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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:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML20234C9511987-05-29029 May 1987 Forwards Final Technical Assistance Rept Covering Insp Performed on Mar-May 1987.Work Under Task Order 007 for FIN A-3550 Complete ML20101U7921982-01-20020 January 1982 Forwards Evaluation of Util Approach to Predicting Torque Loads for Facility Valves by Establishing Inlet Pressure to Valve at Various Positions,Per 811202 Audit Meeting.Valves Capable of Closing If Stated Provisions Accomplished ML20129J5331981-06-16016 June 1981 Forwards Review of Facility Emergency Plan ML20129J5191981-06-0101 June 1981 Forwards Working Paper for Facility Emergency Plan Evaluation 1987-05-29
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Upton. Long Island, New York 11973 (516)282x 2863
' Department of Nuclear Energy FTS 666' t.
Jari.uary 20, 1982 Ms. Mary Haughey Equipment Qualification Branch.
- U.S. Nucler Regulatory Commissi']n Wasington, D.C. 20555 D'ea r _ Ma ry :
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v Brookhaven National Laboratory (BNL) has reviewed the Fermi 2 purge and vent valve operability demonstration information submitted in letters and presented 'at the December 2,1981 audit meeting.
Based on the information available, BNL's Engineering Analysis and Human Factors Group concludes that Detroit Edison can demonstrate that the subject isolation valves are capable of closure under the accident conditions post-ulated (by the licensee) provided the following is accomplished:
- 1. All valves are to be oriented so that the flat sides of the discs face the LOCA flow. -
2.- Applicable valves are to be oriented so that their shafts are "in-plane" with the plane of their associated upstream elbow.
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- 3. A maximum allowable stroke time must be established for each valve for the " inservice test" conditions, i.e., no-load stroke timing.
The maxirrum allowable times established must be low enough to assure that the loads used in the stress analysis presented are not ex'-
ceeded.
'In response to your request concerning time comparisons, Attachment 1 is" presented.
Sincerely yours, ohk DR DOC -
PDR Thomas J. Restivo Engineering Analysis and $
Human Factors Group TJR:sd attachment cc.: R. Bari wo/att.
R. Ha11 W. Kato wo/att.
W. Luckas B. Miller e_
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1.0 REFERENCES
A. Detroit Edison (DE) letter #EF2-55,538 dated November 18, 1981.
B. . Meeting " Purge Valve Audit" at Detroit Edison's Fermi 2 site on December 2, 1981. ,,
C. Wyle Laboratories Report, 55210 - 18.0" Jamesbury Valve Test '(shown to staff at audit meeting).
D. Allis Chalmers test report VER-0209 dated December 17, 1979.
E. .Enrico Fermi Atomic Power Plant Unit 2, Final Safety Analysis Re-port, Figure 6.2-11 " Recirculation Line Break - Primary-Containment .
Ini,tial Pressure Transient" (handout at audit meeting).
F. Jamesbury Corporation letter dated November 12, 1981, B.C. Zannini
- -Janesbury to J. Green - Detroit Edison (handout at audit meeting).
" Aerodynamic Model Tests on Butterfly Valves," by Dr. Ing. C. Keller
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and Dr. Ing. F. Salzmann, published in ESCHER - Wyss News, Volume IX, No.1, January March 1936.
H. " Tests on Streamlined Butterfly Valves," by H. Netsch and F. Schulz published in The Engineers Digest, Volume II No. 8, August 1950 (From Maschinenbau und Warmewirtschaft, Volume 4, No. 9, September 1949). .
I. " Supportive Data Relating to Torque Coefficient Selection for
.Jamesbury Wafer-Sphere Valve with 90* Elbow Directly Upstream of Valve" (handout at audit meeting).
J. Allis Chalmers letter, April 30, 1981. R.H. Zeiders-(AC) to M..
Haughey' (NRC):
Subject:
Butterfly valves for ' containment isolation,
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'n 1-Allis Chalmers Valve Division Tests.
