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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20205N9871999-04-14014 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990308-11 ML20203G0081999-02-12012 February 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 981102-06 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20149D7851997-07-14014 July 1997 Notification of Significant Licensee Meeting W/Util on 970731 in Arlington,Tx to Discuss Case Studies (Response Time & Reactor Feedwater Pump Trip Test) & Common Themes ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20134P5931997-02-21021 February 1997 Forwards Order Imposing Civil Monetary Penalty for Transmittal to Ofc of Fr for Publication.W/O Encl ML20132F5421996-12-19019 December 1996 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961007-11 ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20203B9891995-11-20020 November 1995 Discusses OI Rept 4-95-032 Re Alleged False Statements by Fire Watches to NRC Inspectors.Oe Will Consider Matter Closed from Enforcement Perspective Unless Different View Received within 3 Wks of Date of This Memo ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20236L5631994-08-10010 August 1994 Responds to Former Region V 930422 Request for NRR Evaluation of WPPSS Practices Associated W/Testing RHR Sys While Aligned in SPC Mode ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20247G1561989-05-15015 May 1989 Forwards Director'S Decision 89-03 in Response to 2.206 Petition Re BWR Stability.Petition Filed by Hiatt on Behalf of Ocre Expressing Concerns Re 890309 Power Oscillattion Event & Requested Action W/Respect to All BWRs ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195G7981987-07-31031 July 1987 Partially Deleted Memo Forwarding SALP Rept & Recommendations Re NRC Actions for Plant.W/O Encl IR 05000397/19870061987-07-0101 July 1987 Forwards Draft SALP Rept 50-397/87-06 for Feb-May 1987 for Review.Comments Requested at SALP Board Meeting Schedule for 870707 in Region V.Update of Tables 1-4 Included in Draft. W/O Rept ML20236B1451987-06-18018 June 1987 Forwards Response to DF Kirsch 870507 Memo Requesting Performance Analysis Info for Input to Facility SALP Rept. Review Results Provided in Encl.Encl Withheld ML20214M1381987-05-26026 May 1987 Provides Enforcement Guidance to Regions for Issues Re Control Room Habitability/Control Room Emergency Ventilation Sys Deficiencies.Summary of Plants Reviewed & Documents Describing Findings Encl ML20195G7931987-05-12012 May 1987 Forwards Insp & LER Data Tables for Use in Preparing Performance Analyses for Salp,Per DF Kirsch 870507 Memo. Tables Subj to Review & Comment Until SALP Process Complete. W/O Encls ML20214A0311987-05-12012 May 1987 Notifies of 870514 Briefing on Licensing & Operational Status of Plants Assigned to Project Directorate V,Including Diablo Canyon,Palo Verde,Rancho Seco,San Onfore,Trojan & WPPSS 2 ML20212M8601987-03-0909 March 1987 Forwards SER Re Concerns Identified in Plant Fire Protection Program,As Described in FSAR Through Amend 33.Concerns Resolved Except for Listed Items,Including Adequacy of Safe Shutdown Procedures.Review Excluded Amend 37 Items ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215G1361986-10-14014 October 1986 Summary of 861006 Operating Reactor Events Meeting 86-35 Re Events Since Last Meeting on 860929.