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] |
Text
~
MI ECIECn 55M*"
June 19, 1981 EF2-48238
.il/f \
i Mr. L.L. Kintner Division of Project Management
-/
'Q 7@{D
{ h 3' f j r* 2.41]L 1d U Office of Nuclear Regulation U.S. Nuclear Regulatory Commission L L,.cgg
~
H2 Washington, D.C. 20555
} gg , C'/
Dear Mr. Kintner:
44 [
Reference:
- 1. Enrico Fermi Atomic Power Plant, Unit 2, O' NRC Docket No. 50-341
Subject:
Initial Test Program (Chapter 14) Questions The following is submitted as per our discussion with B. Clayton regarding the Enrico Fermi 2 Initial Test Program as defined in Chapter 14 of the Final Safety Analysis Report.
Listed below are the questions. received that require written responses or changes. It is our understanding thAt all the other questions received on this matter have now been resolved satisfactorily through our verbal discussions. With this letter Detroit Edison commits to change the test program as shown on the marked-up FSAR pages which are attached.
Qttestion Attached FSAR Page(s)
- 5. P0 #12 deleted testing of eqpt. used for servicing LPRM's and dry tubes. Why?
Answer: The wording was revised to specifically again 14.1-34 include this equipment.
- 7. P0 #43 deleted the measurement of leakage l
from drywell to suppression pool. Why?
Answer : This was deleted in error-the wording was 14.1-68 revised to again include this measurement.
l l
l 11. Purpose of test modified so that it now l only requires measurement of reference leg temperatures. Acceptance criteria ni 81oaen/&S, g
. a Memorandum to: June 19, 1981 Mr. L.L. Kintner EF2-48238 Question Attached FSAR Page(s) implias that more is being done. Modify the " criteria" to provide te.1perature criteria which satisfy the stated purpose. Also modify the " purpose" to include checking the calibration of the various instruments. Modify the des-cription to describe how this is done (coin-cide with the stated acceptance criteria).
Answer: This test abstract was modified to address the 14 1-114 abnve concerns. The present Level 2 criteria should determine if recalibration is nec-essary as shown.
- 12. Fil System SU - What is the source of the Level 2 AC7 Where does one look for the predicted value in #3.
Answer: General Electric supplies the Level 1 14.1-136 c'1teria as part of the test specifications for this system.
Criteria #3 was modified to show that the predicted value in question is obtained -
from the Transient Safety Analysis Design ,
Report supplied by General Electric.
- 13. Relief valves, should include demonstration of position indication.
Answer: A Level 2 criteria was added to include 14 1-141 verification of the relief valve position.
- 15. Recirc System - Explain how extrapolation done from M-G set motor trip to drive breaker trip inertia, etc. Deleted 2-pump trip. Must do 2 pump ATWS trip.
Answer: The oreoperational test abstract for the 14.1-30 recirculation system was changed to 14.1-31 specifically include both drive notor 14.1-148 breaker and ATWS trip tests. With this commitment there is no need for the field breaker trip extrapolation referenced in Startup Test Phase abstract and this was deleted.
l 1
(
Memorandum to: June 19, 1981 fir. L.L. Kintner EF2-48238 Attached FSAR'Page(s)
Question
- 16. Table 14.1-1 not consistent with test abstracts.
Modify table to reflect testing described in abstracts.
-STI Pressure Regulator: description shows tests in auto mode. Table does not.
STI FW System: description shows tests (water level setpoint changes) in auto mode. Table doesn't.
STI TSV & CV Fast Closure Trips: descrip-tion states generator trip performed at 100f power. Table shows either SV or CV.
Answer: STI-20 (Pressure Regulator) was modified to delete 14.1-133 the reference to testing in the automatic 1 pad follow mode of recirculation system operation. .
As discussed, STI-21 (FN System) was not chang'ed as the present wording is satisfactory.
Item K was deleted from table 14.1-1 to remove 14.1-159 the inconsistancy with STI-25.
- 20. Is loose parts monitoring system covered by the initial test program?
The Loose Parts Monitoring System was added to 14 1-21 Answer:
the list of Acceptance tests which will be performed in the initial test program.
