Similar Documents at Fermi |
|---|
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-99-0094, 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
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
ML20217A3261999-09-30030 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38
ML20212K8881999-09-30030 September 1999
Refers to 990928 Meeting Conducted at Fermi Unit 2 to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff
ML20212J8331999-09-27027 September 1999
Responds to Licensee 990924 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3/4.6.1.8.Ltr Documents 990923 Telcon with Util in Which NRC Orally Issued NOED
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
ML20216H4541999-09-23023 September 1999
Informs That During 990914 Telcon L Sanders & M Bielby Made Arrangements for Administration of Licensing Exams at Fermi Nuclear Station for Week of Jan 31,2000.NRC Will Make Exam Validation Visit to Facility During Week of Jan 10,2000
ML20216H3561999-09-23023 September 1999
Informs That During 990914 Telcon,L Sanders & M Bielby Made Arrangements with NRC to Inspect Licensed Operator Requalification Program at Fermi Nuclear Station for Week of 991129 Which Coincides with Util Regularly Scheduled Exam
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-99-0056, 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
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-99-0055, 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
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
ML20211C4761999-08-0606 August 1999
Forwards Draft Safety Evaluation Re Proposed Conversion of Current TS to Improved Standard TS
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
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)
ML20209E9991999-06-30030 June 1999
Forwards Insp Rept 50-016/99-01 on 990614-17.No Violations Noted.Potential Weakness in Airborne Effluent Concentration Assessment Identified
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARNRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999
Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed
NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999
Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl
ML20217N9231999-10-15015 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40
NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999
Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons
NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999
Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
ML20217D5331999-10-0707 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39
ML20217A3261999-09-30030 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38
NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999
Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations
ML20216G9791999-09-24024 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37
NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999
Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys
ML20212F3241999-09-20020 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36
NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999
Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public
NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999
Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
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-99-0056, 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-99-0076, 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
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
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-99-0038, 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-99-0040, 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-99-0045, Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl1999-05-0707 May 1999
Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl
NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses1999-04-30030 April 1999
Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses
NRC-99-0059, Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate1999-04-29029 April 1999
Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate
ML20206E2941999-04-28028 April 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 24
NRC-99-0037, Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl1999-04-26026 April 1999
Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl
1999-09-08
[Table view] |
Text
m
)
6 Doug!;,s R. Gipson 4
Senior Vice President, Nuclear Generation Fermi 2 -
l 6400 North Dixie liwy, New}v>rt, Michigan 481f,6 Tel: 734.586.5201 Fax: 734.f>86.4172 Detroit Edison September 24,1999 NRC-99-0092 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555
References:
- 1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43 l
- 2) NRC Administrative Letter 95-05, Revision 2," Revisions to l
Staff Guidance for Implementing NRC Policy on Notices of Enforcement Discretion" i
Subject:
Reauest for Enforcement Discretion The purpose of this letter is to document Detroit Edison's request for Enforcement Discretion with respect to the requirements of Technical Specification (TS) 3/4.6.1.8, Drywell and Suppression Chamber Purge System. This request was made verbally and discussed with NRC personnel during conference telephone calls on September 23,1999.
l On September 22,1999 it was discovered that the Nitrogen Inerting Drywell Air i
Purge Inlet Supply Valve, T4893F601, exceeded the allowable leakage rate specified by Technical Specification Surveillance Requirement 4.6.1.8.2. This enforcement l
discretion request involves an extension of Technical Specification 3.6.1.8, Action i
"b" requirements for an inoperable drywell and suppression chamber purge system supply and/or exhaust isolation valve. The extension would be from 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br /> on September 24,1999, when this action would require the plant to be in Hot Shutdown, until an exigent change to the Technical Specifications (to be submitted by September 25,1999) is approved and implemented. The additional time is necessary to obtain an Exigent Technical Specification and thus avoid a plant shutdown. Based on the infonnation provided in the conference calls on September 23,1999 and as documented in the enclosure to this letter, verbal approval of the Detroit Edison request was granted.
9910010126 990924 ADOCK0500g1
'PDR P
A 1r17 Energy Company
s.
USNRC NRC-99-0092 Page 2 The information included in the enclosure to this letter is provided consistent with the guidance in Section E of the enclosure to Reference 2.
1 If there are any questions, please contact Mr. Norman K. Peterson at (734) 586-4258.
Sincerely, e
Enclosure Attachment cc: J. E. Dyer
^
A. J. Kugler A. Vegel M. V. Yudasz, Jr.
NRC Resident Office Region III l
l l
l i
l i
s Enclosure to NRC-99-0092 Page1 Reauest For Enforcement Discretion-AdditionalInformation 1.
The Technical Specification or other license conditions that will be violated.
