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
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999 Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999 Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl ML20217N9231999-10-15015 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40 NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999 Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal ML20217D5331999-10-0707 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39 ML20217A3261999-09-30030 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38 NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations ML20216G9791999-09-24024 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37 NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999 Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20212F3241999-09-20020 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36 NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999 Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999 Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev 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
,l 4
O. R lph Sylvin Group Vice President
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Detroi! 6400 North Dixie Hi Edison =w ghway l i
j 1
Novenber 17, 1987 NR'-87-0095 i U. S. Riclear Regulatory Commission i Attn: Document Control Desk Washington, D. C. 20555 1
i' References 1) Fermi 2 NIC Docket No. 50-341 NIC License No. NPF-43 l
- 2) IE Bulletin 85-03, Motor Operated Valve Common l Mode Failures During Plant Transient Due to Inproper Switch Settings
- 3) NEDC 31322, BWR Owner 's Group Report on the Operational Design Basis of Selected Safety-Related Motor Operated Valves, Septenber 1986
- 4) Detroit Illison Letter to NIC, " Motor-OperatcIl Velve Switch Settings," VP-86-0137, dated October 1,1986
- 5) Detroit Fdison Letter to NIC, " Supplemental Response to IE Bulletin 85-03," VP-86-0162, dated Decenber 19, 1986
- 6) NIC Letter to Detroit Edison, Inspection Report No. 50-341/87035 (DRS), dated Septenber 23, 1987
- 7) NUREG/CR-4380 " Evaluation of the Motor-Operated Valve Analysis and Test System (MOVATS) to Detect Degra3ation, Incorrect Adjustments, and Other Abnormalities in Motor-Operated Valves" dated January 1986 l 8) NIC Letter to Detroit Illison, Inspection Report l No. 50-341/87022 (DRS) , dated July 23, 1987 l 9) Detroit Edison Letter to NIC, " Readiness 'for Restart", dated October 3,1987
Subject:
Response to IE Bulletin 85 MOV Common Mode Failures During Plant Transient Due to Inproper Switch l Settings l 8711230010 071117 PDR i
0 ADOCK 05000341 1 PDR glal
.e
,, UStE Novenber 17, 1987 tE-87-0095 Page 2 Davis Besse and Sequoyah Unit 2 Nuclear Plants experienced an event during which motor-operated valves failed on demand due to .
improper switch settings. Bcsed on these two events and a number '
of earlier similar events, the IE issued IE Bulletin 85-03 (Reference 2) . The purpose of the. subject bulletin was to.
request licensees to develop and inplement a program to ensure i switch settings of certain safety-related stor-operated valves are selected, set and maintained correctly to accommodate the
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maximum differential pressures expected on these valves during j both normal and abnormal events within the design basis. !
In order to accomplish this purpose, Bulletin 85-03 identified four actions to be taken by licensees. In accordance with the requirements of Item A of Reference 2, Detroit Edison informed the tE (Reference 4) that the operation of ecch valve requiring testing was reviewed in accordance with the Fermi 2 design bases.
The basic methodology set forth in the BWR Owner's Group Report on the Operational Design Basis of Selected Safety-Related Motor-Operated Valves, Reference 3, was used to calculate the maximum valve differential pressure for the opening and closure of each valve. This information was provided in Refererce. 4, Table 1 (Attached) .
Reference 4 was subsequently updated by Reference 5 by confirming- I that fifteen (15) of the thirty-three (33)' IPCI/BCIC valves listed in Table 1 (Attached) were operable based on maxinum differential pressures.
Detroit B31 son's response to the remaining actions identified in IE Bulletin 85-03 are contained in Enclosure 1 of this letter.
Enclosure 2 clarifies some information which was contained in IE Inspection Report 87-035. If you have' any questions, please contact Mr. Lewis Bregni at (313) 586-4072.
Sincerely, Ltb : J ,
1 cc: A. B. Davis !
E. G. Greenman W. G. Rogers J. J. Stefano G. C. Wright USNIC Region III
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Enclosure 1 NIC-87-0095 Page 1 1
TE BULLETIN 85-03 ITEM A Review and document the design basis for the operation of each valve.
