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Category:PRELIMINARY SAFETY ANALYSIS REPORT & AMENDMENTS (PSAR
MONTHYEARML19329E8001977-12-16016 December 1977 Revision to App 1B to Psar.Constitutes Amend 36 to CP & OL Application ML20008D7691974-07-24024 July 1974 Chapter 5 to Midland 1 & 2 PSAR, Use of Coarse Aggregate W/Varied Percentage of Matl Passing Sieve 200. Prepared for Util ML19319C2511969-08-0101 August 1969 Suppl 1 to Davis-Besse PSAR, Formal Questions from Div of Reactor Licensing & Applicants' Responses;Informal Questions from Div of Reactor Licensing & Applicants' Responses; & Discussion of Items in ACRS 700820 Ltr. ML20008D7551969-01-13013 January 1969 App 1A to Midland 1 & 2 PSAR, Glossary of Terms. Includes Revisions 1-36 ML20008D7661969-01-13013 January 1969 Chapter 4 to Midland 1 & 2 PSAR, Rcs. Includes Revisions 1-36 ML20008D7651969-01-13013 January 1969 App 3A to Midland 1 & 2 PSAR, Modal Analysis of Xenon- Induced Oscillations. Includes Revisions 1-36 ML20008D7641969-01-13013 January 1969 Chapter 3 to Midland 1 & 2 PSAR, Reactor. Includes Revisions 1-36 ML20008D7631969-01-13013 January 1969 App 2B to Midland 1 & 2 PSAR, Surface Water Hydrology. Includes Revisions 1-36 ML20008D7621969-01-13013 January 1969 App 2A to Midland 1 & 2 PSAR, Environ Study Meteorology. Includes Revisions 1-36 ML20008D7611969-01-13013 January 1969 Chapter 2 to Midland 1 & 2 PSAR, Site & Environ. Includes Revisions 1-36 ML20008D7601969-01-13013 January 1969 App 1C to Midland 1 & 2 PSAR, Principal Design Criteria. Includes Revisions 1-36 ML20008D7571969-01-13013 January 1969 App 1B to Midland 1 & 2 PSAR, QA Program. Includes Revisions 1-36 ML20008D7671969-01-13013 January 1969 Chapter 5 to Midland 1 & 2 PSAR, Reactor Bldg & Structures. Includes Revisions 1-36 ML20008D7541969-01-13013 January 1969 Chapter 1 to Midland 1 & 2 PSAR, Introduction & Summary. Includes Revisions 1-36 ML20008D7771969-01-13013 January 1969 App 5H to Midland 1 & 2 PSAR, Reactor Bldg Load Response Test. Includes Revisions 1-36 ML20008D7721969-01-13013 January 1969 App 5D to Midland 1 & 2 PSAR, Load Factors & Load Combinations. Includes Revisions 1-36 ML20008D7711969-01-13013 January 1969 App 5B to Midland 1 & 2 PSAR, Reactor Bldg Pressure Tests. Includes Revisions 1-36 ML20008D7591969-01-13013 January 1969 App 1B to Midland 1 & 2 PSAR, QA Plan for Midland 1 & 2. Prepared for Util.Includes Revisions 1-36 ML20008D7811969-01-13013 January 1969 Chapter 8 to Midland 1 & 2 PSAR, Electrical Sys. Includes Revisions 1-36 ML20008D7891969-01-13013 January 1969 App 14A to Midland 1 & 2 PSAR, Chemical Sprays. Includes Revisions 1-36 ML20008D7881969-01-13013 January 1969 Chapter 14 to Midland 1 & 2 PSAR, Safety Analysis. Includes Revisions 1-36 ML20008D7871969-01-13013 January 1969 Chapter 13 to Midland 1 & 2 PSAR, Initial Tests & Operation. Includes Revisions 1-36 ML20008D7861969-01-13013 January 1969 Chapter 12 to Midland 1 & 2 PSAR, Conduct of Operations. Includes Revisions 1-36 ML20008D7851969-01-13013 January 1969 Chapter 11 to Midland 1 & 2 PSAR, Radwastes. Includes Revisions 1-36 ML20008D7841969-01-13013 January 1969 Chapter 10 to Midland 1 & 2 PSAR, Steam & Power Conversion Sys. Includes Revisions 1-36 ML20008D7831969-01-13013 January 1969 Chapter 9 to Midland 1 & 2 PSAR, Auxiliary & Emergency Sys. Includes Revisions 1-36 ML20008D7821969-01-13013 January 1969 App 8A to Midland 1 & 2 PSAR, Separation Criteria & Administrative Procedure for Installation of Class 1E Equipment & Circuits. Includes Revisions 1-36 ML20008D7911969-01-13013 January 1969 Chapter 15 to