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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 ML20217K3161999-10-19019 October 1999 Forwards Amend 195 to License DPR-61 & Safety Evaluation. Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted CY-99-137, Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam1999-10-12012 October 1999 Notifies NRC of Intent to Apply Haddam Neck Plant 10CFR50 App B,Qa Program to Activities Related to Development of ISFSI at Haddam DD-99-11, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 9910041999-10-0808 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 991004 ML20212L1261999-10-0404 October 1999 Forwards Viewgraphs Presented by Licensee at 990923 Meeting with Nrc,In Response to Request 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 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 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 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 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 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 ML20212D0341999-09-20020 September 1999 Expresses Appreciation for Accepting NRC Request for Tour of Haddam Neck Facility During on 991014.Invites R Mellor to Participate in NRC 1999 Decommissioninng Power Reactor Work- Shop:Nrc Insp Program at Decommissioning Power Reactors 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 CY-99-111, Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update1999-09-0202 September 1999 Submits Clarification of Changes Made to Connecticut Yankee QA Program,Per Util 990810 Submittal.Change Will Be Submitted to NRC in Dec 1999 as Part of Annual Update 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 ML20211E8051999-08-20020 August 1999 Forwards Insp Rept 50-213/99-02 on 990420-0719.No Violations Noted.Completion of Corrective Actions for Spent Fuel Bldg Ventilation Issues Adequate 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 ML20210J6021999-08-0202 August 1999 Informs That Info Re Orise Technical Survey Assistance to NRC at CT Yankee Is to Include Copies of Listed Documents CY-99-048, Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls1999-07-29029 July 1999 Forwards Cyap Rept CY-HP-0031,Rev 0, Bounding Dose Assessment for Offsite Radioactive Matls 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. CY-99-066, Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors1999-07-20020 July 1999 Forwards Revised Plan for Recovery of Licensed Matl from Offsite Locations.Completion of Implementation of Plan During Summer of 1999 Is Planned,Contingent on Support Extended by Property Owners,Weather & Uncontrolled Factors 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 ML20210C1491999-07-0101 July 1999 Responds to ,Which Responded to NRC Ltr & NOV & Informs That Engagement in Any Similar Wrongdoing in Future May Result in More Significant Enforcement Action. No Further Action Will Be Taken at This Time ML20209C3911999-06-30030 June 1999 Forwards TS Page 6-3 for Haddam Neck Plant 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 ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195F9011999-06-0909 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp 50-213/98-06 on 990226. Util Did Not Agree with Disposition of Issue Cited as Severity Level IV Violation.Violation Will Be Noncited ML20195H3591999-06-0202 June 1999 Responds to NRC Re Violations Noted in Insp of License DPR-61.Corrective Actions:Disciplinary Actions Were Taken by Util Against Jm Foley & Individual & Departmental Emphasis Is Placed on New HP Stds & Expectations ML20207E9031999-06-0202 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Mt Masnik Will Be Section Chief for Haddam Neck.Organization Chart Encl 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 ML20207B9301999-05-25025 May 1999 Responds to 990114 Correspondence Re Changes to Plant Defueled Physical Security Plan Rev 1 Submitted Under 10CFR50.54(p).Implementation of Changes Subj to Insp to Confirm Changes Have Not Decreased Security Plan ML20207G1761999-05-21021 May 1999 Forwards Insp Rept 50-213/99-01 on 980119-990419 & Closure of CAL 1-97-010.No Violations Noted.Conduct of Activities Associated with Control of Radiological Work at Haddam Neck Generally Characterized as Careful & Thorough 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 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 ML20217K3161999-10-19019 October 1999 Forwards Amend 195 to License DPR-61 & Safety Evaluation. Amend Deletes Certain TSs Either No Longer Applicable to Permanently Shutdown & Defueled State of Reactor or Duplicate Regulatory Requirements ML20217G0711999-10-13013 October 1999 Forwards Insp Rept 50-263/99-12 on 990913-17.No Violations Noted DD-99-11, Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 9910041999-10-0808 October 1999 Informs That Time Provided by NRC Regulation within Which Commission May Act to Review Director'S Decision (DD-99-11) Expired & That Commission Declined Any Review.Decision Became Final Action on 991004 ML20212L1261999-10-0404 October 1999 Forwards Viewgraphs Presented by Licensee at 990923 Meeting with Nrc,In Response to Request 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 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 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 ML20212D0341999-09-20020 September 1999 Expresses Appreciation for Accepting NRC Request for Tour of Haddam Neck Facility During on 991014.Invites R Mellor to Participate in NRC 1999 Decommissioninng Power Reactor Work- Shop:Nrc Insp Program at Decommissioning Power Reactors 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 ML20211E8051999-08-20020 August 1999 Forwards Insp Rept 50-213/99-02 on 990420-0719.No Violations Noted.Completion of Corrective Actions for Spent Fuel Bldg Ventilation Issues Adequate ML20210Q0341999-08-0404 August 1999 Forwards SE Granting Licensee 980724 Relief Request 10 Re Third 10-year Interval ISI Program Plan,Entitled, Limited Exam ML20210J6021999-08-0202 August 1999 Informs That Info Re Orise Technical Survey Assistance to NRC at CT Yankee Is to Include Copies of Listed Documents 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 ML20210C1491999-07-0101 July 1999 Responds to ,Which Responded to NRC Ltr & NOV & Informs That Engagement in Any Similar Wrongdoing in Future May Result in More Significant Enforcement Action. No Further Action Will Be Taken at This Time ML20195F9011999-06-0909 June 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp 50-213/98-06 on 990226. Util Did Not Agree with Disposition of Issue Cited as Severity Level IV Violation.Violation Will Be Noncited ML20207E9031999-06-0202 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Mt Masnik Will Be Section Chief for Haddam Neck.Organization Chart Encl ML20207B9301999-05-25025 May 1999 Responds to 990114 Correspondence Re Changes to Plant Defueled Physical Security Plan Rev 1 Submitted Under 10CFR50.54(p).Implementation of Changes Subj to Insp to Confirm Changes Have Not Decreased Security Plan ML20207G1761999-05-21021 May 1999 Forwards Insp Rept 50-213/99-01 on 980119-990419 & Closure of CAL 1-97-010.No Violations Noted.Conduct of Activities Associated with Control of Radiological Work at Haddam Neck Generally Characterized as Careful & Thorough 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 ML20206R7221999-05-12012 May 1999 Refers to Investigation 1-97-031 on 970616-0718 & Forwards Nov.Investigation Found That Recipient Deliberately Did Not Follow Radiation Protection Procedures,Falsified Documents & Provided Incomplete & Inaccurate Info to NRC ML20206R7021999-05-12012 May 1999 Refers to Investigation 1-97-008 Conducted by Region I & Forwards Notice of Violation.Investigation Found That Recipient Deliberately Attempted to Conceal Release of Contaminated Video Equipment ML20206R8051999-05-12012 May 1999 Responds to 3 Investigations,Repts 1-97-031,008 & 1-98-008 Between 970314 & 980722 as Well as Insp Conducted Between 980720 & 1102.Forwards Synopsis of 3rd OI Investigation 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 ML20206C8631999-04-28028 April 1999 Forwards Amend 194 to License DPR-61 & Safety Evaluation. Amend Authorizes Relocation of Requirements Related to Seismic Monitoring Instrumentation from TSs to Technical Requirements Manual ML20206A6871999-04-22022 April 1999 Informs of Completion of Review of Re Nepco in Capacity as Minority Shareholder in Vermont Yankee Nuclear Power Corp,Yaec,Myap & Connecticut Yankee Atomic Power Co 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 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 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 IR 05000213/19960121999-04-0505 April 1999 Discusses NRC Insp Repts 50-213/96-12 & 50-213/98-04 on 961102-27 Re Airborne Radioactivity Contamination Event That Occurred in Fuel Transfer Canal & Reactor Cavity in Nov 1996.Notice of Violation Encl ML20205J7931999-04-0505 April 1999 Discusses NRC Insp Repts 50-213/96-12 & 50-213/98-04 on 961102-27 Re Airborne Radioactivity Contamination Event That Occurred in Fuel Transfer Canal & Reactor Cavity in Nov 1996.Notice of Violation Encl 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 ML20207B6641999-02-26026 February 1999 Forwards Insp Rept 50-213/98-06 on 981103-990118 & Notice of Violation Re Locked High Radiation Area Doors That Were Found Unlocked by Staff.Security Program Was Also Inspected ML20203H9621999-02-17017 February 1999 Responds to to Dk Rathbun Which Forwarded Number of Questions from Constituent Re Spent Fuel Decommissioned Nuclear plants.NUREG-1628, Staff Responses to Frequently Asked Questions Re Decommissioning of NPPs Encl.W/O Encl 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 1999-09-09
[Table view] |
Text
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Deth Reading V RP51 Reading .
Orig:H8teele !
