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Category:NON-RECURRING TECHNICAL REPORT (ENVIRONMENTAL)
MONTHYEARML20083P1781982-12-30030 December 1982 Midland Vegetation Monitoring Program:Preoperational Characterization of Vegetation & Vegetation Damage Syndromes in Vicinity of Midland Energy Ctr ML20079F9161982-04-14014 April 1982 Site-Specific Atmospheric Diffusion & Dose Projection Models for Midland Nuclear Power Plant, Technical Memo ML20050A9201982-03-0505 March 1982 Soil Dynamic Modulus Study. ML20009C6961981-05-31031 May 1981 1981 Corbicula Assessment for Midland Plant Site. ML19341C7321981-02-28028 February 1981 Site Specific Response Spectra,Part Iii,Seismic Hazard Analysis. ML19338D2791980-02-18018 February 1980 Rept of Archaeological Mitigation & Avoidance on CPC Right-of-Way in Saginaw & Midland Counties,Mi. ML19338D2831979-11-30030 November 1979 Terrestrial Ecological Survey for Midland Nuclear Plant Tittabawassee Substation to Gary Road Substation 345 Kv Transmission Right-of-Way, Final Rept ML19259B1131978-11-15015 November 1978 Terrestrial Ecological Survey-Midland Nuclear Plant Tittabawassee Substation-Gary Road Substation-345 Kv Transmission Row. Major Elements Assessed Were Soils, Vegetation,Mammalian Fauna,Avifauna & Herpetofauna ML19329F0641975-12-31031 December 1975 PMF Near Midland Site, Submitted as Part of Amend 31 to PSAR ML19329F0651974-08-31031 August 1974 PMF Near Midland Site, Submitted as Part of Amend 25 to PSAR ML19329F0701972-04-28028 April 1972 Environ Effects of Midland Plant Cooling Pond Summary Rept. ML19331A4331971-04-30030 April 1971 Environ Impact Review. ML19329F3471970-11-30030 November 1970 Public Health Review,Midland Plant,Units 1 & 2. ML19331B2051970-05-0505 May 1970 Review of Seismic Design Criteria. ML19338C0231970-02-25025 February 1970 Review of Seismic Design Criteria for Facility. ML19338C0301970-02-0404 February 1970 Comments on 691229 Psar,Vol 6. ML19329F2221970-01-31031 January 1970 Model Study Midland Cooling Pond. Prepared for CPC for Transmittal to Bechtel Corp ML19338B9991970-01-0505 January 1970 Comments on 700105 Psar,Amend 5. ML19329E3551969-12-31031 December 1969 Relationships Between Climate & Regional Variations in Snow Cover Density in North America. ML19347A5751969-07-28028 July 1969 Comments on 690605 Psar,Amend 2. ML19347A5781969-02-0303 February 1969 Comments on 681030 Psar,Vols 1 & 2. ML19329F2241968-03-22022 March 1968 Geology,Seismicity & Hydrology Study, for Proposed Midland Site.Received as Part of Amend 6 1982-04-14
[Table view] Category:TEXT-ENVIRONMENTAL REPORTS
MONTHYEARML20083P1781982-12-30030 December 1982 Midland Vegetation Monitoring Program:Preoperational Characterization of Vegetation & Vegetation Damage Syndromes in Vicinity of Midland Energy Ctr ML20062K0801982-07-31031 July 1982 Final Environmental Statement Related to the Operation of Midland Plant,Units 1 and 2.Docket Nos. 50-329 and 50-330. (Consumers Power Company) ML20079F9161982-04-14014 April 1982 Site-Specific Atmospheric Diffusion & Dose Projection Models for Midland Nuclear Power Plant, Technical Memo ML20050A9201982-03-0505 March 1982 Soil Dynamic Modulus Study. ML20039E8951981-12-31031 December 1981 3 to Environ Rept ML20009D1211981-06-30030 June 1981 2 to Environ Rept ML20009C6961981-05-31031 May 1981 1981 Corbicula Assessment for Midland Plant Site. ML19341C7321981-02-28028 February 1981 Site Specific Response Spectra,Part Iii,Seismic Hazard Analysis. ML19338D6151980-09-30030 September 1980 1 to Environ Rept ML19290F4011980-07-31031 July 1980 Evacuation Clear-Time Estimates for Areas Near Midland,Mi Nuclear Power Plant. Oversize Drawings Encl ML19345C1971980-06-30030 June 1980 Public Version of Independent Assessment of Evacuation Times for Midland Nuclear Power Plant, Vol 7,prepared for FEMA ML19338D2791980-02-18018 February 1980 Rept of Archaeological Mitigation & Avoidance on CPC Right-of-Way in