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| ==SUBJECT:== | | ==SUBJECT:== |
| DRESDEN UNIT-1 DECOMMISSIONING PLAN AND TECHNICAL SPECIFICATIONS - | | DRESDEN UNIT-1 DECOMMISSIONING PLAN AND TECHNICAL SPECIFICATIONS - |
| REQUEST FOR ADDITIONAL INFORMATION By letter dated January 7,1986 you provided proposed Technical Specification (TS) changes and an amendment to delete authority to operate Dresden Unit 1. | | REQUEST FOR ADDITIONAL INFORMATION By {{letter dated|date=January 7, 1986|text=letter dated January 7,1986}} you provided proposed Technical Specification (TS) changes and an amendment to delete authority to operate Dresden Unit 1. |
| i By letter dated July 23, 1986 we issued Amendment No. 36 to revise License No. DPR-2 to possession-only status. We also advised you that action on the 1 | | i By {{letter dated|date=July 23, 1986|text=letter dated July 23, 1986}} we issued Amendment No. 36 to revise License No. DPR-2 to possession-only status. We also advised you that action on the 1 |
| ; balance of your application would be taken following your submittal of a safety L analysis and/or a Decommissioning Plan. By letters dated December 22, 1987 as j revised April O,1988 you submitted your proposed Decommissioning Plan and j Environmental Report. | | ; balance of your application would be taken following your submittal of a safety L analysis and/or a Decommissioning Plan. By letters dated December 22, 1987 as j revised April O,1988 you submitted your proposed Decommissioning Plan and j Environmental Report. |
| l j We have reviewed your proposed TS, Decommissioning Plan and Environmental Report and have determined that we need additional information to proceed. | | l j We have reviewed your proposed TS, Decommissioning Plan and Environmental Report and have determined that we need additional information to proceed. |
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| W ISSIONING PLAN AND TECHNICAL SPECIFICATIONS - | | W ISSIONING PLAN AND TECHNICAL SPECIFICATIONS - |
| REQUEST FOR i. "*t. INFORMATION By letter dated January /,198t, sou provided proposed Technical Specification (TS) changes and an amendment to delete authority to operate Dresden Unit 1. | | REQUEST FOR i. "*t. INFORMATION By letter dated January /,198t, sou provided proposed Technical Specification (TS) changes and an amendment to delete authority to operate Dresden Unit 1. |
| By letter dated July 23, 1986 we issued Amendment No. 36 to revise License ' | | By {{letter dated|date=July 23, 1986|text=letter dated July 23, 1986}} we issued Amendment No. 36 to revise License ' |
| No. DPR-2 to possession-only status. We also advised you that action on the balance of your application would be taken following your submittal of a safety analysis and/or a Decomissioning Plan. By litters dated December 22, 1987 as revised April 29, 1988 you submitted your proposed Decommissioning Plan and i Environmental Report. | | No. DPR-2 to possession-only status. We also advised you that action on the balance of your application would be taken following your submittal of a safety analysis and/or a Decomissioning Plan. By litters dated December 22, 1987 as revised April 29, 1988 you submitted your proposed Decommissioning Plan and i Environmental Report. |
| We have reviewed your proposed TS, Decomissioning Plan and Environmental Report and have determined that we need additional information to proceed. | | We have reviewed your proposed TS, Decomissioning Plan and Environmental Report and have determined that we need additional information to proceed. |
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| F ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FOR ORE 5 DEN STATION UNIT 1 DECOMMISSIONING COMMONWEALTH EDISON : | | F ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FOR ORE 5 DEN STATION UNIT 1 DECOMMISSIONING COMMONWEALTH EDISON : |
| DOCKET NO. 50-010 Decommissioning Plan | | DOCKET NO. 50-010 Decommissioning Plan |
| : 1. Your letter dated February 25, 1977, described the storage of radioactively contaminated soil in an excavation at the Dresden Unit 1 HPCI and waste treatment facilities. Indicate the present status of this contaminated aree, tabulate concentrations vs location and the total inventory for each radionuclide. Also, provide direct radiation measurements of soil in micro R/hr above background, as measured one meter from the surface of the contaminated soil area. Estimate the maximum radiation levels that would exist if the layer of uncontaminated soil were removed. State your l .. | | : 1. Your {{letter dated|date=February 25, 1977|text=letter dated February 25, 1977}}, described the storage of radioactively contaminated soil in an excavation at the Dresden Unit 1 HPCI and waste treatment facilities. Indicate the present status of this contaminated aree, tabulate concentrations vs location and the total inventory for each radionuclide. Also, provide direct radiation measurements of soil in micro R/hr above background, as measured one meter from the surface of the contaminated soil area. Estimate the maximum radiation levels that would exist if the layer of uncontaminated soil were removed. State your l .. |
| schedule for removal of the contaminated soil such that levels of radioactivity would be acceptable for release to unrestricted access. | | schedule for removal of the contaminated soil such that levels of radioactivity would be acceptable for release to unrestricted access. |
