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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program ML20084N3541995-03-24024 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20137B5371995-03-22022 March 1995 Rev 11 to 6610-PLN-4200.01, Odcm ML20081C1281995-03-0808 March 1995 Svc Water Sys Operational Performance Insp Self-Assessment Plan ML20073F9411994-09-26026 September 1994 Revised Plan for Long Range Planning Program for TMI Nuclear Station Unit 1 ML20059M2301993-11-12012 November 1993 Rev 7 to 6610-PLN-4200.01, Odcm ML20057B3781993-09-0202 September 1993 Rev 6 of Solid Waste Staging Facility Sys Description ML20127A2181992-10-15015 October 1992 Rev 1 to 6615-PLN-4520.01, REMP - Plan ML20127A2301992-08-11011 August 1992 Rev 30 to Emergency Procedure 1202-32, Flood ML20090D4031991-10-0404 October 1991 Rev 16 to Waste Solidification Process Control Program ML20082M2991991-08-29029 August 1991 Rev 8 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20127A1511991-07-0808 July 1991 Rev 4 to 1000-PLN-4010.01, Gpu Nuclear Corp Radiation Protection Plan ML20082M2951991-06-27027 June 1991 Rev 14 to Operating Procedure 1104-28I, Waste Sodification Process Control Program ML20198B9741991-06-17017 June 1991 Rev 2 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070L3331991-03-15015 March 1991 Rev 1 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20070U9241991-03-0404 March 1991 Rev 0 to 6610-PLN-4200.01, Odcm ML20059H9031990-09-0707 September 1990 Rev 0 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20059C7931990-08-23023 August 1990 Rev 5 to Sys Description 3184-007, Solid Waste Staging Facility ML19351A4371989-11-30030 November 1989 Rev 9 to 9110.PLN-4200.02, Emergency Dose Calculation Manual. ML20248D4071989-09-27027 September 1989 Rev 8 to 9100-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20245K1211989-08-0202 August 1989 Rev 4 to SD 3184-007, Div Sys Description for Solid Waste Staging Facility ML20244C2961989-06-30030 June 1989 Rev 1 to Sys Description SD 3510-013, Div Sys Description for Reactor Bldg Sump Recirculation Sys ML20246M7931989-03-0909 March 1989 Rev 11 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154C7191988-06-0303 June 1988 Rev 10 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20154Q6771988-05-27027 May 1988 Recovery Operations Plan ML20236M1621987-11-0909 November 1987 Radiological Environ Monitoring Program for TMI-1 ML20236M4281987-10-19019 October 1987 Vols 1 & 2 of 1987 TMI Annual Exercise Scenario ML20147F9331987-08-25025 August 1987 Rev 3 to Procedure 1000-ADM-1291.01, Procedure for Nuclear Safety & Environ Impact Review & Approval of Documents ML20238C6391987-08-21021 August 1987 Rev 2 to Design Criteria 3255-86-0004, TMI-2 Design Criteria for Pressurizer Defueling Sys. W/One Oversize Figure ML20236K9601987-07-24024 July 1987 Rev 3 to 3184-007, Solid Waste Staging Facility Sys Description ML20215M3261987-06-19019 June 1987 Rev 16 to Organization Plan ML20215H0301987-06-15015 June 1987 Revised Emergency Plan Implementing Procedures,Including Rev 2 to 6415-IMP-1300.06. Addl Assistance & Notification & Rev 1 to 6415-IMP-1300.16, Contaminated Injuries. Updated Table of Contents Encl ML20215M1291987-03-20020 March 1987 Corrected NCRP Commentary 4, Guidelines for Release of Waste - Water from Nuclear Facilities W/Special Ref to Public Health Significance of Proposed Release of Treated Waste Waters at Tmi ML20214S4481986-12-31031 December 1986 TMI-2 Cleanup Program,Post-Defueling Monitoring Storage ML20212N6711986-12-17017 December 1986 Rev 2 to Test Procedure SC-1302-323 Isolator - Fault Testing. Test Results Encl ML20212H7821986-10-10010 October 1986 Rev 7 to Operating Procedure 1104-28I, Waste Solidification Process Control Program ML20206U7611986-09-26026 September 1986 Rev 1 to SD 3520-010, Div Sys Description for Processed Water Storage & Recycled Sys ML20205E7891986-08-0707 August 1986 Rev 0-03 to Corporate Procedure 1000-ADM-1291.01, Safety Review & Approval Procedure ML20211Q8251986-06-0202 June 1986 Rev 4 to SDD-TI-614, Div I Sys Design Description for TMI-1 Remote Shutdown Sys ML20203N1761986-04-29029 April 1986 Rev 4 to Div Sys Description for Auxiliary Bldg Emergency Liquid Cleanup Sys (Epicor II) 1999-08-12
[Table view] |
Text
.. .,
PROPOSED OUTLINE FOR TEST OF COOLING COIL , ,
PERFORMANCE AT ELEVATED TEMPREATUPIS AND PRESSURES
' - - - + - - _ . . _
1415 166 7910100 8 0 7 0
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PROPOSED OU'ILINE FOR TEST OF COOLING COIL PERFOR".ANCE AT ELEVATED TD:PERATURES AND PRESSURES.
