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
[Table view]
Category:UTILITY TO NRC
MONTHYEARNRC-90-0142, Forwards Revised Semiannual Fitness for Duty Rept,Consisting of Statement Re Percentage of Individuals Tested & Revised Graph,Per G Pirtle Request1990-09-0707 September 1990
Forwards Revised Semiannual Fitness for Duty Rept,Consisting of Statement Re Percentage of Individuals Tested & Revised Graph,Per G Pirtle Request
NRC-90-0152, Forwards Rev 3 to Radiological Emergency Response Preparedness Plan.W/O Encl1990-09-0505 September 1990
Forwards Rev 3 to Radiological Emergency Response Preparedness Plan.W/O Encl
NRC-90-0139, Responds to NRC Re Memorization of Immediate Operator Actions in Abnormal Operating Procedures (Aop). Definition of Immediate Action Under Review to Provide Mechanism for Consistent Application to All AOPs1990-08-31031 August 1990
Responds to NRC Re Memorization of Immediate Operator Actions in Abnormal Operating Procedures (Aop). Definition of Immediate Action Under Review to Provide Mechanism for Consistent Application to All AOPs
NRC-90-0116, Forwards Semiannual Fitness for Duty Rept1990-08-29029 August 1990
Forwards Semiannual Fitness for Duty Rept
NRC-90-0117, Forwards, Fermi 2 Nuclear Power Plant Semiannual Radioactive Effluent Release Rept for Jan-June 1990. No Releases Occurred1990-08-28028 August 1990
Forwards, Fermi 2 Nuclear Power Plant Semiannual Radioactive Effluent Release Rept for Jan-June 1990. No Releases Occurred
NRC-90-0118, Forwards Endorsement 35 to Maelu Policy MF-120 & Endorsement 139 to Nelia Policy NF-921990-08-24024 August 1990
Forwards Endorsement 35 to Maelu Policy MF-120 & Endorsement 139 to Nelia Policy NF-92
NRC-90-0135, Affirms That Util Intends to Conduct Insp of Low Pressure Turbine Rotor Disks During Upcoming Refueling Outage.Insp of Low Pressure Turbine 2 Carried Out During First Refueling Outage.No Evidence of Stress Corrosion Found1990-08-17017 August 1990
Affirms That Util Intends to Conduct Insp of Low Pressure Turbine Rotor Disks During Upcoming Refueling Outage.Insp of Low Pressure Turbine 2 Carried Out During First Refueling Outage.No Evidence of Stress Corrosion Found
NRC-90-0137, Forwards NPDES Permit MI0037028 for Plant,Approved by State of Mi Water Resources Commission During 900719 Meeting1990-08-17017 August 1990
Forwards NPDES Permit MI0037028 for Plant,Approved by State of Mi Water Resources Commission During 900719 Meeting
NRC-90-0136, Requests That NRC Administer Operator Licensing Exam in Dec 1990 & Postpone Operator Requalification Exam1990-08-17017 August 1990
Requests That NRC Administer Operator Licensing Exam in Dec 1990 & Postpone Operator Requalification Exam
NRC-90-0133, Forwards Rev 5 to Security Personnel Training & Qualification Plan.Rev Establishes App D & Records Retention Matrix to Provide Central Location in Plan for Info on Records Retention Pages 3-4,3-8 & 3-9.Rev Withheld1990-08-0909 August 1990
Forwards Rev 5 to Security Personnel Training & Qualification Plan.Rev Establishes App D & Records Retention Matrix to Provide Central Location in Plan for Info on Records Retention Pages 3-4,3-8 & 3-9.Rev Withheld
NRC-90-0112, Responds to NRC Re Violations Noted in Insp Rept 50-341/90-07.Corrective Actions:Review of RF01 Turbine Work Packages to Identify Where Addl Controls Should Be Placed in Similar Future RF02 Packages Conducted1990-08-0303 August 1990
Responds to NRC Re Violations Noted in Insp Rept 50-341/90-07.Corrective Actions:Review of RF01 Turbine Work Packages to Identify Where Addl Controls Should Be Placed in Similar Future RF02 Packages Conducted
NRC-90-0111, Responds to Concerns Re Open Item 90-007-04,per NRC 900627 Request.Potential Enhancements to Drawings Being Reviewed & to Be Resolved by Dec 19901990-08-0303 August 1990
Responds to Concerns Re Open Item 90-007-04,per NRC 900627 Request.Potential Enhancements to Drawings Being Reviewed & to Be Resolved by Dec 1990