This documentation should include the maxinum differential pressure expected during both opening and closing the valve for both normal and abnormal events to the extent that these valve operations and events are included in the existing, approved design basis, (i.e., the design basis documented in pertinent licensee submittals such as FSAR analyses and fully-approved operating and emergency procedures, etc) .
When determining the maximum differential pressure, those single equipment failures and inadvertent equipment operations (such as l inadvertent valve closures or openings) that are within the plant design basis should be assumed.
DNimir IDTSON'S RESPONSE TO TE BULLLTIN 85-03 IWM A The seventeen (17) HPCI and sixteen (16) ICIC system valves identified in Table 1 (Attached) are motor operated valves (MOVs) at Fermi 2 applicable to the subject bulletin. As stated in the cover letter and again in References 4 and 5, the design basis for the operation of each valve requiring testing was performed in accordance with 1(CFR50.55a(g) .
Table 1 shows the original specified differential pressure (dP), for j the selected HPCI and ICIC valves, used by the valve vendor (s) for valve selection and motor-operator sizing. This information is from i the Fermi 2 Master Valve List, and is either a specified dP or the i specified line design pressure. These values are listed for j conparison against the calculated maxinum dP's. '
The originally submitted IE Bulletin 85-03 maxinum dP's (Reference 4) were conservatively determined by an informal engineering calculation.
In aidition, Fermi 2 Nuclear Engineering perforned and formally documented Design Calculation No. 4685, Maximum Differential Pressure for Selected Safety-Related Motor Operated Valves, applying the generic methodology of Reference 3. This calculation includes the twenty-six (26) MOV's with active safety-related functions of the thirty-three (33) Fermi 2 specific valves. A calculation for the remaining MOV's will be conpleted by the Spring LLRT Outage.
The results of Design Calculation 4685 have been used in two (2) ways:
- 1) To review and update the Fermi 2 design base;
- 2) 7b obtain vendor reconfirmation or revision, as necessary of Torque Switch Settings.
The results of Design Calculation 4685 verify that the IE Bulletin 85-03 requirements for each of the twenty-six (26) MOV's evaluated are enveloped by the originally calculated dP's submitted to the NIC in
Enclosure 1 tmC-87-0095 Page 2 Reference 4. Design Calculation 4685 serves as a reconfirmation of the original Fermi 2 design base. The vendors for the selected valves (Wm. Powell and Rockwell International) were provided the results of Design Calculation 4685 to re-evaluate required thrust and reconfirm Torque Switch Settings. Ietters of confirmation have been received with revised Torque Switch Setting recommendations from both vendors.
Torque bypass switch settings were not specifically reviewed for the Bulletin, but have remained as originally established by Fermi 2 for specific valve functional requirements. For the MOV's with an active safety-related function requiring the valve to open, torque switch bypass switches have been used to inhibit the opening torque switch function. This ensures maxinum available operator capacity can be used during unseating and the initial valve stroke movenent when the valve experiences high dP conditions. The control node for each valve is found on the associate valve logic drawing arx3 schematic diagram i which are available on site for review. These docunents provide !
guidelines for maintenance work performed on MOV's to ensure proper adjustments of the torque switch bypass and limit switch settings.
The use of backseating using the open torque switch has been a conmon ,
practice at Fermi 2 in the past. However, based on a recent '
investigation of using the torque switch for brkseating, Detroit Edison has committed to (Reference 9, E.3) rewire the safety-related valves to use a limit switch trip instead of the torque switch for bmkseating. Nominal position is set as 1/2 turn of the valve stem off the backseat with additional adjustment by field testing. Limit i switch position for valve backseating is being confirmed by post ]
modification testing separately from IE Bulletin 85-03 testing. The HPCI/FCIC System MOV's alrea3y tested were tewired prior to IE i Bulletin 85-03 testing. Testing of the subject valves for IE Bulletin l 85-03 provides redundant confirmation of the switch position.
1 As noted in Refererce 5, the thermal overloa3 sizing for MOV's was j reviewed for all 33 selected valves. This review is also docunented i
! in a Detroit Edison Design Calculation. Based on the results, no l l modifications to the thermal overloa3 sizing for the MOV's were l required. .
l l L Tt should also be noted that no limit switch trips are used for safety-related M07 close-direction functioning. Close position limit l
switches provide only operator information and motor operator trip is j by separate close torque switches.
