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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Text
%co Pr:sident Nuclear Operatens Fermi-2 i 6400 Norm Dixie Hghway jom Newport. u,cnigan 4aise February 18, 1985 IQVII (313) 586-4150 EF2-70386 Mr. James G. Keppler Regfonal Administrator Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
Reference:
(1) Fermi 2 NRC Docket No. 50-341 (2) Letter, W. H. Jens to J.G. Keppler, February 16, 1985, EF2-70390
Subject:
Detroit Edison Response Inspection Report 50-341/84-68 This letter responds to the items of noncompliance described in your Inspection Report No. 50-341/84-68. This inspection was conducted by Messrs. R. Mendez, Z. Falevits, K. Tani, and A. Gautam of NRC Region III on December 19-20, 1984 and January 3-5 and 10-12, 1985.
The item of noncompliance is discussed in this reply as required by Section 2. 201 of the NRC's " Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations. The enclosed response also addresses each of the unresolved issues iden-tified in the inspection report. These items are arranged to correspond to the sequence of items cited in the body of the inspection report.
We trust this letter satisfactorily responds to the item of noncompliance and the unresolved issues cited in the inspection report. If you have questions regarding this matter, please contact Mr. Lewis Bregni, (313) 586-5083.
Sincerely,
) cc: P. M. Byron ,
y R. C. Knop .
' C. C. Williams
- d USNRC Document Control Desk Washington, DC 20555 8503050306 850218 PDR F"EB2~"85 U
7 O
ADOCK 05000341 I (
? PDR s49ts, gj'
AI THE DETROIT EDISON COMPANY FERMI 2 NUCLEAR OPERATIONS ORGANIZATION
, RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 DOCKET NO. 50-341 LICENSE NO. CPPR-87
- INSPECTION AT: FERM I 2, ' NEWPORT , MICHIGAN INSPECTION CONDUCTED: DECEMBER.19-20, 1984 JANUARY 3-5, 1985 JANUARY 10-12, 1985 1
~
RESPONSE TO NRC INSPECTION REPORT NO._50-341/84-68 Statement of Noncompliance 84-68-20 10 CFR 50s. Appendix B, Criterion VI, as implemented by DECO Quality Assurance Manual, OAPPR 6, Revision 1 requires that measures be taken to assure that documents such as instructions, procedures, and drawings, including changes thereto, are reviewed for adequacy. . . and are distributed to and used at the location where the prescribed activity is performed.-
b-Contrary to the above, the licensee failed to assure that changes and revisions to drawings were adequately distributed, reviewed, and controlled when used in checkout and initial operation (C&IO) testing of safety-related systems.
The following discrepancies were identified:
- a. There was a lack of consistent procedural requirements.
(C&IO) Startup Instructions Procedure (SIP) 7.7.2.01 Revision 6 requires that superseded revisions of
,. drawings be filed in the Startup Resource Center, while
' procedure' SIP 4. 7. 4. 02 requires that [ unmarked]
superseded revisions be thrown away.
- b. Revisions D, E, F, G, H, I and J of drawing 6I721-2201-2 did not contain the proper stamping signatures and dates, contrary to procedure SIP 7.7.2.01.
- c. Revision D of drawing 6I721-2201-2 was not stamped
" superseded" of " testing void" as required by procedure SIP 7.7.2.01 when portions of the schematic had been changed or when subsequent revisions required new testing., ,
- d. Revisions E and I of drawing GI721-2201-2 were found missing from the files, contrary to procedure SIP 7.7.2.01.
- e. Sections of schematic 6I721-2201-2 were observed to be yellow lined indicating that these sections were tested, although there was. no evidence that tests had been performed.
- f. There was no one consistent method applied among the startup engineers to document the status of performance of C&IO testing required by procedure SIP 7.7.2.01.
i RESPONSE TO NRC. INSPECTION REPORT No. 50-341/84-68 Corrective ' Action Taken and Results Achieved The following corrective actions ace arranged to correspond
- to the sequence of items in the statement of noncompliance:
Startup Instructions '(SI) 7.7.2.01, " Electrical-a.
Checkout Instructions" and SI 4.7.4.02, " Control and Handling of Electrical System Drawings," have been
-revised. Superceded drawings are being stamped or l marked " Superceded" and are filed in the Startup Resource Center.
