333333 Function 30 RRAFCID,11 87F Ind. Var.: ____ ____Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0* 0 8 89 2.159142 93 6.439586 97 _12__831 10__71__99__ 1011 ___ __1031__ 14____ 17.081
TEPR NO. WS129-PR-02 3O PROJECT REPORT REV. 1 ENERCON SERVICES, INC. _PAGE NO. 63 of 90 Functon 30 RRAFC10,11 87F Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 105 19.2 107 21.32 109 23.44 111 25.55 113 27.66 115 29.77 117 31.88 119 33.98 121 36.08 123 38.17 125 40.27 127 42.36 129 44.44 131 46.53 133 48.61 135 50.69 137 52.77 139 54.84 141 56.91 143 58.98 145 61.04 147 63.11 149 65.17 151 67.22 153 69.28 155 71.33 157 73.37 159 75.42 161 77.46 163 79.5 165- 81.54 167 83.57
NO. WS129-PR-02 rp .8 PROJECT REPORT
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ENERCON SERVICES, INC. I _ _I__ __ PAGE NO. 64 of 90 Function 31 RRAFC12 87F Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 87 0 89 2.23 91 4.46 93 6.68 95 8.9 97 11.11 99 13.33 101 15.54 103 17.75 105 19.95 107 22.15 109 24.35 111 26.54 113 28.74 115 30.92 117 33.11 119 35.29 121 37.47 123 39.65 125 41.82 127 43.99 129 46.16 131 48.32 133 50.48 135 52.64 137 54.79 139 56.95 141 59.09 143 61.24 145 63.38 147 65.52 149 67.66 151 69.79 153 71.92 155 74.05 157 76.17 159 78.29 161 80.41 163 82.53 165 84.64 167 86.75 Function 32 RRAFC13,14 87F Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 87 0 89 1.9 91 3.81 93 5.69 95 7.58 97 9.47 99 11.36 101 13.25 103 15.14 105 17.03 107 18.89 109 20.78 111 22.67 113 24.53 115 26.39 117 28.33 119 30 121 31.94 123 33.89 125 35.83 127 37.5 129 39.44 131 41.39 133 43.06 135 45
19R NO. WS129-PR-02 PROJECT REPORT NEC S REV. ENERCONSERVICES, INC. PAGE NO. 65 of 90 Function 32 1 I RRAFC13,14 87F Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 137 46.94 139 48.61 141 50.56 143 52.22 145 54.17 147 56.11 149 57.78 151 59.72 153 61.39 155 63.33 157 65.28 159 66.94 161 68.89 163 70.56 165 72.5 167 74.17 Function 33 RRAFC15, 17 87F Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 87 0 89 1.66 91 3.31 93 4.97 95 6.61 97 8.28 99 9.92 101 11.56 103 13.22 105 14.86 107 16.5 109 18.14 111 19.78 113 21.42 115 23.06 117 24.69 119 26.31 121 28.06 123 29.44 125 31.11 127 32.78 129 34.44 131 36.11 133 37.78 135 39.44 137 40.83 139 42.5 141 44.17 143 45.83 145 47.5 147 48.89 149 50.56 151 52.22 153 53.89 155 55.28 157 56.94 159 58.61 161 60.28 163 61.67 165 63.33 167 65
NO. WS129-PR-02 I z PROJECT REPORT Us ENERCON SERVICES, INC. REV. 1 I _I rPAGE NO. 66 of 90 Function 34 RRAFC19, 20 87F Ind. Var.: Dep. Var.: _ _ _ _ _ Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 87 0 89 2.92 91 5.84 93 8.75 95 11.65 97 14.55 99 17.44 101 20.33 103 23.22 105 26.09 107 28.97 109 31.83 Ill 34.69 113 37.55 115 40A 117 43.25 119 46.09 121 48.92 123 51.75 125 54.58 127 57A 129 60.21 131 63.02 133 65.82 13Ei 6862 137 71.41 139 74.2 141 76.98 143 79.76 145 82.53 147 85.29 149 88.06 151 90.81 153 93.56 15 96.31 157 99.05 159 101.78 161 104.511 1631 107.24 165 109.961 1671 112.67 Function 35 RRAFC Ind. Var.: Dep. Var.: Ind. Var. I Dep. Var. Ind. Var. Dep. Var. 0 0 10000000 10000000 Function 36 RRAFC4Cont Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 10000000 10000000O
NO. WS129-PR-02 Igdu PROJECT REPORT
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I _ __ _ __ _ __ I_ __I PAGE NO. 67 of 90 Function 37 _ RRAFC5Cont Ind. Var.: Dep. Var.: Ind. Var. I Dep. Var. Ind. Var. l Dep. Var. 01 0o 100000001 10000000 Function 38 RRAFC89Cont Ind. Var.: Dep. Var.: Ind. Var. r Dep. Var. l nd. Var. l Dep. Var. 0o 0o 100000001 10000000 Function 39II RRAFC1011Cont Ind. Var.: Dep. Var.: Ind. Var. I Dep. Var. l n d. Var. l Dep. Var. 0° 0l 10000000T 10000000 Function 40 I I RRAFC12Cont Ind. Var.: Dep.Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 10000000 1
NO. WS129-PR-02 ITy~h PROJECT REPORT ENERCON SERVICES, INC. I PAGE NO. 68 of 90 Function 41 RRAFC1314Cont Ind. Var.: Dep. Var.: Ind. Var. l Dep. Var. Ind. Var. l Dep. Var. 0° 0° 100000001 10000000 Function 42 RRAFC1517Cont Ind. Var.: Dep. Var.: Ind. Var. I Dep. Var. Ind. Var. Dep. Var. 0 0 10000000 10000000 Function 43I RRAFC192OCont End. Var.: Dop. Var.: Ind. Var. l Dep. Var. I Ind. Var. Dep. Var. 0o °0 100000001 10000000 Function 44 Pond Temp Simple Ind. Var.: Time (sec) Dep. Var.: Tern.rature F Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 78 7200 78 7200.01 87 100000000 87 Function 45 SGTS Start Time Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var. 0 0 106.9 0 107 _ 119.9 1 120 1 10000000 1 I _ _ I _ _ _ .I__ _ I __ _ I
NO. WS129-PR-02 E l PROJECT REPORT 1I REV. 1 ENERCON SERVICES, INC. I__I PAGE NO. 69 of 90 Function 46 SGTS Fan Heat Ind. Var.: Dep. Var.: Ind. Var. Dep.Var. Ind. Var. Dep.Var. 0 0 1000000 1000000 Function 47 SGTS 0% Ind. Var.: Dep. Var.: Ind. Var. Dep. Var. Ind. Var. Dep. Var.
-1 4800 0 4800 0.144 4800 0.208 4800 0.266 4800 0.316 4800 0.37 4800 0.415 4800 0.456 4800 0.496 4800 0.532 4800 0.559 4800 0.595 4800 0.613 4800 0.623 4800 0.632 4800 0.633 0 5 0 Function 48 SGTS Flow Select Ind. Var.:
Dep. Var.: Ind. Var. I Dep. Var. I Ind. Var. j Dep. Var. 0L 0l 10000001 1000000
m =~ ~~~~PROJECT REPORT N.W1NR0 NO. WS129-PR-02 1R1EV. 1 2NEhRCON SERVICES, INC. PAGE NO. 70 of 90 Control Variables CV _ Funa. Initial Coeff. Coeff. _ ____Upd. Itt. Description Form Value G aO Min Max Mult. I Vapor Temperature tfunc 135 1 0 -1 E+32 1 E+32 0 2 DW Wall Temp sum 135 1 0 -IE+32 1 E+32 0 3 Temp Dfference sum 0 -1 0-1 E+32 1 E+32 0 4ICoefflcient tfunc 0 1 0 _ 10000 0 51UHX sum 0 1 0 -1E+32 IE+32 0 6 IP Top Door sum 14.66328 1 0 -1E+32 1E+32 0 7 DPLow sum 0.54474 27.71 14.68294 -IE+32 1E+32 0 8 iP Upper sum 14.56125 1 0 -1E+32 1E+32 0 9 DPUpper sum 0 27.71 14.56125 -1 E+32 1E+32 0 10 Leakage DP Upper sum 0 27.71 0 0 5 0 11 Turb Flow Upper exp 0 2489.79 0.5 0 1 E+321 0 12 Leak Flow Up sum 0 1 0 0 IE+32 0 13 Leak DP Lower sum 0 27.71 0 0 5 0 14 Turb Flow Low exp 0 1139.86 0.5 _O IE+32 0 15 Leak Flow Low sum 0 1 0 0 IE+32 0 16 Fue Poo Temp sum 125 1 0 0 300 0 17 FP Rm Pipe Temp tf 104 1 1E+32 1E+32 0 18 Wetwell Temp tfunc 95 1 0 -1E+32 1 E+32 0 19 ECCS Rm Pipe Temp if 104 1 -0.1 -IE+32 1E+32 0 20 Main Bid Temp sum 75 1 0 28 200 0 21IPwr I sum 0 150 1 -1E+32 1 E+32 0 22 Pwr 2 exp 0 75 2 -1E+32 1E+32 0 23P wr 3 exp 0 25 3 -1E+32 1E+32 0 24 Pwr 4 exp 0 6.25 4 -1 E+32 1E+32 0 25 Norm Bld Eval sum 0 1 0 -1 E+32 I E+32 0 26 Norm Bld HT if 0 1 0 0 300 0 27 Norm Bid Ht Load 0 1 1f -7200 0 300 0
NO. WS129-PR-02 BillPROJECT REPORT qzj RE5V. 1 E :~CO N SERtVICEAS,INC EAGOE NO. 71of 90 Control Variables CV l _l Func. Initial Coeff. Coeff. l l Upd. Int.
# Description Form Value G aO Min Max Mult.
28 RRAFC123 ff 0 1 -7200 -1E+32 1E+32 0 29 RRAFC12377 tfunc 0 1 0 -1E+32 1E+32 0 30 RRAFC12387 tfunc 0 1 0 -1E+32 1E+32 0 31 RRAFC4 if 0 1 -7200 -1E+32 IE+32 0 32 RRAFC477 tfunc 0 1 0 -1E+32 IE+32 0 33 RRAFC487 tfunc 0 1 0 -1E+32 1E+32 0 34 RRAFC5 if_0 1 -7200 -1E+32 1E+32 0 35 RRAFC577 tfunc 0 1 0 -IE+32 1E+32 0 36 RRAFC587 tfunc 0 1 0-1 E+32 IE+32 0 37 RRAFC89 ifa 1 -7200 -1E+32 1E+32 0 38 RRAFC8977 dfunc 0 1 0 -1E+32 IE+32 0 39 RRAFC8987 tfunc 0 1 0 -1E+32 1E+32 0 40 RRAFC1 011f_ _0 1 -7200 -1E+32 1E+32 0 41 RRAFC101177 tfunc 0 1 0 -1E+32 1E+32 0 42 RRAFC101187 tfunc 0 1 0 -1E+32 1E+32 0 43 RRAFC12 if 0 1 -7200 -IE+32 1E+32 0 44 RRAFC1277 tfunc 0 1 0 -1E+32 1E+321 0 45 RRAFC1287 tfunc 0 1 0 -1E+32 IE+32 0 46 RRAFC1314 if 0 1 -7200 -1E+32 1E+32 0 47 RRAFC131477 tfunc 0 1 0 -1E+32 1E+32 0 48 RRAFC131487 tfunc 0 1 0 -1E+32 1E+32 0 49 RRAFC1517 If 0 1 -7200 -1E+32 1E+32 0 50 RRAFC151777 tfunc 0 1 0 -1E+32 1E+32 0 51 RRAFC151787 tfunc 0 1 0 -1E+32 1E+32 0 52 RRAFC1920 If _0 1 -7200 -1E+32 IE+32 0 53 RRAFC192077 tfunc 0 1 0 -1E+32 IE+32 0 54 RRAFC192087 tfunc 0 1 0 -1 E+32 1E+32 0 55 DP sum 0 1 0 -IE+32 1E+32 0
0" PROJECT REPORT NO. WS129-PR-02 EN 'RCON SERVICES, INC. PAGENO. 72of90 Control Variables CV Func. Initial Coeff. Coeff. Upd. Int Description Form Value G aO Min Max Mutt. 56 0%VIV Flow tfunc 0 1 0 -11E+32 1E+32 0 57 25%VIV Flow tfunc 0 1 0 -1E+32 IE+32 0 58 Selector if 0 1 -0.26 -1E+32 1E+32 0 59 Fan Efficiency mut 0.0116883 0 -1E+321 IE+32 0 60 Fan Heat sum 0 15.73 0 -1E+32 IE+32 0
NO. WS129-PR-02 F PROJECT REPORT L r REV. 1 ENERCON SERVICES, INC. I - I I PAGE NO. 730of90 Function Components Control Variable I Vapor Temperature tfunc Y=G*Interp(X1 ,table__ _ Gothic_s Variable Coef.
# Name location a IEtime cM 2- DC14 Function Components Control Variable 2 DW Wall Temp sum Y=G*(aO+alXla2X2+...+anXn)
Gothic al Variable Coef. Name location a 1 Tsrfs(l) cC33 Function Components Control Variable 3 Temp Difference sum Y=G*(aO+alXl+a2X2+...+anXn) Gothic s Variable Coef. _ Name location a ICval cv2 2 Cvval cvi Function Components Control Variable 4 Coefficient tfunc YCG*lnterp(X1,tab eX2J Gothlcs Variable Coef. Name locationa 1 Cvval cv31 2 -DC15 I _ _ I__ _ 1 I1_ __
I NO. WS129-PR-02 I PROJECI REPORT "bREV. __ ENERCON SERVICES, INC. I PAGE NO. 74 of 90 Function Components Control Variable 5 UHX sum Y=G*(aO-+alXl+a2X2+. ..+anXn) Gothics Variable Coef.
# Name location a iUhx(1) cX1 H Function Components Control Variable 6 IP Top Door sum Y=GI(aO+alXl+a2X2+...+anXn)
Gothlcs Variable Coef. Name location a I P cV1 2 Rm cV1 0.37457 Function Components Control Variable 7 DPLow sum Y=G*(aO+alX1+a2X2+...+anXn) Gothic~_s Variable Coef. Name locatlona I Cwval cv6 -1 Function Components Control Variable 8 IP Upper sum Y.G*(aO-a1X1+a2X2+ ..
+anXn)
Gothicas Variable Coef.
# Name location a 1P cV5 l 2 Rm cV5 -0.21515
.ml NO. WS129-PR-02 Low 2PROJECT REPORT IMB REV. 1 ENERCON SERVICES, INC.
I_____PAGE NO. 75 of 90 Function Components Control Variable 9 DPUpper sum Y=G*(aO+a1X1+a2X2+...+anXn) l Gothie" Variable Coef.
# Name location a 1 Cvval CV8 Function Components Control Variable 10 Leakage DP sum Y=G*(aO+a1X1+a2X2+...+anXn)
Gothlcs Variable Coef. Name location a 1 Bc_p cB2F 2 Cvval w_81 Function Components Control Variable 11 Turb Flow Upper exp Y=G*(aO+alXI)Aa2X2 or G*(alX1)AaO Gothlcs Variable Coef. I Cvval Name location cv10 J a Function Components Control Variable 12 Leak Flow Up sum Y=G*(aO+alXl+a2X2+. ..+anXn) Gothilcs Variable Coef.
# Name location a I Cwal CV10 1226.31 2Cvval cv1I 1
_ _ I __ _ I _ _ I __
E - PROJECT REPORT NO. WS129-PR-02 REV. I ENERCON SERVICES, INC. I _ _ _I _ _ _ _ _ __ . PAGE NO. 76 of 90 Function Components Control Variable 13 Leak DP Lower sum Y=G*(aO+a1X1+a2X2+ .+anXn) . Gothic-s Variable Coef. Name location a 1 Bc_p cB1 F 1 2 Cvval cv6 -1 Function Components Control Variable 14 Turb Flow Low exp Y=G*(aO+a1X1 )a2X2 or G*(flX1)Aaa Gothic s Variable Coef. Name locationa 1 Cwa~l cv131 Function Components Control Variable 15 Leak Flow Low sum Y=G'(aO+a1X1+a2X2+.+ _ _anXn Gothlcs Variable Coef.
# Name location a 1 Cwal cv13 379.9!
2 Cvval cv14 1 Function Components Control Variable 16 Fuel Pool Temp sum Y=G*(aO+alXl+a2X2+...+anXn) Coef_ Gothic s Variable Coef.
# Name location a 1 Teml cV5 1i I I. I
NO. WS129-PR-02 I w PROJECT REPORT REV. ENERCON SERVICES, INC. I __I__ I_PAGE NO. 77 of 90 Function Components Control Variable 17 FP Rni Pipe Temp if(alXl+aO8< alXl+aO=O alXl+aO>O) Y=Ga2X2 Y=Ga3X3 Y Ga4X4 Gothic s Variable Coef.
# Name location a I Wljnc cJ7 1 2 One cM 104 3 One cm 1 4CCwal cv16 I Function Components Control Variable 18 Wetwell Temp tfunc Y=G*lnterp(X1,tableX2)
Gothic a Variable Coef. _ Name location a Etime cM 1 2- DC24 I Function Components Control Variable 19 ECCS Rm Pipe Temp Kf(alXl+aO<0 alXl+aO--0 alXl+aO>O) Y=Ga2X2 Y=Ga3X3 Y=Ga4X4 Gothic s Variable Coef. Name location a lEtime cM I 2One cM 104 3 One cM 104 4 Cvval cv18 1 Function Components Control Variable 20 Main Bid Temp sum Y=G*(aO+alXl+a2X2+. .. +anXn) Gothlc_s Variable Coef.
# Name location a mTemv cVI I
NO. WS129-PR-02 I w PROJECT REPORT 4uS REV. 1 ENERCON SERVICES, INC. II_ I_PAGE NO. 78 of 90 Function Components Control Variable 21 Pwr I sum Y=G-(aO+a1Xl+a2X2+...+anXn) Gothics Variable Coef.
# Name location a 1 Etlme cM -0.0002778 Function Components Control Variable 22 Pwr 2 exp Y=G*(aO+aIXl)Aa2X2 or G*(a1X1)AaO Gothic.s Variable Coef.
Name location a 1 Etime cM -0.0002778 Function Components Control Variable 23 Pwr 3 exp Y=G*(aO+alXl)Aa2X2 or ((alXl)AaO Gothic s Variable Coef. Name location I Etime cM -0.00027778 Function Components Control Variable 24 Pwr 4 exp Y=G*(aO+alXl)Aa2X2 or ;*(a1X1)AaO Gothlcs Variable Coef.
# Name location a 1 Effme cM -0.00027778
L ~b w PROJECT REPORT NO. WS129-PR-02 REV. 1 ENERCON SERVICES, INC. I_____PAGE NO. 79 of 90 Function Components Control Variable 25 Norm Bid Eval sum Y=G*(aO+a1X1 +a2X2+....+anXn) Gothlcs Variable Coef. Name location a I Cvval cv2l 1 2 Cvval cv22 1 3 Cvval cv23 _ 4 Cvval cv24 5 Cwal cv20 -1 Function Components Control Variable 26 Norm Bid HT if(a1X1+aO<0 alXl+aO=0 alXl+aO>O) Y=Ga2X2 Y=Ga3X3 Y=Ga4X4 Gothica Variable Coef. Name location a 1 Cvval cv25 1 2Zero cM I 3 Zero cM I 4 Cwal cv25 1.4629 Function Components Control Variable 27 Norm Bid Ht Load if(alxl+aOcO alXl+aO=0 alXl+aO>O) Y=Ga2X2 Y=Ga3X3 Y=Ga4X4 l Gothic_s Variable Coef. Name location a 1 Etime cM 1 2 Cvval cv26 I _ 3Cvval cv26 1 41Zero ICM 1 ____________ J. L .1.
PRJC RNO. WS129-PR-02 E PROJEcF REPORT REV. _ ENERCON SERVICES, WCe I __I I__ PAGE NO. 80 of 90 Function Components Control Variable 28 RRAFC123 If(alXl+aO<0 a1X1+a0O0 alXl+aO>0) YCGa2X2 Y=Ga3X3 Y=Ga4X4 Gothic s Variable Coef. Name location a IEUme cM 2 Cvval cv29 1 3 Cvval cv30 1 4 Cvval cv3O 1 Function Components Control Variable 29 RRAFC12377 tfunc Y=G*Interp(X1 ,tableX2) Gothica Variable Coef. Name location a I Temv cV4 1 2- DC2 1 Function Components Control Variable 30 RRAFC12384 tfunc Y=G*Interp(X1,tableX I Gothic s Variable Coef. Name location a 1 _Temv cV4 - 21- DC28 1 Function Components Control Variable 31 RRAFC4 ff(aiXl+aO<O alXlaaO=O a1X1+aO>O) Y=Ga2X2 Y=Ga3X3 Y=Ga4X4 Gothic s Variable Coef.
# Name location I a lEtime cM 2 Cvval cv32 1 3 Cvval cv33 1
0q11 NO.WS129-PR-02 iu l PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I _ _ _ _I_ I__ PAGE NO. 81 of 90 41Cvval Icv33 Function Components Control Variable 32 RRAFC478 ffunc Y=G*interp(XltableX2) Gothic s Variable Coef. Name location a I Temv cV4 2 -DC3 1 Function Compon ents Control Variable 33 RRAFC487 tfunc _____ y.Y=G*Interp(Xi,tableX2) Gothic s Variable Coef. Name location a 1 Temv cV4 1 2 -DC29 Function Components Control Variable 34 RRAFC5 if(a1X1+aO 0 a1X1+a0=0 alXl+aO>O) Y=Ga2X2 Y=Ga3X3 YzGa4X4 Gothic s Variable Coef. Name location a iEtime cM 2Cvval cv35 3Cvval cv36 1 4Cvvalcv36 Function Components Control Variable 35 RRAFC578 ffunc Y=G*interp(Xl ,tableX2) Gothic s I Variable Coef. Name IIlocation a
NO. WS129-PR-02 Was PROJECT REPORT U1-REV. _ _ _ ENERCON SERVICES, INC. PAGE NO. 82of90 ITemv cV4 2 -DC41 Function Components Control Variable 36 RRAFC584 ffunc Y=G*lnterp(X1,tableX) Gothics Variable Coef. Name location _ a I Temv cV4 1 2- _DC30 Function Components Control Variable 37 RRAFC89 If(a1X1+a<O0 a1Xl+aO=0 a1X1+aO>O) Y=Ga2X2 Y=Ga3X3 Y=Ga4X4 Gothica Variable Coef. Name location a lEtime cM 2 Cwal cv38 1 3Cvval cv39 1 4 Cvval cv39 1 Function Components Control Variable 38 RRAFC8978 ffunc Y=G*interp(Xi,tableX2) Gothic_s Variable Coef. 0 Name location a I Temv cV1 i 2- DC6 1 Function Components Control Variable 39 RRAFC8984 ffunc YrG*interp(X1,tableX2) Gothic_sa Variable Coef.
NO. WS129-PR-02 A PROJECT REPORT
% 16-3REV. 1 ENERCON SERVICES, INC.
I __ __I__ IPAGE NO. 83 of 90 Name location _ a_l 1 Temv IcV1 l 1 2 -DC31 . Function Components Control Variable 40 RRAFC1011 if(a1X1+a<Oc alXl+aO=0 alXl+aO>O) _______ Y=Ga2X2 Y-Ga3X3 Y-Ga4X4 Gothic VVariable Coef. Name location a I Eime cM 1 2 Cvval cv41 1 3 Cval cv42 i 4 Cvval cv42 1 Function Components Control Variable 41 RRAFC101178 ffunc Y=G*lnterp(X1,tabl eX2) Gothic s Variable Coef. Name location a 1 Temv cV1 2 DC7 = Function Components Control Variable 42 RRAFCIOII84 ffunc Y=G*interp(X1 ,tableX2) Gothics Variable Coef.
# Name location a
_ Temv cV1 2- DC32 1 Function Components Control Variable 43 RRAFC12 if(a1X1+a0<O a1X1+aO=0 a1Xl+aO>O) Y=Ga2X2 Y=Ga3X3 Y=Ga4X4
NO. WS129-PR-02 PROJECT REPORT .W1 LI- REV. 1 ENERCON SERVICES, INC. I __I_ I_PAGE NO. 84 of90 Gothlc"s Variable Coef. Name location a 1 Etime cM 1 2 Cvval cv44 3 Cwal cv45 1 4Cwa cv45 Function Components Control Varlable 44 RRAFC1278 ffunc Y=G*lnterp(X1 ,tabl _ ___ Gothlc._s Variable Coef. Name location a I Temv cV1 2- DC8 1 Function Components Control Variable 45 RRAFC1284 ffunc Y=G*interp(X1,table) Gothlcs Variable Coef. _ Name location a I Temv cVWI _ DC33 Function Components Control Variable 46 RRAFC13i4 lf(a1X1+aOc0 alXl+aO=0 alXl+aO>O) ________ Y=Ga2X2 Y=Ga3X3 Y=Ga4X4 _____ Gothic l Variable Coef. Name location a I Eime cM 1 2Cvval cv47 3 Cavvl cv48 1 _4 Cvval cv48 Function Components Control Variable 47
'I NO. WS129-PR-02 "M I PROJECT REPORT REV.
JPAGE Iz __ ENERCON SERVICES, INC. I_ NO. 85 of 90 RRAFC131478 tfunc Y-G*interp(Xi,tableX2) Gothic"s Variable Coef. Name location a 2- DC9 1 Function Components Control Variable 48 RRAFC131484 tfunc Y=G*Interp(X1,tableX Gothic s Variable Coef.
# Name location a 1 Temv cV1 1 2- DC34 Function Components Control Variable 49 RRAFC15i7 lf(a1X1+a0c0 alX1+aO=0 alX1+aO>O)
Y=Ga2X2 Y=Ga3X3 Y=Ga4X4 Gothic s Variable Coef. Name location a I Etme cM 1 2 Cvval cv5O 3 Cwal cv51 1 4 Cvval cv51 1 Function Components Control Variable 50 RRAFC151778 tfunc Y=G*lnterp(X1 ,tableX2) Gothlc"s Variable Coef. X Name location a 1 Temv cVI 2- DC10 1 Function Components
NO. WS129-rR-02
.t qPROJECT REPORT
="REV. _ _ _
ENERCON SERVICES, IMC. I _ _I I_rPAGE NO. 86 of 90 Control Variable 51 RRAFC151784 ffunc Y=Glinterp(XQ ,tableX2) Gothic s Variable Coef. Name location a 1 Temv cV1 2- DC35 I Function Components Control Variable 52 RRAFC192078 if(alXl+aOcO alXl+aO=0 a1XI+aO'O) Y=Ga2X2 Y=Ga3X3 Y=Ga4X4 Gothic s Variable Coef. Name location a IEtime cmt 2 Cvval cv53 1 3 Cvval cv54 1 4 Cvvat cv54 1 Function Components Control Variable 53 RRAFC192084 tfunc Y=G*interp(XI,tableX2) Gothics Variable Coef. Name location a I Temv CV1 2- DC1I I Function Components Control Variable 54 RRAFC192084 ffunc Y=G*lnterp(X1,tableX2J Gothicq _ Variable Coef. Narne location a 1 Temv cV1 1 2- DC36 1
1 1 PROJECT REPORT NO. WS129-PR-02 U ENERCON SERVICES, [NC. I REV. 1 II_ I_PAGE NO. 87 of 90 Function Components Control Variable 55
- DP sum Y=G*(aO+a1X1+a2X24+..+anXn)
Gothic s Variable Coef. _ Name location a 1P cV6 1 2P cV2sl 1 Function Components Control Variable 56 0%V1V Flow tfunc Y=G*interp(X1,tableX2) Gothic a Variable Coef. Name location a I Cvval cv55 1 2- DC47 1 Function Components Control Variable 57 25%VIV Flow ffunc Y=G*Interp(X ,tableX2) Gothic s Variable Coef. Name location a I 1 Cvval cv55 1 2 DC12 1 Function Components Control Variable 58 Selector if(a1X1+aO<O a1Xl+aO=0 alXl4aO>O) Y=Ga2X2 Y=Ga3X3 Y=Ga4X4 Gothic s Variable Coef.
# Name location a I Cvval cv9 I 2 Cvval cv56 1 3 Cvval cv57 1 4 Cwal cv57 1 I _ _ I__ 1 I1____
NO. WS129-PR-02 11" PROJECT REPORT 4- IREV. 1 ENERCON SERVICES, INC. I__ _ _ _ __ IPAGE NO. 88 of 90 Function Components Control Variable 59 Fan Efficiency mult Y G*(a1X1*a2X2*.. *anXn) Gothlcs Variable Coef. Name location a IVfanf 1 cfQ 2 Dpjnc CJil 1 Function Components Control Variable 60 Fan Heat sum Y=G*(aO+alXl+a2X2+...+anXn) l Gothic s Variable Coe. Name location a 1 One cM 1 2 Cvval cv59 1
s E ; -Lz-u-L;u-uiL,;uu- _ E oo-oCD CD o-o CD o
,EL N 0a0 0 a
_ CL L EL_L CL_ _-_ _ (D CC FOa 8 o aCa a CD c- iL U.aaLL U. N - V- ' e00
.C 00 8 0(DCD8 U~SD&O) M VQQ C
000 8'00 r> Q0 QCD o0 CD CL Eo o _ _ o v CL V'-0 aC C aCD 00 _aIP 0 c.Ra0-O8 co IVC~Cl0000 m mc )0 C)0 C coCDa0 0Os a-V _ aO 0 C CD O t t_ 0 000 00 0 O sc _E__ _ _ _ ___ EOco o o o o O O O PaD oE 2 222 _ _0 nS Da
WNO. WS129-PR-02 n wPROJECT REPORT REV. ENERCON SERVICES, MC. _ _ __ I__ PAGE NO. 90 of 90 Run Options Option Setting. Restart Time (sec) 0 Restart Time Step # 0 Restart Time Control NEW Revaporization Fraction DEFAULT Fog Model OFF Maximum Mist Density (lbm/ft3) DEFAULT Drop Diam. From Mist (in) DEFAULT Minimum HT Coeff. (B/h-ft2-F) 0 Reference Pressure (psia) IGNORE Forced Ent. Drop Diam. (in} DEFAULT Vapor Phase Head Correction INCLUDE Kinetic Ene IGNORE Vapor Phase INCLUDE Liquid Phase INCLUDE Drop Phase INCLUDE Force Equilibrium IGNORE Drop-Liq. Conversion INCLUDE QA Logging OFF Debug Output Level 0 Restart Dump on CPU Interval (sec) 3600
Calc. No. WS129-PR-02 r z CALCULATION F DESIGN VEIICATION Rev._ ENERCON EC. PLAN AND
SUMMARY
SHET Page No. App. 2, 1 of 2 CALCULATION DESIGN VERIFICATION PLAN:
- 1. Verify that the overall approach and methodology are correct and reasonable
- 2. Verify that the design input and the source references used are correct and reasonable
- 3. Verify that the assumptions are reasonable
- 4. Verify that the results arecorct and reasonable (rbdx Name and Sign)
Originator: Paul Hansen Date: 7 2810 f Approver: Ralph Schwartzbeck Date: , i CALCULATION DESIGN VERIFICATION SUMKARY: Verification Scope: The scope includes verification that the overall approach is reasonable, that the report method is acceptable, and that the equations and references used are properly applied. The input datm and assumptions were reviewed for accuracy and applicability. The scope also includes verification that the results are correct and reasonable. Methbds: The report was reviewed using the design review method. Design inputs were reviewed for correctness and to verify their validity. The reference calculation was reviewed to ensure the information was correctly extracted. The assumptions were reviewed to ensure they are reasonable. The overall approach and methodology was reviewed to ensure it is correct and reasonable. The math was verified to ensure arithmetic results were correct The GOTHIC input file was reviewed to verify that the inputs were entered correctly. The report results were reviewed to ensure they are correct and that the output is reasonable when compared to the input Results: The overall approach and methodology was found to be correct and reasonable. The appropriate formulae and data were correctly eitracted from the .refereace calculation. The arithmetic was checked and verified to be correct Numerical values were design verified using a calculator. The GOTMIC input file was correctly populated by the inputs developed within the report. The report results are reasonable and correct and are consistent with similar calculations performed in the past
== Conclusions:==
Based on this review, this report is acceptable in the determination and presentation of the input parameters discussed in the purpose section of the document Based On The Above Summary, This Report Is Determined To Be Acceptable. Yjr fn1eand Sign) Design Verifier: F. Bivins Calhoun I ; lDate: ¶-2.8-o9 Others: Date:
POW Calc. No. WS129-PR-02 CALCULATION Rev. 1 DESIGN VERIFICATION ENERCON SERVICES, INC. CHECKLIST Page No. App. 2, 2 of 2 ITEM CHECKIST ITEMS YES NO N/A 1 Design Inputs - Were the design inputs correctly selected, referenced (latest 0 O O revision), consistent with the design basis and incorporated in fte calculation? 2 Assumptions - Were the assumptions reasonable and adequately described, justified 3 O and/or verified, and documented? 3 Quality Assurance - Were the apprpriate QA classification and requirements o O assigned to the calculation? Codes, Standard and Regulatory Requirements - Were the applicable codes, 4 standards and regulatory requirements, including issue and addenda, properly O 0 0 identified and their requirements satisfied? Construction and Operating Experience - Have applicable construction and _ S operating experience been considered? 6 Interfaces - Have the design interface requirements been satisfied, including _ ] 0 interactions with other calculations? __a_ 7 Methods - Was the calculation methodology appropriate and properly applied to 03 a o satisfy the calculation objective? Design Outputs - Was the conclusion of the calculation clearly stated,. did it 8 correspond directly with the objectives and are the results reasonable compared to the 0 O 0 inputs? 9 Radiation Exposure - Hlas the calculation properly considered radiation exposure to O O 10 the public and plant personnel? Acceptance Criteria - Are the acceptance criteria incorporated in the calculation 10 sufficient to allow verification that the design requirements have been satisfactorily 0 0 0 accomplished? Comments: Editorial comments only. The report is technically correct and suitable for use as design input. The design review considered not only the checklist items identified above, but all basic questions posed by ANSI N45.2.1 1-1977. Design Verifier: F. Bivins Calhoun III ,_ Date: 5- 2 -04 Others: Date:
NO. WS129-PR-02 L PROJECT REPORT REV. 1 ENERCON SERVICES, INC. I__ I_PAGE NO. 1 of 5 APPENDIX 3 FAN MOTOR SPECIFICATION
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NO. WS129-PR-02 l-uPROJECT REPORT 4 e REV. 1 ENERCON SERVICES, INC. II PAGE NO. 4 of 5
NO. WS129-PR-02 n PROJECT REPORT Ul REV. I ENERCON SERVICES, INC. PAGE NO. S of S 368 Ft" *adB411hi Air Disrlbml In fis foum the equtionaprsesm the hbmc to stalhad oftbe ir. ultyp4u
'E.(I11-1) by lg. gfin Po, JIM) cs-whics ic upremlonprmczRy fa the, kxtd to th Wr.Mvlkstion of Eq. (II-in) by the mmt llow ratm of te dir pxodnca up for the ne powt w Iwprtled to the a.
t ZP~ - iJ(11-2) The U power h the &ft of the tol pwa thatis used vq poduchi hazd in atc bead. p -
-t (11-3)
Pan efaldency may be cprezd in tw* wOy The sotalfantffdmy i t ratio of Wa ar pow totho thafe poWo werer In tsi avA4me Am rate Eq. (11-4) becomes L) WU tow Dla, nor n/
'Po Fez b tomtaslppesmujb/f/crft ahaft WWI afi in or W It bas beea comandpcice In the Uhited Stles for to be In felmhL. (P,$
-P to bein hofwatsraind for Wt o U in horz v. B t peial case,
' A= o(1 -4h 635OW't - 11l4o)
The sJtan O W xmv is the atio of th stkc sf power to ie shaft powe iput, Vh (P - C, (11-5) Whem the ta= consistt Uais ane used as vkh Eq. (1U44 Uibg the idtt of Eq. (114b), we set 6-3S .1-)a) O(
Af -oz.-o/ CrJig 331/ P2 I 10Np* OM/ / ' , rM. Calce.No. WS129-CALC-001 RIM CALCLTION COVER. SHIEEiT Rev. 2 ENRCON SEVICES, INC. Page No. 1 of lS0 COLUMMIA STATION GOTHIC SECONDARY ~Clint ENERGY NORTR1WEST
Title:
CONTAINMENT DRAWDOWN MODEL (Sa1tht Relaed) Project: WS129 COVERSET M MUS YES NO 1 Does tbis cdculation oontain any assumptions that reqiconfiatin? (f YES, Identify the r 0 assumptions.) 2 Does tbis calculao sene as an "Altenate Calculation"? (f YES identifyfhedesignverfied calcuation.) Design Ver~ied Calculation No. 3 Does this calculaton supersede an existing celculation? (If YES, iday the superseded 0 calculation) Superseded Calculation No. _ SCOPE OF REVISION: Editorial and Formatting Changes and Minor Calculation Changes Only. REVISION IMPACT ON RESULTS: These changes did not Impact the results; that Is there were no methodology or technical changes to the calculation. Therefore, the Design Verification performed for Revision 0 remains applicable. PRELIMINARY CALCULATION Q FINAL CALCULATION 0 (PtNameandSign) Originator: Paul N. Hansen / Date: yV2lof Design Verifier. F.Bivins Calhounffi(5m Date: I-20.oo Approver: Ralph Schwartzbeck Date: q -2 -f F/
JL Calc. No. WS129-CALC-00 CALCULATION Rev. 2 REVISION STATUS SHEET _ ENERCON SERVICES, INC. Page No. 2 of 150 CALCULATION REVISION STATUS REVISION DATEESCRIPTION 0 Initial issue 1 6/03/2004 Minor Editorial Changes 2 9/28/2004 Minor Editorial and Calculation Change that introduced no impact PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION PAGE NO. REVISION PAGE NO. REVISION 1-2 2 43 2 82 0 98 1 3-5 0 44-53 0 83-85 1 99 1 6-9 1 54-56 1 86-90 0 100-101 0 10 2 57 0 91 1 102 1 11-12 0 58 1 92 0 103-118 0 13-14 1 59-60 0 93 1 119-121 1 15-18 0 61-62 1 94 0 122 2 19 1 63-64 0 95 1 123-124 0 20-27 0 65-70 1 96 0 125 1 28-30 1 71-76 0 97 1 126-150 0 31-35 0 77-78 1 36-37 2 79-80 0 3842 0 81 1 APPENDIX REVISION STATUS APPENDIX NO. PAGE NO. REVISION APPENDIX NO. PAGE NO. REVISION 1 57-60 2 4 All 0 2 All 0 5 All 0 3 0 6 0 7 All 0
m CALCllLATION Calc.No. WS129-CALC-001 DESIGN VERIFICATION Rev. 2 ENERCON SERVICES, INC. PLAN AND
SUMMARY
SHEET Page No. 3 of 15) CALCULATION DESIGN VERMfICATION PLAN:
- 1. Verify that the overall approach and methodology are correct and reasonable
- 2. Verify that the design input and the source references used are correct and reasonable
- 3. Verify that the assumptions are reasonable
- 4. Verify that the results are correct and reasonable APrlntName andhaen)
Originator: Paul Hansen Cio 7 qeh Date: 92 / Approver: Ralph Schw~artzbeck 0 , ( 4lDate: --;/z/ CALCULATION DESIGN VERIFICATION SUMMAKY: Verification Scope: The scope includes verification that the overall approach is reasonable, that the calculation method is acceptable, and that the equations and references used are properly applied. The input data and assumptions were reviewed for accuracy and applicability. The scope also includes verification that the results are correct and reasonable. Methods: The calculation was reviewed-using the design review method. Design inputs were reviewed for correctness and to verify their validity. The referenced design drawings were reviewed to ensure the information was correctly extracted. The assumptions were reviewed to ensure they are reasonable. The overall approach and methodology was review to ensure it is correct and reasonable. The calculation section was reviewed to ensure the appropriate formulae and data were correctly extracted from their references. The Mathcad formulas were reviewed to verify that the equations were accurately entered. The math was verified to ensure arithmetic results were correct. The GOTHIC input files were reviewed to verify that the inputs were entered correctly. The GOTHIC modeling method was reviewed for appropriateness. The calculation results were reviewed to ensure they are correct and that the output is reasonable when compared to the input. Results: The overall approach and methodology was found to be correct and reasonable. The appropriate formulae and data were correctly extracted from the references. The arithmetic was checked and verified to be correct Formulas were identified and accurately entered into Mathcad. Numerical values were design verified using a calculator. The GOTHIC input file was correctly populated by the inputs developed within the calculation. The GOTHiC modeling method are appropriate for this application. The calculation results are reasonable and correct and are consistent with similar calculations performed in the past.
