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
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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
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O. Ralph syiv'a tens v vice Pecodent
, 64:0 Nonh Dmie Higtmay g n Nemport Michigan 4106 f i
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, February 9, 1990 i NRO-90-0017 L
'L U. S. Nuclear Regulatory Commission Attnt Document Control Desk Washington, D. C. 20555 ]
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! Roference: Fermi 2
- NRC Docket No. 50-341 li NR0 License No. NPF-43 i Subject Fermi 2 RadioloDical Emergency Response Plan Revision !
t Attached for your review and approval is a proposed revision to the Emergency Action Level (EAL) scheme in the Formi 2 Radiological ;
Emergency Responso Preparedness (RERP) Plan. It incorporates changes to the initiating conditions for the Notification of Onusual Event !
emergency classification.
1 NUREQ 0654, Appendix 1, provides a definition f or each emergency classification and example initiating conditions. Under 10 CFR 50.72 .
j the NRC requires immediate notification of an emergency declaration and .
one-hour or four-hour reports for non-emergency events. Many of the non-emergency events requiring a one-hour or four-hour report duplicate
. examples of Unusual Event initiating conditions contained in the NUREO Appendix.
1 Several current initiating conditions for Notification of Unusual Event do not accurately reflect the definition because they do not indicats a potential degradation of plant safety or are not precursors to more
- serious events. We applied these criteria in our revision.
We reviewed nach initiating condition that currently leads to an Unusual
. Event doctaration. Of the twenty-four initiators which now exist in the Fermi RERP plan, we propose to make no changes to seventeen and to eliminate seven. The seven initiating conditions that we are proposing !
to eliminate from the Plan would continue to be reported under 10CFR50.72. The basis for these changes is provided in Enclosure A. l The proposed revision to Section D of our RERP Plan is Enclosure B.
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j_ USNRC February 9, 1990 NRC-90-0017 page 2 This proposed change as submitted f or your approvat per 10 CFR 60 Appendix E section IV.B. The revision was discussed with State of Michtgen. Monroe County, and Woyne County emergency management representatives and they support the proposed changes. We will not implement this revision until we receive your concurrence.
Sincerely, h' 1ll'k Enclosures cet A. B. Davis R. Lt. DeFayette W. Q. Rogers W. G. Snen J. F. Stang t
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ENCLOSURE A ,
Summary of Unusual Event initiating Conditions ,
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, i Enclosure A Page 1 Current Fermi 2 Unusual Event Emergency Action Levels (EALs)
Gaseous effluent release greater than instantaneous limits allowed by Technical Specification 3 11.2.1.
Liquid effluent release greater than instantaneous limits allowed by Technical Specification 3 11.1.1.
NUREG 0654, Appendix 1 Radiological effluent Technical Specification limits exceeded.
t 10 CFR 50.72 (b)(2)(iv)(A) or (B) Four-hour report Any airborne radiosctive release that exceeds 2 times the applicablo l concentrations of the limits specified in Appendix B, Table II of Part 20
'- of this chapter in unrestricted areas, when averaged over a time period of one hour or any liquid effluent release that excceds 2 times the limiting combined Maximum Pormissible Concentration (MPC) at the point of entry into i the receiving water (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one L hour.
Discussion Exceeding radiological effluent Technical Specifications limits could be a precursor to higher classifications and has the potential to impact the public.
Conclusion Maintain the current Fermi 2 Unusual Event EALs.
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, l Enclosure A Page 2 j Current Fermi 2 Unusual Event EAL Any unplanned event that results in ECCS discharge into the reactor coolant system as a result of a valid signal.
NUREG 0654. Appendix 1 Energency Core Cooling Systen (ECCS) initiated and discharge to vessel.
10 CFR 50.72 (b)(1)(iv) one-hour report ,
J Any condition that results or should have resulted in Emergency Core Cooling System (ECCS) discharge into the reactor coolant system as a result of a valid signal.
l Discussion ECCS initiation and discharge into the reactor coolant system as a result I
of a valid signal could indicate a degradation in plant safety. However, this condition would be classified as an Unusual Event, Alert, or Site Area Emergency in accordance with loss of reactor coolant fission product barrier EALs. >
Conclusion Delete the current Fermi 2 Unusual Event EAL.