- b. Each revision of drawing 6I721-2201-2 has been reviewed and updated in accordance with SI 7.7.2.01. In accor-dance with the SI, each revision of the drawing was reviewed by the Startup Test Engineer (STE). Yellow-line updating and necessary retesting, with the appropriate marks, stamps and signatures, were performed to the latest drawing revision.
1
- c. See Item b above.
- d. The intermediate revisions were . missing from the file as a result of the Document Control practice of removing and discarding superceded prints , Which did not have yellow marking.- The effect of a missing intermediate drawing revision is not significant since the -latest- drawing -revision reflects the C&IO testing
, status by yellow-lining.the tested portion of the
~,
drawing. Document Control. personnel have been-directed not-- to . discard any drawing .from the " Yellow-Line
. Master" drawing ' file Jand the SI's have been revised-appropriately. Additionally, the need for timely review of 3drawing revisions -in'.accordance with SI
- 7. 7. 2. 01 has . been. emphasized during training sessions
~g iven to the STE's.
4
- e. . Drawing 6I721-2201-2 h'as been corrected and updated i- through Revision L to reflect C&IO testing status in accordance with SI 7.7.2.01.
- f. SI 7.7.2.01 has been revised to clarify the require-ments for yellow-lining the status of C&IO testing.
- Training has been~ conducted to promulgate the requirements of the revised procedure.
i 1
r
RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 Corrective Action Taken to Avoid Further Noncompliance All electrical STE's were directed to ensure that. drawing revisions are processed When received in accordance with Startup Instruction 7. 7. 2. 01. For the case where multiple revisions are issued over a short period of time or more than one revision exists in the file for review, the Startup Instruction has been revised to clarify that the STE will perform his review for each revision, but the yellow-line updating and retest will be performed to the latest drawing revision only. It was emphasized that this clarification does not preclude the need for timely responce to drawing revisions by STE's.
To remind personnel of the procedural requirements, the Document Control Satellite Clerks have been instructed, via Startup letter SU-85-0040 dated January 29, 1985, not to discard superceded revisions of unmarked " Yellow-Lined Master" drawings.
The actions taken will ensure that " Yellow-Line Masters" are maintained in accordance with SI 7.7.2.01.
The Date When Full Compliance Will Be Achieved Full compliance has been achieved.
m- .
RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68 The NRC= inspector and the licensee's representatives performed a physical walkdown of.the as-built field configuration of .the ' main steam line high flow instrument sensing-lines B21-LOO 3A and B21-LOO 4A,' which' provide isolation signals to the MSIV B21-F022A and B21-F028A. It was determined that the sensing line installation appeared to!be adequate per .the as-built isometric drawing; however, the ' inspector . observed the following discrepancies :
. (1) Main stem line D instrument-tap condensing chambers fed by lines B21-LOO 3D and B21-LOO 4D, were observed to be separated by three (3) inches of free air from other sensing lines that were labeled as B31-LOOlA, Division I, an'd B31-LOO 2B, Division II.
(2) Instrument sensing lines labeled B31-LOOlA, Division I, B31-LOO 2A, Division I,- B31-LOOlB, Division II, and B31-LOO 2B, Division II, were separated from one another by six (6) inches of free air.
(3) Instrument sensing lines labeled B31-LOOlA, Division I,
.B31-LOO 2A,LDivision I, B31-LOOlB, Division II,.
B31-LOO 2B, Division II, and B21-LOl6, Division I, were-all routed through one common penetration labeled Pen.
X-28D. -
r The NRC inspector. queried the licensee as to What separation requirements apply to redundant' instrument ~ sensing.-lines at
~
Fermi 2. The' licensee responded that-they will'be inves-tigating the ' above discrepancies to determine if this= is .a separation violation or a mislabeling of the sensing lines.--
Pending a review of the licensee's investigation results, this item is considered unresolved (341/84-68-01).-
RESPONSE TO UNRESOLVED ITEM 84-68-01 The basis for separation criteria is Specification 3071-536.
. This specification defines the design requirements Which account for the effects of pipe ruptures inside the primary containment. A walkdown and evaluation was conducted to verify compliance with this criteria. No discrepancies were identified. Detroit Edison's report of 10 CFR 10.55 (e)-
Item:ll5, Au gust 20,.1984, EF2-69694 informed the NRC of the results of this evaluation.