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Attendance List & Viewgraphs Encl ML20215F2751986-10-0606 October 1986 Forwards Action Timetable Re Coordinated Approach to Resolution of Fire Protection Issues at Facility ML20209A8611986-09-0202 September 1986 Forwards Matls Needed to Complete Assignment During Emergency Preparedness Exercise on 860916-19.W/o Encl IR 05000397/19860121986-08-25025 August 1986 Notification of 860828 Meeting W/Util in Walnut Creek,Ca to Discuss Apparent Violations Involving Equipment Qualification (50-397/86-12),Region V Team Insp 50-397/86-11 & Control of Combustible Matls ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl ML20207J2451986-07-16016 July 1986 Forwards Request for Addl Info Re Util Application to Amend Tech Spec 4.6.4.1 Concerning Drywell Vacuum Breakers,For Transmittal to Licensee.Receipt of Info After 860731 Will Require Rev to 860831 Anticipated Review Completion Date ML20058K6041986-07-0303 July 1986 Informs of Telcon on Status of EA-86-110 Re Health Physics/ Emergency Planning & EA-86-070 Re Fire Protection ML20203B0881986-07-0202 July 1986 Forwards SALP Rept for Feb 1985 - Jan 1986,for Review.Salp Board Rated Licensee Performance Category 1 in Area of Outages & Category 2 in All Other Areas Except Fire Protection.W/O Encls ML20236Y1311986-04-25025 April 1986 Forwards List of Primary Containment Isolation Valves & Valve P&ID Locations as Referenced in Util 860117 & 0218 Request for Amend to License NPF-21 ML20198D7151986-04-24024 April 1986 Forwards Insp Rept 50-397/86-05,notice of Violation & Enforcement History,For Consideration & Action.Civil Penalty Unwarranted Since Fire Watches Immediately Posted & Safety Significance of Fire Loadings Limited ML17278A7091986-04-16016 April 1986 Advises That Deletion of Technical Memo 1227 Overlooked During Issuance of Amend 31 to Fsar.Memo Deleted as Result of Incorporation of Scn 83-135 Into Amend ML20195G7731986-03-14014 March 1986 Forwards Draft SALP Rept for Feb 1985 - Jan 1986,for Review & Comment at 860319 Meeting at Region V.Updated Tables 1 & 4 Also Encl.W/O Encl ML20154K1511986-03-0303 March 1986 Notifies That SALP Board 860312 Meeting Rescheduled for 860319 at Region V.Deviation from Instruction 0701 to Permit a Toth Attendance at B&W Training Course on 860303-15 in Best Interest of SALP Process ML20199D1311986-02-19019 February 1986 Informs That Proposed Recirculation Pump Vibration Testing Plan Acceptable,Based on Licensee Testing Procedure & Supporting Stress Analysis ML20203B1101986-02-13013 February 1986 Forwards Assessment of Lers,Including Results for Input Into SALP Rept for Feb 1985 - Jan 1986.LERs of Above Average Quality ML20195G7801986-02-0909 February 1986 Forwards Data Tables for Use in Preparing Performance Analysis for Salp.Insp Results & LERs Occurring During Last Month of SALP May Not Be Included in Tables.Tables Subject to Review & Comment Until SALP Process Completed.W/O Encl ML20215N3041986-01-30030 January 1986 Provides Summary of Review of Past Experience as Related to Handling of Nonradiological Issues.State of Wa Notified by NRC of Industrial Safety Concerns at Facility.Dm Kunihiro 851213 Memo to State of Wa Encl ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20149M8611986-01-24024 January 1986 Discusses 851202-06 Observation of Seven INPO Members & Two Industry Peer Evaluators During Conduct of Site Visit to Evaluate Three Training Programs at Plant.Significant Milestones Toward Accreditation of Training Programs Listed ML20198H2291986-01-22022 January 1986 Requests Date & Subj of Application for OL Issued on 840413.Info Needed to Complete Review of 850318 Transmittal of License Fee Data & Assessment of Fees & Contractual Costs Through 841222 ML20198G8771986-01-16016 January 1986 Forwards Brief Description & Evaluation of Util 850911 Proposed Tech Spec Change to Revise Composition of Corporate Nuclear Safety Review Board.Proposed Change Acceptable ML20198G8291986-01-0606 January 1986 Forwards Draft Response to 850718 Memo Re Inspector Feedback /Request for Technical Assistance on NUREG-0737,Item II.F.1.Response Based on Review of Util Position on Iodine plate-out ML20141E9281985-12-26026 December 1985 Recommends Survey of Plants Re Licensee Review of Preservice Insp Rept & Submittal of Relief Requests.Relief Requests from Preservice Insp Should Be Submitted Before Issuance of OL & Plant Startup to Permit NRC Review 1999-04-14