ML20055H8921990-07-26026 July 1990
Forwards Certification of Financial Assurance for Decommissioning of Facility,Per 10CFR50.33(k) & 50.75. Util Intends to Retain Unit 1 in Safe Storage Status Until Unit 2 Shut Down & Decommissioned
NRC-90-0131, Forwards Rev 15 to Physical Security Plan.Rev Withheld1990-07-24024 July 1990
Forwards Rev 15 to Physical Security Plan.Rev Withheld
NRC-90-0108, Discusses Deletion of Commitment for Temporary Mod Program, Per Insp Rept 50-341/84-25.Requirement for Operations Engineer to Approve Extensions of Temporary Mods Beyond 30 Days Being Deleted from Procedure FIP-OP1-021990-07-18018 July 1990
Discusses Deletion of Commitment for Temporary Mod Program, Per Insp Rept 50-341/84-25.Requirement for Operations Engineer to Approve Extensions of Temporary Mods Beyond 30 Days Being Deleted from Procedure FIP-OP1-02
NRC-90-0093, Submits Clarification of Design for Plant Suppression Pool Temp Monitoring Sys.Design Adequate to Ensure Suppression Pool Water Temp within Allowable Tech Spec Limits1990-07-18018 July 1990
Submits Clarification of Design for Plant Suppression Pool Temp Monitoring Sys.Design Adequate to Ensure Suppression Pool Water Temp within Allowable Tech Spec Limits
NRC-90-0091, Requests Relief from Commitment to Perform 100% Audits of Tech Spec Line Items.Tech Spec Improvement Program Has Been Completed Which Provides Extensive Review of Tech Spec Line Items1990-07-0202 July 1990
Requests Relief from Commitment to Perform 100% Audits of Tech Spec Line Items.Tech Spec Improvement Program Has Been Completed Which Provides Extensive Review of Tech Spec Line Items
NRC-90-0101, Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status for Each Issue Encl1990-06-29029 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status for Each Issue Encl
NRC-90-0100, Discusses Installation of Motor Operated Valve Limiter Plates,Per IE Bulletin 85-003.Commitment to Install Limiter Plates Deferred Until Time When Valve or Valve Operator Would Be Disassembled for Another Reason1990-06-27027 June 1990
Discusses Installation of Motor Operated Valve Limiter Plates,Per IE Bulletin 85-003.Commitment to Install Limiter Plates Deferred Until Time When Valve or Valve Operator Would Be Disassembled for Another Reason
NRC-90-0088, Discusses Changes Made to Commitment Addressing Calibr Frequency for Inservice Test Instrumentation,Per Violation 87009-03.Nine-month Calibr Frequency for Subj Instrumentation No Longer Appropriate or in Use1990-06-14014 June 1990
Discusses Changes Made to Commitment Addressing Calibr Frequency for Inservice Test Instrumentation,Per Violation 87009-03.Nine-month Calibr Frequency for Subj Instrumentation No Longer Appropriate or in Use
NRC-90-0095, Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request1990-06-0606 June 1990
Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request
NRC-90-0089, Submits Supplemental Response to NRC Concerns on RHR Operability from Insp Rept 50-341/89-17.Util Faced W/ Decision to Provide Addl Overheating Protection to RHR Sys Pump Vs Maintaining Necessary Water Coverage of Fuel1990-06-0404 June 1990
Submits Supplemental Response to NRC Concerns on RHR Operability from Insp Rept 50-341/89-17.Util Faced W/ Decision to Provide Addl Overheating Protection to RHR Sys Pump Vs Maintaining Necessary Water Coverage of Fuel
NRC-90-0085, Provides Plans for Eliminating Temporaary Mods at Plant,Per Insp Rept 50-341/90-051990-05-29029 May 1990
Provides Plans for Eliminating Temporaary Mods at Plant,Per Insp Rept 50-341/90-05
NRC-90-0083, Discusses Action Plan to Review Socket Weld Failures at Plant.Failure History of Socket Welds Will Be Investigated to Determine Whether or Not Significant Common Mode Failure Mechanism Evident.Plan Expected to Be Completed by 9005251990-05-18018 May 1990
