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Line 2: |
Line 2: |
| | number = ML20127M045 | | | number = ML20127M045 |
| | issue date = 12/20/1968 | | | issue date = 12/20/1968 |
| | title = Ack Receipt of 681119 Ltrs Re Gaseous Diffusion Plant in State of Mn.Info Re Contamination of St Paul - Minneapolis & Suburban Water Supplies by Monticello & Elk River Atomic Reactors Encl | | | title = Ack Receipt of s Re Gaseous Diffusion Plant in State of Mn.Info Re Contamination of St Paul - Minneapolis & Suburban Water Supplies by Monticello & Elk River Atomic Reactors Encl |
| | author name = Badalich J | | | author name = Badalich J |
| | author affiliation = MINNESOTA, STATE OF | | | author affiliation = MINNESOTA, STATE OF |
Line 11: |
Line 11: |
| | contact person = | | | contact person = |
| | document report number = NUDOCS 9211250340 | | | document report number = NUDOCS 9211250340 |
| | | title reference date = 11-19-1968 |
| | package number = ML20127M025 | | | package number = ML20127M025 |
| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE | | | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M3801999-10-21021 October 1999 Forwards Insp Rept 50-263/99-06 on 990813-0923.Four Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted ML20216J2491999-09-30030 September 1999 Ack Receipt of 980804,990626 & 0720 Ltrs in Response to GL 98-01,suppl 1, Year 2000 Readiness of Computer Sys at Npps. Staff Review Has Concluded That All Requested Info Has Been Provided ML20217B1421999-09-30030 September 1999 Informs That on 990902,NRC Staff Completed mid-cicle Plant Performance Review of Monticello Nuclear Generating Station. Staff Conducted Reviews for All Operating NPPs to Integrate Performance Information & to Plan for Insp Activities ML20212K9131999-09-30030 September 1999 Refers to 990920 Meeting Conducted at Monticello Nuclear Generating Station to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA ML20216J8091999-09-24024 September 1999 Informs That New Diaphragm Matl Has Corrected Sticking Problem Associated with Increased Control Rod Drive Scram Times.Augmented Testing of Valves at Monticello Has Been Discontinued ML20216G4341999-09-24024 September 1999 Forwards Exam Rept 50-263/99-301 on 990823-26.Violation Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy.Test Was Administered to Two Applicants. Both Applicants Passed All Sections of Exam ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212G9801999-09-23023 September 1999 Refers to Resolution of Unresolved Items Identified Re Security Alarm Station Operations at Both Monitcello & Prairie Island ML20212F0901999-09-21021 September 1999 Confirms Discussion Between M Hammer & Rd Lanksbury to Have Routine Mgt Meeting on 991005 in Lisle,Il.Purpose of Meeting to Discuss Improvement Initiatives in Areas of Operations & Equipment Reliability ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20217A5751999-09-0909 September 1999 Forwards Individual Exam Results for Licensee Applicants Who Took Aug 1999 Initial License Exam.Without Encls ML20211Q6981999-09-0606 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Monticello Operator License Applicants During Wks of 010604 & 11.Validation of Exam Will Occur at Station During Wk of 010514 ML20211L1981999-09-0101 September 1999 Forwards Insp Rept 50-263/99-05 on 990702-0812.No Violations Noted ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211F9961999-08-26026 August 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 990101-990630, Revised Effluent & Waste Disposal Semi-Annual Rept for 980701-981231 & Revs to ODCM for Monitcello Nuclear Generating Plant ML20211C9501999-08-23023 August 1999 Forwards Rev 17 to Monticello Nuclear Generating Plant USAR, Updating Info in USAR to Reflect Implementation of Increase in Licensed Core Thermal Power from 1,670 Mwt to 1,775 Mwt.Rept of Changes,Tests & Experiments Not Included ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions ML20210T9601999-08-12012 August 1999 Provides Rept on Status of Util RPV Feedwater Nozzle Insps Performed in Response to USI A-10 Re BWR Nozzle Cracking ML20210Q0341999-08-0404 August 1999 Forwards SE Granting Licensee 980724 Relief Request 10 Re Third 10-year Interval ISI Program Plan,Entitled, Limited Exam ML20210H0861999-07-28028 July 1999 Forwards Insp Rept 50-263/99-04 on 990521-0701.No Violations Noted.Licensee Conduct at Monticello Facility Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Appropriate Radiological Controls ML18107A7051999-07-20020 July 1999 Provides Suppl Info Which Supersedes Info in 990625 Ltr in Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML20212H3191999-07-16016 July 1999 Forwards Aug 1999 Monticello RO Exam Package,Including Revised Outlines.All Changes Are in Blue Font ML20209G5621999-07-14014 July 1999 Forwards Insp Rept 50-263/99-11 on 990621-24.No Violations Noted.Objective of Insp,To Determine Whether Monticello Nuclear Generating Station Emergency Plan Adequate & If Station Personnel Properly Implemented Emergency Plan ML20196J5351999-07-0202 July 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950515 & NSP Responses & 980917 for Monticello Npp.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 ML20196J9681999-07-0101 July 1999 Informs That in Sept 1998,Region III Received Rev 20 to Portions of Util Emergency Plan Under 10CFR50.54(q).Based on Determination That Changes Do Not Decrease Effectiveness of Licensee Emergency Plan,No NRC Approval Required ML20209B6151999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Y2K Readiness Disclosure Attached ML20196H2291999-06-24024 June 1999 Responds to Administrative Ltr 99-02,dtd 990603,requesting Licensee to Provide Estimate of Licensing Action Submittals Anticipated.Four New Submittals Per Year Are Anticipated ML20207D5851999-05-25025 May 1999 Submits Info Re Partial Fulfillment of License Conditions Placed on Amend 101,which Approved Use of Ten Exceptions for 24 Months Subject to Listed App C Conditions.Util Will Submit Second Rept to Obtain Approval for Continued Use ML20206S0911999-05-17017 May 1999 Forwards Response to NRC 990324 RAI Re Proposed Amend to pressure-temp Limits & Surveillance Capsule Withdrawal Schedule, .Supporting Calculations Also Encl ML20206N5601999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Monticello Npp.Organization Chart Encl ML20206G2181999-05-0505 May 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Dtd 960110,for Plant ML20206G4901999-05-0404 May 1999 Forwards Staff Review of Licensee 960508 Response to NRC Bulletin 96-002, Movement of Heavy Loads Over Sf,Over Fuel in Rc or Over Safety-Related Equipment, .Overall, Responses Acceptable.Tac M95610 Closed ML20206G7741999-05-0303 May 1999 Forwards Insp Rept 50-263/99-02 on 990223-0408.One Violation Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206D1651999-04-27027 April 1999 Forwards Radiation Environ Monitoring Program for MNGP for Jan-Dec 1998, Per Plant TS 6.7.C.1.Ltr Contains No New NRC Commitments or Modifies Any Prior Commitments ML20205N0821999-04-12012 April 1999 Forwards SE of NSP Response to NRC GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Licensee Adequately Addressed Actions Requested in GL ML20205N4811999-04-0909 April 1999 Forwards Licensing Requalification Insp Rept 50-263/99-10 on 990308-12.No Violations Noted.However,Inspectors Through Observation of Simulator Scenario Exams Noted Difficulties in Ability of SM to Simultaneously Implement Duties of SM ML20205N5301999-04-0909 April 1999 Discusses Arrangements Made on 990406 for Administration of Licensing Exams at Monticello Nuclear Generating Station During Wk of 990823.Requests That Exam Outlines Be Submitted by 990128 & Supporting Ref Matls by 990719 ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C4851999-03-26026 March 1999 Informs That on 990203,NRC Staff Completed PPR of Nuclear Plant.