Technical Specification Limiting Condition for Operation (LCO) 3.6.1.8, Action (b) requires that with a drywell and suppression chamber purge system supply and/or j
exhaust isolation valve (s) with resilient material seals having a measured leakage rate exceeding the limit of Specification 4.6.1.8.2, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, i
2.
The circumstances surrounding the situation, including root causes, the need for
)
prompt action and identification of any relevant historical events.
The Drywell Air Purge penetration (X-26) has three isolation valves that are tested concurrently. The Inboard Isolation Valve (T4803F601, Butterfly,24 inch, Neles-Jamesbury,24-8222EX MOD. A) and Outboard Isolation Valves (T4800F407, Butterfly,24 inch, Neles-Jamesbury,24-8922EX MOD. A, and T4800F408, Butterfly, 10 inch, Neles-Jamesbury, 10-8926EX MOD. A) comprise the penetration's isolation.
The piping configuration is such that the T4800F407 is open directly to secondary containment on one side. This configuration lends itself to a direct visual inspection of the valve seat. T4800F408 connects to the nitrogen supply system. During leak testing, boundary valves are used to isolate T4800F408 from the nitgen system. A vent valve between T4800F408 and the test boundary valves is used to depress :rize and vent the piping outboard from T4800F408.
On September 22,1999, a Local Leak Rate Test (LLRT) was performed for penetrntion X-26 as required by Surveillance Requirement 4.6.1.8.2. This test is performed by pressurizing between the inboard and outboard isolation valves and measuring the total leakage of the isolation valves. The penantion exceeded its Technical Specification limit ofless than 0.05 L,(14.87 Standaro Cubic Feet per Hour (SCFH)). The penetration leaked at a rate of 26.7 SCFH. E; sed on direct observation of the T4800F407 and observation of an open % inch vent connection outboard of the T4800F408, test personnel determined that the penetration failed its LLRT due to seat leakage throQ T4803F601. Subsequently, valve T4803F601 was stroked under light pressure in an attempt to clear the sealing surfaces of any debris. The LLRT was performed again, and the leakage from penetration X-26 increased to 82.85 SCFH.
Since the only evolution performed between the two LLRTs was the stroking of T4803F601, this subsequent LLRT further substantiated that the leakage is attributable to T4803F601. Visual and audio inspection (utili7ing Snoop to aid in leak detection) for leakage at the exposed side of T4800F407 and s the vent connection outboard of T4800F408 by a Level II VT Inspector during both tests on September 22,1999
[
E S;
4 Enclosure to NRC-99-0092 Page 2 revealed insignificant leakage relative to the measured leakage rates. A Level III VT Inspector confirmed the initial visual inspection and confirmed that T4800F407 and T4800F408 were an insignificant contributor to the leakage during the second test. A 1
leak detection aid (Snoop) was utilized to aid in leak detection during both tests. Snoop was applied to the seal of T4800F407 and minor bubbling was observed; it was also used at the vent connection outboard of T4800F408 and no leakage was detected through this valve. This substantiated the assessment that the outboard isolation valves are tight.
Review of the LLRT and maintenance records does not indicate an adverse trend for this penetration. Results of previous tests indicate that the penetration leakage has been between approximately 0.6 SCFH and 1.75 SCFH since October of 1998 (four tests).
Failure of T4803F601 was not anticipated; and based on the magnitude of the leak and the change in leakage following valve stroke, the likely cause of the leakage is failure of the seal. The seal was replaced durit.g the Sixth Refueling Outage (autumn of 1998).
Based on the extremely good test results from the previous tests, it is highly unlikely that the cause of this test failure is attributable to any valve other than the T4803F601.
The overall primary containment leakage allowed by Technical Specification is 0.6 L,.
This equates to 178 SCFH. The known leakage from containment prior to September 22,1999 was 67.28 SCFH, leaving a margin of 110.72 SCFH. The leakage from penetration X-26 is 82.85 SCFH leaving a margin of 27.87 SCFH, when considering the T4803F601 as a single boundary valve (i.e., not crediting the outboard valves). The outboard valves will serve to significantly increase this margin, even though leakage
.l was not quantifiable.
3.
The safety basis for the request, including an evaluation of the safety significance and potential consequences of the proposed course of action. This evaluation should include at least a qualitative risk assessment derived from the licensee's PRA.
The safety basis for this request is the action to isolate the affected penetration using outboard isolation valves T4800F407 and T4800F408. While leak rate testing for this penetration can not quantify the leakage of the outboard valves individually, the leakage rate through these isolation devices is believed to be well below the acceptance criteria, as discussed in the preceding section. The compensatory action to verify the penetration is isolated on a periodic basis supports the safety function of the valves to isolate following an accident. Reliability of the resilient seals in these valves and the other similar penetrations at Fermi 2 has been high, providing confidence that unexpected degradation is not occurring in these valves.
i
2nclosure to NRC-99-0092 Page 3 The T4803F601 is not a risk significant component in the Level 1 Fermi 2 PSA. The T4803F601 is not an initiator of an event that leads to core damage and does not prevent a core damage event. The T4803F601 has no effect on core damage and is not modeled in the Level 1 Fermi 2 PSA.
