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
[Table view] |
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Engeeg and Construction MI Edison Ess!=b October 15, 1982 EF2 - 60,134 Mr. L. L. Kintner U. S. Nuclear Regulatory Commission -
Office of Nuclear Reactor Regulation Division of Licensing
Washington, D. C. 20555 ,
Dear Mr. Kintner:
References:
(1) Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341 (2) Letter NRC to Detroit Edison,
" Control ^of Heavy Loads at Fermi 2" (NUREG-0612)
(3) Letter Detroit Edison to NRC, " Control _
of Heavy Loads Over or in Proximity to Irradiated Fuel", EF2-57,432, 6/3/82
Subject:
Control of Heavy Loads y The Reference 2 NRC letter enclosed a' draft report providing an evaluation of Detroit Edison's response on heavy loads (Reference 3). On, September ~2nd a con-ference call was held between Detroit Edison, your-self, and your consultants from EG&G Idaho on the report. This letter responds to the action items given to Detroit Edison as a consequence of that call.
Resolution of these items is provided by making page changes to our Reference 3 submittal.
The enclosed table gives a cross-reference between the appropriate item in your Reference 2 report, the action item derived based on the conference call, and the page change intended to resolve the comment. Some additional page changes to our report are also enclosed to correct typos and reflect design evolu-tion. The page changes are attached as Enclosure 1.
Should you have any further questions, please contact Mr. L. E. Schuerman, (313) 649-7562.
Sincerely,
/
Enclosures
[
cc: F. Clemenson B. Little T. H..,Stickley 821@270228 821015 ///h Eacli PDR ADOCK 05000341 PDR he'p[
A ,
TABLE 1 Cross-Reference between NRC Reference 2 Report and DECO Page Change to Reference 3 Page of. Comment Based Page Change Reference 2 on 9/2/82 to Reference 3 Applicable- Conference Call Applicable 4 NRC can't verify list of 2.1.1-2, hoists. Commitment is 2.1 3-18 desired that future hoists will meet 0612 7, 8 Anticipated load handling 2.1 3.4, procedures will be written 2.1 3-7, prior to OL. Unanticipated 2.1 3-8, load handling procedures Table 2.1 3.c will be written prior to the handling. The pro-cedures will meet 0612.
8 The alternatives to floor 2.1 3-4, lines should be identified. 2.1 3-4a, It was finally agreed that 2.1 3-7, DECO will 1) paint exclu- 2.1 3-7a sion areas 2) by procedure walk down the load paths See Note 1 to insure they're free of obstruction and 3) for significant loads, will place temporary markers for the load path.
10 NRC desired that training 2.1 3-19 and certification require-ments be more specifically stated for the crane and that appropriate industry standards be met for other devices. Operators should also be trained prior to actual operation.
11 NRC desires to know when 2.1 3-15, DECO plans to respond on 2 3 2-70, Special Lifting Devices 2 3 2-70a, and what will be done if 2 3.2-73 there are problems.
J
"\
Page of Comment Based Page Change Reference 2 on 9/2/82 to Reference 3 Applicable Conference Call Applicable 12 NRC desires statements to 2.1 3-16 be revised to show how special slings and non-controlled construction slings will be prevented from being mixed up. Also, dynamic loads is desired to be addressed.
17 NRC desires that DECO See addendum I address the interim mea- to the table sures (NUREG-0612, Article 5 3) in case all final guidelines of NUREG-0612 can't be imple-mented by fuel load.
Notes:
- 1. Painted lines are orovided instead of temporary markers as was originally discussed in the phone call.
J
Addendum 1 to Table 1 Interim Measure From Section 5 3 of NUREG-0612 (1) Restriction of Heavy Loads Over'the Fuel Pool As described in Section 2.1 3.f of Reference 3, the Reactor Building Main Crane is single-failure proof.
Section 2.2.4.a describes the load limit application and plant technical specification requirements that prohibit heavy loads, handled by the non-single failure auxiliary hoist, from being handled over the spent fuel pool. All of the protective devices, pro-cedures and technical specifications described in Section 2.2.4.a needed to satisfy this interim action will be implemented prior to fuel load.
(2) Definition of Safe Load Paths This action has been completed as reported under Sections 2.1 3.a and b of Reference 3, and the revised pages to these sections included in the attachments to this letter.
(3) Load Handling Procedures Edison has committed to complete their written proce-dures prior to criticality defined under the attached revisions to Sections 2.1 3.a, b and c of Reference 3 (4) Training and Qualification of Operators The operator training end qualification program as described in the attached revised pages to Section 2.1 3.g, commits to having this program established prior to fuel load with operator training initiated prior to criticality. The intent is to have each operator's training and qualification completed prior to his involvement with any post criticality heavy load handling event.
(5) Crane Inspection, Testing and Maintenance Edison has committed to an inspection, testing and maintenance program in accordance with the NUREG-0612 guidelines. Written procedures covering this program will be completed prior to fuel load as explained under Section 2.1 3.e of Reference 3 J
(6) Review of Procedures, Equipment and Personnel Qualification for Critical Load Handling over the Reactor
- 1. . Written Procedures Written procedures covering the handling of criti-cal loads over the reactor will include explicit instructions on rigging and movement of loads as described in Section 2.1 3.b and c of Reference 3 These procedures will be completed prior to criticality to meet this interim action.
2.& 3. Visual inspection of cranes, slings and lifting devices, and appropriate repair and replacement of defective components A complete visual inspection of the reactor building crane, and those slings and lifting devi-ces used for reactor reassembly will be performed prior to reactor assembly after the initial fuel load .