| Currently, we have accepted 5 micro R/hr above natural background for gamma emitting radionuclides as measured one meter above an unshield soil surface. | | Currently, we have accepted 5 micro R/hr above natural background for gamma emitting radionuclides as measured one meter above an unshield soil surface. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H4661999-10-18018 October 1999 Forwards Changes to EPIPs IAW 10CFR50.54(q) & 10CFR50,App E, Section V.Details of Changes Encl ML20216J8241999-09-30030 September 1999 Notifies of Removal of NRC Headquarters & Region III Offices from Controlled Copy Distribution of Certain CE Documents. Specific Documents,Associated Controlled Copy Numbers & NRC Location Affected Are Shown on Attachment to Ltr ML20211G1221999-08-27027 August 1999 Forwards fitness-for-duty Program Performance Data for Each of Comm Ed Nuclear Power Stations & Corporate Support Employees within Scope of Rule for six-month Period Ending 990630,IAW 10CFR26.71(d) ML20210N5651999-08-0606 August 1999 Forwards Rev 8 to Nuclear Generating Stations Emergency Plan, for Plants.With Summary of Changes ML20210M9131999-08-0202 August 1999 Forwards Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for Fys 2000 & 2001 for Comed ML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210D2961999-07-20020 July 1999 Forwards Corrected Info for DNPS Unit 3 MOR for June 1999. Year-to Date Forced Outage Hours Should Have Read 70 Hours Instead of 0 on Page 8.Error Also Affected Cumulative Forced Outage Hours Which Should Have Been 24,761 ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196J9131999-07-0101 July 1999 Submits Status of Nuclear Property Insurance Currently Maintained for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR50.54(w)(3) ML20196J9061999-07-0101 July 1999 Provides Evidence That Util Maintains Guarantee of Payment of Deferred Premiums in Amount of $10 Million for Each of Thirteen Reactors,Per 10CFR140.21 ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray ML20209B8241999-06-30030 June 1999 Forwards Five 3.5 Inch Computer Diskettes Containing Revised Annual Dose Repts for 1994 Through 1998 for Individuals Receiving Neutron Dose Not Previously Included in Reported Total Effective Dose Equivalent Values.Without Diskettes ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195E3451999-06-0707 June 1999 Forwards 3.5 Inch Computer Diskette Containing Revised File Format for Annual Dose Rept for 1998,per 990520 Telcon Request from Nrc.Each Station Data Is Preceded by Header Record,Which Provides Info Necessary to Identify Data ML20195D6351999-06-0404 June 1999 Notifies NRC of Actions That Has Been Taken in Accordance with 10CFR26, Fitness for Duty Programs ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20195B2301999-05-19019 May 1999 Requests Approval of Proposed Changes to QA Topical Rept CE-1-A,rev 66a.Attachment a Describes Changes,Reason for Change & Basis for Concluding That Revised QAP Incorporating Proposed Changes Continues to Satisfy 10CFR50AppB ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206F5381999-04-30030 April 1999 Forwards Magnetic Tape Containing Annual Dose Repts for 1998 for Braidwood,Byron,Dresden,Lasalle County,Quad Cities & Zion Nuclear Power Stations,Per 10CFR20.2206(c).Without Magnetic Tape ML20206B1501999-04-22022 April 1999 Forwards 1998 Occupational Radiation Exposure for Dresden Nuclear Power Station,Units 1,2 & 3. Rept Was Revised to Rept Only Individual Radiation Exposures Greater than 100 Mrem ML20206B2471999-04-20020 April 1999 Informs That SE Kuczynski Has Been Transferred to Position No Longer Requiring SRO License.Cancel License SOP-31030-1, Effective 990412 ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures ML20205K5841999-03-31031 March 1999 Submits Rept on Status of Decommissioning Funding for Reactors Owned by Comm Ed.Attachment 1 Contains Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C) ML20196K7001999-03-31031 March 1999 Forwards Dresden Nuclear Power Station,Units 1,2 & 3 Radioactive Effluent Release Rept,Jan-Dec 1998. ODCM Was Submitted by Ltr in Accordance with Dresden TS 6.9.A.4 of Dresden Tech Specs Section 6.14.A.3 ML20205D7231999-03-26026 March 1999 Informs That Region III Emergency Preparedness Inspector Will Be Provided Copy of Comed Exercise Manual for 990526 Annual Exercise at DNPS ML20205B4241999-03-23023 March 1999 Provides Results of drive-in Drill Conducted on 990208,as Well as Augmentation Phone Drills Conducted Since 981015,as Committed to in Util ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20207D6831999-03-0101 March 1999 Forwards fitness-for-duty Program Performance Data for Each Comed Nuclear Power Station & Corporate Support Employees for Six Month Period Ending 981231,per 10CFR26.71(d) ML20207E0931999-02-26026 February 1999 Informs That Region III EP Inspectors Will Be Provided One Copy of Exercise Evaluation Objectives for 990526 Annual Exercise at Dresden Station as Enclosure to Ltr for Review. Proprietary Encl Withheld ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203C7001999-02-0202 February 1999 Informs That Mhb Technical Associates No Longer Wishes to Receive Us Region III Docket Info Re Comed Nuclear Facilities.Please Remove Following Listing from Service List ML20202G0621999-01-25025 January 1999 Forwards 1998 Revs to Commitments Rept Made in Docketed Correspondence for Dresden Nuclear Power Station ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20199E0201999-01-12012 January 1999 Forwards Change to Bases of Dnps,Unit 1 TS Section 3.10, Fuel Handling & Storage. Change Eliminates Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS ML20199C8851999-01-11011 January 1999 Forwards Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3,as Required by TS 6.9.A.5.Year-to-date Generator Hours for Unit 2 for Oct 1998 & Nov 