Sincerely, W.F. Colbert Technical Director Fermi 2 Project i
WFC/smr cc: B. Little i
l 1
- - - - -- - - - -_ _ . __ ___ _ .i
Mr. L.L. Kintner June 19, 1981 EF2-48238 bec: T. A. Alessi R. M. Berg W. F. Colbert
- 11. J. Fahrner F. E. Gregor E. P. Griffing
- 11. R. Holland J. W. Honkala
- 11. J. Jens L. E. Kanous R. S. Miller J. A. Nyquist T. J. O'Keefe E. Lusis P. A. tiarquardt E. fi. Page
.L. E. Schuerman M. W. Shields H. Tauber R. A. Vance A. E. Wegele Document Centrol
- 't f=")** ""if*'3(LPRefs)
EF-2-FSblL - l ace I f and Jr y tu k!~
14.1.3.2.12 Fuel Handling an Vessel Servicing Equipment Preoperational Test lll
- a. Test Objective j/ To verify the operation of the fuel handling and vessel servicing equipment, including tools used 1 / the servicing of control rods and fuel assemblies 9a: The test will also verify the operation 35 of vacuum ' cleaning equipment, the refueling platform, the fuel preparation machine, and the service platform.
- b. Prerequisites - The Checkout and Initial Operations Tests have been completed and the TRC has reviewed and approvea the test procedure and the initiation of testing. Additionally, the refueling platform, fuel preparation machine, and fuel racks must be installed and operational; all slings and lifting devices must be certified at their design load, at least, by the vendor.
- c. General Test Method - Verification of the fuel-handling and vessel servicing equipment is demon-strated by dry operation of the following equipment:
- 1. Cell disa'ssembly tools
- 2. Channel replacement tools 3.
Instrument-handling tools
- 4. Vacuum cleaning equipment
- 5. Interlocks and logic associated with the refuel-ing and service platform are verified
- 6. Proper operation of refueling and service plat-forms are verified.
- d. Acceptance Criteria - All tools must be verified for proper operation. In addition, logic and in-terlocks and sling and grapple load cells must be either verified for proper operation, or demon-I strated to be within their respective engineering I
design specifications.
4 l
I 14.1-34 Amendment 35 - May 1981 j
EF 2-FSAR 14.1.3.2.43 Primary Containment Leak Rate Preoperational Test Test Obiective - To determine the primary containment O
a.
leak rate including containment penetrations, MSIVs, and the drywell to suppression pool vacuum breakers.
- b. Prerequisites - The Checkout and Initial Operations Tests have been completed and the TRC has reviewed and approved the test procedure and the initiation 35 of testing. Permanent plant air supply or a portable air compressor with filters and valves, pressure and temperature sensors, flow meters, and soap bubble and ultrasonic leak detection equipment must be available.
Functional tests of isolation valves described in the nuclear boiler preoperational test (14.1. 3. 2. 6 )
and vacuum breakers described in the containment vacuum breakers preoperational test (14.1.3.2.66) must be completed.
- c. General Test Method - Verification of the integrity of the primary containment boundaries is damonstrated by leak rate testing of the following:
- 1. Local leak rate test of primary containment penetrations
- 2. . Local leak rate test of primary containment iso-lation valves, including MSIVs, and each torus to reactor building vacuum breaker and isolation valve
- 3. Local leak rate tests of drywell to suppression pool vacuum breakers
- 4. Overall containment integrated leakage.
S. hhyafed I ** N c I'S+ ~ df YW'II Io 3 ff!'*
- 35l d. Acceptance Criteri@a - All leak rates from penetrations, valves, and overall containment must be shown to be within their respective engineering design specifications.
l
! '14.1-68 Amendment 35 - May 1981 e
f
l EF-2-FSAR 14.1.4.8.7 Uater Level Megsurement y y Jea k +/,a ca.I;i .-d,0.s S $ f* ^'" ***b " f
'**'** _ ) u rco.s c u p k litLL~kt% M The purpose of.this test is 4to measure the reference leg temperature and recalibrate the instruments if tha measured temperature is different than the value assumed during the initial calibration.
, Description To monitor the reactor vessel water level, four level instrument systems are provided. These are the following:
- a. Shutdown range
- b. Narrow range
- c. Wide range
- d. Fuel range.
These systems are used, respectively, as follows:
- a. Wat0c level measurement, cold shutdown condicions
- b. Feedwater flow and water level control functions, hot 35 operating conditions
- c. Safety functions, hot operating conditions
- d. Safet
%,g le>l ,s.<lhi./J :y functions, cold shutdown conditions.
n to %c ,>.rk. & C.,A e,,i .