Any detected flaws or defects will be corrected before any heavy load handling is attempted where these identified deficiencies could potentially cause a load drop.
- 4. Operator Qualification A formal training and qualification program for crane and hoist operators will be established prior to fuel load. All post criticality heavy load hoisting functions in close proximity to cri-tical system or spent fuel will be handled only by operators trained and qualified under this program. See Section 2.1 3.g of Reference 3 (revised pages attached to this letter).
l l
h i
Table 2.1.1 OVERHEAD HOISTS CAPABLE OF HANDLING LOADS OVER SPENT FUEL OR SHUTDOWN SAFETY SYSTEM COMPONENTS Holst Identification Holst Hoist Number Type Capacity Location Reactor Bldg Crain Main Hoist T3100E002 (1) 125 Ton RB-5th F1.
Reactor Bldg Crane Aux. Holst T3100E002 (1) 5 Ton RB-Sth F1.
N&S Torus Hatch Hoists T3100E032&3 (2) 5 Tn/Ea RB-1st Fl.
HPCI Hoist T3100E030 (2) 12 Ton AB-1st F1.
RCIC Holst T3100E031 (2) 10 Ton RB-1st F1.
RHR Pumps-Div.I Basement Holst T3100E024 (2) 16 Ton RB-Basement RHR Pumps-Div.II Basement Holst T3100F025 (2) 16 Ton RB-Basement RHR Pumps-Div.I 1st Floor Holst T3100E026 (2) 16 Ton RB-1st F1.
RHR Pumps-Div.II 1st Floor Hoist T3100E027 (2) 16 Ton RB-1st F1.
N&S Reciro. Pump Hoists T3100E015A&16A (2) 25 Tn/Ea RB-1st F1.
MG Sets, N, C. & S Hoists T3100E035, 6&7 (2) 12 Tn/Ea RB-4th F1.
MG Set Fluid Drive N&S Hoist T3100E038&9 (2) 20 Tn/Ea RB-4th F1.
CRD Repair Holst T3100E019 (2) 3 Ton RB-3rd F1.
Core Spray Div. I Hoist T3100E028 (2) 16 Ton RB-1st Fl.
Core Spray Div. II Holst T3100E029 (2) 16 Ton RB-1st F1.
Diesel Gen. Div. I N&S Holst" (2) 2 Tn/Ea RHR-Gr. F1.
Diesel Gen. Div. II N&S Holst* (2) 2 Tn/Ea RHR-Gr. F1.
Diesel Gen. Motor Control i Cent. Div. I N&S Hoists * / (2) 4 Tn/Ea RHR-Up. Fl.
Diesel Gen. Motor Control Cent. Div. I" (2) 4 Tn/Ea RHR-Up. Fl.
Ventilation Equip. Rm. Holst" (2) 8 Ton AB-5th F1.
Rofueling Platform Monorail Hoist F1500E006 (2) } Ton RB-Sth F1.
Refueling Platform Aux. Holst F1500E005 (2) } Ton RB-Sth F1.
Refueling Platform Main Holst F1500E004 (2) 1 Ton RB-Sth F1.
Refueling Platofrm Hand Winch F1100E021 (2) 1 Ton RB-Sth F1.
CRD Handling Cart Service Crane F1100E022 (2) 1 Ton RB-3rd F1.
New Fuel Transfer Holst F1100E023 (2) 1 Ton RB-Sth F1.
Fuel Channeling Crane F1100E024 (3) 250 Lb. RB-Sth F1.
Fuel Pool Jib Crane F1100E021 1 Ton RB-5th F1. (1)
NE Equipment Hatch Holst* (2) 12 Ton RB-1st F1.
(1) Overhead Traveling Crane RB-Reactor Building (2) Monorail Hoist AB-Auxiliary Buildin (3) Portable Hydraulic Floor Crane RHR-RHR Building (1)
- These hoists have not yet been specified for purchase, although the trolley support for these hoist locations has been installed. The specified design of these hoists will include conformance with ANSI (1)
B30.16 criteria for " Overhead Hoists".
(1) Revised 10/10/82 2.1.1-2
Table 2.1.2 OVERHEAD HOISTS EXEMPT FROM FURTHER ANALYSIS BECAUSE THEY CANNOT HANDLE HEAVY LOADS OVER SPENT FUEL OR SHUTDOWN SAFETY SYSTEM COMPONENTS A. Hoists incapable of handling heavy-loads over 2000 lbs.
Rated Holst Holst Capacity Location Fuel Channeling Crane 250 lbs. Reactor Bldg.-Sth F1. l (1)
Refueling Platform Monorail Holst 1000_1bs. Reactor Bldg.-5th F1.
Refueling Platform Aux. Hoist 1000 lbs. Reactor Bldg.-Sth Fl.
Refueling Platform Main Holst 2000 lbs. Reactor Bldg.-5th Fl.
Refueling Platform Hand Winch 2000 lbs. Reactor Bldg.-5th Fl.
Fuel Pool Jib Crane 2000 lbs. Reactor Bldg.-Sth Fl.
CRD Handling Cart Service Crane 2000 lbs. Reactor Bldg.-3rd Fl.
New Fuel Transfer Holst 2000 lbs. Reactor Bldg.-Sth F1.
B. Hoists incapable of handling loads over safety shutdown system components.
Floor Drain Sump Cover Holst (2) 5 Ton /ea. Reactor Bldg-Sub Base. (1)
Equipment Drain Sump Cover 5 Ton /ea. Reactor Bldg-Sub Base.