1998 Corrected in Rept ML20206P7411999-01-0707 January 1999 Informs of Delay in Implementation of Strategic Reform Initiative Action Steps.Util Mgt Now Preceeding to Implement Succession Planning Steps for Corporate Ofc & Expects Completion of Action Steps 2 & 3 by 990128 ML20198N7691998-12-30030 December 1998 Forwards Rev 59 to Security Plan for Dresden Nuclear Power Station,In Accordance with 10CFR50.4(b)(4).Rev Withheld ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196B5871998-11-20020 November 1998 Requests That Svc List for All NRC Correspondence Re Any of Six Comed Nuclear Stations Be Modified Per Attached List.All Other Names Previously Listed Should Be Removed ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20195E6451998-11-12012 November 1998 Provides Results of drive-in Drill Conducted on 981007,as Well as Augmentation Phone Drill Conducted on 980917 ML20195F3461998-11-10010 November 1998 Forwards Rev 58 of DNPS Security Plan,Including Listed Changes,Iaw 10CFR50.4(b)(4).Encl Withheld Ref 10CFR73.21 ML20155D2701998-10-27027 October 1998 Forwards Changed Pages from 980423 Submittal Providing Addl Info Marked with Revision Bars & Revised Pages to QA Topical Rept Section 18,for Review ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given 1999-09-30
[Table view] Category:NRC TO UTILITY
MONTHYEARML20058G2941990-11-0505 November 1990 Advises That Written & Operating Operator & Senior Operator Licensing Exams Scheduled for Wk of 910204 & Requests Listed Ref Matls 60 Days Prior to Exam Date ML20058E7141990-10-30030 October 1990 Forwards Exam Forms & Answer Keys,Grading Results & Individual Answer Sheets for Each Applicant ML20059M2101990-09-25025 September 1990 Forwards Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exams to Be Administered on 901010,including Map of Area Where Exams Will Be Taken, Preliminary Instructions for Exam & Equation Sheet ML20058M6141990-08-0707 August 1990 Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date ML20055G2951990-07-13013 July 1990 Advises That SALP 9 Presentation Time Changed Due to Commissioner Carr Visit on 900723 ML20059M8791990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl IR 05000237/19890181989-09-0808 September 1989 Forwards Safety Insp Repts 50-237/89-18 & 50-249/89-17 on 890715-0828.No Violations Noted ML20246K6121989-08-25025 August 1989 Advises That 890818 Proposed Scope & Objectives for Plant Annual Emergency Preparedness Exercise Scheduled for 891101 Acceptable ML20246D0711989-08-10010 August 1989 Forwards Amends 107 & 102 to Licenses DPR-19 & DPR-25, Respectively & Safety Evaluation.Amends Revise Testing Requirements for Other Sys or Subsystems of ECCS or Standby Gas Treatment Sys When One Sys or Subsystem Inoperable ML20248D6401989-08-0404 August 1989 Forwards FEMA Transmitting Revised Exercise Rept for Sept 1987 Emergency Exercise at Plant.No Deficiencies Noted.Six Areas Requiring Corrective Action Identified.Nrc Expects Util to Devote Attention to Resolving Concerns ML20248D6921989-08-0404 August 1989 Advises That Rev 6b to Generating Stations Emergency Plan Transmitted by Util 890710 Form Acceptable & Does Not Decrease Effectiveness of Plan IR 05000010/19890021989-07-31031 July 1989 Forwards Safety Insp Repts for 50-010/89-02,50-237/89-17 & 50-249/89-16 on 890530-0714 & Notice of Violation ML20245G4591989-06-21021 June 1989 Forwards Notice of Consideration of Issuance of Amend to License DPR-2 Re 860107 Application Concerning Decommissioning Plan & Safstor ML20245B1731989-06-15015 June 1989 Ack Receipt of Rev 55 to QA Topical Rept CE-1-A.Program Satisfies Requirements of 10CFR50,App B & Acceptable ML20247G5241989-05-18018 May 1989 Responds to Re Util Position on Dealing W/Dc Grounds After Discussion W/Nrc in 890301 Meeting.Continued Plant Operation Will Be Allowed Only So Long as Applicable Limiting Conditions/Or Action Statements Met ML20246F9731989-05-0303 May 1989 Advises That Requalification Program Evaluation Scheduled for Wk of 890828.Listed Ref Matl Requirements Necessary 60 Days Prior to Exam Date ML20236B7611989-03-0808 March 1989 Advises That Rev 5b to Plant Emergency Plan Consistent W/ Provisions of 10CFR50.54(q) & Acceptable.Approval of Emergency Action Levels (EAL) Does Not Preclude Additions to Upgraded EALs Resulting from NRC Review of Decommissioning ML20235Z6501989-03-0707 March 1989 Ack Receipt of 890127 Submittal of Rev 54 to QA Topical Rept CE-1-A.Program Continues to Satisfy Requirements of 10CFR50,App B & Acceptable ML20246L7481989-03-0303 March 1989 Confirms 890323 Meeting in Glen Ellyn,Il to Discuss Util Quality Verification Program,Per ML20236A0461989-03-0202 March 1989 Advises That 890228 Rev 26 to Plant Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20235T2541989-02-28028 February 1989 Forwards Safety Insp Rept 50-249/89-04 on 880604-890208 & Forwards Notice of Violation IR 05000237/19890061989-02-28028 February 1989 Forwards Safety Insp Rept 50-237/89-06 on 890123,24,27 & 0214-16.No Violations Noted ML20205J4331988-10-24024 October 1988 Advises That 881023 Rev 25 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20207L5581988-10-0707 October 1988 Advises That 880912 Rev 52 to QA Topical Rept CE-1-A Consistent W/Requirements of 10CFR50,App B & Acceptable ML20154Q4071988-09-27027 September 1988 Forwards Request for Addl Info Re Proposed Tech Specs Changes,Decommissioning Plan & Environ Rept to Delete Authority to Operate Facility ML20153G9491988-08-31031 August 1988 Advises That 880809 Rev 6B to Emergency Plan Consistent W/Provisions of 10CFR50.54(q) & Acceptable ML20207F8881988-07-27027 July 1988 Forwards Latest Rev of NRC Manual Chapter 