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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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20202B7191999-01-26026 January 1999 Discusses 990125 Telcon with T Witschen & D Mcneil Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Monticello Nuclear Generating Station.Insp Planned for Week of 990308 ML20199H8321999-01-20020 January 1999 Forwards Insp Rept 50-263/98-18 on 981201-990111.No Violations Were Identified.Conduct of Activities at Monticello Facility Was Generally Characterized by safety- Conscious Operations & Sound Maint Practices ML20199G7721999-01-14014 January 1999 Forwards Request for Addl Info Re GL 88-20, Individual Plant Exam of External Events (IPEEE) for Severe Accident Vulnerabilities, Issued in June 1991 ML20206R8631999-01-12012 January 1999 Informs That Staff Has Prepared TS Interpretation of Requirements for Extending Surveillance Intervals at Plant,Per NRC Request ML20199E4791999-01-0606 January 1999 Forwards SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode, for Monticello ML20206R8741999-01-0404 January 1999 Discusses Clarification of Understanding of Safety Evaluation Related to Deviation from Emergency Procedure Guidelines for Monticello.Staff Agrees with NSP Characterization & Resolution of Issues ML20198R2001998-12-30030 December 1998 Forwards Insp Rept 50-263/98-19 on 981214-18.No Violations Noted.Purpose of Insp Was to Review Plant Chemistry Program, PASS & REMP ML20198P0501998-12-28028 December 1998 Informs of Completion of Review of Relief Request 9 Re Third 10-year Interval ISI Program Plan,Entitled Use of High Alloy/High Nickel Calibr Block for Dissimilar Metal Welds. Supporting SE Encl ML20198G0761998-12-21021 December 1998 Acks Receipt of Notifying NRC That Commitment Noted in Is Complete Re Tornado Effects on Reactor Bldg Superstructure ML20198D0181998-12-15015 December 1998 Informs That as Part of PRA Implementation Plan,Commission Assigned Two SRAs to Each Regional Ofc.Sras Will Routinely Assess Licensee Event Repts,Plant Events,Insp Findings & EAs from Risk Perspective ML20198B7721998-12-14014 December 1998 Forwards Insp Rept 50-263/98-16 on 981014-1130 & Notice of Violation Re Fire Brigade Drill Participation ML20198D0641998-12-10010 December 1998 Forwards SE Accepting Licensee 971118 Request for Review & Approval of Deviation from BWROG Epg,Rev 4,NEDO-31331, March,1997.Deviation Will Permit Rev of Plant EOPs to Recognize 2/3 Core Height as Adequate for Core Cooling ML20196C2411998-11-24024 November 1998 Forwards Insp Rept 50-263/98-17 on 981026-30.No Violations Noted.Security Dept self-assessment Efforts Continue to Be Very Strong ML20196D5641998-11-20020 November 1998 Discusses 981104 Insp Resource Planning Meeting for Monticello & Advises of Planned Insp Effort for Next 6 Months at Plant.Info Provided to Min Resource Impacts on Staff & to Allow for Rescheduling Conflicts to Be Resolved ML20195J8811998-11-19019 November 1998 Informs That EOP Flow Charts C.5-1100 RPV Control, Rev 5 & C.5-1100... Rev 6 Marked Proprietary & Submitted as Attachments 3 & 4 to Util Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20196G6081998-11-19019 November 1998 Submits Correction to Which Advises Licensee That EOP Flow Charts, C.5-1100 RPV Control, Rev 5 & C.5-1100 RPV Control, Rev 6,marked Proprietary,Will Be Withheld from Public Disclosure.Ltr Reissued to Correct Date of Issuance ML20195E3321998-11-12012 November 1998 Forwards SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Facility Has Adequately Addressed Purpose of 10CFR50.54(f) Request.Usi A-46 Program Was Established in Response to GL 87-02 ML20196D7291998-11-10010 November 1998 Forwards Insp Rept 50-263/98-15 on 980831-1014.No Violations Noted.Investigation Team Assembled by Station Mgt to Determine Root Cause of Offgas Sys Problem Was Thorough & Aggressive ML20154L2951998-10-0909 October 1998 Informs That Effective 981011,project Mgt Responsibility for Plant Will Be Transferred from Tj Kim to CF Lyon.Cf Lyon May Be Contacted at Listed Number ML20154F4971998-10-0606 October 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-263/98-09 Issued on 980730 ML20154J2501998-10-0202 October 1998 Forwards Audit of Year 2000 Program at Monticello Nuclear Generating Plant on 980915-17 as Followup to NRC GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants, Issued on 980511 ML20153C4611998-09-21021 September 1998 Submits Comments on Draft Environ Impact Statement for Minnesota Lake Superior Coastal Program 1999-09-09
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'NOV 2 31970 Honorable Edmund S. Muskie Chairman, Subcomittee on Intergoverncental Relations Cocmittee on Government Operations United States Senate
Dear Senator Maskie:
I understand that Chairman Seaborg has responded to your letter of September 17, 1970, with reference to the testimony of Mr. John Dadalich, Executive Director, Minnesota Pollution Control Agency. At the Chairman's request I am pleased to provide the substantive answers to the qucstions posed in your letter.