Hoists (2)
All cranes and hoists located in the following buildings that do not contain safety equipment needed for safe unit shutdown.
- Turbine Building
- Radwaste Building
- Office Service Building
- Auxiliary Boiler Building
- General Service Water Building
- Circulating Water Pump House
- Warehouse No. 19 (1) Revised 10/10/82 2.1.2-2
Figure 1 shows the laydown location for major components during a reactor refueling. Figure 2 is a composite drawing showing the floor area exposed to all heavy loads handled during refueling, and movement of the Spent Fuel Cask prior to and after refueling.
Figures 3 through 11 show the load travel path for each heavy load lift performed during refueling. Figure 3 shows the load path for the movement of the reactor pressure vessel service platform and support tracks from their permanent storage location just north of the equipment hatch during normal operation to temporary place-ment just east of the stud tensioner. Figure 4 shows the load paths for movements of the six Reactor Shield Plugs.
After all of the Reactor Shield Plugs have been moved, the Reacter Pressure Vessel Service Platform is moved back to its new storage location and is placed on top of the Shield Plugs that have also been moved into this location. Figure 5 depicts the load travel paths of the Storage Pool Slot-Plugs to and from the southeast quadrant of the refueling floor. Figure 6 shows the load travel paths of the Fuel Pool Slot Plugs to and from the northwest corner of the refueling floor, the equipment pool and fuel pool gate tra-vel paths within the pools, and the refueling bridge travel path from just west of the drywell. After all of the remo-(1) vable plugs have been placed into their laydown location, the Head Strongback is then attached to the Reactor Building Crane Main Hoist and the Drywell Head. Figure 7 shows the (1) Revised 10/10/82 2.1 3-2
The systematic placemsnt of heavy loads handled for refueling was determined by the refueling procedure sequence of events and the travel limitations of the Reactor Building Crane, with consideration for safety system components located below the fueling floor.
Because of the high strength integrity of the fueling floor-(fifth floor) due to its heavily reinforced, 24-inch thick construction, very little added strength is achieved along the building column lines. However, travel paths along these column lines have been established where it is practicable, to keep the travel and placement as simple as possible, so as not to con-fuse operators and supervisors. The established travel paths (shown in Figures 3-12) will be included in spe-cific maintenance procedures developed prior to criti-cality with the exception of the procedure for the spent fuel cask which will be developed prior to handling after criticality. An initial step in the procedures will require the person responsible for per- (1) forming the lift to verify the safe load path is free of obstructions that would interfere with the movement of the load. Because of the high strength integrity of the fueling floor at all locations and the separation of redundant safety systems located below the fueling floor, deviations from the travel paths shown in Figure 3 through 12 do not notably increase the consequences (1) Revised 10/10/82 2.1 3-4
of any potential accidents as long as these deviations do not traverse over the Reactor, Fuel Storage Pool and Equipment Hatch areas. Therefore, the placement of painted travel path lines for all heavy loads offers 4
very little advantage and could cause confusion.
However, painted barrier lines and signs will be established around the Reactor, Fuel Pool, and Equipment Hatch areas. Additionally, painted travel paths will (1) be provided for the five P::.jor loads handled over the 5th floor deck. These include the Reactor Shield Plugs, Reactor Vessel Head, Drywell Head, Spent Fuel i Cask and the Equipment Storage Pool Slot Plugs.
i 1
(1) Revised 10/10/82 2.1 3-4a i
_ _ . - , _ _ . _ . _ _ _ . _ _ _ _ . _ - . . _ _ _ . _, . . ~ .- _ _ . _ . , _ _ . _ _ _ ,
2.1 3.b A discussion of measures taken to ensure that load-handling operations remain within safe load paths, including procedures, if any, for deviation from these paths.
RESPONSE: Prior to handling heavy loads over or near spent fuel or safe shutdown equipment, load paths shall be iden-tified in specific maintenance procedures or in an attachment to the maintenance order / work package required to perform the particular maintenance task.
Procedures which control the operation of plant hoists and lifting devices shall establish the guidelines required for the identification and approval of any heavy load paths not identified in specific maintenance procedures. When heavy loads are being handled by the (1)
Reactor Building Overhead Crane or portable hoists, the load paths will be verified as free of obstructions prior to initial movement of the load. Additionally, an individual other than the crane operator will moni-tor the movement of the load along the travel path.
These requirements will be included in the procedure for controlling operation of the Reactor Building Crane (No. 32.000.07) and in the procedure for operation of portable hoists (No. 32.000.12).
(1) Revised 10/10/82 2.1 3-7
When heavy loads are being handled by use of monorail hoists, the load path will be verified as being free of obstructions by the operator prior to initial movement of the load. This requirement will be included in the procedure for the operation of monorail hoists (No.
32.000.08). Since the travel path associated with a monorail is fixed, additional effort is not required to monitor load travel for deviation from the specified path.
If the need should arise to deviate from a load path identified in a specific maintenance procedure, a pro-cedural change will be required. Plant administra-(1) tive procedure entitled " Procedure Preparation, Review, Approval, Change, Revision, Cancellation and Distribution" (No. 12.000.07) describes in detail the procedure revision process. Procedures which control the operation of plant hoists and lifting devices shall establish the process for deviation from any heavy load paths previously identified in an attachment to the maintenance order or work package.
(1) Revised 10/10/82 2.1 3-7a
2.1 3.c A tabulation of heavy loads to be handled by each crane which includes the load identification, load weight, its designated lifting device, and verification that handling of such load is governed by a written proce-dure containing, as a minimum, the information iden-tified in NUREG-0612, Secion 5.1.1(2).