The tert will be done at ' rated temperature and pressure and under steady-state conditions and will verify that the reference leg temperatures of the instruments are the values assumed during initial calibration. If not, the instruments will be recalibrated using the measured value. 7h, u ,,, ,/p ,/. : f f fls te,/e,,tsl>f3 i f r e .s/, a
. .! f,al/ <.
/
Yht c -fo ser; Cetterla y;,, alt sind ,,j n<rrow imy(lud ,'ach* dr. sc,. y ,, , , ;,(L y, y , 7g (u, y , , ,, ( ,g ,,,,)f +fu Leve1 1 (f caIll,ed..;.t ;5 neoru 4 e .
Not applicable.
Level 2
- a. The narrow-range level system indicators should agree within 11.5 in, of the average readings
- b. The wide-range level system indicators should agree within 16 in. of the average readings.
.i
[!
i! 14.1-114 Amendment 35 - May 1981 l
i,
EF-2-FSAR The feedwater flow runout capability must not exceed the as-sumed value in the ?SAR.
Level 2 Level control system-related variables may contain oscillatory modes of response. In these cases, the decay ratio for each con-trolled mode of response must be less than or equal to 0.25.
A scram must not occur from low water level following a trip of one of the operating feedwater pumps. There should be a greater than 3-in. water level margi.: to scram for a feedwater pump trip initiated at 100 percent power conditions.
For the feedwater temperature loss test, the increase in simu-lated heat flux cannot exceed the predicted value referenced .
to the actual feedwater temperature change and power level. "Vhech 35 uill Le toK*n inns the Transient hfeVy Analptr Desy R<@.
The average rate of response of the feedwater actuator to large
(>20 percent of pump flo9) step disturbancos shall be between 10 to 25 percent of pump rated feedwater flow /sec. This average response rate will be assessed by determining the time required to pass linearly through the 10 percent and 90 percent response points of the flow transient.
The open loop dynamic flow response of each feedwater actuator (turbine or valve) to small (<10 percent) step disturbances shall be the following:
- a. Maximum time to 10 percent.of a step disturbance -
1.1 sec ,
- b. Maximum time from l0 to 90 percent of a step disturbance - 1.9 sec
- c. Peak overshoot (percentage of step disturbance) -
$15 percent.
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4 14.1-136 Amendment 35 - May 1981
)
p . _ _ . . ._ - .l...._.~_.. _
0 EF-2-FS AR l Level 2 Variables related to the pressure control system may contain oscillatory modes of response. In these cases, the decay ratio for each controlled mcde of response must be less than or equal to 0.25.
The temperature measured by thermocouples on the discharge side of the valves shall return to within 100F of the temperature recorded before the valve was opened. If pressure sensors are available, they shall return to their initial state upon valve 35 closute.
During the 250 psig functional test, the steam flow through each relief valve, as measured by the initial and final bypass valve position, shall not be less than 10 percent under the average of all valve responses.
During the rated pressure test, the steam flow through each re-lief valve, as measured by MWe, shall not be less than 5 percent of rated MWe under the average of all the valve responses.
Yut o$d bl n.f cohs a ),e.fm' e f re I*~$ V^ lJ t yn.'h.L Mg m ~w awl.~ J e A v~ Iv e -
14.1-141 Amendment 35 - May 1981
EF 2-FSAR 14.1.3.2.9 Reactor Recirculation and Motor-Generator Sets Preoperational_ Tests h
- a. Test Obiective - To verify the operation of the re-actor recirculation system, including pumps, and their associated motors and motor-generator sets, valves, instrumentation, and controls. The rated conditions tests are conducted during the Startup Test Program. ,
- b. Prerequisites - The Checkout and Initial Operations Tests have been completed and the TRC has reviewed and approved the test procedure and the initiation of testing. The RBCCWS must receive readiness veri-fication. All required testing of equipment up to the operation of the recirculation pump has been com-pleted, including operation of the motor-generator sets and fluid coupling, recirculation p' imp motor (uncoupled), and all control loops. Reactor inter-nals which are in place are those which can satis-factorily withstand the pressure drops encountered during these tests. Means must be provided to monitor audible noise and vibration of the pumps.
- c. General Test Method - After prerequisite testing, verification of system capability is demonstrated by the proper, integrated operation of the following:
- 1. System Valves (a) operability (b) opening and closing speed (c) manual operation (d) limit switch and torque switch operation (e) position indicating lights.