== Conclusions:==
Based on this review, this calculation is acceptable in the determination and presentation of the input parameters discussed in the purpose section of the document. Based On The Above Summary, The Calculation Is Determined To Be Acceptable. l ft a=F nd Sign) Design Verifier: F. Bivins Calhoun m Date: ¶-*ZS_(q Others: Date:
l Cale. No. WS129-CALC-001 CALCULATION Rev. 2 _______ _ DESIGN VERIFICATION . EERCON SERVICES, INC. CHECKLIST Page No. 4 of /Sb ITEM CHECKLIST ITEMS YES NO N/A Design Inputs - Were the design inputs correctly selected, referenced (latest revision), consistent with the design basis and incorporated in the calculation? 0 E E 2 Assumptions - Were the assumptions reasonable and adequately described, justified 0 El El and/or verified, and documented? _ Quality Assurance - Were the appropriate QA classification and require ts Z El El assigned to the calculation? Codes, Standard and Regulatory Requirements - Were the applicable codes, 4 standards and regulatory requirements, including issue and addenda, properly El El 0 identified and their requirements satisfied? 5 Construction and Operating Experience - Have applicable construction and 0 lo O operating experience been considered? Interfaces - Have the design interface requirements been satisfied, including E] 0 6 interactions with other calculations? Methods - Was the calculation methodology appropriate and properly applied to 3 D O 7 satisfy the calculation objective? . _ Design Outputs - Was the conclusion of the calculation clearly stated, did it 8 correspond directly with the objectives and are the results reasonable compared to the . El El inputs?_ 9 Radiation Exposure - Has the calculation properly considered radiation exposure to El E 1 0 the public and plant personnel? Acceptance Criteria - Are the acceptance criteria incorporated in the calculation 10 sufficient to allow verification that the design requirements have been satisfactorily El El 0 accomplished? Comments: (T~ea me -andign) Design Verifier: F. Bivins Calhoun m[[ L. &5 IDate: 1-8 -o1 Others: Date:
Calc. No. WS129-CALC-001 ie$] CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 5 of 150 Table of Contents PURPOSE .................................................................. 6 APPROACH .................................................................. 6 RESULTS .................................................................. 6 CONCLUSIONS .................................................................. 7 REFERENCE .................................................................. 8 GENERAL REFERENCES ............................................................. 8 DRAWING REFERENCES ............................................................. 9 CALCULATION REFERENCES .............................................................. 10 APPENDIX REFERENCES ............................................................. 10 ASSUMPTIONS ................................................................. 11 GENERAL ASSUMPTIONS ............................................................. 11 VOLUME ASSUMPTIONS ............................................................. 15 DIRECT HEAT INPUT ASSUMPTIONS ............................................................. 16 THERMAL CONDUCTOR ASSUMPTIONS ............................................................. 17 BOUNDARY CONDITION ASSUMPTIONS ............... .............................................. 20 DESIGN INPUTS .................................................................. 20 METHODOLOGY .................................................................. 20 MODELING INPUT DEVELOPMENT .................................................................. 21 BOUNDARY CONDITION INPUTS: ............................................................. 21 INITIAL CONDITION INPUTS: ............................................................. 28 CONTROL VARIABLE INPUTS ............................................................. 34 LEAKAGE FLOW PATHS CONTROL VARIABLES ................................................................. 34 LEAKAGE MODEL DEVELOPMENT ................................................................. 35 PRESSURE CRITERIA INPUTS CONTROL VARIABLES ................................ ......................... 49 FLOW PATH INPUT: ............................................................. 51 VOLUME INPUT: ............................................................. 54 THERMAL CONDUCTOR INPUT:............................................................. 57 PUMP ROOM THERMAL CONDUCTORS ................................................................. 59 PIPING HEAT STRUCTURES .................................................................. 61 PUMP ROOM WALLS AND CEILINGS .................................................................. 65 MAIN REACTOR BUILDING THERMAL CONDUCTORS ............................................................ 72 REFUELING FLOOR THERMAL CONDUCTORS...........................................................................90 THERMAL CONDUCTOR MATERIAL PROPERTIES ................................................................. 92 THERMAL CONDUCTOR BOUNDARY TEMPERATURES .......................................................... 94 HEAT INPUTS AND FAN COOLER UNITS .............. ............................................... 99 FUEL POOL HEAT EXCHANGER INPUTS ............................................................. 112 SGTS FAN PERFORMANCE ............................................................. 115 TIME LINE ............................................................. 125 CALCULATION ................................................................. 126 SENSITIVITY AND SCOPING ANALYSES ............................................................. 126 FINAL ANALYSES ............................................................. 127 INPUT AND ASSUMPTION EVALUATION STUDIES ............................................................. 128 LONG TERM ANALYSIS AND MANUAL OPERATOR ACTION RESPONSE TIME EVALUATIONS ............................................................. 132
.150 APPENDICES.............................................................................................................................................
Calc. No. WS129-CALC-001 00 _"_ CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 6 of 150 PURPOSE The purpose of this calculation is to document the analysis inputs and results of the Columbia Station Secondary Containment drawdown analysis. APPROACH The approach used to develop this model starts with the original model documented in Reference 3.2. A number of sensitivity studies were performed to develop a full understanding of the phenomenon associated with the analysis. These sensitivity studies start with a single volume model, and add complexity one step at a time. The complexity is simply the addition of modeling features, such as internal heat sources, heat absorbing structure (thermal conductors), and wind pressure effects. Additional modeling features such as these are added one at a time to ensure that they were fully understood. The intent of this effort is to develop a multi-node model that will adequately represent the Columbia Generating Station Secondary Containment drawdown analysis. As the model was developed, a number of sensitivity reports were generated. These sensitivities produced lessons learned and were used in the overall model development. Since these evaluations are sensitivity studies, there was no intention to go back and revise each case as new information was developed. The final model developed in this manner, will be completely independent of the model documented in Reference 3.2 and will act as a stand alone document. RESULTS A number of results are produced as part of this calculation. These are divided into short term and long term analysis. The short term analysis determines the time for the SGTS to restore the Secondary Containment Reactor Building pressure below the negative 0.25inch of Water Gauge. As part of the short term study there are eight sets of results documented in Table 51. These eight cases where developed to determine the bounding outside temperatures, wind direction and leakage distribution (leakage split). It is demonstrated by the results in Table 51 that with cold outside air and wind from the easterly direction a bounding result was produced given a 70/30 leakage roof to railroad door distribution. Under these conditions the SGTS would require 872 seconds to restore the Secondary Containment Reactor Building to below negative 0.25inch of Water Gauge. This bounding case number 3 was used to perform the long term analysis. A total of four long term evaluations are conducted each with a different start time for the fuel pool cooling system. The results of the long term analysis are depicted in Figures 7 through 22. The full set of results are provided in Appendix 7.
Caic. No. WS129-CALC-001 F-,: CALCULATION CONTROL SHEETRev. ENERCON SERVICES, INC. Page No. 7 of 150 CONCLUSIONS The results of this evaluation demonstrate the ability of the SGTS system to restore and maintain the Secondary Containment Reactor Building pressure below negative 0.25inch water gauge. The sensitivity studies performed as part of the main body of this calculation demonstrate that the 70% to 30% split of leakage between the upper and lower portions of the containment provide the bounding condition. This split is considered to be conservative based on plant specific testing, which demonstrated that leakage into the building is predominantly from the roof elevation.The cold outside air temperature condition produced a more bounding result than the warm outside air. Under worst case conditions the SGTS can restore the Secondary Containment Reactor Building Pressure back below negative 0.25inch water gauge within 872 seconds. The fuel pool cooling system must be started within 24 hours to ensure that the Secondary Containment Reactor Building Pressure can be maintained below negative 0.25inch water gauge for long term response of the building.
Caic. No. WS129-CALC-001 l - -CALCULATION CONTROL SHEET Rev. 1 ENERCON SERVICES, INC. Page No. 8 of 150 REFERENCE GENERAL REFERENCES 1.1. Standard Review Plan 6.2.3 "Secondary Containment Functional Design" Rev. 2 1.2. GOTHIC 7.1 Users Manual 1.3. 1997 ASHRAE Fundamentals Chapter 26 Climatic Design Inputs 1.4. 1997 ASHRAE Fundamentals Chapter 28 Non Residential Cooling and Heating Load Calculations 1.5. FSAR Chapter 6, Amendment 57 1.6. LCS Table 1.6.4.2-1, Revision 24 1.7. Flow Of Fluids Through Valves, Fittings, and Pipe Crane Technical Paper No. 410 (Appendix 2), Twenty Third Printing - 1986 1.8. Handbook of Hydraulic Resistance 3rd Edition I.E.Idelchik ISBN 1-56700-074-6 (Appendix 2) 1.9. Burns and Roe Contract No. 18, Specification 2802-18, Division 15A 1.10. Standard Review Plan 6.2.1.5 "Minimum Containment Pressure Analysis For Emergency Core Cooling System Performance Capability Studies", Rev. 2 1.11. FSAR Chapter 9, Amendment 57 1.12. CVI 981-00, 122, Rev 1, Vender document number 32 - 5036793 -01, "Generation of CGS Five Percent and Ninety five Percent Wind Speed and Temperature Values" 1.13. Heat Transfer By James Sucec ISBN 0-697-00257-8, Copyright 1985 1.14. 1997 ASHRAE Fundamentals Chapter F24 Table 10. 1.15. FSAR Table 6.2-12 Thermal Characteristics, Amendment 57 1.16. 1996 Annual Book of ASTM Book of ASTM Standards Volume 04.06 Thermal Insulation; Environmental Acoustics 1.17. Technical Memorandum TM-1 146, Rev. 0 "Post LOCA Secondary Containment Pressure Temperature Transient" 1.18. Design Specification for Division 7 Section 7C "Insulated Metal Wall Panel Assemblies and Uninsulated Metal Siding, Rev. 3 1.19. Suppression Pool Temperature Response - Case C Draw. No. 960222.07 FSAR Figure 6.2-12, Amendment 57. 1.20. Temporary Procedure No. 8.3.177 "Secondary Containment Leakage Test" Approved Date 6/5/90 1.21. Technical Memorandum TM-2019, Rev 4, "Summary of Equipment Qualification Profiles", Page 600 1.22. PPM OSP-CONT/IST-Q702, Rev 3, Reactor Building Ventilation Isolation Valve Operability 1.23. PPM TSP-RB-B501, Rev 4, Reactor Building ( Secondary Containment) Drawdown Leakage Functional Test 1.24. NAA-SR-1 0100, Conventional Buildings for Reactor Containment, Dated 25 Jul 1965 1.25. Regulatory Guide 1.1X3, Rev. 0 "Alternative Radiological Source Terms for Evaluation Design Basis Accidents at Nuclear Power Reactors" 1.26. MATHCAD, Version 2001i 1.27. Holtec International HI-Storm 100 Cask System Amendment No. I Safety Evaluation Report Section 4.6 1.28. LCS Table 1.7.1-1, Rev 24 1.29. PPM SOP-FPC-PUMP/HX, Rev 1, PFC Pump and Heat Exchanger Operations 1.30. CGS Technical Specification, S.R. 3.7.1.2, Amendment 169 1.31. 1997 ASHRAE Fundamentals Chapter 22, Figure I
Fe.^ Caic. No. WS129-CALC-001 Lzhp CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 9 of 150 1.32. Introduction to Fluid Mechanics by Fox & McDonald ISBN 0-471-01909-7 Copyright 1978 1.33. ASME Steam Tables Fifth Edition Library of Congress Catalog Number 67-30431 DRAWING REFERENCES 2.1 M567 Rev. 21 2.2 M570 Rev. 37 2.3 M568 Rev. 43 2.4 Renumbered 2.3 2.5 M569 Rev. 47 2.6 M571 Rev. 15 2.7 CVI DWG 02-28-00, 111 Rev. 000 2.8 M810 Rev. 48 2.9 M812 Rev. 51 2.10 M813 Rev. 33 2.11 S709 Rev 33 2.12 S712 Rev 38 2.13 S715 Rev38 2.14 S718 Rev42 2.15 S721 Rev26 2.16 S722 Rev 19 2.17 A507-1 Rev 33, A507-2 Rev 2 2.18 S723 Rev 7 2.19 A508 Rev 27 2.20 A509 Rev 35 2.21 S737 Rev 19
In^i Calc. No. WS129-CALC-001 L131 ENERCON SERVICEiS, C. CALCULATION CONTROL SHEET Rev. tPageNo. 10 of 150 2 CALCULATION REFERENCES 3.1 NE-02-99-14 Rev. 0 -Secondary Containment Volume" 32 NB-02-94-19 Rev. I "Secondary Containment Drawdown Analysisr 3.3 ME-02-92-43 Revision 7 'Room Temperature Calculation for DG Building, Reactor Building, Radwaste Building and Service Water Pumphouse Under Design Basis Accident Conditions" 3.4 ME-02-9240 Revision 0 IrHVAC Systems" 3.5 5.35.18 Rev. 0 -Fuel Pool Temperature (One Pump,2 HEs) 3.6 ME-02-92-41 Rev. 5 "Ultimate Heat Sink Analysis" 3.7 WS129-CALC-002, Rev. 0, "Flow Paths and Loss Coefficient qnputs for Columbia Reactor Building (Safety Rela " 3.8 ElI-02-91-1066, Rev. 0, Setting Range determination for SOT-LM -IA1 3.9 NE-02-82-13 Rev. 2 'Fuel Pool Temperature Transient and Steady State Calculation" j 3.10 NE-02-92-06, Rev. 0, SOT Amubar Flow Meter Correction Factors 3.11 Deleted 3.12 9.23.01, Rev. 1 '"Post LOCA Secondary Containment Press-Temp Transient Analysis 3.13 NB-02-03-12, Rev 0, Calculation of SOTS Flow Rate for input to Safety Analysis 3.14 ME-02-93 -03 Rev. 1 'Stack Monitor Helium Compressor Cooling" 3.15 E'I-02-91-1065 Rev. 1 "Setting range determination for instrument loops SOT-DPIC-IAl, 1A2, lBI, and IB2" APPENDIX REFERENCES 4.1 1997 ASHRAE Fundaentals Chapter 15 Airflow Around Buildings 4.2 1997 ASHRAE Fundamentals Chapter 25 Ventilation And Infiltration 4.3 Drawing M810 Rev. 48 4A 1997 ASHRAE Fundamentals Chapter 26 Climatic Design Inputs 4.5 Basic Heat Transfer by Frank Kreith and William Z. Black (ISBN 0-700-22518-8), I Copyright 1980 4.6 1997 ASHRAE Fundamentals Chapter 28 Non Residential Cooling and Heating Load Calculations 4.7 Flow Of Fluids Through Valves, Fittings, and Pipe Crane Technical Paper No. 410 1 (Appendix 2) Twenty Third Printing 1986 4.8 Handbook of Hydraulic Resistance 3rd Edition I.Eldelchik ISBN 1-56700-074-6 (Appendix 2) 4.9 Specification SPC 28-00, 99 4.10 Specification SPC 28-00, 100 4.11 Heating Ventilating and Air Conditioning Analysis and Design Second Edition By Faye C. McQuiston and Jerald D. Parker ISBN 0-471-08259-7
F~ Cakc. No. WS129-CALC-001 " CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. PageNo. 11 of 150 ASSUMPTIONS GENERAL ASSUMPTIONS 1.1 No credit is taken for secondary containment outleakage. This assumption is based on the guidelines provided in Reference 1.1, which specifically states the following.
"No credit should be taken for secondary containment outleakage."
1.2 The wind speed to be assumed will be based on the extreme wind speed for the region that exceeds the 95% compliance value for the time as defined in Reference 1.12. The 17.2 mph at 33 feet value is selected as the high value documented in Reference 1.12. The guidelines provided in Reference 1.1 state the following. "The negative pressure differential to be maintained in the secondary containment and other contiguous plant area should be no less than 0.25 inches (water) when compared with adjacent regions, under all wind conditions up to the wind speed at which diffusion becomes great enough to assure site boundary exposures less than those calculated for the design basis accident even if exfiltration occurs." In addition, the guidelines provided in Reference 1.25 state the following:
"The effect of high winds on the ability of the secondary containment to maintain a negative pressure should be evaluated on an individual case basis. The wind speed to be assumed is the 1-hour average value that is exceeded only 5% of the total number of hours in the data set. Ambient temperatures used in these assessments should be the 1-hour average value that is exceeded only 5% or 95% of the total numbers of hours in the data set, whichever is conservative for the intended use (e.g., if the high temperatures are limiting, use those exceeded only 5%)."
The outside temperature to be used in the analysis will be selected from the warm (86°F) and the cold (28'F) values provided in Reference 1.12. Sensitivity studies will be used to determine which value to use for the long term analysis. The value that provides a more bounding result will be applied. Based upon the above, this assumption is considered appropriate and conservative. 1.3 Safety Related Room Coolers located throughout the Reactor Building that receive power from Divisions 1 and 3 will be credited in the analysis. The overall heat transfer coefficients for these room coolers are assumed to remain constant for the given flow rates defined in Reference 3.3. It is expected that the variation in the air temperature will change the overall heat transfer coefficient by no more than 5%. Therefore, the overall heat transfer coefficient will be reduced by an additional 5% after the reduction to 65% to account for fouling. 1.4 Flow Path Inputs are documented in Reference 3.7. 1.5 Reactor Building (RB) normal ventilation is excluded from the analysis. In actuality the normal ventilation is tripped and the supply and outlet valves are closed in 15 seconds
F- Caic. No. WS129-CALC-001 k CALCULATION CONTROL SHEET Rea. 0 ENERCON SERVICES, INC. Page No. 12 of 150 after the initiation of an accident signal . This is based on the allowable stroke time of the isolation valves documented in Reference 1.6. Based on quarterly surveillance stroke times from procedure OSP-CONT/IST-Q702 (Reference 1.22), the following are the nominal actual CLOSING stroke times of the RB ventilation supply and exhaust valves: VALVE TESTED CLOSE STROKE TIME, ALLOWABLE LCS Table 1.6.4.2 VALVE CLOSE STROKE ALLOWABLE TIME LCS ROA-V-1 6.5 SEC 15 SEC ROA-V-2 10.4 SEC 15 SEC REA-V-1 6.6 SEC 8 SEC REA-V-2 5.2 SEC 8 SEC During this short time, the flow for both the supply and the exhaust will coast down toward zero. The mass balance of these two systems will cancel each other. 1.6 The SGTS fan performance characteristics are to be included in this evaluation. The basis for this assumption is found in Reference 1.1, which states the following.
"Fan performance characteristics should be considered in evaluating the depressurization of the secondary containment."
1.7 Service water to the room air coolers and fuel pool cooling heat exchanger is assumed to be 78°F for the first two hours. This temperature represents a bounding average water temperature for the ultimate heat sink at the beginning of the accident as demonstrated every 24 hours by plant surveillance (Reference 1.30), which shows an upper temperature limit of 77°F. For analysis purposes, after two hours the service water temperature is immediately increased to 87 0F for the remainder of the analysis. This conservative approach is used to accommodate the simplified room cooler modeling approach. This approach uses tables based on two cooling water temperatures for each room cooler, rather-than the hourly variations used in Reference 3.6. The use of these temperature values ignores the benefits of daily changes in ambient temperature and solar heat gain that allow for the cooling of the ultimate heat sink as demonstrated in Reference 3.6. In effect, a constant ambient condition is used, which is consistent with Reference 1.25, Section 4.3. 1.8 SGTS fan discharges to the elevated release (Reference 2.10). Any pressure reduction associated with wind effects is not credited. Since the elevated release exhausts upward from the roof of the building, it is appropriate to consider a negative or zero wind pressure contribution. The zero value will be applied in this analysis. This assumption is used to bound the discharge pressure of the fan and thus its most limiting performance condition. 1.9 The SGTS Fan Performance is assumed to be based upon the vortex damper at 25% Closed. For the purpose of this calculation, the SGTS fan will be considered to be running at 4800ACFM. This value is the indicated reading or ICFM as seen on the flow recorder in the control room. As shown in Reference 3.8, the upper limit of the fan is 5378 ICFM. Using the uncertainties and margin, the ICFM is reduced to 4800 ICFM. Additional margin is realized in using the indicated flow as actual flow in the SGTS.
w-!Y;,- .Caic. No. WS129-CALC-001 A, CALCULATION CONTROLSHEET Rev.1 ENERCON SERVICES, INC. Page No. 13 of 150 Using the correction factors for the SGTS Annubar flow sensor, Reference 3.10, at 70% Relative Humidity (RH) and 105 0F temperature (design RH and heat from the SGTS heaters), the actual SGTS fan flow would be 5446 ACFM. The 25% closed value was selected to provide a conservative response for the building pressure returning below the negative 0.25inch minimum requirement This is considered conservative, since when the system first starts it is expected that the vortex damper would be fully open. 1.10 The ability of the SGTS to establish the desired negative pressure is based on the greatest negative effect caused by the wind, while the boundary conditions (used to determine inleakage) will use the average pressure for the four sides. In terms of measurement and control, the negative value is bounding since the SGTS is attempting to drive the building pressure to a value of 0.25 inH20 below that which it measures and therefore, the inside pressure to be controlled is forced to a lower absolute value. The implementation of the control system in the plant compensates for the location of the pressure sensors and the design atmospheric conditions by setting the setpoint at 1.7 inH20 (based on the Analytical limit of -0.71 inH20 per Reference 3.15) below that which is measured at most limiting location. Similarly, the GOTHIC models' success will be measured by the greatest negative effect caused by the wind, while the boundary conditions will use the average pressure for the four sides. This is not as great a contradiction as it may sound since the building will in fact experience these different wind pressure effects across its surface, and the pressure control evaluates all four sides and uses the most limiting. The one exception to this approach is the leakage at the railroad door where only one side of the building is involved with leakage. 1.11 The Leakage Flow Split between the upper and lower elevations of the reactor building is assumed to be 70% to 30% split The selection of this conservative split is established based upon specific testing that was done for Columbia Station to determine the relative leakage at different locations into the building. The testing, Reference 1.20, produced a set of results that indicate that leakage from the railroad door is around 10% of the total Reactor Building Secondary Containment Leakage. Since the differential pressure at the railroad door elevation is higher, as demonstrated in the calculation inputs development, a greater leakage assumption at this elevation is conservative. This will be demonstrated further in the analysis runs where a sensitivity study on the flow split will be conducted. 1.12 The initial temperature of the volumes in the three volume model is 75 0F for the main building, refueling floor and the pump rooms. The initial temperature of the volumes are based on a reasonable operational temperature for the reactor building. The initial temperature is based on a review of the normal ventilation system operation using the initial outside ambient air condition specified for this analysis. 1.13 The Fuel Pool Cooling system is started manually by control room operators. Since actions are required to put this system into service by realigning the Standby Service Water (SW) system. The current requirement is to place the system into operation when the 125TF pool temperature limit is reached if the normal cooling is lost and not expected to be restored. No time limit is stated. Sensitivity studies will be performed to determine what delay if any is acceptable. The criteria associated with an acceptable delay is based
V Caic. No. WS129-CALC-001 4 CALCULATION CONTROL SHEET Rev. ENERCON SERVICES, INC. Page No. 14 of 150 on the ability to maintain the secondary containment reactor building below negative 1I 0.25inch water. It is important to note that other restrictions on fuel pool temperature such as fuel temperature and fuel pool structural limits may be more bounding. The delay time established for this analysis may not be acceptable for these other considerations. However, if the other considerations require an early start of the fuel pool cooling system, then the assumption used for this analysis would be bounding since an earlier start time would be required. 1.14 For the purpose of calculating boundary and initial conditions, the ground level pressure is assumed to be 14.696 psia. I1 1.15 The roof level leakage point is assumed to be I foot below the reported roof elevation. This elevation is selected to provide an upper limit on the wind velocity, which will produce a pressure effect on the corrugated sides of the upper reactor building. 1.16 The ECCS room coolers are available to provide cooling 300 seconds after the start of the event. This value is based on the sequence of events documented below. 0 seconds LOOP/LOCA/SW Pump Trips 15 seconds DG Load/ECCS Room cooler fans start/Begin SW start sequence 123 seconds SW-P-IA start 128 seconds SW-PS-IA at 52psigfSW-V-2A starts to open 142 seconds SW-V-2A stops at 20% open for time delay 190 seconds SW-V-2A continues opening 300 seconds Full flow in the ECCS room coolers 1.17 The SGTS fan is assumed to start 120 seconds following the LOOP/LOCA. 1.18 The SGTS fan flow is assumed to be limited to 4,800 ACFM.
Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 15 of 150 VOLUME ASSUMPTIONS 2.1 The total air volume used for Secondary Containment Drawdown analysis is conservatively developed by maximizing the air volume. This conservatism is accomplished using the volume information documented in Reference 3.1. This assumption is based on two basic issues associated with the drawdown analysis. As addressed by Reference 1.1, the allowable leakage is based on one air change per day. Therefore, the larger the air volume assumed the larger the air change per day that is to be expected. The second is that the larger the air space volume the more mass that must be removed to reduce the pressure. 2.2 The volume of the fuel pool is excluded from the air space volume calculation. It is, however, included in the GOTHIC thermal inputs to represent the fuel pool. Although assumption 2.1 identifies the benefit of an over estimate of the air space, the additional conservatism associated with counting the fuel pool is not warranted. 2.3 The secondary containment is modeled as three nodes. The first of these nodes is the pump rooms located on the 422.25' elevation; the second is the main building volume of the reactor building including the railroad bay up to the refueling floor; and the third is the refueling floor. This nodalization was selected to represent the major separations within the reactor building. The refueling floor is selected as one of the volumes since it contains a spent fuel pool and has associated with it, the upper RB siding, which is one of the leakage paths to the outside environment. The pump rooms are all located at the same elevation and contain significant thermal heat loads. They are also in communication with the suppression chamber of the primary containment via heat conduction. The remainder of the reactor building is generally connected by a large open hatch allowing for relatively free communication throughout and thus behaving like a single volume. This region also contains a number of small rooms that contain heat sources and associated safety related room coolers. Combining these rooms with the remainder of the building produces a conservative result. This is based on how the impact of the room heat loads affects the building pressure. Combining these volumes allows the room heat loads to directly impact the main building pressure and temperature. This modeling approach also reduces the effectiveness of the associated room coolers ability to remove this heat, since the resulting temperature is reduced with the increased volume. The air temperature reduction for the rooms artificially minimizes the temperature difference between the air and cooling water that services these coolers. Therefore, the heat removal provided by the coolers is under predicted. 2.4 Any Secondary Containment volume calculated in Reference 3.1 that is associated with the 422.25' elevation, but not the pump rooms is incorporated into the main building volume. These volumes are typically associated with stairwells, air locks, and condensate/CRD pump room areas. The inclusion of these volumes is appropriate and since they are not directly in communication with the pump rooms their inclusion in the main building volume is the logical choice. It should be noted that the pump rooms extend above the 441' elevation to the 471' elevation.
Fr. CaIc. No. WS129-CALC-001 r 3 CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 16 of 150 DIRECT HEAT INPUT ASSUMPTIONS 3.1 The heat load assumed for the Reactor Building is based on Division I & 3 loads, which include HPCS, LPCS and RHRA. The use of Division I & 3 loads maximizes the pump loads to the building, assuming one division of AC power is lost. Pumps and other auxiliary loads associated with Division II are excluded from the list. 3.2 The heat loads documented in Reference 3.3 that are associated with heat transfer from piping and walls are handled explicitly with heat conductors modeled with GOTHIC. This assumption provides a more realistic representation of these heat loads and eliminates excessive conservatism associated with using them as direct heating loads, which is appropriate for Reference 3.3, but inappropriate for this analysis. 3.3 The spent fuel pool decay heat load is 9,794,000 BTU/hr from the value reported in CMR 2449 to Reference 3.6. This value is maintained constant for the entire analysis period, which is considered to be conservative as decay heat will decrease with time. 3.4 The emergency lighting heat loads are assumed to start at approximately 0 seconds and operate continuously. The power to the emergency lights will be lost until the SL-7 1 bus is re-powered from the emergency diesel generator. This will occur 15 seconds after the LOOP. The heat load of the lighting will not be reduced by a large amount during the 15 seconds the lighting is off. Assuming the emergency lighting is on at time zero is conservative. 3.5 The emergency lighting heat loads are assigned to the main reactor building volume. This is a simplification, but is considered reasonable since the majority of these loads are located in the main building. The total emergency lighting load is reported in Reference 3.12 to be 203,700.00 BTUfhr. The referenced material used to establish heat loads specifies the emergency lighting loads for certain areas. These are a subset of the 203,700 BTU/hr and are used to reduce this value when they are explicitly defined. However, in the case when they are reported as combined values with other loads the lighting is not subtracted as described above. The net result of this is that these lighting loads are counted twice, once as a portion of the combined value and once as a portion of the total emergency lighting load. 3.6 The normal lighting is lost immediately and considered to have negligible heat dissipation. 3.7 Normal operating equipment no longer running during the analysis is assumed to dissipate heat based on an exponential decay relationship. This relationship is developed in this calculation.
Caic. No. WS129-CALC-00l Fi 3 CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 17 of 150 THERMAL CONDUCTOR ASSUMPTIONS 4.1 Piping systems that provide heat to the reactor building are modeled as heat conductors. These are associated with HPCS, LPCS, RHRA, and fuel pool cooling. The heat load assumed for the reactor building is based on Division I & 3 loads, which include HPCS, LPCS and RHRA system piping. The use of Division I & 3 loads maximizes the pump loads to the building. The inclusion of these system piping heat loads follows from the pump selection. 4.2 The heat loads associated with the ECCS pumps will be modeled with a tube geometry having an internal temperature boundary condition that matches the Post LOCA suppression pool temperature response. Since the analysis is an assessment of the Reactor Building heat gain following a LOCA, it is appropriate to apply the suppression pool temperature response when accessing the heat loads associated with the system operation following a LOCA. 4.3 The fuel pool cooling piping will provide a heat source following the start of the fuel pool cooling system. The internal boundary condition will match the fuel pool temperature. 4.4 Thermal conductors are assumed to be initially in thermal equilibrium with their boundary conditions. This allows the boundary condition to have a properly established initial temperature profile. 4.5 For the primary containment thermal conductors, the initial thermal profile will be a linear profile starting on the interior with the containment temperature and dropping across the conductor materials to the reactor building temperature. For conductors with the outside ambient as one of the boundary conditions, the temperature profile will be a constant value equal to that assumed for the Reactor Building. The reason for this is that the outside ambient boundary condition is assumed to be adiabatic, as required by Reference 1.1. The heat transfer from the building to the surrounding atmosphere is ignored. These boundaries are treated as adiabatic. This assumption is based on Reference 1.1, which states the following.
"Adiabatic boundary conditions should be assumed for the surface of the secondary containment structure exposed to the outside environment."
4.6 Piping insulation is assumed to be Calcium Silicate as reported in Reference 3.3. 4.7 Polyurethane thermal properties are given in Reference 1.31. Fiber Glass properties are assumed to match that of Glass Wool Packed reported in Reference 1.13. Calcium Silicate properties are obtained from Reference 1.16. 4.8 The Equipment Pool is assumed to be drained. This is the normal configuration with the plant operating, which is the assumed conditions at the start of the analysis. 4.9 The primary containment structure that is in communication with the secondary containment atmosphere will be assigned a convective boundary condition that uses a temperature profile which corresponds to the most bounding accident profile for the primary containment (Reference 1.21). To accomplish this the Main Steam Line Break is
3II1 Caic. No. WS129-CALC-001 M CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 18 of 150 used for the short term response and the Main Steam Line Break, Large LOCA and Small Break LOCA are used to represent the long term response. This composite temperature profile is developed in Reference 1.21. The combination profile is a conservative representation of the containment response, which is the basis for the assumption. The need to include this type of boundary condition is found in Reference 1.1, which states the following.
"Heat Transfer from the primary to secondary containment should be considered." This assumption considers such a phenomena using a bounding temperature profile.
4.10 The Heat Transfer coefficient between the primary containment atmosphere and the primary containment structure is assumed to offer virtually no resistance to heat transfer in the early portion of the accident. This is a reasonable assumption since the highly turbulent blowdown conditions will offer significant heat transfer opportunity in conjunction with condensation on the containment walls. The long term response assumes a constant heat transfer coefficient that is smaller. The value is selected to conservatively represent the heat transfer to the structure. Specifically, the coefficient is assigned to drive heat into the wall while minimizing the cooling benefit that the atmosphere may offer later in the event. This approach is consistent with that documented in Reference 1.1, which states the following.
"Heat transfer from the primary containment atmosphere to the primary containment structure should be calculated using conservative heat transfer coefficients such as those provided in Branch Technical Position CSB 6-1."
This analysis will not directly use the CSB 6-1 values, but will maintain the conservative nature intended by Reference 1.1. The determination of heat transfer coefficients within primary containment is a dynamic calculation dependent upon fluid and structure temperatures. Further complicating the calculation is the condensate rate, which is influenced by the number of non-condensable gases present. Therefore, to properly implement the CSB 6-1 approach it is necessary to model the primary containment response in detail. Rather than use this complicated approach, a bounding approach will be used. The values selected are established in the heat transfer portion of this calculation. 4.11 Radiant Heat Transfer between the Primary Containment Outer wall and the Secondary Containment Atmosphere will be accounted for in the analysis. This assumption is based upon Reference 1.1, which states the following:
' Radiant heat transfer to the secondary containmnent should be considered."