0516, Salp. Region III Will Begin Using New Functional Areas Set Forth in Rev for All SALP Rept Periods Which Extend Beyond 880606 Effective Date of Procedure ML20151C9871988-07-12012 July 1988 Confirms 880706 Plans Re 880714 Mgt Meeting at Region III to Discuss Plant Performance ML20151E8131988-07-12012 July 1988 Forwards Safeguards Insp Repts 50-010/88-04,50-237/88-16 & 50-249/88-17 on 880628-30.Rept Details & Notice of Violation Withheld (Ref 10CFR73.21) ML20150F9801988-07-0808 July 1988 Informs That 880527 Rev 24 to Security Plan for Facility Consistent w/10CFR50.54(p) & Acceptable.Stated Item Deleted Due to Administrative Error Must Be Returned to Plan.Encl Withheld ML20150D8901988-07-0707 July 1988 Requests Addl Info Re Emergency Plan Requirements for Fuel Storage.Lists Questions Requiring Licensee Response Needed for Evaluation of Emergency Action Levels in Emergency Plan.Rev of Site Emergency Plan Suggested ML20150B4481988-07-0505 July 1988 Forwards Hj Miller 880608 Memo Re Site Visit to Attend Exit Meeting for Insp of Emergency Operating Procedures & to Tour Facility ML20150B8991988-06-23023 June 1988 Forwards Draft Rev 5 to ES-601, Administration of NRC Requalification Program Evaluations. W/O Encl ML20153E8941988-05-0303 May 1988 Forwards Safeguards Insp Repts 50-010/88-03,50-237/88-07 & 50-249/88-08 on 880404-08 & Notice of Violation.Notice of Violation Withheld (Ref 10CFR73.21) ML20151Z9261988-05-0202 May 1988 Advises That Changes to 880418 Revs 49 & 50 to QA Topical Rept CE-1-A Meets Requirements of 10CFR50,App B & Acceptable ML20151Y4951988-04-26026 April 1988 Notifies That Submittals Re Allegations Concerning Use of Poor Matls & Poor Mfg Practices by C&S Valve Co Have Been Reviewed.Util Procedures Re safety-related Purchases in Accordance W/Specs.Allegation Considered Closed ML20147J1891988-03-0404 March 1988 Requests Remittance of Fee for Review of 871222 Application Re Decommissioning Documents for Facility ML20147F2241988-03-0101 March 1988 Advises That Util Released from 870306 Commitment to Provide Equipment out-of-svc List to NRC on Weekly Basis.Amount of Equipment out-of-svc Reduced to Level Consistent W/Good Maint Practices ML20149H9241988-02-12012 February 1988 Commends Dedication & Commitment of Individuals Having Gone Through Rigorous Study & Training for NRC License.Nrc Will Formally Present License Certificates of Newly Licensed Individuals,If Requested ML20149G5261988-02-12012 February 1988 Forwards Pilot Requalification Exam,In Anticipation of Resumption of Requalification Testing Later This Yr.Util Should Review Programs & Manpower Commitments.W/O Encl ML20148G2701988-01-20020 January 1988 Informs That Revs 42-48 of QA Topical Rept CE-1-A Acceptable Per 10CFR50,App B ML20234B8361987-12-31031 December 1987 Responds to Re Scope & Objectives for Plant Exercise Scheduled for 880301.Proposed Objectives Acceptable ML20237D7661987-12-22022 December 1987 Responds to to TE Murley Re Effects of Postulated Dc Power Failure on ECCS Performance for Plants.Compliance W/Requirements of 10CFR50.46 & App K Cannot Be Concluded. Operation of Units During 60-day Period Acceptable ML20237F0571987-12-17017 December 1987 Confirms 880119 Enforcement Conference in Glen Ellyn,Il to Discuss 861128 & 29 Deinerting Events,Per 871204 & 10 Discussions ML20237D3881987-12-11011 December 1987 Summarizes 871117-18 Meeting to Review Performance of Operating Nuclear Power Plants & Related Issues of Greatest Safety Significance.Facility Categorized as Requiring Close Monitoring to Determine Effectiveness of Corrective Actions ML20236X8811987-12-0808 December 1987 Advises That 871125 Rev 22 to Security Plan Consistent W/ Provisions of 10CFR50.54(p) & Acceptable ML20236V6171987-12-0101 December 1987 Forwards Exam Rept 50-237/OL-87-03 Administered on 871026-30.Exam & Answer Key Encl ML20236W5351987-12-0101 December 1987 Forwards Safeguards Insp Repts 50-010/87-08,50-237/87-34 & 50-249/87-33 on 871026-30 & 1102.No Violations Noted ML20236N5091987-11-10010 November 1987 Ack Receipt of Allegation RIII-87-A-0138 in Which Alleger Expressed Concern Re Plant Fuel Pool.Util Requested to Address Procedures or Practices in Place to Assure Integrity of Fuel Racks in Fuel Pool & Concrete Structure ML20236L1031987-11-0202 November 1987 Forwards Request for Addl Info Re 861126 Application for Amend to Physical Security Plan in Response to Miscellaneous Amends & Search Requirements.Requests Response within 60 Days of Receipt of Ltr 1990-09-25
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20210L1061999-08-0202 August 1999 Forwards Insp Rept 50-010/99-13 on 990702-27.No Violations Noted.Insp Examined Activities in Areas of Facility Management & Control & Radiological Safety ML20210B7071999-07-16016 July 1999 Responds to Requesting Review & Approval of Three Proposed Changes to Ceco QA TR,CE-1A Per 10CFR50.54(a)(3) & 10CFR50.4(b)(7) ML20196K3231999-06-30030 June 1999 Informs That Effective 990703,NRC Project Management Responsibility for Dresden,Unit 1 Station Will Be Transferred to P Ray ML20196D3491999-06-18018 June 1999 Forwards Insp Repts 50-237/99-08 & 50-249/99-08 on 990408-0521.Four Non-Cited Violations Noted.Maint on safety- Related Emergency CR Not Performed Well.Low Impact Issues Re Communications Present in Operations,Maint & Security ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20207G2571999-06-0303 June 1999 Informs That Effective 990328,NRC Ofc of NRR Underwent Reorganization.Within Framework of Reorganization,Division of Licensing Project Management Created ML20206Q3111999-05-18018 May 1999 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety ML20206P2431999-05-13013 May 1999 Forwards Insp Rept 50-010/99-09 on 990325-0506.