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MONTHYEARML20212H2861999-09-24024 September 1999 Proposed Tech Specs 3/4.6.1.8,allowing Continued Operation Until Next Plant Shutdown at Which Time Valve T4803F601 Will Be Repaired Project stage: Request 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 Project stage: Other 1999-09-24
[Table View] |
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:OUTGOING CORRESPONDENCE
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 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 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 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 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 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 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 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 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 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 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 ML20210J2121999-07-23023 July 1999 Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation 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 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 ML20209E9991999-06-30030 June 1999 Forwards Insp Rept 50-016/99-01 on 990614-17.No Violations Noted.Potential Weakness in Airborne Effluent Concentration Assessment Identified ML20209B2471999-06-29029 June 1999 Informs That NRR Revised Schedule for Conversion of Fermi 2 TS to Improved Std Ts.Planned Amend Date Has Been Moved to 990930 & Date for Draft Amend Has Been Moved to 990806 ML20207E4961999-06-0101 June 1999 Forwards Insp Rept 50-341/99-07 on 990402-0515.One Violation of NRC Requirements Occurred Re Failure to Keep TS Requirements Re Approval of Overtime Deviations.Violations Being Treated as non-cited Violations,Consistent with App C ML20207D3311999-05-26026 May 1999 Forwards Insp Rept 50-341/99-04 on 990503-07.No Violations Noted.During Insp,Nrc Observation of Licensee Activities Showed Radiological Emergency Response Preparedness Program Maintained in Effective State of Operational Readiness ML20206N7351999-05-14014 May 1999 Forwards RAI Re Plant Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During DBA Conditions ML20206N4621999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created. Reorganization Chart Encl ML20206J9131999-05-10010 May 1999 Forwards SE Finding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, ML20206Q7041999-05-0606 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-341/99-02 on 990308 ML20206G4931999-05-0505 May 1999 Refers to DE 980804 Requests for Relief (PR-8,Rev 2 & PR-12) from IST Requirements of ASME Code for RHR Pumps.Review of Relief Requests Completed.Se Approving Relief Requests Encl ML20206K4031999-04-29029 April 1999 Forwards Partially Withheld (Ref 10CFR73.21) Insp Rept 50-341/99-08 on 990405-09.No Violations Noted.Concern Expressed Over NRC Observations of Poor Performance Demonstrated During Some Contingency Response Drills ML20205T3841999-04-23023 April 1999 Forwards Insp Rept 50-341/99-03 on 990218-0401.Two Violations Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20205S8481999-04-20020 April 1999 Informs That Changes in Rev 22 Do Not Decrease Effectiveness of Emergency Plan & Plan Continues to Meet Stds of 10CFR50.47(b) & Requirements of App E to 10CFR50.NRC Approval Is Not Required ML20205Q7001999-04-15015 April 1999 Forwards Amend 16 to License DPR-9,allowing Possession of Nominal Amount of Special Nuclear Matl,In Response to 980717 Application.Related SER & Notice of Issuance Also Encl ML20205P1691999-04-14014 April 1999 Forwards Insp Rept 50-341/99-06 on 990315-19.No Violations Noted.Insp Focused on Aspects of Radioactive Effluent Monitoring,Liquid Waste Processing,Esf Filtration & CR Habitability & Solid Waste Mgt & Transportation Programs ML20204E4061999-03-19019 March 1999 Forwards Insp Rept 50-341/99-05 on 990308-11.No Violations Noted.Insp Concluded That Fire Protection Program Was Effective ML20204E0271999-03-17017 March 1999 Forwards SE Accepting Licensee & Suppl, ,which Requested NRC Approval of Alternative Rv Weld Exam,Per 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5), for Plant,Unit 2 for 40-month Period ML20207L7281999-03-0909 March 1999 Informs That Util Ltrs & 981026 Responding to GL 96-01, Testing of Safety-Related Logic Circuits, Completes Licensing Action for Fermi 2 ML20207J1401999-03-0808 March 1999 Forwards Insp Rept 50-341/99-02 on 990111-29 & Notice of Violation.One Violation Identified in Area of Design