Radiant heat transfer between other heat structures is ignored as these structures are typically cooler and exclusion of this feature is deemed to be conservative for this type of analysis. 4.12 The primary containment wall is assumed to be composed of a steel vessel and concrete. Any air gap or insulating material is not accounted for as they would serve to hinder the heat transfer to the Reactor Building. The containment vessel (Drywell Wall Steel Liner) is assumed to be 1.5 inch carbon steel plate. The actual liner has varying thickness based on location. In some cases, the thickness is less than 1.5 inches. However, the very conservative exclusion of the air gap described above allows this simplification without
41 Caic. No. WS129-CALC-001 R2z]". ENERCON SERVICES, INC. CALCULATION CONTROL SHEET Rev. I Page No. 19 of 150 any reduction in the models' overall conservative approach. 4.13 The reactor building roof will be treated as an 18 gage steel sheet All other material associated with the roof will be ignored. Since the roof is treated as adiabatic, this assumption will be conservative because the overall heat capacity of the roof will be reduced. Reducing the heat capacity of the roof forces the model to calculate a greater amount of energy maintained in the building atmosphere, thus producing a conservatively higher pressure. 4.14 It is assumed that the temperature in the D104 corridor is 104TF. This value is selected to bound that expected under normal or accident conditions. The convection resistance that exists between the air in the corridor and the wall is ignored and the boundary condition of the conductor is set to 104 0F. The temperature and the convection assumptions are used to conservatively minimize heat transfer from the pump rooms to the corridor. 4.15 The wetwell composite profile, Table 37, is composed of the data extracted from Reference 1.19 up to the end of that curve. The Wetwell composite profile is set at 200 0 F for the duration to the end of the analysis. This higher Wetwell composite profile is a conservative assumption.
Calc. No. WS129-CALC-001 Ea ENERCON SERVICES, INC. CALCULATION CONTROL SHEET Rev. Page No. 20 of 150 0 BOUNDARY CONDITION ASSUMPTIONS 5.1 The Terrain in the area of the Meteorological Tower, as well as the Reactor Building, are judged to be open terrain with scattered obstacles generally less than 30 feet high. DESIGN INPUTS
- 1. Wind Speed 17.2 mph Reference 1.12
- 2. Outside Air Temperature 860F/28 OF Reference 1.12
- 3. Initial Service Water Temperature 770F Reference 1.30
- 4. Service Water Temperature is a function of time established in Reference 3.6 S. Fuel Pool Cooler Pump Flow 575 gpm Reference 3.5
- 6. Fuel Pool Cooler Service Water Pump Flow 575 gpm Reference 3.5 METHODOLOGY The GOTHIC inputs documented in this calculation are based upon engineering standards and no new methods or experiments are used in their development. MATHCAD software (Reference 1.26) is used to calculate these inputs, which is an accepted tool in the industry and used at ENERGY NORTHWEST. The MATHCAD file is provided in Appendix 1. The inputs are developed specifically for use in the EPRI GOTHIC 7.1 thermal hydraulic analysis software (Reference 1.2). The analysis portion is performed using the aforementioned GOTHIC software, which is an industry recognized program for thermal hydraulic analysis of this type.
i Calc. No. WS129-CALC-001 l CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 21 of 150 MODELING INPUT DEVELOPMENT BOUNDARY CONDITION INPUTS: The boundary conditions to be used in the model were modified to account for the wind conditions and pressure information calculated in Appendix 1 and 3. The basis for the pressure and temperature values are established using ASHRAE methods applied and documented in Appendix 1 and 3. The resulting boundary conditions are listed in Tables 4 and 5. The following discussion provides a derivation of the boundary condition pressures established for the door and roof line leakage paths. These pressures are calculated as the total stagnation pressure acting on the building leakage locations. For a given wind speed, wind direction and temperature the dynamic and static pressures are calculated for the building leakage locations. The first step is to calculate the static pressure contribution which is a function of temperature and elevation. This is followed by the determination of the wind pressure contribution which is a function of temperature, elevation and wind velocity. The relationship used to establish the static pressure outside as a function of height is based on the Bernoulli equation (Reference 1.32) and is defined as follows. (Equation 1) PoElev(EL,Temp) = Patm - p(Temp)*(EL-441ft)*g*C Where EL is the elevation of the location of interest, Temp is the air temperature, g is the gravity constant and C is the unit conversion constant The ground level pressure is Patm at 441feet. Patm= 14.696psi (Assumption 1.14) g = 32.2ftlsec 2 (Reference 1.32) For the static pressure at the top of the railroad door the following values are used. Twin = 86°F (Design Input 2, Reference 1.12) ELRRDoor = 441ft + 28ft = 469ft (Reference 3.1) The static pressure at the roof line is calculated in a similar manner using the following values. Twin = 86"F (Design Input 2, Reference 1.12) ELRoof = 667ft (Assumption 1.15 and Reference 3.1) The density of the air is calculated using the ideal gas law (Reference 1.32) p(860F) = 0.0731b/ft9 The static pressure at the door elevation 469ft is PoElev(469ft, 86 0F)= 14.68186psi The static pressure at the roof elevation 667ft is
Caic. No. WS129-CALC-001 hi CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 22 of 150 PoElev(667ft, 86F) = 14.58189psi The wind induced pressure effect is calculated using the Bernoulli Equation (Reference 4.2) along with the appropriate wind pressure coefficients (Reference 4.1) as follows. This analysis assumes the terrain category of the Met Tower is Category 3 and the reactor building is also Category 3 (Assumption 5.1). Table 1 - Terrain Category Terrain Description Exponent "a" Layer Thickness Category 1 Large city centers, in which at least 0.33 1500 50% of buildings are higher than 70ft, over a distance of at least 6500ft upwind__ _ _ _ _ 2 Urban, suburban, wooded areas, and 0.22 1200 other areas with closely spaced obstructions compared to or larger than single family dwellings (over a distance of at least 6500ft upwind) 3 Open terrain with scattered obstacles 0.14 900 generally less than 30ft high. 4 Flat, unobstructed areas exposed to 0.10 700 wind flowing over a large water body (no more than 1600ft inland) These categories are used to establish the appropriate wind velocities at the site as a function of elevation. The boundary condition-values are developed using the MathCad software. Since this software understands and converts engineering units, some of the conversions are not explicitly documented in the following derivations. (Equation 2) Pw(V, Temp, Hmet, Hbuild, Cp) = Cp
- p * (UH (Met, Build, V, Hmet, Hbuild))2 27.7 lin z g psi Where V is the wind velocity in miles per hour, Temp is the outside air temperature (°F), Hmet is the met tower height (ft) where the wind speed is measured, Hbuild is the height (ft) were the pressure effect is calculated, Cp is the wind pressure coefficient, Press and Temp are the pressure and temperature used to establish the air density.
Calc. No. WS129-CALC-001 Fvl CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 23 of 150 UH is a function used to convert the measured wind velocity to wind velocity at the point of interest, such as the door or roof line. Equation 3 provides specifics of the function. Met = 3 and Build = 3 are the Terrain categories (Assumption 5.1 and Reference 4.1). Using a met tower wind speed of 17.2 mph, Reference 1.12, the door level velocity is calculated in Appendix I to be 16.809 mph and the roof level velocity is calculated in Appendix 1 to be 22.517 mph. VWDVD = K 900O( HBuild I (Equation 3) WE z~tMai) t 900ft) The wind pressure coefficient is developed in Appendix 3 of this document. These coefficients are established for the upper and lower leakage paths as well as the location of instrumentation credited in the analysis. The wind pressure coefficient is used to account for the wind direction on the surface of the building. The values used in this analysis are summarized in Table 2. Note that the wind pressure coefficients for the instrumentation are based on incident angles used in the analysis.
aic. No. WS129-CALC-001 Fs-`3CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 24 of 150 Table 2 - Local Wind pressure coefficients as a Function of Wind Incident Angle and Location Building Face Average Local Average Local Average Local Average Local Wind Incident Wind pressure Wind pressure Wind pressure Wind pressure Angle coefficient For coefficient coefficient coefficient Upper Surface Pressure Pressure Railroad Door Instrument 1A4 Instrument A3 _ 00 0.638 NOT USED NOT USED 0.517 150 0.63 NOT USED NOT USED NOT USED 300 0.466 0.25 NOT USED NOT USED 450 0.238 NOT USED NOT USED 0.5 600 -0.0294 -0.10 NOT USED NOT USED 750 -0.415 NOT USED NOT USED -0.50 900 -0.738 -0.55 -0.90 -0.85 1050 -0.685 -0.742 NOT USED NOT USED 1200 -0.619 NOT USED NOT USED -0.50 1350 -0.5597 -0.65 NOT USED NOT USED 1500 -0.545 NOT USED NOT USED -0.35 1650 -0.47 NOT USED NOT USED NOT USED 1800 -0.403 NOT USED NOT USED NOT USED The values provided in Table 2 include information that is used to assess test data used in the development of the building leakage relationships. These values are applied later in this document. For Secondary Containment drawdown analysis purposes, two wind directions are evaluated, which include winds from the East and winds from the South East The wind coefficients applied to each area of interest is documented in Table 3. Table 3 - Wind Pressure Coefficient Assignment and Wind Incidence Angle Case Upper Upper Upper Upper Rail Road Pressure Building Building Building Building Door Wind Instrument South Face North Face East Face West Face Pressure Wind Wind Wind Wind Wind Coefficient Pressure Pressure Pressure Pressure Pressure (CpRR) Coefficient Coefficient Coefficient Coefficient(I Coefficient (Incident (Incident (Incident (Incident ncident (Incident Angle) Angle) Angle) Angle) Angle) Angle) Analysis -0.738 -0. 738 0.638 -0.403 0.517 -0.90 Value Wind (90°) (900) (00) (180°) (0°) (900) Direction Instrument From East _A3 Analysis 0.238 -0.5597 0.238 -0.5597 0.5 (450) -0.65 Value Wind (450) (1350) (450) (1350) (1350) Direction Instrument From South IA4 East (Wind Angle 1350) At the door and roof level, the wind induced pressure is calculated as follows for an Easterly wind direction. This wind direction is assigned a wind angle of 900, and has a 0° incidence angle on the eastern wall where the Railroad Bay door exists (Refer to Appendix 3 Figure 5).
FIt Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 25 of 150 Twin= 860F Vwin= 17.2 mph At the door level, the calculation uses the Railroad Door Coefficient CpRR as follows. (CpRR(90))p)(14.6 pi860F)UH(Met,Build,VWin,HmetLowELRRDoor-44lft) 2 27.71in 2*g psi
= 0.06832in where CpRR(90') is the wind pressure coefficient for a wind angle of 90° = 0.517 p(14.696psi,86' F) is the density of the air = 0.0731bMft3 UH is the wind velocity as a function of the terrain conditions = 16.809mph Met, Build documented in Table 1= 3,3 measured velocity (VWin) = 17.2mph Height of the measurement (HmetLow) = 33ft Elevation of the building where the calculation is perfomrmed (ELRRDoor) = 469ft TWin = 86°F At the roof level, the calculation uses the wind coefficient for each upper face. The Easterly wind has a O° incident angle on the Eastern Wall, 900 incident angles for the North and South Walls, and 1800 incident angle for the Western Wall. As shown in Appendix 1, the wind incidence at the roof level is a weighted average of the four sides.
CpU(90 0) 0.738 - 0.738X149ft)+ (0.638 - 0.403X133ft) 0 2(149ft + 133ft) --. 3 CpU(90°)
- p(14.696psi,86°F)Um (Met, Build, MWin, HmetLow, EL.Roof - 441ft)2 27.71in 2 psi
=-0.07945in Where ELRoof is the building elevation where the calculation is performed. ELRoof = 667ft.
Calc.No. WS129-CALC-001 M CALCULATION CONTROL SHEETRev. 0 ENERCON SERVICES, INC. Page No. 26 of 150 The total pressure for the boundary conditions is the total of the static and wind effect pressures. The pressure boundary condition at the door is as follows. 14.68186psi +0.06832in 27 = 14.68433psi 27.71in The pressure boundary condition at the roof is as follows. 14.58189psi - 0.07945in lpsi = 14.57903psi 27.71in Note that when evaluating the success of building pressure reduction efforts, the minimum exterior pressure is used based on the above relationships applying the minimum wind pressure coefficient for the roof elevation. Refer to assumption 1.10 for additional discussion. Table 4 - High Temperature Boundary Condition Inputs Used For Leakage Calculations Fluid Boundary Conditions Easterly South Wind Easterly ________ Wind _ _ _ Press. Temp. Press. Temp. Description (psia) (F) (psia) (F) Roof Leakage 14.57903 86 14.58052 86 Gound Leakage 14.68433 86 14.68425 86 Elevated Release 14.58189 86 14.58189 86
Calc. No. WS129-CALC-001
@-.na CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 27 of 150 Table 5 - Low Temperature Boundary Condition Inputs Used For Leakage Calculation Fluid Boundary Conditions Easterly South Wind Easterly Wind Press. Temp. Press. Temp.
Description (psia) (F) (psia) (F) Roof Leakage 14.56511 28 14.56678 28 Gound Leakage 14.68294 28 14.68285 28 Elevated Release 14.56832 28 14.56832 28
F ,aX Calc. No. WS129-CALC-001 9 CALCULATION CONTROL SHEET Rev. 1 IENERCON SERVICES, INC. Page No. 28 of 150 INITIAL CONDITION INPUTS: The control pressure for the secondary containment building at the sensing elevation of 576ft-6in is calculated and used to establish the building initial conditions. This building pressure is calculated for both the 95% and 5% temperature values, Reference 1.12. From these values, the initial condition for each of the building volumes is calculated at the corresponding volume center. The building initial conditions are established using the outside pressures developed above along with the outside pressure at the instrument tap for the SGTS elevation 576ft-6in. The approach is to determine the SGTS control differential pressure that is required to ensure the worst case pressure difference in the building is 0.25inch WG. The control pressure is evaluated for each of the three elevations of interest, which include the door, the upper structure and the instrument tap itself The mathematical relationship (based on Bernoulli Equation Reference 1.32) used to determine the inside pressure is provided in Equation 4. Pinside= Pcontrol- p(TinsideXElevation - 576.5ft)g (Equation 4) The internal pressure as a function of elevation is simply the pressure at the control elevation (576ft 6in) adjusted for the elevation change within the building. The arguments used in determining the control elevation pressure are as follows.
- Tinside is the building temperature
- p is the density of the air based on building temperature
- Elevation is the elevation of the inside pressure being calculated
- g is the gravitational constant
- Pcontrol is the pressure inside the building at the instrument elevation The control pressure (Pcontrol) is calculated using Equation 5.
Pcontrol= (Poutside+ Pwind + APsp) lpsi (Equation 5) 27.71in The terms included in this relationship are
- Outside Static Pressure (Poutside) defined previously (Equation I) in the boundary conditions section of this calculation to be a function of elevation and temperature
- Wind induced pressure increase (Pwind) defined previously (Equation 2) to be a function of wind direction, wind speed, outside air temperature and elevation.
- Finally, the control setpoint (APsp) is found using a MathCAD Solve routine based on ensuring that the building pressure satisfies the negative 0.25inch water gauge criteria.
As can be seen, the control pressure is simply the total outside pressure added to the setpoint value. The setpoint differential pressure (APsp) is selected to ensure that the pressure difference at the three elevations is maintained at no less than negative 0.25inch WG. A MathCAD function is defined to evaluate the setpoint pressure difference value for each of the locations. Equation 6 shows the relationships used to evaluate the pressure differential based on Equations 1, 2 and 4.
Calc. No. WS129-CALC-001 tiE CALCULATION CONTROL SHEET Rev. 1 ENERCON SERVICES, INC. Page No. 29 of 150 (Equation 6) APiPoElev [{PiElev(TempOut,Templn,H,V,APsp, Cplnstronment) - PoElev(H,TempOut)} psi
- Pw(V,TempOut, Hmet, H - ELBuildLow,CpWall)]
where PoElev(H,TempOut) Outside Pressure Function Based on Equation 1 Pw(V,TempOut, HmetH - ELBuildLow,CpWall) Wind Pressure Function Based on Equation 2 PiElev(TempOut,Templn,H,V,APsp,CpInstrument) Inside Pressure Function Based on Equation 4 Notice that the function uses two wind pressure coefficients (CpWall and CPlnstrunment). The first of these is used to establish the internal pressure based on the control pressure defined in Equation 5. The second is used to evaluate the wind pressure applied to the wall being evaluated. When considering the instrument location, these values are the same as illustrated below.
Caic. No. WS129-CALC-001 C:t CALCULATION CONTROL SHEET Rev. ENERCON SERVICES, INC. Page No. 30 of 150 The mathematical evaluation used to determine the setpoint control is illustrated below. The approach is to solve for the required APsp value to ensure negative 0.25in pressure difference exists at the roof, railroad l I door and instrument locations. Notice that the solve routine requires a seed value, which in this case is - 0.50in. A seed value is provided only to begin the calculations iterative solution. The value has no impact on the result it simply provides a place to start in obtaining a solution. For each elevation, the setpoint is solved to satisfy the negative 0.25in criteria. The value to be used will be the minimum of the I three calculated. The example that follows is based on a wind from the East with the "1A3" instrument I providing control of building pressure. APspWin :=-0.501in Given APiPoEle(TmaxTBuild, ELBuildHigh VWin, APspWin, CpInst(" 1A3 ",90) ,CpUMin(90)) = -0.25i. APspWinU:= Find(APspWin) Given APiPoEle4Tmax,TBuild, ELInst, VWin, APspWin, Cplnst(" IA3 ",90),Cpunst(" 1A3", 90)) = -0.25in APspWinI := Find(APspWin) Given APiPoEle4TTmax, TBuild, ELKingKongDoorTop, VWin, APspWin ,Cplnst(" IA3", 90),CpRR(90)) = -0.25in APspWinL := Find(APsp Win) Tmax= 86Fahr APspWinL = -0.028 in APspWinU = -0. 2 14in APspWini = -0.25 in Because of the wind pressure coefficient assignment, the instrument location provides the controlling pressure differential and the resulting initial pressures are calculated using this value.
Calc. No. WS129-CALC-001
&v2M CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 31 of 150 The initial pressure of the control volume is calculated as follows.
PInstWin = PiElev(TempOut, Templn, H, V, APsp, CpInstrument) PInstWin = 14.612psi With the internal pressure established at the instrument location (Pcontrol) the initial pressure in each of the volumes of the GOTHIC model can be determined using Equation 4. The GOTHIC code assigns the pressure to the center of the volume, therefore, the center elevation of each of the volumes is calculated as part of the calculation of the initial conditions. Volume 1 represents the main portion of the Reactor Building between the pump rooms and the refueling floor. The instrumentation that measures pressure is included within this volume and the pressure change between the center of the volume and the instrument location is calculated using the temperature of the main reactor building volume. ELCenterVI = ELMain + HTMain/2 ELMain= 441ft HTMain= 163.875ft ELCenterVl = 522.938ft PinitialConditionVI = 14.612psi + (576.5ft - 522.938ft)(0.0741b/ft 3 )(gc)(1ft2 /144in 2 ) PinitialConditionVI = 14.63949psi Volume 2 is used in support of the SGTS modeling and is within the main volume described by Volume 1. The volume height and elevation values are arbitrarily established based upon elevations information for the SGTS system provided in Reference 2.8. ELCenterV2 = 577ft + 1.5ft/2 ELCenterV2 = 577.75ft PinitialConditionV2 = 14.612psi + (576.5ft - 577,75ft)(0.0741b/ft3)(gc)(1ft2/144in2) PinitialConditionV2 = 14.61125psi Volume 3 This volume is used in association with cooling water modeling and has an arbitrarily assigned initial pressure.
Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 32 of 150 Volume 4 represents the pump rooms at the lowest elevation of the building. The elevation pressure change associated with the calculation of Volume 4 initial pressure includes both Volume I and Volume 4. The relationship is divided to accommodate different densities between the two volumes. ELInst = 576.5ft ELPumpRm = 422.25ft HTPumpRm = 46.75ft The pump room and main building temperatures are assumed to both be 75 0F and therefore, have the same density. PinitialConditionV4 = 14.612psi + (576.5ft-(422.25ft+46.75ft)) )(0.0741b/ft 3)(gc)(I ft2/144in 2 )
+ (46.75ft/2) (0.0741b~fl?)(ge)(1ft0144irte)
PinitialConditionV4 = 14.67933psi Volume 5 represents the refueling floor at the highest elevation of the building. The elevation pressure change associated with the calculation of Volume 5 initial pressure includes both Volume I and Volume 5. The relationship is divided to accommodate different densities between the two volumes. ELInst = 576.5ft ELRefuelFloor = 604.367ft HTRefuelFloor= 63.303ft ELCenterV5 = ELRefuelFloor + HTRefuelFloor/2 ELCenterV5 = 636.018ft The refuel floor and main building temperatures are assumed to both be 75F and therefore, have the same density. PinitialConditionV5 = 14.612psi + (576.5ft-604.367ft )(0.0741b/ft3 )(gc)(I ft2 /144in2 )
+ (604.367ft-636.018ft)((0.0741b/f&)(gc)(1 ft2 /144in2 )
PinitialConditionV5 = 14.58122psi The resulting initial conditions for the volumes are documented in Tables 6 and 7. Table 6 - High External Temperature (86F) Initial Conditions INITIAL CONDITIONS Easterly Wind South Easterly Wind BUILDING ELEVATION BUILDING BUILDING BUILDING BUILDING PRESSURE TEMPERATURE PRESSURE TEMPERATURE Refueling Floor (Volume 5) 14.58122psi 75F 14.58307 75F Main Building volume (Volume 1) 14.63949psi 75F 14.64134psi 75F Pump Rooms (Volume 4) 14.67933psi 75F 14.6812psi 75F SGTS Volume (Volume 2) 14.61125psi 75F 14.61310psi 75F
F~rl Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEETRev. 0 ENERCON SERVICES, INC. Page No. 33 of 150 The Initial Conditions documented in Table 7 are calculated in the same manner as documented above, however, the cold outside air temperature value of 28°F is used. Table 7 -Low External Temperature (28°F) Initial Conditions INITIAL CONDITIONS Easterly Wind South Easterly Wind BUILDING ELEVATION BUILDING BUILDING BUILDING BUILDING PRESSURE TEMPERATURE PRESSURE TEMPERATURE Refueling Floor (Volume 5) 14.5682psi 75F 14.5699psi 75F Main Building volume (Volume 1) 14.62647psi 75F 14.62817psi 75F Pump Rooms (Volume 4) 14.6663psi 75F 14.66801psi 75F SGTS Volume (Volume 2) 14.59822psi 75F 14.59993psi 75F
Fn Calc. No. WS129-CALC-001 Md CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 34 of 150 CONTROL VARIABLE INPUTS This model uses control variables to calculate the leakage flow and assess building pressure response. To accomplish the first of these tasks, control variables are used in combination with flow boundary conditions to establish the volumetric leakage flow at the roof and railroad door leakage points. This approach is taken to allow for laminar as well as turbulent leakage into the building. Test data is used to develop the necessary relationships. Control variables are also used to calculate the pressure difference across the leakage paths. This simple calculation is required to modify the volume pressure calculated in GOTHIC at the center of the volume to correspond with the elevation of the leakage path. LEAKAGE FLOW PATHS CONTROL VARIABLES The drawdown model includes leakage into the building from two primary locations. These locations are the corrugated structure above elevation 612ft-10.5in, Reference 2.21, and the rail road door. The criteria for establishing these flow paths is the allowable leakage into the building for a given differential pressure of 0.25inches of water. The volumetric flow associated with this differential pressure is assumed to be one air change per day per guidance in SRP 6.2.3. For the calculation, the volume selected is based on the building volume established in this calculation, which has a total volume of 3,424,238.83ft 3 . This volume is calculated in the Volume Inputs section of this document, which corresponds to a leakage flow rate of 3,424,238.83ft 3 /[(24hr/day)(60min/hr)] = 2378cfin. The calculation in Reference 3.1 derives a volume of 3.477xW106 iV.This value is rounded up to a nominal value of 3.5x106 ft3. This corresponds to a leakage flow rate of 3,500,000f03 1[(24 hr/day)(60min/hr)I = 2430 cfin. This bounding conservative value will be used in the analysis. The leakage relationship documented in Reference 1.24 specifies that the leakage is based upon a combination of Laminar and Turbulent flows producing the following relationship. LeakageFlow = A
- DP + B * -5DP (Equation 7) where DP is the pressure differential A is the laminar flow coefficient and B is the turbulent flow coefficient To implement this flow model, a leakage flow control variable is linked with the GOTHIC flow boundary condition. Using this approach, the need to specify flow path criteria is not critical as they are not used to establish flow into the building. The only issue is to establish a reasonable area to ensure that the velocity of the entering fluid is not artificial and influencing the model with momentum effects.
F^~ lCaic. No. WS129-CALC-001 1 CALCULATION CONTROL SHEET Rev 0 ENERCON SERVICES, INC. Page No. 35 of 150 LEAKAGE MODEL DEVELOPMENT This section of the calculation documents the approach to be used when accessing the leakage flow model. Reference 1.20 provides data from a test of the secondary containment leakage. Reference 1.24 provides the basic relationship for a leakage flow correlation (Equation 7) to be used with the data relating the controlling differential pressure to the leakage flow rate. The data used to develop the coefficients "A" and "B" used in Equation 7 is provided in Table 8. The first step in this effort is to evaluate the data developed as part of the secondary containment leakage test. This initial evaluation will be used to establish an understanding of the data and how it will be applied. This data will be further evaluated using the pressure modeling methods previously described (Appendix 1). This later evaluation is used to transform the measured pressure into applied pressures at the roof and railroad door leakage points. Once the pressure conditions are understood at these locations, the data will be further evaluated to determine the characteristics of the leakage flow. This characterization of the leakage flow will be used to establish the Leakage Model used in the GOTHIC analysis. Table 8 - Reference 1.20 Data Description Variable Test 1 Test 2 Test 3 Test 4 Test 5 Test 6 Name Outside TWin 64 66 68 70 72 75 Temperature (F) Inside Tinside 80.5 82 80 80 79 79 Temperature Wind Speed VMet 13.52/12.6 7.8/9.9 12.63/14.2 13.6/15.3 13.4/14.2 5.617.3 (mph) SGTS Flow Leakage 2111 2017 2019 2032 2056 2539 Differential APmeasured 0.48 0.448 0.46 0.39 0.448 0.65 Pressure measured by Pressure Instrument 1A4 (inWG)__ _ _ ___ Wind Direction 175/180 156/170 172/183 177/188 175/185 241180 The approach to be used in this effort is to correlate the leakage data to the pressure differential at the roofline and the Railroad Bay Door using the control differential pressure. The first step in this effort is to convert the control differential pressure to corresponding pressures at the four sides of the roofline as well as the Railroad Bay door. The data provided in Table 8 contains a range of wind speeds and directions that may not be directly related. In addition, the Met Tower height used to measure the values reported is not known. A review of the data is conducted to determine how to apply this data given the aforementioned uncertainties. The impact of the values reported in the table will determine the contribution of the leakage that is laminar versus that which is turbulent. Specifically, the data will establish the coefficients used in the Equation 7 relationship.
Calce. No. WS129-CALC-001 _ CALCULATION CONTROL SECE ev. 2 ECON SERVICES, INC. Page No. 36 of 150 To determine the impact of the uncertainty, an evaluation of the data assuming the measurement was taken from the high Met Tower height (245fiet) and the low Met Tower height (33fect) was conducted. In addition, thc data was evaluated assuming the highest wind speed and the lowest wind speed. ihe evaluation used the methods that are described below for establishing the characteristis of the leakage. This evaluation showed that assuming the higher velociy listed in Table 8 is measured from the lower tower elevation produced {he largest laminar contribution of the leakage flows, or greatest "A" coefficient in Equation 7. The larger the lamfnar component CA") the greater the leakage flow rate for a given differential pressure (DP) as illustrated in Equation 7. The data was used to establish the maxirmu laminar component ("A"), since it maximizes the building leakage. Therefore, the analysis that follows will apply the assumption that the Met Tower measurement is from 33 feet using the highest wind speeds. With regards to the wind direction, the variability within the tests was considered to be sufficiently small that the average wind direction could be used. The one exception to this is the data documented in Test #6. While evaluating the Test #6 data, an inconsistency was revealed between the wind direction and the measured differential pressure. Specifically, this test produced a fairly high measured pressure differential, which is not expected for the instrument "IA4" location for either the reported 180° value or the average 2100 value. It is, however, consistent with the reported wind direction of 241°. Based on this evaluation, Test #6 is used assuming the wind direction is rounded to 240 °. A further adjustment of the data is required to address the issue of indicated versus actual flow documented for SOTS in Table 8. With regards to the SMTh flow, it is appropriate to adjust the flow values documented in Table 8 from an indicated flow to an actual flow using the results of calculation NE-02 06 (Reference 3.14). After the indicated flow is converted to actual it is further adjusted to account for fluid conditions entering the building from the outside. The first step is to apply a conservative correction factor to convert the Indicated CFM (ICEM values provided in Table B to Actual CFM (ACFM) values. The conversion is based on the temperature of the air at the annabar located downstream of the fan. This temperature value is calculated based on the inlet temperature with heat added from the 21 kW heater and the fan. For the given flows and tcrnperatures provided in Table 8 the maximum temperature is calculated in Appendix I (page 57) to be 130 0F. A review of the Reference 3.14 data tables indicates that We largest correction factor at the assumed 2 temperature results from 100/ humidity for the low barometric pressure (Refer to page 5.009 of Reference 3.14). This value of 1.2053 is applied to the data to obtain the Actual CFM for the test data. This correction is thus far associated with flow from within the building, while the leakage flow is from outside the building. The flow is further modified to account for leakage flow fom outside the building The approach is to simply establish the leakage flow necessary to conserve mass in the building. Therefore, leakage flow rate is calculated as follows. Leakage = (1.2053XSGmThFw) p 14.696psi, Twnside) p14. 696ps4 Thin) The relationship assumes dry air which was confirmed to be conservative for the analysis by sensitivity comparison with 100% humidity. The msulting leakage flow rate is included for each of the test cases in Table 9.
Table 9 -Revised Test Data Description Variable Test I Test 2 Test 3 Test 4 Test S Test 6 Name _ Outside TWIn 64 66 68 70 72 75 Temperaturo Inside Tinside 80.5 82 80 80 79 79 Temperature Wind Speed VMet 13.52 9.9 14.2 15.3 14.2 7.3 (mph) Leakage Flow Leakage 2467 2359 2379 2404 2446 3038 2 (ACEM) Differential APmeasured 0.48 0.448 0.46 0.39 0.448 0.65 Press=r measured by Pressure Instrument 1A4 (iWO) _ _ Wind Direction 180 165 180 180 180 240 This data is ready for Brther evaluation using the pressure modeling methods previously descnbed. The wind pressure coefficients developed in Appendix 3 and reported in Table 2 are used in this effort to convert the measured pressurc to the local pressure at the Roofline and Railroad Bay Door (Table 10).
.Z Caic. No. WS129-CALC-001 .CALCULATION CONTROL SHEETRev. 0 ENERCON SERVICES, INC. Page No. 38 of 150 Table 10 - Wind pressure coefficients Test Data Upper Upper Upper Upper Rail Road Pressure Description Building Building Building Building Door Wind Instrument (Wind South Face North Face East Face West Face Coefficient Wind Direction Wind Wind Wind Wind (Incident Coefficient Angle) Coefficient Coefficient Coefficient( Coefficient Angle) (Incident (Incident (Incident Incident (Incident Angle)
Angle) Angle) Angle) Angle) Test Data -0.0294 -0.619 -0.545 0.466 -0.35 0.25 Wind (600) (120°) (150°) (30°) (150°) (300) Direction Instrument South (240) IA4 Test Data 0.63 -0.47 -0.415 -0.685 -0.50 -0.742 Wind (150) (1650) (750) (1050) (75°) (1050) Direction Instrument South (165) IA4 Test Data 0.638 -0.403 -0. 738 -0. 738 -0.85 -0.55 Wind (00) (1800) (900) (900) (900) (900) Direction Instrument South (180) 1A4 For a wind direction from the South (1800), the southern side of the building would use a 00 incident angle and the associated wind pressure coefficient. The Railroad door is on the East side of the building and for a Southern wind would use the flow coefficient associated with a 900 incident angle and wind pressure coefficient value at the lower elevation. The details of how these wind pressure coefficients were developed and assigned are provided in Appendix 3. It should be noted that the test data used Pressure Instrument "1A4" exclusively. With these wind pressure coefficients determined for each test condition, it is possible to determine the wind contribution to the measured pressure differential and establish the corresponding pressure differences for the four roofline sides and the railroad bay door. The relationships used in this effort are developed and documented Appendix 1. The mathematical relationships that apply these methods are illustrated below. To calculate the wind pressure effect the met tower velocity is compensated for elevation and obstructions as follows, using the previously defined Equation 3. (900f )0.14 (HBuild 0. 14 (Equation 3) D= VME THMet) 90ft ) For the wind pressure contribution to the control instrument, Hmet is 33 feet and Hbuild is 135.5 feet. For the upper elevation, Hmet is 33 feet and Hbuild is 226 feet. The railroad bay door calculation will use Hmet of 33 feet and Hbuild of 28 feet. With the measured velocity converted to the velocity at the elevation of the pressure instrument ("IA4"), the wind contribution to the pressure measurement can be calculated. The method used to calculate the wind pressure contribution is outlined in Appendix 1, but is simply the dynamic pressure portion of the well documented Bernoulli equation (Reference 1.32) multiplied by the appropriate wind pressure coefficient. Using this approach, the wind pressure effect on the measured instrument for Test 6 is calculated as follows.
Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev 0 ENERCON SERVICES, INC. Page No. 39 of 150 Opi~u ~~I7NDVSUED= m = (.25p(Tin (05)p(IW in) 2 2~ 27.71linH20 2 (Equation 8) 2 psi The wind pressure contribution to the measurement is calculated specifically so that it can be subtracted from the measured value, revealing the static pressure difference at the measurement location. The static pressure contribution can then be modified to represent that expected at the roof elevation as well as the railroad door. Furthermore, knowing the wind speed and the wind pressure coefficients at different locations on the building, the wind pressure can be calculated for those locations and added to the corrected static pressure values. This allows the establishment of the wind pressure differences on the leakage locations that correspond with the test data. The mathematical relationship that accomplishes this is defined below for each face of the building, as well as the rail road door. The following summarizes what the equation shows. Using the wind speed information and location of the instrument, the wind pressure contribution to the measured value can be calculated and subtracted from that measured value provided in Table 9. APMl's,.d - APXdMe.rved (Equation 9) The outside static pressure change between the measurement elevation (HbuildMid) and the elevation of interest (HBuildUp) on the building (i.e., Roof) can be calculated using the Bernoulli equation and density based on the outside Temperature (Toutside) documented in Table 9. The same is done for the internal conditions using the internal temperature (Tinside) also documented in Table 9. p(1 4.7 psi, Win, "air"XgXHBuildMid - HBuildUp) p(I 4.7 psi, TInside, "air"'XgXHBulldMid - HBuildUp) The difference between these values is added to Equation 9. Finally, the wind pressure determined using Table 9 wind speed and direction, as well as Equations 3 and 8, is added to the aforementioned quantity. The combined relationship for each of the sides of the building is illustrated below with a functional form of Equation 8 represented as Pwo. The term CpRoof is the weighted average coefficient for the roof as defined in Appendix 1.. The resulting pressure difference across the walls at the roof level is provided in Equation 10.
Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 40 of 150 EQUATION 10 AP Roofi = AP Measured i - AP WindMeasuredP (P gas(Pa Twin1 , "air') - P ga (PatmnTlnsidej,"air)).[g-(HBuildMid- HBuildUp)] 27.71-
+ Pw(VWin1,TWin., HmetLow,HBuildUp, CpRoofJ)
The resulting pressure difference across the rail road bay door is provided in Equation 11. EQUATION I I AP RRDoori =AP Measured i - AP WindMeasured (Pgas(Patm.TWini, air) - P gas(PatmnTnsidei,
+ Pw( VWin.,TWin.,HmetLow, HBuildJ CpRRDoors air')) gp(HBUidMid- HBuildI) 277in I
F>^ Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 41 of 150 The calculated wind pressure for each of the cases listed in Table 9 are provided in Table 11. Table 11 - Wind Pressure Effect Calculation Results Case I Case 2 Case 3 Case 4 Case 5 Case 6 Vwind Inst 16.476 12.065 17.305 18.645 17.305 8.896 Vwind Roof 17.699 12.96 18.59 20.03 18.59 9.557 (mph) VwindRR 13.213 9.675 13.877 14.952 13.877 7.134 (m ph) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Air Density 0.0734 0.0732 0.0735 0.0735 0.0737 0.0737 Inside (lb/fO)__ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ Air Density 0.0758 0.0755 0.0752 0.0749 0.0746 0.0742 Outside (lb/&:) APwind Inst -0.073 -0.052 -0.079 -0.092 -0.079 9.42E-03 (in H20) APwind -0.044 -0.018 -0.048 -0.055 -0.047 -8.29E-03 Roof Roof (in H20) APwind RR -0.072 -0.023 -0.079 -0.092 -0.079 -8.50E-03 (in H20) I Recall that the pressure correction accounts for the wind pressure as a function of direction and elevation (Table 9). In addition., the static pressure change for the inside and outside, based on the measured temperatures, is included. The building height information (Hbuild... values) used in this calculation is provided below.
