Similar Documents at Fermi |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N4261999-10-25025 October 1999 Forwards Amend 17 to License DPR-9 & Safety Evaluation. Amend Revises TS by Deleting SR D.3.c,which Required Weekly Observation of Nitrogen Cover Gas Pressure within Sodium Storage Tanks Located in Sodium Building NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999 Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl NRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999 Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed ML20217P1661999-10-21021 October 1999 Forwards Insp Rept 50-341/99-17 on 990927-1005.No Violations Noted ML20217M0771999-10-19019 October 1999 Confirms Discussion Between GL Shear,M Mitchell,E Kosky, D Williams,B Rumins,D Harmon & W Rutenberg in Public Meeting on 990923.Purpose of Meeting Was to Discuss Current Status RP Program at Enrico Fermi 2 ML20217N9231999-10-15015 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40 ML20217E5671999-10-14014 October 1999 First Partial Response to FOIA Request for Documents.Records in App a Already Available in Pdr.App B Records Encl & Being Released in Entirety NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999 Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal ML20217D5331999-10-0707 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39 ML20217F5931999-10-0707 October 1999 Forwards Insp Rept 50-341/99-11 on 990724-0908.Two Violations Re Failure to Follow Procedures While Sampling Standby Liquid Control Tank & Wear Dosimetry Properly Being Treated as Noncited Violations ML20217B8261999-10-0404 October 1999 Forwards Summary of Decommissioning Insp Plan for Fy 2000. Plan Will Be Updated Annually & May Be Revised at Any Time Based Upon Future Insp Findings,Events & Resource Availability ML20212J8121999-10-0101 October 1999 Discusses Plant,Unit 2 Completion of Licensing Action for GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at Npps. Ack Efforts That Licensee Have Completed to Date in Preparing Plant for Y2K Transition ML20212K8881999-09-30030 September 1999 Refers to 990928 Meeting Conducted at Fermi Unit 2 to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff ML20217A3261999-09-30030 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38 NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations ML20212J8331999-09-27027 September 1999 Responds to Licensee 990924 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3/4.6.1.8.Ltr Documents 990923 Telcon with Util in Which NRC Orally Issued NOED ML20216G9791999-09-24024 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37 NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999 Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20216H3561999-09-23023 September 1999 Informs That During 990914 Telcon,L Sanders & M Bielby Made Arrangements with NRC to Inspect Licensed Operator Requalification Program at Fermi Nuclear Station for Week of 991129 Which Coincides with Util Regularly Scheduled Exam ML20216H4541999-09-23023 September 1999 Informs That During 990914 Telcon L Sanders & M Bielby Made Arrangements for Administration of Licensing Exams at Fermi Nuclear Station for Week of Jan 31,2000.NRC Will Make Exam Validation Visit to Facility During Week of Jan 10,2000 ML20212F3241999-09-20020 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36 NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999 Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public ML20217A9421999-09-0909 September 1999 Informs That NRC Plan to Conduct Addl Resident Insps Beyond Core Insp Program Over Next 6 Months to Assess Improvements in Areas of Procedural Compliance & Quality of Work. Historical Listing of Plant Issues Encl NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999 Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev ML20211Q0991999-09-0303 September 1999 Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999 Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999 Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d) ML20211G4951999-08-24024 August 1999 Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999 Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval IR 05000341/19990131999-08-19019 August 1999 Discusses Insp Rept 50-341/99-13 & OI Rept 3-98-039 Conducted Into Potential Misconduct of Operator Formerly Employed by De.Nrc Determined That Violation of NRC Regulations Occurred.Synopsis of IO Rept Encl NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999 Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation ML20211C0521999-08-17017 August 1999 Forwards Tables for Sections 3.6 & 3.7 of Draft Safety Evaluation of Proposed Conversion of Current TS to Improved Standard TS NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999 Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev ML20217E6181999-08-13013 August 1999 FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available IR 05000341/19990011999-08-10010 August 1999 Forwards Insp Rept 50-341/99-01 on 990619-0723 & Nov. Violation of Concern Because Operators Did Not Understand License Requirements & Placed Plant in Configuration Where EDG 11 Was Removed from Service IR 05000341/19990121999-08-0606 August 1999 Forwards Insp Rept 50-341/99-12 on 990712-0716.No Violations Noted.Insp Focused on Implementation of Plant Chemistry & Radiological Environ Monitoring Programs & Operation of post-accident Sampling Sys ML20211C4761999-08-0606 August 1999 Forwards Draft Safety Evaluation Re Proposed Conversion of Current TS to Improved Standard TS NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999 Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS ML20210N5451999-08-0303 August 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33 NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999 Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS ML20210J2121999-07-23023 July 1999 Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999 Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl ML20209H7211999-07-14014 July 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32 NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999 Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal ML20209F6571999-07-12012 July 1999 Forwards Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted.Weak Procedural Guidance,Communications Issues & Configuration Control Weaknessess Were Evident NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999 Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions ML20196J5511999-07-0202 July 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & DE Responses & 980729 for Fermi 2.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 as Result of Review of Responses ML20209C6141999-07-0101 July 1999 Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999 Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included 1999-09-09
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20247P9411989-05-17017 May 1989 FOIA Request for Final Open Item Transmittal Ltrs Per NRC Insp Procedure 94300B for Listed Plants ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20215L9971987-05-0101 May 1987 Forwards Final EGG-NTA-7205, Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Enrico Fermi-2, Informal Rept. Plant Conforms to Generic Ltr on Item ML20214R7141987-03-26026 March 1987 Forwards EGG-NTA-7574, Conformance to Generic Ltr 83-28, Item 2.2.2 - Vendor Interface Programs for All Other Safety- Related Components:Fermi-2, Final Informal Rept.Plant Conforms to Generic Ltr on Item ML20214Q2731986-09-11011 September 1986 Provides Results of Author 860903-05 & 09-12 Investigation of Whether Cracks in Base Mat Pose Safety or Operational Hazards.Base Mat Will Safely Carry Design Static & Seismic Loads & Exfiltration of Water to Ground Is Impossible ML20154K3631986-02-26026 February 1986 Forwards Listed Documents Containing Discussions of Embedment Plate Issue,In Response to 860221 Telephone Request.Addl Documents May Be Stored in Warehouse.W/O Encls ML20137P4581986-01-31031 January 1986 Forwards Rept on 860124 Site Visit W/J Kudrick & a Notafrancesco to Meet W/Util Representatives Re Fairbanks Morse Model 38TD8-1/8 Opposed Piston Engines.Statement for Work & Visit Also Encl ML20127M9561985-05-17017 May 1985 Forwards Responses to Re Questions & Comments on Final Idvp Rept ML20127M2791985-05-15015 May 1985 Grants Permission to Microfiche Proprietary Info Submitted in Support of Facility License Application ML20100D7411984-11-30030 November 1984 Forwards Revised Pages to Section 8.0 W/Instruction Sheet for Insertion Into Idvp Final Rept,In Response to 841126 Telcon.Exhibit 8.2.2-1 & Section 8.2.1 Revised to Assign Valid Design Control Observation to Root Cause ML20099E2431984-11-16016 November 1984 Responds to NRC 841105 Request for Info Re Generation of Potential Finding Rept Resulting from Annulus Pressurization Review Question.Cygna Expects NRC & Util to Resolve Annulus Pressurization W/O Addl Idvp Review ML20106D2351984-10-19019 October 1984 Forwards Section 8.0 to Rev 2 to TR-83021-1, Fermi 2 Idvp Final Rept, in Response to Bj Youngblood 840327 Request. Info Re Freezing in RHR Complex Included ML20084C2431984-04-20020 April 1984 Notifies of 840430 Meeting W/Util & NRC at Sargent & Lundy Ofcs to Discuss Idvp Structural Review Activities in Preparation for Response to Item 3 of NRC ML20082F0831983-11-14014 November 1983 Forwards Vol 4 to Idvp, Suppl to Final Rept ML20077F7051983-07-29029 July 1983 Advises That Suppl to Final Rept for Independent Design Verification Program