Midland 1 & 2 PSAR, Proposed Tech Specs. Includes Revisions 1-36 ML20008D7801969-01-13013 January 1969 Chapter 7 to Midland 1 & 2 PSAR, Instrumentation & Control. Includes Revisions 1-36 ML20008D7791969-01-13013 January 1969 Chapter 6 to Midland 1 & 2 PSAR, Engineered Safeguards. Includes Revisions 1-36 ML20008D7781969-01-13013 January 1969 App 5I to Midland 1 & 2 PSAR, Design Features for High Energy Pipe Failure Outside Reactor Bldg. Includes Revisions 1-36 ML20008D7761969-01-13013 January 1969 App 5G to Midland 1 & 2 PSAR, QC Procedure for Field Welding of Liner Plate. Includes Revisions 1-36 ML20008D7741969-01-13013 January 1969 App 5F to Midland 1 & 2 PSAR, Reactor Bldg,Structural Analysis. Includes Revisions 1-36 ML20008D7731969-01-13013 January 1969 App 5E to Midland 1 & 2 PSAR, Yield Reduction Factors. Includes Revisions 1-36 ML20008D7701969-01-13013 January 1969 App 5A to Midland 1 & 2 PSAR, Design Bases for Structures, Sys & Equipment. Includes Revisions 1-36 1977-12-16
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20058L8721992-12-31031 December 1992 1992 Annual Rept,Cpc ML20126D7211992-12-16016 December 1992 Potential Part 21 Rept Re Actual Performance of Rosemount Supplied Bailey Bq Differential Pressure Transmitters Differing from Rosemount Original Spec.Bailey Controls Encl.Evaluation Not Yet Performed ML20246N1221988-12-31031 December 1988 CMS Energy 1988 Annual Rept ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20196J3801987-12-31031 December 1987 CMS Energy Corp 1987 Annual Rept ML20215G2441987-06-16016 June 1987 Part 21 Rept Re Failure of Load Sequencing Equipment Supplied in Aug 1977 During Scheduled Testing.Caused by Open Electrical Connection on One Crimp Lug.Since 1978,insulated Lugs Used on All Equipment ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure ML20207R9041986-12-31031 December 1986 CPC 1986 Annual Rept ML20214A0951986-11-14014 November 1986 Insp & Evaluation Re Adequacy of Stabilization Plan,In Response to Util 860701 Request for Withdrawal of Applications to Extend CP & Util Motions Seeking Withdrawal of OL Application ML20215G6801986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20205F6141986-08-13013 August 1986 Part 21 Rept Re Connecting Rod Bolts for Dsrv Engines.Listed Procedures Recommended for Next Connecting Rod Insp, Including Replacement of Bolts Due to Cracked Threads & Large Grooves & Galls in Threads ML20206U0591986-07-0202 July 1986 Part 21 Rept Re Potential Defect in Component of Dsrv Standby Diesel Generators,Involving Problem W/Fastening of Engine Connecting Rod Assembly Which Could Result in Engine Nonavailability.Procedure Will Be Issued by 860718 ML20197H2581986-05-0808 May 1986 Part 21 Rept 135 Re Defect W/Lube Oil Sump Tank Foot Valve of Standby Diesel Generator.Caused by Extrusion of Liner Matl Due to Overpressurization.Corrective Actions Being Developed.List of Affected Sites Modified ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20205N6811986-04-14014 April 1986 Final Part 21 & Deficiency Rept 86-03 Re Consolidated Pipe & Valve Supply,Inc Certified Matl Test Repts.Initially Reported on 860321.Six raised-face Orifice Flanges Statused & Segregated Per QA Procedures ML20205N7381986-04-14014 April 1986 Interim Deficiency & Part 21 Rept 86-02 1 Re Elastomer Liner in Clear Flow Co Foot Valves Used in Lube Oil Sump Tanks of Tdi Diesel Generators.Initially Reported on 860321. Action Will Not Be Pursued Unless Facility Reactivated ML20140H5991986-03-24024 March 1986 Second Interim Deficiency Rept 86-01 Re Error in Bechtel Computer Analysis