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
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_ _ _ _ _ _ - - - - -
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,/ ! NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055MX)01 SEP 2 31993 Scientech, Inc.
ATTN: James Meyer, Project Manager 11821 Parklawn Drive Rockville, MD 20852
Dear Mr. Heyer:
Subject:
Contract No. NRC-04-91-068, Task Order No. 24 Entitled,
" Individual Plant Examination (IPE) Reviews, Internal Events, Back End Only" (Fermi Unit 2)
In accordance with Section G.5, Task Order Procedures, of the subject contract, this letter definitizes Task Order No. 24. This effort shall be performed in accordance with the enclosed Statement of Work.
Task Order No. 24 shall be in effect from September 30, 1993 through September 29, 1994 with a total cost ceiling of $15,054.96. The amount of
$14,205.00 represents the total estimated reimbursable costs and the amount of
$849.96 represents the fixed fee.
The obligated amount of this task order is $15,054.96.
Accounting Data for Task Order No. 24 is as follows:
APPN No.: 31X0200.360 B&R No.: 36019202300 JOB CODE: L1933 B0C No.: 2542 Obligated Amount: $15,054.96 RES Identifier: RES-C93-216 i o .
The following individuals are considered to be essential to the successful performance for work hereunder: James Meyer and Mohsen Khatib-Rahbar.
The Contractor agrees that such personnel shall not be removed from the effort under the task order without compliance with Contract Clause H.1, Ke.y Personnel.
The issuance of this task order does not amend any terms or conditions of the subject contract.
Your contacts during the course of this task order are:
Technical Matters: John Flack, Project Officer (301) 492-3979 Contractual Matters: Paulette Smith, Contract Administrator (301) 492-7670 1
R C h 930923 g' NRC~04-91~O68 PDR
.s
'4 NRC-04-91-068 '
Please indicate your acceptance of this Task Order No. 24 by having an official, authorized to bind your organization, execute three copies of this document in the space provided and return two copies to the above Contract Administrator. You should retain the third copy for your records.
As we rapidly approaching September 30, our fiscal year ending date, you should expedite the execution of and return of this document. Unless the signed documents are returned to me prior to that date, I cannot assure you of the continued availability of these funds. You also also requested to FAX a copy of the signed document as soon as possible to ensure that the NRC has adequate time to record this obligation of funds. The facsimile number is (301) 492-4994.
If you have any questions regarding the modification, please contact Paulette Smith, Contract Administrator, on (301) 492-7670.
Sincerely,
.d .
Jd . Fields, Contracting Officer Contract Administration Branch No. 3 Division of Contracts and Property Management Office of Administration
Enclosure:
Statement of Work ACCEPTED: * ,
. .m Mars'h'a11 Y , V NAM BD11BZEL EDLhxMic DLDee TITLE September 27, 1993 DATE
k Contract NRC-04-91-068 Scientech STATEMENT OF WORK Task Order - 24 TITLE: Individual Plant Examination (IPE) Reviews, Internal Events Back-End Only (Fermi 2)
DOCKET NUMBER: 50-341 HRC PROJECT MANAGER: John H. Flack, RES (301-492-3979)
NRC TEAM LEADER FOR FERMI 2: John H. Flack, RES (301-492-3979)
TECHNICAL HONITOR: John H. Flack, RES (301-492-3979)
PERIOD OF PERFORMANCE: September 30, 1993 through September 29, 1994 EACKGROUND:
On November 23, 1988, the NRC issued Generic Letter 88-20, " Individual Plant Examination," which stated that licensees of existing plants should perform a systematic examination (IPE) to iden.tify any plant-specific vulnerabilities to severe accidents, and to report the results to the Commission. The purpose of the IPE is to have each utility (1) develop an overall appreciation of severe accident behavior; (2) understand the most likely severe accident sequences at its plant; (3) gain a quantitative understanding of the overall probability of core damage and radioactive material releases; and (4) reduce the overall probability of core damage and radioactive releases by modifying procedures and hardware to prevent or mitigate severe accidents. All IPE submittals will ' -
be reviewed by the NRC staff to determine if licensees met the intent of Generic Letter 88-20.