Ft Caic. No. WS129-CALC-001 k CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 42 of 150 HBuildUp = 667ft - 441ft = 226ft HBuildMid = 576.5ft - 441 ft = 135.5ft HBuildL = 469ft - 441ft = 28ft The resulting pressure differentials calculated using Equations 10 and 11 are provided in Table 12. Table 12 - Calculated Local Pressure Differences Case Upper Railroad Bay Door 1 0.469 in 0.528 in 2 0.444 in 0.524 in 3 0.463 in 0.495 in 4 0.403 in 0.419 in 5 0.463 in 0.469 in 6 0.623 in 0.643 in Per Assumption 1.11, a flow split of 70%/o30% is assumed for the data. This will be used to calculate a leakage correlation for the roofline and the railroad bay door. The same turbulent/laminar flow relationship used in Reference 1.24 will be applied in determining the coefficients for the building leakage. As described in Reference 1.24 and illustrated in Equation 7, the leakage flow rates are proportional to either 1/2or 1 power pressure difference. Therefore, the pressure differences established in Table 10, along with the measured flow rates, are used to provide a power relationship for each of the leakage path ways. This will result in a set of relationships based on Equation 7. The data that will be evaluated to establish the appropriate coefficients are summarized in Table 13.
eCalcN. WS129CALC 001 ILi CALCULATION CONTROL SHEET CRv. 2 ENERCON SERVICES, INC. Page No. 43 of 150 Table 13 - Calculated Local Pressure Differences and Leakage Flows Test Case Roof Rilroad Leakage Flow Differential Door (ACFM) Pressure Differential __ _ Pressure
#1 0.469 in 0.528 in 2467
#2 0.444 in 0.524 in 2359
#3 0.463 in 0.495 in 2379 2
#4 0.403 in 0.419 in 2404
#5 0.463 i 0.469 in 2446
#6 0.623 m 0.643 in 3038 The data in Table 13 is used to establish a curve fit using a power fimction provided as part of the MathCad software package. To complete the evaluation, it is necessary to include a zero flow condition established at 0 inch pressure difference.
The power function is described by the MathCad software as follows.. Returns a vector containg the coefflclentfor apower core of thefonn azt+cthat best proximates the data in vectors vx and vy. Vector vg contains guess valuesfor the three coefficients. This function is used to obtain a sense of the Leakage Data behavior as a finction of differential pressure. From the results of this assessment, it will be possible to select the appropriate "Ae and "IB"coefficients used in Equation 7. Evaluating the data with the aforementioned power function showed that the Roof leakage flow was proportional to the 0.644 power of the differential pressure. The Railroad door leakage Ilow was shown to be proportional to the 0.598 power of the differential pressure The "e' coefficient returned in each case was less than 1 and is considered to be Insignificant and ignored in the establishment of the Equation 7 coefficienits. TIe approach taken to establish the Equation 7 coefficients is to weight the % and I power values ofthe relatio p, to match the curve developed by the MathCad Result Figures I and 2 illustrate the characteristics of the flow and compares the power function with the weighted resulting relationships. From Figure 1, it can be seen that the characteristics of the leakage at the roof are best represented by l/3V"of the leakage is laminar, while the remaining 2/3- are turbulent Figure 2 illustrates that the flow at the railroad door matches the measured flow with 75% turbulent flow condition and 25% ofthe flowbehaving as laminar.
1 -% 0Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 44 of 150 I
,1.
0.75 z0. 64 4 050.5 0.33Z+0.67 (Z) 0.25 0 0 I 0 z 1 Figure I - Leakage Flow Characteristics At Roof Level
=l£. Cac. No. WS129-CALC-001 a
ENERCON SERVICES, INC. CALCULATION CONTROL SHEET Rev. Page No. 45 of 150 I 1 0.75 0.75z 05+.25z z0.598 0.5 0.25 u o 0.25 0.5 0.75 0 z I Figure 2 - Leakage Flow Comparison For Railroad Door
l Calc. No. WS129-CALC-001 i CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 46 of 150 The coefficients for Equation 7 can now be established for each of the leakage flow paths using the following relationship. LeakageRoof = FS(2430ACFM) A(AP)+ B(AP) 112 where A = 0.33(C) B = 0.67(C) AP = 0.25in FS=0.7 Solving C = 4074.25 A = 1344.5 B = 2729.75 LeakageRoof = 1344.5(AP)+ 2729.75(AP)Y2 LeakageDoor= (I - FSX2430ACFM) = A(AP) + B(AP)" 2 where A = 0.25(C) B = 0.75(C) AP = 0.25in FS=0.7 Solving C = 1666.29 A = 416.57 B = 1249.71 LeakageDoor = 416.57(AP)+ 1249.7 1(AP) 12 These relationships are established for a technical specification value 2430CFM assuming an air temperature of 75TF. A ratio of the densities are used to modify the values for use with the temperature conditions considered in this evaluation.
F. %Calc. No. WS129-CALC-O01
-Rv , CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 47 of 150 Tmax=86 0F Roof Leakage Roof Laminar Term 1344.5 p(l4.696psi,75 0F) =1372.16 p(l 4.696psi,T max)
Roof Turbulent Term 2729.75 p(14.696psi,75 0F) =2785.91 p(14.696psi,Tmax) RoofLeakage(86 0 F) = 1372.1 6AP + 2785.9 IAPm' Tmax=86 0F Door Leakage Door Laminar Term 416.57 p(14.696psi,75 4 69 F) - 425.14 p(l . 6psi, T max) Door Turbulent Term 1249.57 p(14.696psi,75 F) -1275.43 p(I 4.696psi, T max) DoorLeakage(86 0F) = 425.14AP + 1275.43AP'
;.1" Caic. No. WS129-CALC-001 f- CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 48 of 150 Tmin = 28 0F Roof Leakage Roof Laminar Term 1344.5 p(14.696psi,75 0F) =1226.31 p(l4.696psi,Tmin)
Roof Turbulent Term 2729.75 p(14.696psi,75 F) = 2489.79 p(1 4.696psi,T min) RoofLeakage(28 0F) = 1226.3 IAP + 2489.79AP1 2 Tmin=28 0F Door Leakage Door Laminar Term 416.57 p(14.696psi,75°F) = p(l 4.696psi,T min) Door Turbulent Term 1249.71 p(14.696psi,75 0F) =1139.86 p(l4.6 9 6 psi, T min) DoorLeakage(28 0 F) = 379.95AP + 1139.86AP I 2
Caic. No. WS129-CALC-001 3") CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 49 of 150 PRESSURE CRITERIA INPUTS CONTROL VARIABLES The successful depressurization of the secondary containment reactor building is determined by evaluating the pressure at the leakage locations. The leakage locations are at the roof and railroad door elevations. These two extremes in the building elevation provide a bounding look at the pressure difference across the building walls. The elevations considered are the 667ft (roof) and 469ft (railroad door). Control variables are used to calculate the building internal pressures at these elevations as follows. P = PVOLUME + PVOLUME ELEVATIONVOLUMECENTER) gCc where PVOLUME = the GOTHIC calculated volume pressure PvoLUNM = the GOTHIC calculated volume density c = the gravitational constant C = conversion constant Two internal pressure values are calculated in this manner one at the roof level (GOTHIC Control Volume
- 5) and one at the railroad door (GOTHIC Control Volume 1). The volume center of volume I is determined based on values documented in the volumes input section (Table 18) to be 522.94ft. Similarly the volume 5 value is 636.02ft The leakage path elevations were previously defined to be roof 667ft and railroad door 469ft.
Based on these values the control variable equations can be defined as follows. PROOF PVOLUMES + PYOLUMES j 0.215psi f ) PRALROADDOOR = PVOUMI+ i bm) OL UMEL + p OL U]El (0.37S SUMI0.7psi-f
Calc. No. WS129-CALC-001
.4} CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 50 of 150 These pressures are then compared with the minimum pressures acting on the leakage path. For the railroad door, the minimum pressure is the same as the boundary condition pressure since the pressure is on one side of the building only. For the roof, the minimum side pressure is used as opposed to the weighted pressure used in the boundary condition. The minimum pressures are calculated in Appendix I for the roof elevation.
F- . Calc. No. WS129-CALC-001
- CALCULATION CONTROL SHEET Rev.
ENERCON SERVICES, INC. Page No. 51 of 150 FLOW PATH INPUT: Flow paths are used in the GOTHIC model to provide hydraulic connections between volumes and boundary conditions. The upper leakage flow path is associated with the refueling floor, while the lower leakage flow path is associated with the main reactor building volume. These flow path areas and hydraulic diameters are simply calculated to be based upon the anticipated flow with a 0.25inWG pressure difference. The flow path area and hydraulic diameter for the upper leakage path are calculated as follows.
" = 0.075lftb I2(0.25in1(144inft2)(32.2) f bI( 27.71inJ 'ec Flow = 2430cfin(0.7) = 1701 .Ocfin Area = Flow/v = 1701 0c (60Osec/(33.4fe Area = 0.85ft 2 The Hydraulic Diameter is calculated for each of the leakage flow paths as follows.
HD = V4Are/o = 1.04ft
Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 52 of 150 The flow path area and hydraulic diameter for the lower leakage path are calculated as follows. p = 0.0 7 5 ft' l1b 2 S5inQ144 inyft2 )(32.2) f ( 0 75f't(27.71in)' Flow = 2430cfin(0.3) = 729.0cfin Area = Flow/I = 7 2 9 .OCf (60S." 33.4fts)
/ '7 (0eminl3 pasec))
Area = 0.36ft 2 The Hydraulic Diameter is calculated for each of the leakage flow paths as follows. HD= 4Areal = 0.68ft Flow Paths between the volumes are established based on Reference 3.7. The flow path information used is provided in Table 14. The values are combined into values suitable for the GOTHIC Input (Table 15). It should be noted that flow paths associated with the SGTS are documented later in this report. Table 14 Flow Path Information from Reference 3.7 Description Flow Friction Hydraulic Forward Reverse Area Length Diameter Loss Loss Coeff. Coeff. RHRB TO 471 56.65 2 1.74 1.52 1.52 RHRA TO 471 54.61 2 1.86 1.52 1.52 RCIC TO 471 20.82 2 1.80 1.56 1.56 RHRC TO 471 33.47 2 2.63 1.50 1.50 LPCS TO 471 13.41 2 1.96 1.50 1.50 BPCS TO 471 12.45 2 1.14 1.50 1.50 CRD/COND TO 471 16.83 2 1.40 1.50 1.50 572S - 606S, 1 409.61 2 11.89 1.5 1.5
Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 53 of 150 Table 15 GOTHIC Flow Paths Description From Elev Ht To Elev Ht Flow Hydraulic Inertial Len Fric Len Vol Vol Area Dia (ft)(ft.) (ft) (ft) (f)ft)(t Pump RoomTo Main 4 466 0.1 1 471 0.1 191.41 1.767 105.31 2 Building _ _ I Pump Room To Main 4 422.25 16.7 1 441 0.0104 16.83 1.4 105.31 2 Building Main Building To Fuel 1 572 0.1 5 607 0.1 409.61 11.89 112.33 2 Floor SGTS Inlet 1 577 1.5 2 577 1.5 1.767 1.5 10 I SGTS Discharge 2 577 1.5 3P 671.17 1.5 1.767 1.5 10 157.81 Roof Leakage 5 667 0.1 2F 667 0.1 0.85 1.04 130 1 Ground Leakage 1 468.5 0.5 IF 468.5 0.5 0.36 0.68 136 1
F] Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. ENERCON SERVICES, INC. Page No. 54 of 150 VOLUME INPUT: The purpose of this section is to document the basis for the volume inputs developed for the drawdown analysis. The model is composed of three volumes. These volumes represent the refueling floor with its refuel pool, the pump rooms located on the 422.25 foot elevation and the remainder of the reactor building. The volumes are developed using information provided in References 3.1 and 3.9. The result of this effort is provided in Table 18. Table 16 provides the volume inputs obtained from Reference 3.1. These inputs are used to generate the values depicted in Table 17 as described below. The 1 fuel pool liquid volume is obtained from Reference 3.9 and has a value of 350,000 gallons. Note I gallon equals 0.13368 ft3 resulting is a fuel pool liquid volume of 46,788 ft. Table 16 - Volume Values Obtained From Reference 3.1 Elevation Description Volume Value Fuel Pool Air Volume Volume (ft3) (ft3) (ft3) Reactor Building Inputs 422.25' (includes pump 195,522.54 195,522.54 rooms) 441' (includes pump room 204,327.76 204,327.76 mezzanines) RRB 76,897.33 76,897.33 471' 325,391.98 325,391.98 501' 232,981.87 232,981.87 522' 340,597.54 340,597.54 548' 347,95__94_347,958.94 347 958.9 572' 426,012.10 426,012.10 Total RB below Refueling 2,149,690.06 Floor w/pump rooms 606' - 10.5" Refueling Floor 1,327,248.77 700.00 1,274,548.77 I I 606' - 10.5" Fuel Pool Water 46,788.00 Volume Pump Room Inputs 422.25' RHR B 72,302.76 72,302.76 422.25' RHR A 71,064.20 71,064.20 422.25' RCIC 42,033.90 42,033.90 422.25' RHR C 35,756.92 35,756.92 422.25' LPCS 27,933.37 27,933.3 422.25' HPCS 50,476.90 50,476.90 422.25' CRD 45,553.05 45,553.05 Total pump rooms 345,121.10 Total RB below Refueling 1,804,568.96 Floor w/o pump rooms 1 This volume is based on the dimensions of the fuel pool and includes all volume occupied by fuel assemblies as well as water.
F2 Caic. No. WS129-CALC-001 L CALCULATION CONTROL SHEET . 1 ENERCON SERVICES, INC. Page No. 55 of 150 The pump room volume is established based on the Pump Room inputs, which as described in the assumptions, overlap with the Reactor Building Inputs. Therefore, the Pump Room Volume is simply the summation of the Pump Room Volumes listed in Table 16. The main building volume is the sum of the Reactor Building Volumes minus the Pump Room Volume and the refueling floor volume. The volume inputs for the described volumes are provided in Table 17. The total Reactor Building Volume is different from that reported in Reference 3.1 due to the Spent Fuel Pool normal water volume. This water is assumed to be present in this calculation to allow the modeling of the fuel pool heat input response. Table 17 - Three Node Volume Inputs Node Description Total Internal Fuel Pool Air Volume Input Volume Fraction Volume Volume Volume Water Pump Room Volume (ft3) 345,121.10 (ft3) (ft) 345,121.10 uth 345,121.1 2 ( 0 3 es I Main Building Volume 1,804,568.96 1,804,568.96 1,804,568.96 0 Refueling Floor Volume 1,327,248.77 52,700 1,274,548.77 1,321,336.77 3.541% Fuel Pool Water Volume ___ 46,788 0 NA NA Total _ 3,424,238.83 NA NA The GOTHIC Inputs are documented in Table 18. 2 Refueling Floor Input Volume is 1,274,548.77fi 3 + 46,788ft' 3 Pool Fraction is 46,788ft 3 /1,321336.77fW
______ CCaIc. No. WS129CALC001
" CALCULATION CONTROL SHEETRev.
ENERCON SERVICES, INC. Page No. 56 of 150 l Table 18 - GOTHIC Inputs Volume Description Volume Elevation 4 Height Hydraulic Pool Area 1 No. Diameter I upt) 00t2c fi f 1 Main Building 1,804,568.96 441 163.875 28.9 DEFAULT 2 SGTS Fan Inlet 1,000__ 577 1.5 1.5 DEFAULT 3 Fuel Pool Cooling 10 568.125 1 1 DEFAULT I I System 4 Pump Rooms 345,121.1 422.25 46.75 69.07 DEFAULT 5 Refuel Floor 1,321,336.77 604.367 63.303 31.34 1360 4 Refueling Floor elevation is established to accommodate the liquid volume. 5 Volume 2 was set to 100Oi13 to ensure reasonable run time without adversely impacting the results.
Calc. No. WS129-CALC-001 E.1 ni;CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 57 of 150 THERMAL CONDUCTOR INPUT: This section documents the basis for the basic heat conductor inputs to be used in the GOTHIC drawdown model. The inputs are developed for the three node model. The three nodes represent the pump rooms, refueling floor and the remainder of the reactor building. The results of this calculation are 48 thermal conductors. The primary thermal conductors information is summarized in Table 19. The walls are in general concrete and the pipes are carbon steel. Those conductors that are described as composite have more than one material associated with them. The material composition and the thickness of the different material regions is provided in Table 35 of this report. The boundary condition specifics are found in the Thermal Conductor Boundary Temperatures section of the report. Table 19 Thermal Conductor Inputs Cond. Conductor Side 1 Side 2 Thick. O.D. Surface Geom Details Description Thermal Thermal Area Condition Condition (in) (in) (ft2) I Uninsulated Pump Room Wetwell 0.38 21.02 2,307.56 Tube Table 21 __ Piping 2 Insulated Piping Pump Room Wetwell 2.38 22.00 642.19 Tube Table 21 (Composite) 3 Uninsulated Main Reactor Fuel Pool 0.29 7.31 406.34 Tube Table 21 Piping Building 4 Pump Room Pump Room Adiabatic 36.00 NA 1958.06 Wall Table 23 Exterior Concrete Wall 5 Pump Room Pump Room Adiabatic 48.00 NA 4359.37 Wall Table 23 Exterior Concrete Wall 6 Pump Room Pump Room Adiabatic 60.00 NA 714.00 Wall Table 23 Exterior Concrete Wall 7 Pump Room Pump Room Adiabatic 72.00 NA 133.00 Wall Table 23 Exterior Concrete Wall 8 Pump Room Wall Pump Room D104 36.00 NA 1405.68 Wall Table 23 _____ Corridor _ 9 Pump Room Wall Pump Room D104 48.00 NA 1026.37 Wall Table 23 Corridor 10 Pump Room Wall Pump Room D104 72.00 NA 208.25 Wall Table 23 Corridor 11 Pump Room Pump Room Main Reactor 18.00 NA 2,908.00 Wall Table 23 _ Ceiling Building 12 Pump Room Pump Room Main Reactor 24.00 NA 3,117.00 Wall Table 23 Ceiling Building 13 Pump Room Wall Pump Room Main Reactor 35.12 NA 5,630.62 Wall Table 23 Building
Calc. No. WS129-CALC-001 F -i-3 CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 58 of 150 Cond. Conductor Side 1 Side 2 Thick O.D. Surface Geom Details Description Thermal Thermal Area Condition Condition (in) (in) (fet) 14 Pump Room Wall Pump Room Main Reactor 48.00 NA 121.87 Wall Table 23 Building 15 Pump Room Wall Pump Room Main Reactor 58.14 NA 706.87 Wall Table 23 ________ Building _ 16 Pump Room Pump Room Pump Room 35.10 NA 4,743.45 Wall Table 23 Internal Wall (9,286.9)6 17 Pump Room Pump Room Pump Room 60.00 NA 97.50 Wall Table 23 Internal Wall 18 Pump Room Pump Room Wetwell 64.06 NA 5,975.00 Wall Table 23 Wetwell Wall (Composite) _ 19 Pump Room Pump Room Wetwell 154.86 NA 5,676.25 Wall Table 23 Wetwell Wall (Composite) 20 AUXILIARY Main Reactor Pump Room 24.00 NA 92.00 Wall Table 30 ROOMS Floor Building 21 AUXILIARY Main Reactor Adiabatic 33.98 NA 1,324.00 Wall Table 30 ROOMS Wall Building ___ 22 AUXLIARY Main Reactor Main Reactor 12.00 NA 4,995.25 Wall Table 30 ROOMS Wall Building Building 23 AUXILIARY Main Reactor Main Reactor 18.00 NA 444.50 Wall Table 30 ROOMS Wall Building Building 24 AUIMLIARY Main Reactor Main Reactor 23.36 NA 1,241.50 Wall Table 30 ROOMS Wall Building Building _ 25 AUXILUIRY Main Reactor Main Reactor 36.00 NA 322.00 Wall Table 30 ROOMS Wall Building Buildin_ 26 AUXILLARY Main Reactor Main Reactor 44.26 NA 264.50 Wall Table 30 ROOMS Wall Building Building 27 AUXILIARY Main Reactor Main Reactor 72.00 NA 450.85 Wall Table 30 _ROOMS Wall Building Buildingi 28 AUXILIARY Main Reactor Main Reactor 102.00 NA 40.25 Wall Table 30 _ ROOMS Wall Building Building 29 AUXILIARY Main Reactor Main Reactor 12.00 NA 1,149.36 Wall Table 30 _ ROOMS Floor Building Building 30 AUXILIARY Main Reactor Main Reactor 18.00 NA 814.31 Wall Table 30 ROOMS Floor Building Building I._ 31 AUXILIARY Main Reactor Main Reactor 24.00 NA 150.00 Wall Table 30 ROOMS Floor Building Building 32 AUXILIARY Main Reactor Main Reactor 32.00 NA 101.66 Wall Table 30 ROOMS Floor Building Building 33 AUXILIARY Main Reactor Drywell 60.00 NA 289.00 Wall Table 30 ROOMS Wall Building (Composite) . 6 The area of internal conductor walls in the pump rooms (Table 23) are calculated based on both sides of these walls. Therefore, when applied in the GOTHIC conductors model 1/2 the value is used.
Calc. No. WS129-CALC-001 Y'7 CALCULATION CONTROL SHEETRev. 0 ENERCON SERVICES, INC. Page No. 59 of 150 Cond. Conductor Side 1 Side 2 Thick O.D. Surface Geom Details Description Thermal Thermal Area Condition Condition (in) ( (in) (ft2) 34 AUXILIARY Main Reactor Fuel Pool 62.55 NA 422.87 Wall Table 30 ROOMS Wall Building 35 MISCELLANEO Main Reactor Main Reactor 12.00 NA 9,789.87 Wall Table 30 US WALLS Building Building _ 36 MISCELLANEO Main Reactor Main Reactor 23.16 NA 5,445.41 Wall Table 30 US WALLS Building Building 37 MISCELLANEO Main Reactor Main Reactor 27.79 NA 1,704.00 Wall Table 30 _ US WALLS Building Building 38 MISCELLANEO Main Reactor Main Reactor 37.04 NA 2,334.49 Wall Table 30 _ US WALLS Building Building 39 MAIN Main Reactor Adiabatic 23.83 NA 24,402.43 Wall Table 30 STRUCTURE Building WALLS 40 MAIN Main Reactor Adiabatic 28.41 NA 44,567.01 Wall Table 30 STRUCTURE Building WALLS 41 MAIN Main Reactor Main Reactor 24 NA 55,700.90 Wall Table 30 STRUCTURE Building Building FLOOR 42 DRYWELL Main Reactor Drywell 61.37 NA 9,443.95 Wall Table 30 WALLS Building (COMPOSITE) 43 DRYWELL Main Reactor Drywell 72.09 NA 13,332.51 Wall Table 30 WALLS Building (COMPOSITE) 44 FUEL POOL Fuel Pool Drywell 60.00 NA 1,743.75 Wall Table 30 WALL (COMPOSITE) _ __ _ 45 FUEL POOL Fuel Pool Main Reactor 60.00 NA 4,378.75 Wall Table 30 WALL Building 46 COMPOSITE Refueling Adiabatic 1.598 NA 34,800.06 Wall Table 33 WALL Floor (Composite) 47 COMPOSITE Refueling Adiabatic 0.049 NA 20,194.28 Wall Table 33 ROOF Floor Composite) 48 CONCRETE Refueling Main Reactor 24.00 NA 16,205.50 Wall Table 33 _ FLOOR Floor Building The thermal conductors are developed for each of the three distinct volumes used in the building model. These volumes include the pump rooms, the main reactor building and the refueling floor. PUMP ROOM THERMAL CONDUCTORS The pump rooms contain thermal conductors that have a heated surface (Primary Containment), have an adiabatic surface (Assumption 4.5), communicate with the main reactor building volume and have both
itl Caic. No. WS129-CALC-001 M CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 60 of 150 surfaces internal to the volume. The conductors that have a heated surface are associated with operational ECCS pipes (Assumption 4.1) as well as primary containment walls. These heat structures will be assigned a boundary condition that is a time dependent temperature value that matches the wetwell response to the LOCA conditions, Table 37. Those conductors within the pump room that are assigned an adiabatic boundary condition are associated with walls and floors that communicate to conditions outside of the reactor building. The thermal conductors that communicate with the main reactor building volume are the pump room ceilings. The conductors that contain both sides within the pump room volume are the walls that adjoin the pump rooms.
Caic. No. WS129-CALC-001 FI.' CALCULATION CONTROL SHEET Rev. Page No. 61 of 150 1 ENERCON SERVICES, INC. PIPING HEAT STRUCTURES Table 20 provides all of the basic data as well as calculated surface areas for the piping system heat conductors. It should be noted that the Fuel Pool Heat Exchanger Room Piping is located in the Main Reactor Building Volume. TotalDia = OD + 2(InsulThick) TotalWaliThick = (TotalDia - ID) 2 Surface.Area = ir(TotalDiaXLgth) Table 20 - Raw Data for Piping Systems That Provide Heat Source Room Location 7 Structure Description BOUNDARY CONDITION Diam Lgth Schedule OD Wall Thick ID Insul Thick TOTAL WALL THICK TOTAL DIA Surface Area Ref II ______________(in) (ftlI) (In) (in) (In)_ (in)_ (in) __n (It2) ____ RHR PUMP 2C ROOM R- RHR(3)-1 WETWELL 24 64.92 SA106 STD 24.00 0.375 23.25 0 0.375 24 407.90 3.4 3 (R14) GROUP B ____ RHR PUMP 2C ROOM R- RHR(1)-2 WETWELL 18 111.50 SA106 STD 18.00 0.375 17.25 2 2.375 22 642.19 3.4 3 (R14) GROUP B FUEL POOL HX ROOM FPC(1)-l-l FUELPOOL 10 15.00 SA106 STD 10.75 0.365 10.02 0 0.365 10.75 42.22 3.4 GROUP B FUEL POOL HX ROOM FPC(l)-l-l FUELPOOL 8 18.00 SA106 STD 8.625 0.322 7.981 0 0.322 8.625 40.64 3.4 GROUP B FUEL POOL HX ROOM FPC(2)-1-I FUELPOOL 8 5.00 SA106 STD 8.625 0.322 7.981 0 0.322 8.625 11.29 3.4 GROUP B 7 Note that RHR Pump 2C Room R-3 is used as opposed to RHR Pump 2A specified in Assumption 4.1. Review of the Reference 3.4 calculation indicates that the RIHRC piping representation used in the model bounds that associated with RHRA therefore, the model documented in this calculation is conservative.
Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. ENERCON SERVICES, INC. Page No. 62 of 150 Room Location 7 Structure BOUNDARY Diam Lgth Schedule OD Wall ID Insul TOTAL TOTAL Surface Ref Description CONDITION Thick Thick WALL DIA Area I1 THICK
. (in) (ft) (in) (in) (in) (in) (in) (in) (ft2)
FUEL POOL HX ROOM FPC FUEL POOL 6 180.00 SA106 STD 6.625 0.280 6.065 0 0.28 6.625 312.20 3.4 GROUPB LPCS PUMP ROOM R-5 LPCS(2)-1 WETWELL 24 80.63 SA106 STD 24.00 0.375 23.25 0 0.375 24 506.61 3.4 (R12) GROUPB LPCS PUMP ROOM R-5 LPCS(1)-2 WETWELL 16 105.90 SA106 STO 16.00 0.375 15.25 0 0.375 16 443.38 3.4 (R12) GROUPB HPCS PUMP ROOM (R-6) HPCS(2)-1 WETWELL 24 84.85 SA106 STD 24 0.375 23.25 0 0.375 24 533.13 3.4 Rl1 GROUPB I HPCS PUMP ROOM (R-6) HPCS(1)-4 WETWELL 16 99.44 SA106 STD 16 0.375 15.25 0 0.375 16 416.53 3.4 RI I GROUPB _ _ _
Caie. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 63 of 150 To establish heat structures that represent the piping system it is necessary to divide these system into those associated with Fuel Pool Cooling and ECCS. The next step is to further sub divided them into insulated and not insulated. The final step is to group the piping by wall thickness. Piping within each group is combined into a heat conductor by calculating an average diameter and thickness that is representative of the total surface area of the group. This approach provides an equivalent heat sink to represent each piping group minimizing the number of heat structures required by the model. Table 21 summarizes the result of this calculation. h s (AreaXThickness) AvgThickness = ( ra 1:(Area) A _(AreaXDia) X (Area)
Calc. No. WS129-CALC-001 Fs-r', ME I CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 64 of 150 Table 21 Piping System Thermal Conductor Inputs Cond. # Piping Piping Internal Conductor Conductor Insulation Conductor Conductor Piping Insulation Location Description Boundary Geometry Outside Thickness Wall Surface Area Material Material Condition Diameter Thickness (ft2) (in) (in) Pump Uninsulated Suppression Tube 21.02 0 0.38 2,307.56 SA106 NA Room Piping Pool Post Volume LOCA Temperature
Response
2 Pump Insulated Suppression Tube 22.00 2 2.38 642.19 SA106 Calcium Room Piping Pool Post Silicate Volume LOCA Temperature
Response
3 Main Uninsulated Fuel Pool Tube 7.31 0 0.29 406.34 SA106 NA Building Piping Temperature Volume Calculated by GOTHIC
Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 65 of 150 PUMP ROOM WALLS AND CEILINGS The data associated with walls and ceilings is developed in Table 22. SurfaceArea = (HeightXWidth) Note that where the width and height are not provided the surface area was taken directly from the reference. Table 22 Pump Room Walls and Ceilings Structure Location Structure Elevation WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation (ft) (ft) (ft) (in) (ft2 LOCATION Il ROOM RHR PUMP 2B NORTH WALL 422 29.25 48.75 36 1425.94 R6 3.3 Concrete Wall ROOM R-1 (R7) ROOM RHR PUMP 2B SOUTH WALL 1 422 25 48.75 36 1218.75 RB 3.3 Concrete Wall ROOM R-1 (R7) ROOM RHR PUMP 2B SOUTH WALL 2 422 5 48.75 60 243.75 RB 3.3 Concrete Wall ROOM R-1 (R7)_ ROOM RHR PUMP 2B SOUTH WALL 3 422 2.5 48.75 48 121.88 RB 3.3 Concrete Wall ROOM R-1 (R7) ROOM RHR PUMP 2B SOUTH WALL 4 422 17 48.75 30 828.75 RB 3.3 Concrete Wall ROOM R-I (R7) ROOM RHR PUMP 2B WEST WALL 1 422 7 19 72 133.00 GROUND 3.3 Concrete Wall ROOM R-l (R7) BELOW GRADE _ ROOM RHR PUMP 2B WEST WALL 1 441 7 29.75 72 208.25 D104 3.3 Concrete Wall ROOM R-l (R7) ABOVE GRADE CORRIDOR ROOM RHR PUMP 28 WEST WALL 2 422 34.5 19 48 655.50 GROUND 3.3 Concrete Wall ROOM R- I (R7) BELOW GRADE ROOM RHR PUMP 2B WEST WALL 2 441 34.5 29.75 48 1026.38 D104 3.3 Concrete Wall ROOM R-1 (R7) ABOVE GRADE CORRIDOR
Calc. No. WS129-CALC-001 F iCALCULATION CONTROL SHEET Rev. ENERCON SERVICES, INC. P No. 66 of 150 Iage Structure Location Structure Elevation WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation LOCATION (ft) (ft) (t (in) (ft2 ) 1 ROOM RHR PUMP 2B CEILING AREA 18 1533 RB 3.3 Concrete Floor ROOM R-l (R7)_ ROOM RHR PUMP 2A NORTH WALL 422 21.75 19 36 413.25 GROUND 3.3 Concrete Wall ROOM R-2 (R6) BELOW GRADE ROOM RIIR PUMP 2A NORTH WALL 441 21.75 29.75 36 647.06 AMBIENT 3.3 Concrete Wall ROOM R-2 (R6) ABOVE GRADE _ ROOM RHR PUMP 2A SOUTH WALL 422 29.25 48.75 36 1425.94 R7 3.3 Concrete Wall ROOM R-2 (R6)_ ROOM RHR PUMP 2A WEST WALL 422 47.25 19 36 897.75 GROUND 3.3 Concrete Wall ROOM R-2 (R6) BELOW GRADE ROOM RHR PUMP 2A WEST WALL 441 47.25 29.75 36 1405.69 D104 3.3 Concrete Wall ROOM R-2 (R6) ABOVE GRADE CORRIDOR __ ROOM RHR PUMP 2A EAST WALL 422 28.5 48.75 30 1389.38 R15 3.3 Concrete Wall ROOM R-2 (R6) SECTION I ROOM RHR PUMP 2A CEILING AREA 18 1375 RB 3.3 Concrete Floor ROOM R-2 (R6)_ _ RCIC PUMP ROOM R-3 NORTH WALL 441 7 29.75 60 208.25 AMBIENT 3.3 Concrete Wall (RI5) SECTION I RCIC PUMP ROOM R-3 NORTH WALL 441 44 29.75 48 1309.00 AMBIENT 3.3 Concrete Wall (RI5) SECTION 2 _ RCIC PUMP ROOM R-3 WEST WALL 422. 31.50 48.75 36 1535.63 R6 3.3 Concrete Wall (RI5) SECTION I _ RCIC PUMP ROOM R-3 WEST WALL 422 2.00 48.75 60 97.50 R6 3.3 Concrete Wall (R15) SECTION 2 RCIC PUMP ROOM R-3 EAST WALL 422 10.00 48.75 36 487.50 R14 3.3 Concrete Wall (RI5) _ _ _____ RCIC PUMP ROOM R-3 CEILING AREA 24 944.00 RB 3.3 Concrete Floor ( RI S5
) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ I _ _ _I
.. CALCULA.T CONROSClc. No. WS129-CALC-001 ENER1CONT L SHERIES Rev. 1 ENERON SERVICES, INC. Page No. 67 of 150 Structure Location Structure Elevation WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation LOCATION (ft) (ft) (t (in) 2 (ft ) LOCATION RHR PUMP 2C ROOM R-4 NORTH WALL 441 23.5 29.75 48 699.13 AMBIENT 3.3 Concrete Wall (R14) SECTION 1 RHR PUMP 2C ROOM R-4 NORTH WALL 441 3 29.75 60 89.25 AMBIENT 3.3 Concrete Wall (R14) SECTION 2 RHR PUMP 2C ROOM R-4 WEST WALL 422 10 48.75 36 487.50 R15 3.3 Concrete Wall (R14)
RHR PUMP 2C ROOM R-4 EAST WALL 422 21 48.75 36 1023.75 RB 3.3 Concrete Wall (R14) SECTION 1 I RHR PUMP 2C ROOM R-4 EAST WALL 422 4.5 48.75 54 219.38 RB 3.3 Concrete Wall (R14) SECTION 2 _ RHR PUMP 2C ROOM R-4 EAST WALL 422 8 48.75 36 390.00 R12 3.3 Concrete Wall (R14) SECTION 3 _ _ RHR PUMP 2C ROOM R-4 CEILING AREA 24 535 RB 3.3 Concrete Floor (R14) LPCS PUMP ROOM R-5 NORTH WALL 422 8 48.75 36 390.00 R14 3.3 Concrete Wall (R12) SECTION I LPCS PUMP ROOM R-5 NORTH WALL 422 17.5 48.75 36 853.13 RB 3.3 Concrete Wall (R12) SECTION 2 _ LPCS PUMP ROOM R-5 SOUTH WALL 422 48.75 36 877.50 RI 1 3.3 Concrete Wall (R12) 18.00 LPCS PUMP ROOM R-5 EAST WALL 441 21.50 29.75 48 639.63 AMBIENT 3.3 Concrete Wall (R12) SECTION I LPCS PUMP ROOM R-5 EAST WALL 441 7.00 29.75 60 208.25 AMBIENT 3.3 Concrete Wall (R12) SECTION 2 LPCS PUMP ROOM R-5 CEILING AREA 24 523 RB 3.3 Concrete Floor (1112) _ _ _ _ HPCS PUMP ROOM (R-6) NORTH WALL 422 18 48.75 36 877.50 R12 3.3 Concrete Wall R12 __
- Cac. No. WS129-CALC-001 CALCULATION CONTROL SHEETRev.