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20205N9871999-04-14014 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 990308-11 ML20203G0081999-02-12012 February 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 981102-06 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20149D7851997-07-14014 July 1997 Notification of Significant Licensee Meeting W/Util on 970731 in Arlington,Tx to Discuss Case Studies (Response Time & Reactor Feedwater Pump Trip Test) & Common Themes ML20137C9201997-03-20020 March 1997 Forwards Documentation of Meeting Conducted in Region 4 Office on 970225 to Discuss NRC Enforcement Policy as Applied to Nonescalated Enforcement ML20134P5931997-02-21021 February 1997 Forwards Order Imposing Civil Monetary Penalty for Transmittal to Ofc of Fr for Publication.W/O Encl ML20132F5421996-12-19019 December 1996 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 961007-11 ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20203B9891995-11-20020 November 1995 Discusses OI Rept 4-95-032 Re Alleged False Statements by Fire Watches to NRC Inspectors.Oe Will Consider Matter Closed from Enforcement Perspective Unless Different View Received within 3 Wks of Date of This Memo ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20236L5631994-08-10010 August 1994 Responds to Former Region V 930422 Request for NRR Evaluation of WPPSS Practices Associated W/Testing RHR Sys While Aligned in SPC Mode ML20056E5141993-08-12012 August 1993 Submits SALP Schedule for FY94 Per Mgt Directive 8.6 ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20247G1561989-05-15015 May 1989 Forwards Director'S Decision 89-03 in Response to 2.206 Petition Re BWR Stability.Petition Filed by Hiatt on Behalf of Ocre Expressing Concerns Re 890309 Power Oscillattion Event & Requested Action W/Respect to All BWRs ML20245B6421989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Steam Line Flooding.Though Little Actual Damage Experienced,Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20245B6531989-04-15015 April 1989 Forwards Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Events Determined to Involve Deficiencies in Control Sys ML20245B6191989-04-15015 April 1989 Forwards Evaluation Rept Re BWR Overfill Events Resulting in Steam Line Flooding.All Events Included Reactor Depressurization Followed by Uncontrolled Condensate or Condensate Booster Pumps Injection or Both ML20245B7501989-04-15015 April 1989 Forwards Engineering Evaluation Rept on BWR Overfill Events Resulting in Flooding of Steam Lines.Potential for Equipment Damage Believed to Exist & Any Damage Occurring Should Be Fixed Prior to Restart ML20147E3621988-02-28028 February 1988 Summary of 880223 Operating Reactors Events Meeting 88-008. List of Attendees,Tabulation of long-term Followup Assignments to Be Completed & Summary of Reactor Scrams Encl ML20195G7981987-07-31031 July 1987 Partially Deleted Memo Forwarding SALP Rept & Recommendations Re NRC Actions for Plant.W/O Encl IR 05000397/19870061987-07-0101 July 1987 Forwards Draft SALP Rept 50-397/87-06 for Feb-May 1987 for Review.Comments Requested at SALP Board Meeting Schedule for 870707 in Region V.Update of Tables 1-4 Included in Draft. W/O Rept ML20236B1451987-06-18018 June 1987 Forwards Response to DF Kirsch 870507 Memo Requesting Performance Analysis Info for Input to Facility SALP Rept. Review Results Provided in Encl.Encl Withheld ML20214M1381987-05-26026 May 1987 Provides Enforcement Guidance to Regions for Issues Re Control Room Habitability/Control Room Emergency Ventilation Sys