Prepared by CAG ENGINEERING DEPARL1ENT -
AMERICAN AIR FILTER CO., INC.
LOUISVILLE, KENTUCKY _
Prepared for METROPOLITAN EDISON C0::PANY READING, PENNSYLVANIA
'Jork Accomplished under:
PURCllASE ORDER 93342 SUBMITTED FOR CUSTOMER APPROVAL 16 Decembdr 196S 1415 167
PO 1 uhid u w RS 1044
- 1. Materials of Construe:, ion - identical, 5/8 inch 0.D.
Copper tubc, heavy wall - 0.049 inch, 0.007 inch copper fins spaced 6 per inch, copper headers with schedule 80 rteci connections (Test coil uses screwed connections, Full Coil uses ASA flanged connections), cicanabic fit-tings with high temperature 0-rings.
During tests, results will be considered valid if performance as given by water side data agrecs with perform..nce as given by gas mixture side data. Sufficient test data vill be generated to demonstrate reproducibility.
III. DESCRIPTION OF APPARATUS The apparatus used to test this coil has been previously used to test cooling coil performance and can generally be considered to consist of three systems which are the pressurc vessel, the test section, and allied instrumentation. A brief description of these systems is given below.
- 1. Pressure vessel and Mixture Circulation System. The steam-air mixture will be circulated through a closed loop system by means of a centrifugal blower. (See Figure 1.) On 1 caving the blower the mixture is completely contained in the duet system of the test section and is expelled from this duct af ter leaving the coil. This test section, discussed later, is completely sur-rounded by the 42 inch I.D. insulated shc11 capabic of with-standing the required pressure. The section containing the cooler is slightly larger to accommodate the coil manifold and accompanying piping. After leaving the cooler the mixture enters a transition section and is recirculated back to the fan inlet through the 12 inch I.D. duct provided for this purpose. A large blank-off plate is attached to the fan outlet to prevent the mix-ture's returning directly to the blower and not being returned through the recirculate duct.
In order to insure proper mixing, the steam and air are injected upstream of the blover. Compressed ai r is provided by the normal
" plant" air system and the steam is produced by a large (600 bhp) boiler. The mi:.ture flow is controlled by means of a damper on the Ian inict.
- 2. Containment Cooler Test Section and Water Sunply System. The test section wi;l consist of the cooler and all of its attached duct system of the sizes indicated in Figure 1. The cooler will be a 24 x 24 inch section idcutical in construction to the " full size" unit as shown on AAF Drawing No. MC Thermocouples will be placed in these ducts before and after the cooler to indicate the inlet and out1ct, wet and dry bulb tempera-ture. A rnoisture separator pad, of glass matte construction, vill be installed to remove any entrained water droplets present.
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P00R O H M *m Thermoccuples will also be placed in the water manifold as close to the coil as is practical to give an accurate indication of the et mer ' s performante and minimize any water temperat rc men-suremerit crror.
Because of heat balance inaccuracies encountered in previously run tests, a sheet metal housing will be installed over cach end of the coil having the return bends. This will be donc to prc-vent an unmeasurable heat gain by conduction to these parts due to their presence in the hot atmosphere.
Cooling water will be supplied to the coil from a large tank by means of a centrifugal pump. The supply will be arranged to pro-vide water flow through the coil counterflow to the mixture flow.
Valves will be provided to regulate the flow and on-line water flow measurement will be used to indicate quantity. The cooler inlet temperature uill be maintained through the addition of colc water to the supply. Any excess will overflow into the drain line.
The condensate will be collected in the sump where the temperature will be measured. The flow will be nicasured by a tapered tube flow meter as it is drained from the system. It will be returned to the boiler feed water system.