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Enclosure A Page 3 Current Fermi 2 Unusual Event EAL Failure of Safety Relief Valve (SRV) to reset.
NUREG 0654 Appendir 1 Failure of a safety or relief valve in a safety related system to close fullowing reduction of applicable pressure.
10 CFR 50.72 (b)(1)(1)( A) One-hour report The initiation of any plant shutdown required by the plant's Technical Specifications.
Discussion This condition is addressed by Technical Specifications Section 3 4.2.1 which requires the operator to complete specific actions to restore the SRV to operable status or to shutdown the reactor. If, as a result of this condition the operators were unable to maintain reactor water level above the safety limit, an Unusual Event would be declared based on loss of reactor coolant fission product barrier. Inability to comply with Technical Specification shutdown requirements would result in an Alert or Site Area Energency classification based on degraded safety system or reactivity control initiating conditions.
Conclusion Delete the current Fermi 2 Unusual Event EAL.
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--s Enclosure A Page 4 Currant Fermi 2 Unusual Event EALs -
Loss of- any Engineered Safety Features System (s) functions requiring --
shutdown in accordance with Technical Specifications, c Reactivity Control Limiting Conditions for Operation exceeded requiring '
snutdown in accordance with Technical Specifications.
Loss of primary containment penetration conductor overcurrent protectivs devices requiring shutdown in accordance with Technical Specifications.
NUREG 0654, Appendix 1 Loss of engineered safety feature or fire protection system function requiring shutdown by Technical Specifications (e.g., because of -
malfunction, persom.el error or procedure inadequacy).
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10 CFR 50 72 (b)(1)(1)(A) One-hour report The initiation of any plant shutdown required by the plant's Technical -
Specifications.
Discussion These conditions are addressed by various sections of Technical Specifications, each of which require the operator to restore the system to .
operation or shutdown within a specified time frame. These events do not i impose plant transients that could lead to a more serious event. The exception is reactivity control LCO 3 1 3 6, control rod coupling. If a control rod became decoupled, a contrcl rod drop accident could occur and potentially result in fuel clad failure. This event would be classified as an Unusual Event or Alert based on loss of fuel clad fission product barrier. Inah*' tty -to comply with the Technical Specification shutdown requirements a ".1 be classified as an Alert or Site Area Emergency in accordance wicn Jegraded safety system or reactivity control EALs.
Conclusion
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Delete the current Fermi 2 Unusual Event EALs. =
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Enclosure A Page 5
' Current Fermi 2 Unusual Event EAL Safety Limits exceeded requiring shutdown according to Technical Specifications. l NUREG 0654, Appendix 1 Abnormal coolant temperature and/or pressure or abnormal fuel temperatures outside of Technical Specification limits.
10 CFR 50.72 (b)(1)(1)(A) One-hour report The initiation of any nuclear plant shutdown required by the plant's Technical Specifications. .
Discussion Exceeding a safety. limit could degrade the reactor pressure vessel or fuel.
This event could be a precursor to a more serious condition.
-t Conclusion Maintain current Fermi 2 Unusual Event EAL.
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Enclosure A ,
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' Current Fermi 2 Unusual Event EAL Abnormal Reactor done pressure above Technical Specification Operational limits.
NUREO 0654. Appendix 1 Abnormal coolant temperature and/or pressure or abnormal fuel temperatures outside of Technical Specification limits.
10 CFR 50 72 (b)(1)(1)(A) One-hour repor' The initiation of any nuclear plant shutdown required by the plant's Technical Specifications.
Discussion This condition is addressed by Technical Specification 3 4.6.2, which requires the operator to restore reactor domo pressure within limits in 15 minutes or be in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Inability to reduce reactor pressure to operational limits within 15 minutes indicates a problem that could be a precursor to a more serious condition.
Conclusion Maintain current Fermi 2 Unusual Event EAL.
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Enclosure A '
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-Current Fermi 2 Unusual Event EAL Reactor Cooldown Rate exceeding Technical Specifications.