Discusses Action Plan to Review Socket Weld Failures at Plant.Failure History of Socket Welds Will Be Investigated to Determine Whether or Not Significant Common Mode Failure Mechanism Evident.Plan Expected to Be Completed by 900525
NRC-90-0074, Discusses Insp of Flash Tanks & Reactor Feed Pump Strainers. No Further Evidence of Moisture Separator Reheater Debris Discovered in Strainers,Stub Tubes,Wire Mesh or Structural Members1990-05-18018 May 1990
Discusses Insp of Flash Tanks & Reactor Feed Pump Strainers. No Further Evidence of Moisture Separator Reheater Debris Discovered in Strainers,Stub Tubes,Wire Mesh or Structural Members
NRC-90-0082, Documents Commitments Made During Recent Meetings & Telcon on RHR Sys Small Bore Connections1990-05-11011 May 1990
Documents Commitments Made During Recent Meetings & Telcon on RHR Sys Small Bore Connections
NRC-90-0068, Forwards 1989 Annual Financial Repts for Detroit Edison Co & Wolverine Power Supply Cooperative,Inc1990-05-0101 May 1990
Forwards 1989 Annual Financial Repts for Detroit Edison Co & Wolverine Power Supply Cooperative,Inc
NRC-90-0071, Responds to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-341/90-03 Re Emergency Preparedness Exercise Weaknesses. Corrective Actions:Case Studies Will Be Developed & Presented in Licensed Operator Requalification Training1990-04-30030 April 1990
Responds to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-341/90-03 Re Emergency Preparedness Exercise Weaknesses. Corrective Actions:Case Studies Will Be Developed & Presented in Licensed Operator Requalification Training
NRC-90-0078, Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Bow. Util Has Decided That Fuel Channel Boxes Will Not Be Used After First Bundle Lifetime1990-04-25025 April 1990
Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Bow. Util Has Decided That Fuel Channel Boxes Will Not Be Used After First Bundle Lifetime
NRC-90-0051, Responds to SALP 11 Board Rept 50-341/90-01.Outage Critique Action Plan Issued for First Refueling Outage Identifying Lessons Learned & Areas Needing Improvement1990-04-12012 April 1990
Responds to SALP 11 Board Rept 50-341/90-01.Outage Critique Action Plan Issued for First Refueling Outage Identifying Lessons Learned & Areas Needing Improvement
NRC-90-0060, Responds to 900104 Request for Supplemental Station Blackout Submittal1990-03-29029 March 1990
Responds to 900104 Request for Supplemental Station Blackout Submittal
NRC-90-0061, Forwards Addl Info Re Proposed Drywell Level Instrument Line Configuration,As Followup to 890927 Tech Spec Change Request.Rept Provides Info Re Reasons for Designating Primary Containment Isolation Valve Normally Opened1990-03-27027 March 1990
Forwards Addl Info Re Proposed Drywell Level Instrument Line Configuration,As Followup to 890927 Tech Spec Change Request.Rept Provides Info Re Reasons for Designating Primary Containment Isolation Valve Normally Opened
NRC-90-0055, Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47 - Safety Implications of Control Sys in Lwrs. Overfill Protection Sys Adequately Separated from Main Feedwater Control Sys1990-03-19019 March 1990
Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47 - Safety Implications of Control Sys in Lwrs. Overfill Protection Sys Adequately Separated from Main Feedwater Control Sys
NRC-90-0024, Suppls Response to Violations Noted in Insp Rept 50-341/85-47 Re Security Records.Util Intends to Rely Solely on Historical Tapes to Retrieve Records Required by Physical Security Plan.Hard Copy Computer Logs Will Be Discarded1990-03-16016 March 1990
Suppls Response to Violations Noted in Insp Rept 50-341/85-47 Re Security Records.Util Intends to Rely Solely on Historical Tapes to Retrieve Records Required by Physical Security Plan.Hard Copy Computer Logs Will Be Discarded
NRC-90-0045, Forwards Inservice Insp Summary Rept of 1989 Inservice Insp at Fermi 2 Nuclear Power Plant.1990-03-13013 March 1990
Forwards Inservice Insp Summary Rept of 1989 Inservice Insp at Fermi 2 Nuclear Power Plant.