The T4803F601 is a credited component of the Level 2 Fermi 2 PSA. The T4803F601 or the other in line isolation valves must close to isolate penetration X-26. The success criterion is that either inboard or outboard isolation valves in a line must close and remain closed for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With the penetration isolated by the outboard isolation valves, failure of the T4803F601 has no effect on the Level 2 PSA results and the success criteria for penetration X-26 is met. Therefore failure of the T4803F601 is not risk significant.
4.
The basis for the licensee's conclusion that the noncompliance will not be of potential detriment to the public health and safety and that neither an unreviewed safety question nor a significant hazard consideration is involved.
Total combined primary containment leakage allowed by Technical Specification 3.6.1.2 b. is 0.60 L,or 178 SCFH. As discussed previously, the actual combined primary containment leakage, including T4803F601, is approximatelyl50 SCFH, taking no credit for the outboard isolation valves in this penetration.
In addition, with the penetration X-26 outboard valves closed, it is believed that leakage for this penetration remains well within the 0.05 L, limit associated with this Technical Specification. The proposed remedial actions are also similar to actions that would be required by Fermi 2 (proposed) Improved Technical Specifications for restoring the flow path leakage.
5.
The basis for the licensee's conclusion that the noncompliance will not involve adverse consequences to the environment.
As discussed above, the proposal involves no significant hazard consideration. The proposal will not change the types or amounts of effluents that may be released offsite, nor increases individual or cumulative occupational radiation exposures, since the proposal essentiaily maintains the overall leakage of the penetration within the required limits.
6.
Any proposed compensatory measure (s).
The T4800F407 and T4800F408 isolation valves are normally closed isolation valves that will be closed and deactivated assuring the valves remain closed until the
1 Enclosure to NRC-99-0092 Page 4 T4803F601 is repaired. They will be verified closed every 31 days. T4800F407 and T4800F408 will not be cycled until the plant is shutdown to repair the T4803F601.
l Because the leakage through the outboard isolation valves cannot be individually quantified, a flanged cover will be installed over the opening of T4800F407 by September 28,1999 to provide an additional leakage barrier. This flange will remain in place until the plant is shutdown to correct the penetration leakage. Leak testing of this penetration will be performed at least every 45 days to verify that the 0.6 L, is not exceeded due to additional penetration leakage. This testing will niso qualitatively verify the integrity of the outboard isolation barriers (employing the visual and audio inspection techniques and Snoop similar to techniques used on September 22,1999, as described above).
7.
The justification for the duration of the noncompliance.
The time requested will allow time to obtain an Exigent Technical Specification change.
Detroit Edison expects this amendment request will be submitted by September 25, 1999. The NRC approval of the Technical Specification Amendment may take as long as four weeks. The compensatory measures discussed above are being implemented.
The actions are equivalent to what will be approved in the Technical Specification Amendment.
8.
A statement that the request has been approved by the facility organization that normally reviews safety issues (Plant Onsite Review Committee, or its equivalent).
1 This request has been reviewed and approved by the Fermi 2 On Site Review Organization (OSRO).
9.
The request must specifically address how one of the NOED criteria for i
approc,riate plant conditions specified in Section B is satisfied.
Criterion 1 (a) of Section B is applicable to this request. This criterion states in part:
"1.
For an operating plant, the NOED is intended to (a) avoid undesirable transients as a result of forcing compliance with the license condition and, thus l
minimize potential safety consequences and operational risks..."
i In this case, Fermi 2 is operating and unless this request is granted would be required to shutdown. Assuming a required plant shutdown carries the same risk as a given inadvertent scram, the shutdown activity increases core damage risk potential compared to continued plant operation with T4803F601 leaking.
I l
i i
Enclosure to NRC-99-0092 Page 5 Thus, this situation meets a criterion given in Section B of the NRC Guidance for Issuance of Enforcement Discretion.
10.
If a follow-up license amendment is required, the NOED request must include marked-up Technical Specification pages showing the proposed Technical Specification changes. The actuallicense amendment request must follow within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. includes a marked-up version of the current Technical Specification pages.
11.
A statement that prior adoption 01 approved line-item improvements to the Technical Specifications or the Improved Technical Specifications would not have obviated the need for the NOED request.
Detroit Edison submitted Improved Technical Specifications in April 1998. The NRC is expected to approve the submittal in September 1999. However, Improved Technical Specifications does not fully obviate the need for this NOED request.
l 12.
Any other information the NRC staff deems necessary before making a decision to exercise enforcement discretion.
All NRC comments and requests for information have been incorporated into Items 1 through 11 above.
i d
i
)