Control.Violation of Concern Because Errors Existed in Three of Six Calculations Reviewed ML20207G5711999-03-0404 March 1999 Discusses 990301 Meeting Between GL Shear,M Mitchell, D Williams,C Budnik & M Clements Re Current Status of Radiation Protection Program at Facility ML20207E2491999-02-22022 February 1999 Discusses Licensee 980617 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program for MOV Periodic Verification for Fermi-2.Forwards RAI Re Fermi-2 Response to GL 96-05 ML20207E6451999-02-22022 February 1999 Submits Correction to Insp Rept 50-341/98-15 Issued on 981207.Rept Incorrectly Documented That Loose Internal Sleeving on Turbine Control Valve Caused Power Oscillations Greater than 10% During Plant Operation ML20203F6761999-02-11011 February 1999 Forwards Request for Addl Info Re Conversion to Improved Standard Ts,Section 3.6 for Fermi 2 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20203F6911999-02-10010 February 1999 Discusses Completion of Licensing Action for Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors, ML20203G6411999-02-0808 February 1999 Informs of Receipt of Encl FEMA Correspondence Received 990119,transmitting FEMA Final Exercise Rept for 980608 Plume Exposure Pathway Exercise at Enrico Fermi II Npp.No Deficiencies Were Identified During Exercise ML20202H8881999-02-0404 February 1999 Clarifies Intent of RAI Re Plant Staff Qualifications & Reg Guide 1.8,Rev 2, Qualification & Training of Personnel for Nuclear Power Plants, Dtd Apr 1987.Staff Position on Issue Neither New Nor Different Position from Previous Position ML20202H6111999-01-25025 January 1999 Requests Addl Info Re Conversion to Improved Std Tss, Section 3.5 for Fermi 2 ML20206S1111999-01-21021 January 1999 Forwards Insp Rept 50-341/98-19 on 981110-990104.No Violations Noted.Inspectors Noted Potential Trend Re Documented Operability Assessments That May Not Have Been Performed for C/A Resolution Documents ML20199G7561999-01-14014 January 1999 Forwards Request for Addl Info Re Conversion to Improved Stds Tss,Section 3.3 for Plant ML20198S3101999-01-0606 January 1999 Forwards Amend 15 to License DPR-9,consisting of Changes to TS in Response to 980128 Application.Related SER & Notice of Issuance,Also Encl 1999-09-09
[Table view] |
Text
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1 e . p Ett
): $ UNITED STATES J 7j. . NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. enans wt 4,g /. September 27, 1999
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Mr. Douglas R. Gipson SeniorVice President
- Nuclear Generation Detroit Edison Company
'6400 North Dixie Highway Newport, Michigan 48166-
SUBJECT:
. NOTICE OF ENFORCEMENT D!SCRETION FOR THE DETROIT EDISON
' COMPANY REGARDING FERMI 2 (TAC NO. MA6521, NOED NO. 99-6-007)
Dear Mr. Gipson:
. By letter dated September 24,1999, you requested that the NRC exercise discretion not to enforce compliance with the actions required in Technical Specification (TS) 3/4.6.1.8. Your l letter documented information.previously discussed with the NRC in telephone conferences at j 2:00 p.m. and 4:45 p.m. on September 03,1999. The principal NRC staff members who 1 participated in the telephona conferences were: j Suzanne Black, Acting Director, Project Directorate (PD) lli, Office of Nuclear Reactor Regulation (NRR)
Claudia Craig, Chief, Section 1, PD lli, NRR Andrew Kugler, Project Manager, Section 1, PD lli, NRR George Hubbard, Chief, Balance-of-Plant and Containment Systems Section, Plant Systems Branch, NRR .
Richard Lobel, Senior Reactor Engineer, Plant Systems Branch, NRR
- Marc Depas, Deputy Director, Division of Reactor Projects, Region ill (Rlli)
Steven Reynolds, Deputy Director, Division of Reactor Safety, Rlli pg"p9 Anton Ve9el, Chief, Branch 6, Rlli David Passehl, Project Engineer, Branch 6. Rlli gh '
Steven Campbell, Senior Resident inspector, Fermi 2, Rill You stated that at 1:45 p.m. on September 22,1999, penetration X-26 (drywell air purge) failed its local leak rate test (LLRT) performed in accord:nce with TS 4.6.1.8.2, requiring entry into
.TS 3.6.1.8, Action b.' Action b. required that the inoperable (i.e., high leakage) valve (s) be repaired within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Otherwise, you would be required to place the plant in hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and co!d shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Your staff determined that almost all of the leakage was through the inboard isolation valve (T4803F601) on penetration X-26 and that it was not possible to repair this valve without shutting the plant down.