Program.Initially Reported on 860121.No Corrective Actions Will Be Pursued & No Further Repts Will Be Submitted Unless Project Reactivated ML20154N3431986-03-10010 March 1986 Initial Part 21 Rept 135 Re Potential Problem W/Lube Oil Sump Tank Foot Valve of Dsrv Standby Diesel Generator for Facilities.Cause Not Determined.Recommends Utils Inspect Condition of Foot Valve Liners & Notify Tdi of Findings ML20153F5391986-02-14014 February 1986 Interim Part 21 & Deficiency Rept Re Error in Bechtel Computer Analysis Program ME101.Initially Reported on 860121.No Corrective Actions or Further Repts Will Be Submitted Until Project Reactivated ML20137N6101986-01-10010 January 1986 Interim Part 21 & Deficiency Rept 85-08 Re Isolated Failures of Betts Spring Co Intake & Exhaust Valve Springs Reported by Tdi.Initially Reported on 851218.Corrective Actions Will Be Pursued If Units Reactivated ML20141N8361985-12-31031 December 1985 CPC 1985 Annual Rept ML20138M3891985-12-12012 December 1985 Topical Rept Evaluation of Rev 1 to BAW-1847, Leak Before Break Evaluation of Margins Against Full Break for Rcs.... Rept Presents Acceptable Justification to Eliminate Dynamic Effects of Large Ruptures in Piping ML20198C4981985-11-0606 November 1985 Part 21 Rept Re Potential Defect in Dsr or Dsrv Standby Diesel Generator Intake & Exhaust Valve Springs Mfg by Betts Spring Co.Users Recommended to Inspect Engines for Broken Springs & Identify Original Mfg ML20138B9531985-10-0909 October 1985 Interim Deficiency Rept Re Larger than Anticipated Util Movement Where Freezewall Crossed safety-related Utils at Monitoring Pits 1,2,3 & 4.Initially Reported on 850917.No Action Will Be Taken ML20138C3111985-10-0808 October 1985 Interim Deficiency Rept Re Limitorque motor-operated Butterfly Valves Not Opening Electrically After Closed Manually.Initially Reported on 850912.No Corrective Actions Will Be Taken Unless Facility Reactivated ML20138C3251985-10-0808 October 1985 Interim Deficiency Rept Re Loose Set Screws on Anchor Darling Swing Check Valves & Disc Nut Pin Problems Causing Inoperability.Initially Reported on 850912.No Further Corrective Action Will Be Taken Unless Facility Reactivated ML20132B0261985-09-0303 September 1985 Part 21 Rept Re Possibility of Engine Ingestion of Unwelded Part in American Air Filter Standby Diesel Generator Intake Silencer.Immediate Hold Should Be Placed on Diesel Engines/Intake Silencers Not Yet in Svc ML20132D3191985-07-10010 July 1985 Interim Part 21 & Deficiency Rept Re Rupture During Testing by Wj Woolley Co of Inflatable Seal,Mfg by Presray Corp,Used in Personnel Air Locks in Reactor Containment Sys.Initially Reported on 850614 ML20129G0601985-04-26026 April 1985 Interim Deficiency Rept Re Potential for Cracking of Check Valves in on-engine Mounted Starting Air Piping of Tdi Diesel Generators.Initially Reported on 850401.Cause Not Determined.No Corrective Actions.Related Correspondence ML20112J3951985-03-22022 March 1985 Interim Part 21 & Deficiency Rept Re Failure of Gulf & Western MSIV Actuator Latch Roller Bearing.Matter Will Not Be Pursued Unless Plants Reactivated ML20100B6361985-01-21021 January 1985 Rept on Welding Allegations ML20114D3571984-12-21021 December 1984 Interim Deficiency Rept Re Diesel Fuel Oil Tank Soils Borings.Initially Reported on 841121.No Corrective Actions Necessary Due to Present Project Shutdown ML20100K9791984-11-27027 November 1984 Part 21 & Interim Deficiency Rept Re Ruskin Mfg Co Interlocking Blade Fire Dampers.Initially Reported on 841121.Corrective Action Will Not Be Pursued & No Further Repts