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20205A5881999-03-24024 March 1999 Forwards Request for Addl Info Re Submittal Requesting Rev of pressure-temperature Limits & Surveillance Capsule Withdrawal Schedule ML20204H4711999-03-18018 March 1999 Forwards SER Concluding That Util Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello & Adequately Addressed Actions Requested in GL 96-05 ML20207H5161999-03-11011 March 1999 Forwards Insp Rept 50-263/99-01 on 990112-0222.No Violations Noted ML20207F4091999-02-28028 February 1999 Forwards Fitness for Duty Program Performance Data for Six Month Period from 980701-981231,IAW 10CFR26.71 ML20207F6741999-02-24024 February 1999 Forwards Summary of Nuclear Property Insurance Maintained at Monticello & Prairie Island Nuclear Generating Plants ML20207F6901999-02-23023 February 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 980701-981231, Off-Site Radiation Dose Assessment for 980101-981231 & Revised Effluent & Waste Disposal Semi- Annual Rept for 980101-980630, for Monticello ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J8091999-09-24024 September 1999 Informs That New Diaphragm Matl Has Corrected Sticking Problem Associated with Increased Control Rod Drive Scram Times.Augmented Testing of Valves at Monticello Has Been Discontinued ML20212G7171999-09-24024 September 1999 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Its.Conversion Package Submittal Continues to Be Targeted for Aug of 2000 ML20212A9761999-09-0909 September 1999 Submits 1999 Annual Rept of Any Changes or Errors Identified in ECCS Analytical Models or Applications ML20211K7971999-09-0101 September 1999 Informs That Util Reviewed Rvid as Requested in NRC .Recommended Corrections Are Listed ML20211K2591999-08-27027 August 1999 Forwards NSP Co Fitness for Duty Program Performance Data for Six Month Period Ending 990630 ML20211F9961999-08-26026 August 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 990101-990630, Revised Effluent & Waste Disposal Semi-Annual Rept for 980701-981231 & Revs to ODCM for Monitcello Nuclear Generating Plant ML20211C9501999-08-23023 August 1999 Forwards Rev 17 to Monticello Nuclear Generating Plant USAR, Updating Info in USAR to Reflect Implementation of Increase in Licensed Core Thermal Power from 1,670 Mwt to 1,775 Mwt.Rept of Changes,Tests & Experiments Not Included ML20210U1831999-08-12012 August 1999 Revises 980202 Commitment Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions ML20210T9601999-08-12012 August 1999 Provides Rept on Status of Util RPV Feedwater Nozzle Insps Performed in Response to USI A-10 Re BWR Nozzle Cracking ML18107A7051999-07-20020 July 1999 Provides Suppl Info Which Supersedes Info in 990625 Ltr in Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. ML20212H3191999-07-16016 July 1999 Forwards Aug 1999 Monticello RO Exam Package,Including Revised Outlines.All Changes Are in Blue Font ML20209B6151999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Y2K Readiness Disclosure Attached ML20196H2291999-06-24024 June 1999 Responds to Administrative Ltr 99-02,dtd 990603,requesting Licensee to Provide Estimate of Licensing Action Submittals Anticipated.Four New Submittals Per Year Are Anticipated ML20207D5851999-05-25025 May 1999 Submits Info Re Partial Fulfillment of License Conditions Placed on Amend 101,which Approved Use of Ten Exceptions for 24 Months Subject to Listed App C Conditions.Util Will Submit Second Rept to Obtain Approval for Continued Use ML20206S0911999-05-17017 May 1999 Forwards Response to NRC 990324 RAI Re Proposed Amend to pressure-temp Limits & Surveillance Capsule Withdrawal Schedule, .Supporting Calculations Also Encl ML20206D1651999-04-27027 April 1999 Forwards Radiation