ENERCON SERVICES, INC. Page No. 68 of 150 Structure Location Structure Elevation WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation LOCATION (ft)_(ft) (ft) (in) (ft2) _ 1I HPCS PUMP ROOM (R-6) SOUTH WALL 422 35 48.75 36 1706.25 RB 3.3 Concrete Wall R13 SECTION 1 _ HPCS PUMP ROOM (R-6) SOUTH WALL 422 5 48.75 60 243.75 RB 3.3 Concrete Wall R14 SECTION 2 HPCS PUMP ROOM (R-6) EAST WALL 441 35.5 29.75 48 1056.13 AMBIENT 3.3 Concrete Wall R17 SECTION 1 HPCS PUMP ROOM (R-6) EAST WALL 441 7 29.75 60 208.25 AMBIENT 3.3 Concrete Wall R18 SECTION 2 HPCS PUMP ROOM (R-6) CEILING AREA 24 1115 RB 3.3 Concrete R19 _Floor ROOM RHR PUMP 2B EAST WALL 422 50 23.75 154.863 1187.50 WETWELL 3.3 COMPOSITE ROOM R-1 (R7) SECTION I TO WALL PRIMARY CONTAINMENT ROOM RHR PUMP 2B EAST WALL 446 50 25 64.063 1250.00 WETWELL 3.3 COMPOSITE ROOM R-1 (R7) SECTION 2 TO WALL PRIMARY __ CONTAINMENT ROOM RHR PUMP 2A EAST WALL 422 27 23.75 154.863 641.25 WETWELL 3.3 COMPOSITE ROOM R-2 (R6) SECTION 2 TO WALL PRIMARY CONTAINMENT ROOM RHR PUMP 2A EAST WALL 446 27 25 64.063 675.00 WETWELL 3.3 COMPOSITE ROOM R-2 (R6) SECTION 3 TO WALL PRIMARY CONTAINMENT _
- ' '.Caic. No. WS129-CALC-001
'I F CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 69 of 150 Structure Location Structure Elevation WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation LOCATION RCIC PUMP ROOM R-3 SOUTH WALL
__ _ __ _ __ (t 422 0 0t 44 0 0t 23.75 (in) 154.863 (ft 2 ) 1045.00 WETWELL 3.3 COMPOSITE I (R15) SECTION 1 TO WALL PRIMARY CONTAINMENT RCIC PUMP ROOM R-3 SOUTH WALL 446 44 25 64.063 1100.00 WETWELL 3.3 COMPOSITE (R15) SECTION 2 TO WALL PRIMARY CONTAINMENT RHR PUMP 2C ROOM R-4 SOUTH WALL 422 44 23.75 154.863 1045.00 WETWELL 3.3 COMPOSITE (R14) SECTION 1 TO WALL PRIMARY CONTAINMENT RHR PUMP 2C ROOM R-4 SOUTH WALL 446 44 25 64.063 1100.00 WETWELL 3.3 COMPOSITE (R14) SECTION 2 TO WALL PRIMARY CONTAINMENT LPCS PUMP ROOM R-5 WEST WALL 422 27 23.75 154.863 641.25 WETWELL 3.3 COMPOSITE (R12) SECTION 1 TO WALL PRIMARY CONTAINMENT LPCS PUMP ROOM R-5 WEST WALL 446 27 25 64.063 675.00 WETWELL 3.3 COMPOSITE (R12) SECTION 2 TO WALL PRIMARY __ _ CONTAINMENT HPCS PUMP ROOM (R-6) WEST WALL 422 47 23.75 154.863 1116.25 WETWELL 3.3 COMPOSITE R15 SECTION I TO WALL PRIMARY CONTAINMENT
F .Cal. No. WS129-CALC-001
.A CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 70 of 150 Structure Location Structure Elevation WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation LOCATION
____(ft) (ft) _ (In) (ft2) h1I HPCS PUMP ROOM (R-6) WEST WALL 446 47 25 64.063 1175.00 WETWELL 3.3 COMPOSITE RI 6 SECTION 2 TO WALL PRIMARY CONTAINMENT Similar to the piping system assessment described above, the Pump Room has criteria used to establish thermal conductors associated with walls and ceilings. The walls and ceilings are grouped by thickness. Pump Room conductors within each group are combined into thermal conductors by calculating an average thickness that is representative of the total area of the group. This approach provides an equivalent heat sink to represent each Pump Room conductor group minimizing the number of thermal conductors required by the GOTHIC model. E (AreaXmickness) AvgThickness = E (Area)
; !4rS iCalc. No. WS129-CALC-001 ; ;W4 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 71 of 150 Table 23 summarizes the results of this thermal conductor calculation.
Table 23 Pump Room Concrete conductors PUMP ROOM CONCRETE THERMAL CONDUCTORS Conductor # BOUNDARY CONDITION I ORIENTATION THICKNESS SURFACE AREA Material Details (in) (ft2 ) BOUNDARY CONDITION ADIABATIC 4 Wall 36 1958.063 Concrete S Wall 48 4359.375 Concrete 6 Wall 60 714 Concrete 7 Wall 72 133 Concrete BOUNDARY CONDITION D104 CORRIDOR 8 Wall 36 1405.688 Concrete 9 Wall 48 1026.375 Concrete 10 Wall 72 208.25 Concrete BOUNDARY CONDITION MAIN REACTOR BUILDING I Ceiling 18 2908 Concrete 12 Ceiling 24 3117 Concrete 13 Wall 35.117 5630.625 Concrete 14 Wall 48 121.875 Concrete 15 Wall 58.138 706.875 Concrete BOUNDARY CONDITION INTERNAL 16 Wall 35.1 4743.45 (9286.9) Concrete 17 Wall 60 97.5 Concrete BOUNDARY CONDITION WETWELL 18 COMPOSITE WALL 64.063 5975 Table 35 19 COMPOSITE WALL 154.863 5676.25 Table 35
CaFc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 72 of 150 MAIN REACTOR BUILDING THERMAL CONDUCTORS The main reactor building has thermal conductors that have a heated surface (Primary Containment - Drywell above 501', wetwell below 501'), have an adiabatic surface (Assumption 4.5), communicate with the pump room and refueling floor volumes, and have both surfaces internal to the volume. The conductors that have a heated surface are associated with primary containment walls. These heat structures will be assigned a boundary condition that is a time dependent temperature value that matches the drywell and wetwell response to the LOCA conditions, Table 36 and 37. Those conductors within the main reactor building volume that are assigned an adiabatic boundary condition are associated with walls that communicate to conditions outside of the reactor building. The thermal conductors that communicate with the pump rooms and refueling floor are the pump room ceilings and the refueling floor. The conductors that contain both sides within the main reactor building volume are the walls that adjoin the internal rooms. Those conductors that are associated with internal rooms are documented in Tables 24 and 25. It should be noted that the thermal conductors associated with these internal rooms have conductors that communicate with the reactor building atmosphere, the fuel pool, the ambient and the primary containment. These are identified in the table by the boundary condition column of the table. The atmosphere boundary condition is identified as adiabatic in the table. Table 26 develops a summary of the thermal conductors that represent the exterior walls of the reactor building. Table 27 develops a summary of the thermal conductors that are in communication with the drywell as well as the fuel pool that communicate with the main reactor building volume. The floor thermal conductors are developed in Table 28. The thermal conductor thickness and surface area inputs are summarized in Table 30. Thermal conductor thickness is defined to be the inner surface to the outer surface of the structure unless specified otherwise.
Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 73 of 150 Table 24 identifies the wall, floor and ceiling dimensions and reports the surface area calculated from these thermal conductors associated with the Auxiliary Rooms. The boundary conditions are identified along with the thermal conductors material and orientation. All of these conductors communicate with the Main Reactor Building Volume. The inclusion of a column labeled Boundary Condition Location is only to identify what communicates with the other side of the conductor. The term INTERNAL identifies that both sides of the conductor are in communication with the Main Reactor Building Volume. SurfaceArea = (HeightXWidth) Note that where the width and height are not provided the surface area was taken directly from the reference. Table 24 Auxiliary Rooms Walls, Floors and Ceilings Structure Location Structure WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation LOCATION (ft) ft) (in) (ft 2) FUEL POOL HEAT NORTH WALL 22.75 14.00 24 318.50 INTERNAL 3.3 Concrete Wall EXCHANGER PUMP ROOM (R506)_ FUEL POOL HEAT SOUTH WALL 22.75 14.00 24 318.50 INTERNAL 3.3 Concrete Wall EXCHANGER PUMP ROOM (R506) FUEL POOL HEAT WEST WALL 31.75 14.00 30 444.50 ADIABATIC 3.3 Concrete Wall EXCHANGER PUMP ROOM (R506) _ FUEL POOL HEAT EAST WALL 20.75 14.00 18 290.50 INTERNAL 3.3 Concrete Wall EXCHANGER PUMP ROOM SECTION I WALL (R506) _ _ FUEL POOL HEAT EAST WALL 11.00 14.00 18 154.00 INTERNAL 3.3 Concrete Wall EXCHANGER PUMP ROOM SECTION 2 (R506) BLOCK WALL _
Calc. No. WS129-CALC-001
.^- CALCULATION CONTROL SIEET Rev. 0 ENERCON SERVICES, INC. Page No. 74 of 150 Structure Location Structure WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation LOCATION (ft) (ft) (in) (ft2)
FUEL POOL HEAT CEILING AREA 31.75 14.20 72 450.85 INTERNAL 3.3 Concrete Wall EXCHANGER PUMP ROOM BELOW 572' (R506)_ FUEL POOL HEAT CEILING AREA 31.75 8.50 64 269.88 FUEL POOL 3.3 Concrete Wall EXCHANGER PUMP ROOM BELOW FUEL (R506) POOL FUEL POOL HEAT FLOOR 31.75 22.75 18 722.31 INTERNAL 3.3 Concrete Floor EXCHANGER PUMP ROOM (R506) DC MCC ROOM (DIV. 1) NORTH WALL 12.00 28.50 36 342.00 ADIABATIC 3.3 Concrete Wall (R212) DC MCC ROOM (DIV. 1) SOUTH WALL 10.00 28.50 12 285.00 INTERNAL 3.3 Concrete Wall (R212) DC MCC ROOM (DIV. 1) WEST WALL 6.50 28.50 12 185.25 INTERNAL 3.3 Concrete Wall (R212) DC MCC ROOM (DIV. 1) EAST WALL 8.00 28.50 12 228.00 INTERNAL 3.3 Concrete Wall (R212) DC MCC ROOM (DIV. 1) CEILING - - 18 92.00 INTERNAL 3.3 Concrete Floor (R212)_ DC MCC ROOM (DIV. 1) FLOOR - - 24 92.00 PUMP ROOM 3.3 Concrete Floor (R212)_ MCC ROOM (DIV 2) (R410) NORTH WALL 7.5 24 12 180.00 INTERNAL 3.3 Concrete Wall MCC ROOM (DIV 2) (R410) SOUTH WALL 7.5 24 12 180.00 INTERNAL 3.3 Concrete Wall MCC ROOM (DIV 2) (R410) WEST WALL 16.5 24 12 396.00 INTERNAL 3.3 Concrete Wall SECTION I MCC ROOM (DIV 2) (R410) WEST WALL 3.5 24 42 84.00 INTERNAL 3.3 Concrete Wall SECTION 2 II MCC ROOM (DIV 2) (R410) EAST WALL 20 24 12 480.00 INTERNAL 3.3 Concrete Wall MCC ROOM (DIV 2) (R410) CEILING 20.00 7.5 24 150.00 INTERNAL 3.3 Concrete Floor
..t Calc. No. WS129-CALC-001 ...... CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 75 of 150 Structure Location Structure WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation LOCATION
_ _ __ __ __ __ __ __ __ _ _ _ _ _ __ __ __ __ __ _ _ _ (f t ) (ft ( in ) ( ft 2 ) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ MCC ROOM (DIV 2) (R410) FLOOR 20.00 7.5 12 150.00 INTERNAL 3.3 Concrete Floor MCC ROOM (DIV 1) (R411) NORTH WALL 21.5 25 36 537.50 ADIABATIC 3.3 Concrete Wall MCC ROOM (DIV 1) (R41 1) SOUTH WALL 17.5 25 12 437.50 INTERNAL 3.3 Concrete Wall SECTION I MCC ROOM (DIV 1) (R41 1) SOUTH WALL 4 25 48 100.00 INTERNAL 3.3 Concrete Wall SECTION 2 MCC ROOM (DIV 1) (R41 1) WEST WALL 6.00 25.00 12 150.00 INTERNAL 3.3 Concrete Wall MCC ROOM (DIV 1) (R41 1) EAST WALL 8.50 25.00 12 212.50 INTERNAL 3.3 Concrete Wall MCC ROOM (DIV 1) (R411) CEILING 8.50 12.50 12 106.25 INTERNAL 3.3 Concrete Floor MCC ROOM (DIV 1) (R41 1) CEILING - - 12 9.6 INTERNAL 3.3 Concrete Floor MCC ROOM (DIV 1) (R41 1) FLOOR 8.50 12.50 12 106.25 INTERNAL 3.3 Concrete Floor MCC ROOM (DIV 1) (R41 1) FLOOR - - 12 9.6 INTERNAL 3.3 Concrete Floor ANALYZER ROOM IA (R516) NORTH WALL 5.50 23.00 21 126.50 INTERNAL 3.3 Concrete Wall SECTION 1 ANALYZER ROOM I A (R516) NORTH WALL 3.50 23.00 42 80.50 INTERNAL 3.3 Concrete Wall SECTION 2 ANALYZER ROOM IA (RS16) SOUTH WALL 8.00 23.00 12 184.00 INTERNAL 3.3 Concrete Wall ANALYZER ROOM IA (R516) WEST WALL 6.00 23.00 12 138.00 INTERNAL 3.3 Concrete Wall ANALYZER ROOM IA (R516) EAST WALL 15.00 23.00 12 345.00 INTERNAL 3.3 Concrete Wall ANALYZER ROOM IA (R516) CEILING - - 12 5.66 INTERNAL 3.3 Concrete Floor ANALYZER ROOM IA (R516) FLOOR - - 32 5.66 INTERNAL 3.3 Concrete Floor ANALYZER ROOM 1B (R512) NORTH WALL 6.00 23.00 21 138.00 INTERNAL 3.3 Concrete Wall ANALYZER ROOM 1B (R512) SOUTH WALL 6.00 23.00 12 138.00 INTERNAL 3.3 Concrete Wall ANALYZER ROOM lB (R512) WEST WALL 14.00 23.00 36 322.00 INTERNAL 3.3 Concrete Wall SECTION I ANALYZER ROOM 1B (R512) WEST WALL 1.75 23.00 102 40.25 INTERNAL 3.3 Concrete Wall SECTION 2 I I_
a Calc. No. WS129-CALC-001
. A CALCULATION CONTROL SHEET Rev.
ENERCON SERVICES, INC. Page No. 76 of 150 Structure Location Structure WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and Description AREA CONDITION Orientation LOCATION (ft) (ft) (in) (ft 2) _ ANALYZER ROOM 1B (R512) EAST WALL 16.00 23.00 12 368.00 INTERNAL 3.3 Concrete Wall ANALYZER ROOM lB (R512) CEILING 6.00 16.00 12 96.00 INTERNAL 3.3 Concrete Floor ANALYZER ROOM IB (R512) FLOOR 6 16 32 96.00 INTERNAL 3.3 Concrete Floor 112 RECOMBINER MCC NORTH WALL 17 17 60 289.00 DRYWELL 3.3 Concrete Wall ROOM (DIV. 1) (R611) _ H2 RECOMBINER MCC SOUTH WALL 17.00 17 12 289.00 INTERNAL 3.3 Concrete Wall ROOM (DIV. 1) (R61 1) . _ _ _ H2 RECOMBINER MCC WEST WALL 9.00 17 12 153.00 INTERNAL 3.3 Concrete Wall ROOM (DIV. I) (R611) - H2 RECOMB1NER MCC EAST WALL 9 17 12 153.00 INTERNAL 3.3 Concrete Wall ROOM (DIV. I)(R611) - H2 RECOMBINER MCC CEILING 9 17 12 153.00 INTERNAL 3.3 Concrete Floor ROOM (DIV. 1) (R611) - H2 RECOMBINER MCC FLOOR 9 17 12 153.00 INTERNAL 3.3 Concrete Floor ROOM (DIV. 1) (R61 1) H2 RECOMBINER MCC NORTH WALL 9 17 60 153.00 FUEL POOL 3.3 Concrete Wall ROOM (DIV. 2) (R6o12) -- H2 RECOMBINER MCC SOUTH WALL 9 17 12 153.00 INTERNAL 3.3 Concrete Wall ROOM (DIV. 2) (R612) _ H2 RECOMBINER MCC WEST WALL 20 17 24 340.00 INTERNAL 3.3 Concrete Wall ROOM (DIV. 2) (R612) ___ H2 RECOMBINER MCC EAST WALL 20.00 17.00 12 340.00 INTERNAL 3.3 Concrete Wall ROOM (DIV. 2) (R612) __________ H2 RECOMBINER MCC CEILING 9.00 20.00 12 180.00 INTERNAL 3.3 Concrete Floor ROOM (DIV. 2) (R612) ___________ H2 RECOMBINER MCC FLOOR 9.00 20.00 12 180.00 INTERNAL 3.3 Concrete Floor ROOM (DIV. 2) (R612) I I I
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ENERCON SERVICES, INC. Page No. 77 of 150 Table 25 identifies the wall dimensions and reports the surface area calculated for these thermal conductors associated with the Miscellaneous Interior Walls. The boundary conditions are identified along with the thermal conductors material and orientation. All of these conductors communicate with the Main Reactor Building Volume. The inclusion of a column labeled Boundary Condition Location is only to identify what communicates with the other side of the conductor. The term INTERNAL identifies that both sides of the conductor are in communication with the Main Reactor Building Volume. SurfaceArea = (IleightXWidth) Table 25 Miscellaneous Interior Walls Associated Room Elevation WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and AREA CONDITION Orientation LOCATION I (ft) (ft) (ft) (in) (fe) I R206 471.0 10.86 28.00 12 304.21 INTERNAL 2.17 Concrete Wall R213 471.0 38.03 16.50 12 627.43 INTERNAL 2.17 Concrete Wall R211 471.0 21.73 16.50 12 358.54 INTERNAL 2.17 Concrete Wall R208 471.0 20.18 28.00 12 564.96 INTERNAL 2.17 Concrete Wall R214 471.0 55.88 16.50 12 921.94 INTERNAL 2.17 Concrete Wall R305 501.0 41.67 19.00 12 791.81 INTERNAL 2.18 Concrete Wall R312 501.0 24.70 19.00 12 469.22 INTERNAL 2.18 Concrete Wall R320 501.0 15.43 19.00 12 293.27 INTERNAL 2.18 Concrete Wall R309 501.0 72.54 19.00 12 1378.33 INTERNAL 2.18 Concrete Wall R315 501.0 46.30 12.25 12 567.23 INTERNAL 2.18 Concrete Wall R319 501.0 12.35 19.00 12 234.61 INTERNAL 2.18 Concrete Wall R412 522.0 26.24 24.00 12 629.73 INTERNAL 2.19 Concrete Wall R408 522.0 64.83 24.00 12 1555.82 INTERNAL 2.19 Concrete Wall R405 522.0 20.84 24.00 12 500.08 INTERNAL 2.19 Concrete Wall UNLABELED 522.0 24.70 24.00 12 592.69 INTERNAL 2.19 Concrete Wall NEAR OPEN FLOOR HATCH _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ R 07 548.0 71.00 24.00 27.79 1704 INTERNAL 2.19 Concrete Wall
Fv " Caic. No. WS129-CALC-001 t CALCULATION CONTROL SHEET Rev. ENERCON SERVICES, INC. Page No. 78 of 150 Associated Room Elevation WIDTH HEIGHT THICKNESS SURFACE BOUNDARY REF Material and AREA CONDITION Orientation LOCATION 548.0 _ (ft5.(ft)2 (in) (fte) II R509 548.0 58.60 24.00 23.16 1407.66 INTERNAL 2.19 Concrete Wall R510 548.0 60.20 24.00 23.16 1444.7 INTERNAL 2.19 Concrete Wall R5 11 548.0 55.57 24.00 23.16 1333.57 INTERNAL 2.19 Concrete Wall R505 548.0 52.48 24.00 23.16 1259.48 INTERNAL 2.19 Concrete Wall R605 572.0 18.52 32.88 37.04 609 INTERNAL 2.19 Concrete Wall R606 572.0 52.48 32.88 37.04 1725.49 INTERNAL 2.19 Concrete Wall
Caic. No. WS129-CALC-001 F 13CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 79 of 150 Table 26 identifies the exterior wall dimensions and reports the surface area calculated for these thermal conductors. The boundary conditions are identified along with the thermal conductors material and orientation. All of these conductors communicate with the main reactor building volume. The inclusion of a column labeled Boundary Condition Location is only to identify what communicates with the other side of the conductor. The term ADIABATIC identifies that these conductors do not transfer heat out of the main building although they do transfer heat with the main reactor building volume. SurfaceArea = 2(HeightXWidth) Table 26 Main Reactor Building Walls Structure Description Elevation WIDTH HEIGHT THICKNESS SURFACE ARIEA BOUNDARY REF Material and CONDITION Orientation (ft) (ft) (ft) (in) (ft2) LOCATION RB ELEVATION 471 471 129.67 28 32 7261.52 ADIABATIC 3.1 Concrete Wall NORTH & SOUTH __ RB ELEVATION 471 471 145.84 28 31 8167.04 ADIABATIC 3.1 Concrete Wall EAST & WEST RB ELEVATION 501 501 128.17 19 29 4870.46 ADIABATIC 3.1 Concrete Wall NORTH & SOUTH ______ RB ELEVATION 501 501 144.5 19 27 5491 ADIABATIC 3.1 Concrete Wall EAST & WEST RB ELEVATION 522 522 128.25 24 28.5 6156 ADIABATIC 3.1 Concrete Wall NORTH & SOUTH RB ELEVATION 522 522 144.84 24 25 6952.32 ADIABATIC 3.1 Concrete Wall EAST & WEST ____________ _ RB ELEVATION 548 548 128.83 22.00 25.02 5668.67 ADIABATIC 3.1 Concrete Wall NORTH & SOUTH . RB ELEVATION 548 548 145.00 22.00 24 6380 ADIABATIC 3.1 Concrete Wall EAST & WEST . RB ELEVATION 572 572 129.08 32.88 23.52 8487.23 ADIABATIC 3.1 Concrete Wall NORTH & SOUTH ___ RB ELEVATION 572 572 145.00 32.88 24 9535.2 ADIABATIC 3.1 Concrete Wall EAST & WEST _
FrCaic. No. WS129-CALC-001 3'A CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 80 of 150 Table 27 identifies the Drywell and Fuel Pool wall dimensions and reports the surface area calculated for these thermal conductors. The boundary conditions are identified along with the thermal conductors material and orientation. This table is organized differently from the previous tables in terms of the boundary conditions. The boundary conditions are described by both the structure description as well as the boundary condition location. With the exception of the Fuel Pool Wail communicating with the drywell all of these structures communicate with the main reactor building volume atmosphere on one side. The fuel pool wall in question provides heat transfer between the drywell and the fuel pool. The wall thickness reported in the table is established by scaling the referenced drawing. The drywell wall heights are established to be the floor to floor distance. For example, the height of the drywell wall reported for the 572ft elevation is 34.88ft = (606ft 10.Sin) - (572ft) The upper elevations of the drywell wall are reported as having a width as opposed to an outer radius. The width value used is the overall outside dimension of the wall illustrated in the referenced drawing. This will represent the conservative upper bound of this structure, which acts as a source of heat to the reactor building model. For the fuel pool walls the thickness is taken from the referenced drawing to be 5ft. This value is assigned to both the drywell and reactor building sides of the pool. The fuel pool wall height is established based on the inside pool dimension provided in referenced drawing. For the drywell side of the fuel pool, the wall width is the center to center distance between columns K and L illustrated in the Reference 2.15. For the reactor building side of the fuel pool the wall width is established using Reference 2.18 plan dimensions 113ft-2*22.5ft+2*34ft The surface area of these structures is calculated as follows. SurfaceArea = 2,r(OuterRadiusXHeight) OR SurfaceArea = (WidthXHeight)
ik'; Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. I ENER7CON SERVICES, INC. Page No. 81 of 150 Table 27 Drywell And Fuel Pool Walls Structure Description Elevation Inside Outer WIDTH HEIGHT THICKNESS SURFACE BOUNDARY Material REF Radius Radius AREA CONDITION LOCATION __(ft (ft) (ft) (ft) (in) (ft 2) __ Il DRYWELL WALL 501 46.2 21 60.860 6095.95 RB Concrete 2.12
. Wall DRYWELL WALL 522 41 26 69.77 6697.88 RB Concrete 2.13 I__Wall DRYWELL WALL 548 27.35 33.59 24 74.88 5065.26 RB Concrete 2.14 Wall DRYWELL WALL 572 48.00 34.88 62.31 1674.00 RB Concrete 2.15, NORTH Wall 2.16 DRYWELL WALL 572 48.00 34.88 62.31 1674.00 RB Concrete 2.16 SOUTH Wall DRYWELL WALL EAST 572 45.00 34.88 73.05 1569.38 RB Concrete 2.16
._ Wall FUEL POOL WALL 568 45.00 38.75 60 1743.75 DRYWELL Concrete 2.18
_____ __ _ _ Wall FUEL POOL WALL 568 113 38.75 60 4378.75 RB Concrete 2.15 _ _ _ _ _ __ _ _ _ _ __ __ __ _W all I
Caic. No. WS129-CALC-001 F II CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 82 of 150 The calculation of the Main Reactor Building Floors is developed using the dimensions listed in Table 28. The Lost Area column in the table provides a summary of the corresponding areas listed in Table 28. As described below these areas are subtracted from the over all area. SurfaceArea = (WidthXHeight) - LostArea Table 28 Main Reactor Building Floors Structure Elevation VIDTH HEIGHT THICKNESS LOST AREA SURFACE BOUNDARY REF Material and Description (Table 29) AREA CONDITION Orientation LOCATION (fit) (ft)((in) (ft2) (ft2) RB 471 129.67 145.84 24 14124.40 4786.68 INTERNAL 3.1 Concrete Floor ELEVATION 471 FLOOR RB 501 128.17 144.5 24 8152.56 10368.00 INTERNAL 3.1 Concrete Floor ELEVATION 501 FLOOR _ __ _ ___ RB 522 128.25 144.84 24 6835.20 11740.53 INTERNAL 3.1 Concrete Floor ELEVATION 522 FLOOR RB 548 128.83 145.00 24 5565.59 13115.24 INTERNAL 3.1 Concrete Floor ELEVATION 548 FLOOR RB 572 129.08 145.00 24 3025.67 15690.93 INTERNAL 3.1 Concrete Floor ELEVATION 572 FLOOR
Calc. No. WS129-CALC-001
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laCALCULATION CONTROL SHEET Rev. ENERCON SERVICES, INC. Page No. 83 of 150 When calculating the floor areas within the main building it is necessary to subtract the areas occupied by other building features as well as floor areas already accounted for by rooms within the building that are developed separately. Table 29 summarizes the values that will be subtracted from the floor calculation for the main building. Table 29 Areas Subtracted From Main Building Floors LOST FLOOR AREAS ELEVATION PENETRATION AUXILIARY MISCELLANEOUS PRIMARY Total Area Note Reference AREAS ROOM FLOOR ROOM WALL CONTAINMENT AND CEILING AREAS Table 27 provides AREAS (Table 23 (Width)(Thickness) Radius Values to and Table 24) Table 25 calculate areas unless noted otherwise 1I (ft) ) (f (ft2 ) (ft
- 2) (ft2) 2 (fet) 471 55.76 6,117.00 146.68 7,289.59 13,609.03 Primary 3.1,3.7 Containment
._ _Radius 48' 2" 471 53.72 53.72 3.7 471 19.82 _ 19.82 3.7 471 33.47 33.47 3.7 471 13.41 13.41 3.7 471 12.45 12.45 3.7 471 382.5 _ 382.5 3.7 471 Total 14,124.40 501 331.58 667.05 213 6,705.54 7,917.17 3.7 501 97.55 97.55 3.7 501 91.94 91.94 3.7 501 27.01 27.01 3.7
Caic. No. WS129-CALC-001 Ha, . CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 84 of 150 LOST FLOOR AREAS ELEVATION PENETRATION AUXILIARY MISCELLANEOUS PRIMARY Total Area Note Reference AREAS ROOM FLOOR ROOM WALL CONTAINMENT AND CEILING AREAS Table 27 provides AREAS (Table 23 (Wldth)(Thlckness) Radius Values to and Table 24) Table 25 calculate areas unless noted otherwise 1 (ft) (ft2 t) (ft2 ) (ft 1) _ _ _ _ _ 501 18.88 18.89 3.7 501 Total 8,152.56 522 20.58 265.85 602.33 5,281.02 6,169.78 3.7 522 117.40 117.40 3.7 522 548.02 548.02 3.7 522 Total 6,835.20 548 402.03 823.97 602.32 3,544.62 5,372.94 3.7 548 102.59 102.59 3.7 548 82.06 82.06 3.7 548 8.00 8.00 3.7 548 Total 5,565.59 572 63.25 219.16 1809.56 2,091.97 Primary 3.7 Containment Diameter assumed to be 48ft which equals the width in table 27 572 466.85 1466.85 1 3.7
., = _ Calc. No. WS129-CALC-001 F;,,,!,., CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 85 of 150 LOST FLOOR AREAS ELEVATION PENETRATION AUXILIARY MISCELLANEOUS PRIMARY Total Area Note Reference AREAS ROOM FLOOR ROOM WALL CONTAINMENT AND CEILING AREAS Table 27 provides AREAS (Table 23 (Width)(Thickness) Radils Values to and Table 24) Table 25 calculate areas unless noted otherwise 1I (ft)) (ft) 2 2 (ft ) (ft2) (ft2) 572 466.85 466.85 J 13.7 572 Total I_ 3,025.67 1 1
Caic. No. WS129-CALC-001 Fv, a. CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 86 of 150 Similar to the Pump Room thermal conductors the main reactor building volume thermal conductors are combined. The walls and ceilings are grouped by thickness. Main building conductors within each group are combined into a thermal conductors by calculating an average thickness that is representative of the total area of the group. This approach provides an equivalent heat sink to represent each main building conductor group minimizing the number of thermal conductors required by the GOTHIC model. E (AreaX4hickness) AvgThickness = E (Area) Table 30 summarizes the results of this thermal conductor calculation.
- _: Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 87 of 150 Table 30 Main Building Thermal Conductors Conductor # BOUNDARY THICKNESS SURFACE Material CONDITION / AREA Details ORIENTATION
. (in) j (ft2) . -
AUXILIARY ROOMS PUMP ROOM . - 20 Floor 24 92 Concrete ADIABATIC 21 Wall 33.98 1,324 Concrete INTERNAL 22 Wall 12 4,995.25 Concrete 23 Wall 18 444.5 Concrete 24 Wall 23.36 1,241.5 Concrete 25 Wall 36 322 Concrete 26 Wall 44.26 264.5 Concrete 27 Wall 72 450.85 Concrete 28 Wall 102 40.25 Concrete 29 Floor 12 1,149.36 Concrete 30 Floor 18 814.31 Concrete 31 Floor 24 150 Concrete 32 Floor 32 101.66 Concrete DRYWELL_ 33 Wall 60 - 289 Table 35
- j. Caoc. No. WS129-CALC-001
.3 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 88 of 150 Conductor # BOUNDARY THICKNESS SURFACE Material CONDITION / AREA Details ORIENTATION (in) ut)
FUEL POOL 34 Wall 62.55 422.875 Concrete MISCELLANEOUS WALLS _ ____ _INTERNAL 35 Wall 12 9789.87 Concrete 36 Wall 23.16 5,445.41 Concrete 37 Wall 27.79 1,704 Concrete 38 Wal 37.04 2,334.49 Concrete MAIN STRUCTURE . - ADIABATIC 39 Wall 23.83 24,402.43 Concrete 40 Wall 28.41 44,567.01 Concrete INTERNAL 41 Floor 24 55,700.90 Concrete DRYWELL WALLS RB 42 Wall 61.37 9,443.95 Table 35 43 Wall 72.09 13,332.515 Table 35 FUEL POOL DRYWELL 44 Wall 60 1,743.75 Table 35
F;Caic. No. WS129-CALC-001
.. pCALCULATION CONTROL SHEETRev. 0 ENERCON SERVICES, INC. Page No. 89 of 150 Conductor # BOUNDARY THICKNESS SURFACE Material CONDITION / AREA Details ORIENTATION
_ (in) (ft2) __ _ RB ___I_ 45 Wall 60 4,378.75 Concrete
Calc. No. WS129-CALC-001 E CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 90 of 150 REFUELING FLOOR THERMAL CONDUCTORS The data used to develop the thermal conductors for the refueling floor is provided in Table 31. The final inputs are provided in Table 32. Table 31 identifies the wall, floor and ceiling dimensions and reports the surface area calculated from these thermal conductors associated with the Refueling Floor Volume. The boundary conditions are identified along with the thermal conductors material and orientation. All of these conductors communicate with the Reffieling Floor Volume. The term ADIABATIC identifies that these conductors do not transfer heat out of the refueling floor although they do transfer heat with the Refueling Floor Volume. Table 31 - Refueling Floor Thermal Conductors Structure Elevation WIDTH HEIGIIT THICKNESS LOST AREA SURFACE BOUNDARY REF Material and Description (Table 26) AREA CONDITION Orientation LOCATION (ft2) _(f)(ft) (tt)(in) (ft2) RB ELEVATION 606.9 134.33 61.13 1.598 16,422.21 ADIABATIC 3.1 COMPOSITE 606' 101/2" NORTH WALL SOUTH RB ELEVATION 606.9 150.33 61.13 1.598 18,377.85 ADIABATIC 3.1 COMPOSITE 606' 101/2" EAST WALL W E ST _ _ _ __ _ _ _ _ __ _ _ _ _ _ _ _ _ _ RB ELEVATION 606.9 150.33 134.33 24 3,988.79 16,205.5 INTERNAL 3.1 CONCRETE 606' 101/2" FLOOR FLOOR RB ROOF 668 134.33 150.33 0.049 20,194.28 ADIABATIC 3.1 COMPOSITE __ FLOOR
AM <Caic. No. WS129-CALC-001
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ENERCON SERVICES, INC. Page No. 91 of 150 When calculating the floor areas within the refueling floor it is necessary to subtract the areas occupied by other building features. Table 32 summarizes the values that will be subtracted from the floor calculation for the refueling floor. It should be noted that there may be more than one penetration value associated with a floor. When this is the case a row will be included in the table to represent each penetration. Table 32 Areas Subtracted From Refueling Floor Areas LOST FLOOR AREAS ELEVATION PENETRATION AUXILIARY MISCELLANEOUS FUEL PRIMARY Note Reference AREAS ROOM FLOOR ROOM WALL AREAS POOL CONTAINMENT AND CEILING (Width)(Thickness) Table 27 provides AREAS (24) Table 25 Radius Values to calculate areas unless noted otherwise (ft) (ft 2 ) f (Vt) Vt1) (V2 ______ II 606.9 409.61 1360 1809.56 Primary 3.1, 3.7 Containment Diameter assumed to be 48ft which equals the width in table 27 606.9 409.61 _ 3.7
Calc. No. WS129-CALC-001 FUi CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 92 of 150 Similar to the main reactor building thermal conductors the refueling floor volume thermal conductors are combined. The walls and ceilings are grouped by thickness. Table 33 summarizes the results of this thermal conductor calculation. Table 33 Refueling Floor Thermal Conductors Conductor # BOUNDARY CONDITION / THICKNESS SURFACE Material ORIENTATION AREA Details (in) (ft2) 46 ADIABATIC 1.598 34,800.06 Table 35 COMPOSITE WALL 47 ADIABATIC 0.049 20,194.28 Table 35 COMPOSITE ROOF 48 MAIN REACTOR BUILDING 24 16,205.5 Concrete VOLUME CONCRETE FLOOR THERMAL CONDUCTOR MATERIAL PROPERTIES The basic material properties that will be applied to the structures are provided in Table 34. Several of the structures are identified as having several materials or are composite structures. The composition of these structures are provided in Table 35. Table 34 Material Properties Material Description Density Conductivity Heat Capacity Reference (lb/ft) (BTU/hr/ftfF) (BTU/IbF) Concrete 144 0.54 0.2 1.13 Carbon Steel 490 26.00 0.11 1.13, Piping Specification SA106 Calcium Silicate is 0.0375 (0 0F) 0.201 1.16 0.0375 (200°F) 0.0417 (300 0F) 0.0458 (400 0F) 0.05 (500"F) 0.055 (600 0F) Poly Urethane 2.5 0.1 -0.2 0.48 1.14 (Ref 1.14 (0.1 Used) Table 4), 1.15 Fiberglass 6 0.029 0.21 1.13 (Glass Wool I._ Packed)
Caic. No. WS129-CALC-001 Xi:NCALCULATION CONTROL SHEET ev. ENERCON SERVICES, INC. Page No. 93 of 150 Table 35 Composite Structure Material Composition Conductor Description 8 Thickness Material Reference 1 I Wetwell Wall Steel Liner 1.5 Carbon Steel 3.3 Wetwell Wall Poly Urethane 2.25 Poly Urethane 3.3 Wetwell Wall Fiberglass 0.3125 Fiberglass 3.3 Wetwell Wall Concrete 60 Concrete 3.3 18 Total Thickness 64.0625 Wetwell Wall Steel Liner 1.5 Carbon Steel 3.3 Wetwell Wall PolyUrithane 2.25 Poly Urethane 3.3 Wetwell Wall Fiberglass 0.3125 Fiberglass 3.3 Wetwell Wall Concrete 150.84 Concrete 3.3 19 Total Thickness 154.9 Insulated Piping Steel 0.38 Carbon Steel 3.3 Insulated Piping Insulation 2 Calcium Silicate 3.3 2 Total Thickness 2.38 Refueling Floor Walls Metal 0.049 Carbon Steel 1.18 Interior Refueling Floor Walls Insulation 1.5 Fiber Board 1.18 Refueling Floor Walls Metal 0.049 Carbon Steel 1.18 Exterior 46 Total Thickness 1.598 47 Refueling Floor Roof 0.049 Carbon Steel Assumption 4.13 Drywell Wall Steel Liner 1.5 Carbon Steel Assumption 4.12 Drywell Wall Concrete 58.5 Concrete 33 & 44 Total Thickness 60 Table 24 Drywell Wall Steel Liner 1.5 Carbon Steel Assumption 4.12 Drywell Wall Concrete 59.87404 Concrete __LOX __ 42 Total Thickness 61.37404 Table 24 Drywell Wall Steel Liner 1.5 Carbon Steel Assumption 4.12 Drywell Wall Concrete 70.59747 Concrete 43 Total Thickness 72.09747 Table 24 8 Drywell Concrete Thickness is developed by subtracting the Steel Liner thickness from the overall thickness.