Will Be Made Unless Plant Reactivated ML20100D9841984-11-21021 November 1984 Deficiency Rept Re Diesel Fuel Oil Tank Boring Logs.Util Response to Dow Chemical Co 841113 Request for Admissions Encl ML20100E4451984-11-15015 November 1984 Interim Deficiency Rept Re Cardinal Industrial Products Corp Spare Studs Received W/O Ultrasonic Exam.Initially Reported on 841010.Corrective Actions Will Not Be Pursued Unless Midland Reactivated ML20100E2621984-11-15015 November 1984 Interim Part 21 & Deficiency Rept Re Rosemount 1153 Series B Transmitters Potentially Leaking.Initially Reported on 841010.Four Units Shipped to Facilities.Corrective Actions Will Not Be Pursued ML20100E2371984-11-15015 November 1984 Interim Part 21 & Deficiency Rept Re Tdi Fuel Control Level Cap Screws.Initially Reported on 841010.No Corrective Actions Will Be Pursued & No Further Repts on Subj Made Unless Midland Reactivated ML20099E3531984-11-0909 November 1984 Interim Deficiency Rept Re Small Bore Piping Anchor Design. Initially Reported on 840816.Listed Corrective Actions Will Not Be Pursued & No Further Repts Will Be Made Unless Facilities Reactivated ML20093C3211984-10-0101 October 1984 Rev 0 to QA Program Plan for Shutdown Phase ML20093H3961984-08-0202 August 1984 Interim Deficiency Rept Re Seismic Qualification of Power Supplies for Eccas & Ni/Rps Equipment.Initially Reported on 840705.No Activity Being Currently Pursued.No Further Repts Will Be Made Unless Facilities Reactivated ML20093H8521984-08-0202 August 1984 Interim Deficiency Rept Re Field Installation of Itt Grinnell Struts & Extension Pieces.Initially Reported on 840705.No Activity Being Currently Pursued.No Further Repts Will Be Made Unless Facilities Reactivated ML20096A7781984-07-27027 July 1984 Final Deficiency Rept Re Defective Capstan Springs in Pacific Scientific Mechanical Shock Arrestors.Initially Reported on 840106.W/o Description of Investigation & Corrective Actions.Related Correspondence ML20093H8111984-07-27027 July 1984 Final Part 21 & Deficiency Rept Re Capstan Springs in Mechanical Shock Arrestors Supplied by Pacific Scientific. All Suspect Shock Arrestor Capstan Springs Will Be Inspected for Cracks & Defective Springs Replaced ML20093H8871984-07-20020 July 1984 Interim Deficiency Rept Re Reactor Coolant Pump Seals & Seal Covers.Initially Reported on 840622.No Activity Currently Being Pursued.No Further Repts Will Be Made Unless Facilities Reactivated ML20090G2141984-07-18018 July 1984 Idcvp:Control Room HVAC Sys Performance Requirements, Draft Topical Rept ML20093H4751984-07-17017 July 1984 Interim Deficiency Rept Re Core Flood Line Piping Supports in Reactor Pressure Vessel Connection Supplied by Bechtel. Overstressing Could Occur in Pipe Supports.No Commitment Made for Further Repts ML20096A2951984-07-11011 July 1984 Final Deficiency Rept Re Concrete Embedment Design Using Shear Lugs Located Outside Compression Zone.Initially Reported on 821203.Use of Shear Lugs Outside Compression Zone Is Proper Design Technique.Related Correspondence ML20093G7891984-07-11011 July 1984 Final Deficiency Rept Re Concrete Embedment Design Using Shear Lugs Located Outside Compression Zone.No Corrective Action Required.Not Reportable Under 10CFR50.55(e) 1992-12-31
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D d APPENDIX lhA CHE4ICAL SPPAYS INTRODUCTION A chemical additive has been added to the reactor building spray for the purpose cf re=cving any radioactive iodine which cay be released folleving a less-of-coolant accident. The chemical spray solution is a boric acid solution containing sodiu= thiosulfate and enough sodiu= hydroxide to for=