NUREG 0654. Appendix 1 Other plant conditions exist that warrant increased awareness on the part of a plant operating staff or state and/or local offsite authorities or require plant shutdown under Technical Specification requirements or !
involve other than normal controlled shutdown (e.g., cooldown rate exceeding technical specification limits, pipe cracking found during operation) .
10 CFR 50.73 (a)(2)(1)(B) Licensee event report Any operation or condition prohibited by the plant's Technical Specifications.-
Discussion Exceeding the cooldown rato could degrade the reactor pressure vessel.
This condition could be a precursor to a more serious condition. ,
Conclusion Maintain current Fermi 2 Unusual Event EAL.
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Enclosure A Page 8 Current Fermi 2 Unusual Event EALs ,
Loss of offsite power or loss of onsite AC power capability.
Loss of power distribution systems requiring shutdotin according to Techr.ical Specifications.
Loss of vital DC electrical power sources requiring shutdown in accordance with Technical Specifications.
NUREG 0654, Appendix 1 Loss of offsite power or loss of onsite AC power capability. ,
10 CFR 50.72 (b)(1)(1)(A) One-hour report The initiation of any nuclear plant shutdown required by the plant's Technical Specifications.
10 CFR 50.72 (b)(2)(ii) Pour-hour report Any event or condition that results in manual or automatic actuation of any Engineered Safety Feature (ESP), including the Reactor Protection System -
(RPS).
Discussion These events impose transients on plant systems that could lead to a more serious event.
Conclusion Maintain current Fermi 2 Unusual Event EALs.
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Enclosure A Page 9 4
Current Fermi 2 Unusual Event EAL Significant loss of communications capability.
NUREG 0654, Appendix 1 Indications or alarms in process or effluent parameters not functional in Control Room to an extent requiring plant shutdown or other significant loss of assessment or communication capability (e.g., plant computer, Safety Parameter Display System, all meteorological instrurentation).
10 CFR 50.72 (b)(1)(v) One-hour report Any event that results in a major loss of emergency assessment capability, offsite response capability, or communications capability.
Discussion This event does not indicate a degradation in plant safety and does not have the potential to degrade to a more severe situation.
Conclusion Delete the current Fermi 2 Unusual Event EAL.
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Enclosure A ,
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Current Fermi 2 Unusual Event EAL Other hazards being experienced or projected (aircraft crash onsite, explosion near or onsite, toxic or flammable gas release, turbine rotating component failure causing rapid plant shutdown, train derailment onsite).
NUREG 0654, Appendix 1 Other hazards being experienced or projected.
- a. Aircraft crash onsite or unusual aircraft activity over facility
- b. Near or onsite explosion ,
- c. Near or onsite toxio or flammable gas release
- d. Turbine rotating component failure causing rapid plant shutdown 10 CFR 50.72 (b)(1)(vi) One-hour report Any event that poses an actual threat to the safety of the nuclear power plant or significantly hampers site personnel in the performance of duties necessary_for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases.
Discussion These events could be a precursor to a more serious event. Assistance from offsite authorities may be required and this declaration would provide them with useful information.
Conclusion Maintain current Fermi 2 Unusual Event EAL.
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Current Fermi 2 Unusual Event EAL Natural phenomenon being experienced or projected beyond normal values. ;
NUREG 06511, Appendix 1 Natural phenomenon being experienced or projected beyond usual levels
- a. Any earthquake felt in-plant or detected on station seismio instrumentation k
b.- 50 year flood or low water, tsunami, hurricane surge, seiche
- c. Any tornado onsite
- d. Any hurricane 10 CFR 50.72 (b)(1)(iii) One-hour report
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Any natural phenomenon or other external condition that poses an actual
. threat to the safety of the nuclear power plant or significantly hampers site personnel in the performance of duties necessary for the safe operation of the plant.
Discussion-These events could be a precursor to a more serious condition. Assistance from.offsite authorities may be required and this declaration would provide them with useful information.
Conclusion Maintain current Fermi 2 Unusual Event EAL.