Detroit Edison letter EF?-55,980 dated January 4,1981' (with attach-
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ments: a) " Combined' Loading Stress Analysis on Shaft for Purge Valves" b) " Seismic Qualification of 6" Purge Valve; based on Report JHA-76-34'(PI-2406)." .
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2.0 EVALUATION Detroit Edison's/Jamesbury's approach to predicting torque loads for Fermi 2's valves was to establish the inlet pressure to the valve at the var-ious valve positions from 90' (full open) to O' (full closed). Delay time (LOCA initiate to start of stroke), closure time under load (based on direc- -
' tion of net torque) and containment response (worse-case) are accounted for in their approach.
Based on the information available, BNL's evaluation is as follows:
The drywell pressure response curve in Reference E was given as the de-
. sign condition for which operability demonstration of all purge and vent iso- ~
lation valves (drywell and wetwell) is based. During the audit (Reference E)
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the ifcensee confirmed that this was the worse-case accident (highest rate of
-pressure increase) condition. The wetwell response also shown in Reference E is shown to be far less severe relative to valve loads.
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ok- . Dynamic torque coefficients (C T ) used for the stress analysis of the Janesbury valves in Fermi 2 stem from an 18.0" Jamesbury valve test program conducted by Wyle Laboratories and reported in Reference C. Pressure and valve closure history data _ from this test was used in con,iuriction with data
-from an actuator - solenoid valve assembly vent test (same type used on test valve at Wyle) to establish Cy values at the various disc angles.
Based on Jamesbury's briefing at the audit meeting and information con-
- tained in submittal letters, the following can be summarized:
- -The test setup used at Wyle was. basically a straight pipe approach flow configuratrion.
- The Wyle test valve was installed and tested only with the discs flat side facing the flow.
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\j - The inlet test-pressure during the ifyle tests'was higher at all disc angles than the drywell pressure profile given in Reference E.
- The 18.0"' test valve at Wyle was of the same design (Wafer Sphere) as !
the Fermi 2 valves. The aspect ratio of the 18.0", 20.0", and 24.0" ,
were said to be the same.
- _The operability case assumed in the load analysis is that one of the two in-series valves is failed in the full open (90') position.,
Jamesbury assumes.a.150% increase in the dynamic torque coef ficients developed from Wyle Tests to account for upstream piping elbow af- --
, fects.-
The test setup used at Wyle does not provide data to establish C T valves based on non-uniform approach flow conditions. Jamesbury has attempted to justify their 150% assumption by comparing their valves to the Allis Chalmers valves which were tested with elbow configurations as reported in Re-
'ference D. Jamesbury's comparisons shown in Reference I were on the basis of equivalent aspect ratios (t/D) where the Jamesbury CT values are shown to be significantly higher than the Allis Chalmers CT values. "
Jamesbury's comparison ofT C ' for their design to Allis Chalmer's CT 's on the basis of equivalent aspect ratios alone is inappropriate, particularly based on their approach to determining loads (determining con-tainment pressure vs. disc angle). The comparison does not reflect disc shape differences between the two designs. Information contained in Reference G.
Figure 3, indicate that discs having approximately the same aspect ratios but different shapes can have very different coefficients at given disc angles.
Some differences were significantly more than were indicated in the Jamesbury
- Allis Chalmers comparisons (Reference I).
For those valve installations with an " elbow upstream - shaft oriented out-of-plane configuration," disc closure rotation direction must also be con- g sidered when predicting dynamic torques. Allis Chalmer's test program indi-cated that closure rotation direction would significantly influence torque de-veloped. This aspect was not reported in Reference D, but was made known in Reference J. Jamesbury's analysis has not considered this aspect for the Fermi 2 valves.
Affect on dynamic torque due to flow pattern o.ff of an associated in-series upstream valves had not been addressed by D.E. in their evaluation.
Separation distances between each in-series valve pairs was observed (during walk-around inspection) to be small. These distances are nuch less than the 15D used in the Instrument Society of America's (ISA) Standard S39.4 for a similar configuration.
