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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Doug!u R. Gipson
.,-- Seni ir Viec l'rnident, Nutlear Generation ferrai 2 6100 krth liisie ifwh Newpirt, Michigan 4s100, Td 3(3 FMT,2nl Fat 31WC.4172 Detroit Edison September 2,1997 NRC-97-0080 U. S. Nuclear Regulatory Commission i
Attn: Document Control Desk Washington D. C. 20555
References:
- 1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
- 2) NRC Special Inspection Report No. 50-341/96017, dated February 3,1997
- 3) NRC Notice of Violation (NRC Inspection Report 96017),
dated August 1,1997
- 4) Detroit Edison letter, NRC-96-0092, Licensee Event Report, g
No.96-014, dated November 4,1996 Q~!
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- 5) Detroit Edison letter, NRC-96-0104, Licensee Event Report, No.96-018, dated December 5,1996
Subject:
Reply to Notices of Violation finspection Report No. 50-341/96017'l Enclosed is Detroit Edison's response to the apparent Violations contained in Reference 2 and issued as Notices of Violation in Reference 3.
Detroit Edison :ecognizes the existence of the work management issues described in the cover letter to the Notices of Violation and has taken corrective action to stem conti nued problems in this area. Specifically, a number ofinitiatives have been
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, NRC-97-0080 Page 2 implemented to improve Technical Specification impact statements in work packages and to ensure that all applicable Technical Specification action statements are appropriately entered and exited. An Operations Work Control Group, consisting of two licensed Senior Reactor Operators (SRO) and two licensed Reactor Operators, has been formed, This group, rather than the normal, previously unlicensed work control personnel, has responsibility for ensuring that the Technical Specification impact statements in work packages are correct. Additionally, an administrative SRO position, staffed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day Monday through Friday, has been established in the Tagging Center to maintain control and coordination of work packages and impact statement execution. This provides an additional SRO review of the Technical Specification implications of proposed work package execution, and allows the Nuclear Shift Supervisor to remain focused on normal plant operation.
Another recent initiative is the Critical Work Review which is conducted approximately two weeks prior to work execution, to ensure the necessary coordination for Technical Specification impacted activities currently scheduled.
This meeting is chaired by the Operations Work Control Supervisor, and is attended by Work Control, Maintenance, System Engineering and the Work Week Manager, with support from other functional areas as required. This synergistic approach is intended to provide yet another opportunity to identify and resolve potential coordination problems associated with Technical Spec #ication impacts.
There have been several general improvements made to the work control process as well. These include formation of a Work Management Improvement Committee to provide input and review for improvements in work management practices, a Maintenance Work Package Walkdown Checklist to help in identifying potential problems before ajob is started, and designation of Work Week Managers to help oversee and coordinate scheduled work. These improvements are intended to help ensure that work is thoroughly planned, scheduled and executed in a manner consistent with the requirements of the Technical Specifications.
Regarding the Detroit Edison presentation of a complex legaljustification at the predecisional enforcement conference for the actions of the Fermi 2 staff, we agree that the Fermi 2 staff should have contmunicated better with the NRC prior to implementation of the Technical Specification clarification. We believed, however, that the detailed discussion presented at the predecisional enforcement conference was needed to allow NRC senior management to understand the complex interrelationships associated with the various Technical Specifications. In the future, we will communicate with the NRC staff, should a similar situation arise.
Iminediate and short term corrective actions have been completed as discussed in this response. The following commitments are being made in this letter:
- 1. The wording in the procedure governing Technical Specification Clarifications is being strengthened to specifically state that Technical
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. NRC 97-0080 Page 3 Specification Clarifications must never contradict or change the s 3rding of a 1 Technical Specification requirement. This revision will be completed by l Octoler 31,1997. I
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- 2. A license amendment will be prepared to allow the interpretation discussed in l Violation 50-341/96017-Ol A to be implemented into the current Fermi 2 j Technical Specifications, prior to the implementation of the ITS. l
- 3. Violation 50-341/96017-Ol A will be discussed in Operations Continuing '
l Training with emphasis on literal compliance with Technical Specifications.
l This training is expected to be completed by December 19,1997.
If there are any' questions, please contact Norm Pet rson, Director- Nuclear j Licensing, at (313) 586-4258.
Sincerely, .
h Enclosure ec: A. B. Beach O. A. Harris M. J. Jordan A. J. Kugler M. V. Yudasz, Jr.