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205K5521999-04-0202 April 1999 Forwards Partially Withheld Security Insp Repts 50-010/99-07,50-237/99-07 & 50-249/99-07 on 990308-12.Two non-cited Violations Identified Involving Failure of Security Personnel to Implement Required Measures ML20207L7141999-03-0808 March 1999 Discusses Transmitting Changes Identified as Rev 59 to Security Plan for Dresden Nuclear Power Station,Units 1,2 & 3.Staff Determined That No NRC Approval Required in Accordance with 10CFR50.54(p) ML20203G3631999-02-10010 February 1999 Forwards Insp Rept 50-010/99-02 on 981218-990129.No Violations Noted.During Insp,Activities in Area of Facility Mgt & Control,Decommissioning Support Activities & Radiological Safety Were Examined ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20199F3291999-01-14014 January 1999 Ack Receipt of Ltr Dtd 981230,transmitting Changes Identified as Rev 59 to Plant Security Plan,Submitted Under Provisions of 10CFR50.54(p) ML20198A2531998-12-10010 December 1998 Ack Receipt of Which Transmitted Changes Identified as Rev 57 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20198A2511998-12-10010 December 1998 Ack Receipt of ,Which Transmitted Changes Identified as Rev 58 to Plant Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20196E2371998-11-27027 November 1998 Discusses Licensee ,Requesting That Agreement in Be Changed to Reflect Latest NRC Conditions Requiring Licensees to Notify NRC of Transfer of Assets to Affiliates Imposed in Connection with Approval of Transfer ML20196A4121998-11-19019 November 1998 Forwards Safety Evaluation Accepting Proposed Changes to QA TR CE-1-A,Rev 66,by ,As Modified by Ltrs & 1027.Proposed QA Tr,Rev 66 Continues to Comply with Criteria of 10CFR50,App B ML20195J4271998-11-13013 November 1998 Forwards Insp Repts 50-010/98-18,50-237/98-27 & 50-249/98-27 on 981013-16 & Notice of Violation.Mgt Activities Were Focused Toward Maintaining Effective Security Program ML20154P9051998-10-20020 October 1998 Ack Receipt of 980821 Submittal,Per 10CFR50.54(a),requesting Review & Approval of Proposed Changes That Reduce Commitments in QA TR,CE-1-A.Util Should Refrain from Implementing Subj Changes Until Formal Notification Given ML20154F6291998-10-0606 October 1998 Forwards Insp Rept 50-010/98-16 on 980723-0918.No Violations Noted.During Period Covered by Insp,Activities in Areas of Facility Mgt & Control,Spent Fuel Safety & Radiological Safety Examined ML20154B6761998-10-0101 October 1998 Informs That NRC Reviewed Comm Ed Submittals & Finds,Util Has Adequately Addressed Actions in GL 95-07,as Discussed in Encl SE ML20153C4941998-09-21021 September 1998 Forwards SER Accepting Qualified Unit 1 Supervisor Initial & Continuing Training Program for Dresden Nuclear Power Station IR 05000010/19980151998-08-13013 August 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/98-15, 50-237/98-18 & 50-249/98-18 Issued on 980629.Corrective Actions Will Be Examined During Future Insps ML20237B1321998-08-11011 August 1998 Forwards Corrected Copy of NOV Re Insp Repts 50-010/98-15, 50-237/98-18 & 50-249/98-18 Conducted on 980601-04.Notice Did Not Contain Safeguards Info.Administrative Error Resulted in Document Being Marked as Safeguards Info ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20236L1151998-07-0606 July 1998 Forwards Insp Rept 50-010/98-13 on 980319-0630.No Violations Noted.Activities in Area of Facility Mgt & Control,Sf Safety & Radiological Safety Were Examined ML20236F1471998-06-29029 June 1998 Forwards Insp Repts 50-010/98-15,50-237/98-18 & 50-249/98-18 on 980601-0604.Areas Examined within Security Program Were Identified ML20236G9961998-06-26026 June 1998 Forwards Insp Repts 50-237/98-14 & 50-249/98-14 on 980403- 0527.No Violations Noted.Unavailability of HPCI Sys Continued to Be Problem at Dresden During Insp Period ML20249C3121998-06-23023 June 1998 Inorms That Proposed Revision 66 to QA Topical Rept,CE-1-A, Not Acceptable.Requests That Licensee Refrain from Implementing Changes Until Formally Notified ML20248B9431998-05-27027 May 1998 Discusses 980520 Public Meeting Re Dresden Unit 1 Decommissioning Activities & Dry Cask Storage Project. Meeting Handouts Encl ML20247E3061998-05-0808 May 1998 Confirms Discussion W/B Snell Re Agreement to Have Meeting on 980520 at Plant,Training Bldg to Discuss Unit 1 Status & Plans,Problem Identification & Prevention & Dry Cask Storage Status IR 05000010/19980081998-05-0101 May 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/98-08, 50-237/98-08 & 50-249/98-08.Corrective Actions Will Be Examined During Future Insps ML20216G6311998-04-0909 April 1998 Summarizes 980312 Meeting Conducted at Region III Ofc in Lisle,Il,To Discuss Util Performance Re Action That Util Taken in Response to NRC 10CFR50.54(f) Ltr, Re Safety Performance at Facilities.List of Attendees Encl ML20217J2131998-04-0202 April 1998 Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided ML20217E8191998-03-26026 March 1998 Discusses Review of Dec 1997,rev 7K to Generating Stations Emergency Plan,Submitted Under Provisions 10CFR50.54(q).NRC Approval Not Required,Changes Do Not Decrease Effectiveness of Plan ML20217D5951998-03-25025 March 1998 Forwards Insp Repts 50-010/98-08,50-237/98-08 & 50-249/98-08 Conducted Between 980302 & 11.Areas within Security Program Were Examined.Nov & Insp Details Being Withheld ML20248L7911998-03-18018 March 1998 Forwards Insp Rept 50-010/98-02 on 971215-980226 & Nov.Rp Program Exhibited Number of Weaknesses.Program Declined Through Most of 1997 Until Control Informal,Personnel Not Well Informed