NRC-90-0043, Responds to NRC 900224 Ltr Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 9002021990-03-0909 March 1990
Responds to NRC 900224 Ltr Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 900202
NRC-90-0054, Responds to NRC 900212 Order Modifying License & Notice of Violation.Corrective Actions:Former Director of Nuclear Security No Longer Works for Util & Extensive Actions Taken to Improve Communications W/Nrc1990-03-0909 March 1990
Responds to NRC 900212 Order Modifying License & Notice of Violation.Corrective Actions:Former Director of Nuclear Security No Longer Works for Util & Extensive Actions Taken to Improve Communications W/Nrc
NRC-90-0037, Forwards Completed Questionnaires for Types of Insps,Audits & Evaluations,In Response to Generic Ltr 90-01, Voluntary Participation in NRC Regulatory Impact Survey.1990-03-0505 March 1990
Forwards Completed Questionnaires for Types of Insps,Audits & Evaluations,In Response to Generic Ltr 90-01, Voluntary Participation in NRC Regulatory Impact Survey.
NRC-90-0029, Responds to Violations Noted in Insp Rept 50-341/89-36. Corrective Action:All Personnel in Operations & I&C Viewed Professionalism Video Which Included Presentation of Facts Concerning Event1990-03-0505 March 1990
Responds to Violations Noted in Insp Rept 50-341/89-36. Corrective Action:All Personnel in Operations & I&C Viewed Professionalism Video Which Included Presentation of Facts Concerning Event
NRC-90-0028, Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Revised Pages of Rept for Jul-Dec 1988, Containing Recalculated Noble Gas Releases & Doses1990-03-0101 March 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Revised Pages of Rept for Jul-Dec 1988, Containing Recalculated Noble Gas Releases & Doses
NRC-90-0034, Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results1990-02-26026 February 1990
Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results
NRC-90-0036, Forwards Response to NRC Survey on Nuclear Fuel Cycle Industry Future Activity,Per 900122 Request1990-02-26026 February 1990
Forwards Response to NRC Survey on Nuclear Fuel Cycle Industry Future Activity,Per 900122 Request
NRC-90-0026, Forwards Monthly Operating Rept for Jan 1990 for Fermi Unit 2 & Revised Rept for Dec 1989,correcting Error in Net Electrical Generation Figure1990-02-15015 February 1990
Forwards Monthly Operating Rept for Jan 1990 for Fermi Unit 2 & Revised Rept for Dec 1989,correcting Error in Net Electrical Generation Figure
NRC-90-0020, Forwards Response to Violations Noted in Insp Rept 50-341/89-31 Re Maint Support for Security Equipment.Addl Instrumentation & Control Repairmen Hired.Encl Withheld (Ref 10CFR73.21)1990-02-12012 February 1990
Forwards Response to Violations Noted in Insp Rept 50-341/89-31 Re Maint Support for Security Equipment.Addl Instrumentation & Control Repairmen Hired.Encl Withheld (Ref 10CFR73.21)
NRC-90-0010, Responds to NRC 900102 Ltr Re Violations Noted in Insp Rept 50-341/89-30.Corrective Actions:Storage Area in Machine Shop closed-out & QA1 Matl Returned to Warehouse Where Positive Controls in Effect & Shift Turnover Procedure Revised1990-02-0101 February 1990
Responds to NRC 900102 Ltr Re Violations Noted in Insp Rept 50-341/89-30.Corrective Actions:Storage Area in Machine Shop closed-out & QA1 Matl Returned to Warehouse Where Positive Controls in Effect & Shift Turnover Procedure Revised
NRC-90-0013, Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design. Subj Valves Not Used by Util1990-01-26026 January 1990
Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design. Subj Valves Not Used by Util
NRC-90-0012, Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 19911990-01-26026 January 1990
Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 1991
NRC-90-0016, Responds to 10CFR26 Re fitness-for-duty Programs.Util Conducting Testing for Drugs Described in 10CFR26,App a, Section 2.1(a) & at Cutoff Levels Defined in Sections 2.7(3)(1) & 2.7(f)(2) as of 9001031990-01-26026 January 1990
Responds to 10CFR26 Re fitness-for-duty Programs.Util Conducting Testing for Drugs Described in 10CFR26,App a, Section 2.1(a) & at Cutoff Levels Defined in Sections 2.7(3)(1) & 2.7(f)(2) as of 900103
NRC-89-0297, Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp1990-01-12012 January 1990
Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp
NRC-89-0240, Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches1990-01-11011 January 1990
Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches
1990-09-07
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DOITOil Femil2 Edison HEiEN c:a June 1, 1987 NIC-87-0078 U. S. !bclear Regulatory Commission Attna Document Control Desk Washington, D. C. 20555
References:
- 1) Fermi 2 NIC Docket No. 50-341 NBC License No. IPF-43
- 2) Inservice Inspection - Non Destructive Examination (ISI-EE) Program Plan for Fermi 2, Revision 0, Change 2, dated January 1987.