RESPONSE: The attached Table 2.1 3.c provides a list of heavy loads that will be carried by each crane along with any designated lifting devices. In order to control future heavy loads to be handled over or near spent fuel or required safe shutdown equipment, the procedures governing the operation of the Reactor Building Crane, Monorails, and Portable Hoists will require the guide-lines of NUREG-0612 be invoked by either specific main- (1) tenance procedures or by attachment to maintenance orders / work packages prior to movement of heavy loads in these areas.
Of the seventeen (17) procedures listed in Table 2.1 3.c, sixteen (16) have been written and approved; however, some revisions are needed to incorporate addi-tional commitments contained in this revision.
(1) Revised 10/10/82 2.1 3-8
Table 2.1 3.c TABULATION OF HEAVY LOADS OVERHEAD HOIST; REACTOR BUILDING CRANE MAIN HOIST AREA; REACTOR BUILDING FIFTH FLOOR LOAD LOAD WEIGHT LIFTING DEVICE WRITTEN PROCEDURE
, 1. Drywell Head 67 Ton Head Strongback Maintenance Proce- (1)
(T2301A001A) (F1300E009) dure No. 35.000.81
- 2. Reactor Shield 100 Ton /Ea 3-Leg Sling, + Maintenance Proce-Plugs (6) dure No. 35.000.80 3 Reactor Pressure 6 Ton Service Platform Maintenance Proce-Vessel Service Plat- Lifting Device dure No. 35 000.74 form (F1300E010) (CEX-33240A)
- 4. Vessel Head Insulation 5 Ton Spreader Beam, + Maintenance Proce-(B1151H001) dure No. 35.000.121
- 5. Reactor Pressure 81 Ton Head Strongback Maintenance Proce-Vessel Head (F1300E009) dure No. 35.000.83
- 6. Reactor Pressure 5 Ton Connects directly Maintenance Proce-Vessel Head to Main Holst dure No. 35.000.83 Strongback Hook (F1300E009) 7 Storage Pool Slot 43 Ton /Ea 2-Leg Sling, + Maintenance Proce-Plugs (4) dure No. 35 000.115
- 8. Fuel Pool Slot Plugs 9 Ton /Ea 1-Leg Sling, + Maintenance Proce-(4) dure No. 35.000.113 9 Stud Tensioner 6 Ton Connects directly Maintenance Proce-(F1300E007) to Main Holst Hook dure No. 35 000.82
- 10. Steam Dryer 42 Ton Dryer / Separator Maintenance Proce-(B1107D041) Sling (F1300E008) dure No. 35 000.84
- 11. Steam Separator 73 Ton Dryer / Separator Maintenance Proce-(B1112D002) Sling (F1300E008) dure No. 35.000.85
- 12. Storage Pool Gate 14 Ton 2-Leg Sling, + Maintenance Proce-dure No. 35 000.116
- 13. Fuel Pool Gates 4.3 Ton & 2-Leg Sling, + Maintenance Proce-(A & B) 2 5 Ton dure No. 35.000.89
+ Not Yet Purchased
'(1) Revised 10/10/82 2.1 3-9
Table 2.1 3.c (Cont'd)
LOAD LOAD WEIGHT LIFTING DEVICE WRITTEN PROCEDURE
- 14. Crane load Block 5 Ton None
- 15. Spent Fuel Cask 100 Ton Redundant Cask Main'enance t Proce-(F1600E001) Slings dure No. #
- 16. Concrete Floor 5 Ton 4-Leg Sling, + Maintenance Proce-Hatch (El-10 column location) dure No. #
- 17. RWCU Demin Floor 14 Ton 4-Leg Sling, + Maintenance Proce-Plug dure No. #
- 18. Equipment Hatch Plugs 17 Ton 4-Leg Sling, + Maintenance Proce-dure No. 35 000.117
- 19. Debris Shipping Cask # + Maintenance Proce-dure No. #
- 20. Fuel Storage Racks # + Maintenance Proce-dure No. #
l
- 21. Refueling Bridge 14 Ton 4-Leg Sling, + Maintenance Proce-(T2502D001) dure No. 35 000.87
- 22. Dryer / Separator 2.4 Ton Attaches directly Maintenance Proce-Sling (F1300E008) to Main Hook dure No. 35 000.84
, and 85
- 23. Vessel Head Insula- 1.2 Ton Attaches directly Maintenance Proce- (1) tion Spreader Beam to Main Hook dure No. 35.000.121 TABULATION OF HEAVY LOADS OVERHEAD HOIST: REACTOR BUILDING AUXILIARY HOIST (5 TON)
AREA: REACTOR BULDING FIFTH FLOOR LOAD LOAD WEIGHT LIFTING DEVICE WRITTEN PROCFDURE
- 1. Maintenance Tools 5 Ton #, + Maintenance Proce-dure No. 32.000.07 (1)
- 2. Lifting Fixtures 5 Ton #, + Maintenance Proce-dure No. 32.000.07 3 New Fuel Vault Plugs 21 Ton 4-Leg Sling, + Maintenance Proce-dure No. 35 000.118 1 0 To Be Determined Later
- + Not Yet Purchased (1) Revised 10/10/82 2.1 3-10
Table 2.1 3.c (Cont'd)
TABULATION OF HEAVY LOADS LOAD LOAD WEIGHT LIFTING DEVICE WRITTEN PROCEDURE OVERHEAD HOIST: CORE SPRAY DIVISION 1 AND 2 HOISTS (2 16-TON)
AREA: REACTOR BUILDING FIRST FLOOR
- 1. Core Spray First 8} Ton a, + Maintenance Proce-Floor Hatch (2) dure No. 32.000.08
- 2. Core Spray Basement 8} Ton #, + Maintenance Proce-Floor Hatch (2) dure No. 32.000.08 ,
- 3. Core Spray Pump Ton #, + Maintenance Proce-Motors (4) dure No. 32.000.08 E2101000A-D OVERHEAD HOIST: NE EQUIPMENT DOOR HOIST (12 TON)
AREA: REACTOR BUILDING FIRST FLOOR NE Equipment Door 11 3 Ton * ' Maintenance Proce- (11 T2301A001B dure No. 35 000.11 OVERHEAD HOIST: DIESEL GENERATOR MOTOR CONTROL CENTER DIVISION 1 AND 2 (4 4-TON)
AREA: RHR BUILDING UPPER FLOOR
- # #, + Maintenance Proce-dure No. 32.000.08 OVERHEAD HOIST: DIESEL GENERATOR NORTH AND SOUTH DIVISION 1 AND 2 HOISTS (4 2-TON)