or Disciplined & Mgt Involvement Lacking ML20216B8321998-03-0606 March 1998 Forwards Decommissioning Insp Plan for Remainder of FY98 for Plant,Unit 1,for Info.Plan Will Be Updated Approx Twice Each Yr & May Be Revised at Any Time Based on Future Insp Findings,Events & Resource Availability ML20203H9651998-02-26026 February 1998 Confirms Discussion to Have Meeting on 980312 in Lisle,Il to Discuss Comed Nuclear Operating Division Performance as Relates to Actions Comed Taken in Response to NRC Ltr ,re Safety Performance at Comed Nuclear Facilities ML20203B1651998-02-0909 February 1998 Informs That Effective 980209 R Burrows Has Been Assigned as Project Manager for Plant,Unit 1 ML20202H1701998-02-0909 February 1998 Discusses 980114 Meeting W/Listed Attendees in Lisle,Il to Discuss Commonwealth Edison Co Performance Re Actions Util Has Taken in Response to NRC 970127,10CFR50.54(f) Ltr Concerning Safety Performance at Util Facilities IR 05000010/19970241998-02-0303 February 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-24, 50-237/97-24 & 50-249/97-24.Actions Will Be Examined During Future Insp ML20202C7821998-02-0303 February 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-19, 50-237/97-19 & 50-249/97-19.Corrective Actions Will Be Examined During Future Insp ML20198T4491998-01-20020 January 1998 Advises of Planned Insp Effort Resulting from Dresden Plant Performance Review.Details of Insp Plan for Next 6 Months Encl ML20198N7181998-01-15015 January 1998 Discusses Conversation Between I Johnson & J Gavula Re Cancellation of Planned Routine Mgt Meeting on 980122 in Lisle,Il ML20197H8761997-12-23023 December 1997 Forwards Insp Repts 50-010/97-26,50-237/97-26 & 50-249/97-26 on 971029 & 1106.No Violations Noted.Noncited Violation Re Failure to Implement FFD Provisions Contained in Plant Procedure Was Identified ML20197G5641997-12-19019 December 1997 Ask Receipt of Ltr Dated 971002,which Transmitted Changes Identified as Rev 56 to Dresden Nuclear Station Security Plan,Submitted Under Provisions of 10CFR50.54(p).Changes Do Not Decrease Overall Effectiveness of Plan ML20197E9681997-12-19019 December 1997 Forwards Insp Repts 50-010/97-24,50-237/97-24 & 50-249/97-24 on 971016-1122 & Notice of Violation ML20203J6481997-12-16016 December 1997 Final Response to FOIA Request for Documents.Forwards Documents Listed in App A.Documents Will Be Available in PDR ML20203J8091997-12-15015 December 1997 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-010/97-20, 50-237/97-20 & 50-249/97-20 on 971030 1999-08-02
[Table view] |
Text
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September 27, 1988 Docket No. 50-10 Mr. W. E. Morgan Nuclear Licensing Administrator Commonwealth Edison Company One First National Plaza Post Office Box 767 Chicago, Illinois 60690-0767
Dear Mr. Morgan:
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SUBJECT:
DRESDEN UNIT-1 DECOMMISSIONING PLAN AND TECHNICAL SPECIFICATIONS -
REQUEST FOR ADDITIONAL INFORMATION By letter dated January 7,1986 you provided proposed Technical Specification (TS) changes and an amendment to delete authority to operate Dresden Unit 1.
i By letter dated July 23, 1986 we issued Amendment No. 36 to revise License No. DPR-2 to possession-only status. We also advised you that action on the 1
- balance of your application would be taken following your submittal of a safety L analysis and/or a Decommissioning Plan. By letters dated December 22, 1987 as j revised April O,1988 you submitted your proposed Decommissioning Plan and j Environmental Report.
l j We have reviewed your proposed TS, Decommissioning Plan and Environmental Report and have determined that we need additional information to proceed.
- Please provide your response to the enclosed request for additional i j information by November 20, 1988.
I Sincerely, i a ,
4 /s/
Peter B. Erickson, Project Manager I Standardization and Non-Power i Reactor Project Directorate l l Division of Reactor Projects - III, IV, l
- Y and Special Projects ,
j Office of Nuclear Reactor Regulation ,
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Enclosure:
As stated
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c September 27, 1988 Docket No. 50-10 '
Mr. W. E. Morgan Nuclear Licensing Administrator comonwealth Edison Company One First National Plaza Post Office Box 767 Chicago, Illinois 60690-0767
Dear Mr. Morgan:
SUBJECT:
DRESDEN UNii -
W ISSIONING PLAN AND TECHNICAL SPECIFICATIONS -
REQUEST FOR i. "*t. INFORMATION By letter dated January /,198t, sou provided proposed Technical Specification (TS) changes and an amendment to delete authority to operate Dresden Unit 1.
By letter dated July 23, 1986 we issued Amendment No. 36 to revise License '
No. DPR-2 to possession-only status. We also advised you that action on the balance of your application would be taken following your submittal of a safety analysis and/or a Decomissioning Plan. By litters dated December 22, 1987 as revised April 29, 1988 you submitted your proposed Decommissioning Plan and i Environmental Report.
We have reviewed your proposed TS, Decomissioning Plan and Environmental Report and have determined that we need additional information to proceed.
Please provide your response to the enclosed request for additional information by November 20, 1988.
Sincerely, , ;
cL4etm A &
Peter B. Erickson, Project Manager ;
Standardization and Non-Power ;
Reactor Project Directorate !
Division of Reactor Projects - !!!, IV, l V and Special Projects '
Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See next page l
l
Mr. W. E. Morgan Dresden Nuclear Power Station Commonwealth Edison Company CC:
Michael I. Miller, Esq.