I
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Enclosure 1 tmC-87-0095 Page 3 IE BULIRITN 85-03 T'ITM B Using the results from item A above, establish the correct switch settings . This shall include a program to review and revise, as necessary, the nethods for selecting and setting all switches (i.e.,
torque, torque bypass, position limit, overload) for each valve operation (opening and closing) .
If the licensee determines that a valve is inoperable, the licensee shall also make an appropriate justification for continued operation in accordance with the applicable technical specifications.
DmunT EDTSON'S RESPONSE 'ID TE BULLETTN 85-03 I'IDI B Using revised Torque Switch Settings provided by the valve vendors, Fermi 2 engineers prepared a design change document, Potential Design Change 6557, which directed plant maintenance efforts to establish new settings to neet the IE Bulletin 85-03 criteria. Torque bypass switch settings were not altered by this effort as noted previously, i Open-direction limit switch settings have been established as a l separate issue, although some adjustment was later made due to field testing for IE Bulletin 85-03 Action C. Potential Design Change 6557, Rev. C, was fully inplenented for revised Torque Switch Settings as of ,
September 30, 1987. i Fermi 2's MOVATS program has found each MOV tested able to neet the IE Bulletin 85-03 acceptance criteria established. A brief report of j testing conducted to date was provided in Refererce 9, Item E.8. -
Additional details are provided under Item C of this enclosure. The test program did identify one of ten notor-operator assenblies functioning with a target thrust value above the operator rating.
Although the valve had met the MOVATS test criteria, this motor operator was replaced with a larger notor operator resolving this problem. The remaining twenty-three (23) MOV's to be tested were reviewed for the sane problem.
Only one (1) valve, of the remaining twenty-three (23) E5150F012, has been found to have an operator sized less than its IE Bulletin 85-03 target thrust value. This valve is not required to perform an active safety function, and is not c 10CFR50, Appendix J valve. The valve has and continues to neet its ASME XI Pump and Valve Program criteria. Based on the results of the MOV's already tested, the E5150F012 notor-operator assenbly is capable of reeting the IE Bulletin 85-03 acceptance criteria and, therefore, the valve is considered to be operable. However, based on plant-life service considerations the E5150F012 notor-operator will be replaced with a higher load rated operator during the Spring 1988 LLRT Outage.
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l Enclosure 1 NIC-87-0095 Page 4 TE BUllEPIN 85-03 ITEM C Individual valve settings shall be changed, as appropriate, to those established in Item B, above. Whether the valve setting is changed or not, the valve will be demonstrated to be operable by testing the valve at the maximm differential pressure determined in item A above with the exception that testing motor--operated valves under corditions simlating a break in the line containing the valve is not required.
Otherwise, justification should be provided for any cases where testing with the maximm differential pressure cannot practicably be performed. This justification should include the alternative to maximum differential pressure testing which will be used to verify the correct settings.
Each valve shall be stroke tested, to the extent prcctical, to verify that the settings defined in Item B above have been properly implemented even if testing with differential pressure cannot be performed.
DETTIOTT ETSON imSeONSM 'IO TE BULTEPTN 85-03 TTFM C Applying the results of the generic evaluation effort reported by Beference 3, six (6) HPCI valves and four (4) BCIC valves of the Fermi 2 specific design do not require dP testing. These valves are identified in Table 1 Notes 1 and 2 (Attached) . For the remaining EPCI and BCIC system valves, Fermi 2 is performing operability testing which inposes dP's on the valves as part of system performance confirmation. This is being accomplished by plant startup test program performd to verify proper system initiation, valve sequencing, and flow and pressure capability. Operability testing of HPCI/BCIC systems will continue as required by the Fermi 2 Technical Specifications and post maintenance modification requirements. The dP's experienced by the valves during operability tests are not as high as the calculated dP's, but do represent dP's under the actual plant conditions. These operating condition dP's are conservatively bounded by the static testing program for MOV's as described below.