6
!- 4 ,
RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 RESPONSE TO UNRESOLVED ITEM 84-68-01 (Continued)
Detroit Edison's investigation of unresolved item 84-68-01 revealed that there was no violation of separation criteria.
Each of these instrument lines belongs to Division I. The appearance of separation criteria violations was created by
-labeling errors. The incorrect labeling was documented on a Deviation / Event Report. To correct this discrepancy, the identification of the instrument lines has been verified and the incorrect labels will be removed. The policy for labeling instrument lines in the drywell is being reviewed.
RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68-02 The inspector reviewed P&ID 6M721-2089, Revision K, and other electrical drawings (discussed below) and observed the following discrepancies :
(1) Fermi 2 FSAR Figures 7.3-10' sheets 1, 2, and 3 do not appear to ' reflect the implementation of FMR S-1109 dated March 15, 1979.
(2) It1 appears thatsthe correct reactor low water level interlocks are not used in the MSIV isolation logic (Ref. drawings 6I721-2095-14 & 15, Revision C) .
(3) Color code discrepancies exist between the drawings listed in the brackets. (6I721-21-16
[ sic-6I721-2155-16] and 17, Revision C, and 6I721-2282-55, 60, 65, and 70, Revision F. ) -(Ref.
DCP-B2100-IO5 and IO6, IDCN-442, IRMR-1087 and DCN-5990.) It appears that some of the referenced design chaage documents were not properly and com-pletely irplemented.
RESPONSE TO UNRESOLVED ITEM 84-68-02 (1) Detroit Edison made an effort to keep the FSAR updated during the construction phase. FSAR Figure 7.3-10, sheets 1, 2, and 3, " Nuclear Boiler System FCD" are covered under Interfacing Procedure 11.000.121, "FSAR and ER kmendments." This procedure provides for annual updates of the FSAR beginning two years after the operating license is issued. Typically, however, there is a significant delay in the incorporation of changes into FSAR drawings issued and maintained by General Electric if the change is not initiated by GE. This is the case with FMR S-1109. To alleviate this problem, Detroit Edison will obtain the mylars for these drawings and will maintain these drawings -internally.
The revised drawings will be . annotated to show that the GE issued drawings are being maintained by Detroit Edison. FSAR Figure 7.3-10 is being revised by FCN-84-579 which is scheduled to be incorporated by July, 1986.
(2) The reactor low-water level interlocks shown on drawings 6I721-2095-14 & 15 are correct. Although the drawing appears to combine Division I and II signals, a closer examination reveals that the separation criteria have been met. In a meeting subsequent to the inspection, the NRC inspector concurred.
RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 RESPONSE TO UNRESOLVED ITEM 84-68-02 (Continued)
(3) The_ inspectors observations concerning color code discrepancies are correct. These particular color code discrepancies exist because an acceptable alternate cable type was used due to material availability when the cables were installed. In this case, Cable Code No. 119 was substituted for No. 111. DCN-5990, which documented the change, corrected the cable color'on the pull card and wiring diagrams 6I721-2282-55, 60 and 70, but failed to change the color on schematics-i 6I721-2155-16 and 17. This error was corrected on Revision D of the schematics except for 2 cables which were again overlooked.
Cable color does not affect the function of the circuit. In accordance with the electrical'and I&C ,
as-built program, a Deviation / Event Report (DER) was used.to document this . discrepancy. This DER will be posted against the drawing to prevent confusion until the drawing is updated.
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r RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68-03 As-built wiring drawing 6SD7212501-40, Revision E. , was reviewed for general arrangement of devices, identification of devices and external cables.
Device locations were found to be in accordance with the above as-built drawing. External cables 200022 A and B were reviewed in the rear compartment of position E8 and found identified and located per above as-built drawing.
During this review it was observed that the following devices and termination blocks, identified on the above as-built drawing, had either temporary or missing identification tags in the field: PK, PL, PM, PG, LA, LB, LC, LD, AA, AN, RA and RZ. The licensee reported there was no current program in place to identify such devices inside cabinets. Pending further review, this is an unresolved item (341/84-68-03A).
During inspection of the 4KV switchgear core spray pump cubicle, the inspector observed that numerous terminal blocks had not been labeled in accordance with the connec-tion diagrams. Labels were observed to be missing from most of the terminal blocks in the 4KV Bus No. 65E position E10 cubicle.