Sidley and Austin One First National Plaza Chicago, Illinois 60603 Mr. J. Eenigenburg Plant Superintendent Dresden Nuclear Power Station Rural Route #1 Morris, Illinois 60450 U. S. Nuclear Regulatory Commission Resident Inspectors Office
. Dresder Station Rural Route #1 Morris, Illinois 60450 Chairman Board of Supervisors of Grundy County Grundy County Courthouse Morris, Illinois 60450 Regional Administrator Nuclear Regulatory Commission, Region III l 799 Roosevelt Road, Bldg. f4 1 Glen Ellyn, Illinois 60137 '
Mr. Michael E. Parker, Chief Division of Engineering Illinois Department of Nuclear Safety 1035 Outer Park Drive, 5th Floor Springfield, Illinois 62704 l
I l
F ENCLOSURE REQUEST FOR ADDITIONAL INFORMATION FOR ORE 5 DEN STATION UNIT 1 DECOMMISSIONING COMMONWEALTH EDISON :
DOCKET NO.50-010 Decommissioning Plan
- 1. Your letter dated February 25, 1977, described the storage of radioactively contaminated soil in an excavation at the Dresden Unit 1 HPCI and waste treatment facilities. Indicate the present status of this contaminated aree, tabulate concentrations vs location and the total inventory for each radionuclide. Also, provide direct radiation measurements of soil in micro R/hr above background, as measured one meter from the surface of the contaminated soil area. Estimate the maximum radiation levels that would exist if the layer of uncontaminated soil were removed. State your l ..
schedule for removal of the contaminated soil such that levels of radioactivity would be acceptable for release to unrestricted access.
Currently, we have accepted 5 micro R/hr above natural background for gamma emitting radionuclides as measured one meter above an unshield soil surface.
- 2. We understand that much of the liquid waste produced from the 1984 chemical cleaning of the primary loop is still on-site in unprocessed form. Plans
' for processing and disposing of this waste should be provided, along with information on volume, activity by nuclide, waste classification, and (
3 chelate content. Any necessary change to the process control program, the quality control prograr, or the transportation packaging program should be submitted. The plan for disposal of the chelate chemical cleaning waste ,
a should demonstrate assurance of disposal at an arid LLW disposal site '
, prior to termination of access to such facilities. l Similar information should be submitted for any other significant quantity of radioactive waste currently on-site. ,
t Costs for dealing with the significant quantities of stored wastes should !
be accounted for in the overall decommissioning cost analysis. I
- 3. Wastes to be produced in preparation for the "dormancy" period should be i fully characterized in Section 2. Information should be provided on volume, activity content by nuclide, concentrations, processing plans, waste classification, and chelate content if any. Mixed wastes should be l identified if present. This should be done for each contaminated waste source listed in Section 2.1.1, "SAFSTOR" Operations, and for each waste stream during the dormancy period described in Section 2.1.2, "Dormancy."
- 4. The internal funding method proposed, as well as the amount of financial surety provided, is not consistent with 10 CFR Part 50.75 of the i
' Coer. mission's final decommissioning regulations of June 27,1988(53FR l 24049). A financial surety method consistent with those regulations must be submitted.
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- 5. The cost figures given for decomissioning Dresden Unit 1 appear to be inconsistent. A figure of $108 million is given in Table 4.2 and stated to be in 1985 dollars while a figure of $110 million is given in Table 4.3 and stated to be in 1987 dollars.
- 6. Section 4.2 states that the Dresden Unit I decomissioning cost estimate !
in Table 4.2 does not include interest, inflation, or tax effects, but that l these factors are accounted for in the financial plan described in Section '
l 4.3. The only cost figure provided is $150 million per unit which appears I to be an average of the Table 4.3 estimates for all 11 CECO units. The l
effects of interest, inflation, and taxes, and other influences on the Dresden 1 decommissioning cost should be analyzed and provided.
- 7. No basis is provided for the estimated decomissioning cost for Dresden Unit 1 other than a reference to a 1985 study by TLG Engineering. A fully detailed basis for the estimated cost of decomissioning Dresden 1 should be supplied unless the default amount prescribed in the final decommis-sioning regulations (10 CFR Part 50.75C) is to be used for financial assurance purposes. This information should take into account the apparent uncertainty as to when final dismantling and decontamination will I actually occur.
l l 8. Costs during the SAFSTOR or dormancy period (Section 4) are stated as l being treated as operating costs. The rationale for treating these costs l other than as straight decomissioning costs should be fully described, l and consistency with the new decomissioning regulations should be demonstrated.
- 9. We have found the financial assurance aspects of the decommissioning plan {
for Dresden to be deficient. The Commission recently voted to disallow !
use of the internal reserve method of setting aside funds for decomis- i sioning. Because Comonwealth Edison has been using and proposes to l continue using the internal reserve method of funding for Dresden Unit I l (Dresden Unit 1 Decommissioning Plan, p. 26), Comonwealth Edison's approach is essentially incompatible with current Comission policy.
Notwithstanding the policy expressed in the final rule to treat plants )
already shutdown on a case-by-case basis, we have cone'uded that internal reserve should not be allowed for Dresden Unit 1 or other shutdown power plants. Therefore, we ask that Commonwealth Edison redraf t its funding plan for Dresden Unit 1 to stipulate that all decommissioning funds for Dresden Unit 1 be placed in an external account as described in both the proposed decomissioning rule and in NUREG-0584, Rev. 3 (Assuring the Availability of Funds for Decommissioning Nuclear Facilities). For f unds already accumulated in an internal reserve, Comonwealth Edison Could either transfer then to an external account or start from a zero balance by assuming that any funds accumulated so far in an internal reserve will l
not be credited to its decommissioning reserve. >
- 10. P. 27. It is stated that, "The estimated costs of decomissioning one ,
unit are approximately $150 million (stated in 1987 dollars) as detailed l in Table 4.3." However, Table 4.3 (p. 31) in91cated that the estimated Dresden Unit I decomissioning cost in 1987 dollars is $110 million.
This discrepancy should be explained or revised.
l
- 11. P. 27. There is no provision for inflation or amortization schedules showing the annual rate of collection of funds over the life of the decommissioning process. If Commonwealth Edison chooses not to consider inflation in its current estimates, it should at least indicate how frequently it plans to update decommissioning cost estimates for Dresden Unit 1 and adjust its amortization schedule accordingly. Similarly, there is no discussion of assumptions concerning projected earnings on the -
- decommissioning fund, which should be provided whether an internal or an j external fund is being used. Comonwealth Edison should provide this information.
- 12. P. 30. Table 4.2 provides a summary of estimated Dresden Unit 1 decorrnis-sioning costs. Although these figures appear reasonable, there is no detail backing them up. We request that Comnonwealth Edison provide this detail in their next submission or provide funding assurance for the
.. amount specified in 10 CFR Part 50.75(c).