Saginaw & Midland Counties,Mi. ML19260A7471979-11-30030 November 1979 0 to Environ Rept ML19338D2831979-11-30030 November 1979 Terrestrial Ecological Survey for Midland Nuclear Plant Tittabawassee Substation to Gary Road Substation 345 Kv Transmission Right-of-Way, Final Rept ML19261E2321979-06-29029 June 1979 Amend 67 to Application for CP & Ol,Consisting of Revision 9 to Environ Rept.Includes Addl Info Requested in Wh Regan 790522 & 781011 Ltrs,Revised Matl on Water Usage & Corrections of Errors & Omissions ML19270F6221979-02-27027 February 1979 to Environ Rept Containing Updated Matl as Detailed in Application Page ML19259B1131978-11-15015 November 1978 Terrestrial Ecological Survey-Midland Nuclear Plant Tittabawassee Substation-Gary Road Substation-345 Kv Transmission Row. Major Elements Assessed Were Soils, Vegetation,Mammalian Fauna,Avifauna & Herpetofauna ML20062D1071978-11-10010 November 1978 Amend 52 to Environ Rept Re Correction of Errors & Requests for Addl Info as Requested by Wh Regan'S 780522,781011, & s ML20126F1081977-01-31031 January 1977 Final Environmental Statement for the Construction of the Midland Plant Units 1 and 2,CONSUMER Power Company ML19329F0641975-12-31031 December 1975 PMF Near Midland Site, Submitted as Part of Amend 31 to PSAR ML19329F0651974-08-31031 August 1974 PMF Near Midland Site, Submitted as Part of Amend 25 to PSAR ML19329F0701972-04-28028 April 1972 Environ Effects of Midland Plant Cooling Pond Summary Rept. ML19331A4331971-04-30030 April 1971 Environ Impact Review. ML19329F3471970-11-30030 November 1970 Public Health Review,Midland Plant,Units 1 & 2. ML19331B2051970-05-0505 May 1970 Review of Seismic Design Criteria. ML19338C0231970-02-25025 February 1970 Review of Seismic Design Criteria for Facility. ML19338C0301970-02-0404 February 1970 Comments on 691229 Psar,Vol 6. ML19329F2221970-01-31031 January 1970 Model Study Midland Cooling Pond. Prepared for CPC for Transmittal to Bechtel Corp ML19338B9991970-01-0505 January 1970 Comments on 700105 Psar,Amend 5. ML19329E3551969-12-31031 December 1969 Relationships Between Climate & Regional Variations in Snow Cover Density in North America. ML19347A5751969-07-28028 July 1969 Comments on 690605 Psar,Amend 2. ML19347A5781969-02-0303 February 1969 Comments on 681030 Psar,Vols 1 & 2. ML19329F2241968-03-22022 March 1968 Geology,Seismicity & Hydrology Study, for Proposed Midland Site.Received as Part of Amend 6 1982-07-31
[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
[Table view] |
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7[0' PUBLIC IIEALTl! REVIEW
}fIDLAND PLANI UNITS 1 AND 2
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'U.S. DEPARTME'lT OF IIEALTif, EDUCATION, A'ID WELFARE Public I!calth Scrvice Environ =cntal l!calth Service 15ureau of .Radiolo;;ical !!c tich Division of Environmental Radiation f Nucicar Facilitics Branch November 1970 l .'G77 8 0 0 6 25 0 Q'33 l
l i _ . -
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. e g PREFACE
.. l Thin re port in ono of n uc rlies eli Innod to .asmu r t : .. s h., v.i inli n ..: '
evaluations by the Public !!calth Service of the environmental effectu
.of nucicar facilitics. The evaluation is based on a detailed technical review of design information for the facility as well as the " Environ-mental Report" submitted to the Atomic Encray Commission under the conditions of the National Environmental Policy"Act of 1969. Reviews of individual facilitics are performed by the Nuclear Facilitics Branch of the Division of Environmental Radiation, Bureau of Radio-logical IIcalth. The Branch, as a part of this revicu process, has developed and referenced several technical, documents to support the discussions prcsonted. In addition, for this facility, the Food and Drug Administration has reviewed certain aspects of the plant's operations pertaining to the use of process steam for manufacturing consumer products.