The Comission's policy pertaining to the locating of nucicar facilities with respect to the proximity of public water intales is contained in the Comission's regulations,10 CFR Parts 50 and 100 (copies enclosed). Part 50 Section 50.34 requires an applicant to describe and give a safety assessment of the site on which the facility will be constructed, including as a minimum the site evaluation factors identified in Part 100. One of these factors is the hydrological characteristics of the site (5100,10(c)(3)]. Our specific procedure in reviewing the Elk River and Monticello sites, as well as any other site, has been to detennine. the location of all domestic water supplies such as rivers, lakes, wells, and reservoirs which are in the vicinity of the proposed plant and which may be affected by the proposed operation. Then on an individual basis we evaluate the influence of effluent releases from the plant on the sources of water.
The ranner in which we handled this specific problem relative to the location of the Minneapolis-St. Paul water intakes downstream of the Monticello plant exerplifies this procedure. Our evaluation of this problem is given on pages 32 to 37 cf the Safety Evaluation (copy enclosed) prepared by the Civision of Reactor Licensing as a part of the review of the safety of the Monticello plant. In this evaluation we considered the design of the liquid waste disposal systems, the location of the Monticello plant relative to the Minneapolis and St. Paul water intakes, the characteristics of the Mississippi River in this area, and potential levels of radioactive releases, both accidental and routine, from the plant. ' Our evaluation concluded that postulated releases from the Monticello plant would not endanger7 -I ;fg, ge health and safety of the citizens residing in the Minneapolis-
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. Honorable Edmund S. Muskie (
As to your more general question of the distance of reactor sites from-urban areas such as the Minneapolis-St. Paul metropolitan area, 10 CFR Part 100, 5100.11 (copy enclosed) of the Commission's regulations provides guidance relative to this question. The attached excerpt from AEC staff responses to concerns _ stated by persons making limited appearances in the public hearing on the Monticello facility briefly explains the application of 10 CFR Part 100 in our review of the Monticello facility.
If I can be of any further assistance to you in responding to these questions, please let me know.
Sincerely,
- a % , , , m Harold L. Price Director of Regulation
Enclosures:
- 1. 10 CFR Part 50
- 2. 10 CFR Part 100
- 3. Monticello Safety Evaluation [m)
- 4. Excerpt REVISED IN OFFICE OF DIRECTOR OF REGULATION TO REVISE PARAGRAPHS 2 & 3, PAGE 1, AND INCLUDE 6100.11, FIRST FULL PARAGRAPH PAGE 2, THIRD LINE.
SEE ATTACHED YELLOW FOR PREVIOUS CONCURRENCES \
Distribution: ' ~
P. A. Morris H. K. Shapar Public Document Room (50-263)
Congressional (2)
G. Ertter (DR-2801)
E. G. Case Secretary (2)
H. L. Price R. C. DeYoung B. Schur
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,MR. KNOTTS:- In the .tatement made by the_ City of.Si.' Paul (St.1 Paul ,
' ', Statement Page 18) a_ question was raised as to the placement ofLnucicar
'i I power plents in relation to population centers. The statement went on
=l further to raise a question as to why the provisions of 10CFR 100,11 (a)(3) shouldn't be read as requiring the siting of nucicar reactors even
- . s further away from population centers such as the Twin City metropolitan j area. Mr. Vassallo would you please comment?