- 3) NIC Letter to Detroit Elison Conpany, " Request for Mditional Information Relative to the Fermi 2 First Ten-Year Interval Inservice Inspection Program Plan,"
data 3 March 27,1987.
Subject:
Mditional Information on First Ten-Year Interval ISI Procram Plan In the Referencs 3 letter, the NIC requested Detroit Riison to provide additional information on the Fermi 2 ISI-f0E Program (Reference 2) . I As stated in the request, the inforlaation is needed by the Nlt Staff j to couplete its review and evaluation of the Fermi 2 ISI-mE Program '
for the first ten-year interval of inspection.
Detroit Eli z.I's response to the three itens of a3ditional information requested is enclosed. Also, as requested, a copy of this respotse is being sent to the attention of Mr. B. Brown at Idaho National ,
Digineerirvj Laboratory (INEL) . l 1
l a \
8706050159 870601 PDR ADOCK 05000341 i [ '
G PDR ,
I l
L ;
s . . . .
USNIC Anne 1, 1987 NIC-87-0078 -
Page 2 If you have any questions regarding this submittal, please contact Mr. Iewis Bregni at (313) 586-4072. I Sincerely,
_ '4 . T.
F. E. Agosti Vice President MJGlear Operations Enclosure oc: B. Brown (INEL)
A. B. Davis )
W. G. Rogers J. J. Stefano
( E. G. Greenman l
l l
l l
. - - - ~ . - .- - - ~ . - - - . . .. . . ,
w .
Ehclcsure ta NIC-87 -0078 Page 1 ADDITIONhL IIFOINATION REWESZlD
, .A. Plans fcy inservice er. amination of the Beacter pressure Veseel'
. welds shouM address the degree of compliance _with Regulatory ,
a aside 1.150, " Ultrasonic Testing Of Reactor Vessel Welds During Preservice ard Inservice Examinations". Discuss the near-surface e examination and resolution with regards to finding service ,
irduced flaws and the use of electronic gating as related to the !
volume 60 material near the surface that is not being examined.
Detroit B!Ison h p Item Ar Inservice examircations of the Beactor Pressure Vessel will be
, performed using both manual and mechanical examination tecimiques from the outside surface of the vessel. The CRP presentation,
!- which is the primary data acquisition technique to be used .for recording and analysis, is not electronically gated to esclude any areas during either the manual or mechanized examinatioris. ,
i The eltetronic gate / strip chart is used as a supplemental data recording system during mechanized examinations to flag areas of.
major concern.
Mere is a sinall volume, typically less than 1/2 inch, on the outside entry surface of the vessel which ic, masked by the initial pulse of the trans2fucer in which irdications would not be detected. This initial pulse effect is minimized by the design -
of trensducer wedges, in ithe case of manual examinations; or the modales which hold rultiple' transducers when performing examinations using mechenized technigaes.. The effect of this
! initial pulse as well as any other limitations encountered which affect the examination vollune as prGacribed by ASEE Section' XI ,
i will be documented in an emination report as required by -
Regulatory G2ide 1.150, Revision 1, Appendix A.
I Regulatory Q2ide 1.150, Revision 1, Appendix A, Section 3.1(a) addresses, as a primary concern, the vessel inner surface area ,
and_ recocuends tie use of the 2 percent notch which panetrates the internal (clad) surface of calibration blocks' for detoction -
of flaws in the region. This is the calibration.and examic9 tion method that will be used. Therefore, service induced flaws which
- may originate in the inner surface clad material and propagate i
- into the base material in the order of magnitude of the 2%
calibration notch specified in Section V, Article 4, Figure T-44.1 would have a.h!.gh probability of detection depending upon their orientation with respect to the search units.