Will Be Provided by 831014.Suppl Based on Util Comments & Specific NRC Comments at 830615 Meeting & in 830617 Telcon.Completion Schedule Encl ML20023B3841983-05-0303 May 1983 Forwards Pages 2.20-2.32 Inadvertently Omitted from Independent Design Verification Program Final Rept. ML20069M0511983-04-29029 April 1983 Forwards Independent Design Verification Program,Final Rept, Vols 1,2 & 3.Rept Presents Results & Conclusions of Review Conducted Per 821216 Independent Design Verification Program Plan ML20076A7011978-11-0101 November 1978 Forwards Errata to Subj Facil FSAR Amend 16 Which Was Recently Submitted to NRC ML20210E0611973-09-24024 September 1973 Forwards Description of Retirement Plan for Facility, Expanding on Plan Submitted w/730119 Ltr.Details Re Disposition of Sodium & Blanket Matls Unknown.Sodium May Be Shipped to Hanford & Blanket Matl to Savannah River ML20210E0061973-01-19019 January 1973 Forwards Retirement Plan for Facility.Early Approval of Proposed Blanket & Sodium Onsite Storage Requested.Fully Detailed Retirement Plan Cannot Be Developed Until Questions Re Blanket & Sodium Storage Settled ML20210D9711972-04-28028 April 1972 Submits Info Re Decommissioning of Facility,Per AEC 720331 Request.Major Activities of Decommissioning Plan Listed. Bases,Schedule & Cost Estimates for Decommissioning Encl 1989-05-17
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999 Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999 Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl ML20217N9231999-10-15015 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40 NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999 Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal ML20217D5331999-10-0707 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39 ML20217A3261999-09-30030 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38 NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations ML20216G9791999-09-24024 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37 NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999 Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20212F3241999-09-20020 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36 NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999 Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999 Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999 Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld ML20211Q0991999-09-0303 September 1999 Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999 Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d) ML20211G4951999-08-24024 August 1999 Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999 Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999 Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999 Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev ML20217E6181999-08-13013 August 1999 FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999 Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS ML20210N5451999-08-0303 August 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33 NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999 Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999 Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl ML20209H7211999-07-14014 July 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32 NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999 Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999 Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions ML20209C6141999-07-0101 July 1999 Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0049, Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure Encl NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999 Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included ML20209C1081999-06-29029 June 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 30 NRC-99-0050, Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included1999-06-24024 June 1999 Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included NRC-99-0075, Forwards Operator License Renewal Application,Nrc Forms 398 & 396 for CR Effan,License SOP-30186-3.Encl Withheld1999-06-22022 June 1999 Forwards Operator License Renewal Application,Nrc Forms 398 & 396 for CR Effan,License SOP-30186-3.Encl Withheld ML20212J3861999-06-18018 June 1999 Forwards Rev 29 to Approved UFSAR LCR That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0047, Responds to NRC 990513 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Revised Design Calculation DC-5957, GL 96-06 Calculations, Encl1999-06-0909 June 1999 Responds to NRC 990513 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Revised Design Calculation DC-5957, GL 96-06 Calculations, Encl ML20195G2001999-06-0808 June 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 