Region llI Wayne County Emergency Management Division
i
, Enclosure to NRC-97-0080 Page1 4
JtESPONSE TO VIOLATIONS Violation (50-341/96017-01 A)
Technical Specification 3.9.10.2. permits any number of control rods and/or control rod drive mechanisms be removed from the core and/or reactor pressure vessel provided that at least the following requirements are satisfied until all control rods and control rod drive mechanisms are reinstalled and all control rods are inserted in the core.
Technical Specification 3.9.10.2.a. requires that the reactor mode switch be OPERABLE and locked in the Shutdown position or in the Refuel position per Specification 3.9.1, except that the Refuel position "one-rod-out" interlock may be bypassed, as required, for those control rods and/or control rod drive mechanisms to be removed, after the fuel
! assemblics have been removed as specified in Technical Specification 3.9.10.2.b l through e.
Section 7.6.1.1.3.4 of the Fermi Updated Final Safety Analysis Repoit (UFSAR) l desci.i ms the ftmetional testing of refueling interlocks. The UFSAR did not describe the acceptabilit" of performing this test under conditions where multiple control rods are already withdrawn when the test is made.
Contrary to the above, on October 13,1996, the licensee performed a functional test of refueling interlocks under conditions which were not permitted by Technical Specification 3.9.10.2. Specifically, the test was performed under conditions where multiple control rods were already withdrawn from the core, and the reactor mode switch was not locked in either the Shutdown position or the Refuel position.
Reason for Violation Following repairs to the refueling bridge, surveillance testing in accordance with Technical Specifications was required in order to demonstrate operability of the Mode Switch and refueling interlocks. Portions of this testing require the Mode Switch to be placed in the STARTUP/ HOT STANDBY and RUN positions. However, with the reactor partially defueled, multiple control rods had been withdrawn and could not be reinserted without first installing fuel or blade guides in the affected core cells.
Following a review of the Fermi 2 Technical Specifications and the improved Standard Technical Specifications (ISTS), NUREG-1433, Revision 1, Detroit Edison concluded that the required surveillance testing could be perfomied within the intent of the existing Technical Specifications. A Technical Specification Clarification was developed and approved allowing the required surveillance testing. This clarification provided a
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.- Enciccure to NRC 97-0080 Page 2
- c rationalization for concluding that the mode switch could be moved from the SilUTDOWN or REFUEL position to the STARTUP/IlOT STANDBY and RUN positions, consistent with the position taken in NUREG 1433, Revision I that with no fuel assemblies in the core cell, the associated control rod has no reactivity control function and is not required to remain inserted. This rationalization and the resulting activities were not consistent with the literal requirements of Technical Specification 3.9.10.2.a however, and the Detroit Edison staff should have contacted the NRC to obtain the appropriate regulatory exemptions.
Corrective Stens that have been Taken and the Results Achieved The Technical Specification Clarification in question has been canceled. All other active Technical Specification Clarifications have been reviewed to identify any similar cases where a clarification was developed relying on the ISTS. No other examples were identified.
Personnel involved in the review and approval of Technical Specification Clarifications have been made aware of this violation end t.aderstano that Technical Specification Clarifications cannot be written to provide any relief from literal compliance with Technical Specification requirements.
Corrective Stens that will be Taken to Avoid Further Violations The procedure goveming Technical Specification Clarifications has been reviewed against NRC inspection guidelines on Technical Specification Interpretations. The
- procedure was determined ta appropriately prohibit the use of clarifications to provide relief from Technical Specification requirements. However, as a result of this review, the procedural wording is being strengthened to specifically state that Technical Specification Clarifications must never contradict or change the wording of a Technical Specification requirement. This revision will be completed by October 31,1997.
A license amendment to implement improved Technical Specifications (ITS) at Fermi 2 is being developed. Implementation ofITS is expected to reduce the need for Technical Specitication Clarifications and also to reduce the possibility of this type ofinterpretation error in the future. A license amendment will be prepared to allow the interpretation discussed in this event to be implemented into the current Fermi 2 Technical Specifications, prior to the implementation of the ITS.
This event will be discussed in Operations Continuing Training with emphasis on literal compliance with Technical Specifications. This training is expected to be completed by December 19,1997.
, Enclosure to NRC-97 0080 Page 3
] late When Full Compliance will be Achieved Full compliance was achieved on December 10,1996 when this Technical Specification Clarification was canceled. Additional corrective actions will ensure continued compliance.