an alkaline pH buffer with the %cric acid. This solution co= position is cc=-
=cnly referred to as " alkaline suw.u:.1 thiosulfate. "
J The sodiu: thiosu] Nte in the alkaline sodium thiosulfate solution reacts rap-idly, co=pletely, a irreversibly with iodine, and was, in fact, suggested by Griffith(1) in his 15c3 study en the use of sprays for re=oving iodine frc=
reactor building at=cspheres. The sodium hydroxide is not intended to play an active role in the absorption of iodine; its function is =erely to preserve the long-tem the desiredstability pH. of the alkaline sodiu= thiosulfate solutien by =aintaining Data p esently available (2-7) indicate that the alkaline sodiu= thiosulfate 1
solution is satisfactory when used in a properly engineered syste=.
IODITE RD! OVAL EFFECTIVENESS ORNL (NSPP)has conducted facility. These tests, a nu=ber of spray as reported in ORNL tests in the Nuclear) h253(7 Safety Pilot Plant
, have de=enstrated that elemental radicactive iodine is rapidly recoved by chemical sprays.
' Using an NSPP run =ade at accident conditions closely approxi=ating those pre-dicted for Midland Units 1 and 2, the =easured iodine half-life was 31 seconds; that is, half of the radioactive iodine was re=oved fro = the Jtea=-air atmos-phere in 31 seconds after starting the sprays. These data haw been scaled to
' the Midland Units 1 and 2 design. They result in an iodine h C life of 28 seconds with the full spray installed capacity operating (2350 sp=) and a half-life of 56 seconds at half capacity. The iodine half-life reported in Section 14.2.2 3 7 is 61 seconds at full capacity and 121 seconds at half capacity.
A large number of confirmatcry tests (T-12) have been =ade which demonstrate that che=ical sprays are effective for ied' 'e re= oval. These spray tests have been
=ade using a vide range of variables - spray distributions with droplet sizes ranging frc= 100 to 1200 =icrons, fall heights ranging from a few feet to approxi=ately 50 feet, temperature and pressure conditions varying from a=bient to =ax1=u= accident conditions, iodine concentrations ranging fro = 1 to 130
=g/ cubic ceter, single and multiple spray nozzle installations, spray fluxes ranging frec O.007 to 0.2 gra per square foot vessel cross section, and cen-densing and noncondensing conditions. With this vide range of confir=atory
. test conditions, we are confident that the Midland Units 1 and 2 che=im spray syste=s vill perfom as predicted, b.
V 0 0 0 ?S 800730076f lhA-1 A=end=ent No. 5 11/3/69 3 ,,, - . . -.oi , - .
y 1m y .-- -, , ws.,e - , , , , -
,.,.e ..,n . ,,-
l' t .
ORGANIC ICDINE
, i The organic iodine consists pri=arily of = ethyl iodide but includes a s=all,
, al= cst insignificant, fraction of cther organic iodides. '
i Experimental data obtained under a vide variety of conditions en the amount of
' = ethyl iodide released frc= overheated fuel are repcrted in nu=ercus publica-tiens. Iodine release experiments using irradiated Zircalcy-clad UO, fuel in a
inPWR accident Section 1h.2.2 environment 3 7 Six tests show (13 1-ss)than were the perfor=ed 5 percent at organic Battelle1"orthwest di?.e assu=ed
- Laboratories.
organic for=. They found that 1 percent er less cf airborne iodine (ggg in the Thirteen other experi=ents were perfor:ed in England /; all but two shov less than 0.2 percent as = ethyl iodide. The highest result was 1
3 percent. There are a number of other experiments reported in the literature which deal with the a= cunt of nonreactive iodine released frc= overheated fuel.