Deficiencies.Summary of Plants Reviewed & Documents Describing Findings Encl ML20195G7931987-05-12012 May 1987 Forwards Insp & LER Data Tables for Use in Preparing Performance Analyses for Salp,Per DF Kirsch 870507 Memo. Tables Subj to Review & Comment Until SALP Process Complete. W/O Encls ML20214A0311987-05-12012 May 1987 Notifies of 870514 Briefing on Licensing & Operational Status of Plants Assigned to Project Directorate V,Including Diablo Canyon,Palo Verde,Rancho Seco,San Onfore,Trojan & WPPSS 2 ML20212M8601987-03-0909 March 1987 Forwards SER Re Concerns Identified in Plant Fire Protection Program,As Described in FSAR Through Amend 33.Concerns Resolved Except for Listed Items,Including Adequacy of Safe Shutdown Procedures.Review Excluded Amend 37 Items ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215G1361986-10-14014 October 1986 Summary of 861006 Operating Reactor Events Meeting 86-35 Re Events Since Last Meeting on 860929.Assignees Should Review Identified Responsibilities & Completion Dates & Advise If Dates Cannot Be Met.Attendance List & Viewgraphs Encl ML20215F2751986-10-0606 October 1986 Forwards Action Timetable Re Coordinated Approach to Resolution of Fire Protection Issues at Facility ML20209A8611986-09-0202 September 1986 Forwards Matls Needed to Complete Assignment During Emergency Preparedness Exercise on 860916-19.W/o Encl IR 05000397/19860121986-08-25025 August 1986 Notification of 860828 Meeting W/Util in Walnut Creek,Ca to Discuss Apparent Violations Involving Equipment Qualification (50-397/86-12),Region V Team Insp 50-397/86-11 & Control of Combustible Matls ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl ML20207J2451986-07-16016 July 1986 Forwards Request for Addl Info Re Util Application to Amend Tech Spec 4.6.4.1 Concerning Drywell Vacuum Breakers,For Transmittal to Licensee.Receipt of Info After 860731 Will Require Rev to 860831 Anticipated Review Completion Date ML20058K6041986-07-0303 July 1986 Informs of Telcon on Status of EA-86-110 Re Health Physics/ Emergency Planning & EA-86-070 Re Fire Protection ML20203B0881986-07-0202 July 1986 Forwards SALP Rept for Feb 1985 - Jan 1986,for Review.Salp Board Rated Licensee Performance Category 1 in Area of Outages & Category 2 in All Other Areas Except Fire Protection.W/O Encls ML20236Y1311986-04-25025 April 1986 Forwards List of Primary Containment Isolation Valves & Valve P&ID Locations as Referenced in Util 860117 & 0218 Request for Amend to License NPF-21 ML20198D7151986-04-24024 April 1986 Forwards Insp Rept 50-397/86-05,notice of Violation & Enforcement History,For Consideration & Action.Civil Penalty Unwarranted Since Fire Watches Immediately Posted & Safety Significance of Fire Loadings Limited ML17278A7091986-04-16016 April 1986 Advises That Deletion of Technical Memo 1227 Overlooked During Issuance of Amend 31 to Fsar.Memo Deleted as Result of Incorporation of Scn 83-135 Into Amend ML20195G7731986-03-14014 March 1986 Forwards Draft SALP Rept for Feb 1985 - Jan 1986,for Review & Comment at 860319 Meeting at Region V.Updated Tables 1 & 4 Also Encl.W/O Encl ML20154K1511986-03-0303 March 1986 Notifies That SALP Board 860312 Meeting Rescheduled for 860319 at Region V.Deviation from Instruction 0701 to Permit a Toth Attendance at B&W Training Course on 860303-15 in Best Interest of SALP Process ML20199D1311986-02-19019 February 1986 Informs That Proposed Recirculation Pump Vibration Testing Plan Acceptable,Based on Licensee Testing Procedure & Supporting Stress Analysis ML20203B1101986-02-13013 February 1986 Forwards Assessment of Lers,Including Results for Input Into SALP Rept for Feb 1985 - Jan 1986.LERs of Above Average Quality ML20195G7801986-02-0909 February 1986 Forwards Data Tables for Use in Preparing Performance Analysis for Salp.Insp Results & LERs Occurring During Last Month of SALP May Not Be Included in Tables.Tables Subject to Review & Comment Until SALP Process Completed.W/O Encl ML20215N3041986-01-30030 January 1986 Provides Summary of Review of Past Experience as Related to Handling of Nonradiological Issues.State of Wa Notified by NRC of Industrial Safety Concerns at Facility.Dm Kunihiro 851213 Memo to State of Wa Encl ML20151Q9751986-01-29029 January 1986 Requests Identification of Div Contact for Regional Insp Team Leaders to Arrange NRR Alternative Shutdown & Fire Protection Reviewer Technical Assistance on region-based post-fire Safe Shutdown Insps.Schedule of Insps Submitted ML20149M8611986-01-24024 January 1986 Discusses 851202-06 Observation of Seven INPO Members & Two Industry Peer Evaluators During Conduct of Site Visit to Evaluate Three Training Programs at Plant.Significant Milestones Toward Accreditation of Training Programs Listed ML20198H2291986-01-22022 January 1986 Requests Date & Subj of Application for OL Issued on 840413.Info Needed to Complete Review of 850318 Transmittal of License Fee Data & Assessment of Fees & Contractual Costs Through 841222 ML20198G8771986-01-16016 January 1986 Forwards Brief Description & Evaluation of Util 850911 Proposed Tech Spec Change to Revise Composition of Corporate Nuclear Safety Review Board.Proposed Change Acceptable ML20198G8291986-01-0606 January 1986 Forwards Draft Response to 850718 Memo Re Inspector Feedback /Request for Technical Assistance on NUREG-0737,Item II.F.1.Response Based on Review of Util Position on Iodine plate-out ML20141E9281985-12-26026 December 1985 Recommends Survey of Plants Re Licensee Review of Preservice Insp Rept & Submittal of Relief Requests.Relief Requests from Preservice Insp Should Be Submitted Before Issuance of OL & Plant Startup to Permit NRC Review 1999-04-14
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Text
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DOCKET NUMBER: 50-397 RESPONSIBLE BRANCH: Envireemental Projoete Braneh No. 2 FROJRCT LEADER: M. Grotenhuis REQUESTED COMPLETION DATE: September 20, 1972 DE8CRIPTION OF RESPONSE: Radweste Sectfon for Envirvemental Statement REVIEW STATUS: Completed In response to your request, we have prepared and attached to this memo the radweste section for the Envirommental Statement for Easford 2 Nuclear Power Station. The writeup and soures terms were prepared by R. Smith with input from ORNL.
The source terms were informally transmitted to the Radiological Assese-ment Braneh en July 6, 1972. The Sl essy prints of the liquid and gaseous waste treatment system have been provided to your staff.
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(Tedesco, u Director for Centainment sty Direeterate of Licensing
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Waste Treatment Section for Environmental Statement Hanford-2 Nuclear Fower Station 3.5 Radioactive Waste Systems During the operation of Hanford-2 Nuclear Power Station, radio-active material is produced by fission and by neutron activation reactions of metals and other material in the reactor coolant system.
Small amounts of gaseous and liquid radioactive wastes will enter the effluent streams and then be processed within the station to minimize the radioactive nuclides that will ultimately be released to the atmo-sphere and into the Columbia River under controlled and monitored conditions. The radioactivity that may be released during operation of the station will be in accordance with the Commission's regulations, as set forth in 10 CFR Part 20 and 10 CFR Part 50.
The waste handling and treatment systems to be installed at the station are discussed in the Preliminary Safety Analysis Report and in the Applicant's Environmental Report, both dated August 1971.