BNL believes that in the case of the Fermi 2 valves, elbows (where ap '
plicable) are in such close proximity to both of the in-series valves, the flow pattern from the elbow should provide the predominant affect on the ap-proach flow pattern as it affects dynamic torque. DE's 150% increase in h straight pipe established CT's to account for the upstream elbow effect is considered conservative for the valve to valve effect.
NOTE: Test results reported in Reference G (Figure 12) indicate that the af fect to increase dynamic torque developed in a downstream butterfly valve due to flow distribution off of a modulating upstream butterfly (close proximity) is minor at large angles of upstream valve opening (Figure 12 uses 0* as full open). At smaller upstream valve opening angles, the affect is to significantly reduce the dynamic torque developed in the downstream valve.
Detroit Edison has indicated that they plan to re-orient (where neces- ~
sary) the subject . isolation valves as follows:
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- a. Flat face of disc to face LOCA flow (This was presented at audit meeting, Reference B).
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b.- Applicable valves-are to be re-oriented so that their shaf ts are "in-plane" with the plane of their associated upstream elbow (Re-ference I).
NOTE: Based on information available from submittals and from discus-sions with some butterfly valve manufacturers, the industry's general belief is that the "in-plane shaft-upstream elbow" configuration is equivalent to the ..
" straight upstream piping" configuration with respect to dynamic torques. No documentation (test or analytical) has-been made available by manufacturers or licensee's nor does BNL know of any documentation to support the industry's belief. At this time, BNL can only offer its opinion that the maqnitudes of the dynamic torques are likely to be equivalent for the aforementioned on-figurations.
Based on implementation of these plans, BNL finds that Detroit Edison can demonstrate that the subject valves are capable of closure against the accident condition (LOCA and seismic) postulated.
m NOTE: A maximum allowable stroke time must also be established for each Q valve for the " Inservice Test" conditions i.e., no-load stroke timing. The maximum allowable times must be _ low enough to assure that the loads used in the stress analysis are not exceeded.
Table 'l _ summarizes the torque and pressure loads used in the stress analysis as~ compared to the predicted torque loads at 0* and 90" and maximum ,
containment pressure potential (drywell and wetwell). Predicted torques at 90* are based on 150% of straight pipe determined Cy's and torques at 0* are from seating torque curves presented in Reference A.
. As can be'seen from Table 1, the torque values used in the stress an-alysis are significantly higher than the predicted torques at 0* and 90 for the 6.0",10.0", and 20.0" val ves.
The stress analysis' torque for the 24.0" valves ~is. shown to be lower than the predicted torque at 90*. The piping installations of_the 24.0"
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C tvalves are considered straight pipe (i.e. uniform approach flow) configured, and as such, the Jamesbury determined straight pipe C T 's would apply. The 3440 ft. Ibs. which is the straight pipe predicted torque times 1507. should be considered conservative for the 24.0" valves.
The pressure loads'used for the stress analysis are also shown to be
, conservative. Table I shows that'the pressure loading used in the stress analysis is higher for all valve sizes than the maximum containment pressures predicted. In fact, the pressures used for the 6.0",10.0" and 20.0" valve are more. than twice the maximum pressures predicted.
The licensee has shown that the stress values predicted are within the design allowables specified. Seismic loads have been included in the anal- -
ysis.
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In Reference A, Detroit Edison presented the torque output curves for the various air-operated actuators used on the Fermi 2 valves. Based on these curves, it can be concluded that the operators can provide the torques neces-sary to close and seat the valves while operating from their 90" (full open) initial position. These same curves indicate that the operator torque ratings are not exceeded.
Detroit Edison also (Reference A) provided information concerning sizing '~
of the motor operator for the 24.0" valve. The information demonstrated that the operators are sized to stroke the valves under the leads postulated at 80%
reduced voltage.