AREA: RHR BUILDING GRADE FLOOR Diesel Generator # #, + Maintenance Proce-Components (i.e. dure No. 32.000.08 cylinders, cylinder liners)
OVERHEAD HOIST: VENTILATION EQUIPMENT HOIST (8-TON)
AREA: AUXILIARY BUILDING
- # #, + Maintenance Proce-dure No. 32.000.08 0 To Be Determined Later
+ Not Yet Purchased (1) Revised 10/10/82 2.1 3-14
2.1 3.d Verification that lifting devices identified in 2.1 3.c.
above, comply with the requirements of ANSI N14.6-1978, or ANSI B30 9-1971 as appropriate. For lifting devices where these standards, as supplemented by NUREG 0612, Section 5.1.1(4) or 5.1.1(5), are not met, describe any proposed alternatives and demonstrate their equivalency in terms of load-handling reliability.
RESPONSE: To date, there are only three lifting devices provided for the handling of heavy loads that would fall within the guidelines of ANSI N14.6-1978, as defined in NUREG-0612. These are the RPV Head Strongback, the Dryer / Separator lifting device, and the Vessel Head Insulation Spreader Beam. A design review by General Electric finds that the RPV Head Strongback and Dryer /
Separator lifting device do meet the design strength criteria of Section 3 2 of ANSI N14.6-1978, taking into account the combined static and dynamic load forces.
However, certain components in these lifting devices do not meet the additional strength criteria of Section (1) 6.2 for single failure proof systems. Although General Electric recommendations do not find it practical to modify all of these components to meet this criteria, i this is still being reviewed by Edison. Action 4
determined by this review on any possible modifications or additional analyses will be initiated prior to fuel load and will be completed prior to the use of these devices after initial criticality.
(1) Revised 10/10/82 2.1 3-15
- i. The Vessel Head Insulation Spreader Beam is being i designed to achieve compliance with the ANSI N14.6 strength criteria for combined static and dynamic (1) load forces. The Spent Fuel Cask handling system is accepted as single-failure-proof and is addressed in detail in the Enrico Fermi FSAR, Section 9 1.4.2.1.
4 4
i i
i l
n l
(1) Revised 10/10/82 l 2.1 3-15a
i All other special lifting devices and slings will be purchased to ensure that the requirements of ANSI N14.6-1978 and ANSI B30 9-1971 are satisfied. Existing slings used for construction will not be retained for handling of heavy loads around critical equipment after the plant is operational.
The requirements of the stress design factor will include the maximum static and dynamic loads as defined by NUREG-0612. Any single-failure-proof handling systems will also meet the requirements of NUREG-0612, Section 5.1.6.
All slings that fall within the concerns of NUREG-0612 will be clearly marked to identify their qualification for that application. This includes a load rating (1) accounting for static and dynamic loads for hoist speeds up to 30 ft/ min for these slings, as well as any information which might restrict certain specific slings to specific hoist / load applications.
2.1 3.e Verification that ANSI B30.2-1976, Chapter 2-2, has been invoked with respect to crane inspection, testing, and maintenance. Where any exception is taken to this standard, sufficient information should be provided to demonstrate the equivalency of proposed alternatives.
, RESPONSE: For the Reactor Building Crane, Main and Auxiliary Hoists, crane inspection, testing, and Maintenance Pro-cedures will comply with the guidelines in ANSI B30.2-1976, Chapter 2-2. Should any deviations from this standard be required, they will be equivalent to (1) Revised 10/10/82 2.1 3-16
the requiremsnts of ANSI B30.2-1976. The requiremsnts of this standard will be incorporated into the Reactor Building Crane General Maintenance Procedures Nos.
35.000.120 and 34.000.43 These procedures will be (1) written prior to fuel load.
For all other overhead hoists listed in Table 2.1.1, inspection, testing, and maintenance procedures will comply with ANSI B30.16-1973, Chapters 1.2 and 2.2.
2.1 3.f Verification that crane design complies with the guide-lines of CMAA Specification 70 and Chapters 2-1 of ANSI B30.2-1976, including the demonstration of equivalency of actual design requirements for instances where spe-cific compliance with these standards is not provided.
RESPONSE: The reactor building main crane is the only single-failure-proof crane at the plant site. The Enrico Fermi 2 Atomic Power Station FSAR, Section 9 1.4.2.1, describes the single failure proof design features incorporated in the 125 ton crane.
i The Fermi 2 Reactor Building Crane was designed under the EOCI #61 " Specifications for Electric Traveling Cranes".