Environ Monitoring Program for MNGP for Jan-Dec 1998, Per Plant TS 6.7.C.1.Ltr Contains No New NRC Commitments or Modifies Any Prior Commitments ML20196K7831999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Monticello & Prairie Island Nuclear Generating Plants,Per Requirements of 10CFR50.75(f)(1) ML20205H5731999-03-29029 March 1999 Submits Required 1998 Actual & 1999 Projected Cash Flow Statements for Monticello Nuclear Generating Plant & PINGP, Units 1 & 2.Encl Contains Proprietary Info.Proprietary Info Withheld,Per 10CFR2.790(b)(1) ML20205C6561999-03-26026 March 1999 Submits Semiannual Update on Project Plans for USAR Review Project & Conversion to ITS ML20207F4091999-02-28028 February 1999 Forwards Fitness for Duty Program Performance Data for Six Month Period from 980701-981231,IAW 10CFR26.71 ML20207F6741999-02-24024 February 1999 Forwards Summary of Nuclear Property Insurance Maintained at Monticello & Prairie Island Nuclear Generating Plants ML20207F6901999-02-23023 February 1999 Forwards Effluent & Waste Disposal Semi-Annual Rept for 980701-981231, Off-Site Radiation Dose Assessment for 980101-981231 & Revised Effluent & Waste Disposal Semi- Annual Rept for 980101-980630, for Monticello ML20203A3081999-01-28028 January 1999 Forwards TS Page 60d,as Supplement 3 to 971125 LAR Re CST Low Level Hpci/Rcic Suction Transfer.Page Includes NRC Approved Amend 103 Changes for Use by NRC in Issuing SER ML20202F7821999-01-27027 January 1999 Forwards 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(vi).Ltr Contains No New Commitments or Modifies Any Prior Commitments ML20206S0331999-01-20020 January 1999 Submits Annual Rept of Safety & Relief Valves Failure & Challenges ML20206P1221998-12-31031 December 1998 Forwards LAR for License DPR-22,revising TS pressure-temp Curves Contained in Figures 3.6.1,3.6.2,3.6.3 & 3.6.4, Deleting Completed RPV Sample SRs & Requirement to Withdraw Specimen at Next Refueling Outage & Removing Redundant SR ML20198M3271998-12-28028 December 1998 Submits Change to Commitment for Submittal of ITS Application.Util Plans to Provide ITS Conversion Package Submittal to NRC in Dec of 2000 ML20198J7511998-12-22022 December 1998 Informs of Completion of Listed Commitment Made in Re Severe Accident Mgt. Severe Accident Mgt Guidelines Have Been Assessed,Plant Procedures Have Been Modified & Training of Affected Plant Staff Has Been Completed ML20198J4311998-12-21021 December 1998 Forwards Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv. Under Separate Cover,Licensee Is Providing LAR to Revise Curves ML20198J7711998-12-14014 December 1998 Documents 981214 Discussion with NRC Staff Re Deviation from Emergency Procedure Guidelines ML20195C8781998-11-11011 November 1998 Forwards Supplement to 971125 License Amend Request Re Condensate Storage Tank Low Level Suction Transfer Setpoints for HPCI Sys & Reactor Core Isolation Cooling Sys ML20195C9631998-11-11011 November 1998 Forwards 120-day Response to NRC GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment ML20195E2261998-11-10010 November 1998 Submits Suppl 1 to Util Response to NRC Request for Addl Info Re 981118 Request for Deviation from Emergency Procedure Guidelines ML20155H6591998-11-0404 November 1998 Forwards Response to 980910 RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20155F9091998-10-27027 October 1998 Forwards Master Table of Contents to Rev 16 of Usar.Info Was Inadvertantly Omitted at Time of 981023 Submittal 05000263/LER-1998-005, Forwards LER 98-005-00,re HPCI Being Removed from Service to Repair Steam Leak in Drain Trap Bypass.Commitments Made by Util Are Listed1998-10-21021 October 1998 Forwards LER 98-005-00,re HPCI Being Removed from Service to Repair Steam Leak in Drain Trap Bypass.Commitments Made by Util Are Listed ML20154L9321998-10-12012 October 1998 Forwards Suppl 2 to LAR & Suppl 980319,which Proposed