3.5.1 Liquid Waste
, Liquid wastes which may be subject to possible radioactive con-l l tamination will be collected in the liquid radwaste system where they will be monitored, stored, and processed for re-use or for discharge ~
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f to the cooling tower blowdown stream. The liquid radwaste system will be divided into several subsystems so that the liquid wastes from various sources can be kept segregated and processed separately. Cross connections between these subsystems will provide additional flexibil-ity for processing of wastes by alternate methods. The interrelation-ships of these systems and their interaction with other components'are shown in Figure 3.5.1. The liquid radwastes wil) be classified, col-lected and treated as high purity, low purity, chemical, detergent, sludges or concentrated wastes. The terms "high purity" and " low purity" refer to the conductivity and not radioactivity. Table 3.5.1 lists the principal assumptions used in evaluating the waste treatment systems.
m High purity (low conductivity) liquid wastes will be collected in the waste collector tank, principally from the coolant piping and equipment drains, and processed through a filter and a mixed-bed demineralizer. Af ter processing, the waste will be collected in a vaste sample tank. Normally, it will be transferred from the sample tank to the condensate storage tank for re-use. However, on infrequent occa- g sions a portion of this waste will be processed through a vaste con-centrator (10 gpm) and discharged to the cooling tower blowdown line.
In our evaluation, we assumed that 10% of the annual volume would be evaporated and released and the remaining 90% would be recycled.
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Low purity (high conductivity) liquid wastes will be collected in the floor drain collector tank, principally from the various floor drain sumps. From the floor drain tank the wastes will be processed through a precoat type filter and a mixed-bed demineralizer and col-lected in a sample tank. Normally, these wastes will be routed to the condensate storage tanks for reuse. However, some of wastes may be routed to the chemical waste tanks for processing through the waste concentrator before discharge.
Our analysis considered a daily input into the low purity system of 8,390 gallons at an activity equivalent to 35% of primary coolant and tha~ 15% of this waste will be evaporated prior to being released to the circulating water discharge canal. The remaining 85% of this waste was assumed to be recycled.
Radioactive high conductivity chemical wastes from sampling, laboratory drains, and chemical decontamination solutions will be collected in the chemical waste tanks. taese chemical westes are of such high conductivity as to preclude treatment by ion exchange and will be neutralized and processed through the waste concentrator.
The condensate will be routed to distillate tanks where it will be released to the circulating water discharge canal.
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i Our analysis considered a daily input to this system of 4,300 gallons, including 10% of the equipment drain and 15% of the floor .
drain waste volume. and that 100% of the condensate will be released to the circulating water discharge canal.
Liquid wastes containing detergents or similar cleaning agegts from fuel cask claaning and personnel decontamination will be col-lected in a detergest drain tank. Processing will consist of passing .
the waste through the detergent drain filter to remove solids and concentrating it in one of the two waste concentrators. In our evaluation, we considered the potential effluents from the detergent system to be a small fraction of the waste from the other systems and did not analyze them separately.
Annual releases of fission product radionuclides from Hanford-2 were calculated based on reactor operation at 3458 MWt (maximum power) for 292 full power days. Corrosion product activities were based on operating experience with boiling water reactors. The applicant expects the normal cooling tower blowdown flow to be 4000 gpm. We accepted this dilution flow estimate and, therefore, rather than total curies released, the annual average concentration of radioactive material in the liquid effluents prior to dilution will be the limiting constraint for the annual liquid waste discharges. Based on the assumptions shown in Table 3.5.3, the annual releases of radioactive materials in the
liquid waste were calculated to be a fraction of those values shown in Table 3.5.1 (excluding tritium). To compensate for treatment equipment downtime and expected operational occurrences, the values have been normalized to 0.25 Ci/yr, which limits the annual concentration in the
-8 discharge canal to less than 4 x 10 pCi/ml. Based on our evaluation, we estimate that about 10 Ci/yr of tritium will be released to the '
environment. The applicant estimates that 0.16 Ci/yr of mixed isotopes and 16 Ci/yr of tritium will be released to the environment in the liquid effluent.
3.5.2 Gaseous Waste During power operation cf the plant, radioactive materials released to the atmosphere in gaseous effluents include low concentra-tions of fission product noble gases (krypton and xenon), halogens (mostly iodines), tritium contained in water vapor, and particulate material including both fission products and activated corrosion products.