Fermi 2 does not believe that replication of the dP's calculated and reported in Design Calculation 4685 are practical or worthwhile test conditions. The assumptions of the calculations are conservative in that they maximize the end result. Replication testing would require altering valve logic and tutbine punp controls by tenporary modification in order to achieve the configurations modeled in Reference 3 and induce the conditions of the calculation. The risk to safety-related conponents and systems by such alterations, in order to perform the testing, do not appear to justify its use. Additionally, static testing systems are available, which have been accepted by the hTC, to test MOV switch settings. Fermi 2 will conply with the requirements of IE Bulletin Item C by using MOVATS Inc.
Enclosure 1 IGC-87-0095 Page 5 Recommendation for using MOVATS to comply with IE Bulletin 85-03 requirements is contained in both References 6 aM 7. As this system has been fully evaluated by the NRR's Engineering Technology Division, no explanation of the MOVATS technique or capabilities will be discussed in this submittal. Detroit Edison enphasizes that the testing performed against the calculated dP's is done in a i conservative manner. As stated, the calculation method in Design Calculation 4685 is conservative in that it maximizes the results.
The dP's were provided to MOVATS to determine a thrust equivalent, 90% j probability margin, and 90% confidence margin, plus an error margin l l for each selected valve's opening and closing targets. Due to significant data scatter in the MOVATS data base from field testing, the margins added can be very large. For example: for testing MOV E4150F0ll, observed during inspection (Reference 6), the opening i target thrust is 12,245 lbs. However, the calculated thrust ,
equivalent is only 5,209 lbs.; this represents a 135% margin. 1
)
MOVATS testing presents fewer equipment and personnel risks than )
replicated dP testing. In addition it also provides greater )
precision, repeatability of the test corditions, and imnediate '
I retesting to check adjustments. For these reasons, Fermi 2 has chosen to apply MOVATS testing to the 33 selected valves required for the Bulletin response. Testing of valves has been conpleted on ten (10) of the thirty-three (33) selected valves. The test program for the remaining twenty-three (23) valves will be completed by the end of the the Spring 1988 ILRT Outage. Data submittal of the testa results will be provided by a supplemental report no later than 90 days after restart from the ILRT Outage.
Reference 9, Attachnent E.8, reported overall success with the testing of ten (10) MOV's. These ten (10) MOV's are identified in Ibte 3 on 1 Table 1. Ibte 4 on Table 1 identifies valve E4150F079, and Note 5 identifies valve E5150F008, both of which were discussed in the Reference 9 attachnent. Ibte 6 identifies three (3) MOV's fourd with an overthrust condition which was identified and corrected under MOVATS testing that has been conpleted to date. Ibtes 7 through 11 of Table 1 provide additional information.
MOV's E4150F079 and E5150F008 were discussed in the attachnent to Reference 9. As discussed under Item b of this enclosure MOV E5150F012 represents a like situation as that originally found with MOV E5150F008. The notor repimenent performed on MOV E4150F079 was based on an Engineering judgenent to expedite restoration of the valve's operability. Concurrence was obtained from Limitorque to use the large notor with a higher Torque Switch Setting which ha3 resulted from valve ILRT. This eliminated a potential notor stall problem without requiring repetition of the ILRT on the valve.
As detailed in Enclosure 2, the overthrust condition for MOV E4150F0ll was corrected by repacking the valve and reducing the Torque Switch 1
1
lj
,, Enclosure 1
~ NRC-87-0095 Page 6 1
^ Setting to an as-left value which results in ' total notor-operator ]
' thrust less than the. operator rating. The other two (2) MOV's were i corrected.in a similar manner. j J
Also, as reported in Reference 9, the opening torque switches were .
adjusted such that open Torque Switch Settings now meet the IE. 1 Bulletin 85-03 meeptance criteria.for the. ten (10) MOV's tested.
However, as previously discussed, the opening torque switches are bypassed to inhibit their function during the high dP portion of.the stroke. This ensures that valve ' opening will occur under high dP conditions for. the 23 untested MOV's. With the incorporation of limit ;
switch position trips for valve backseating, the lesser Torque Switch i Settings are no longer critical, and the open Torque Switch Settings J of the remaining twenty-three (23) MOV's'.will be raised during MOVATS .
testing.