Changes to Ts,App a of Operating License DPR-22 for Mngp.Number of Addl Typos & One Title Change on Pages Associated with Amend Request Have Been Identified 05000263/LER-1998-004, Forwards LER 98-004-00 Re Manual Scram Inserted Following Pressure Transient Closes Air Ejector Suction Isolation Valves & Trips Offgas Recombiners.Ler Contains Listed Commitment1998-10-0909 October 1998 Forwards LER 98-004-00 Re Manual Scram Inserted Following Pressure Transient Closes Air Ejector Suction Isolation Valves & Trips Offgas Recombiners.Ler Contains Listed Commitment ML20154L8671998-10-0909 October 1998 Forwards Suppl 1 to LAR for License DPR-22, Replacing Exhibits B & C of Original Submittal to Reflect Item 2 & Subsequent Changes.Request for APRM Flow Converter Calibr Interval Extension,Withdrawn ML20154J6201998-10-0505 October 1998 Forwards Rev 49 to Monticello Security Plan.Encl Withheld, Per 10CFR73.21 ML20153F5351998-09-25025 September 1998 Submits Semiannual Status Update on Project Plans for USAR Review Project & Conversion to Improved TS ML20153F0051998-09-25025 September 1998 Forwards Suppl 1 to 971031 Application for Amend to License DPR-22,replacing Exhibit C Which Contains TS Pages Incorporating Proposed Changes Described in Original 971031 Request ML20153D8561998-09-17017 September 1998 Forwards Rev 17 to EPIP A.2-414, Large Vol Liquid Sample &/ or Dissolved Gas Sample Obtained at Post Accident Sampling Sys. Superseded Procedures Should Be Destroyed.Ltr Contains No New NRC Commitments,Nor Does It Modify Prior Commitments ML20153D1441998-09-17017 September 1998 Informs NRC That Listed Commitments 1 & 3 Were Completed by End of 1998 Refueling Outage.Commitments Involved Final Disposition of Remaining Outlier Components Re All Known Outstanding Work Associated with GL 87-02,Suppl 1,USI A-46 ML20153E0331998-09-17017 September 1998 Forwards Response to NRC 980629 RAI Re RPV Weld Chemistry Values Previously Submitted as Part of Plant Licensing Basis.Next Monticello RPV Sample Capsule Scheduled to Be Removed During 1999/2000 Refueling Outage ML20153E9011998-09-0909 September 1998 Forwards Rev 1 to MNGP Colr,Cycle 19, Incorporating Changes to power-flow Maps in Figures 6 & 7.Changes Made to Correct Errors in Stability Exclusion Region & Stability Buffer Region Shown on Rev 0 ML20151S7401998-08-28028 August 1998 Responds to NRC Re Violations Noted in Insp Rept 50-263/98-09.Corrective Actions:Procedure 4 AWI-04.04.03 Will Be Revised to Eliminate Term Urgent from Section 4.3.1.D ML20238E8201998-08-26026 August 1998 Forwards Effluent & Waste Disposal Semi-Annual Rept for Jan-June 1998 & Revised Effluent & Waste Disposal Semi- Annual for Jul-Dec 1997. Ltr Contains No New NRC Commitments,Nor Does It Modify Any Prior Commitments ML20237E9741998-08-26026 August 1998 Forwards Rev 4 to EWI-09.04.01, Inservice Testing Program. Rev of Inservice Testing Program Reflects Valves Added as Result of Component Mods Recently Performed ML20237E6821998-08-25025 August 1998 Forwards fitness-for-duty Program Performance Data for Six Months Period Ending 980630 1999-09-09
[Table view] |
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sp-1989
, 04-196h STATE OF MINNESOTA MINNESOTA POLLUTION CONTROL AGENCY 459 BOARD oF HEALTH BUILDING UNIVER$1TY CAMPUS MINNE APOLIS 55440 December 20, 1968 Mr. Harold L. Price Director of Regulations U. S. Atomic Energy Commission Washington, D. C. 20545
Dear Mr. Price:
I wish to acknowledge receipt of your letters dated November 19, 1968, regarding 1) infomation as to a gaseous diffusion plant in Minnesota, and
- 2) response to my letter of September 3,1968, reganiing various questions submitted by Mr. Steve J. Gadler, with attachments.
l Your comments and that of your staff are greatly appreciated and are now being reviewed by members of the Agency, our staff, and also our con-sultant on radioactivity.