You requested that a Notification of Enforcement Discretion (NOED) be issued pursuant to the NRC's policy regarding exercise of discretion for an operating facility, set out in Section Vll.c of the " General Statement of Policy and Procedures for NRC Enforcement Actions" (Enforcement Policy), NUREG-1600, and be effective until the associated exigent TS amendment is issued and implemented. This letter documents our telephone conversation on September 23,1999, at 5:30 p.m., when we orally' issued this NOED.
~
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k c D.R. Gipson Licensee Event Descriotion and Evaluation Penetration X-26 has three isolation valves that are tested concurrently. The single inboard isolation valve is a 24-inch butterfly valve (T4803F601) and the two outboard isolation valves (in parallel) are a 24-inch butterfly valve (T4800F407) and a 10-inch butterfly valve (T4800F408).
.The piping configuration is such that the T4800F407 is open directly to secondary containment on one side. This configuration lends itself to a direct visualinspection of the valve seat.
T4800F408 connects to the nitrogen supply system. During leak testing, boundary valves are used to isolate T4800F408 from the nitrogen system. A vent valve between T4800F408 and the
= test boundary valves is used to depressurize and vent the piping outboard from T4800F408.
On September 22,1999, a LLRT was performed for penetration X-26 as required by TS
- Surveillance Requirement 4.6.1.8.2. This test is performed by pressurizing between the inboard and outboard isolation valves and measuring the total !eakage of the isolation valves. The penetration exceeded its TS limit of less than 0.05 L. (equivalent to 14.87 standard cubic feet per hour (SCFH)). The penetration leakage rate was 26.7 SCFH. Based on direct observation of T4800F407 and observation of an open %-inch vent connection outboard of T4800F408, test personnel determined that the ' penetration failed itt LLRT due to seat leakage through !
T4803F601. Subsequently, valve T4803F601 was stroked under light pressure in an attem.9t to clear the sealing surfaces of any debris. The LLRT was performed again, and the leakage from
._p enetration X-26 increased to 82.85 SCFH. Since the only evolution performed between the two LLRTs was the stroking of T4803F601, this subsequent LLRT further substantiated that the leakage was attributable to T4803F601. Visual and audio inspection by a Level ll VT Inspector (utilizing Snoop, a soap bubble-type test, to aid in leak detection) for leakage at the exposed side of T4800F407 and at the vent connection outboard of T4800F408 during both tests on ;
September 22,1999, revealed insignificant leakage relative to the measured leakage rates. A I Level lli VT Inspector confirmed the initial visual inspection and confirmed that T4800F407 and I T4800F408 were an insignificant contributor to the leakage during the second test. Snoop was J
. utilized to aid in leak detection during both tests. Snoop was applied to the seal of T4800F407 l
and minor bubbling was observed. It was also used at the vent connection outboard of l T4800F408 and no leakage was detected through this valve.
The licensee reviewed the LLRT and maintenance records and did not find any indication of an adverse trend for this penetration. Results of previous LLRTs for the penetration ranged between approximately 0.6 SCFH and 1.75 SCFH since October of 1998 (four tests). Failure of ,
T4803F601 was not anticipated and, based on the magnitude of the leak and the change in
- leakage following valve stroke, the licensee conc!uded that the likely cause of the leakage is failure of the seal. The seal was replaced during the Sixth Refueling Outage (autumn of 1998). '
Based on the previous test results, the licensee concluded that it is unlikely that the cause of this test failure is attributable to any valve other than T4803F601.
i The overall primary containment leakage allowed by TS 3/4.6.1.1 is 0.6 L,. This equates to i
'178 SCFH. The known leakage from containment prior to September 22,1999, was 67.28 SCFH, leaving 'a margin of 110.72 SCFH. The leakage from penetration X-26 is
. 82.85 SCFH, leaving a margin of 27.87 SCFH, when considering T4803F601 as a single boundary valve (i.e., not crediting the outboard valves). The outboard valves, when closed, would serve to significantly increase this' margin, even though the leakage through the outboard 4
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<- L D.R. Gipson - valves could not be quantifiedi in addition, with the penetration X-26 outboard valves closed, the licensee concluded that the leakage for this penetration remains well within the 0.05 L, limit associated with TS 3.6.1.8. The licensee concluded that the proposed action will not change the - .!
types or amounts of effluents that may be released o# site, nor increase individual or cumulative o
occupational radiation exposures, since the proposal is expected to maintain the overall leakage ,
of the penetration within the required limits, l The licensee's safety basis for this request is summarized as follows:
j The action to isolate the affected penetration using outboard isolation valves T4800F407 and T4800F408. While leak rate testing forthis penetration can not quantify the leakage of the outboard valves individually, the leakage rate through these isolation devices is believed to be well below the acceptance enteria, as discussed above. In addition, the -
compensatory action to verify the penetration is isolated on a periodic basis supports the T safety function of the valves to isolate following an accident. Reliability of the resilient seals in these valves and the other similar. penetrations at Fermi 2 has been high, providing confidence that unexpected degradation is not occurring in these valves.