Sc=e of these experiments have observed greater than 5 percent nonrecovable iodine; however, these experiments were conducted under conditions that are not applicable to the PWR accident environment. It is en the basis of all the
} data above that we concluded that 5 percent nonre=ovable iodine was a conserva-tive value for use in the accident analysis. l Spray tests at Oak Ridge National Laboratcry(7,15) and Battelle-Northwest Laboratory (16) have de=enstrated that alkaline sodium thiosulfate spray is ef-fective for re= oval of methyl iodide. While the removal rate is not as dra:atic as that for ele = ental iodine, the methyl iodine re= oval rate is sufficient to
'} =ake a significant reduction in the airborne iodine eencentration and thus in I_
s_/ the off-site doses.
Spray test A-12 in the Contain=ent Systems Experiment (CSE)(16) de=cnstrated I that alkaline thicsulfate spray re=cves methyl iodine fro = a stea=-air environment with a half-life of 80 minutes. Scaling this to Midland Units 1 and 2 predicts a methyl iodide half-life of 52 minutes.
PARTICUIATE IODINE i
A s=all fraction of the iodine assumed to be roleased folleving the LOCA may attach to particles and dust to for= particulane aerosols. Several studies have shewn that, should the particulate aerosols be for:ed, they vill be rapidly re-moved frc= the reactor building at=osphere.
Stinchec=be and Goldsmith (II' 16) have shown that sub=icron particles are re=oved with 95 to 99 percent efficiency by condensing steam. They clso show that the ther=al and vapor presse-e gradients, which exist in the condensing stea= envi-ron=ent, drive the sub=icron particles tevard the eccler surfaces where they are re=oved frc= the atmosphere with the condensing water vapor.
I -
Particles greater than 0.2 =icron size are re=oved efficiently by impac+. ion with the reactor building spray; these particles less than 0.2 =icron size are not.
However, the s= aller particles serve as condensation nuclei which grow until gravitational and inertial forces result in rapid deposition of these par ticles. (17, 19) The absence of particles, after aging, de=enstrates the effee-gr "' tiveness of this removal =echanis=. Idkevise, ve; r s=all thermal gradients act g
l a l driving forces which caus9l migration of particles to the spray drop surfaces and thereby enhance removal.l 7) i 14A-2 00&&
A=endment No. 5 11/3/69 u,_ _, _ .u . _ _ _ . . _ , _ . _ _ . _ _ _ _ _ _ . _ . _ _ ~ . , _ . _ _ _ _ _ , . . . _ . _
1 1
l High ersteconcentrations of small(eO, 21) particles are very unstable and rapidly agglet-into larger particles.
j These are effectively removed by impac-tien with spray drops, by washout frc: the ecndensing stea=, and by settlement.
As a result, nearly all particulates are expected to be removed frc: the re-actor building atmosphere.
Experiments in the CSE(0) have de=enstrated rapid re= oval of particulates by I
spraying. These tests indicate removal rates in a condensing stea: enviren-cent - similar to that in the reactor buildi:2g following an LCCA - of cne third
-f to one half as fast as for elemental iodine.
HY?cICDCUS ACID Hypoicdous acid is a product of elemental iodine hydrolysis by alkaline aqueous solutions.(22) The addition of sodium thiosulfate to an alkaline solution pre-cludes formation of hypoiodcus acid in any significant a: cunt. Sodium thio-l i
sulfate reacts instantaneously with elemental iodine, reducing the iodine to iodide. Thus, no ele ental iodine is available for hydrolysis to the hypc-iodcus form.
REFERENCES (1) Griffith, V., The Removal of Iodine Fro the Atmosphere by Sprays, AHSB(S)R h5, 1963, pp 7-12.
i
! (2) Cottrell, W. B., ORNL Nuclear Safety Research and Develop =ent Program, Bicenthly Report for July-August 1967, OR%-TM-1986, p 35 (3) Cottrell, W. B., ORNL Nuclear Safety Research and Develop =ent Program, Bimonthly Report for March-April 1968, ORNL-TM-2230, p 81.