28 ML20195E7391999-06-0303 June 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 27 NRC-99-0046, Forwards Rev 6 to Fermi 2 ITS Submittal ,to Provide Remaining Responses to NRC RAI Re ITS Section 3.3, & Update ITS Submittal to Reflect Responses.Brief Abstract of Changes Contained in Attachment 11999-06-0202 June 1999 Forwards Rev 6 to Fermi 2 ITS Submittal ,to Provide Remaining Responses to NRC RAI Re ITS Section 3.3, & Update ITS Submittal to Reflect Responses.Brief Abstract of Changes Contained in Attachment 1 ML20207D9631999-05-26026 May 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section) ML20195B3381999-05-19019 May 1999 Forwards Rev 25 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section) NRC-99-0040, Requests NRC Approval of Revs to Weld Tables of Encl Relief Requests RR-A21,rev 1 & RR-A22,rev 1.Revs Do Not Impact Basis for Original Requests for Relief Because There Is No Change to Technical Basis or Proposed Alternative1999-05-14014 May 1999 Requests NRC Approval of Revs to Weld Tables of Encl Relief Requests RR-A21,rev 1 & RR-A22,rev 1.Revs Do Not Impact Basis for Original Requests for Relief Because There Is No Change to Technical Basis or Proposed Alternative NRC-99-0039, Requests Relief from ASME Section XI Requirement to Examine Essentially 100% of Selected Category B-J Pipe Welds,Per 10CFR50.55a(g)(5)(iii).Relief Request RR-A23,encl1999-05-14014 May 1999 Requests Relief from ASME Section XI Requirement to Examine Essentially 100% of Selected Category B-J Pipe Welds,Per 10CFR50.55a(g)(5)(iii).Relief Request RR-A23,encl NRC-99-0041, Requests Relief from ASME Section XI Requirements to Examine Essentially 100% of Accessible Category B-D Nozzle Welds,Per 10CFR50.55a(g)(5)(iii).Rev 1 to Relief Request RR-A6,encl1999-05-14014 May 1999 Requests Relief from ASME Section XI Requirements to Examine Essentially 100% of Accessible Category B-D Nozzle Welds,Per 10CFR50.55a(g)(5)(iii).Rev 1 to Relief Request RR-A6,encl NRC-99-0038, Requests Relief from ASME Section XI 1980 Requirement to Examine Essentially 100% If Category B-A RPV Shell Weld Lengths,Per 10CFR50.55a(g)(5)(iii)1999-05-14014 May 1999 Requests Relief from ASME Section XI 1980 Requirement to Examine Essentially 100% If Category B-A RPV Shell Weld Lengths,Per 10CFR50.55a(g)(5)(iii) NRC-99-0045, Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl1999-05-0707 May 1999 Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses1999-04-30030 April 1999 Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses NRC-99-0059, Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate1999-04-29029 April 1999 Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate ML20206E2941999-04-28028 April 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 24 NRC-99-0037, Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl1999-04-26026 April 1999 Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl 1999-09-08
[Table view] |
Text
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POWEn REACTOR DEVELOPMENT COMPANY AT - 7L R eceWesBAftete 1911 FIRST STREET W DETROIT,MICIIICAN 48226 P....PTT.,
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TEL EPDeOMEs NEWPOR T. NICHIC AN January 19, 1973 Wr. L. Hanning Huntzing Director of Regulation g U. S. Atomic Energy Coussissica W Washington, D. C. 20545
~
Dear Mr. Huntzing:
. FADC is currently engaged in preparing the reactor fuel for
- shipment to Savannah River for reprocessing. Actual ahtonent is ;
ccheduled to start before the end of January. j Simultaneously, FRDC has been devalopic 'rement plan for the plant. The premises for this plan , aitted in FRDC's letter to you dated April 28, 1972 and were uti:ized in PRDC's financial projections submitted to the Commission last year. Enclosed with this letter is a more detailed outline of the plan.
In connection with the retirement plan, it should be remembered that a significant portion of the Fermi I plant (i.e., that part of the :
I electric generating system starting with and downstream from the second-ary sodium system where it enters the steam generator building) is owned by The Detroit Edison Company. This Edison-owned portion is non-nuclear
., and has no radioactivity. We understand that Edison plans to continue, 3 as in the past, to use the Fermi I turbines for peaking power utilizing T fossil fuel. In addition, Edison plans to install at least two 1100 Mwe boiling-water reactors on the site. One of these reactors is already l 4
a der construction.
In view of the foregoing, the retirement plan relates principal-
. ly to the portion of the Fermi plant owned and operated by PRDC, and tckes into account the added protection afforded by the fact that the :
r; tired plant will be physically a part of a sizable complex of nuclear '
fccilities.