OBJECTIVI:
The purpose of this contract is to solicit contractor support in order to enhance the NRC review of licensees' IPE submittals. This contract includes the examination and~ evaluation of the Fermi 2 IPE submittal, specifically with regard to the "back-end" analysis. The contractor review will be of limited, scope and consist of a " submittal only" review and the licensee's response to questions raised by the staff. The " submittal only" review and gathering of associated insights will help the NRC staff determine whether the licensec's IPE process met the intent of Generic Letter 88-20, or whether a more detailed review is warranted.
By identifying the IPE's strengths and weaknesses, extracting important insights and findings, and providing a comparison to staff reviewed and accepted PSAs (e.g. NUREG-1150, PSAs identified in NUREG-1335 Appendix B), it l
1
is expected that the NRC will be in a better position to expeditiously evaluate the licensee's IPE process. To provide support under this contract, the contractor will search for obvious errors, omissions and inconsistencies in the IPE submittal and the licensee's response to a " Request for Additional Information," (RAI) as described in the work requirements listed below.
WORK REOUIREMENTS AND SCHEDULE:
The contractor will perform a " submittal only" review of the Fermi 2 "back-end" IPE analysis. [The review is to include only the Level II analysis.
Review of Level III (consequence analysis) is beyond the scope of this contract.] The contractor shall provide the qualified specialists and the
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necessary facilities, materials, and services to carry out such a review. The contractor will utilize NRC review guidance documents for detail and reference, as well as other interim guidance provided by the NRC Technical Monitor. The contractor is not expected to make a plant / site visit in order to perform this review.
Jubtask 1. Review and Identification of IPE Insichts Perform a back-end " submittal only" review of each IPE submittal and identify important IPE insights by completing the NRC IPE Data Summary Sheets. During the review, focus on the areas described below under " Work Requirement." The contractor will note any: (1) inconsistencies between methodology employed in the IPE submittals and other PSA studies, and (2) inconsistencies between the submittal's IPE findings 'and findings stemning from other PSAs (See NUREG-1335, Appendix B). Respond explicitly to each work requirement by noting important review findings including any IPE strengths and weaknesses.
Appropriately characterize any shortcomings with respect to the impact on IPE conclusions. Identify and provide a justification for a Request for Additional Information (RAI).
Word Reouirement 1.I. Perform a General Review of the Licensee's IPE' -
Back-End Analytic Process Check the following:
1.1.1 The IPE submittal is essentially complete with respect to the ,
level of detail requested in NUREG-1335. (
1.1.2 IPE employed methodology is clearly described and justified for selection. Approach is consistent with Generic Letter 88-20 Appendix 1.
1.1.3 The IPE employed a viable process to confirm that the containment -
and containment systems represent the as-built, as-operated plant.
1.1.4 IPE back-end had been appropriately peer-reviewed ta help assure the analytic techniques were correctly applied.
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Work Reauirement 1.2. Review of the Containment Analysis / Characterization Check the following:
1.2.1 The IPE analysis appropriately treated front-end and back-end dependencies, i.e., plant damage states considered reactor system / containment system availability, system mission times, inventory depletion, dual usage (spray vs. injection).
1.2.2 Classes of sequences with significant probability (those that meet the G.L. 88-20/NUREG-1335 screening criteria) were evaluated !
further using simplistic, but realistic, containment event trees.
1.2.3 The focus of the IPE's containment analysis was on failure modes and timing. Containment failure modes are censistent with those identified in Table 2.2 of NUREG-1335.
1.2.4 The IPE process assessed and identified contributors to containment isolation failure.
1.2.5 System / human response were integrated with the phenomenological aspects of accident progression into the containment event trees.