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Enclosure A Page 12 Current Fermi 2 Unusual Event EAL
-Uncontrolled plant fire NUREG 0653,' Appendix 1 Fire within the plant lasting more than 10 minutes.
10 CFR 50.72 (b)(1)(vi) One-hour report '
Any event that poses an act'ual threat to the safety of the nuclear power plant or significantly hampers site personnel in the performance of duties !
- necessary for the safe operation of the nuclear power plant including fires, toxic gas releases, or radioactive releases. ,
4 Discussion This event could be a precursor to a more serious event depending on plant equipment involved. Offsite assistance may be required and this declaration would provide offsite authorities with useful information.
Conclusion Maintain current' Fermi 2 Unusual Event EAL.
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Enclosure A
- Page 13 Current Fermi 2 Unusual Event' EAL Loss of One Fission Product Barrier - Fuel' clad failure.
.NUREG 0654, Appendir 1 Fuel' damage indication 10 CFR 50.72 (b)(1)(ii) One-hour report
- Any event or condition during operation that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded. -
~ Discussion This. event indicates a degradation in plant safety and has the potential to degrade to a more severe situation.
Conclusion Maintain current Fermi 2 Unusual Event EAL.
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Enclosure A Page 14 Current Fermi 2 Unusual Event EALs Loss of One Fission Product Barrier
- Reactor water level safety limit exceeded according to Technical Specification 2.1.4.
- Reactor Coolant System leak rates greater than those specified in Tschnical Specification 3 4 3 2.
NUREG 0654, Appendix 1 Exceeding primary system leak rate technical specification 10 CFR 50.72 (b)(1)(ii) One-hour report Any event or condition during operation that results in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded.
Discussion This event indicates a potential degradation in plant safety and has a potential to degrade to a more severe situation.
Conclusion Maintain current Fermi 2 Unusual Event EALs.
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.: 6 Enclosure A Page 15 Current Fermi 2 Unusual Event EALs Loss of One Fission Product Barrier - Loss of Primary Containment Integrity requiring plant shutdown in accordance with Technical Specifications.
Loss of One Fission Product Barrier - Loss of Secondary Containment Integrity-requiring plant shutdown in accordance with Technical Specifications.
-NUREG 0654, Appendix 1
(' Loss of Containment Integrity requiring shutdown by Technical l l Specifications. ;
I l- 10 CFR 50.72 (b)(1)(A) One-hour report '
1 i The initiation of any nuclear plant shutdown required by the plant's Technical Specifications, or j 10 CFR 50.72 (b)(1)(ii) One-hour report Any event or condition during operation that results in the condition of l
the nuclear power-plant, including its principal safety barrier, being j seriously degraded. l l
Discussion l Primary Containment is one of the principal fission product barriers and l its backup is Secondary Containment. If coupled with the loss of another fission product barrier these events could result in a radiological release i to the public. ;
1 Conclusion Maintain the current Fermi 2 Unusual Event EALs.
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s-Enclosure A
'Page 16 Current Fermi 2 Unusual' Event EAL Security _ threat, attempted entry, attempted sabotage.
NUREG 0654. Appendix 1 Security threat _of attempted entry or attempted sabotage.
10 CFR 73 71 One-hour report Explicit threats, which are information received by a security organization that an act of theft or radiological sabotage will be attempted, are to be i reported to the NRC.
-Discussion These events could be a precursor to a more serious security event._ -
Assistance from offsite authorities may be required and this declaration would provide them with useful information.
Conclusion Maintain current Fermi 2 Unusual Event EAL. +
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1 Enclosure A Page 17 Current Fermi 2 Unusual Event EAL Transportation or= contaminated injured individuals from the facility to an offsite medical facility.
NUREG 0654, Appendix 1 4 Transportation of contaminated injured individual' from site to' offsite ,
hospital.
10 CFR 50.72 (b)(2)(v) Pour-hour report Any event requiring the transport of a radioactively contaminated person to an offsite medical facility for treatment.
Discussion This event does not impact plant safety and could not lead to a-degradation ,'
of plant safety.
Conclusion ,
Delete current Fermi 2 Unusual Event EAL.
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