Table 1 STRESS TOROUE PREDICTED STRESS MAXIMUM ACCIDENT ANALY. (LOCA) ANALY. PRESSURE SIZE LOCATION T0 ROUE O 90" PRESS. DRYWELL WETWELL VALVE ID in. DW or WW FT-LBS (FT-LBS (FT-LBS) (PSIG) (PSIG) (PSIG)
V4-2061 V4-2063 6.0 6.0 WW WW 315 315 160 160 80
.30 150 150 25 25 g
V4-2060 10.0 DW /30 690 345 150 58 --
VR3-3014 20.0 WW 2300 1700 2060 62 --
25 VR3-3016 20.0 WW 2300 1700 2060 62 --
25 VR3-3013 20.0 WW 2300 1700 2060 62 --
25 VR3-3015 20.0 WW 2300 1700 2060 62 --
25 VR3-3012 24.0 DW 3200 3200 3440 62 58 --
VR3-3023 24.0 DW 3200 3200 3440 62 58 --
VR3-3011 24.0 DW 3200 3200 3440 62 58 --
VR3-3024 24.0 DW 3200 3200 3440 62 58 --
VR3-3019 6.0 WW 260 160 80 62 --
25 VR3-3026 6.0 DW 260 160 80 62 58 --
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- The_ maximum potential drywell accident pressure is approximately 58 psig and the wetwell's approximately 25 psig. Both are less than the 68.5 psig AP
. capability based on TD . Valve closure time from a valve assembly structural
, integrity. standpoint does not appear to be critical for the 6.0" valves.
For 10.0" Valves a.UgecurveD{ elbow)whereCT = 0.0213
- b. 00 = 1000 in
- c. TD = 730 ft-lbs.
= 34.3 psi AP = 0.02 x 1000 The 10.0" valve is attached to the drywell. The drywell reaches 34.3 psic in approximately 2.0 sec from LOCA initiate based on the drywell response in Figure 1 (Reference A). This time is approximately three times the 0.65 o sec shown by the licensee in Figure 6 (Reference A).
In that the AP capability is shown to be less than the maximun drywell potential, it would appear that a limitation is required on the valve closure time allowable during the inservice tests.
For 20.0" Valves
- a. UgecurveC{ elbow)whereCT = 0.0125
- b. D3 = 8000 in
- c. TD = 2300 ft-lbs.
= 23.0 psig
_.AP = 0.0125 x 8000 l)
V The 20.0" valves are connected to the wetwell. .The maximum potenti '
wetwell pressure is approximately 25 psig-(Reference E) which is slightly higher than the AP capability of 23 psig which is based on TD = 2300 ft-lbs.
Reference E shows that the wetwell-would require over 20 seconds to reach 23 psig. This compared to the 1.3 second time shown in Figure 7 (Reference A).
Valve closure. tine from a valve assembly structural standpoint does not appear to. be critical for the 20.0" valves'.
For 24.0" Valves-
- a. ~Use curve A'(3 straight pipe), where CT = 0.009
.b. -D3 =.13824 in
- c. TO = 3200 ft-lbs. >
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AP = 0.009 3824
= 25.7 psig 9
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The 24.0" valves are connected to the drywell. Figure 1 (Reference A) shows that the drywell would require approximately one second to reach 25 psig. Figure 8 (CTQ = A) (Reference A) shows valve closure in 1.25 seconds, where the drywell pressure reaches approximately 27 psig. This is higher than
'the 25.7 psi AP capability (based on TD ). As previously mentioned, the CT value assumed was the maximum value on Curve A (Figure 4) 1.e., at 90" (full open). By using a CT value of 0.005 which is at 75* (less at lower angles) 1 "-
a AP capability (based on dT ) of 46.3 psi is calculated. Fiqure 1 (Reference A) shows that the drywell would require approximately 4 seconds to reach 46 psig. This can be compared to the 1.25 second closure time shown by the licensee for the 24.0" valves.
In that the AP capability is shown to be less than the maximum drywell potential, it would appear that a limitation is required on the valve closure time allowable during the inservice tests.
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