- T4803F601 is not a risk-significant component in the Level 1 Fermi 2 Probabilistic Safety i Analysis' (PSA). T4803F601 is not an initiator of an event that leads to core damage .
and does not mitigate a core damage event. The failure of T4803F601 has no effect on core damage and is not modeled in the Level 1 Fermi 2 PSA.
T4803F601 is a credited component of the Level 2 Ferm! 2 PSA. T4803F601 or the outboard isolation valves must close to isolate penetration X-26. The success criterion is that either inboard or outboard isolation valves in a line noust close and remain closed for 24 hcnrs. With the penetration isolated by the outboard isolation valves, the licensee concluoed that the failure of T4803F601 has no effect on the Level 2 PSA results and the success criteria for penetration X-26 is met and, therefore, failure of T4803F601 is not risk significant.
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- In conjunction with the discretion granted in the NOED, the following compensatory actions will be' taken- l I
- 1. Isolation valves T4800F407 and T4800F408 (both normally closed) will remain closed and be deactivated, assuring the valves remain closed until T4803F601 is repaired.
T4800F407 and T4800F408 will not be cycled until the plant is shutdown to repair the !
T4803F601.
- 2. Isolation valves T4800F407 and T4800F408 will be verified closed every 31 days.
' In simple terms, the Level 1 PSA evaluates the response of the plant to transients, expressed in the form of core camage frequency. The Level 2 PSA evaluates the containment t esponse to the events developed in the Level 1 PSA.
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D.R. Gipson l
- 3. Because the leakage through the outboard isolation valves cannot be individually t
quantified, a flanged cover will be installed over the opening of T4800F407 by
- September 28,1999, to provide an additionalleakage barrier. This flange will remain in place until the plant is shutdown to correct the penetration leakage.
- 4. Leak testing of this penetration will be performed at least every 45 days to verify that the 0.6 L, is not exceeded due to additional penetration leakage. This testing will also qualitatively verify the integrity of the outboard isolation barriers (employing the visual and audio inspection techniques and Snoop similar to techniques used on September 22,1999, as described above).
The time requested for the NOED will allow time to obtain an exigent TS change. Detroit Edison
! submitted the amendment request on September 24,1999. The licensee has indicated that the compe.nsatory measures discussed above are already being implemented.
1.
l Criterion 1(a) of Section B.2 of the NOED guidance in NRC Inspection Manual Part 9900 is l applicable to this request. This criterion is intended to:
L avoid undesirable transients as a result of forcing compliance with the license condition and, thus minimize potential safety consequences and operational risks...
In this case, Fermi 2 is currently operating and unless this request is granted, would be required to shutdown. Assuming a required plant shutdown carries the same risk as a given inadvertent scram, the licensee concluded that the shutdown activity increases the potential risk compared to continued plant operation with T4803F601 leaking. Thus, this situation meets a criterion given in Section B of the NRC Guidance for Issuance of Enforcement Discretion. The NOED request was reviewed and approved by the Fermi 2 On-Site Review Organization.
NRC Staff Evaluation
. The NRC staff has reviewed your request for the NOED. The staff concludes that the Snoop testing results for outboard valve T4800F408 provide reasonable assurance that this valve is leak tight. While your staff estimated that the leakage through the other outboard isolation valve (T4800F407) was very low, the compensatory action of adding a blank flange to the end of that pipe will provide further assurance that there is little or r'o leakage through this portion of the peraatration. The blank flange was installed on September 25,1999. Maintaining these valves closed and deactivated and the blank flange in place should ensure that this portion of the containment boundary performs its design safety function if it is called upon. In addition, you will be leak-testing the penetration every 45 days. It is our understanding that the leakage obtained during this testing will be combined with the known leakage and compared to 0.6 L . This testing will ensure that any degradation in the outboard isolation valves / blank flange will not go undetected. As discussed during the telephone calls on September 23,1999, the existing TS will require that the leaking valve is repaired prior to restart if the plant shuts down for any reason before the next refueling outage. The staff concludes that the existing TSs, in conjunction with the compensatory actions, provide assurance that the safety function of the
i
. D.R. Gipson -S-penetration will be met if it is called upon. The staff also concludes that this requests meets Criterion 1(a) of Section B.2 of the NOED guidance.