The ten (10) MOV's selected represent a worst-case selection of the i thirty-three (33) MOV's in the Fermi 2 IE Bulletin response program. l Based on the success of MOVATS test conducted on these initial ten I (10) MOV's Detroit Edison is confident that all thirty-three-~(33) ;
MOV's can demonstrate performance suitable to meet the TE Bulletin 1 85-03 acceptance criteria. I l
l l
l 0
t I
Enclosure 1 PEC-87-0095 Page 7 TE BULLETIN 85-03 I'IM4 D 1
Prepare or revise procedures to ensure that correct switch settings !
are determined and maintained throughout the life of the plant. '
Ensure that applicable industry recommendations are considered in the preparation of these procedures.
DETROTT EDISON RESPONSE TO TE BUIJEI'IN 85-03 I'191 D Fermi 2 Nuclear Engineering (NE) will provide program control and direction to the Nuclear Production (NP) Maintenance department for required testing. Details of each valve and actuator design, switch settings, functions, acceptance criteria, trended data and design base l
documentation will be tracked by this tabulation. Fermi 2 NP Maintenance and Engineering already has procedures in place for i controlling switch setting and field testing of MOV's, including operational dynamic testing.
To provide enhanced engineering capability, and in response to the critique of Reference 6, training of Detroit Edison personnel on the MOVATS system and the data (signature) analysis is being obtained.
, Several engineers, currently assigned responsibility for the test I program and Bulletin response, will receive training prior to any additional valve testing. Maintenance technicians will receive training on the use of the MOVATS 2150 test system prior to the LLRT outage which is schedule for Spring 1988. MOVATS has been contracted to test and report on all thirty-three (33) selected valves of the Fermi 2 IE Bulletin 85-03 response. This will provide Fermi 2 personnel sufficient experience to continue the correct and accurate application of the MOVATS technique. ,
1 An administrative procedure to provide the appropriate dircction and )
establish formal interfacing requirements between the current NE and NP procedures is being developed. This effort will also be coupletEd by the end of the 1988 LLRT Outage. This document will assign responsibility and provide the necessary interfaces between NE and IP departments for the future conduct of the program. Until the IE Bulletin 85-03 testing and reporting is conplete, a task force has been established with NE and IP participation, which is chaired by a responsible NE staff engineer also assigned as the IE Bulletin 85-03 response coordinator. This task force ensures close working contact a between NE and NP on the required valve testing. It will also develop I and test the necessary administrative interfaces and program q requirements using the thirty-three (33) selecta3 valves as the case j study. j In summary, the action commitments including those acted previously are: .
- _.-_-_ D
.. Enclosure 1-13C-87-0095 l Page 8 l
l l
- 1. Complete dP calculations for seven (7) additional MOV's by the end l of the Spring 1988 ILRT Outage. I I
- 2. Replace the motor operator on E5150F012 during Spring 1988 LLRT .l Outage; )
- 3. Backseat limit switch position confirmation during MOVATS testing of the remaining twenty-three (23) MOV's; 1
- 4. Train engineers in signature analysis;
- 5. Train maintenance technicians on test system;
- 6. Revise NB 5.6, and revise appropriate maintenance instructions, as necessary;
- 7. Testing of the remaining twenty-three (23) MOP's;
- 8. . Establish permanent training program for engineering requirements and maintenance training requirements, and;
- 9. Establish MOV diagnostic test program for thirty-three (33) selected valves as part of the Fermi 2 ISI Program.
Conpletion of these action commitments will be reported in the supplemental report following the LLRT Outage.
Finally, using the initial testing of the selected valves as a baseline, NE will develop acceptance criteria and/or guidelines for predictive identification of MOV problems. One suggested method is to conpare subsequent FCC motor signature to the conbined ICC motor and valve actuator signature profiles initially recorded. This and any other methods will be evaluated and reported on in the supplemental report.