""I I' 1 R. S. Boyd ;
D. R. Muller Dooket Nos.30-213 ai 30 26 si? i
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Mr. Frank Sehroeder , .Ii' 8~-/ ' #*
Manager,-Water Itsester Safety J' .
Program Offies 6
Phillipe Petroleum Ceepany tlt * #c P. O. Dez 2067 Idaho Falle, Idahe_ _ 83401 Dear Mr. Schroeder Copies of safety evoluations listed below are encioned for your informations i
- 1. Safety Svaluaties by the Division of Roaster 1 Licenstag in the matter of Canaseticut Yankee -
Atomie Power Company, dated May 11,1967
- 2. Safety Evaluaties by the Division of Remotor U - 4== in the matter of Northern States Power Campsey, Montieelle Nealear Generating Plant, Unit 1, dated May 4,-1967 ,
aineerely yours,
'~
Original mgnedg IL S Wde h 3. Boyd, Assistant Direeter for Remoter Projects Division of Hometer Lisensing Emeleeures
- 1. Safety Evaluaties, Casa-Yankee
- 2. Safety Kyminaties, NSP - Mestiselle o
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12720 Twinbrook Parkway Rockville, Maryland 20852 April 2, 1968 Dr. Dean E. Abrahamson 1092 25 Ave., S. W.
Minneapolis, Minn. 55414
Dear Dr. Abrahamson:
This is in reply to your ictter of March 2, 1968, in which you raised various technical quest.ons concerning the Monticello reactor, our participation in its evaluation, and the release of tritium from it and reactors in general.
As stated in " Surveillance of Nuclear Power Reactors,"
Public Health Reports, Vol. 82, No. 10, pages 906, we recommended that states conduct pre-operational surveillance for a period of one year primarily to evaluate plant operations after startup. We feel that the Minnesota Health Department, by virtue of past experience, need not conduct a pre-operational program of this extent. The main objective of the pre-operational survey at Monticello is to establish the icvels of environmental radioactivity at the time of startup and any anomalies that exist; the period of time over which this is done is relatively unimportant. Therefore, the Minnesota Health Department's plan to establish these levels is, in our -
opinion, adequate primar!.ly because they presently possess sufficient experience to conduct the necessary operational surveillanc e .
To our knowledge, the State of Pennsylvania is the only state to impose stricter limits on reactor operators than the AEC.
This practice, however, has not been based on a concern that the levels generally released from a reactor are high or unsafe, but merely on the basis that such a facility does nec need a limit as high as an AEC discharge limit in order to operate. Pennsylvania limits the total annual tritium discharge from Shippingport to the amount it is calculated to produce. On this basis the average concentration in condenser V
1
- 2-A cooling water is in order of magnitude below the discharge concentrations permitted by the AEC. The upper limit used by_all states thus far has been the 10 CFR 20' values or
~
equivalent values as given by the ICRP. As a Federal agency we examine nuclear facilities to insure that discharge concentrations conform with the PHS Drinking Water Standards l and that guidelines of the FRC are met. Enclosud are copies '
of the Drinking Water Standards and FRC Reports 1 and 2. A reprint entitled, " Digest of Protection Standards and State ,
Regulations for Radioactivity in Water," is also enclosed. [ '
The Monticello reactor will use zirconium clad fuel elements.
~
t The boron shim plates as far as we can tell will be clad with stainless steel though this may change in light of boron being a primary source of tritium. The R&D aimed at determining a tritium escape coefficient for Zr clad fuel is yet incomplete. Battelle Manorial Institute is doing; work ,
on this subj ect. Members of our staff have, through personal communication 'vith the people at Battelle, been informed that the tritium tends to react with the Zr and form a hydride '
resulting in a lower escape coefficient than is the case with stainless steel. This would tend to agree with the tritium concentration data printed by Smith in his paper. You apparently used the Yankee primary coolant concentration data in your calculations. Yankee uses stainless steel clad. fuel and is a PWR. A PWR uses a chemical shim (boric acid is added to the primary coolant) whereas a BWR uses cladded shim plates. Therefore, data from a BWR which uses Zr clad fuel could be used in calculating tritium discharges from Monticello '
but data from a reactor with a different configuration is not t
appropriate.
Attached is a calculation giving.the tritium unit conversion and a brief evaluation of the dose from tritium, which we -
-- hope answers some of your specific questions.
t l
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3-l-- We appreciate your concern on this subject, and wish to reiterate that we will review the Monticello site in light of the discharge limits when they are submitted to assure l
that no public health problems exist relative to the reactor operation.
Sincerely yours, Ernest D.11arward, Chief Nuclear Facilities Section Enrironmental Surveillance _
and Control Program.