The major source of gaseous waste activity during normal plant operation will be the offgas from the main steam condenser air ejector. Other sources of gaseous waste include turbine gland seal steam exhaust, of fgases f rom the mechanical vacuum pump, ventilation air released from the radwaste, reactor, and turbine building exhaust
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systems, and purging of the drywell and suppression chamber. A schematic flow diagram of the gaseous waste treatment system is shown in Figure 3.5.2.
Offgas from the main condenser air ejector will flow through one of two catalytic recombiners where the hydrogen and oxygen ,
recombine to form steam which is condensed and returned for use in the plant. The waste gas stream will be sent to a holdup pipe which will be designed to delay the full volume of vaste gases for a -
period of at least 10 minutes to permit the decay of short-lived activity. From the holdup pipe the gases will flow through charcoal beds, after having the gas humidity reduced by moisture separators
! and desiccant dryers. Xenon and krypton activities will be j selectively held up on the charcoal beds. In addition, the charcoal j
will also retain radioactive iodine, and long lived radioicotopes in the particulate form, such as strontium-89, strontium-90, and cesium-137. The applicant estimated 42 days xenon and 46 hours5.324074e-4 days <br />0.0128 hours <br />7.60582e-5 weeks <br />1.7503e-5 months <br /> krypton holdup with 30 scfm air inleakage. In our analysis we assumed that the xenon radioisotopes are delayed 18 days and that the krypton isotopes are delayed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on the charcoal beds with 40 scfm air inleakage into the three-shell condenser. The charcoal ,
delay system will consist of 8 beds, each bed containing about 3 tons of charcoal and will be operated at O'F.
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) .
1 l
The steam air exhaust from the turbine gland seal system will pass through a gland seal condenser where the steam will be condensed !
and the noncondensibles exhausted to the gland seal holdup line.
Steam for the turbine gland seal will be generated using effluent from the condensate demineralizer. Based on using this relatively clean steam for turbine gland seal, no radioisotopic discharges were calculated to be released through this route. .
The mechanical vacuum pump, used during startup, exhausts air.
and radioactive gases from the main steam condenser. Offgases from this system will be discharged to the environment without treatment.
The primary containment (drywell) is normally a sealed volume. .
However, during periods of refueling or' maintenance it may be neces-sary to purge the drywell and suppression chamber and when this occurs, the potential exists for the release of airborne radioactivity to the environment. Normally, the purge releases will not be treated before release to the environment, however, the system will be designed auch that the purge exhaust can be directed to the standby gas treatment system in the event of abnormal air activity levels. In our evaluation, we assumed no treatment before release to the environment. The annual releases from this source is not expected to be a contributing source of activity.
)
i Ventilation air flow will be provided to the reactor building, turbine building, and the radwaste building. Most of the ventilation systems will utilize 100% outside air with no recirculation. Exhaust air from the non-contaminated areas of the reactor building, the rad-waste building, and the turbine building will be exhausted through the roof vent of the buildings without treatment. The potentia 11y' contaminated areas of the reactor building, turbine building, and radwaste building will be filtered through HEPA filters before being discharged to the atmosphere. The annual releases from these sources are not expected to be a contributing source of activity.
Table 3.5.2 shows the anticipated annual release of radio-
)
active materials in the gaseous effluent calculated in our evaluation based upon the conditions listed in Table 3.5.3 The applicant esti-mated that between 300 and 580 curies per year of noble gases and no iodine will be released to the environment in the gaseous effluent.
3.5.3 Solid Waste Four types of solid wastes will be packaged for offsite disposal. Dry wastes will be compacted in 55-gallon drums. Spent filter cartridges will be packaged in shielded drums. Evaporator wastes will be accumulated in phase separators and sludge tanks and
t
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then pumped into a solidification mixture contained in drums. Resins from the spent resin tank will be discharged to a shielded shipping ,
container.