- 2. Logic and Interlocks (a) recirculation pump trip with reactor low j leveland/orwithreactorhighpressuree/>JW5) recirculation pump runback with reactor
! low level and loss of feed pump (b) recirculation flow limit for NPSH protec-l tion with low FW flow (c) scoop tube positioner lockup with signal
( failure l$I '
! (d) MG set drive motor lockout 14.1-10 Amendment 35 - May 1981 l
l
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EF-2-FSAR (e) MG set drive motor circuit breaker trip (f) circulating lube oil system l (g) annunciators.
- 3. Operational Testing (a) single pump operation at minimum speed (b) single and dual pump operation at higher loop fInws within flow and cavitation limits
~ c' j,,, a w, < 6.u. b r h or' be (c) pump tr *!'"O.L'%
b.
j.[* #$#hI ips , :=I"JI"Q'4;, u wJ p ,, k 'r e(J a 'd>'
- n %codbheo.
(d) % #%,u l recirc?',NEing pump and t.< piping
- o. nr +r.p v <ibration measuremants (e) MG set motor, coupler, and genarator (f) jet pump consistency.
- o. Acceptance Criteria - Performance cannot be evaluated properly in the preoperational phase, and, therefore, no conclusions on performanca can be reached until the system is tested during the power test program.
Expected values of measured parameters will be tabu- ~
lated before the test. Significant variations from these values will be investigated. All system com-ponents must be either verified for proper operation,
- or demonstrated to be within their respective engi-neering design specification.
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14.1-31 Amendment 35 - May 1981
EF-2-FSAR l 14.1.4.8.28 Recirculation System q Purpose <
- a. To verify that the feedwater control system can satisfactorily control tNe water level without a resulting turbine tripf scram and obtain actual pump speed / flow
- b. To verify rec!*culation pump startup under pres-surined reactor conditions
- c. To obtain recirculation system performance data
- d. To verify that no recirculation system cavitation occurs in the operable region of the power-flow map.
Description The reactor coolant recirculation system consists of the reac-tor vessel and two piping loops. Each loop contains a centrif-ugal recirculation pump and two isolation valves located in the drywell and 10 jet pumps in parallel situated in the reac-tor downcomer. Each recirculation pump takes suction from the reactor downcomer and discharges through a manifold system to the nozzles of the 10 jet pumps. Here che flow is augmented by suction flow from the downcomer and delivered to the reactor inlet plenum. ,
Recirculation pump trips are performed to determine the feed-water control system transient characteristics. Power to the recirculation pump motors is supplied from the station primary electrical bus through a fluid-coupled morne-generator set connected to each pump. Separation of the motor-generator set from its bus results it. a 1 css of pumping power and a con-sequent flow coastdown. The reactor transient respanse during the trip and coastdown of one recirculation motor-generator set 35l and its pump will be determined. All single-pump trips will be initiated' by tripping the motor-generator set drive motor breaker. Single pump trips of one motor-generator set drive motor will be used to determine the feedwater control system transient performance. Th;;; t;;.. lec.te _ f il be e-tr r ' t:d ,
r- ;
- ~ ^'- ficli bce. hun r 13-e:
Recirculation pump restarts become increasingly ditficult after a trip at reactor operating pressures. A successful pump re-start depends on the correct placement of the scoop tube in order to prevent a set stall. The tests will include changing the scoop tube position so that pump breakaway occurs at a tachometer output equivalent to between 5 and 15 cps. The limit switches on the positioner are then set for this range.
k 4
i 14.1-148 Amendment 35 - May 1981 h
- EF-2-FSAR 14.1.4.8.20 Pressure Regulator Purpose
- a. To determina the optimum settings for the pressure control loop by analysis of the transients induced in the reactor pressure control system by means of the pressure regulators
- b. To demonstrate the takeover capability of the backup pressure regulator on failure of the controlling pressure regulator and to set spacing between the setpoints at an appropriate value
- c. To demonstrate smooth pressure control transition between the control valves ar.d bypass valves when the reactor generates more steam than is used by the turbine.
Description The pressure setpoint is dgereased rapidly and then increased rapidly by about 10 lb/in.', and the response of the system will be measured in each case. It is desirable to accomplish the setpoint change in less than one second. At specified test conditions, the load limit setpoint is set so that the transient is handled by control valves, bypass valves, or both.