It is anticipated that at an appropriace time, PPDC will be i dissolved and E.fison will assume responsibility for the entire plant Since retirement costs and post-retirement curveillance expenses are censitive to the parameters of the retirement plan, the nature of the mmmmar 4.10
FowER' REACTOR DEVEtorMENT CAMPANY Mr. L. Manning Muntzing ~2- January 19. 1973 arrangement between PRDC and Edison cannot be definitired at least unti}
AEC action in principle is forthcoming on those aspects of the pisn which, if not approved, would result in major increases in previously estPnated costs. The two principal items in this category are co-site storagc of '
the radial blanket subassemblies and of the primary sodium. Fcr example, the incremental cost of removal, shipment and burial of the radial blanket is estimated at about $2.2 million.
In terms of PRDC's schedule for fuel removal and sodium drainage >
of the rasetor, PRDC needs to determine by the end of .Tebruary *dhether or not the blanket elements can, as proposed, be: left in the reacter. Delsy beyond that time will result in the added costs of having to mark time.
Also, until the questions of blanket and sodium stcrage are settled, PP.DC cannot develop a fully detailed retirement plan together with propcsed technical specifications to cover the retired facility. <
for all the foregoing reasons, early approval of the prPPosed blanket and sodium on-site storage is requested. If thir approval cannot at this stage be given definitively, then PRDC requests that sue.h approval .
be given in principle subject to provision of such further inforzation er action as the Commission may require and/or subject to subcequent agreement by The Detroit Edisen Company. In this latter connectica, Edison hss informally expressed to FRDC its concern about the fincncing of Llan}.et removal and burial should such acticn be required by the Commissicc at some future time, j Va weald be glad to cry to ans'ser any questions you or your staff may have. )
Ve truly yocs ,
a hVg (
- Eld % L. Alext.nderson Gencral Managt.r T bcce M. L. Batch J. B. Nims '
ELA/dem R. C. Callen R. G. Rateick Enclosure W. L. Cisler W. W. % ite A. P. Dennell H. A. WagncT cet Mr. John R. Hamann J. B. Denniston C. H. K utmore -
(
Vice President Y.. P. Johnson P. Erickson - AEC l The Detroit Edison Company J. E. Mayern R. Schemel - ([C W. C. Marrirton A. A. Ehoudy E. C. Newton E. H. Pagt
.. )
'. 4.11
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towta RU.cloot DEVELOPAa7 COMPAW _
RETIRFXDtr PLAN El e
Disregarding the fuel, which is being shipped off-site, the princip.a1 a kontces of radie setivity presently on-cite are: (a) the axial blanket sectior.s g of the core subast.+.ablies, (b) the radial blanket cubassemblies, (c) the pri: nary W sodium, (d) activated materials within the primary system ani (e) miscellaneous. ;
contaminated faqvipment curside the reactor building. As met forth more. fully belev, scene of this radioactive material will be shippel,off-site a.r.d some will he stored on-site. Insofar as such material remains on-site, the relevant .
I sys,tems or attorate areas will be sealed or otherwise isolat.ed and appropriate monitoring, sorveillse,:e, acd related progr.ac.s put inte effect. A:tess to a'rean whe.r~ e radioactivity rsmains will be limited to authorised personnel. Added protection C11'. be provided I;y the secess-courrel and sarveillance prot, rams
" associated with ct!er auchar reactors ncw under construction c:r planned for the g '
site. M -
- 1. ,Radicactive Blanket Elements After shipment of fuel is completed, the. axial blanket sections of the fuel subasstablies will be shipped off-stte fer disposal sit a !.icensed burial .
site. Contracts will be pitced Gith Nuc. lear Engineering or e rsinnilar crganiza- <
tion to provide for the trt.nsportation and buriel and for any licenses or per- l t
mite required to carry cut this activity.