All solid waste will be packaged and shipped to a licensed burial site in accordance with AEC and DOT regulations. Based on a plants presently in operation, it is expected that approximately 900 drums of spent resin filters, flocculation wastes and evaporator bottoms will be generated per year. We estimate that each drum will contain about 2.9 curies after 180 days decay. In addition, it is expected that 600 drums /yr of dry waste containing less than 5 Ci/yr will also be generated.
e e
. l Table 3.5.1 Calculated Annual Release of Radionuclides in the Liquid Effluent from Hanford-2 ,
Nuclide Curies Nuclide Curies Rb-86 0.000045 I-133 0.0 15 Sr-89 0.0087 I-135 0.000044 Sr-90 0.00057 Cs-134 .0.028 Sr-91 0.000031 Cs-136 0.0064 Y-90 0.00081 Co-137 0.019 Y-91m 0.00002 Ba-137m 0.018 Y-91 0.016 Ba-140 0.012 Er-95 0.0001 La-140 0.012 Nb-95 0.000096 Co-141 0.00027 No-99 0.0014 Ce-143 0.000037 Tc-99m 0.0013 Ce-144 0.000063 Ru-103 0.000068 Pr-143 0.00011 Ru-106 0.000024 Pr-144 0.000063 Rh-103a 0.000068 Nd-147 0.000028 Rh-106 0.000024 Cr-51 0.0017 Te-127m 0.00002 Mn-54 0.00013 ,
Te-127 0.000022 Fe-55 0.0067 Te-129s 0.00018 Fe-59 0.00027 Te-129 0.00011 Co-58 - 0.017 Te-131a 0.000028 Co-60 0.0017 Te-132 0.00095 P-32 0.000033 1-130 0.000019 W-187 0.000079 I-131 . 0 .0 84 U-237 0.00002 1-132 0.00098 Np-239 0.00048 Total (Excluding tritium) % 0.25 Curie Tritium N 10 ci/yr
l k ) ,
TABLE 3.5.2 CALCULATED RADIOACTIVE RELEASES IN GASEOUS EFFLUENTS FROM HANFORD NO. 2 REACTOR IN CURIES PER YEAR Turbine and Mechanical Main Total for Reactor Vacuum Condenser Reactor Radionuclide Buildings Pump Air Ejector Unit Kr-83m 2 11 13 Kr-85m -
3.240 3,240 Kr-85 -
760 760 Kr-87 , 10 1 11 Kr-88 10 1,190 1,200 Kr-89 34 -
34 Xe-131m -
230 230 Xe-133m -
40 40 Xe-133 - 1,500 24,700 26,200 '
Xe-135m 17 -
17 Xe-135 15, 215 - 230 Xe-137 60 - 60 Xe-138 50 -
50 TOTAL 32,085 1-131 0.13 -
0.13~
1-133 0.59 - -
0.59
. i
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TABLE 3.5.3 PRINCIPAL ASSUMPTIONS USED IN EVALUATION HANFORD No. 2 REACTOR
- 1. Thermal power 3458 Mw(t)
- 2. Plant factor 0.8
- 3. Failed fuel Equivalent to 100,000 pCi/sec noble gas mixture after 30 min holdup decay for a 3400 MWt reactor
- 4. Reactor Building Leak Rate 480 lb/hr - liquid
- 5. Turbine Building Leak Rate 480 lb/hr - steam
- 6. Condenser air inleakage 40 cfm - air
- 7. Partition coefficients (for iodine):
Steam / liquid in reactor vessel 0.012 Reactor Building liquid leak 0.001 Turbine Building steam leak 1.0 Air ejector - 0.005 .
Recombiner system 0.1 Charcoal bed ,
0.000001
- 8. Holdup Times Air ejector gas 10 min -
Xenon lactopes - delay on charcoal beds 17.9 days Krypton isotopes - delay on charcoal beds 24.4 hrs
- 9. Decontamination Factors: Anton Ca.Rb Others Mixed-bed dominera11:er 100 10 100 Evaporator 1000 10,000 10,000
- 10. Removal factors ,
Mo & TC 100 Y 10
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