I Since the original submission to you of some 80 questions posed by Mr.
Gadler, he has drafted an additional 27 questions that bear consideration by the Atomic Energy Commission. I have enclosed a copy of these questions-signed by Mr. Gadler and again ask that these be answered in his behalf and as a matter of infonnation to our Agency.
One further question I neglected to ask you at the outset, and for your comment, was a statement that was made by the Congressional Joint Comittee on Atomic Energy in the congressional report under date of February 1968, that states: "Until experience is gained and adequate safeguards are proved out, prudence dictates that large reactor installations be fairly far re-moved from population centers."
If this is true, why, then, was the Monticello nuclear power reactor located only forty miles upstream from the Minneapolis-St. Paul Metropolitan Area, having a population of approximately two million people, and the water supply for in excess of one million people? Would you please clarify for us the statement as it appeared and is quoted in the Congressional Record?
DA-1969 Rec'd Off. Dir, of Reg.
9211250340 690217 Date '/4b 4'N PDR ADOCK 05000263 '-
P PDR 6 Time fM4)_ i
)
Mr. Harold L. Price 12/20/1968 Washington, D. C.
Again I wish to express my appreciation to you and others of the AEC staff for your cooperation in providing the information requested in the past, and I trust that the above request for additional information and answers will be forthcoming in the very near future.
Very truly yours, r-l 9
John P. Badalich, P.E.
Execuiive Director JPB:mmb Enclosure
1
'. r . . ..
COSTAhINATION OF ST. PAUL - MINNSAPOLIS A'O SUBU?3AN WATSR SUPPLIES BY M0" TIC::LLO AND ELK RIVSR ATOMIC RIACTORS
,[ '
c [
- 1. What are the types and a ounts of radioactivo poHutants that win bo discharged into tho Mississippi River by tho Monticello roactor por
, day? Per year? ,
- 2. In the eventof a serious atomic accidont that would contaminate
- tho )dssissippi River with radioactive poHutants will AEC provido the Twin Cities water for drinking and industrial purposos?
l 3 If not, why did the ASC approvo NSP c pordt at Monticono?
- 4. Is an emergency water supply for the St. Paul and Minneapolis water systems in oxisting U.S. Atomic Snorgy Commission plans if tho -
- river is contaminated with radioactivo poHutants? _
- ct.
- 5. Has c.:7 nrobable atomic accident at the Monticeno reactor that j would provcnt utilizing Mississippi River water by St. Paul and, ,_ _
Minneapolis boon discussed with concerned public water officials?
l 6 In the event of the emergency in (4) above how win industrios i dependant upon the hississippi water stay in op3 ration?
- 7. In the ovent of an atomic or other accident at the Monticano .
reactor that would ponute the Kississippi River water for an down-river users especiany the St. Paul -- Minneapolis residents who win .
nay for thb added water costs if an emergoney sourco of water scomes
~
availabic) , ,
- 8. Since the health and safetyaf the public which includes integrity .
of the St. Paul. - Minneapolis whler supplies is a responsibility of the .
! Atonic 3nergy Commission-both by law and its oun regulations, how win i the Atomic Enorgy Conmission provent the ponution of the Eississippi River with radioactive pouutants which are a minion to a binion times
- more toxic than any chemical known to man) - '
- 9. .ince the Atomic Energy Commission has permitted the construction of I the Monticeno reactor above the St. Paul and Kinneapolis water intakes
- on the Mississippi River win the Atomic Energy Commission carry out the intent of. the congress and provent- the discharging of radioactive raterials into the river thereby providing for tho health and safety of i the down-river residents. ,
, 10. What type of communication networks are to be provided in case _ of
- the. inevitable atonic acyident at the Monticallo atonic reactor which
- would destroy.St. Paul - Minneapolis water supplies?
l i R. What are the prosent plans or arransoment for t.lorting St. Poul -
I Minneapolis water officials of an accidenal discharge of radioactive .
materials into the Mississippi River at Monticano?