The inspector observed missing identification tags inside the cubicle for the following components LA, LB, LD, LC, AF, AE and AZ. The licensee does not have a current program in place to identify missing identification tags inside a cubicle. This matter will be reviewed in a subsequent inspection and is considered unresolved (84-68-03B).
RESPONSE TO UNRESOLVED ITEM 84-68-03 For electrical equipment, Detroit Edison's policy is to provide adequate and accurate identification labels on components which are operated by operations personnel.
Identification numbers are placed on internal components as an aid to wire and test the unit and they are applied as
- determined by the manufacturer and testing personnel.
Therefore, not all positions, components, or panels will be tagged to the same degree. Other than fusing type and size which is being covered under an ongoing program, Detroit Edison engineering does not require internal component identification tagging.
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RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68
-RESPONSE TO UNRESOLVED ITEM 84-68-03 (Continued)
If Detroit Edison determines that an internal component must be operated by an operator, permanent tags will be installed to facilitate operation and prevent operator error. In Unresolved Item 84-68-03, the components identified as not having identification tags are either automatic control devices or passive circuit components which do not require operator action.
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RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68-08 Electrical road maps [ Lead Design Document Index - LDDI] for 480V and 4160V switchgear were reviewed for adequacy and clarity of information. The following discrepancies were observed.
(1) Attachment 3, page 3 of 47, refers to wiring diagrams as having modifications which deviate from standard internal connections. There was no clarification as to what these deviations entail.
(2) Attahcment 3, page 13 'of 47, refers to wiring diagrams as not always showing exact locations of devices. It could not be determined how many drawings and how much variation of location was being indicated.
(3) Attachment 3, page 14 of 47, indicates that schematics show relay and limit switch contact developments, "as applicable." It could not be determined what devices and developments were not applicable.
(4) Attachment 3, page 13 of 47, references wiring diagrams not to be lead documents for identifying spare cable conductors. There was no reference to the correct lead documents for identifying spares.
(5) Attachment 3, page 13 of 47, regarding the use of wiring diagrams states, "May not reflect as-built wiring configuration of actual equipment, but is functionally correct in accordance with lead document, schematic." This disposition was not considered acceptable because it is contrary to as-built requirements as it could inadvertently cause errors during maintenance.
The items above are considered unresolved (341/04-68-08).
RESPONSE TO UNRESOLVED ITEM 84-68-08 The electrical and I&C road maps have been revised twice since the subject NRC inspection. The revisions have incor-porated a number of changes based on comments from the NRC, recommendations from Nuclear Quality Assurance based upon their verification of the utility of the Lead Design Document Index (road maps) and comments from the users. The current revision of the Lead Design Document Index (LDDI) is substantially more functional.
RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 RESPONSE TO UNRESOLVED ITEM 84-68-08 (Continued)
The specific discrepancies documented by the NRC in the inspection report are addressed below:
(1) The modifications referred to are those due to the craftsman option, i.e., the connections are electri-cally equivalent and consistent with the schematic, but may not accurately reflect the point-to-point wiring.
Such deviations were identified during the walkdowns of the electrical and I&C equipment and evaluated. Their resolution will occur When the drawings are updated under the electrical and I&C as-built program.
(2) Detailed dimensions for locations of devices found on the wiring diagrams can be obtained from the vendor dr& wings. For futuro design changes which affect the location of such devices, location details will be included on the drawit:gs in the Engineering Design Package. The LDDI has been revised to delete the statement about device location information on wiring diagrams.
(3) The "as applicable" statement refers to the devices illustrated on the individual schematic.
(4) Revision 2 of the LDDI refers to the cable pull cards to identify spare conductors. If the cable pull card indicates that the cable has 16 or more conductors, then the wiring diagram is the lead document for spare conductors.
(5) The statement by the NRC is acknowledged. Wiring interconnection and termination deviations were identified during the walkdowns of the electrical and I&C equipment and evaluated. Their resolution will occur when the drawings are updated under the l electrical and I&C as-built program.
l RESPONSE'TO NRC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68-09 Connection points on drawings 6SA721-2501-52
[ sic-6SD721-2501-52] show that on terminal block 1B, two conductors terminate on points 5 and 6. According to the drawing, a number eight conductor is terminated on point 6 and a number twelve is terminated on point 5. The inspector observed that the above connections were reversed in the field. The drawing designated these conductors as being connected to the main current transformer on the incoming power leads. The connection of the No. 2 conductor should be to the ground of the current transformer, but according to the as-built connection, the No. 12 conductor was connected on the positive side of the current transformer.