The evaluation presented in this report is directly responsive' to the requirements placed on Federal agencies by the National Environnental Policy Act and as such is intended to state the position of the l Department of llealth, Education, and Welfare on the environmental 1
cffects of the operation of the facility. The report is also intended, in the traditional role of the Public !!calth Service, to provide informa-l tion to the particular State health department involved for use in condneting their radiological health program for the facility.
O 9
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IttIRODUCIION AND CONChUSIONS This report summarizes the Public HeaIlth Service's evaluation of the environmental effects of the Midland Plant Units 1 and 2, proposed for construction near Midland, Michigan. This evaluation is based
,. on design information( and an Environmental Report ( provided
{ by the Consumers Power Company in support of an application for a construction permit. Two pressurized water reactors (PUR) of contem-porary' design ( ) will be used. Each will operate at an ulticute output of 2,552 hut, or 650 MRe. The plant will be located on the south shore of the Tittabawassco River ncai Midland, Michigan and will utilize a la rga pond for condenser cooling water. Commercial service for Units 1 and 2 is scheduled.for November,1974, and Noveraber,1975, respectively.
A distinguishing feature of the facility is that it is the first plant designed to supply process steam for an industry. About 25 percent
' (4,050,000 lb/hr) of the plant's steam energy will be supplied to the Dow Chemical Company for manufacturing cinomicals and pinatics at its Midland Plant. The acceptability of the Dow Company's proposed use of process steam which may potentially contain low concentrations of l radioactivity has been reviewed by the Food and Drug Administration (FDA). ,
I This revicw included considerayion of sito suitability, radioactive waste production and management practices, the proposed environmental l
l surveillance program, the documented emergency planning activitics,
e
. . i f
- and the rac lation problems presented by the furninhing of proccan steam from the plant to the Dow Chemical Company's Midland operations.
The principal conclusions of this review are as follows:
i
- 1. ' The noin factor in siting the Midland plant appears to be the I
l proximity of the Dow C.hemical Company plant hhich will utilize process 4
secam produced by th'c nucicar generators. There appears to us to be no major compromiscs, made on the site to accomplish this feature; i therefore, the site is concluded to be suitable for the facility as i
planned. ,
t 2 The radioactive waste treateent system planned for the Midland plant should be capabic of reducing ,cffluents to the lowest practicablo Icvel providing judicious use is made of all system components. This con-
, clusion is con'ditioned,*however, on the fact that the plant should have a minimum of 60 days holdup of gascous wastes and management
, should proclaim a philosophy of properly maintaining and using all
! liquid waste systems'.
i I
! ' 3. A document certifying the safety of the products of the Dow plant i
utilizing p'rocasa secam should be submitted for the review of Federal agencies which have regulatory.or other vested interests regarding the consumer utilization of these products.
1
- 4. Plant operating procedures concerning radioactivity Icycis in process steam and the monitoring systems to be used is not completc l enough to permit evaluation of potential hazards. A more detailed l .
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3 operational plan which describes the monitoring system should bc developed and provided to the Food and Drug Administration.
- - - 5. The proposed envirocuental surveillance program is generally adequate for assessment of environmental and public health effects from any radioactivity discharges that occur as a result of operating
{ the facility.
- 6. ' Emergency planning for the. facility is, in our judgment, incompletc at this stage of the application. Detailed plans nccd to be developed that clearly show relationships between the operator and the Michir.an Department of !!calth for all non-routine releases of radioactivity to the environment. -
- 7. If the above conditions are met, it is our opinion that radiological effects relative to the environment and the public due to the operation
. of Units x and 2 of the Midland pla 't will be minical.
- i RADI0 ACTIVE WASTE MANAGEMENT l '
l When Mid?.and's waste management system was finalized it incorporated the best waste treatment systems availabic at that time. Recent technological advances have been made, however, in the design of waste treatment systems and in the manne,r in which they arc operated./td
As a reasonabic alternative to. installing a "ncar zero release system,"
I we have concluded that the applicant should: 1) operate the present .
liquid waste system 100 percent of the time and 2) operate the gaseous waste treatment system with a minimum holdup time of 60 days. The l
4
- c. ,
. . . , . I
. 4 applicant should also c1carly state, as official . company policy, its commitment to use these waste management systems to their full capacity at all times to maintain all discharge levels at as low a level as' practicabic. In this respect, it is noted that the "cican" liquid waste system has no evaporator, but does have the capability to divert the waste to the " dirt'y" waste system which does.