All radial blanket subasse.nblies ocV in the reactor vessel (approximately
- 37 inner radial b2ankets and approximately 484 cater radial blankuts) are t.o be i left ic place. Other radial blanket subassemblies now in the pools may be returned tg the reactor, to the decay tank in the reactor building, or shipped to a litensed L'arial site. The activat.fon levels ard pirtonium centent associa-ted Vith ,*.hese cliements as calculated for Jsine,1,1973, ate listed in Table 1. l The less than 6 Kg of plutcaiva involved in distributed in over 25.000 Kg of depleted uranium and at a lnaximum concentratio c. of abeut 0.1% of the urantuta. ,
b i T'nere will be two 1100 !!we BWRs on t'ne site with :far raors plutoniun involved. I The priniary rystum of which the reacter vesssi is a part will be sealed, a sarveillance progran will be establishedt and access to the facility will bc ILuited to authorized personr.el, all sis more fully de9cribed below. In FRDC's t judgnent, leaving the radial blanket elecents in place appears to.bn at least as satisfactory a d18Fosition of this materiel as off-site barial,would be. ,
- 2. Miscellaneous Contatrinated Equipment and Paterials
) ,
l Unirradiated radial blanket subassemblies, donmy subassemblies, sources, i and other miscellaneous tctivated uaterials and e.quipr.ent will be stored in ,
the reactor or shipped to a licensed burial site. Sous, mis.:allaneous contami-l nated or other equipnent nct shipped to a burial site will be dismantled and l utored in the equipment decay tanks within the reactor building. The a nount g "
I and attivity of this equipment las not yet been idantified. .5 4.12
- i
F P093 REACTOR DeMimMENT CCMFANY L
.1-l
- 3. raiioactive Endi'ra ,
Radioactive pris.ary caodiun and modium from the transfer tank in the Fuel and Repair Luilding (FARB) will be stored on site. The sodium in the l
' prirary system will be syphoned to the sodium servica building and allowed to f reeze in the three 15,000 gallen storage tankr. In the sodium Storage Roc"a and in the cold trar, hot trap, and plugginF meter system in the Cold Trap Room. These two rooms are described in I.N. 4 of the H.S.R. and will I
he closed so as.to prevent entry except through a door which is either locked or welced 'ahst or by removal of part of a shield wall. An inert nitrogen cover gas 'ander s11gnt positive pressure will be maintained over the frozen i
sodium in the storage tanks. In the event that the indicated repositories do not provide sufficient capacity, auxiliary storage capacity will be pro-vided or the excess radioactive modium will be shipped off-site for burial.
l The activity levels asrociated with the sodium to be so stored, as calculated for June 1,1973, are listed in Table 2.
R I'-
The method of dealing with residual radioactive codium in the transfer tank and in the cold Crap in the TARB has yet to be decided.
- 4. itcactor' Building Penetrations, 1
These penetrations are described in Table 110.1 of the H.S.R. Sodium and 1ts piping will be cut and capped just external to the building. One j of the above-floor ventilation pipe penetrations of the building will not be capped bot vill cantsin an absolute filter co permit the building to brev he. Electrical anti instrumentation penetrations will be lef t as is.
The three personnel and equipment access penetrations will be dealt with as follova: the equipoest door, which is op2rable only from the inside, will I be lolted closed; the emergency mirlock will be changed so as to provide exit o
but not entry; the perscnnel airlock will be locked on the cutside.
- 5. Sealing of the Primarv System l
After transfer cf the primary nodium to the sedium service building, the primtry system will be cooled. fy sealing, a Ecs-tight system will then I be forn.ed consisting of the prosent primary sodium system plus the primary l abield tank, the machinery dome, and the primary sodium service and secondary sodium systems out to che caps pinced on the pipes. This system will then be back filled with carbon dioxide which will react with the recidual sodium to l form an inert solid compound Na2CO 3 . Carbon dioxide gas will be maintained under positive pressure within the t.ealed system. The activity levels h
W associated with t*nis system, exclunive of the radial blankets, are shown in Table 3 as es1culated for June 1,1973.