T V Caic. No. WS129-CALC-001
'11 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 94 of 150 THERMAL CONDUCTOR BOUNDARY TEMPERATURES PRIMARY CONTAINMENT DRYWELL CONDUCTOR INNER WALL TEMPERATURE The inner surface of conductors used to represent the primary containment are assigned a temperature that corresponds to the containment accident profile. As described in Assumption 4.9 a composite of the LOCA and MSLB are used. The profiles for these accidents are obtained from Reference 1.21 and illustrated in Table 36.
In addition, a conservative representation of the associated heat transfer coefficient (Assumption 4.10) will be used to ensure that the heat flow is biased into the structure from the containment atmosphere. The heat transfer coefficient is assigned the Type 4 (Refer to Table 38) in the GOTHIC Model. The coefficient used is as follows. If the vapor temperature is greater than the wall temperature the value assigned is 1120BTU/hr/ft2/R This value corresponds to 4 times the maximum UCHIDA heat transfer coefficient documented in Reference 1.10 (28OBTU/hr-ft 2 -F). If the vapor temperature is less than or equal to the wall temperature than the value assigned is 0.lBTU/hr/ft 2 fR (Heat Transfer Coefficient Type 2 Refer to Table 38). This minimum value is considered to be a representative natural convection heat transfer coefficient that will minimize wall cooling to ensure a conservative result. Table 36 - Composite Profile Assigned to Drywell Boundary Condition Time Temperature (sec)(F 0.0 135 0.1 150 0.7 328 1 290 4 285 10 280 1,000 280 2,000 285 10,000 280 86,400 250 1,000,000 165 10,000,000 110
Caic. No. WS129-CALC-001 i,,, ,,,aCALCULATION CONTROL SHEET Rev. 1 ENERCON SERVICES, INC. Page No. 95 of 150 PRIMARY CONTAINMENT WETWELL CONDUCTOR INNER WALL TEMPERATURE The inner surface of conductors used to represent the primary containment wetwell are assigned a temperature that corresponds to the wetwell pool accident LOCA profile. The profile for the accident is obtained from Reference 1.19 and illustrated in Table 37. See assumption 4.15 for discussion of the profile. I 1 Table 37 - Composite Profile Assigned to Wetwell Boundary Condition Time Temperature (sec)(F) 0 95 10 105 100 150 1,000 160 10,000 200 35,000 204 50,000 200 10,000,000 200 FUEL POOL CONDUCTOR INNER WALL TEMPERATURE The inner surface of conductors used to represent the fuel pool will be assigned a temperature that corresponds to the calculated fuel pool temperature. The GOTHIC model will dynamically calculate this value. D104 CORRIDOR CONDUCTOR INNER WALL TEMPERATURE The west wall of two RHR pump rooms communicate with an adjacent corridor designated as D104 in Reference 3.3. The outer surface of these wall conductors are in communication with the air temperature of the D104 Corridor. It is assumed that the temperature in the D104 corridor is 1047F. This value is selected to bound that expected under normal or accident conditions. The convection resistance that exists between the air in the corridor and the wall is ignored and the boundary condition of the conductor is set to 104F. The temperature and the convection assumptions are used to conservatively minimize heat transfer from the pump rooms to the corridor.
Calc.No. WS129-CALC-001 FCALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 96 of 150 Table 38 - GOTHIC Heat Transfer Coefficient Inputs Heat Transfer Coefficient Types - I Heat Cndl Sp Nat For Description Type Transfer Nominal Cnv Cnd Cnv Cnv Cnv Rad Option Value FF Opt Opt HTC Opt Opt Opt 1 Sp 1 14 2 Drywell Temperature Ambient Profile (Table 36) and HTC 2 Sp Conv1 18 OFF Drywell Convection HTC _ Coefficient 3 Sp Heat 0 Adiabatic Boundary Flux .___Condition 4 Direct ADD UCHIDA HORZ OFF ON RB Side Pipe CYL Conductor Convection
._ _Coefficient 5 Direct ADD UCHIDA HORZ OFF ON RB Side Pipe CYL Conductor Convection
__ Coefficient 6 Direct ADD UCHIDA HORZ OFF ON RB Side Pipe CYL Conductor Convection Coefficient 7 Sp Temp 1 26 WW Inside and ECCS Inside Pipe _ _ _ Temperature (Table 37) 8 Sp Temp 1 25 Fuel Pool Cooling System Inside Pipe Temperature 9 Direct ADD UCHIDA VERT OFF ON RB Side Vertical Wall
. . SURF Convection Coefficient 10 Direct ADD UCHIDA FACE UP OFF ON RB Side Floor Convection Coefficient 11 Direct ADD UCHIDA FACE OFF ON RB Side Ceiling
_DOWN I _Convection Coefficient 12 Correlation Set VERT OFF OFF Fuel Pool Side Wall SURF Heat Transfer __ Coefficient
£Calc. No. WS129-CALC-01l t -: CALCULATION CONTROL SHEET Rev. 1 l ENERCON SERVICES, INC. Page No. 97 of 150 Natural Convection Correlation's used in the analysis are as follows.
Vertical Surface - Flat vertical surface used for internal walls h = (kfax40.59Raa m,0.13RaVf3) Where k is the thermal conductivity of the fluid; L is the characteristic length of the heat sink; Ra is the dimensionless Rayleigh number. Face Up - Flat horizontal surface facing upward such as a floor When the surface is hotter than the surrounding fluid the following is used. h = (/6JMa(0.54Ra42s,0.14RaV) When the surface is cooler than the surrounding fluid the following is used.
= (L).27Rao2S Where k is the thermal conductivity of the fluid; L is the characteristic length of the beat sink; Ra is the dimensionless Rayleigh number.
F] Calc. No. WS129-CALC-001
- CALCULATION CONTROL SHEET Rev.
ENERCON SERVICES, INC. Page No. 98 of 150 Face Down - Flat horizontal surface facing downward such as a ceiling When the surface is cooler than the surrounding fluid the following is used. h = (~fi+a$0.54Rao25,0.14Ra* ) When the surface is hotter than the surrounding fluid the following is used. h= /L).27Rao-5 Where k is the thermal conductivity of the fluid; L is the characteristic length of the heat sink; Ra is the dimensionless Rayleigh number. Horizontal Cylinder - Horizontal Cylinder such as a pipe. h = ( f)+a(0.53RaU ,0.126RaX ) Where k is the thermal conductivity of the fluid; L is the characteristic length of the heat sink; Ra is the dimensionless Rayleigh number. Vertical Surface with Radiation Option (Heat Transfer Coefficient Type 5) Refer to Vertical Surface described above for the correlation applied for natural convection. Adiabatic Surface This boundary is assigned a zero heat flux. Radiation Heat Transfer Option The radiation heat transfer option which allows heat transfer between the thermal conductor surface and the air space will be applied to those conductors that represent a potential heat source to the reactor building. Included amongst these are the drywell wall, wetwell wall and the piping conductors.
- 1 Calc. No. WS 129-CALC-001 n-z CALCULATION CONTROL SHEET Rev.
ENERCON SERVICES, INC. Page No. 99 of 150 HEAT INPUTS AND FAN COOLER UNITS This section develops the basis for the direct heat loads and cooler inputs that will be included in the GOTHIC drawdown analysis. Direct heat loads are defined to be electrical heat loads that are assumed to be applied directly to the atmosphere without the need to evaluate any physics of heat transfer. The result of this effort is Table 39. This table provides the values to be used as well as the time when they start and stop in the analysis. These values are summations of values provided in Table 40, which includes the referenced basis for each input used to create the summary Table. The main building electrical equipment that is tripped off at the time of the LOOP will provide residual heat to the building. This heat load decays with time and is described by the Equation 15. Equation 15 is developed based upon the same criteria outlined in Reference 3.12. Equation 15 K= ~ T hr - See Note 9 II K= 500F F 5,266.28BTU1(^h)(°F)) Q = 5,266.28 BTU (150e-T -tair) Where T is the elapsed time in hours tair is the vapor temperature of the main reactor building volume (Volume 1) 9 The value 263,314BTU/hr represents the 229,184BTU/hr + 34,13OBTU/hr provided on page 39 of Reference 3.12
F}.\' Catc. No. WS129-CALC-001 F CALCULATION CONTROL SHEET Rev. 0 ENERCON SERNCES, INC. Page No. 100 of 150 Table 39 - Summary of Direct Heat Input Loads MODEL Volume Heat Load Value Heat Load Value Time Starts Time Ends (BTU/hr) (BTU/s) (seconds) (seconds) Pump Room 880,089.8 244.5 30 Never Pump Room 43,487.51 12.08 When Fan Starts Never Main Building 155,651.4 43.24 0 Never Main Building 39,434.55 10.95 When Fan Starts Never Main Building 15,724.04 4.37 When Fuel Pool Never Cooling Starts Main Building Equipment Equation 15 Equation 15 0 NA Main Building Emergency 156,236.08 43.4 0 Never Lighting Refueling Floor 78,479.26 21.8 0 Never Refueling Floor 9,794,000.0 2,720.56 0 Never (Fuel Pool) I Table 40 - Direct Heat Loads For Drawdown Analysis MODEL Location Location Heat Load Description Heat Load Time Starts Time Ends Reference Volume Description Value _____(BTUlhr) (seconds) (seconds) Pump Room R1 HPCS Pump Room Lighting 11,601.53 30 Never 3.3 _(R-6) Pump Room R11 HPCS Pump Room RRA-M FN/4 Fan 23,929.79 When Fan Never 3.3 (R-6) Motor Cooler Starts Pump Room R11 HPCS Pump Room HPCS-M-P13 6,213.15 30 Never 3.3 (R-6) Pump Room Rl1 HPCS Pump Room HPCS-M-P/1 Pump 435,000.00 30 Never 3.3 (R-6) Motor Pump Room Ri l HPCS Pump Room FDR-P-4AB Floor 5,585.34 30 Never 3.3 (R-6) Drain Pump Motors Pump Room R12 LPCS Pump Room Lighting 7,541.00 30 Never 3.3 R-5 Pump Room R12 LPCS Pump Room RRA-M-FN/5 Fan 12,498.97 When Fan Never 3.3 R-5 Motor _ Cooler Starts Pump Room R12 LPCS Pump Room LPCS-M-P/1 Pump 238,000.00 30 Never 3.3 R-5 Motor Pump Room R12 LPCS Pump Room LPCS-M-P/2 6,213.15 30 Never 3.3 R-5 Pump Room R15 RCIC Pump Room Electrical Equipment, 11,192.07 30 Never 3.3 R-3 lights, cable Pump Room R6 RHR Pump 2A Electrical Equipment, 11,703.90 30 Never 3.3 _ _ I Room lights, cable
ZCafc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 101 of 150 MODEL Location Location Heat Load Description Heat Load Time Starts Time Ends Reference Volume Description Value (BTUlhr) (seconds) (seconds)_______ Pump Room R6 RHR Pump 2A PSR-M-P/5 motor 850.00 30 Never 3.3 Room Pump Room R6 RHR Pump 2A RRA-M-FN/2 Fan 7,058.75 When Fan Never 3.3 Room Motor Cooler Starts Pump Room R6 RHR Pump 2A RHR-M-P/2A 126,000.00 30 Never 3.3 Room Pump Room R6 RHR Pump 2A FDR-P-IAB 5,585.34 30 Never 3.3 Room Pump Room R7 RHR Pump 2B Electrical Equipment, 14,604.28 30 Never 3.3 Room R-1 (R7) lights, cable Main Building R212 DC MCC Room Electrical Equipment, 11,874.51 0 Never 3.3 (DIV. 1) (R212) lights, cable Main Building R212 DC MCC Room RRA-FC-12 Fan Motor 6,876.85 When Fan Never 3.3 (DIV. 1) (R212) - Cooler Starts Main Building R410 MCC Room (Div 2) Electrical Equipment, 0 Never Never 3.3 _ _ _ _ _ _ _lights, cable Main Building R410 MCC Room (Div 2) RRA-FC-10 Fan Motor 0 Never Never 3.3 (R410) Main Building R411 MCC Room (Div 1) Electrical Equipment, 35,964.76 0 Never 3.3 (R411) lights, cable Main Building R411 MCC Room (Div 1) RRA-FC-l 1 Fan Motor 9,192.79 When Fan Never 3.3 (R411) Cooler Starts Main Building R506 Fuel Pool Heat Lighting 28,321.39 0 Never 3.3 Exchanger Pump Room ,RS06) Main Building R506 Fuel Pool Heat FPC-M-P/IA or FPC- 15,724.04 When Fuel Never 3.3 Exchanger Pump M-P/IB Pump Motor Pool Cooling Room (R506) Starts Main Building R506 Fuel Pool Heat RRA-FC-19 or 20 Fan 12,722.17 When Fan Never 3.3 Exchafiger Pump Motor Cooler Starts Room (R506) Main Building R512 Analyzer Room IB Electrical Equipment, 9,758.94 0 Never 3.3 (R512) lights, cable Main Building R512 Analyzer Room lB RRA-FC-17 Fan Motor 3,274.69 When Fan Never 3.3 (R512)Cooler Starts Main Building R516 Analyzer Room IA Electrical Equipment, 8,462.30 0 Never 3.3 (R516)lights, cable Main Building R516 Analyzer Room IA RRA-FC-15 Fan Motor 3,274.69 When Fan Never 3.3 (R516) Cooler Starts Main Building R611 H2 Recombiner Electrical Equipment, 18,289.48 0 Never 3.3 MCC Room (Div. 1) lights, cable (R611L) Main Building R61 I H2 Recombiner RRA-FC-13 Fan Motor 4,093.36 When Fan Never 3.3 MCC Room (Div. 1) Cooler Starts (R611)
EK. CALCULATION CONTROL SHEET Caic. No. Rev. WS129-CALC-001 1 ENERCON SERVICES, INC. Page No. 102 of 150 MODEL Location Location Heat Load Description Heat Load Time Starts Time Ends Reference Volume Description Value TUhr) (seconds) (sonds Main Building R612 H2 Recombiner Electrical Equipment, 0 Never Never 3.3 MCC Room (Div. 2) lights, cable Main Building R612 H2 Recombiner RRA-FC-14 Fan Motor 0 Never Never 3.3 MCC Room (Div. 2) (R612) Main Building Reactor Stack Monitor Load 42,980.0 0 Never 3.14 Building _- Main Building Reactor Emergency Lighting Emergency Lighting 156,236.08 '8 0 Never 3.12 Building __ __________ Main Building Reactor Main Reactor Off Line Equipment 263,314.00 NA NA 3.12 Building Building Equipment Heat Decay Pre trip Equation 15 Heat Load Refueling Floor Reactor dry cask 78,479.26 0 Never 1.27 Building (23kW) Refueling Floor . Refueling Floor Fuel Pool Decay Heat 9,794,000.00 0 Never 3.6 Fuel Pool (Assumption Water 3.3) It should be noted that the refueling floor fuel pool water heat load described in Table 40 is applied to the liquid in the fuel pool modeled in GOTHIC. Heat transfer from the pool to the rest of the building is accounted for by heat and mass transfer from the pool. All other heat loads listed in Table 40 apply the heat loads to the building volume atmospheres. Rooms within the reactor building are equipped with safety related fan cooler units. These units are cooled by Service Water and provide safety related cooling to those areas with equipment required to mitigate the consequences of an accident. Table 41 provides a list of the rooms where coolers are credited as well as the overall UA (Reference 3.3) value to be used to establish the GOTHIC inputs. Note that the minimum water flow rate reported in Reference 3.3 is used, which corresponds with the Cooler UA value reported. In addition, the air flow rate reported in Table 41 is the 90% value used in Reference 3.3 to develop the UA calculation. 10 The value reported is based on 203,700.00 (Reference 3.12) with Lighting values listed above subtracted. i.e., 203,700.00 - 11,601.53 - 7,541.00 - 28,321.39 = 156,236.08. Note that only explicitly defined lighting loads are subtracted. Refer to Assumption 3.5 for additional discussion.
Calc. No. WS129-CALC-001 r, CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 103 of 150 Table 41 Cooler Coils Credited in Model Room Coil Designation Cooler Cooling Air Flowrate Reference UA Water Flowrate (gpm) (cfm) (BTU/ hrF) R506 Fuel Pool HX Room RRA-CC-19, 20 17,140 21 9,000 3.3 R212 DC MCC Room Div. 1 RRA-CC-12 10,550 10 5,850 3.3 R411 MCC Room Div. I RRA-CC-1l 9,921 8 5,157 3.3 R516 Analyzer room IA RRA-CC-15 6,765 7 2,970 3.3 R512 Analyzer room lB RRA-CC-17 6,765 7 2,970 3.3 R611 Hydrogen Recombiner MCC RRA-CC-13 8,236 7 3,690 3.3 Room Div. 1 RI4 RHR Pump Room R-4 RRA-CC-I 9,321 15 4,687 3.3 R12 LPCS Pump Room R-5 RRA-CC-5 16,340 32 8,437 3.3 RI I HPCS Pump Room R-6 RRA-CC-4 36,510 30 14,062 3.3 Per assumption 1.3 the overall UA values listed above are reduced to 65% to account for fouling and then again by an additional 5% to account for changes in the UA value associated with changes in inlet air temperature. Per assumption 1.7, cooling water temperatures of 78°F and 870F will be used to develop the cooler heat removal values as a function of room temperature. These temperature values represents a simplification of cooling water temperature as illustrated in Figure 3. It can be seen that the use of a single value is clearly conservative for the first 14 hours of the analysis. Using this information and the method presented in Reference 3.4, the heat removal of each cooler as a function of air temperature is calculated. The MathCad software was used to establish the inputs and the method is illustrated below.
lCacc. No. WS129-CALC-001 ok CALCULATION CONTROL SHEET Rev. ENERCON SERVICES, INC. Page No. 104 of 150 To determine the heat removal rate of the fan coolers, it is assumed that the volume flow rate of the air past the coil is constant The mass flow rate, however, changes because the density of air varies with temperature. As a result, the heat capacity rate of the air will change with temperature. To account for this in the calculation of heat removal rate, the following function is defined. Al(T) = 0.24 BR (Pd. (T)AirFlow lbR AirFlow=1 0,OOOcfin T=780F A 1(78oF)=024BTU l0074 BT U,000cfn=177.6 IbR ~ft 3 m The heat capacity rate for the water is calculated in a similar manner. B1 = 5 0 0 hB(R(mIn) WaterFlow WaterFlow = 2 gpm B1 = 500 BU(min)(2 1gpm)= 1 0 5 0 0 BTU 50hr(R)(gal) ' hr(R) As described earlier, the overall UA value of the cooling coil will be reduced to address fouling and uncertainty in the constant temperature assumption. For the coil RRA-CC-l 9 UAl = 0.95(0.65)(17,140 BTU/hrf 2 ) = 10,584 BTU/hrf
CaFc. No. WS129-CALC-001
, CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 105 of 150 The MathCAD solve block is used to determine the heat removal. This method requires the initial guess values, which are defined below. The results of these calculations for each of the coils used are provide in Tables 42 and 43.
T= 100TF Y = 20 F XI = 50 0F Q = 50,000 Calculation of Heat Transferred based on Air T:= 100R Y, := 2Fahr X1 := 50Fahr Q := 50000BTU Inital Guesses hr Given =( I _ I XI = Y- + Tw yI e ( I1 Q= A1 (})-T - Xl-Al(T) HTR(T) :=Find(Y1 9XlQ) i:=0.. 16 Ti := 80Fahr + i 5Fahr Tw = 78Fahr [ y1)xi j=TR kQ 1J j
Cale. No. WS129-CALC-001 FI1 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 106 of 150 Pond Temperature 92 I _ 89
= 86 E- I
- a- - A/- -
a-laILaI L.6
&L83-E 80 77 1 10 j I_
100 1000 Time (hr) Figure 3 - Actual (Reference 3.6) and Assumed Pond Temperature vs. Time
Caic. No. WS129-CALC-01l F2, CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 107 of 150 The selection of a three volume model has a conservative impact on the performance of the fan coolers. These coolers are typically located within small compartments within the reactor building. Including these volumes within the main reactor building volume as opposed to providing their own volumes, produces an underestimate of the temperature these coolers will be worldng against Assuming that the volume temperature is represented by the main portions of the reactor building will lead to a lower initial temperature (approximately 75 0F) and produce overly conservative conditions in terms of the aforementioned room cooler performance. The reason that the performance is overly conservative results from the fact that the rooms where the heat sources and coolers are located would actually experience temperature increases that are greater than that reflected by the overall building temperature rise. This of course is the result of applying the heat inputs to a smaller volume as compared to the main portion of the reactor building. Further aggravating this situation is the assumption that the initial temperature of the area is significantly lower than that anticipated for the rooms, since the coolers would be removing heat from air that is greater than or equal to 104 0F. Therefore, the coolers are virtually ineffective with the lower temperature assumption. The arguments provided are applicable to the pump rooms. In the interest of producing a conservative representation of these coolers the 75F reactor building temperature is assigned to all three volumes included in the model.
Caic. No. WS129-CALC-001
. CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 108 of 150 Table 42 Cooling Water Temperature 78F Air Cooling Unit Heat Removal Temp (F) (BTU/hr)
FF# 2 FF#3 FF#4 FF# 7 jFF# 8 FF# 9 FF# 10 FF# 11 RRA-CC-1 RRA-CC-4 RRA-CC-5 RRA-CC- RRA-CC- RRA-CC-13 RRA-CC-15 RRA-CC-I_11 12 or17 L9 or20 0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 78 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 80 7440.00 14400.00 10300.00 7746.87 8050.52 6860.00 5980.00 10558.70 82 14900.00 28700.00 20600.00 15483.24 16089.70 13700.00 12000.00 21097.89 84 22300.00 43000.00 30900.00 23209.11 24117.54 20600.00 17900.00 31617.61 86 29700.00 57200.00 41100.00 30924.49 32134.05 27400.00 23900.00 42117.85 88 37100.00 71400.00 51300.00 38629.39 40139.26 34200.00 29800.00 52598.65 90 44500.00 85600.00 61600.00 46323.82 48133.15 41000.00 35800.00 63060.02 92 51900.00 99800.00 71800.00 54007.81 56115.77 47800.00 41700.00 73501.98 94 59300.00 114000.00 81900.00 61681.35 64087.10 54600.00 47700.00 83924.55 96 66600.00 128000.00 92100.00 69344.45 72047.17 61400.00 53600.00 94327.74 98 74000.00 142000.00 102000.00 76997.13 79995.97 68200.00 59500.00 104711.57 100 81400.00 156000.00 112000.00 84639.38 87933.53 75000.00 65500.00 115076.06 102 88700.00 170000.00 122000.00 92271.23 95859.85 81800.00 71400.00 125421.24 104 96000.00 184000.00 133000.00 99892.69 103774.95 88500.00 77300.00 135747.11 106 103000.00 198000.00 143000.00 107503.76 111678.84 95300.00 83200.00 146053.70 108 111000.00 212000.00 153000.00 115104.45 119571.52 102000.00 89100.00 156341.03 110 118000.00 225000.00 163000.00 122694.78 127453.01 109000.00 95000.00 166609.10 112 125000.00 239000.00 173000.00 130274.75 135323.32 116000.00 101000.00 176857.96 114 133000.00 253000.00 183000.00 137844.37 143182.47 122000.00 107000.00 187087.60 116 140000.00 267000.00 193000.00 145403.67 151030.45 129000.00 113000.00 197298.06 118 147000.00 280000.00 203000.00 152952.63 158867.29 136000.00 118000.00 207489.34 120 154000.00 294000.00 213000.00 160491.28 166692.99 142000.00 124000.00 217661.47 122 162000.00 308000.00 222000.00 168019.63 174507.57 149000.00 130000.00 227814.48 124 169000.00 321000.00 232000.00 175537.68 182311.03 156000.00 136000.00 237948.36 126 176000.00 335000.00 242000.00 183045.45 190103.39 162000.00 142000.00 248063.16 128 183000.00 348000.00 252000.00 190542.94 197884.66 169000.00 148000.00 258158.88 130 190000.00 362000.00 262000.00 198030.17 205654.85 176000.00 154000.00 268235.54 132 198000.00 375000.00 272000.00 205507.15 213413.98 182000.00 159000.00 278293.17 134 205000.00 388000.00 282000.00 212973.88 221162.04 189000.00 165000.00 288331.78 136 212000.00 402000.00 291000.00 220430.38 228899.06 196000.00 171000.00 298351.39 138 219000.00 415000.00 301000.00 227876.65 236625.04 202000.00 177000.00 308352.02 140 226000.00 428000.00 311000.00 235312.71 244340.00 209000.00 183000.00 318333.70 142 233000.00 442000.00 321000.00 242738.57 252043.94 215000.00 188000.00 328296.44 144 241000.00 455000.00 330000.00 250154.23 259736.88 222000.00 194000.00 338240.26 146 248000.00 468000.00 340000.00 257559.71 267418.83 229000.00 200000.00 348165.18 148 255000.00 481000.00 350000.00 264955.02 275089.81 235000.00 206000.00 358071.22
;i Caic. No. WS129-CALC-001 t -' CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 109 of 150 Air Cooling Unit Heat Removal Temp 1 ~~(BTUlr FF# 2 FF# 3 FF# 4 FF# 7 FF# 8 FF# 9 FF# 10 FF# 11 RRA-CC-1 RRA-CC-4 RRA-CC-5 RRA-CC- RRA-CC- RRA-CC-13 RRA-CC.15 RRA-CC-11 12 or 17 19 or 20 150 262000.00 494000.00 359000.00 272340.17 282749.81 242000.00 211000.00 367958.41 152 269000.00 507000.00 369000.00 279715.16 290398.86 248000.00 217000.00 377826.75 154 276000.00 520000.00 379000.00 287080.01 298036.96 255000.00 223000.00 387676.27 156 283000.00 533000.00 388000.00 294434.73 305664.12 261000.00 229000.00 397507.00 158 290000.00 546000.00 398000.00 301779.33 313280.36 268000.00 234000.00 407318.94
Caic. No. WS129-CALC-001 lA CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 110 of 150 Table 43 Cooling Water Temperature 87@F Air Cooling Unit Heat Removal Temp UF) (BTU_ _ _ FF# 28 FF# 29 FF# 30 FF# 32 FF# 33 FF# 34 FF# 35 FF# 36 RRA-CC-1 RRA-CC-4 RRA-CC-5 RRA-CC-11 RRA-CC-12 RRA-CC-13 RRA-CC-15 RRA-CC-19 I _or 17 or 20 0 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 87 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 89 7420.00 14300.00 10300.00 7723.26 8025.02 6840.00 5970.00 10514.87 91 14800.00 28500.00 20500.00 15436.04 16038.73 13700.00 11900.00 21010.29 93 22200.00 42700.00 30700.00 23138.36 24041.14 20500.00 17900.00 31486.27 95 29600.00 56900.00 40900.00 30830.21 32032.26 27300.00 23800.00 41942.85 97 37000.00 71000.00 51100.00 38511.63 40012.09 34100.00 29800.00 52380.02 99 44400.00 85100.00 61300.00 46182.59 47980.65 40900.00 35700.00 62797.85 101 51800.00 99200.00 71500.00 53843.15 55937.97 47700.00 41600.00 73196.30 103 59100.00 113000.00 81600.00 61493.29 63884.03 54500.00 47600.00 83575.41 105 66500.00 127000.00 91700.00 69133.01 71818.86 61300.00 53500.00 93935.21 107 73800.00 141000.00 102000.00 76762.34 79742.47 68000.00 59400.00 104275.70 109 81100.00 155000.00 112000.00 84381.29 87654.86 74800.00 65300.00 114596.91 1il 88400.00 169000.00 122000.00 91989.86 95556.05 81600.00 71200.00 124898.86 113 95700.00 183000.00 132000.00 99588.06 103446.04 88300.00 77100.00 135181.56 115 103000.00 197000.00 142000.00 107175.91 111324.86 95000.00 83000.00 145445.04 117 110000.00 210000.00 152000.00 114753.41 119192.51 102000.00 88900.00 155689.30 119 118000.00 224000.00 162000.00 122320.58 127049.00 108000.00 94700.00 165914.38 121 125000.00 238000.00 172000.00 129877.43 134894.34 115000.00 101000.00 176120.29 123 132000.00 251000.00 182000.00 137423.95 142728.55 122000.00 106000.00 186307.05 125 139000.00 265000.00 192000.00 144960.18 150551.63 129000.00 112000.00 196474.67 127 147000.00 279000.00 202000.00 152486.11 158363.60 135000.00 118000.00 206623.18 129 154000.00 292000.00 212000.00 160001.75 166164.47 142000.00 124000.00 216752.60 131 161000.00 306000.00 222000.00 167507.12 173954.25 149000.00 130000.00 226862.95 133 168000.00 319000.00 231000.00 175002.23 181732.94 155000.00 136000.00 236954.24 135 175000.00 333000.00 241000.00 182487.08 189500.57 162000.00 142000.00 247026.49 137 183000.00 346000.00 251000.00 189961.69 197257.14 169000.00 147000.00 257079.73 139 190000.00 360000.00 261000.00 197426.06 205002.66 175000.00 153000.00 267113.97 141 197000.00 373000.00 271000.00 204880.21 212737.15 182000.00 159000.00 277129.23 143 204000.00 386000.00 280000.00 212324.15 220460.62 188000.00 165000.00 287125.54 145 211000.00 399000.00 290000.00 219757.88 228173.07 195000.00 171000.00 297102.91 147 218000.00 413000.00 300000.00 227181.42 235874.52 202000.00 176000.00 307061.36 149 226000.00 426000.00 310000.00 234594.78 243564.97 208000.00 182000.00 317000.91 151 233000.00 439000.00 319000.00 241997.97 251244.45 215000.00 188000.00 326921.58 153 240000.00 452000.00 329000.00 249390.99 258912.96 221000.00 194000.00 336823.40 155 247000.00 465000.00 339000.00 256773.86 266570.51 228000.00 199000.00 346706.38 157 254000.00 478000.00 348000.00 264146.59 274217.12 235000.00 205000.00 356570.53
CaIc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 111 of 150 Air Cooling Unit Heat Removal Temp ___FF# 28 FF# 29 FF# 30 FF# 32 FF# 33 FF# 34 FF# 35 FF# 36 RRA-CC-1 RRA-CC-4 RRA-CC-5 RRA-CC-11 RRA-CC-12 RRA-CC-13 RRA-CC-15 RRA-CC-19 Ior 17 or 20 159 261000.00 491000.00 358000.00 271509.19 281852.79 241000.00 211000.00 366415.89 161 268000.00 504000.00 368000.00 278861.66 289477.54 248000.00 217000.00 376242.47 163 275000.00 517000.00 377000.00 286204.02 297091.37 254000.00 222000.00 386050.30 165 282000.00 530000.00 387000.00 293536.28 304694.31 261000.00 228000.00 395839.38 167 289000.00 543000.00 396000.00 300858.45 312286.35 267000.00 234000.00 405609.75
Caic. No. WS129-CALC-001 j_ CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 112 of 150 FUEL POOL HEAT EXCHANGER INPUTS The fiel pool heat exchanger will be explicitly modeled using the heat exchanger datasheet provided in Reference 3.5. The modeling approach is illustrated in Figure 4 where the GOTHIC heat exchanger component will be used to represent a single fule pool heat exchanger. Figure 4 - Fuel Pool Cooler Modeling Approach
P~^J ae, Calc. No. WS129CALCC001l F CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. PageNo. 113 of 150 The GOTHIC inputs are calculated as follows. GOTHIC Inputs Shell Side Velocity and Flow Area Heat Exchanger Specification information is obtained from Exchanger Specification Sheet attached to Calculation 5.35.18 (Reference 3.5) VSS:= 3.4-ft VTS:= 5.94 f- Atrv= 625ft 2 sec sec TubeOD:= 0.75in NumTubes := 94 TubePasses :=2 TFpin:= 125Fahr TFPout:= 11 IFahr TSWin - 95Fahr Tswout = 109Fahr E.
- =TFi +TFPout TSW(
TSWt TSWin + TSWout 2 ) Shell Side Mass Flow Rate and Flow Area MassFlowShell:= FPC i = 78.958Fr Fahr} sec GFpC Ass = 0.377ft2 (TFPia lb Gs: Far p Tube Thickness and Flow Area GSW ATS := - ATS = 0.216ft2 VTS TubeOD - funHD ATS NumTubes TubeWall'fhick 2 TubeWaIlThick = 0.051 in funHT ATS ) = 0.649in NumTubes
F- Calc. No. WS129-CALC-001 _ - __ CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 114 of 150 Tube Mass Flow Rate and Tube Length MaSSFlOWTubc G Fh- 79.503-s TSw = 95Fahr GS- TFab) Se TubeLength := finPerin(TubeOD)*TubePasses NumTubes Outer and Inner Surface Areas TubeOuterArea funPerim(TubeOD) *TubePasses *TubeLength -NumTubes TubeOuterArea = 625ft 2 TubelnnerArea := funPerin(TubelD)-TubePasses *TubeLength *NumTubes 2 TubeInnerArea = 540.493 ff fim{e TubeID + TubeOD 2 19 7 i fnerin( J2 .17i
*( TubeID + TubeOD )
TubeAvgArea := funPermr )-TubePasses -TubeLength -NumTubes 2 TubeAvgArea = 582.747 ft The service water temperature used to provide fuel pool cooling is developed in Reference 3.6, and simplified as per assumption 1.7.
CaFc. No. WS129-CALC-001 F4 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. PageNo. 115 of 150 SGTS FAN PERFORMANCE The fan component used to represent the SGTS is provided with the flow characteristics of the fan as required by assumption 1.6. SGTS Model Inputs The Standby Gas Treatment system will be modeled as a GOTHIC Volumetric Fan component with an inlet volume a discharge boundary condition and two flow paths (Figure 5). Elevtedan IletRB Volume Figure 5 - SGTS Model Figure 5 illustrates the basic modeling approach that will be used for the SGTS. The SGTS inlet will take suction from the reactor building volume through the inlet flow path, which connects the two volumes illustrated in Figure 5. This inlet flow path is developed to include the pressure drops associated with the SGTS filter, heater, etc. as listed in the table below. It should be noted that the flow value used to establish the pressure drop is different than what is assumed in the analysis. This will not impact the results since this information is used to establish a loss coefficient and the pressure drop will be calculated by the GOTHIC code.