! (4) Cottrell, W. B., ORNL Nuclear Safety Research and Develop =ent Prcgram, '
i i
Bicenthly Report for May-June 1968, ORNL-m-2283, pp 6h-73 (5) Cottrell, W. B., ORNL Nuclear Safety Research and Develop =ent Program, i Bicenthly Report for July-August 1968, ORNL-m-2368, Section 3 5 (6) Cettrell, W. B., ORNL Nuclear Safety Research and Develop =ent Program, Annual Report for 1967, ORNL-h228.
(7) Parsley, L. F. and Franzreb, J. K., Re cval of Icdine Vapor From Air and f Stean-Air At=cspheres in the Nuclear Safety Pilot Plant by Use of Sprays, ORNL h253, June 1968.
(8) Nuclear Safety Quarterly Report; November, December 1967, January 1968; for Nuclear Safety Branch of USAEC Divisicn of Reactor Develcirent and Technology, b.v the Staff of Battelle-Northwest, BNWL-816.
i (9) Nuclear Safety Quarterly Report; February, March, April 1968; for Nuclear
' Safety Branch of USAEC Division of Reactor Develop =ent and Technology, by the Staff of lattelle-Northwest, BNWL-885 l O.
U oo M 14A-3 Amindment No. 5 11/3/69
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I (10) j W.,
Sodium Thiosulfate Sprays, Reaction of Molecular IodineCRW.-h076, and of Methyl Iodid pe169With Parker, (11)
Nishizava, Y. , et al. , "A Study of the Re= oval of Iodine F phere No. by Sprays,'
11, November 19eo,Journal cf the pp 590-oC2. Japan Society of rem the Atmos-Nuclear Pever
, Vol 8, (12) Maekava, T., et al.,
I - Removal of Iodine by Sprav Under Atmospheric Press Ja9n Society of Nuclear Power, Vol 7, No.10, pp 563 ournal of the
, 1905569
- ~
(13) K.,
Coleman, L. F. and McCor:ack, J. D. , Co parison Centainment 2 Behavior of a Simulant ased With s of theFission Irradiated "C , ENL-581, March 1968, Table h, p A.5 .
From (lk)
J.,
Behavior April 1965 of Gas-Borne Iodine, Some TRG-R-983(W)
Experiments Relating t o the UKAEAC
, Windscale, England, (15) Parker, G. V., Creek, G.
E., and Horton, N. R., Dissolutio n and Hydrolysis Progress Report for Period Ending Decemberof Methyl Iod ram Annual (16) 31, 1967, CPlTL-h228, April 1968.
Nuclear Safety Quarterly Report; May, June, July 1969
( . Branch of published). USAEC Division of Reactor Development ogyand (to Technol, be for Nu (17)
P.,
by Condensing Steam," AERE-M-121h.Stinchcombe, " Removal of Iodine From AtmosphereR. A. and (18)
P.,
Stea=," Journal of Nuclear Energy
" Removal of IodineParts A/B, Vol 20Sti F rom Condensing (19) , pp 261-275, 1966.
G., "Diffusiophoresis and Them Vapor Syste=s," Aerosol Science, C. N. Davies, EdGo New York, New York, pp ophoresis in Water 163-194 (1 % 6). ., Academic Press, Inc. ,
(20) Collings, D. A.,
et al., " Experience in Trapping Iodine 131 -
andElements Other Fission Products Released From AGR-Type Fuel , -
, p 113
" TID 76 (21) Ke11holtz, G. W.,
Safeguards in Nuclear Installations," 0RNL-NSIC-13" eered Filters (22)
, p 139, October 1966.
Parsley, L. F. and Wantland, J. L. , " General Considerati Use of Sprays," pp 256-26h, Nuclear Safety Program ons I.garding Annual the P for Period Ending Dece=ter rogress Report 31,1968, ORNL-4373 .
\ 00043 lhA-h Amendment No. 5 11/3 /69