Indications, regardless of applitude, will be recorded on tape during' the mechanized examissations for analysis. Similarly, signal responses will be scrutinized durire the manual
- examination process and indications will be recorded for further malysis and_ resolution.
i
- . - - - . -. .. . - - - - - - .-+ _ . ,-.- , . . - , , - - , , _ . - , , , , . , .
i
. +
Ehclosure to 15C-87-0078 Page 2 B. The Licensee has discussed the augmented examinations that will be performed in accordance with NURBG-0313 and -0619, IE Bullet.in l
Nos. 80-07 and 83-02, and NIC Generic Letter 84-11. In addition to the requested infoimation in item A above, discuss any other ,
augmented examinations that will be performed during the first 10-year inspection interval (e.g. compliance with NURBG-0800, Section 3.6.1; NURBG-0803; IE Bulletin 80-13; etc.) .
Detroit Elson Response to Item Br IURBG-0803, Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping.
With regard to piping, Detroit Eison has' performed or.has incorporated into its program the following itens which satisfy the staff recomendations contained in NORBG-0803.
- 1. To ensure the integrity of the Sctam Discharge Volume (SDV) piping and supports a walkdown of the SDV piping system was performed to verify the as-built condition. A seismic i analysis and stress report was performed on the piping system in accordance with A!ME Section III, Class 2.
- 2. EDV piping welds have been selected in aocordance with -
requirements of AfME Section XI, and have been included in '
the ISI-PDE Program (Reference 2, page A-6-81) .
- 3. A preservice weld inspection using Ur and MP has been performed for the selected SDV piping welds. ;
In addition, although not reconsnended in NURBG-0803, a visual walkdown of the SDV piping is performed os part of the leakage reduction program.
IE Bulletin No. 80-13, Cracking in Core Spray Sp&rgers This bulletin was forwarded to Detroit Eison for information and
. required no writtEra response. However, although IE Eulletin No.
- 80-13 is not specifically addressed in the ISI-BOE Program, a visual examination (VT-3) of the core spray spargers and core-spray vessel interior piping is performed. This inspection is - ,
described on page A-6-59 of Reference 2. Consistent with the '
examination frequercy and type given for vessel internals in A!ME Section XI, the core sprt.y sparger and interior piping are scheduled for inspection at the first refueling outage and every.
3 years thereafter. Please note there is an error in the nethod 1 of examination to be used as given in Reference 2. A remote visual examination will most likely be used as opposed to direct. ,
i 1
i-_ . . _ _ __ _ __ _ _ _ .--, , _. _ - _ = = .. _ ... _ , _ . _ , _-. _ ... _ .s -
l Enclosur@ to !
NIC-87-0C18 !
Page 3 Petroit Etlison Response to Item Bt (Cont.)
NUREG-080!), Standard Review Plan - Section 3.6.1., Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment.
There are no augmented inspections identified in the Fermi 2 ISI-?DE Progrge for piping between containment isolation valves.
We selection of Class 1 and 2 pressure retaining piping welds for inservice inspection was made using the requirements of ASME Section XI. These weld selection criteria are discussed in Part E, Appendices A and B of Reference 2.
Weld selection criteria include consideration for terminal ends, high stress, coderate stress, and random selection. These criteria were used to select welds for inservice inspection in piping between containment isolation valves as well. Therefore, es a result of the established method for selecting pipe welds, sume welds in piping between containment isolation valves are included in the ISI-10E Program.
Some welds that are located in piping between containment isolction valves are inaccessible (i.e. those within penetration assenblies) . Cn the basis of tre established weld selection criteria, one moderate stress weld would have required examination. For this case a specific relief request has been made and is contained in Section 4.0 of Reference 2.
It should be noted that the Fermi 2 Construction permit
@ plication was tendered in 1969, which precedes the date of issuance of NUREG-0800.
L
l Belosura to i NIC-87-0078 - l Page 4 i.
- C. Provide the staff withia reference list of calibration blocks including identificationsi material specifications, and sizes
Detroit E$ison Response to Item Cr REFERE!CE ID No. DESCRIPTION MATERIAL TYPE HEAT ND.