The backup regulator is tested by simulating a failure of the ,
opera. ting pressure , regulator so that the backup regulator takes
- over control. The response of the system is measured and eval-uated and regulator settings are optimized. The matrix of test ,
mode and conditions is tabulated below.
Test Condition Number Mode Input 1 2 3 4 5 6 __
CV Setpoint No Yes Yes Yes Yes Yes CV Fall to Back up No Yes Yes Yes Yes Yes BPV Setpoint Yes Yes No Yes Yes Yes i BPV Fall to l
Back up Yes Yes No Yes No Yes ;
l Rec ire .
Modes Local Local Master Local, Manual Manual Manual Manual Qae .ae+
h &nMIMT j 14.1-133 Amendment 35 - May 1981
EF-2-FSAR !
TABLE 14.1-1 STARTUP TEST PROGRAM ques weseel 8 es Ce&d Taat Eggiqlgg g Teet nestep 3 3 4 S 6 mee r ene y se. Test mean teet &
a e e a e e
& Cheeseel and todteenesteet e e e e e 3 eedset tee measur emente .
3 Pueb Leading e 4 Pu!& Case Smendemo steegan a e a e e l Cat e e a 6 Sden postereente and Cemeset and seguonce e a e
? ester teven meesessenete e e e 0 Ilue Pe#feemence a e s 9 t#est Ce 66te et ten a e e e e at apet Cetatestsen a e e
e a e Ml 64 Precess Ousewtee a la seeeter Case goetea6en Cent 6mg Systee e e a il eagh-Presense Costant Inleertnoe Svetes e e 14 Senested Pterees tempeestores e a e e e e il System Sagene6en e e to Core powse esotestetaan e e e e e e e 51 Core reefoemence e 18 Steam Predwettest e it Case powee = wood ammae sessense m e a e e.it 44 Preseese megeletes
- Setgesat Changee f..pr I.
L m e a me'88
= Seesup 8egulates L.or a
JL Peedwatee Systee = ree.ametes Asap Te ap a e
= isatee Levet setpetat Cnentes L a e miel
= neettmo Lose
+ etesames evneva Capest&6 y a af8l m4*8.sP mie.hl,S' 35 33 fust6s=* vetoe Sesee64Lensee 33 matvo seen vs.se a m4*f.SP m.;p t fl m888.SP e
. One vann mI U SDI SI e Pw&& les&ettest e mift 24 nelief veneee 31 twatae Stop venue end Cantes!
- L.SP(8 8 m.St.Ill m.80l l'EI volse Feet Closere tr6pe e
36 She ~ fece Outende Contret asas e e e e a
- 31 Plow Centret a e 30 Bestreuletten systee e tesp One Pump e e System Peetereense o e a e meneeettet ten vetif agetsee n
. Runnece m 39 tese of fdB of f ette powee L.Sallt e a e e a e e le viteessen messeramente o e 31 seekseelessen Systen Flow Collteettom 13 Seeetoe mesee Cle nup Systes e 33 Seendeen meet esoneet sysses e e e a e 34 Paptag Systems Dyisease seeposee sey e L e Lesen seneen flew control asas. a. ese Pigere 8 4.1 3 f ar Test (*nn4st anne rege,e esp.
A e mestes menest flew arattet mode. D. Teetang et messeet elseutetten an lett ined line see he done anyttee followtag Test e e Teet 1 . t of flew eentret. Conditten 3.
SP e Setem pensattitty. e. setween feet Cond6ttene 1 and B.
SS e Setes espoetes. d. Down setteint only.
B e Beres deflette. e. Detenee teet Condit6nna 1 and 6.
Se e 97 pees vetee reopenas. f. Det***e Test Conet tienn 3 est 3.
- g. Pwevee maoise pnwee test p* tat.
- n. Deterenne easteen pomoe withnet seven.
1.
3 9efere 1,999 Pe. f e,e eet tv,8 bine trip., t imin, ei-tof f -.rei r.wte . -1. net i. . t. t.o. e-e.e.
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}i 14el-159 Amendment. 35 - May 1981 e --
EF- 2-FS AR.
...~ ACCEPTANC3 TESTS (Cont'd)
- 10. Miscellaneous Heating, Ventilation, and Air Condi-tioning Systems Acceptance Tests
- 11. Torus Water Management System Acceptance Tests I2. Loan Psyk Mw;hA3 .Tph,., geeap+ ,,,a T<ds l
i 14.1-21 Amendment 35 - May 1981 L____________--_ _ - - - - _ - - - _