If it were necessary to remove the radini blanket subarsedlies from the I
(
reactor versel at some later date when nurmal fuel handling equipuent is no
- 4. n 1
PowEn REACTOR DEVE14PMENT COMPANY
, 3 i
. longer operable, the CIDs could be removt.d from the rotating shield plug.
Through this large accesa hole, tools could be inscrced to remove the subassemblies into a chielded contciner.
- 6. The Secondary Sodium System Sodium fo: this acn-radioactive syatem has been drained to storage tanks from which it will be recavered and sold. The residual sodium in the piping and equipment external to the building will be reacted, probably with steam, so that chare is no hazard from fire or from hydro-gen formation. Components of the system can then be salvaged or scrapped as time peruits and need fcr the space for other uses arises.
- 7. Reactor Auxiliary and Fuel Handling Systens Pools and waste liquid tar.ks will Ire drained, flushed and cleaned of any significant contamination. All componects of the waste gas, clean gas, recirculating gas and steam cleaning systems will be cleaned of significant contamination if possible. Whenever (and if) this is not possible, the component will be saaled and access to the etea made such that entry can be gained only through well locked doors cr by removal of heavy shielding plugs.
- 8. Facility Area Fene_e_
Either (a) the present fence (see Figure 501.5 of the H.S.R.) will be maintained intact or (b) it will be rerouted so as to allow easier access to uncontaminated areas. In either event, chete will be a single access gate manned continuously by a security guard or locked.
- 9. Alministrative and Technical Files -
L Legally required anf other significant records will be retained. The li Letroit Edison Company is expected to be ghe file custodian once PRDC is dissolved.
l l 10. Surveillanc.e
- a. Physical Barrier Inr.pection, Visual inspection of the fence and buildings will be made weekly to l determine that the physical barriers are intact, and gates and doors are properly locked.
- b. Cover Cas Pressu3 Nitrogen cover tas will be maintained over stored sodium, and entbon
- dioxide cover gas will be ma{ntained over those systems .containing i residaal radioactive soditra. The cover gas pressure of each of thesc
- Systems which can be completely closed by welding will not need a controlled atmosphere 4.14
l 1
Powsa RE C1DR DEVEIAPNENT COMPANY l
systems will be maintained at approximately 1 psig. A low pressure switch will energize a light located in a continuously manned control room. The alarm systems will be tested (uarterly.
- c. Water Seepage
}
'm To detect the presence of water seepage into regions which contain g stored or residual radioactive sodium, water detectors will be installed.
Alarms for each of these regions will be located in a control room and monitored continuously. Those regions selected for water seepage surveil-lance are:
- 1) The space between the biological shield and the
, Reactor Building
- 2) Primary sodium overflow tank pit
- 3) Primary sodium cold trap room
- 4) Primary sodium storage tank room
- The alarm systems will be tested quarterly.
- d. Environmental Radiation Survey To verify that no detectable release of radioactive material has occurred, samples of 1) airborne dust, 2) precipitation, 3) surface water, and I 4) drinking water will be sampled quarterly and analyzed for gross alpha, gross bets and gamma activity according to the following:
Sample Measurement Airborne Dust Gross Alpha, Cross Beta Precipitation Gross Alpha, Cross Beta and Gamma Surface Water Gross Beta Drinking Water Gross Beta Sampling locations will be selected from those shown in the present technical specifications. Once Detroit Edison's full Fermi 2 monitoring program is in effect, these items will automatically be covered and available in Edison's reports.