On the basis of the NRC staff's evaluation of your request, we have concluded that a NOED is warranted because we are clearly satisfied that this action involves minimal or no safety impact, is consistent with the Enforcement Policy and staff guidance, and has no adverse impact on public health and safety. Therefore, it is our intention to exercise discretion tsot to enforce compliance with TS 3.6.1.8, Action b., for penetration X-26 until the associated exigent TS amendment is issued and implemented. You submitted the request for the TS amendment on September 24,1999, and the NRC staff is reviewing it. The NRC staff plans to complete its review and issue the TS amendment within 4 weeks of the date of this letter.
As stated in the Enforcement Policy, action will be taken, to the extent that violations were
{
involved, for the root cause that led to the noncompliance for which this NOED was necessary.
Sincerely, d w vL h2LCk ,
Suzann'e C. Black, Acting Director Project Directorate 111 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-341 cc: See next page
J Mr. Douglas R. Gipson Fermi 2 Detroit Edison Company cc:
John Flynn, Esquire Senior Attomey Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Drinking Water and Radiological
. Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P. O. Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 U.S. Nuclear Regulatory Commission Resident inspector's Office 6450 W. Dixie Highway Newport, Michigan ~ 48166 Monroe County Emergency Management .
Division 963 South Raisinville I Monroe, Michigan 48161 '
Regfanal Administrator, Region lil U.S. Nuclear Regulatory Commission j
801'Narrenville Road i Hle, Illinois 60532-4351 Norman K. Peterson
' Director, Nuclear Licensing Detroit Edison Company Fermi 2 - 280 TAC 6400 North Dixie Highway Newport, Michigan 48166 I
l December 1998 i
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' September 27,-1999 D.R. Gipson. -+. #
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penetr'a tion will be m if it is' called upon.' The' staff also concludes that this requests meets
- Criterion 1(a) of Section B.2 of the NOED guidance '
s 1
i On the basis of thd NRC staff's evaluation of your request, we have concluded that a NOED is warranted because we are clearly satisfied that this nction involves minimal or no safety impact, is consistent with the Enforcement Policy and staff guidance, and has no adverse impact on public health and safety. Therefore;it is our intention to exercise discretion not to enforce compliance with TS 3.6.1.8, Action b., for penetration X-26 until the associated exigent TS amendment is issued and implemented. .You submitted the request for the TS amendment on September 24,1999,~ and the NRC staff is reviewing it. The NRC staff plans to complete its review and issue the TS amendment within 4 weeks of the date of this letter.
As stated in the Enforcement Policy, action will be taken, to the extent that violations were involved, for the root cause that led to the noncompliance for which this NOED was necessary.
Sincerely, ORIG. SIGNED BY Suzanne C. Black, Acting Director Project Directorate lil Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-341 cc: See next page DISTRIBUTION:
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OFFICIAL RECORD COPY j
- September 27, 1999 L
, D.R. Gipson l penetration will be met if it is called upon. The staff also concludes that this requests meets Criterion 1(a) of Section B.2 of the NOED guidance.
On the basis of the NRC staff's evaluation of your request, we have concluded that a NOED is warranted because we are clearly satisfied that this action involves minimal or no safety impact, is consistent with the Enforcement Policy and staff guidance, and has no adverse impact on public health and safety. Therefore, it is our intention to exercise discretion not to enforce compliance with TS 3.6.1.0, Action b., for penetration X-26 until the associated exigent TS amendment is issued and implemented. You submitted the request for the TS amendment on September 24,1999, and the NRC staff is reviewing it. The NRC stafiplans to complete its review and issue the TS amendment within 4 weeks of the date of this letter.
As stated in the Enforcement Policy, action will be taken, to the extent that violations were involved, for the root cause that led to the noncompliance for which this NOED was necessary.
Sincerely, l
ORIG. SIGNED BY Suzanne C. Black, Acting D; rector i Project Directorate lil !
Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-341
- cc
- See next page DISTRIBUTION:
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DATE 09/ 2.7/99 09/M /99 09/ 27 /99 09/ 27 /99 09/Q /99 OFFICIAL RECORD COPY