However, additional, upgraded criteria included in the later CMAA #70-1976 specification was already a l
part of the manufacturer's design practices. The following identifies these criteria and provides the I (1) Revised 10/10/82 2.1 3-17 l
results of Edison's analysis verifying the Formi 2 crane's conformance with this criteria.
For all other overhead hoists listed in Table 2.1.1, CMAA #70 and ANSI B30.2 are not the applicable stan-dards for these hoists. ANSI B30.16-1973 is the appli-cable standard. The recirculating pump hoists design does conform to this standard. The remaining hoists, which are not yet purchased, have been specified to conform to ANSI B30.16.
These hoists and any other future cranes or hoists that fall within the concerns of NUREG-0612 will meet the (1) design guidelines of NUREG-0612.
a (1) Revised 10/10/82 2.1 3-18
2.1 3.g Exceptions, if any, taken to NSI B30.2-1976 with respect to operator training, qualification, and conduct.
RESPONSE: Operator training, qualification, and conduct will be in compliance with the requirements of ANSI B30.2-1976 for operation of overhead, traveling cranes. Operators of various types of cranes will be trained and qualified to the appropriate standard for the specific s type of equipment to be used. Records of personnel (1)
~
- training and qualification will be retained. This training program will be administered by the' Nuclear Operations Training Group. The training program
.i will be implemented prior to fuel load and those indi-viduals operating cranes / hoists will be qualified prior to involvement with any post-criticality heavy load handling event.
l.
l
~
(1) Revised 10/10/82 2.1 3-19
TABLE 2.2.1 HOISTS OPERATING OVER SPENT FUEL OR THE REACTOR VESSEL Holst Rated Number Holst Typ_e Capacity T3100E002 Reactor Bldg. Crane Traveling Overhead 125 Ton Main Holst Aux. Hoist Hoists 5 Ton #
F1500E004 Refueling Platform Traveling Overhead 2000 lbs.
Main Hoist F1500E005 Refueling Platform Hoists 1000 lbs.
Aux Holst F1500E006 Refueling Platform Traveling Monorail 1000 lbs.
Monorail Holst Hoists Refueling Platform Hand winch Fixed Manual Winch 2000 lbs.
F1100E020 Channel Handling Boom Boom Trolley Holst 200 lbs.
F1100E021 Fuel Pool Jib Crane Boom Holst 2000 lbs.
F1100E023 New Fuel Transfer Holst Traveling Poom Holst 2000 lbs.
F1160E024 Fuel Channeling Crane Portable Floor Crane 250 lbs. (1) 0 Restricted to 1500 lbs. when traveling over spent fuel.
(1) Revised 10/10/82 2.2.1-2
TABLE 2.2.2 OVERHEAD HOISTS EXEMPT FROM FURTHER ANALYSIS N Y CANNOT HANDLE HEAVY LOADS OVER SPENT FUEL OR THE REACTOR VESSEL A. Hoists Incapable of Handling Heavy Loa.ds Over 2000 lbs.
Rated Holst Holst Capacity Location Refueling Platform Monorail Hoist 1000 lbs. Reactor Bldg.-Sth F1.
Refueling Platform Aux. Hoist 1000 lbs. Reactor Bldg.-Sth F1.
Refueling Platform Main Holst 2000 lbs. Reactor Bldg.-5th F1.
Refueling Platform Hand Winch 2000 lbs. Reactor Bldg.-5th F1.
Fuel Pool Jib Crane 2000 lbs. Reactor Bldg.-5th F1.
Channel Handling Boom Holst 200 lbs. Reactor Bldg.-5th F1.
New Fuel Transfer Holst 2000 lbs. Reactor Bldg.-Sth F1.
Fuel Channeling Crane 250 lbs. Reactor Bldg.-Sth F1. (1)
(1) Revised 10/10/82 2.2.2-2
( )
TABLI: 2.3.2 v'
ENRICO FERMI UNIT 2 IIEAVY LO?.D IIANDLTNG: LOAD /ARPA 1P!:'ACT MATHIX
!!OIST: REACTOR BUILDINc, CRANE MAIN llOIST - T3100E002 LOCATION DUILDING: REACTOR BUILDING .
IMPACT ALONG BUILDING COORDINATE LINE D ALONG DUILDING CCORDINATE LINE AREA PROM COORDINATE LINE 13 TO 15_1/3 FROM COORDINATE LINE TO _ _
LOADS sal'ETY RSI.ATED llAZARD
' SAFETY R U I.A*.*E D !!siZ Ai'D l FLOOR /ELEV. EQUIPMENT ELIM. FLOOR /ELEV. EQUIPME?N dLIM.
CATEccay acr:.w tu
- 1. Drywell IIead Subbasement 1. Div 1 RIIR b,e T2301A001A 540' - 0" Piping (1) 1(67 'Ibn) 2. Div 1 EECW b,e Piping
- 3. Torus c,e Basement 1. Div 1 EECW b,e 562' - o" Piping
- 2. Div 1 RIIR b,e Piping
- 3. RCIC Turbine b,c,e E>:hau s t Piping
- 4. IIPCI Turbine b,c,e Exhaust Piping
- 5. Div 1 Ri!R b,o Service Watcr Piping ,
(1) REVISED 10- 10-82 2.3.2-2
rm TABLE 2.3.2 ENRICO PERMI UNIT 2 !!EAVY LOAD !!ANDLING: LOAD / AREA IMPACT MATRIX b)
IIOIST: REACTOR BUILDING CRANE MAIN !!OIST - T3100E002 LOCATION BUILDING: REACTOR BUILDING IMPACT ALONG DUILDING COORDINATE LINE B ALONG BUILDING COORDINATE LINE AREA FROM COORDINATE LINE 13 TO 15 h, FROM COORDINATE LINE TO LOADS SAFETY RELATED IIAZARD SAFETY RELATED IIAZARD FLOOR /ELEV. EQUIPMENT ELIM. FLOOR /ELEV. EQUIPMENT ELIM.