Both Division II core spray pumps (B&D) have this discrepancy. This matter is considered unresolved pending further review to determine Whether the drawing is incorrect or whether the field installation is incorrect.
(341/84-68-09).
RESPONSE TO UNRESOLVED ITEM 84-68-09 This discrepancy between the drawing and the installed wiring has been documented and evaluated under Detroit Edison's electrical and I&C as-built program. The evaluation indicated that the installed wiring is functionally equivalent to the wir s shown on drawing 6SD721-2501-52; although, the routing of wire between termination points in the field does not match exactly the wiring shown on the drawing. Since functionally equivalent wiring has no effect on the operation of the equipment, the discrepancy was not detected When the system was tested.
This discrepancy was documented on Deviation / Event Report (DER) No.85-109 and the drawing will be updated prior to exceeding 5% power. To prevent confusion to operations and maintenance personnel using this drawing, the DER which documents this discrepancy will be posted against the drawing until the drawing is updated.
Detroit Edison has recently completed extensive walkdowns of electrical and I&C equipment in order to identify and resolve differences between the as-built plant and design drawings. This program has provided assurance that deviations are documented and corrected. Refer to Detroit Edison's final report on 10CFR50.55(e) Item 143, Reference 2, for additional information.
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t RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68-10 The inspector observed that inside the core spray pump D cubicle, the positive and negative conductor terminationo were reversed when connected to current transducers identi-fied as XCCC-5. Drawing 6SD721-2501-52 shows the black
[ sic-white] conductor connected to the negative terminal and the white [ sic-black] conductor connected to the positive terminal of the current transducer. The field installation was observed to be the reverse of the above connection.
Additionally, the schematic diagram also indicates that the positive and negative connections do not agree with the field installation. The licensee stated that the termi-nation of the other end is to an AC ammeter and was of no consequence. Howe ver, schematic diagram 6SD721-2211-4 shows the connection to a DC ammeter. It appears that testing or start up personnel switched the wiring without initiating the proper design change paper to . revise the schematic and wiring diagrams. This matter is considered unresolved.
(341/84-68-10).
RESPONSE TO UNRESOLVED ITEM 84-68-10 As discussed above, a DC ammeter was installed using black cable for the negative lead and white cable for the positive lead. Detroit Edison's standard practice and the design drawing call for black leads to be positive and white leads to be negative. Cable color has no effect on the function of the circuit. This discrepancy has been documented and the cables will be corrected to maintain the site standard.
As previously discussed in this report, Detroit Edison has recently completed an extensive program to identify, correct and prevent the recurrence of similar discrepancies between
. the drawings and the as-built plant. Details of this program-are being supplied to the NRC in Detroit Edison's final report of 10 CFR 50.55(e) Item 143.
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RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68-11 During observation of the terminations inside panel Hll-623, the' inspector noted an extra connection on points 9 and 10 on a relay identified in the panel as AX-K120. Drawing No.
6I721-2045-60, Revision H, which shows the control develop-ment of this relay, indicated that this was incorrect.
These points were later verified to be normally closed contacts that were not identified during testing by startup personnel. These normally closed contacts are in series with control room indication and could if undetected provide false indication to control roem operators. This issue is considered unresolved pending further review of this matter (341/84-68-11).
RESPONSE TO UNRESOLVED ITEM 84-68-11 The Core Spray Pumps are operated from the control room by back lighted switches which flash if the pump switch is in the OFF position. In the auto mode, the Core Spray Pumps will start automatically When reactor water level is low or drywell pressure is high. During normal plant operation, the flasher warns the operator that the Core Spray Pump is not prepared to start automatically.
As installed, the flasher would operate correctly during normal operation and would warn the operator that the pump was not prepared to respond to an emergency. However, after an automatic start signal is received and the Core Spray Pump has responded, if the Core Spray Pump is manually stopped, the flasher will not operate. This discrepancy existed on all 4 Core Spray Pumps.