SS-2 28-XXX-1.5-SS-2-FER A!ME Sh-358 (Sh 240 GR. 304) 24720 SS-3 2&XXX-1.076-SS-3-FER A!ME SA-358 (Sh 240 GR. 304) 24720 CS-5 26-XXX-1.125-CS-5-FER A!ME SA-155-GR NCF 70 9919 (Sh-516 GR. 70)
CS-6 26-XXX-1.500-CS-6-FER A!ME Sh-155 KC70 (Sh-516 2G2575 GR. 70)
CS-7 24-100-1.531 CS-7-FER AfME SA-106 GR. B . 453543
. SS8 24-100-1.531-SS-8-FER A!ME Sh-358 (Sh 240 GR. 304) 724043 I CS-9 24-80-1.218-CS-9-FER AfME SA-106 GR. B ~ L25222 l SS-10 22-XXX-1.125-SS-10-FER A!ME Sh-240 GR. 304 855315 CS-ll 20-100-1.281-CS-ll-FER AfME SA-106 GR. B 253732 (Sh 333 GR. 6)
CS-12 20-80-1.031-CS-12-FER A!ME Sh-106 GR. B L25047 SS-13 20-80-1.031-SS-13-FER AfME Sh-358 GR. 304 855315 (SR 240 GR. 304) l CS-14 14-XXX-1.0-CS-14-FER A!ME SA-106 GR. B L20993 CS-15 12-100-0.844-CS-15-FER A!ME Sh-106 GR. B 234537 SS-17 12-80-0.688-SS-17-FER A!ME Sh-358 (SR 240 GR. 304) 646518-2D CS-18 10-120-0.844-CS-18-FER A!ME Sh-106 GR. B L61275 SS-19 10-80-0.594-SS-19-FER A!ME Sh-376 GR. 304 535641 CS-20 8-160-0.906-CS-20-FER A!ME SA-106 GR. B 252086 CS-il 6-160-0.719 CS-21-FER A!ME Sh-106 GR. D N54044 CS-22 6-120-0.562-CS-22-FER A!ME SA-106 GR. B N54029
- SS-23 4-160-0.531-SS-23-FER A!ME Sh-376 GR. 304- M0118 CS-24 4-120-0.434-CS-24-FER A!ME Sh-106 GR. B G97821-l SS-25 4-80-0.337-SS-25-FER A!NE Sh-376 GR.' 304 M2152 CS-26 3-160-0.438-CS-26-FER AfME SA-106 GR. B - L24259 i CS-27 2.50-160-0.375-CS-27-FER A!ME SA-106 GR. B X773794 SS-28 2-160-0.344-SS-28-FER A!NE SA-182 GR. F304 75678 SS-29 1.5-160-0.281-SS-2 M ER AfME SA-132 GR. 304 SZ460 l SS-30 28-XXX-2.5-SS-30-FER A!NE 358- (Sh-240 GR. 304) IK5853 CS-31 20-XXX-1.5-CS-31-FER A!ME Sh 516 GR. 70 2C1676
- CS-32 12-140-1.125-CS-32-FER A!ME SA-106 GR. B 45860 -
I SS-33 PL .750-SS-33-FER A!ME SA-240 GR. 304 F81443 l l SS-34 PL-1.5-SS-33-FER AfME SA-240 GR. 304 F74272
{ CS-35 2-XXX .4-CS-35-FER A!ME SA-106 GR. B N57214 CS-36 10-80 .594-CS-36-FER A!ME SA-106 GR. B LO4243 CS-37 10-160-1.125-CS-37-FER A!ME Sh-106 GR. P, 252486 CS-38 12-80 .688-CS-38-FER AME SA-106 GR. 3 ' N13535 CS-39 14-80 .750-CS-39-FER A!ME SA-106 GR. B N12947 CS-40 18-40 .562-CS-40-FER A!ME SA-106 GR. B LO2322
{ CS-41 18-80 .938-CS-41-FER A!ME Sh-106 GR. B -N95312 1
CS-42 20-40 .594< S-42-FER A!ME Sh-106 GR. B 33210 i CS-43 24-40 .688-CS-43-FER A!ME SA-106 GR. B LO3155 i
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'Ehclosura to NRC-87-0078 Page 5 REFERE2CE ID No. DESCRIPTION MATERIAL 'IYPE HEAT NO.