CATECOP.Y .C.*.TECOR'I
- 1. Drywell !!ead Basement Div 1 Cable b,e #
T2301A001A 562' - 0" Trays *
(67 . Ton) .
IP-009 1C-008 1C-009 (1) IP-011 1C-100 1C-001 1K-004 1C-002 1K-008 IK-032
~
l (1) REVISED 10-10-82 l
- Sco Cable Tray Index 2.3.2-3
TABLE 2.3.2 ENRICO FERMI UNIT 2 IIEAYY) I.OAD !!ANDLING: LOAD / AREA IMPACT MATRIX IIOIST: REACTOR DUILDING CRANE MAIN IIOIST - T3100E002 LOCATION -
BUILDING: REACTOR BUILDING IMPACT ALONG BUILDING COORDINATE LINE B ALONG BUILDING COORDINATE LINE-AREA FROM COORDINATE LINE 13 TO 15 1/3 FROM COORDINATE LINE TO LOADS SAFETY RELATED IIAZARD SAFETY RELATED IIAZARD FLOOR /ELEV. EQUIPMENT ELIM. FLOOR /ELEV. EQUIPMENT ELIM.
Can,bORr UnTt.uGRY
- 1. Drywell IIcad First Floor 1. Div 1 RIIR b,e T2301A001A 583' - 6" Piping
( fon) .
Div 1 Cable Trays
. 2C-089 Second Floor 1. Div 1 Core b,e 613' - 6" Spray Piping
- 2. Div 1 EECW b,e -
Supply and Return Piping (1) REVISED 10-10-82
- Sce Cable Tray Index 2.3.2-4
. . . . , - ._. .. , . _ , . . , n. n , , . . , . . . , ,n,
_.c-.-w 4.3. ,t u . .u tu r _ r. u . . a. . . - . o. . : um t .v_ . a..u : wC/A. .,2 ..
1a .p,.C M,, TRI.\.
L s,. sv.s .n 3.un7 s s c,s. . ..a
.- A s . ~ y .-. .J . , L\
, . . ,7 q, E.sts w s IDCATIOt: BUILDII;G: RIZCKG DUILDI :G - FIRST l'ID3R Am a[l %k,,i tu w A'ONG A LI::E FIDI EUILDI::G COO:CINATES E4,, 12-3/4 to D'2, 13-3/4 11SDS TJJOR/ELTIATION SAFl?? RELATED E's2IdC SAFI11T PJ2ATED- FAZARD ECUIDI2:T ELDi!!ATION FIDOR EQUIR" DIP EQUIE E .T l CATACORY FiWATION . CATAGORY I t NE EQUIMIENT DOOR BASD1ENT DISCHARGE LINES FIDI ADS-SRV * -
V22-2071 AND NON- C ADS-SRV V22-2030 l
l 4
- STILL UNDER REVI W I, 2.3.2-35a (REVISED 10-10-82)
Tho handling of the unloaded Vossel Head Insulation Spreader Beam, which is connected directly to the Reactor Building Crane Main Hook, meets single failure proof criteria during movement of the Spreader Beam from its storage location to the drywell.
Items No. 5 and 6 Reactor Pressure Vessel Head Strongback and Reactor Pressure Vessel Head The Reactor Pressure Vessel Head is removed only during cold shutdown conditions and only with its special lifing device, the Reactor Pressure Vessel Head Strong-back. The Torus is not required to maintain cold shut-down and sufficient redundancy exists such that a postulated load drop will not cause the loss of other safety functions. Additionally, load / floor analysis demonstrates that a load drop will not damage any i
safety-related equipment away from the Reactor Vessel, if the RPV Head is not carried more than 4 feet above the floor along its travel path and laydown area.
Maintenance Procedure No. 35.000.83 shall include this limitation in its specifications.
The handling of the RPV Head over the Reactor Vessel meets the criteria of NUREG-0612, Section 5.1.6 for (1)
- single failure proof handling systems, with the following comments:
(1) Revised 10/10/82 l
2 3 2-70 4
- 1. General Electric has stated that the RPV Head Lifting lugs do meet the criteria of NUREG-0612, Section 5.1.6(3). However, Edison review and acceptance of this analysis is still ongoing
- 2. General Electric, however, has stated that the RPV head strongback lifting device has several components that do not meet the additional design strength criteria of ANSI N14.6, Section 6.2. Although some of these components can be modified to meet this criteria, General Electric recommendations find this to be impractical for all of these components. This is (1) also still under Edison review.
As stated in Section 2.1 3.d, action determined by this review on any possible modifications or additional analyses will be initiated prior to fuel load and will be completed prior to the first post critical use of these devices.
The direct redundant attachment of the Strongback to the Reactor Building Crane Main Hook, has sufficient strength to meet single failure proof guidelines whenever this lifting device is carried unloaded from its storage location to the Drywell area, or RPV Head or Drywell Head Laydown Locations.
(1) Revised 10/10/82 2 3 2-70a
Additionally, safety-related system redundancy preclu-des any system from performing its safety-related func-tion when these loads could possibly be dropped.