. Enclosure to NRC-97-0080 Page 4 Violation (50 341/96017-01111 Technical Specification 4.0.4 requires, in part, that entry into an OPERATIONAL CONDITION shall not be made unless the surveillance requirements associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified.
Technical Specification 3.3.6 requires, in part, that the control rod block instrumentation channels shown in Table 3.3.61 shall be OPERABLE consistent with the applicability listed in that table. Table 3.3.6-1 requires that intermediate Range hionitors be OPERABLE in OPERATIONAL CONDITION 5.
Contrary to the above, on November 5,1996, OPERATIONAL CONDITION 5 was entered without performing the surveillance requirements for Technical Specification 3.3.6. Specifically, a current surveillance was not made for any of the required channels of the Intermediate Range hionitoring instrumentation, prior to entry into OPERATIONAL CONDITION 5 as required by Table 3.3.6-1 and Technical Specification 4.0.4.
Reason for Violation As described in Licensee Event Report (LER)96-018, the reason for the violation was that a transposition error occurred when the initial set of dial indicator readings were being taken during tensioning of the Reactor Pressure Vessel (RPV) studs. The transposition error was due to a poor transfer ofinformation between personnel when the dial indicator reading in question was transmitted by technicians via radio communication from the reactor cavity to the official record on the Refueling Floor. The actual reading of 0.8060 inches was transposed to be 0.8600 inches on the official record. This resulted in RPV llead stud number 27 being detensioned during the final trim pass causing an unrecognized entry into OPERATIONAL CONDITION 5 (REFUELING). Because the mode change was not recognized, the surveillance requirements for the Intermediate Range hionitoring Instrumentation of Technical Specification Table 3.3.6-1 were not performed. A contributing factor for this lack of recognition was that the personnel involved did not adequately review or question the inconsistency in the dial indicator readings or the number of turns required for the trim adjustment.
Corrective Steps that have been Taken and the Results Achieved As described in LER 96-018, the immediate corrective action taken was to retension stud number 27 to within specified tolerances.
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. Enclosure to NRC-97-0080 Page 5 During the investigation it was determined that a declaration of OPERATIONAL CONDITION 4 (COLD SHUTDOWN) is more appropriate af ter the trim pass adjustment when all stud elongation is verified to L: within tolerances. Operations has changed the declaration of a mode change from OPERATIONAL CONDITION 5 to OPERATIONAL CONDITION 4 to be when stud elongation is verified to be within tolerance.
The Reactor Vessel llead Detensioning and Tensioning procedure has been revised to incorporate the following considerations:
Elongation data recorded by technicians in the reactor cavity and reported via radio communications will be compared to the reading recorded on the official records. Any discrepancies will be resolved prior to subsequent clongation adjustments.
Trim adjustments requiring more than one turn will be evaluated by the Refueling Floor Coordinator prior to proceeding with trim adjustments.
e The definition for a fully tensioned Reactor Vessel Head will be when all studs are verified to be within elongation tolerances.
. The NSS will be notified when the studs are ready for trim adjustments to assure the plant is ready to enter OPERATIONAL CONDITION 4.
- The NSS will also be notified when all studs have been elongated and are verified to be within tolerance.
A three way communications process has been implemented as part of the Operational Excellence Plan into the Operations Department Instructions (ODI), specifically ODI-006," Operations Department Communications," and ODI-007," Command and Control."
This communication technique is used by operations and maintenance personnel and should help to ensure that errors such as the one cited in the violation are minimized.
Corrective Steps that will he Taken to Avoid Further Violations All corrective actions connected with this event have been completed.
Date When Full Compliance wilife Achieved Full compliance was achieved when stud number 27 was retensioned to within tolerances and Technical Specification surveillance requirements were met.
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. Enclosure to NRC-97 0080 Page 6 Violation (50 341/96017-01C)
Technical Specification 3.7.1.5 requires, in part, that the Ultimate lleat Sink, comprised of two one half capacity residual heat removal (RHR) reservoirs with the capability of being cross-connected, shall be OPERABLE with two reservoir cross-connect lines, each with two OPERABLE motor operated cross-connect valves.
Action "c" of Technical Specification 3.7.1.5 requires, in part, that with one or more reservoir cross-connect valves inoperable, within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> open and de-energize both valves in at least one cross-connect line and verify that these valves remain open and de-energized at least once per 7 days. Othenvise, declare both reservoirs inoperable and take the action of e. below.