)
Enclosure 2 NBC-87-0095 Page 1 {
1 l
l FOLLOWUP ON INSPECTION REPORT NO. 50-341/87035 (DRS)
IE Inspection Report 87-035 amongst other things discussed some of the MOVATS testing that was perfomed at Fermi 2. Within the Inspection Report, Item 3 paragraph a, Test Observation a couple of incorrect statements were made concerning testing of MOV E4150F0ll:
Statement 1) That "as-found open thrust (14740 lbs) did not meet the l target thrust in the static condition (25593 lbs) ."
Correction 1) The open-direction target thrust is 12, 245 lbs; this )
is under the as-found thrust, therefore this MOV passed the target thrust test.
Statement 2) That "the open target thrust desired on this valve slightly exceeds the rating of the motor operator."
Correction 2) The rating of the EMB-O motor operator is 24,000 lbs.,
well above the open target thrust of 12,245 lbs.
Statenent 3) That "In order to neet the target thrust, the as-left open torque switch setting was raised."
Correction 3) In fact, the open torque switch setting was lowered.
The initial setting was >2.75 of 3.00 (maxinum limiter plat allowable setting). The resulting total thrust at this setting was >30,000 lbs which is an overthrust i
condition relative to the operator rating. The valve was repacked, ard then the Torque Switch Setting was reduced to 1.5+. The Torque Switch Setting was subsequently raised to an as-left open Torque Switch Setting of 2.2+ during post-maintenance and for final MOVATS testing. The as-left Torque Switch Setting 1 (2.2+) reduced the total thrust below the operator 1 rating to resolve the overthrust cordition. {
These corrections will clarify the test results reported for valve E4150F0ll to correct the possible misinterpretations of the Fermi 2 testing to date, and to address the concerns expressed about Fermi 2 response to IE Bulletin 85-03. As shown by this example, in addition I to the report, Item E.8, in lotter Reference 9, Fermi 2's MOV test l program is progressing better than reported by Reference 6. Detroit 1 l Edison will ensure proper communication of the tests, problems I
observed by the MOV test program and corrective measures taken. Fermi 2's engineers are working to ensure all problems identified by the MOV test program are resolved. Emphasis has been placed on achieving and maintaining MOV configurations and Torque Switch Settings in compliance with the design bases and IE Bulletin 85-03 requirements.
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. Table 1 Notes imC-87-0095 Page 1 i
TABLE 1
- 1. Does not perform an active, safety-related valve function, extremely low probability of changing position; maximum dP replicate testing not required per NEDC-31322 (Reference 3) . :
i
- 2. Functions to close only for isolation of line break; dP replicate testing is not required per IE Bulletin 85-03 (Reference 2) .
- 3. MOV tested by MOVATS, Inc. during Fermi 2 Outage 87-06.
- 4. MOV passed IEB 85-03 testing; motor replaced with larger size due to an increased close Torque Switch Setting to neet LLRT. Valve to be reworked and close Torque Switch Setting to be reduced during the Spring 1908 LLRT Outage.
- 5. MOV passed IEB 85-03 testing; target thrust exceeded operator I l rating, a larger motor-operator assembly was installed and I retested to pass IEB 85-03 criteria.
l
- 6. Torque Switch Settings found such that MOV operating in overthrust conditions; MOV reworked and Torque Switch Settings reduced to eliminate overthrust, MOV passed IEB 85-03 testing.
- 7. 107R50, Appendix J valve.
- 8. Actual Torque Switch Settings as documented in the Fermi 2 post-maintenance MOV testing procedure, MI-E0043. Recommended Torque Switch Settings provided by valve vendors after review of maximum calculated differential pressures from Design Calculation 4685.
- 9. MOV has no vendor recommended Torque Switch Settings; Torque Switch Settings determined by startup testing. Actual settings may vary depending upon maintenance performed.
- 10. Calculated dP's were not provided by Table 1 of Reference 4. A separate calculation to determine the IEB 85-03 dP values will be completed by Decenber 31, 1987.
- 11. MOV's for which the original specified dP is the design -line pressure.
NA = Not applicable, value applied only to the required saf ety-relates function.
_ - _ - - _ _ _ ._- -_ -_ _ _ _ _ _ _ _ _ _ _ - _ _ . - . _ __ _ - __