General Electric has stated that the strength allow-ances used for the design of the Dryer / Separator lifting device does not allow for adequate strength to meet ANSI N14.6-1978, Section 6.2 criteria for maximum combined static and dynamic load forces during handling of the separator in air. General Electric currently does not recommend any practical method to upgrade this lifting device to meet Section 6.2 additional strength or dual load path criteria.
However, General Electric's findings have not taken (1) into consideration that the separator is underwater while it is handled over the reactor. This is undergoing further review.
Action determined by this review on additional analysis or any practical modifications will be initiated prior to fuel load and will be completed prior to post-criticality handling of the Dryer / Separator.
Item No. 12 Storage Pool Gate Movement of the 14 ton Storage Pool Gate during a refueling outage is from its operating location to a
, location within the Storage Pool, where it will be (1) Revised 10/10/82 2 3 2-73
secured to the side of the pool. ESF systems located below the Storage Pool have sufficient redundancy and separation to preclude the complete loss of a system due to a potential load drop.
Item No. 13 Fuel Pool Gates A & B Movement of the Fuel Pool Gates during a refueling outage is from their operating location to their storage location along the same (south) wall of the Fuel Storage Pool, where the gates are to be secured to the wall. Analysis of the Fuel Pool floor structure finds that it can withstand a potential Fuel Pool Gate drop from a hieght of 17 feet above the Pool Floor.
r 2 3 2-73a
Further analysis is continuing to verify that there will be adequate fuel rack protection against the possibility of a fallen gate toppling against the racks after it has fallen to the pool floor.
Item No. 15 Spent Fuel Cask Handling / hoisting procedures and administrative controls for the Spent Fuel Cask are described in the Enrico Fermi 2 Final Safety Analysis Report, Section 9.1. The likelihood of a handling system failure for this load has been demonstrated and accepted as being extremely small.
Items No. 16.and 17 Concrete Floor Hatch (Co. El-101 and the RWCU Demineralizer Concrete Floor Plugs The concrete floor hatch located at building coordinates El-10}
will be handled by the auxiliary hoist. The RWCU deminera- (1) lizer concrete floor plugs are outside the coverage area of the Reactor Building Hoists and methods to lift these heavy loads are still under investigation. Additional hoisting equipment and the maintenance procedure covering the use of this equip-ment will be in accordance with the NUREG-0612 guidelines and will be implemented prior to the handling of these plugs after initial operation.
Item No. 18 Equipment Hatch Plugs The Equipment Hatch Plugs will be placed in the immediate vicinity of the Equipment Hatch opening whenever the hatch is to be opened for access. The handling of these plugs is still under study. This study and any potential modifica-tions will be completed prior to the handling of these plugs after initial operation.
2 3 2-74 (1) Revised 10/10/82 i
L. DIESEL GENERATOR HOISTS AND DIESEL GENERATOR MOTOR CONTROL CENTER HOISTS The diesel generator hoists and diesel generator motor control center hoists are used during correc-tive and maintenance procedures on the diesel generators. The accidental dropping of'a diesel engine component will have no effect upon any other system required for safe shutdown or decay heat removal.
M. VENTILATION EQUIPMENT HOIST The Ventilation Equipment Hoist is an 8-ton overhead hoist used for corrective and preventive maintenance on various ventilation components.
There is adequate floor strength to withstand an inadvertant load drop up to 10 tons, from the fifth floor to the third floor without impacting critical systems below the third floor. Maintenance Procedure No. 32.000.08 will specify this load limit for all lifts except those incurred during
( cold shutdown. Deviations from this specification 1
will require formal approval in accordance with the i procedure described in the response to Section 2.1 3.b.
(
1 1
i l
l 2 3 2-80
N. NE EQUIPMENT HATCH HOIST The Equipment Hatch Holst is a 12-ton monorail hoist used exclusively to move the NE Equipment Hatch to one side of the drywell NE Equipment access opening. This is to be performed during shutdowns whenever large equipment is to be moved to or from the drywell (i.e. N. recirculation pump motor).
The only safety-related equipment located under the monorail travel path of this hoist are the (1) discharge pipes from ADS safety relief valve V22-2071 and NON-ADS safety relief valve V22-2070.
The handling of the NE equipment hatch will not take place whenever the availability of these valves is required for reactor protection.
The methods and written procedures covering the handling of this hatch will be completed prior to post criticality.
(1) Revised 10/10/82 2 3 2-80a
III. RESULTS Results are summarized below:
DESCRIPTION OF HEAVY LOAD WEIGHT OF THICKNESS OF MAXIMUM HEAVY LOAD IMPACTED SLAB DROP HEIGHT Reactor Shield Plugs 100 T/ea 24" 5'-0" Fuel Pool Slot Plugs 9 T/ea 24" 12'-0" Drywell Head 67 Ton 24" 5'-6" (1)
Vessel Head Insulation 5 Ton 24" 12'-0" RPV Head 81 Ton 24" 4'-0" Steam Dryer 42 Ton 42" 12'-0" Steam Separator 73 Ton 42" 9'-0" RPV Strongback 5 Ton 24" 12'-0" RPV Service Platform 6 Ton 24" 12'-0" CRD Transfer Cask 2 Ton 30" 20'-0" Stud Tensioner 6 Ton 24" 12'-0" Fuel Pool Gates 4 3T&2 5T 72" 17'-0" Storage Pool Slot Plugs 43 T/ea 24" 5'-4" Recirculation Pump Holst (outside primary containment) 25 Ton 1'-0" (1) Revised 10/10/82 2 3 2.87
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