CSCL44 12.750-CSCL-X-1.0262- AEME SA-508 CL2 218993 44-FER IN-45 12.9-IN-X-1.165-45-FER AfME SB 166 AVX CS-46 14.125-CS-X .95-46-FER AfME SA-508 CL2 218993 CSCL47 5.438-CSCL-X .813-47-FER AfME S1508 CL2 218993 CSCL48 6.438-CSCL-X .782-48-FER A!NE SA-508 OL2 218993 IN-49 6.5-IN-X .802-49-FER AEME SB-166 2155-0-3443 CS-50 10-100 .719-CS-50-FER AEME SA-106 GR. B N52963 CSCL51 IR-CfCL-51-FER AfME SA-508 CL2 02Q99NQP CSCL52 FS/L-CSCL-52-FER A!NE SA-508 CL.2 Q20100NQRP CS-53 8.75-6.25-8-CS-53-FER AfME SA-540-GR B24 6051044 CECL54 14.5-CSCL-X-1.200-54-FER ASIM A-508 CL2 020110NQP CSCL55 29.375-CSCL-X-1.760-55-FER ASIM A-508 CL2 020110NQP '
SS-56 14.5-SS-X-1.200-56-FER ASIM A-182 F304 82741 SS-57 29.375-SS-X-1.500-57-FER ASIM A-182 F304 82741 f SB-58 SB-2667-58 AfME SA-533 GR. B CL.1 C5445-1 SB-59 SB-2667-59 AfME SA-533 GR. B CIASS 1 C4504-3 SB-60 SB-2667-60 ASME SA-533 GR. B CIASS 1 C4505-3 SB-62 SB-2667-62 AfME SA-533 GR. B CIASS 1 - C-4578 SIAB 1 ED-63 SD-2667-63 ASME SA-508 CIASS 1 AEME SA-508 CIASS 2 ED-64 ED-2667-64 AEME SA-508 CIASS 1 216617 ASME SA-508 CIASS 2 AV 3504-909446 ,
ED-65 SD-2667-65 AfME SA-508 CIASS 1 OlOlN- l 772B-4 l AfME SA-508 CIASS 2 IV-3459 SER 194 ED-66 SD-2667-66 AfME SA-508 CIASS 1 OlOlN-773B-7 l AEME SA-508 CIASS 2 IV3459 SER 194 ED-67 SD-2667-67 AEME SA-182 F304 Cl335 ASME SA-508 CIASS 2 AV3926 SD-68 ED-2667-68 SA-182 F304 61581-CV A!NE SA-508 CIASS 2 2L-1318 ED-69 ED-2667-69 AEME SA-182 F304 AfME SA-508 CIASS 2 ED-70 SD-2667-70 ASME SB-166 9492 AEME SB-182 F304 3082570 SC-74 SC-2667-74 AEME SA-540 GR. B24 ED-76 ED-2667-76 AEME SA-508 CIASS 2 AV3929-9E9210 ED-77 SD-2667-77 AEME SA-508 CIASS 2 AV3929 9E9210 SD-78 ED-2667-78 AEME SA-508 CIASS 2 E -4A CB&I MK-4A SB-166 SA-508 CIASS 1 MK-5A CB&I N -5A SB-166 SA-508 CIASS 2 B31 CAP GE 66B9241 SA-403 GR. 304 743668
Enclosur@ to IGC-87-0078 Page 6 RITERi@CE ID No. DESCRIPTION MATERIAL TYPE HEAT NO.
B31S'IU B-3047025 AS40 GRADE B-23 95865 CS-79 IR-CSCL-79-FER SA-508 CIASS 2 Q20lllNQP CS-80 PL-1. 5-CS-80-FER SA-516 GRADE 70 2G7527 CS-81 IR-CS-81-FER SA-105 5458619 KCE
- 1. 53 - CS FER Reference ID No.
Wall Thickness Pipe ~ Schedule Pipe Diameter CS-Stainless Steel CSCL-Carbon Steel Clad PL-Plate CS-Carbon Steel IN-Inconnel XXX-Special Thickness or Schedule
! ED-2667-70 This series of calibration blocks supplied by Conbustion Ehgineering i.
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