Action "e.2" of Technical Specification 3.7.1.5 requires, in part, that in OPERATIONAL CONDITIONS 4 or 5, declare RIIRSW system (residual heat removal service water), the EESW system (emergency equipment service water) and the diesel generator cooling water systems inoperable and take ACTION required by Technical Specifications 3.7.1.1, 3.7.1.3 and 3.7.1.4.
Contrary to the above, on October 4,1996, through October 5,1996, while in OPERATIO'NAL CONDITION 5, the Ultimate lleat Sink was not OPERABLE because two reservoir cross-connect lines, each with two OPERABLE motor operated cross-connect valves, were not available. The Division 2 valves (El150-F602A and F602B) were rendered inoperable by operators and one of the Division 1 valves (F601 A) failed to open. At that time, the licensee failed to declare the RilRSW, EESW, and the diesel generator cooling water systems inoperable and failed to take the actions required by Technical Specifications 3.7.1.1,3.7.1.3 and 3.7.1.4.
Reason for Violation The reasons for the violation are:
- 1. The failure of the control room operator to recognize that deenergization of bus 72ED caused the closed RilR reservoir cross-connect valve (El 150-F0602B) to be inoperable, thereby resulting in a failure to enter action c, and subsequently action e, of Technical Specification 3.7.1.5;
- 2. The failure of valve El 150-F0601 A to open such that a cross-connect between the RIIR reservoirs was not established; and
e Enclosure to NRC-97 0080 Page 7
- 3. The failure of the control room operator to realize that valve Ell 50-F0601 A had not opened, thereby resulting in another failure to enter action e of Technical Specification 3.7.1.5.
The control room operator cited in 1) above and as described in Licensee Event Report (LER)96-014 failed to enter the appropriate Technical Specification action statement because the Limiting Condition for Operation (LCO) tracking sheet prepared by licensed and non-licensed operators was based on the assumption that the other cross-connect function was OPERABLE with the other division of power available. Proper attention was not paid to the LCO requirements of the Technical Specifications which required that
, this OPERABLE cross-connect line have both valves in the line open and de-energized.
The failure of valve El 150-F0601 A , a ball valve, to open as cited in 2) above and described in LER 96-014 was due to a loose set screw on the valve operator spline bushing, resulting in the spline bushing becoming disengaged from the drive spline of the operator bull gear. The valve position indication was indicating changing valve position by rotation of the valve operator stem which was not connected to the valve.
The failure of the control room operator cited in 3) above to recognize that valve El150-F0601 A had failed to open, although valve position indicated open, was inadequate interpretation of the information available concerning RHR reservoir levels. Therefore, only when water was added to the Division I reservoir with no change in the level of the cross-connected Division 2 reservoir, and further confirmed when the opposite division closed valve (El150-F0602B) was opened, was it recognized that El150-F0601 A&B cross-connect line had not provided a flow path.
Corrective Steps that have been Taken and the Results Achieved As described in LER 96-014, a cross-connect path was established on October 5,1996, at 1549 hours0.0179 days <br />0.43 hours <br />0.00256 weeks <br />5.893945e-4 months <br /> when El150-F602B was manually opened. The El150 F601 A valve operator was repaired prior to restart from the fifth refueling outage by providing a small recess for the spline bushing set screw and by securing the set screw in place. The other cross-connect valves have also been modified with the set screw recess.
The appropriate operations personnel involved in this event received discipline in accordance with Detroit Edison's Positive Discipline Program. A lessons learned document was prepared for the Operations department and this event was discussed with shitt operations personnel.
The bus shutdown procedures have been evaluated. No changes to these procedures were deemed appropriate due to the potential for varying combinations of plant conditions and equipment availability. However, work control documents will incorporate specific
$ Enclosure to l NRC 97-0080 Page 8 component impacts during bus shutdown. These work control documents will be reviewed by the Operations Work Control Group. This group, rather than the normal, previously unlicensed work control personnel, has responsibility for ensuring that the Technical Specification impact statements in work packages are correct.
The Ultimate IIcat Sink cross-connect valve surveillance procedures have been evaluated to detennine the need to provide positive indication that a cross connect path is established when the associated cross-connat path valves are in the open position as indicated in the control room. These procedures were revised prior to the first quarterly performance of the surveillance after restart from the fifth refueling outage.
Corrective Steps that will he Taken to Avoid Further Violations All corrective actions connected with this event have been completed.
Date When Full Compliance will be Achieved Full compliance was achieved on October 5.1996 when a cross-connect between the RHR reservoirs was established.
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