Enclosures
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. J I. TRIT!UM UNIT CONVER$10N J .- . _ _ . 3 18 1 One Tritium Unit (TU) = 1 atom H/10 atoms 11 water contains f
?
23 22 2 (6.0225x10 /18.015 = 6.686x10 atoms of hydrogen por gram. !
M Assuming a maximum density of Ig/ml (3.98 c), then 1 TU corresponds. .
i l- _
10 3
-J to (1 TU)(6.686x1022 ,t,c, IN/gm)(1gm/ml)(1/10 atoms H/
1 atom !! TU1 '= N' = 6.6859x10 atoms of tritium por ol.
4 If the half l life of tritium is taken as 12.262 years (C.M. Lede cr, cc.al., ;
Table of Isotopes, Wi'.cy,1967) then a (12.262 years)(3.156x10 sec/ycar) = 38.70x10 s 7
The docay constant is A = in 2/Tta .
t
- i-O.6932/3/87x10 8 = 1.791x10
- 9 see
-l' or dis /sce atom. Tho' activity 0
l (AN) corresponding to 1 TU is 31.791x10~9 dis /sec atom)(6.696x10
~5 atoms) = 11.99x10 dis /sce m1' ,
~to' 1 pico curic (pC1) = 10 curies .
10 l 1 curic = 3.7x10 dis /sce i -n ~ 3. N n &:r.frec ,
e ,
. ....c.c. ,
- i. - '
- . :N. :' ' M .< n: ml.::. x' 2~~ itslssa 7Ci =
~
- 3. 2 4>.10 pCi/mlj or l1 TU = 3.24 pCi H/literHOj 2 This value probably differs from the 3.3 pCi/ liter in Smith's .g paper due to a different value for the half-life,
&p 9p La II. EVALUATION OF THE DOSC FROM TRITIUM If one assumes that the body water reached equilibrium
i trithm icval of the intaka then fcr & constant inecke'of a level
"~
of ITU (3.24,pci H per liter of 'iater) the body water would have
~ ~
a - n;i'. ip; e f 277r:st=: f.; '.h12-5 3g 7, l
' *This equilibrium should be reached fairly rapidly (~ -100 days) due to the reported effective half-life of triciated water in the body-of 12 days. .
.--m..
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4 y e,e,- ,-y-,,y,q,--- PW ==rn-v'==ew=---se-+> v --rvr-- c - -e -e 'r e eW w e m G N s-+*-#- 'T* 'r-*--~~m--mart--*m=*=e-aw a ea-+ r v m---~s*
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The maximum beta particle energy emitted by tricium decay ic 0.018 McV. The average beta cacrgy should be approximately 1/3 of this or O.005 McV '(6KcV) . The dose to the oody water from this activity ;
-6 'crg/McV)(1.2x10'0 dis /sec g)(6x10'3 Hov/
icyc1 would bc . 60x10 dis)'(100 crg/g rad =1.15x10 rads /sc$ .15x10"I0 rad /sec)
~7 H'
I (3.156x10 sec/ year) = 3.635x10 . rad /ycar = 3.635x1 h 6 year ,
'~~
Therefore 1 TU = 0.364x10*3 mrad /ycar to body water
........__......,_m..._-.__.... ...,.. .
4 If a quality factor
- of 3 is assumed for the low energy beta
~3 mrad /ycar)(3 mrce/ mrad) particles of tritium then TU (0.364x10 9
I 1 TU = 1.092x10-3 mrem /ycar;
~ ~~
l A constant intake of 1000 TU =_1.092_ mrem /ycar ~,1_ mrem /yoarj _
These calculations cay not be strictly accurate when applied to i
calculation of soft tissue dose for .the following reasons: .
i
! 1. The dose to cellular components other than vator was negicceed.
- 2. Tissues vary in their water content
- 3. The biological half-life of tritium encorporated into cellular t
molecules might be greater than the biological half-life of tritium in body water.
~
- 4. The relative biological offect of tritium encorporated in DNA f 4 and other cellular components may be greater than cormaonly. ,
.I assumed on the basis of specific ioni;:ation.
I o
' *This is the current- terminology for the rad to rem conversion factor rather than RBE which now only applies to a specific effccc. -
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- 5. There may be a possibility of tritium enrichment in tissues due to differences in membrano diffusion and chemical reaction rates caused by the mass difference between 1!TO .
and 110. It is known, for example, that the sap of weepin?.
2 willow trecs is slightly enriched in deuterium ( 11) compared to the norr.a1 isotopic ratio of 11/ 11 found in water.
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