MR. VASS A1.1.0 : Part 100 is the Commission's regulation on reactor site
~! criteria. First, I would lik: to note, that the provisions of 10CTR 100.11 (a)(3), which deals with establishing population center distances
- is dependent on subsections (a)(2) of 10Crn 100.11. Subsection 100.11 (a)
(2) deals with establishing low population zones.
t As discussed in the AEC regulatory staff's Safety Evaluation, the low population zone distance is one mile which nects the guidelines of
. 10CFR 100,11 (a)(2) as shown on page 44 of the Safety Evaluation. Since i
the low population zone distance satisfies the provisions of'10CFR 100.11 (a)(2), thic distance is used directly to deternine the population center distance in accordance uith 10 Crn 100.11(a)(3), which states, "A pop-ulation center distance of at 1 cast one and one-third times the distance from the reactor to the outer boundary of the lou population zone. In applying this ruide, due consideration should be given to the population distribution within the population center. Where very large cities are involved, a greater distance may be necessary because _of total integrated
~~k population dose consideration." This means that for the Monticello- site the required population center distence vould have to be at least one-and-As defined in 10 CFR 100.3, " Population
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center distance means the d ista-nce iron the reactor to the nearest boundary i.
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- Attached excerpt is a response provided by the AEC regulatory staff to limited appearance statements made by representatives of the City of St. Paul in the Matter of 'iorthern States Power Company Olonticello Nuclear Generating Plant, Unit 1), Docket No. 50-263.
The attached was provided for the record (Inserted following Transcript page 2029) during the August 7, 1970 session of the public hearing in the subject matter.
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There is no such population center 'onc and one-third miles from the reactor, St.- Cloud with a population of approximately 33,000 is- 22 miles from th'c t
- site. The distance of the Twin City metropolitan area is approximately
,j 30 miles from the site, and meets the requirements of 10 CFR 100,11 (a)(3).
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.- . 3 S tay. u N y -1D) a cycstiou Ur . raised as . t!.; W cec: . at "of nuclear o power plz ;ts in relnt oa to p;, : u.o:. c: u . -. S c., s enta _. :. v;;at c,n:
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.i shouldn't be reed as' requiring th citin;-c uekcc reactors ovcu ,
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,. 8 1:n. VASSALLO: P.m 100 is tN Cc;n:;csicr5 -r:plction on r actor site criteria. Firs. t , I would likc to c.cte, th'. ': provi:. c. c; 100rk-1 r
I 100.11 (d (3) > w;:ich Genic wi th c;tchlich .. x.rc.latic: a .:: c'i o t u c c :., .
, is dependent on ;Lsactions (a) (2) of 20Cc , .::.11. Lx:.c..i.cn 103.11 (c)-
(2) deals with cmc.bli shing lo . pgulaticc. . .m.
As ,ccu m d in the AEC re3W nory s u.J 's Safe ty ic. , ,,_ s:, th.,
low population zona distance is one n11c2 M :. := cts the ryidelincs of 4
l 100Fn 100.11 (a)(2) as shoua on y;c 4 4 of 'the scfety-Evcluction. Since i the lou ponulation zonc distenec catisfict L:
4 provi r.ioc.e of 10CFR.100.11 (c)(2), this distance ic used directly to de tcrmine th. :
.cpulatior center distenec w. cc:ordcnce uith 10 C"I n 100.11( )(3), which s;ctec, "A pop-ulation ecatcr distance of at Icest one cad one-tFird tinas the W ;:. re fro; the rece tor to the outer hourdcry o f- th; lw populction zone. Ir applyi ng, :.1. aide, due considerction shoLid bc givcn ' to the pc; ;ction i
distributica uithin the populction conte;. Uhcrc verj Icrge citice c'e involved, c greater distance may be racerccry beccucc of' tot:1 integrcted
,j pcpulation doce conrideration." This .2: Jc a t for the Monticcilo. cite f thy reguired population ecn:cr distance would -hnvc to be at lenet c: cud one-thi rd tiles from.the reac tor. As defined in 3 CT~.: .- 100. 3, "ropulction t
ccnter distence nenns tu' distance frm; the cecetor to the .ncarest boundary T
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, of a densely populated center containing noro than about 25,000 residents."
There is no such population center one and one-third miles from the reactor.
St. Cloud with a population of approxirnately 33,000 is 22 miles from th'e 1'
site. The distanco of the Tuin City metropolitan area is approximately 30 miles from the site, and reets the requirements of 10 CFR 100.11 (a)(3).
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