Allowances for recovery actions were made to allow for accident management actions.
1.2.6 The IPE submittal approprtately documented radionuclide release characterization for accident sequences exceeding the Generic Letter 88-20 (or NUREG-1335) screening criteria.
Work Reauirement 1.3. Review the Ouantitative Nature of the Accident Proaression and Containment Performance Analysis Check the following:
1.3.1 The licensee employed a reasonable process to understand and quantify severe accident progression. The process lead to a determination of important conditional containment failure probabilities, and considered phenomenological uncertainties, '
either qualitative or quantitative.
l.3.2 Dominant contributors to containment failure are consistent with insights from other PSAs of similar design.
1.3.3 The IPE appropriately characterized containment performance for each of the CET end-states by assessing containment loading (either calculated or referenced).
1.3.4 The containment analysis considered the impact of severe accident environments on equipment behavior.
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Work Reouirement 1.4. Review the IPE Approach to Reducina the Probability of Core Damaae or Fission Product Release Check the following:
1.4.1 The IPE analysis appears to support the licensee's definition of vulnerability, and that the definition provides a means by which the identification of potential vulnerabilities (as so defined) and plant modifications (or safety enhancements) is made possible.
1.4.2 The identification of plant improvements and proposed modifications are reasonably expected to enhance plant safety. <
Work Recuirement 1.5. Review Licensee's Resoonse to Containment Performance Imorovement Recommendations Check that the licensee appropriately responded to recommendations stemming i from the Containment Performance Improvement (CPI) Program, i.e., that the licensee's assessment, findings, conclusions and actions (as appropriate) considered the following as a function of containment type:
BWRs (KARK I,II,III) o Harden vent o Alternative water supply for drywell spray / vessel injection o Enhanced reactor pressure v;;sel depressurization system reliability o Implementation of Revision 4 of the BWR Owners Group EPGs o Improved hydrogen igniter power supply (Mark III)
Additional for BWR (MARK III) o Evaluation of vulnerability to interrupted power supply to' hydrogen igniters and need for improvement 1
PWR Ice Condenser Containments o Evaluation of vulnerability to interrupted power supply to '
hydrogen igniters and need for improvement PWR Dry Containments o Evaluation of containment and equipment vulnerabilities to hydrogen combustion (local and global) and need for improvement. This would include consideration of gaseous pathways between the cavity and the upper containment volume to confirm adequate communication to promote natural circulation and recombination of combustible gases in the reactor cavity.
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Work Reauirement 2.0. Comolete Data Sheets A. Summarize data on the Consolidated Data Summary Sheet as described below.
CONSOLIDATED DATA
SUMMARY
SHEET (INTERNAL EVENTS) o Conditional containment failure probability given core damage:
o Significant PRA findings:
o Enhanced plant hardware (implemented after 1988 PRA) containment modifications:
o Potential containment improvements under consideration and not modeled:
B. Complete the NRC data summary sheets and note any lack of information, as appropriate. However, exclude those data entries marked "BNL Data Entry." These data will be collected by Brookhaven National Laboratory under a separate contract.
Subtask 2. PreDare Preliminary Technical Evaluation ReDort Prepare a preliminary Technical Evaluation Report with the outline prescribed below. .
I. Executive Summary '
Provide a brief overview of the IPE review, the scope and depth as appropriate. Place emphasis on review areas identified as being important and rationale for importance, i.e., found to be important in other PSAs of similar design. Discuss any important or unique plant characteristics. Note plants with similar features and any important* '
insights stemming from other relevant PSA studies.
II. Contractor Review Findings Explicitly address each work requirement element listed above under i Subtask 1, " Review and Identification of IPE Insights." Discuss any strength or weakness so identified and significance with respect to the overall IPE effort. Identify any additional information (in the form of questions back to the licensee) which would be important to the review effort. List these questions separately in an appendix. Indicate why the information is important for closure.