Detroit Edison's investigation revealed that this discrepancy resulted from insufficient control of consecutive design changes to the same circuit. FMR-1030 Revision B (implemented GE FDDR-KHI-567 Revision 0) was issued on May 27, 1979. This FMR added the contacts which are described by the Inspector. FMR-1396 (implemented GE FDDR-KHI-620) was issued on January 1, 1980. This EMR removed these contacts. Howe ver , FMR-1030 was revised and re-issued as Revision C on April 29, 1980. Therefore, the contacts, Which were required by FDDR-KHI-567 and later removed by FDDR-KHI-620, were re-installed. FDDR-KHI-620, which superceded FDDR-567, did not reference the document it supercrded.
Detro_t Edison has initiated action to implement FDDR-KHI-620 for all 4 Core Spray Pumps.
RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 L
- UNRESQLVED ITEM 84-68-12 The following are examples where the equipment connections were installed such that the electrical components will function as designed but are not in accordance with the connection and/or schematic dia grams. The licensee has indicated that they will identify and document the deficiencies and revise the connection diagrams to reflect as-built installation. These matters will be followed-up in subsequent inspections.
(a) Limit switch compartment of core spray minimum flow
. bypass valve "B" was checked against drawing numbers 6I721-2211-9, Revision G. According to the drawing, the connection from terminal point 36 is green block
[ sic] conductor, the field installation was observed to be red. The schematic diagram also shows this connection to be incorrect. The inspector observed that this field connection is properly terminated at motor control center cubicle E2150F031B. The above discrepancies were noted as deficiencies and documented by the licensee.
(b) During review of the connections inside a motor control center cubicle it was observed that the field termina-tions were CR to R to F relays instead of CR to F to R relays as shown on drawing SSA721-2521-9
[ sic-5SD721-2521-9], Revision B. Additionally, conductors identified as N o. 10 and No. 12 to contactors F and R respectively, were not in accordance with this same drawing; also in this cubicle, the drawing indicated a ground. at the 120V/24V transformer low side connection, while the connection was to the 480V/120V transformer low side connection.
1&ue issues (5) (a), and (5) (b) above are considered unresolved (341/84-68-12).
RESPONSE TO UNRESOLVED ITEM 84-68-12 -
Item (a) ' addresses a wiring drawing and schematic that show a conductor as Green-Black when the installed conductor is Red. The Green-Black conductor' was replaced with the spare Red conductor from the same cable by DCR E-3993. The DCR revised the pull card and cable routing report but did not change the. schematic. The schematic has:been revised to show the correct color of the conductor.
' RESPONSE TO NRC-INSPECTION REPORT NO. 50-341/84-68
- -I t em (b) addresses two items where the installed wiring was functionally equivalent to the design drawing; although, the point-to-point -wiring did not match the drawing exactly.
This discrepancy will be resolved in accordance with Detroit
- Edison's as-built program as described in this response under Unresolved Item 84-68-09. In this case, the drawing will- be updated.
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RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68-14 The inspector reviewed the as-built inspection program performed by the licensee utilizing the licensee's LDDI.
The auxiliary relay room high pressure coolant injection relay cabinet Hll-P620 was visually inspected by the NRC inspector-to ascertain the effectiveness of the licensee's as-built verification program. The visual inspection consisted of a comparison between the number of wires landed at the panel terminal points and the number of wires shown on the applicable design . drawings. This effort included relay terminations, plugs, etc...
The following discrepancies were identified:
(1) Sche'matic Diagram 6I721-2225-1, Revision K dated September 28, 1984, indicated the following:
(a) Contact 3-4 of relay K3 is being utilized to interlock valve E4150-F021. However, this contact was found to be a spare in panel Hil-P620.
(b) Contact 3-4 of relay K4 is being utilized to interlock valve E4150-F021. However, this contact was found to be a spare in panel Hil-P620.
(c) Contacts 1-7, 3-7, and 2-8 of relay K82 were being utilized to interlock relay K35. However, relay K82 was found to be a spare in panel Hil-P620.
(2) Schematic Diagram 6I721-2225-1 [ sic-6I721-2221-12],
Revision C [ sic-F] dated October 4, 1984 [ sic],
indicated that contacts 1-2 of relay K92 are being utilized. Inspection of the relay in panel Hil-P620 indicated that contact T1-M1 was being utilized.