- 13. A local area map defining the unrestricted areas used for offsite dose calculations for gaseous and liquid effluents should be included in the TS.
In addition, a site map clearly defining the restricted area pursuant to 10 CFR 20.3(a)(14) should be included, r
14 a) Provide a table showing Dresden Unit 1 personnel exposure experiences for the years 1978 thru 1988 indicating the man-rem exposures b plant system, regardless of how these exposures were o>tained (ye.g.,
duringnormaloperations, maintenance,repairorrefuelingactivities) and by whom (e.g., by plant operations personnel, plant maintenance personnel, contractor /vendorpersonnel,etc.).
b) Provide a similar table for tne SAF510s p iod. Provide discussion l which confirms that your ALARA program will maintain the state-of-the- ,
art for reducing personnel exposures to a minimum. '
- 15. Revise Section 5.8 to show the design features of the monitoring system :
for the SAFSTOR decomissioning. Include the offsite and onsite environ- I mental monitoring stations. '
- 16. In accordance with Section 12.5, NUREG-0800, confirm that your health ;
physics procedures for performing bioassay during the SAFSTOR period i will conform to the recommendations of Regulatory Guide 8.26. "Application of Bioassay for Fission and Activation Products,' or submit equivalent bioassay criteria. !
- 17. Are you contemplating spent fuel pin consolidation onsite prior to shipment I to the Federal High Level Waste Repository? If so, provide estimates of the expected occupational radiation exposures involved, of the volume of i low level waste generated, and the contribution of this activity to gaseous j and liquid radioactivity releases to the environment.
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- 18. Describe the treatment and monitoring to be provided for effluents from i the refueling building ventilation exhaust, liquid waste storage tankage vent exhaust, hot lab vent exhaust, hot machine shop vent exhaust, radwaste treatment building ventilation exhaust, the high-level solid radioactive waste storage vaults, the low-level waste storage building, the low-level waste handling building, and any other pathway for the release of radio- ;
i active materials. i
- 19. Provide an estimate of the number of employees required for the SAFSTOR decomissioning time period. Provide a breakdown by permanent and ,
contractor workers of the employees required. If this number is not i expected to be relatively stable, give estimate of changes anticipated.
- 20. Provide a description of fission and corrosion prodnet sources in the (a) movement of fuel from the core spentfuelpool(SFP))waterfrom:
intothepool,and(b defective fuel stored in the pool. Include a listing of the radionuclides and their concentrations (expressed in uCi/mL) deco The radionuclides of interest should expectedb'I"80Co, include 5 Co, g ssioning137 Cs, and Cs.
- 21. Provideadescriptionofradioactivematerialsthagmaybecogeairborne j as a result of failed fuel and evaporation (e. Kr, and I
, Theradionuclidedescriptionshouldincludecablatedormeasuredconcen-H,respectively). i l trations expected during decomissioning.
- 22. Provide a description of the dose rate at the surface of the pool water l
- from the fuel assen611es, control rods, burnable poison rods or any I miscellaneous materials that may be stored in the pool. l
- 23. Discuss the manner in which occupational exposure will be kept ALARA during s the decomissioning. Include the need for and the manner in which cleaning l of the crud on the SFP walls will be performed to reduce exposure rates in l
, the SFP area.
j 24. The radionuclide inventory data provided are insufficient to determine waste I j processing requirements, waste volumes, waste classification, or identify special wastes such as oils or chelates. As requested earlier in connection with Section 2, a complete characterization of waste to be generated, i processed, and disposed during the SAFSTOR phase of decomissioning is '
needed.
- 25. In Section 7.1 it is stated that waste volume estimates assume a 40 to 60 percent void fraction in the waste containers. To maximize stability in a low-level waste disposal unit it is necessary to minimize voids in waste l
6 packages to the extent practicable. It is unclear whether the assumed voids are based on incomplete container filling or on the odd-shaped nature of rubble ar;d scrap wastes. In any case efforts should be made to
' minimize voids so that long-tem stability can be achieved at disposal sites.
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- 26. Note 1 on p. 53 states that most wastes from the dormancy period can be disposed at Dresden Units 2 or 3. We assume this means that wastes generated would be processed and shipped from Units 2 or 3 rather than disposed at Units 2 or 3. These wastes should be identified and accounted for as Unit I wastes.
- 27. In Section 7.4 nonradioactive wastes are briefly discussed. Criteria that will be used for separating nonradioactive from radioactive wastes should be specified. Also, the administrative programs and equipment to be used to ensure these wastes are properly separated should be described.
Technical Specifications
- 1) Offsite dosimeters should have their location documented on a map as part
, of the TS.
Offsitewatersamplingshouldbespecified(locationandradionuclide).
The sampling should be in a downstream location with respect to surface water and groundwater.
4 Onsite sampling should be described as to radionuclides sampled and the location.
- 2) TS (Section 5.0) should include training on 10 CFR Parts 19, 20, 61 and 71 as a minimum. A retraining frequency should be specified.
- 3) The procedure list (Section 5.0) should include calibration instruments, effluent releases, transportation and emergency plan implementing procedures.
- 4) In Section 5 the licensee has deleted the requirement to retain records of radioactive shipments. We consider these records should be retained for the currently required period of five years.
- 5) In a letter, dated December 10, 1987, the licensee responded to an allegation concerning potential degradation of the fuel racks and concrete structure as a result of stagnant conditions in the spent fuel pool for over two years. This led to the growth of micro-organisms which could corpromise the safe storage of the Dresden Unit 1 fuel due to microbial influenced corrosion. The Decommissioning Plan and Technical Specifications should address the corrective action taken to assure safe spent fuel storage.
Specifically, the Technical Specifications should address source and quality of makeup water and emergency makeup water and operability of spent fuel pool cleanup system including quality of spent fuel pool water.
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- 6) Define GSEP in paragraph A of page B.3/4.2-2.
1 1