- 3. Containment Conler Instrumentation. The mixture flow will be mca-sured utilizing the sharp-edged orifice method. The resulting pressure drop will be indicated with a U-tube manometer. The sys-tem pressure will be measured by an " instrument" quality Bourden gage. The absolute pressure is then determined by addir.g this pres-sure to the barometric pressure measured in the same area by means of a mercury column barometer. The w.et and dry bulb temperatures will be measured by means of thermocouples. The wet bulb thermo-couple will be covered with a cotton wick aad supplied with water from time to time. All temperatures will be indicated and recorded utilizing a 24 point Esterline-Angus recorder.
A stop watch will be utilized to assure accurate time measurements when setting and monitoring the coolant flow rate. The coolant circulation measurement loop consists of a collection tank and suitable valving. The water can be diverted to a scales where weight rate of flow is determined without disturbing system opera-tion. The flow will be adjusted by means of' a ' control valve on the downstream side of the cooler.
IV. EXPERIMENTAL PROCEDURE The following procedure will be used to determine the heat transfer characteristics of the contvinment cooling c, oil.
- 1. The air circulation and water supply system will be started.
The steam and air rates will be adjusted, as necessary, to pro-duce the desired condition of temperature, pressure and humidity.
1415 170
P00ROMlE D w
- 2. The blowcr damper will be adjusted to give the proper mixturc flou
- 3. The cooling water flow rate and temperature will be adjustcd to give the required conditions.
- 4. Steps 1, 2 and 3 will be repeated as necessary until stabili:cd conditions are reached.
- 5. Data vill be recorded utilizing all instrumentation to determine the required temperature, pressure and humidity of the :ixture at the inlet and outlet. Tne temperature and flow rate of the cooling water w ill be verified. The condensate temperature and flow rate will be recorded.
- 6. The coil performance can then be determined knowing the cooling water flow rate and its temperature difference. The heat gained by the water system can then be verified by computing the heat lost by the mixture.
A successful test run shall be defined as operation at steady state conditions for a period of fifteen (15) minutes or more. Temperatures, pressures, pressure drops, and flow rates must have reached these steady state icvels and damped out excessive oscillations (The con-trol adjustments normally will allow small oscillations while not per-mitting larger variances). Steady state operation is evidence of the fact that condensate is not building up on the heat transfer surfaces.
Any degree of such build-up would rapidly change temperatures and pres-sure drops due to the very high condensation rates in this type service.
Innsmuch as there are many pieces of data to be observed, as well as a likelihood that any one test run will not be successful in achieving a heat balance (described hereafter), it is impossible to prepublish a rigid test schedule.
During a nominal period of stay of test witnesses (two or three dyas) there will be ample opportunity to evaluate the test procedure, ob-s,erve data being recorded, and gain a working knowledge of the test equipment. For witnesses to stay through the entire testing portion of the program, will require residency for a much longer period in the event of unplanned shutdowns and rework.
V. CALCULATION PROCEDURE Upon completion of a test run in which data appears to be sound (as previously defined), a trial heat balance will be made using the rater side (or coolant) data against the air side (or mixturc) data. If the heat transfer balance is made uithin reasonabic accuracy, the strip chart and all other recorded data sh:11 be appropriately r.arhed uith a test identification number for later reference. (Test data for runs which do not balance will not be so coded).
1415 171
/h51 RS 107.4 Density and mixture flow rate calculatio:u, for the trial hcat balcncc will be carried out in the usual manner, i.e. based on partial pres-sure laws. Eqt" tion (1) definds the density calculation.
PM +PM s s a a (1) p = 10.73(T + 459.7) where p = density, lbs/cu.ft.
P = partial pressure of air, psia I M = molecular weight of air (28.97) 'el ab P,= partial pressure of steam, psia M,= molecular weight of steam (18.)
T = temperature, F Equation (2) defines the volume flow rate calculations at conditions.
CFM = 1096.5 C A (
do i where CFM = volume flow rate, cubic feet per minute C
d
= rifice constants, dimensionless (determined through I calibration in place)
A = orifice flow area, square feet OPD = orifice pressure drop, inches water gage p = density, lbs/cu.ft.
The experimentally determined performance characteristics of the test coil,once established, will be compared with computer generated test coil performance characteristics. In this manner a direct relation-ship will be shown betscen computed results and those that have been measured experimentally. This comparison is made for each of the run conditions and is assumed to remain uniform regardless of coil size.
(Past test programs on similar coil configurations bear this out.)
In the case of the present test, the computer solution for the full sized (45 inct long) coils involves only accounting for the different length. Applying the ' comp'arison factor' to computer generated full scale coil data will demonstrate expected performance of the full sized coil bank in service.
1415 172
.