Caic. No. WS129-CALC-01 x , CALCULATION CONTROL SHEET Rev. ENERCON SERVICES, INC. Page No. 116 of 150 Table 44 - SGTS Fan Suction Information Fan Suction Losses Pressure Drop Heat Input Flow Reference
.(inches WG) (kW) (ACFM)
Moisture Separators Loaded 2 4457 #1.9 para. 3.5.2 (pg. 15A-12) Two Electric Heating Coils 0.2 21 4457 #1.9 para. 3.5.4 (pg. 15A-14) Pre-Filters Cleanup loaded 1.0 4457 #1.9 para. 3.5.3 DP (pg. 15A-13) Two HEPA Filters loaded 4 4457 #1.9 para. 3.5.5 to 900grams dust (pg. 15A-17) Two Charcoal Absorber 6 4457 #1.9 para. 3.5.6 Filters (pg. 15A-19) Electric Strip Heaters 4457 1.9 Total DP 13.2 Total DP (psi) 0.488 _ Area Assumed 1.767 ft_ Velocity 42.039 ft/sec
Caic. No. WS129-CALC-001
,id-- CALCULATION CONTROL SHEET Rev. 1 ENERCON SERVICES, INC. Page No. 117 of 150 To ensure a conservative result, a total DP value of 13.5inwg will be assumed in this analysis. Using the pressure drop value of 13.5inwg, an equivalent pressure loss coefficient is developed for the assumed area.
The flow rate listed in Table 44 is less than that assumed in the analysis, but it provides the basis for the pressure drops. The flow information provided in the table is provided as Indicated CFM (ICFM). However, to add conservatism to the calculation of the pressure loss coefficient that follows, the flow rate is treated as if it is Actual CFM (ACFM). I 14 4 P= . 31psi Temp = 68 Fahr 3 R3 Flow:= 4457cfn vffsat (68Fshr).-= 0.016 lb lb 2 Area:= 1.767t 13.5inmg AP := ~ Velocity := - Area vfrsat(68Fahr).A-lb Velocity= 42.039 ft AP=0.488 psi sec P gas (PTemp, "air) = 0.074 lb ft3 2AP Kinlet:= Kinlet = 34.633 p g,,(PTemp, "air').velocity2
FzrTCahc. No. WS129-CALC-01 F CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 118 of 150 Therefore the inlet flow path will have a loss coefficient of 34.633 as calculated above with an area of 1.767ft2 . The hydraulic diameter associated with this area is l.5ft (18inch). The fan inlet volume is used only to allow for the inlet flow path described above. This allows for the accounting of the pressure drop between the SGTS inlet and the fan inlet. The fan is modeled as a volumetric fan component with the flow driven by a forcing function that is based on the fan performance curve provided in Reference 2.7 and reproduced below in Figure 6. SGTS Fan 20 15-.. CD~10 5 0 5000 10000 15000 20000 Flow (CFM)
-- *VIV 0%Closure - VIV 25% Closure Figure 6 - Fan Performance Curve Without Limit on Maximum Flow The fan performance curve is entered into the GOTHIC model as a forcing function of flow (ACFM) vs.
pressure (psid). The data read from the curve (Reference 2.7) is reproduced in the table below with the GOTHIC inputs provided in Table 46.
F ^Caic. No. WS129-CALC-001 E1~ ENRCN 3 S CALCULATION CONTROL SHEET Rev. 1 ENERC0N SERVICES, INC. Page No. 119 of 150 Table 45 ACFM VIV 0% CLOSED VIV 25% CLOSED VIV 25% CLOSED (in water gauge) (in water gauge) (psid) 0 16.25 16.25 0.6F 1 2000 16.75 16.625 0.599963912 I 3000 17.25 16.5 0.595452905 4000 17.375 16 0.577408878 5000 17.5 15.25 0.550342837 6000 17.25 13.875 0.500721761 7000 17 12.25 0.442078672 8000 16.5 10 0.360880549 9000 15.5 7.5 0.270660411 10000 14.75 4 0.144352219 11000 13.75 0 0 12000 12.625 13000 11.5 14000 10.25 15000 8.75 16000 7.375 17000 5.75 18000 4 20100- 0 _ 11 This value is artificially set to allow for input into the GOTHIC table which requires a consistent upward or downward trend in the data. If the data is used exactly as depicted on the fan curves the GOTHIC code would run into difficulties under conditions where a given pressure has two flows. Establishing the artificial value avoids this conflict and has minimum impact on the results.
Calc. No. WS129-CALC-001 C.;>ALCULATION CONTROL SHEET Rev. 1 ENERCON SERVICES, INC. Page No. 120 of 150 The fan flow assumed in the analysis is limited to 4800ACFM (Reference 3.13 and assumption 1.18). Table 46 - GOTHIC Inputs VIV 25% CLOSED ACFM I (psid) 0.61 0 0.6 2000 0.5955 3000 0.5774 4000 0.5503 4800 0.5007 4800 0.4421 4800 0.3609 4800 0.2707 4800 0.1444 4800 0 4800 The discharge side of the fan is represented by a junction, which extends from the fan outlet to the exit of the elevated release. Since there are four fans associated with the SGTS, the fan with the longest flow path is evaluated. This is fan SGT-FN-IB2 based upon a review of Reference 2.8. The data associated with the flow path is provided in Table 47. The flow coefficient calculations are provided after the table.
I Calc. No. WS129-CALC-001 F CALCULATION CONTROL SHEET Rev. I ENERCON SERVICES, INC. Page No. 121 of 150 Table 47 - SGTS Discharge Flow path Input Development Discharge Flow Path _ Description Width Depth Diameter HD Length Area Loss Coeff Corrected Elevation Reference Loss I1 (in) (in) (in) j(ft)_(f_) _ Coefficient (f L) Fan Discharge Connection 18.25 15.125 1.378433208 1 1.916884 0.0174 0.013 2.9 Flexible Connection 18 1.5 1 1.767146 _ 2.9 Vertical Run 18 1.5 3 1.767146 _ 2.9 90 degree Elbow _ 18 1.5 2.904579 1.767146 0.240 0.240 2.9 Horizontal Run 18 1.5 15.73958 1.767146 _ _2.8 Butter Fly Valve (SGT-V-5B2) 18 1.5 0.961538 1.767146 0.300 0.300 _2.8 90 degree Elbow 18 1.5 2.904579 1.767146 0.240 0.240 2.8 Horizontal Run 18 1.5 5.288462 1.767146 _ 2.8 Tee Connection 18 1.5 0 1.767146 1.100 1.100 2.8 Horizontal Run 18 1.5 8.173077 1.767146 __2.8 90 degree Elbow 18 1.5 2.904579 1.767146 0.240 0.240 2.8 Horizontal Run _ 18 1.5 14.91118 1.767146 _ _2.9 45 degree Elbow 18 1.5 1.380665 1.767146 0.192 0.192 _ 2.9 45 degree Elbow 18 1.5 1.380665 1.767146 0.192 0.192 2.9 Horizontal Run 18 1.5 7.179459 1.767146 _ 2.9 Discharge to Duct 18 1.5 0 1.767146 1.000 1.000 583.08333 2.9 Elevated Release Duct 20 20 1.666666667 23.79167 2.777778 - 606.875 2.9 Flow Past Tee 20 20 1.666666667 0 2.777778 - - 2.9 Discharge Into Elevated Release 20 20 1.666666667 1 2.777778 1.000 0.405 2.9 Elevated Release 45 120 5.454545455 64.29167 37.5 671.17 2.10 Discharge to Atmosphere 45 120 5.454545455 0 37.5 1.000 0.002 671.17 2.10
Calc. No. WS129-CALC-001 ENERCONSE CES, INC. CALCULATION CONTROL SHEET lRev. jPageNo. 122 of 150 Fan Discharge Connection Loss Coefficient This loss coefficient ia calculated using the meod ouldincd in Diagram 5-27 of£eference 1.8 (See Appendix 2). Pgas(P*T- fltiY)- ~ )-D ReNun(P,T,FL4D):= finDra .D p(75fahr) = 1.231x 1 lb 1.767fl2 ft se45.271in 176f 480iin)=45.271sc pg(l4.Ijsi,75Farair") =0.074-3 ReValuw:= ReNuni14.msi,725Fahr,4800ftf, I) 2 ReValue=4.095x 10S 3X:=0.3exp(-ReValuelOF ) 5)=4.999x 103 Fout :=funArea(lgin) Fin:= l8.25n 15.125n Fout 4-Fout
-- 0.922 Hmout:. - Hout =l.5ft Fin nclfin)
HDifr 4-Fin E Din+ HJout 2 (18.2Sinm+15.125in) 2 ckm := 0.002
Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 123 of 150 From Diagram 5-27 len:= I ft Hen = 0.695 HD From Diagram 2-1 (Reference 1.8) 1 X = 0.014 (1.8.log(Revalue) - 1.64)2 fc 18.25 inYf FoutC2 Asim= + 15.25iA Fin) Asim= 0.013 KFanDischarge:= Asim + SX KFanDischarge = 0.0153 The loss coefficients calculated with Reference 1.7 were found to bound those calculated based upon methods presented in Reference 1.8. Component Loss Coefficient Reference 45deg elbow 0.192 1.7 90deg elbow 0.24 1.7 Butterfly 0.3 1.7
jCalc.No. WS129-CALC-001 CALCULATION CONTROL SHEETRev. 0 ENERCON SERVICES, INC. Page No. 124 of 150 Flow through Tee Connections are calculated using methods provided in Reference 1.8 (Appendix 2). Tee Connection Values Reference Flow From Branch __1.8 A 0.55 Table 7-1 1.8 Qs/Qc,Fs/Fc 1 zeta'cs 2 Diagram 7.4 1.8 Loss Coefficient 1.1 Flow Past Tee in Stack _ 1.8 Qs/Qc I 0 _ _ _ _ zetac,st 0 Straight Passage I Several of the loss coefficients are calculated based upon the actual area of the section, such as the stack. Since these are all combined into one flow path, the loss coefficients must be adjusted to allow for a common assumed area for the flow path. This is accomplished by multiplying the result by the squared ratio of the assumed area to the actual area. Corrected Loss Coefficient is calculated as follows. Fan Discharge Connection (.0153 1.767146) = 0.013 1.916884 From the table 47 the flow path inputs are established to be Frictional Length = 157.81 ft - This value is the sum of the lengths provided in Table 47. Inertial Length =10ft - This value was established via evaluation of the models fan response time to plant data. To match the plant data, a value of lOft was required. Area = 1.767ft 2 - This value is arbitrarily selected to correspond with the duct runs listed in Table 47 The forward and Reverse Loss Coefficients are the sum of the corrected loss coefficients provided in Table 47 Forward Loss Coefficient 4 Reverse Loss Coefficient 4 The hydraulic diameter corresponds to that document for the assumed area. Hydraulic Diameter= 1.5ft
Y.' Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 1 ENERCON SERVICES, INC. Page No. 125 of 150 TOIE LINE The analysis is based on a time line assessment that is documented below. 0 seconds LOOP/LOCA 0 seconds Emergency Lighting On (Assumption 3.4) 15 seconds Normal HVAC Isolates (Assumption 1.5) 30 seconds All ECCS Pump Heat Loads Start (Reference 1.17) 120 seconds SGTS Fan Starts (Assumption 1.17) 300 seconds Fan Cooler Units Start, Fuel Pool Cooler Starts (Assumption 1.16) 12 hours Fuel Pool Cooling Starts, As selected by Energy Northwest (Assumption 1,13) I I
F._0.. .Caic. No. WS129-CALC-001 tg ;^: CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 126 of 150 CALCULATION SENSITIVITY AND SCOPING ANALYSES The final model developed started with the multinode model documented in Reference 3.2, which was used to access the building response using realistic conditions that did not include conservatism's associated with a licensing basis analysis. A review of that model led to the development of a simplified single volume model. This initial single volume model was developed using leakage flow paths at the roof and railroad door. These flow paths were developed using a turbulent flow model that assumed a 50/50 flow split between the paths given equal pressure drops. In addition, the model assumed very conservative temperature and wind speed conditions. The analysis results and model description can be found in Appendix 4, Section I. This initial single volume modeling effort demonstrated that the 50/50 split assumption is not achieved with actual pressure and temperature conditions. The pressure difference is not the same at the two leakage flow points. From this, the modeling development continued with the understanding that the flow split would be developed based on equal pressures at the leakage locations and the actual flows would be quite different. These early results indicated that the pressure criteria most difficult to satisfy are at the roof level for both the cold and warm exterior conditions. This is the result of the leeward side pressure effect producing a great challenge to the SGTS. The next set of single volume sensitivity studies documented in Section II of Appendix 4, entitled "Single Volume Model Sensitivity On SGTS Maximum Fan Flow", were performed to evaluate the impact of increasing the assumed SGTS flow rate. The additional change was to modify the discharge pressure assumed for the SGTS stack to eliminate the dynamic pressure of the wind. These analyses showed some improvement, but did not result in a successful return to below the desired minimum pressure condition. This set of results further revealed that the leakage flow model used in this analysis is overly conservative. The use of the turbulent flow model should be replaced with a better representation. Prior to the implementation of a more realistic leakage flow model, a number of studies were performed to access the significance of certain modeling features. The next set of studies eliminated the wind pressure effect as well as the internal heat sources. The analysis is documented in Section III of Appendix 4, entitled "Single Volume Model Sensitivity Study Elimination of Wind Pressure Effect All Internal Heat Sources Modified Leakage Moder'. The results of this study suggest that the modeling approach of using the windward side pressure as the source of inleakage at the roof level is overly conservative. A more reasonable approach is to credit the average pressure on all four sides of the upper building elevation. The final set of single volume analysis are documented in Section IV of Appendix 4, entitled "Single Volume Model Sensitivity Study Modified Leakage Model"
.- A.-I F- A Cale. No. WS 129-CALC-001 L CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 127 of 150 FINAL ANALYSES The model developed in the earlier portions of this calculation will be used to evaluate the drawdown effectiveness of the Columbia Station Standby Gas Treatment and Secondary Containment Systems. This analysis will include the short-term recovery of the building to below 0.25"WG as well as an assessment of the long-term ability to maintain the 0.25"WG criteria.
The analysis includes all heat loads within the Reactor Building that are pertinent for the LOOP LOCA assessment as documented previously. These loads impact both the short-term response as well as the long-term response. The loads that will impact the short-term response are primarily the electrical heat loads. With the exception of the decaying normal heat loads, all electrical loads will impact the long-term response as they continue to put energy into the building. There are loads that will be involved throughout the analysis, but will not begin to impact the building response until later in the analysis. These loads include decay heat in the fuel pool as well as heat transferred from the primary containment. These sources of energy are delayed by the heat storage capacity of the fuel pool and the primary containment walls, respectively. Coupled with the increase in temperature of the ultimate heat sink, these sources could potentially raise building pressure back above the 0.25"WG. Therefore, the analysis is run for a total analysis time of 30 days. As part of the analysis documented in the main body of this report, several sensitivity studies will be conducted. The first of these will be an assessment of the leakage flow split. Assumption 1.11 identifies that the basis of the model will be a 70% to 30% flow split between the roof and the railroad door, respectively. Based upon testing documented in Reference 1.20, this value provides a conservatively high representation for the railroad door leakage contribution and may underestimate the roof leakage. To evaluate the significance of this selection, a case using a 90% to 10% flow split between the roof and the railroad door, respectively, will be performed. This analysis will be conducted based on boundary conditions documented in Tables 4 & 5 and initial conditions documented in Tables 6 & 7. The flow split described in Assumption 1.11 is based on pressures across the roof and railroad bay doors being equal. Since weather conditions will alter the actual pressures across these leakage paths, it is necessary to evaluate the two extremes to fully demonstrate the impact of these conditions. Therefore, the boundary conditions identified in Table 4 and Table 5 will be evaluated with their corresponding initial conditions documented in Table 6 and Table 7.
Caic. No. WS129-CALC-001 F CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 128 of 150 INPUT AND ASSUMPTION EVALUATION STUDIES The input development has lead to a total of eight possible cases for initial evaluation. These address two bounding wind directions, outside temperature conditions, as well as flow split. These cases will be evaluated as part of the model development to establish the necessary inputs for long term analysis. A number of changes to the base deck (APPENDIX 6) are required to evaluate these different cases. Specifically, the initial conditions of the volumes are changed along with the boundary conditions and control variable inputs. All other GOTHIC Code inputs are unchanged for this effort. Each of these cases is run to evaluate the short term response, specifically the time to reach the 0.25inch water gauge acceptance value. The case that produces the longest response time will be used to establish the inputs to the final analysis. The GOTHIC file names and a description of the cases are provided in Table 48. The initial conditions of the volumes as well as the boundary condition values are provided in Table 49. Changes to the control variable inputs associated with leakage flow and pressure evaluation are provided in Table 50. Table 48 - Case Description and GOTHIC designation Case Deck Name Description I TNMFFI.GTH Warm Air with Easterly wind and 70/30 leakage flow split 2 TNMFFI SE.GTH Warm Air with South Easterly wind and 70/30 leakage flow split 3 TNMFFWI.GTH Cold Air with Easterly wind and 70/30 leakage flow split 4 TNMFFWISE.GTH Cold Air with South Easterly wind and 70/30 leakage flow split 5 TNMFF19.GTII Warm Air with Easterly wind and 90/10 leakage flow split 6 TNMFFW19.GTH Cold Air with Easterly wind and 90/10 leakage flow split 7 TNMFFISE9.GTH Warm Air with South Easterly wind and 90110 leakage flow split 8 TNMFFWISE9.GTH Cold Air with South Easterly wind and 90/10 leakage flow split
., Caoc. No. WS129-CALC-001 . CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 129 of 150 Table 49- Case Initial and Boundary Conditions Initial Conditions Boundary Conditions Case Pressure Pressure Pressure Pressure Temperature BC Roof BC Door BC Release Temp (1F)
Volume 1 Volume 2 Volume 4 Volume 5 (F) Pressure (psia) Pressure (psia) Pressure (psia) (psia) (psia) (psia) (psita) 1 14.63949 14.61125 14.67933 14.58122 75.00 14.57903 14.68433 14.58189 86.00 2 14.64134 14.61310 14.68120 14.58307 75.00 14.58052 14.68425 14.58189 86.00 3 14.62647 14.59822 14.66630 14.56820 75.00 14.56511 14.68294 14.56832 28.00 4 14.62817 14.59993 14.66801 14.56990 75.00 14.56678 14.68285 14.56832 28.00 5 14.63949 14.61125 14.67933 14.58122 75.00 14.57903 14.68433 14.58189 86.00 6 14.62647 14.59822 14.66630 14.56820 75.00 14.56511 14.68294 14.56832 28.00 7 14.64134 14.61310 14.68120 14.58307 75.00 14.58052 14.68425 14.58189 86.00 8 14.62817 14.59993 14.66801 14.56990 75.00 14.56678 14.68285 14.56832 28.00
F,..;.SS Calc. No. WS129-CALC-001
. CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 130 of 150 Table 50 - Case Control Variable Inputs Control Variable Inputs Case IP Top Door IC DP Low aO DP Low 1P Upper IC DP Upper aO DP Laminar Turbulent Laminar Turbulent Upper Door(A) Door (B) Roof (A) Roof (B) 1 14.66728 0.47230 14.68433 14.56526 0.286 14.57558 425.14 1275.43 1372.16 2785.91 2 14.66914 0.41870 14.68425 14.56711 0.277 14.57710 425.14 1275.43 1372.16 2785.91 3 14.65426 0.79474 14.68294 14.55223 0.250 14.56125 379.95 1139.86 1226.31 2489.79 4 14.65597 0.74491 14.68285 14.55394 0.250 14.56296 379.95 1139.86 1226.31 2489.79 5 14.66728 0.47230 14.68433 14.56526 0.286 14.57558 141.71 425.14 1764.21 3581.88 6 14.65426 0.79474 14.68294 14.55223 0.250 14.56125 126.65 379.95 1576.69 3201.16 7 14.66914 0.41870 14.68425 14.56711 0.277 14.57710 141.71 425.14 1764.21 3581.88 8 14.65597 0.74491 14.68285 14.55394 0.250 14.56296 126.65 379.95 1576.69 3201.16
- , Caic. No. WS129-CALC-001 F;5 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 131 of 150 The results of these short term studies are documented in Table 51. They show that for the 70/30 split, the wind from the easterly direction bounds the south easterly wind. In addition, the cold outside air conditions bound that of the warm outside conditions. This is contrary to that demonstrated in the early studies documented in Appendix 4 and 5, but the difference is associated with the leakage flow model, which has changed since that early analysis. For the 90/10 split, the easterly wind direction remains dominate over the south easterly and the outside temperature has a small affect on the time to reach 0.25inch water gauge.
These results demonstrates that the 70/30 split assumption (Assumption 1.11) is conservative and will be applied for the long term analysis. In addition, the cold air temperature value of 28 0F provided a bounding result for the assumed flow split when compared with the warm condition. This occurs because of the large calculated differential pressure required across the railroad door to ensure that the entire building remains below 0.25inch water gauge. Therefore, the cold air temperature will be assumed for the long term evaluations. The model used for the final analysis evaluations will be based on that documented as Case 3. Table 51 - Results of Short Term Analysis Case Description Time to Reach 0.25inch water (sec) 1 Warm Air with Easterly wind and 70/30 leakage flow split 743 2 Warm Air with South Easterly wind and 70/30 leakage flow split 720 3 Cold Air with Easterly wind and 70/30 leakage flow split 872 4 Cold Air with South Easterly wind and 70/30 leakage flow split 831 5 Warm Air with Easterly wind and 90/10 leakage flow split 680 6 Cold Air with Easterly wind and 90/10 leakage flow split 660 7 Warm Air with South Easterly wind and 90/10 leakage flow split 672 8 Cold Air with South Easterly wind and 90/10 leakage flow split 645
Calc. No. WS129-CALC-001 Sr;X CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 132 of 150 LONG TERM ANALYSIS AND MANUAL OPERATOR ACTION RESPONSE TIME EVALUATIONS As stated in Assumption 1.13, the fuel pool cooling will need to be started manually from the control room since the normal cooling will be lost. The response of the fuel pool will have an impact on the ability to maintain the 0.25inch water gauge pressure requirement. Delay in fuel pool cooling results in pool heat up and ultimately pool boiling. The heat up of the pool by the stored fuel will provide a source of heat and mass to the refueling floor volume (Volume 5). This will lead to a pressure increase of the building if cooling is not restarted. The long term analyses, which are used to demonstrate the ability to maintain the building depressurized will evaluate acceptable operator action times to ensure the building remains depressurized. The results of these studies as well as those associated with stored fuel temperatures and structural limits, which are beyond the scope of this analyses, should be used to establish any procedural operator action criteria. This analysis will define an upper and lower operator action time to be used in the sensitivities. The lower time is set to be 20 minutes. This value is selected to provide a time that exceeds the 10 minute operator action criteria that is in general acceptance in the industry for operator actions associated with manual start of safety systems. The upper limit will be based upon the time required to reach bulk boiling of the fuel pool. To represent this time a pool temperature of 212 0F is used in combination with the assumed pool initial temperature of 125TF. Given the previously defined pool volume and decay value, an estimate of the time can be calculated as follows using steam table information obtained from Reference 1.33. Cp(212F)p(212F)(VolumePoolX212F - 125F) A tim, =Az QDsvff, 0.9 9 8 BTU 59.814 lb (46788ft3 X212F - 125F) lbF ft3T ( 1lhr
- A 2720.56 B As-,
fl1ame = t%3600sec) sec Atime = 24.8hr Since this simple calculation does not include heat or mass transfer, the actual time should be longer. However, in the interest of providing margin to the bulk boiling condition, which will challenge the ability of the fuel pool cooling system, 24 hours will be selected.
. Calc. No. WS129-CALC-O01 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 133 of 150 Table 52 - Long Term Analysis Cases Case Deck Name Description Figure 9 TNMFFW1.GTH Cold Outside Air Easterly Wind Direction 7,8, 9 and 10 70/30 Leakage Split Fuel Pool Cooling Start Time 20 minutes 10 TNMFFW3hr.GTH Cold Outside Air Easterly Wind Direction 11, 12, 13 and 14 70/30 Leakage Split Fuel Pool Cooling Start Time 3 hours 11 TNMFFWl2hr.GTH Cold Outside Air Easterly Wind Direction 15, 16, 17 and 18 70/30 Leakage Split Fuel Pool Cooling Start Time 12 hours 12 TNMFFW24hr.GTH Cold Outside Air Easterly Wind Direction 19, 20, 21 and 22 70/30 Leakage Split Fuel Pool Cooling Start Time 24 hours Each of these long term cases were run for a total of 30 days. The results are depicted in Figures 7 through 22. The full set of graphical results for each of these cases is provided in Appendix 7. These figures illustrate the overall response of the building volumes and leakage flow path pressure difference. In each case the building pressure is restored and maintained below the 0.25inch water gauge.
Calc. No. WS129-CALC-001
.- IA CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 134 of 150 TNMFFWI Long Term Minimum DP Criteria Evaluation 1.sH1!1111i I 11ll Iil~
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Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 135 of 150 TNMFFW1 Vclurne Pressure Response 14.74 14.72 I11111!1 I i 101!1 11111 1111111 1 MainVolume PR1 I l l1i t1~~ ~~ lll
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Figure 8 - Volume Pressure Response Fuel Pool Cooling Start at Time = 20minutes
- hdfCalc. No. WS129-CALC-001 21 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 136 of 150 TNMFFW1 Reactor Building Temperatures
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Calc. No. WS129-CALC-001 E CALCULATION CONTROL SHEET Rev. 0 lENERCON SERVICES, INC. Page No. 137 of 150 TNMFFWI Flows Into and Out of Reactor Building II4 h IIIIIIillr!
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Figure 10 - Flow Into and Out of Building Fuel Pool Cooling Start at Time = 20minutes
ICaic. No. WS129-CALC-001 F CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 138 of 150 FuelPoolCool3hr Long Term Minimum DP Criteria Evaluation 1.25 MII PU11c1 I IIIN I )III i II~I II1111 l 0.75 III I III II IICoIn I Water11rnperat IIl I 3i n iI 11ii A Y iL11111I 1Inctea=e Iro- S i IiIII dIVIIIIIiii 11111l 111111111 I II111111
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Figure 11 - Minimum Pressure Differential Response Fuel Pool Cooling Start at Time = 3 hours
mm !; . Caic. No. WS129-CALC-001 F CALCULATION CONTROL SHIEET Rev. 0 ENERCON SERVICES, INC. Page No. 139 of 150 FuelPoolCool3hr Volume Pressure Response 14.74 111111 1 !!~~~~ilil 1 III 111F~1112 L RXillccr ,,P 14.72 anVlm R
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Fm ,,] Calc. No. WS129-CALC-001 w CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 140 of 150 FuelPoolCool3hr Reactor Building Temperatures t5 l-Main VodumeTV1 lll lFloloonstarts ll 14 _Pum p Roorn Volume TV4 I I I 1;~ I I I 11111 10_ - RbeW Floor Volume TV5 ___ ¢ 3 Rue P o Pool Cocft Starts xI3i I1IItw E
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Caic. No. WS129-CALC-001 k CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 141 of 150 FuelPoolCool3hr Flows Into and Out of Reactor Building S _ _ ______ _II! 111111 I_ lo7 1i1 2 1 11 I yl 11111 11 2 II H il IL 3v ,-LAKAGE' LOWER_ X
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Figure 14 Flow Into and Out of Building Fuel Pool Cooling Start at Time = 3 hours
. Calic. No. WS129-CALC-001 u CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 142 of 150 FuelPoolCooll2hr Long Term Minimum DP Criteria Evaluation 4 7C 1.z I 1IH111 1~ I1111 1IWilI I II MINNI PUP,1,v9 DP 1111 II Ii 1IMI I
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Caic. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 143 of 150 FuelPoolCooll2hr Volume Pressure Response 14.74
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Calc. No. WS129-CALC-001 x] CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVCES, IC. Page No. 144 of 150 FuelPoolCool12hr Reactor Building Temperatures 170 IIW i I i pMa R T V1 Volume I 1 !!!1111! 1I I PI 11i 9 l 160 - Pump Roam Volume TV4 1Reel Flor Vobzne TV . 10 R_u Pool I IS . I1 I I II I 1 140 C 130 120 M I I... 90 I 1Hill1 1,11 111glill~ 02!111 I I TI!! 1!!! I Io !1111!1 !i I11!! II III LIl ll l I0I+{l III!1 11 ! I 1111 I 1I 1 1111 1 I 11 I 10 100 1000 10000 100000 10000000 Time (sac) Figure 17 Volume Temperature Response Fuel Pool Cooling Start at Time = 12 hours
Calc. No. WS129-CALC-001 I D CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, IC. Page No. 145 of 150 I FueltPoolCooll2hr Flows Into and Out of Reactor Building 61III i j ! : lli . 1III 1I - I It Iii IMI 11 1111_ I_1 IIm LE6WAKAGE- LOWER FVi
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-- i Calc. No. WS129-CALC-001 ..1.. CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 146 of 150 FuelPoolCool24hr Long Term Minimum DP Criteria Evaluation 1.5 1.25 I I !M11i I -SMIN DP LOW cV7 1!1l Lll~
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Figure 19 Minimum Pressure Differential Response Fuel Pool Cooling Start at Time 24 hours
2A 3, Caic. No. WS129-CALC-001 J CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 147 of 150 FuelPoolCool24hr Volume Pressure Response 4.i 14
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Caic. No. WS129-CALC-001 Fritos a CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 148 of 150 FuelPoolCool24hr Reactor Building Temperatures 20_- Voume TVI Mbain 'ul l__lll IlilFUlookvodnst.rs l 2 -Pump Room Volume TV4 l._ ' 190 - Refuel Floo Volizre TV5 C 150I I 1 I 11 E 130 S: 170 10 100 1000 10000 1000000 10000000 1 Time ("c) Figure 21 Volume Temperature Response Fuel Pool Cooling Start at Time =24 hours
Calc. No. WS129-CALC-001 w- i CALCULATION CONTROL SHEET Rev 0 ENERCON SERVICES, INC. Page No. 149 of 150 FuelPooiCool24hr Flows Into and Out of Reactor Building a . U- 1 -. I II 1 1 I I 11 1I I IIH IIII i iiiiiii I t I IIt iI 4 I II10 I Ij I I - LEAAGELOWERV1 III 11 11 I I I IIIINETPPFV4 LEA HIM Y 2I
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{ Calc. No. WS129-CALC-001 CALCULATION CONTROL SHEET Rev. 0 ENERCON SERVICES, INC. Page No. 150 of 150 APPENDICES APPENDIX I- BOUNDARY AND INITIAL CONDITIONS APPENDIX 2- LOSS COEFFICIENT REFERENCE MATERIAL APPENDIX 3- WIND PRESSURE COEFFICIENT DEVELOPMENT APPENDIX 4- SINGLE VOLUME SENSITIVITY STUDIES APPENDIX 5- THREE VOLUME SENSITIVITY STUDIES APPENDIX 6- GOTHIC INPUTS BASE DECK APPENDIX 7- LONG TERM ANALYSIS GRAPHICAL RESULTS
C
'~' ENERGY ENR YG-1 Page No. Contd on page G-2Z NORTHWEST People-*_Vison ___________
APPENDIX G Calculation No. NE-02-01 -05 Prepared by / Date: nS Woo'f/' Verified by/Date: NIA Revision No. 0 REV BAR. The purpose of this appendix is to capture some sensitivity evaluations performed by the verifier as part of the review of this calculation model. At the time this review, the text portion of the calculation was not available, so all of the following discussion is in terms of the GOTHIC variable names and resulting graphs. The actual file that this evaluation started with was a "planned LBD case' from WS1 29-CALC-001 (Appendix E of this calculation) prior to the development of the "final LBD case" presented in Appendix D. Some results from this verification were used to determine the final LBD case. The acceptance criteria for a drawdown case are as follows:
- 1. The entire building is drawn down to -0.25"wg.
This can be determined by examining graph 9 'Close-up: Drawdown Time", which is a narrow sliver of graph 17, for the most limiting dP. The limiting dP is that experienced by cv9, and drawdown is reached when cv9 = 0.25 as long as it occurs before 1200 seconds. (TSR 3.6.4.1.4 Bases) NOTE: CV9 is control variable 9 in the table of control variables. CV7 and CV9 are the differential pressures experienced by the flow leakage paths, lower and upper respectively. A positive value of 0.25 represents the pressure differential of -0.25"wg because of the direction reversal.
- 2. The 30-day pressure response for the entire building remains drawn down to -0.25"wg.
This can be determined by examining graph 17 'Drawdown Time', for the same limiting dP cv9 remaining above 0.25 until 2.592e6 seconds. (TSR 3.6.4.1.5) The following sensitivity studies use the model for case 11 (planned LBD case) to perform the evaluation. The files are located in CENTRAL-STOR and also on the corporate LAN in [FUELS] /GOTHIC/MODELS; the file names are TxxFFWyyyy, where xx = % lower leakage and yyyy = service water start time, using 'mn" for minute and "hr" for hour. Evaluations include the following: Sensitivity studies
- 1. Determine the limiting "leakage split' between the sheet metal walls (upper leak path) and the rail bay doors (lower leak path), based on the impact to drawdown time. The fraction of the total leakage from the lower path was varied from 0.05 up to 0.5. Further evaluation in the range of 0.5 up to 1.0 was not warranted because the drawdown was no longer viable; i.e. either not possible within the proposed TS limiting time of 20 minutes (1200 s) or never achieved. The results table shows that the model is sensitive to this change, with leakage being the parameter with the largest impact on drawdown time. Results table can be found on page G-7. In general, the limiting leakage split is 45% lower / 55% upper, as determined by the fact that the 50%/50% case does not meet criterion 1 or 2.
MATHCAD and EXCEL spreadsheet pages were used to determine the parameters to enter into the control variables in order to change the leakage split. The pages are included for the record, and can be found on pages G-4 to G-27.
- 2. Evaluate the impact of the service water start time on the secondary containment drawdown time.
The LBD case is for a 12-hour start. Evaluations were performed for 5, 20 minutes, 1, 3, 6, 9, 12, and 24 hours. The results, shown on page G-28, indicate that any delay in service water start time of greater than 1 hour yields the same drawdown time. However, any cooling that is performed in the first hour has an adverse impact on drawdown time, actually increasing the time to drawdown. This result is still bounded by 20 minutes total drawdown time, but should be kept in ?.5%9Q1 RI
Page No. Cont'd on page ENERGYAPEDXGG2 G5 NORTHWEST APPENDIX G G-2 G-3 Pejple*V-sion10n 7 ns l Calculation No. NE-02-01-05 Prepared by / Date: CM, fMl Verified by/Date: N/A I Revision No. 0 REV BAR. mind, or evaluated more thoroughly, if this margin needs to be used in the future. Service water start time does not need to be considered.
- 3. Determine if modeling limitations are responsible for 100% humidity on 606' elevabon. It was found that more exact modeling of the flow paths between 606' and 572' elevation, in order to increase air circulation, did not have enough of an impact on the relative humidity to warrant a model change.
Refuel floor peak relative humidity Description filename Peak RH LBD case T30FFW12hr.GTH 100 Case w 606' paths T30FFW12hr+.GTH 100 The "+" was added to the filename indicate the additional modeled flow paths. It was possible that air circulation might lower relative humidity below 100%.
- Evaluate bounding EQ containment temperature profile LBD Case 11 uses the composite temperature profile for primary containment function from Profile la in TM-2019 [function page G-29], but the EQ program uses the bounding profile shown on the same graph [function page G-30]. Both of these options are more conservative than the profile currently in FSAR 6.2. This case evaluated the impact of using the higher PC temperature.
Bounding EQ Containment Temperature Profile _ Description filename Drawdown time LBD case T30FFW12hr.GTH 872 Case with limiting PC T30FFW12hrPC.GTH 873 profile The result shows that the model is insensitive to this change in containment profile and produced a negligible 1-second impact on the drawdown time of around 15 minutes.
Reference:
NE-02-03-10 GOTHIC code (V&V) All GOTHIC FILES, EXCEL SPREADSHEETS, & WORD text files can be examined in CENTRAL-STOR / DOCUMENTS / CALC / 2001 / NE-02-01-05 directory NE-02-01-05 rO AppG.doc WORD file; pages G-1 through G-3, G-28 NE-02-01-05 rO prep.xis EXCEL file; pages G-4 through G-27, G-29, G-30 GOTHIC v7.1 files: TxxFFWvvv, where xx = % lower leakage [05, 10, 20, 25, 30, 35, 40, 45, 50, 55, 60, 65, 75, 80, 85, 90, 95] and yyyy = service water start time, using Omn" for minute and 'hr" for hour [05mn, 20mn, 45mn, 01hr, 03hr, 06hr, 09hr, 12hr, 24hr] I Each GOTHIC run contains:
- design description *.DES
- graphics files *.GBK, *.GDT, *.GER, *.GIN
- backup file *.SAV
- solver files *.SD1, *.SDM, *.SER, *.SGR, *.SIN, *.SOT
.,r*Q,1 P1
ENERG S APage No. Contd on page NORTHWEST APPENDIX G G3 GL People *Vislon
- Solutions Calculation No. NE-02-01-05 Prepared by / Date: LS Woosley Verified by/Date: N/A Revision No. 0 REV BAR.