(3) Schematic Diagram 6I721-2225-5, Revision I dated October 4, 1984, indicated that Fuse F22 was wired to TBDD point 13 and fuse F21 was wired to TBDD point 14.
However,. field and applicable connection diagram 6I721-2045-54, Revision L, indicated that F22 was wired to TBDD-14 and F21 was wired to TBDD-13. Items 8.a.(1)(2) and (3) are considered unresolved pending licensee action (341/84-68-14).
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RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 I RESPONSE TO UNRESOLVED ITEM 84-68-14 (1) Field Modification Request (FMR) 4378 and Design Change Package (DCP) 3500IO2 modified the wiring to the configuration that is currently installed and changed the design drawings. However, the EMR and DCP failed to include drawing 6I721-2225-1, "HPCI System Notes and Relay Tabulations," among the drawings to be revised to reflect this modification. Revision M of the relay tabulation drawing has been issued and properly incorporates the EMR and DCP.
(2) FMR 4378 replaced the GE HFA type relay designated K92 with an Agastat type GP relay. This changed the relay contact numbering convention, but not the function of the relay designated as K92. Contacts 1-2 on the old relay became contacts T1-M1 on the new relay. This change was made on drawings 6I721-2225-1 and 6I721-2221-12 where the contacts were still shown as 1-2. The K92 relay development shown on 6I721-2221-12 '
has been deleted on Revision G because the information is redundant to the information shown 6I721-2225-1 and 6I721-2225-6.
(3) This discrepancy, a drafting error, reversed the leads used to monitor the fuse condition for fuses F21 and F22. These fuses are in the same circuit. As wired, the fuse condition, which is not a safety-related function, was still being monitored. The schematic diagram, 6I721-2225-5, has been revised to Revision J which corrects the drawing to show fuse F21 wired to TB-DD-13 and fuse F22 wired to TB-DD-14.
This unresolved item involves 3 drawing errors. Two of the errors resulted from the failure to identify and correct all of the applicable information shown on the drawings when a design change was made. The third error was a drafting error. To reduce these types of errors, an improved design verification program under Fermi 2 Engineering Procedure 4. 3 has been instituted. Additionally, Detroit Edison personnel have conducted extensive walkdowns of Fermi 2 electrical and I&C equipment and performed drawing-to-drawing checks to identify and correct existing errors. A detailed description of this Fermi 2 as-built program is contained in the final report of 10CFR50.55(e), Item 143, Reference 2.
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RESPONSE TO NRC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68-17 C&IO test procedure TF.000.017.01, Revision 4, dated January 25, 1983, relating to the tests and inspections performed to shielded cable 234427-26 [ sic-234437-2C] indicated by the documented signatures of the test engineer that the cable was checked for proper termination (ref. 3.3), that the cable shield is grounded Where applicable (ref. 7.1), that the cable was checked for proper phasing and continuity
" working drawings" are yellow-lined (ref. 7.3). Contrary to the above, the shield of the above cable was found ungrounded and improperly terminated during licensee's walk-down. This item is considered unresolved pending licensee review and action (341/84-68-17).
1 RESPONSE TO UNRESOLVED ITEM 84-68-17 This item is a continuation of the previous item, open Item 84-68-16, Which discusses a jumper between TBAA-80 and TBAA-84. This jumper is shown on the wiring diagram, 6I721-2045-54, Revision K, although the jumper is not installed in the field. The schematic shows the shield as grounded. TBAA-84 is a ground connection. The cable shield i is terminated at TBAA-80. Without the jumper installed, the shield for cable 234427-2C was correctly terminated, as documented in C&IO Test TF.000.017.01, but the shield was not grounded as was documented in DER-85-021 during the walkdown.
The jumper was apparently removed during testing to prevent connecting terminal TBAA-80 to ground because TBAA-80 was also being used as part of an energized circuit. This occurred because two design changes were issued against drawing 6I721-2045-54 which required using terminal TBAA-80.
DCP E4100001 used TBAA-80 to terminate the shield of cable 234427-2C and installed a jumper from TBAA-80 to ground
- (TBAA-84). FMR 4198 used TBAA-80 to connect the relays in Hll-P612 and Hil-P614 to the coils which activate the "HPCI AUTO ISOLATION SIGNAL B" in Hil-P620. This error was not identified When the design changes were incorporated. As installed, both circuits worked properly although the cable shield was not grounded. Had the jumper been installed, it would have resulted in a single ground on a DC system but the HPCI Auto Isolation Signal B would ntill have been functional.
w Engineering Design Package (EDP) 2135 has been issued to correct this discrepancy.