III. Overall Evaluation and Conclusion l
Summarize the " submittal only" review conclusions based on the information submitted and significance of IPE strengths and weaknesses.
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IV. IPE Insights, Improvements, and Commitments Characterize important IPE findings and insights, including any
) significant containment characteristics or analytic assumptions that impact insights. Describe and characterize any significant enhancements implemented by the licensee, specifically in response to important insights which stem from the IPE process. Identify any licensee commitments and characterize the need to track commitments based on the impact on IPE conclusions. Also identify and characterize any potential improvements not forthcoming but perceived to be significant.
V. IPE Evaluation and Data Summary Sheets Attach: (a) Consolidated Data Summary Sheets using the above outline, and (b) the NRC IPE data sheets.
Appendix: Questions and Comments Provide all questions and comments which are to be discussed with the licensee. Provide rationale for comments, especially when seeking additional information.
Subtask 3. Prepare Final Technical Evaluation Report Review the licensee's response to staff questions and comments. Update the preliminary TER developed under Subtask 2, as appropriate, based on the additional information received from the licensee.. Emphasis should be placed on review areas identified under Subtask 2. Provide rationale as appropriate to support the need for any additional follow-on studies or recommendations.
Note: The contractor should be prepared to participate in telephone communications with the licensee and/or discussions with NRC review team members regarding the licensee's responses to questions and issues '
stemming from the preliminary TER.
4 REPORT REOUIREMENTS:
Technical Reports )
0 The contractor will. submit to the NRC Technical Monitor four copies of the Preliminary Technical Evaluation Report (TER) on February 28, 1994. Copies will include three hard copies and one 3.5" computer diskette version (Wordperfect 5.1 or other IBM PC compatible software acceptable to the NRC IPE Team Leader). The Preliminary TER shall summarize all findings, results, and conclusions in the areas examined in the format described under Subtask 2. If the contractor finds that the licensee's IPE is obviously deficient in any of ,
the areas examined, the Technical Monitor should be notified in advance. I Deficient or weak areas should be clearly documented in the Technical I Evaluation Report. In addition, if the contractor finds that there are I specific areas that need additional in-depth review, the Team Leader should be notified of the areas, and provided with the rationale for subsequent review.
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The contractor will submit to the NRC Technical Monitor three copies of the Final Technical Evaluation Report (TER) two weeks after the receipt of the licensee's response to staff questions and comments. Copies will include two hard copies and one 3.5" computer diskette version (Wordperfect 5.1 or other IBM PC compatible software acceptable to the NRC IPE Team Leader). The Final TER shall update all findings, results, and conclusions in the areas examined in the format described under Subtask 2 as appropriate.
I BUSINESS LETTER REPORT:
The contractor shall provide monthly progress reports in accordance with the requirements of the basic contract.
MEETINGS AND TRAVEL:
One, one person trip to NRC Headquarters to present and discuss review findings and conclusions.
ESTIMATED LEVEL OF EFFORT:
For each IPE reviewed:
Subtask 1 80 contractor hours l Subtask 2 80 contractor hours Subtask 3 16 contractor h'ours
- It shall be the responsibility of the contractor to assign technical staff, employees, and subcontractors who have the required educational background, experience, or combination thereof, to meet both the technical and regulatory ;
objectives of the work specified in this S0W. The NRC will rely on l representation made by the contractor concerning the qualifications of the 4 .
personnel proposed for assignment to this task order including assurance that all information contained in the technical and cost proposals, including resumes and conflict of interest disclosures, is accurate and truthful.
I NRC FURNISHED MATERIAL: ,
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- 1. Licensee's IPE submittal.
- 2. Licensee's response to staff generated questions and associated information.
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n TECHNICAL DIRECTION:
The NRC Project Manager is:
John H. Flack Severe Accident Issues Branch Division of Safety Issue Resolution U.S. NRC, Mail Stop NL/S 324 Washington, D.C. 20555 Telephone No. (301) FTS-492-3979 5
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