The following sensitivity studies use the final LBD case to perform the evaluation. The files are located in CENTRAL-STOR and also on the corporate LAN in [FUELS] IGOTHIC/MODELS; the file names are LBD CASExx, where xx = H (added SGT heater), no (no heaters). The file LBD case is the same as that used to generate Appendix D, but with a different name. Evaluations include the following: Impact of explicit modeling the SGT heaters Determine the impact of modeling the SGT heaters in the inlet volume rather than as part of the fan heat, in order to maximize the volumetric expansion. Compare to the impact of not modeling the SGT heaters at all in the model. I Explicit Modelina the SGT Heaters l Description filename Drawdown time LBD case - fan heat LBD case 882 Case with inlet heat LBD caseH 964 Case with no heat LBD caseno 881 The result shows that the model is sensitive to this change in inlet heat methodology. With the heater added to the SGT fan inlet volume (V2), the gas expansion takes place before the volumetric fan removes it, rather than heating as it is removed. This is validated by the -20F increase in train temperature observed by the system engineer. This is also validated by the reduction in humidity, which is the purpose for which the heaters were included in the design. If this effect is included in the LBD model, then the ICFM/ACFM conversion will need to be dropped
- Impact of shifting starting pressure Determine the impact of modeling the entire building at above atmospheric pressure at the start of the accident evaluation. This could be accomplished by shifting the pressure such that cv7=0 rather than cv9=0. However, then the rest of the building would be above atmospheric pressure at t=0, which is a condition not in compliance with Technical Specifications, and is therefore not required to be analyzed.
Evaluations that were NOT performed, with the reason for decision and disposition:
- EQ has requested in the past that secondary containment zones be assessed at an initial temperature of 124F rather than 104F, due to summer heat during plant operation as part of efforts to remove outage barriers. Current safety analyses are the short term and long term drawdown, supporting the TS JCO and the EQ program respectively; and the long term is used for the EQ equipment in the secondary containment. This is documenting the decision that a sensitivity case was not needed, and further evaluation was not necessary, because high building temperature above 104F is a condition beyond plant design.
- The GOTHIC model in NE-02-01-05 does not assume that any of the floor plugs are removed. PER 203-1229 dealt with barrier impairment issues regarding open floor plugs. The current drawdown model supporting the JCO NE-02-94-19 contains open floor plugs, and therefore any plant activity with the floor plugs removed was considered bounded by the safety analysis and required no further evaluation. It was decided that, for this calculation, the safety analysis would not credit the floor plug hatch because it is not the current plant design. The change management issues with our customers in the plant will have to be addressed in the PDC. The maintenance rule evaluations are required to perform the risk assessment, whether for the floor-plug-removed evolutions or not; maintenance personnel are not accustomed to performing the evaluation and will need training.
9)rQl RI
LS Woosley 'F4/,Py NE-02-01-05 rO APPENDIX G page G-4 NE-02-01-05 DRAWDOWN prep Flow path input INPUTS time (hr) time (sec) leakage flow rate 2430 cfm 100%/day density 0.075 ft3/lb assumed 0.333333 1200 pressure differential 0.25 in wg TS 1 3600 gc 32.2 ft Ibf/lbm s 3 10800 6 21600 conversions 9 32400 convert ft2 to in2 144 in2/ft2 CRC 10 36000 convert psi to in.H20 27.71 in/psi CRC 11 39600 convert min to sec 60 sec/min CRC 12 43200 24 86400 Sample Calculation 0.5 fraction of flow area velocity V= 33.4 ftlsec path flow 1215 cfm area A= 0.6063 ft2 hyd dia HD = 0.879 ft
LS Woosley NE-02-01-05 rO APPENDIX G page G-5 leakage split calculation for input to NE-02-01-05 drawdown calc flow path fraction lower = KK doors upper = roofline path 1 path 2 flow 1 flow 2 AREA 1 hyd dia I AREA 2 hyd dia 2 LOWER UPPER cfm cfm ff2 ft ff2 ft 0 1 0 2430 0 0.000 1.213 1.243 0.1 0.9 243 2187 0.121 0.393 1.091 1.179 0.2 0.8 486 1944 0.243 0.556 0.970 1.111 0.25 0.75 607.5 1822.5 0.303 0.621 0.909 1.076 0.3 0.7 729 1701 0.364 0.681 0.849 1.040 0.4 0.6 972 1458 0.485 0.786 0.728 0.962 0.5 0.5 1215 1215 0.606 0.879 0.606 0.879 0.6 0.4 1458 972 0.728 0.962 0.485 0.786 0.7 0.3 1701 729 0.849 1.040 0.364 0.681 0.75 0.25 1822.5 607.5 0.909 1.076 0.303 0.621 0.8 0.2 1944 486 0.970 1.111 0.243 0.556 0.9 0.1 2187 243 1.091 1.179 0.121 0.393 1 0 2430 0 1.213 1.243 0 0.000
LS Woosley ?// ' NE-02-01-05 rO APPENDIX G page G-6 leakage split calculation for input to NE-02-01-05 drawdown calc with 20min SW start TxxFFWyyyy cold air/east wind with this split flow nath fraction lower = KK doors upper = roofline results path I path 2 flow 1 flow 2 laminar turbulent laminar turbulent CASE DD TIME LOWER UPPER cfm cfm A2 door door A3 roof roof FILENAME sec from mathcad sheet from mathcad sheet o 1 0.0 2430.0 0.05 0.95 121.5 2308.5 277.7 69.4 208.3 5529.3 1824.7 3704.7 0.1 0.9 243.0 2187.0 555.4 138.9 416.6 5238.3 1728.6 3509.7 0.2 0.8 486.0 1944.0 1110.9 277.7 833.1 4656.3 1536.6 3119.7 0.25 0.75 607.5 1822.5 1388.6 347.1 1041.4 4365.3 1440.5 2924.7 0.3 0.7 729.0 1701.0 1666.3 416.6 1249.7 4074.3 1344.5 2729.7 0.35 0.65 850.5 1579.5 1944.0 486.0 1458.0 3783.2 1248.5 2534.8 T35FFW20mn 0.4 0.6 972.0 1458.0 2221.7 555.4 1666.3 3492.2 1152.4 2339.8 T40FFW20mn 1053 0.45 0.55 1093.5 1336.5 2499.4 624.9 1874.6 3201.2 1056.4 2144.8 T45FFW20mn noDD 0.5 0.5 1215.0 1215.0 2777.1 694.3 2082.9 2910.2 960.4 1949.8 T50FFW20mn noDD 0.6 0.4 1458.0 972.0 3332.6 833.1 2499.4 2328.1 768.3 1559.9 0.7 0.3 1701.0 729.0 3888.0 972.0 2916.0 1746.1 576.2 1169.9 0.75 0.25 1822.5 607.5 4165.7 1041.4 3124.3 1455.1 480.2 974.9 0.8 0.2 1944.0 486.0 4443.4 1110.9 3332.6 1164.1 384.1 779.9 0.9 0.1 2187.0 243.0 4998.9 1249.7 3749.1 582.0 192.1 390.0 0.95 0.05 2308.5 121.5 5276.6 1319.1 3957.4 291.0 96.0 195.0 1 0 2430.0 0.0 NE-02-01-05 rO Appendix G page G-6
LS Woosley NE-02-01-05 rO APPENDIX G page G-7 leakage split calculation for input to NE-02-01-05 drawdown calc with 12 hr SW start TxxFFWyyyy cold air/east wind with this split flow nath fraction lower = KK doors upper = roofline results path 1 path 2 flow 1 flow 2 laminar turbulent laminar turbulent CASE DD TIME LOWER UPPER cfm cfm A2 door door A3 roof roof FILENAME notes sec from mathcad sheet from mathcad sheet 0 1 0.0 2430.0 0.05 0.95 121.5 2308.5 277.7 69.4 208.3 5529.3 1824.7 3704.7 T05FFW12hr 618 0.1 0.9 243.0 2187.0 555.4 138.9 416.6 5238.3 1728.6 3509.7 T1OFFW12hr 660 657 0.2 0.8 486.0 1944.0 1110.9 277.7 833.1 4656.3 1536.6 3119.7 T20FFW12hr 750 0.25 0.75 607.5 1822.5 1388.6 347.1 1041.4 4365.3 1440.5 2924.7 T25FFW12hr 807 0.3 0.7 729.0 1701.0 1666.3 416.6 1249.7 4074.3 1344.5 2729.7 T30FFW12hr 872 872 0.35 0.65 850.5 1579.5 1944.0 486.0 1458.0 3783.2 1248.5 2534.8 T35FFW12hr 950 0.4 0.6 972.0 1458.0 2221.7 555.4 1666.3 3492.2 1152.4 2339.8 T40FFW12hr 1045 0.45 0.55 1093.5 1336.5 2499.4 624.9 1874.6 3201.2 1056.4 2144.8 T45FFW12hr 1167 0.5 0.5 1215.0 1215.0 2777.1 694.3 2082.9 2910.2 960.4 1949.8 T50FFW12hr no DC 0.6 0.4 1458.0 972.0 3332.6 833.1 2499.4 2328.1 768.3 1559.9 T60FFW12hr nevera iM 0.7 0.3 1701.0 729.0 3888.0 972.0 2916.0 1746.1 576.2 1169.9 T70FFW12hr never 0.75 0.25 1822.5 607.5 4165.7 1041.4 3124.3 1455.1 480.2 974.9 T75FFW12hr never 0.8 0.2 1944.0 486.0 4443.4 1110.9 3332.6 1164.1 384.1 779.9 T80FFW12hr never 0.9 0.1 2187.0 243.0 4998.9 1249.7 3749.1 582.0 192.1 390.0 T9OFFW12hr never 0.95 0.05 2308.5 121.5 5276.6 1319.1 3957.4 291.0 96.0 195.0 T95FFW12hr never 1 0 2430.0 0.0 LEAKAGE STUDY o 2500 a Ii V) 2000 _ 0
. 1500 3 1000 _ -- ' look for limiting leakage split 0
'O 500 .,limiting leakage w 20 min SW g.
2 0 0.2 0.4 0.6 0.8 1 I .2 flow path 1 fraction NE-02-01-05 rO Appendix G page G-7
LS Woosley , NE-02-01-05 rO APPENDIX G page G-8 COMPUTE LEAKAGE FLOWS FROM BUILDING from p. 46 of WS129-CALC-001 dP = 0.25 in wg CHECK path I path 2 leakage leakage leakage LOWER UPPER C A B LOWER C A B UPPER SUM 0 0 0.05 0.95 277.7 69.4 208.3 121.5 5529.3 1824.7 3704.7 2308.5 2430.0 0.1 0.9 555.4 138.9 416.6 243.0 5238.3 1728.6 3509.7 2187.0 2430.0 0.2 0.8 1110.9 277.7 833.1 486.0 4656.3 1536.6 3119.7 1944.0 2430.0 0.25 0.75 1388.6 347.1 1041.4 607.5 4365.3 1440.5 2924.7 1822.5 2430.0 0.3 0.7 1666.3 416.6 1249.7 729.0 4074.3 1344.5 2729.7 1701.0 2430.0 0.35 0.65 1944.0 486.0 1458.0 850.5 3783.2 1248.5 2534.8 1579.5 2430.0 0.4 0.6 2221.7 555.4 1666.3 972.0 3492.2 1152.4 2339.8 1458.0 2430.0 0.45 0.55 2499.4 624.9 1874.6 1093.5 3201.2 1056.4 2144.8 1336.5 2430.0 0.5 0.5 2777.1 694.3 2082.9 1215.0 2910.2 960.4 1949.8 1215.0 2430.0 0.6 0.4 3332.6 833.1 2499.4 1458.0 2328.1 768.3 1559.9 972.0 2430.0 0.7 0.3 3888.0 972.0 2916.0 1701.0 1746.1 576.2 1169.9 729.0 2430.0 0.75 0.25 4165.7 1041.4 3124.3 1822.5 1455.1 480.2 974.9 607.5 2430.0 0.8 0.2 4443.4 1110.9 3332.6 1944.0 1164.1 384.1 779.9 486.0 2430.0 0.9 0.1 4998.9 1249.7 3749.1 2187.0 582.0 192.1 390.0 243.0 2430.0 0.95 0.05 5276.6 1319.1 3957.4 2308.5 291.0 96.0 195.0 121.5 2430.0 1 0 00
LS Woosley "11450/y NE-02-01-05 rO APPENDIX G page G-9 ADD TEMPERATURE EFFECT TO LEAKAGE FLOWS (from page G-8) from page 47-8 of WS129-CALC-001 enter ratio to establish outdoor conditions density 1.020573 <86F dP = 0.25 in wg ratio = 0.912094 0.912094 <28F path I path 2 leakage leakage LOWER UPPER A B LOWER A B UPPER 0 0 0.05 0.95 63.32669 189.9801 110.8217 1664.282 3378.997 2105.569 0.1 0.9 126.6534 379.951 221.6388 1576.689 3201.155 1994.75 0.2 0.8 253.2976 759.902 443.2754 1401.501 2845.472 1773.111 0.25 0.75 316.6243 949.8821 554.0971 1313.907 2667.63 1662.292 0.3 0.7 379.951 1139.853 664.9142 1226.31 2489.788 1551.471 LBD case 0.35 0.65 443.2777 1329.833 775.7359 1138.719 2311.945 1440.652 0.4 0.6 506.6044 1519.813 886.5576 1051.125 2134.103 1329.833 0.45 0.55 569.9311 1709.784 997.3748 963.5315 1956.261 1219.013 0.5 0.5 633.2577 1899.764 1108.196 875.9377 1778.419 1108.194 0.6 0.4 759.902 2279.715 1329.833 700.75 1422.735 886.5551 0.7 0.3 886.5554 2659.666 1551.472 525.5632 1067.051 664.9165 0.75 0.25 949.8821 2849.646 1662.294 437.9693 889.2096 554.0971 0.8 0.2 1013.209 3039.617 1773.111 350.3754 711.3676 443.2777 0.9 0.1 1139.853 3419.568 1994.747 175.1877 355.6838 221.6388 0.95 0.05 1203.18 3609.548 2105.569 87.59386 177.8419 110.8194 1 0 control variable f-n cv15 cv14 cv12 cv11 al G al G 3 M G 1
-0
?* _(0 6eeI g,1?o teolus A
r169576 I
/
-- \ ;.\
Calculation of nputs For 90o10 Split E:- 100 1L,: 0.05 Lkwn.frRoof- 0.33 Ttuzift Raof- 0.67 Lcatr Dac. 0.25 Tmbulcu Door.- 0.75 GF)( Fs 24130 m[Lura~Rcaf L3 (25) + nliulm RoDK A3 ( 2? )] + a:.. F7id4A3)
.3- 291.018 LcnincRo1f13..25 + ThtulejRor.n3 (.25') - 121.5 LuingrRodfA3 - 96.036 Tbuftat.oFA3 - 194.982
,a:.. 100 Giv (1 - FS>2430 . [Linr DoertAR2(.25) + Tufbulet Door.A2(.25 )]
Ait: 74 1.g2) 2- 5276.57
. I .. -......
LcacDoor-A2..25 + Turbult Door. A2.(.25 ) 2.309 x-10 (I - FS}2430 - 2309 X 103 LcmwDoacrA2 - 1319.14 TnbuitEDaor-m - 3957.43 Tmsx - aFd1 .2-.7...03 n3- 291.018 rhursday, Jun 03, 2004 11:36 AM
6-il
- I J'
- . .
Calculation of Inputs For 90110 Split ML- 100 LcaWm Rof - 0 33 Tubmnbt Rof - 0.67
+
LcaminrDoor- 0.25 Tubulamt Dcar - 0.75 Gor ns-2430 - [LtniruRyDiA3.(Z5) Tubuinat n.aA3-(.25 05)] aL:- FLr4A3) A3 - 582.036 LcntwrRnctA3.25 + TmbukntRoo!A3 (.25 ) - 243 LantaicrRnaA3 - 192.072 TmbunitRoar3 - 389.964 A:;- 1 (i - Fs).2430 - [LUinai Doar_.-(.25)+Tutu*at Dor-A2(.25)]
- - FLA2)
AA -499826 (-----. - - - -_ . 7 _. ........... Latinar Dar-4.25 + Tmbullat.Doar-A2(.25 ) - 2.187x (I -FS).2430 - 2.187 IC 0 Lcnkwc_DocrAZ - 1249.71 TuzbulatDor*AU - 3749.14 I'm= - mFui A2 - 4.99 x 10 A3 -582f36 Thursday, Jun 03, 2004 11:31 AM
(-Iz
'qL. /2-Calculation of Inputs For 90/10 Split AL 100 LumicnmRoof- 0.33 Tuitlit Roof - 0.67 LentwcrDoor- 0.25 TmbuitDow7 - 0.75 GFn )(
Fs-2430 w 1Lmkzu_Rodcf A3-(.25) + TmubmtloRaof-A3 (.25 0)]
+
A V h4-A3) A3- 1164.072 Lcniucr-RnoM3-.25 + Tnulit Rnd-A3-(.25 ) - 486 LczutcRto A3- 384.144 TnultRnoofA3 - 779.928 AL, 100 (1 - Fs).2430. [Lc. uLDooz4 (.25) + TmbulatDor-At2.(.25 )] M:- FfnrA2) A2 -4443.43 LcdnsurDoorAA.. 2 + Turbunt Door.A2.25 ) - 1.944 I0. (I- FS).2430 - 1944.x0 LmktuDoorAA - 1110.86 Tuxlat.Doar-A - 333257 Tnx_ - iFdU
# - 4.443 x 103 A3- 1.164x103 Thursday, Jun 03, 2004 11:35 AM
6-!3
,' I nc,-
/I Cakulation of Imputs For 90/10 Split aL:- 100 RF- 0.25 LcnfrcRoof- 0.33 Twbukzt Roof.. 0.67 Lckr Docr- 0.25 TumultDoorm- 0.75
+
GFve) FS5 2430 a [LamrurRcf-A3 (.2.5) + Tmtub=_Raf. A3 (.25 0.)] fl.- ftd4M) A3- 1455.09 LamihRonofA3* .25 + TxbultRaof.A3.(.25 ) - 607.5 Lmdnr Roof-A3 - 480.18 TmtulntlRoofA3 - 97491 a&- 100 (I - FS).2430 - [LerwrDoer4-(.25) + TwbulDoor-.(.25 )] fl:- FmXnA) A2 - 4165.71 LcntarDocr.A2.25 + Tmbulct.Door-A2-(.25 )- 1.822 X 10 (I - FS)-2430 - 1.822 K10 Lnkwc Dorl - 1041.43 TtuletDo&r-A2 - 3124.29 Tmax - ih A2 - 4.166 x 10 A3 - 1.455 X10 Thursday, Jun 03, 2004 11:35AM
7o Cakulation of Iputs For 90110 Split Ai- 100 IL, 0. 3 LuenrRoof - 033 Tdwulaitjaf- 0.67 Lincar Do - 0.25 Tmtrbuknt Do _0.75 Divm FS.2430.a[Lk_ A3 (.25) + Abut Rcf A3 (5 )] + far- F4A3) A3 - 1746.108 LruznzrzRA3.25 + TmRaf-A3(.25- ) - 729 Latr.w.RoDf-A3 - 576.216 TuledofA3 - 1169.E92 I,,:- 100 Gov (i - FS) 2430 . [Lmr_Daor.A2.(.25) + nbulWDo.r.A2(25")] ea2- 3888 1.2 _ 388 LrrncDawrA2.25 + ftbuiat Doar.A2(.25 () - 1.701x 10 (1- Fs).2430 - 1.701 x 10 LkrDorA2 - 972 T21aDoo~ar2 - 2916 Tm - Fa 3.8883 A3 - 1.746 a 10 Thursday, Jun 03, 2004 11:35 AM
(-1< I. tc. - - -- Calculation of Inputs For 90190 Split A3 :_ D00 FS:- 035 Loziwc-Raf - 0.33 Twtulcnt-Rf-- 0.67 LctneubLoar- 0.25 TuxtulCsDoar - 0D.5
+
Fs72430. [L.urRoafn.3-(.25) + Twbulmt-Raof A3 (.2S )] 3:.- noWW) A3 - 2037.126 Lcmic RnoofA3-.25 + Tmbumet Df-A3.(.25 ) - 850.5 LcneiiRzof A3 - 672.251 TmbultRntfA3 - 1364.874 A2:- 100 Goi (I - FS)-2430 - [LimiLr DmcrA2t 25) + TmtbulatDow-A2(.25 0)] AZ:- Fmd(A2) n- - 3610.29 LcinhwDoarA2..25 + Trbulet.Do.r-A2.(.25 ) - 1579 . 10 (1 - Fs).2430 - 1.579 x 10 LenitaTDoa-A2 - 902.57 Tmbulmt.Do&-A2 - 2707.71
-A-3.61 x 3 A3 - 2.037 x 103 Monday, Jun 07, 2004 11:31 AM
6 j/ .-;a Calculalinn of Irputs For 90110 Split AL:- 100 0.4 Lcninr Rontcr 0.33 T1tuiztynct- 0.67 LmarupDowr- 05 TmbulntDowr - 0.75 Frs2430 [Lumxkin_Ryfo-M3 (.25) + T_ Rof-A3-(-25
+
A3- 2328.144 LenkrRotA3.J5 + Td~art octf.A3.(Q25 ) - 972 LcnincRrA3 - 768.287 ToRbuiettnfA3 - 1559.856 A,- 100 (i - Fs).2430 * [Lauin Dcar-A21(.25)+ Tzb~ulaDcar-.A2(.255)] M:- FmA2) A2 -333257 Lcans-DoarA2-.25 + TzbualaDoar-A2-(.25 ) - lASS x (1- Fs).2430 _ 1.458 x 10 LoarDcrA2 - 833.14 TubeuletDo&ar- - 2499.43 Tmax - F -3.333 x 10 A3 - 2.328 X10 Thursday, Jun 03, 2004 11:36AM
*5j*I ,/c~5Z Calculation of bqnuts For 90110 Split Fs:- 0.45 LwutwRoaf - 0.33 Tdbu1int.Roof- 0.67 Laming Doar- 0.25 Tmtukit Docr - 0.75 Fs-2430 m[L~min-Rf 3.(.25) + m lat!o-A.(2 . +
Al.- ml4A3) A3 - 2619.162 Lczkwg Roat.A3..25 + Tmt tRnaf-A3(.23 ) _ 1.093 .10 LemRa-ftf3 - 864323 Tuzbu]et-Rocf*A - 17542838 A~2:- 100 (I - FS).2430 m[Lani+/-~_Dcar.A2.(M2) ThdurztulerDoar.A2(.2505)l M.- 74CA2) A2 - 3054286
-------- --1--I.- -.I.---+-.--..-..- ----.- ..... ...- -------- ...... ......-
Lumtmr Doar.A2.25 + Tvdu1.zt..Dom~rA2.(.25Y') - 1.336 - 10 (1 - rs).2430 - 1.337 x Lammar.DcarA2 - 763.71 Twbu1at.Doer*A2 - 2291.14 Tmnx - IftA2 - 3.055 x10 3 A3 -2.619 mia Monday, Jun 07, 2004 11:30 AM
( f i /.J I: I
/ 'I ,I II
.6 So Calculation of Inputs For 90110 Split a3:- 100 FS :-0.
LcktrRo_-033 TmbetlRnaf - 0.67
'."+
LenkicDocr- 0.25 Twbulht Docr - 0.75 GM Fs-2430. [L. .onA3-(.25) + TMRf3-(25 )] RS :- FEWMA3) A3 - 2910.18 Lcms.RnfA3 25 + T~buint Rocm3-(25 ) _-. 215 X10 Laminar RafA3 - 960.359 TwbuutRoacfA3 - 1949.82 AZ:- 100 MUM (1 - rs>2430 m.[LimkrDoorfAl2I5) + Tburt Door.A2*( 25c)] M.:- F4A2)
- - 2777.14
. - .... - -.- ....... .+- . -. .. -.. - .- ..,.. A- - .. - - , . ..-..+ -- - - - - - ...__..
Lctmar Dor-A2..25 + TdbumlatDooar-Afl(.25) - 1.215 x103 (I - FS) 2430 - 1.215 X10 LcnrkDccw-A2 - 69429 TmbuVat.Daar-A2 - 2082.86 1M2x - ual nU- 2.777 x 103 A3 - 2.91 x 10 Thursday, Jun 03, 2004 08:44 AM
Calculation of Inputs For 90110 Split A3:- 100 Fs :- 0.55 LsinwRcfnd- 0.33 Twbulintnoa- 0.67 LekncauDor- 0.25 Tbu*atDor - 0.75 Fs.2430. [Lcnhi RoafA3(.25)+ TUbUlfltRDORflA(.25 0)] A3.- Fu4A3) A3- 3201.198 - + Lauwnc Rono3-.25+ TmwbuItRof-A3-(25 )_-1336 K le Lcnhur Rot A3 - 1056395 TubuletRniuA3 - 2144.802 A2:- 100 (1 - Fs)2430 a [LmkctDoar.A2-(25) TmtuntDcar-A2-(.25 )] A.L:- r An) A2-2499.43 LcnrW_DcarnA2-25 + Tukut Door-A2-(.259) -1.093 a 1O3 (1 - Fs) 2430 - 1.093 x le Liminr Do MAU - 624.86 - T buwIntDaw-A2 - 1874.57 ; TMsx - U 3 A2 - 2.49 x l A3 - 3.201a103 Monday, Jun 07, 2004 11:30 AM
Y'Qv 16 Calculation of Imputs For 90/10 Split A3:- 100 FS:- 0.6 LunnmtrRoof - 033 Tmbuhu=tRof -0.67 Lanksr-Dowr- 0.25 Tutukm Door - 0.75 FS. 2430 - [Lcmw.Roo A3.(.25) + Tulaflcof.A3 (.25'
+
A3 3492.216 LartneRnrtA3..25 + Turuint Ri xtA3(.25-) - 1.458 x 10 Ldnduc-Raf-A3 - 1152.431 TbumaigtRnaA3 - 2339.784 A2 :- 100 (1 - Fs).2430 a [Lamiuc Dour-M(.25) + Tuftlmt Doar.-(.250 )] A - Fi(A2) A2] 2221.71 Lcnhw DcaorA2..25 + Tufbalat Dor-A2.(.25') - 972 (i - FS).2430 - 972 LcnkwarDoc A2 - 555.43 Tmbu1at$Dor-r_- 1666.29 3 TMx - azFdw A2 - 2.222 x 10 A3 - 3.492 x 103 Thursday, Jun 03, 2004 08:44 AM
by?
&7' 'A Calculation of hputs For 90110 Split A3:- 100 rs .- 0.65 Lenrira Rofr- 0.33 TwbuktuRoo- 0.67 LcilncDoor- 0.25 TbuzltDoar- 0.73
+
Fs.2430d [Lumhcw..RooPn3-(.25) + Tmbulcityoof.A3.(.25 )] M.3:- Fi4KA3) A3 - 3783.234 LcnkiRcocf-fl.25 + TmbulictRnof.A3 (.25 )3-1579 x LctarRroA3 - 1248.467 TtuintRntA3 - 2534.766 An:- 100 Gow (1 - Fs)-2430 . [LinirjDocr-.(.25) + TubulatDacr.A2(.2505)] R.2:- Fbd4A2) A2- 1944 Lc2kur_Dacr.A2-.25 + Turbukt Dcor-A2-(.25 ) - 850.5 (i - FS)-2430 - 850.5 LctnairDocm1A2 - 486 Tuftlo&Doar-A2 - 1458 Tmax - I~u 1.2-1944X _ 10 A3 - 3.783 a 10 Monday, Jun 07, 2004 12:47 PM
Caulcation of Inputs For 90110 Split A3n 100 Fs:-0.7 Luwincynctf- 0.33 Ttxuk+/-nt-ia- an6 LmnkiirDagr- 0.25 TNtudat-Dawr - 0.75 Givni+ Fs. 2430 m [Lcnktryoctn A.(.25) + TW Raaof.,A3 .(2?5')] A3:-- FlrgA3) n3- 4074.251I1 LuminpcRctA3.25 + Turbukztyoo(.A3.(I.25) -1.70,1x LinnhicRo~a3 - 1344.503 vv'\ TmtuimtRoa!.A3 - 2729.749 A2:- 100 Dime (i - nSY2430 a [Luznir~Dowcn.C25) TuzbukztDaor.A2 .(5.25)] n- 1666.29 LumnikarDoc-AI.25 + Tmbulm-et or.A2.(.25 5) - 729 (i - FsI2430 -729 Lummc Door 12 - 416.57 ftbulat-Doorfl2 - 1249.71 Tnm mFda J.2-1.666 la3103 - 4f074 x103 Thursday, Jun 03, 2004 08:44 AM
Z 2/17s Culculation of bputs For 90110 Split FS :- 0.75 LcnmelRoof- 0 33 TuzRntlzcf.- 0.67 LamirDocr- 0.25 Tmbulal Dor - 0.75 Fs-2430 - [L.rrnot4ffAX .25) + A ut Rod(A3{.25D)]
+
3:-- Fb4MA3) n3 - 4365269 LmndnRof-d3-.25 + T ulaRof-A3(.25') - 1£22 X 0 LmrdRyofA3 - 1440.539 TmbuletRacflm - 2924.731 A2 :- 100 (i - Fs)-2430 . [L.uDoccrw-(.25) + Twdukttoar-.A 2(.25a .5)] A].- FiW2) A2-1388-57
... . .. 6075 LcnmrDowrA-.25 + Tuebi l-Doacr-A2(.25') - 607.5 (I - Fs)-2430 - 60O73 Lcinc._DooMr2 - 347.14 TbbulatDoor-A2 - 1041.43 Tc -X FE 9 A3 - 4365 103 Thursday, Jun 03, 2004 08:43 AM
Zo /?c Calculation of Iputs For 90110 Split A3:- 100 FS :- 0.8 LonqRoof- 033 TibulbktRof - 0.67 LcnturDoar- 0.25 TwbuatDoor - 0.75 + Gove FS. 2430 a [Lainc RyOf i3t(.25) + ra Ae3Rof.CA3(.25D )] 13:- Fb4d(A3) A3 - 4656.287 LurcicRoa.A3'.25 + Tubulet.Roof-A3(25 ) - 1944x-EIO LacituaRonfdA3 - 1536.575 Tmbult.RoeA3 - 3119.713 AZ:-100 (I - Fs).2430 a [LEUmlDoaAocZn(25) + Tnbu1toDaor-A2.(.25 )] A.:- nu(A2) A2- 111026 2 Lanhir DoarU-A. 5+ Thzbuktot.Dar-.A2(.25 ) - 486 (1 - Fs)-2430 - 486 LacnhiuDoorA2 - 277.71 TmtultDor-A2 - 833.14 Tm nx- s Fu . 1 3 A2 - 1.111 x 1 A3 - 4.656 x 103 Monday, Jun 07, 2004 07:40 AM
Calculation of Imputs For 90110 Split A3:- 100 FS :0.E5 LacinrRoof- 0.33 TuVbat Roef- 0.67 LnmrBDoar- 0.25 TbubltDear - 0.75 Gou FS2;430. [Lmiuur _Roat3 (.25) + T bub=-RaoafA3 (.25 .s)] + 3.:- Flad(A3) A3 - 4947305 Lctr RoafA3..25 + Ttbuk Roof.A3 (.25 ) - 2.065 x 10 LcnrirRof-A3 - 1632.611 TbulntRodfA3- 3314.695 AZ:- 100 Givo (1 - Fs).2430 a [LcnkrDotrsacrn.25) + TubuIatDoar.A2(.25")] A,:-,Fin(A2) AZ- 833.14 LcrnuDor-A2..25 + TuzbuatDor.A2.(.25) - 364.5 (i - FS).2430 - 364.5 Litiar oa1r.A2 - 208.29 TtuftlDoacr - 624.86
-A
- 833.143 A3 - 4.947 x 10 A4onday, Jun 07, 2004 12:48 PM
6-1r
/O/9o Calculation of Iquts For 90110 Split A3:- 100 s:- 0.9 LcnifjryaS- 0.33 TuituiatRoo- 0.67 Lamwr _Dcar- 0.25 Tuhbukt Dar- 0.75 GL) +
Fs-2430 a [Lcnkwc_Roaf A3-(.25) .Tu&WotRoafA3 t.25 ")] A:] F*_4A3) A3- 5238.323 Lmiwnaryaf3-.25 + TiRbat.Rof-A3-(.22 ) _ 2.187 x103 LaminacRoc A3 - 1728.647 Tumtnt Roo A3 - 3509.677 A2:- 100 Gou (I - Fs)-2430 a [Ltnar-Dor-A2].25) + TbualntDor.-P2-(.250 s)] A:-_ Fk4A9) P2 -555.43 LaminurDor.A2,.25 + TudbuMtp_Do-A2-(.2Y ) - 243 (1- FS)-2430 - 243 LmamurDocr.A2 - 138.86 Tbu~ltDoc-A2 - 416.57 Trx - I FdU A2- 555.429 3-3.238.10 Thursday. Jun 03, 2004 08:42 AM
3-.I-9 </ Calculation of Iputs For 90110 Split A3 :- 100 Fis:_ 095 Lmcrtoaf- 033 TumtuiatoRaf- 0.67 LcitrcDocr- 0.25 TmbultuDoor 0.75 + Givo Fs.2430. [Lmikw _Rcaft3-(.25) + tpnuolmRjcfA3-( 25 C)] 3:-
- _4£A3)
A3 - 5529.341 LkincRRofa3-.25 + Tu]fflt RnaVA3(25') - 230 x 103 LeniuRndA3 - 1824.683 TubulctRnaA3 - 3704.659 n:-_ 100 (i - Fs)>2430 * [LiamictDoaorA2.(25) + TbuwctDos AT-(.255)] A2.:- ftd4£) A2 - 277.71 Lcmikuc Dom2A.25 + TuumbictDocr.A2T( 25) - 121-5 (I - Fs)Y2430 - 121 5 LonjacrDoor-fl - 69.43 TufwtlbtDoa*AA - 208.29 TInax - I Fu AZ- 277.714 3 - 5.529. I10O Thursday, Jun 03, 2004 08:45 AM
LS Woosley 0 04K NE-02-01-05 rO APPENDIX G page G-28 SW start variation cold air/east wind with flow split flow path fraction results path 1 path 2 SW delay CASE DD TIME LOWER UPPER sec FILENAME notes sec 0.3 0.7 T30FFWyyyy 300 T30FFW05mn 5 min 881 1200 T30FFW20mn 20 min 872 43200 T30FFW12hr 12 hr 872 0.4 0.6 T40FFWyyyy 300 T40FFW05mn 5 min 1053 1200 T40FFW20mn 20 min 1053 2700 T40FFW45mn 45 min 1045 3600 T40FFW01 hr 1 hr 1045 10800 T40FFW03hr 3 hr 1045 21600 T40FFW06hr 6 hr 1045 32400 T40FFW09hr 9 hr 1045 43200 T40FFW12hr 12 hr 1045 86400 T40FFW24hr 24 hr 1045 Service Water start variation 1200 X ; 0 . ; D .,, - . . . .. -S; .
< > - > a' t- X: -_' 'd 1000 -
4 f . . r ,: . , ,;<- x, s -, = i 4S,
' _, 'St ' s ' '- ') xf 'i'- X - - 0nd - z 0; w l w > X s _ ,, e s _ ; ; Z z _ + _ j 0 _ _ i . . >., > j ,. k _
z _: . ' :,' -'! , . , , \- ' ' r , . * - ' 7 0 800 7 : - ) . ' . _ l',; ' ' ' ; * ? -; E 0 =" > w0 . . ' ... - f.,' -....:. -' i" . , -. ;, ' , '. ' 0 600
, ' ' ,' ": > 0 - ;' '- -, .,-'- ;': : 3
' , .:: ,. - ', , ". . i' ' E ' ' ' N "
- f ' - - ' X, ' '- ' ' . '
'0 400
- ; -- [ + 40% lower / 60% upper l
- - - t 30% lower / 70% upper l 200 -
f 0t:
.=.
D. e i f- y
.: . t-. f-: :. - - .
.. : - .: -: ^ -: :
0 i E r 0 20000 40000 60000 80000 10000 0 start time
Cold Air with Easterly wind and 70/30 leakage flow split 6C 7 1 Jun/0912004 12:12:45 GOTHIC Verslon 7.1(QA) - January 2003 File: G:\GOTHIC\MODELS\TNMFFW12hr+ Function 14 PC Temperature 0 0 0.2 0.4 0.6 0.8 1 Ind Var. Xle6
Cold Air with Easterly wind and 70/30 leakage flow split Jun/09/2004 12:56:25 GOTHIC Version 7.1 QA) - January 2003 File: G:\GOTHIC\MODELS\TNMFFW12hr_PC Function 14 PC Temperature 0 0 20 40 60 80 100 fifinge La4I X1 e3}}