'O t 3
yf y .
~
e TlQW&% . __ . _, . . _ .
l- .
9
- 12. Sinco tho Atode Unnrcy Co r. mission is responsiblo for the "hoalth and safoty" how u3 u they provent s tbotar;o of tho 250,000 gan on radio-
- activo unter rotontion tanks at Monticono?
- 13. In the event of sabatage or accidental bursting of the 250,000 gan on radioactivo unter rotontion tanks who viu adviso St. Paul wator officials about the accident.
4
- 14. Who win adviso St. Paul and Minnonpolis public officials of tho .
serious radioactivo contamination of the rivor?
l 15. , who wiu dotermine the air.ount and ty;ra of radioactivo materials discharged into the river? Who advises who, when and by what roans?
l 10. Since semntics plays such a largo role in nucicar literature and
! torminology and the Atode Energy Cor. mission refers to serious atomic accidents as incidents or occurrences, is it possiblo to withhold ' n-
! formation affecting the safety and health of peopic by reporting an 1 atomic accident at Monticcuo as an incident?
- 17. . Sinco it is incumbent upon the op3 ration of any atomic facility with*this state to make fun and comploto disclosures concerning types a and amounts of radioactivo materials to bo discharged into the environ-ment, how doos NSP intent to provide the information and to whom?
i
- 18. Does NSP intend to dilute radioactive mterials for discharge into i the Mississippi River at the same ratio used by the U.S. Atomic Energy -
Commission's reactor at Elk River?
19 Does dilution of those radioactive toxic mtorials that NSP desires
- to dischargo into the St. Paul - Minneapolis water supplies reduce their dangers to the drinking populaces?
- 20. Since dilution of these cumulativo types of radiation does not i reduce their irraversiblo characteristics, how can the NSP or the Atomic Energy Commission protect the public health and safety sinco the
, populace will be drinking radio active water?
- 21. What win be seving to the KSP stockholders in KG produced by the into the environment 4
i Monticano and therebyatonic reactor polluting thruand St. Paul theFinneapolis discharging $fds,~tead of out-state shipment for burial and perpetual Atomic Energy Commission caro?
4
- 22. Since radioactivo nuclides or radioactive materials are an subject to a law of nature that the rate of physical decay natural to each can-
- not be altered to mtko then less radioactivo regardless of the amount of dilution or dispersion or' dejg;t).on, how does the Atomic Snergy .
Commission proposo to preservo the environment and rarevent the radio-active pouution of the St. Paul - Minneapolis water supplies?
23'. Sinco the Mississippi River is the source of water for St. Paul and Minnoapolis and'others doun-river, why does NSP dosire to discharge radioactivo wastes into tho rivor?
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. 4-24, 31nco aTl radiation rogardles." of the deso is cunalativo and irrevor31blo and sinen the radioactive wanto froa the ato:dc reactor at 1.ontico110 if discharced into the rivar wiTL incroase substantially, the re.dionativo dosagos to tho St. Pant and Minr.onpolis water usors why doas lGP want to uso tho Mississippi River for radioactive wasto ,
disposal?
- 25. Sinco a Tor $g cordos of smill radioactivo insults to tho huwin body rny accunulato to produco long-dolayod serious injury uhy has the U.S. Atorde Snargy Comission affirmod and approved the Monticollo atonde roactor that wants to dischargo radioactivo pollutants into the river and the atmosphoro thoroby incroasin;; tho dosages to down-river residents with its routes of water.and atnosphorio disposal?
- 26. Sinco the nost tc r.pting and nost econonical radioactivo disposal routo for tho Monticollo roactor is the Mississippi Pdver, uhat assuranses will the MN/, and down-river water usors that USP
- is not " riding the rivor"7
- 27. Since tho U.S. Atenic Ener6y Cor;7.ission is not concerned with the integrity of the St. Pau'l and hinnonpolis water supplies, uhnt right do they have to polluto timso waters?
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