, e. Facility Radiation Survey Radiation surveys will be made to check for the presence of gamma radia-tion and transferable contamination. Gamma radiation measurements will be made using portable survey instruments and the contamination checks using smears. Surveys and smears will be made of the following areas on e 4.15 1
POWEn REACron DEVELOPMENT COMPANY
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quarterly ba, sis. ,
pntalment Building
- 1) Fxit port area
- 2) M&chinery dome - door and window seals
- 3) Operating floor Fuel and Repair Building
- 1) Cold trap room access semis Auxiliary Butidings l
- 1) Cold trap room seals,
- 2) Godium storage room seals
- 11. Administrative Cortrols A person will be designated to control the keys to the locked gate and doors and to control authorized entry into restricted areas. The results of the environmental and facility radiation surveys will be reported to the AEC qJarterly in writing. An annual renort on the status of the deactivated facility will be submitted to the A!:C. Unusual events will be reported to the AEC as required by license and by means of the annual report. Records k or logs will be kept with respect to the environmental and facility radiation W l surveys, water seepage, testing of the cover gas and water seepage alarm l
. systems, inspection of the physical barriers and unusual events.
l E
B l
I B
January 22, 1973
TABLE 1 CALCULATED ACTIVITY OF THE RADIAL BLANKET DUE TO FISSION PRODUCTS AND STAINLESS STEEL (June 1. 1973)
Fission Products Attivity (Curies)
Sr-90 (28.8 y) 1900 Y-90 (64 hr) 1900 Y-91 (61 d) 300 l Zr-95 (65 d) 400 Ru-106 (368 d) 1000 Rh-106 (30 sec) 1000 Sb-125 (2.7 y) 70 Cs-137 (30 y) 1700 Ce-144 (282 d) 15000 Pr-144 (18 m) .- 15000 Pm-147 (2.6 y) 800 Total Fission Products 39000 Stainless Steel co-58 (71 d) 70 Fe-59 (45 d) 1 Co-60 (5.3 y) 440 Cr-51 (28 d) 50
, Total Stainless Steel 510 Total 39500 PLUTONIUM CONTENT OF THE RADIAL BLANKET Isotope Mass (kg)
Pu-239 5.92 Pu-240 .002 Pu-241 5 x 10' Pu-242 %0 Total 5.92 4.17
l g1
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, TABLE 2 ACTIVITY OF STORED PRIMARY SYSTEM SODIUM (Curies)
B Isotope Total Activity
.. B 137 Cs 1.7 Sr 90 y,7 Na 0.4 All Others <0.04 3, Total 3.8 i
Stored Quantity - 356,000 lb.
Based on previous aseasurements, final B
values to be based on measurements in progress In addition, activity in the primary sodium service system coid trap is estimated to be 5 curies. Principal isotopes are Cal 37 and Sr90 4.18
n.-- ~
TABLE 3
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CALCULATED ACTIVITY OF STAINLESS STEEL WITHIN THE REACTOR VESSEL
-d ' (NEGLECTS BIANKET SUBASSD(BLTES) s, (June 1,1973) i 1
Activity Source (Curies)
Component Co-58 Fe-59 Co-60 Cr-51 Total Control & Safety Rod Qiannels Portion in Core , 21 L .9 L 30 Portion in Blanket 1 L .9 L 10 Portion between Blanket E and holddown L L .9 L 1 Molddown Mechanism Inner Region +1 1 158 L E Outer Region (R > 41.cm)
Shield Bars L L 70 L 158 70 12 .3 105 .1 117 Thermal Shield E Lower Upper
,- 1 L
.2 L
88 9
.1 L
89 9
Holddown Coluan L L 4 L 4 Safety Rods - Poison Section Lower L L L L --
Middle L L L L --
Upper L L L L --
Rotating Plug L L L L Support Plates .7 .3 965 .1 975 Support Structure .1 .1 35 L 35 Support Structure Shielding .2 .1 35 . L 35
.* low Baffles L L 2 L 2 Conical Flow Guide L L L L -
Imwer Reactor Head Shielding L L 18 L 18
' Transfer Rotor L L L L --
OEM L L 6 L 6 Reactor Vessel - Negligible -
Total 36 <2 1514 <2 %1550 L = less than 0.1 curies 4.19
. _ _ _ _ _ _ _ _ _ _ _ _ _ .