RESPONSE TO NPC INSPECTION REPORT NO. 50-341/84-68 UNRESOLVED ITEM 84-68-19 During the as-built review, the inspector examined FMR 7096, Revision 0, A and B. This FMR addressed the requirements of GE FDDR KH1-1041, Revision O to provide bypass of limiting resistors EDl-R1 during manual mode of RCIC turbine and GE FDDR KH1-1086, Revision O, addressed the same in the HPCI turbine control. The inspector ' noticed that on sheet 4 of FMR 7096, Revision 0 and A, the circuit had been modified by the licensee's engineer and sent to the field for incorpora-tion without written documented approval from GE for this change. Revision B of the FMR again modified the G2 circuitry in a different way than Revision A, but no written approval was available. It also contained GE FDDR KH1-1086, Revision O, without superseding it; therefore, having two open FDDRS addressing the same item.
Furthermore, review of incorporation of above FMR into the applicable design schematic diagram 61721-2042-15, Revision F, indicated that the circuit shown on this drawing does not conform to FMR specifications and was modified during the incorporation into the drawing. Note that the drawing revision block reads: "Per FMR-7096, Revision B. . . " even though drawing did not reflect FMR-7096, Revision B as specified.
The above appears to be another example where an engineer or a draftsman modified a design drawing arbitrarily without following the specific requirements of the design change document.
This matter is considered unresolved (341/84-68-19).
RESPONSE TO UNRESOLVED ITEM 84-68-19 Detroit Edison was authorized by the GE Project Manager to revise GE design prior to GE's approval, where necessary at design interfaces, on an "at risk" basis. The risk is not related to plant safety, but to additional cost for rework if GE disagreed with the design change. Changes to GE design by Detroit Edison were listed on the cover of the related FMRs and transmitted to GE for their review and concurrence or comment. GE, in turn, would revise their FDDR or FDI or send a letter stating their concurrence or disagreement.
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RESPONSE TO NRC INSPECTION REPORT NO 50-341/84-68 Changes to FDDR KH1-1041, Revision O, were transmitted to GE on FMR 7096, Revision 0, by letter EF2-69,460, dated June 21, 1984. FMR 7096, Revision 0, was approved by the responsible discipline engineer on June 19, 1984. GE subsequently issued FDDR KH1-1086, Revision 0, to address the design change. The latter FDDR was more conceptual in nature and lacked sufficient detail, by itself, to perform the necessary construction. FMR 7096, Revision B, expanded on the design of FDDR KH1-1086, Revision 0, to allow construction to proceed. Since FMR 7096, Revision B, did not change the GE conceptual design, Revision B was not tv ismitted to GE for review and concurrence.
The NRC inspector was correct relative to two (2) FDDRs being ope.n and applicable to the same design item. GE superseded FDDR KH1-1041 Revision 0, by issuing FDDR KH1-1041, Revision 1, on December 28, 1984. The latter revision cancelled FDDR KH1-1041 and referred to FDDR KH1-1086 for the applicable design. Relative to construction activities, EMR 7096, Revision B, issued FDDR KH1-1086, Revision O. Per Detroit Edison procedures governing the FMR process, preceding revisions of a FMR are superseded by the latest FMR revision issued. FDDR KH1-1041, Revision 0, was for construction purposes superseded by FDDR KH1-1086, Revision 0, through FMR 7096, Revision B. Revision B of the FMR was issued on August 24, 1984.
Detroit Edison has investigated the Inspector's concern that a design document was changed arbitrarily. During incorporation of the FMR into drawing 6I721-2042-15, Revision F, the draf tsman recognized that sheet 9 of the FMR contained an error. This observation was based on having reviewed previous sheets of the FMR, specifically sheets 2, 3 and 7. Realizing the error, the draftsman incorporated the correct design into the drawing. It is recognized that such practice is not appropriate and should not take place.
Procedural changes have been implemented which address this concern. Additional controls (including the use of a checklist) are being implemented during verification of the drawing revision process. Additional related information is provided in the response to 10CFR50. 55(e) Item No. 143.