Such a design places a high reliance on plant procedures to achieve a lowest procticable levci. Such a commitment would be consistent with the changes proposed by the Atomic Energy Commission in 10CFR20 and 10CFR50,(5) and would publicly acknouledge the company's realtration of the necessity for maintaining and improving the quality of the environment.
PROCESS STEA!! SYSTD1 ,
Most of the steam delivered to the adjacent Dou Chemical Company plant will be condensed and returned as heated fecdwater after use in the
~
various chemical pro.cosses. The f. team not condensed will be rcplaced by Dow with treated makeup water. A tertiary nator cycle with a heat exchanger between the secondary and tertiary ' systems is discussed in Amendments 15-19 of the PSAR. This system is designed to prevent any
. radionuclides found in the secondary system due to primary to secondary Icakage from being transported to the Dow plant. The applicant plans to use an on-line continuous gamma monitor that will alarm in the control room if the Icvel of radioactivity exceeds 3 x 10-6 Ci/ce, on the process steam line to thd Dow plant. There will also be a e
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3 conti.nuous monitor on the secondary secam system. These monitors
- are to help insure that radioactivity is not released to Dow at concentrations in the secam significantly greater than the back-ground beta-gamma Icycis of Lake Huron water.
There is no indication as to whether or not the above course of action is initiated automatically, nor how long it will take to switch from one heat exchanger to the other, nor hou much radioactivity could possi,bly enter. the tertiary system during this time period. More j
. information relating to this monitoring system is needed to permit a l -
t
, - full evaluation of this operation.
i The process steam will be used by' Dow in the manufacture of consumer products. The Food and Drug Administration should be provided with a
, listing of the compounds
- which will como into contact with the process steam. -
I
\ ENVIROE4 ENTAL SURVEILLANCE PROGSAM The applicant's environmental surveillance program is generally of sufficient scope to allow an adequato evaluation of the plant's environmental impact. One additional documentation, however, that we believe should be included is a detailed plan for the sampling of non-aquatic foodstuffs. We believe that the applicant should document the extent to which he, or some other Federal or State agency, vill sampic such items.as milk anId ghe,various crops groun in the area.
l An investigation should also be made as to whether dairy cattic may e
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4
. -) s obtain drinking water downstream of the plant in :;nch a way t.h.it I-131 may reach and c.xpose the population. In aihtition, we rair.nent <
that the applicant indicate the degree to which he plans to coordinate his proposed environmental surveillance programs with that of the Michigan Department of Health. Such coordination is essential for health agencies to be able to verify the continuing adequacy of their environmental surveillance. .
DERGENCY PLANNING The emergency planning information presented by the applicant in the PSAR appears to be quite comprehensive, especially with respect to the coordination with the Dow Chemical Company and the local police and civil defense authoritics. The State Department of IIcalth has the responsibility for evaluating offsite conditions and directing
, all actions to protect 'the public in the event of non-routinc releases of radioactivity. The arrangement between tho' company and the State Department of llealth has not been cicarly delineated in regard to this aspect of the emergency plan.
I .
I
)
. y REFERENCES
- 1. Hidland Plant--Units 1 and 2, " Preliminary Safety Analysis Report with Amendments," Docket Nos. 50-329 and 50-330, Pub lic Document Room, U.S. Atomic Energy Commission, Washington, D.C.,
January 13, 1969. ,
- 2. Hidland Plant--Units 1 and 2, " Applicant's Environmental Report, Construction Permit Stage," Ibid., July 24, 1970.
- 3. "A Pressurized Water Reactor Nuclear Power Station," Unpublished Report, U.S. Department of Health, Education, and Welfarc, Public Health Service, Bureau of Radiological IIcalth, Division of Environmental Radiation, September 1,1967.
, 4. Rancho Seco Nuc1 car Generating Station, Unit 1, " Preliminary Safety Analysis Report," Docket No. 50-312, Public Document Room,
- U.S. Atomic Energy Commission, Washington, D.C., November 1967.,
- 5. " Standards for Protection Against Radiation," Rules and Regulations of the U.S. Atomic Encrgy Commission, Code of Federal Reculations, Titic 10, Parts 20 and 50, The Federal Register, Vol. 35, No. 63, .
April 1, 1970.
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