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
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I Robert McKeon Assistant Vice Presidient and anagw, Operations MI -- ' e N orth Dixie Hwy -
Edison n%=""** 1rme October 2,1995 -
NRC-95-0105 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
References:
- 1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
- 2) Detroit Edison letter to NRC, " Request for Discretionary -
Enforcement," NRC-95-0091, dated September 29,1995
Subject:
Revision to Request for Discretionary Enforcement As discussed with Mr. T. Colburn on September 30,1995, this letter is a revision to ,
Reference 2 which is being submitted to document that additional auto-connected I loads are affected by the incomplete surveillance requirements. These additional l loads do not invalidate the reasons provided in Reference 2 for Discretionary l Enforcement. The revised enclosure and load list from Reference 2 are included with this letter. The enclosure is marked to indicate changes in the discussion provided earlier.
The purpose of this letter is to request discretionary enforcement with respect to the requirements of Technical Specification (TS) Action statement 3.8.1.1.d "A.C.
Sources - Operating" and TS 4.0.3 " Failure to Perform a Surveillance Requirement Within the Allowed Surveillance Interval," which requires shutdown within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after the allowed TS 4.0.3 surveillance performance extension. This shutdown is required when both separate and independent onsite A.C. electrical power sources are inoperable due to potentially inadequate surveillance test performance. Detroit Edison is submitting this request to obtain deferral from limited aspects of surveillance requirements which have not been adequately completed so that surveillance testing can be completed for the affected components in an orderly manner. 1 At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on September 28,1995, all four diesel genen. tors were declared inoperable due to missed Technical Specification (TS) surveillance requirements due to incomplete control switch and relay contact position verification during surveillance testing. To conduct the required surveillance testing, all four diesel v
n-.. .
- \l 9510060201 951002- 1 PDR ADOCK 05000341 3 P _ .a -- _PDR_ ..
. -. . .- - ..- - _ . . - - - ~ . - ..- -. - - - . . .. .
i USNRC
~*
. October 2,~ 1995 ,
j generators will be required to be removed from service in a sequential manner so that i the associated output breaker closure switch can be manipulated. In addition, various L emergency core cooling system support components (i.e., ECCS room coolers) will j need to be taken out of service to perform verification that the load sequencing control relay contacts are operating properly. In order to ensure a well planned testing
- program and to ensure that the proper plant conditions exist for removing equipment from service, longer than the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed by Technical Specification 4.0.3 is required.
f Based on successful operation of the diesel generators during the last refueling l outage and the monthly surveillance testing, and the industry and Fermi 2 history of high reliability for the associated control switches and control relays for the functions .
I
- which have not been fully verified, Detroit Edison is confident that the diesel generators are fully functional as tested.
} Detroit Edison is requesting that the completion of the remainder of the required
] surveillance testing be deferred to the next plant outage. The enforcement discretion is requested to begin at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on September 29,1995, and will remain in effect j until an emergency Technical Specification change is approved. Detroit Edison will submit the emergency Technical Specification change request for approval by Tuesday, October 3,1995. Detroit Edison will develop and perform necessary tests,
) including evaluating whether performing on-line testing is consistent with prudent
- risk management. If this request is granted, then for the period that this enforcement i discretion is in place and to avoid strictly compliance related operational restraints, the diesel generators will be declared administratively operable.
i If there are any questions related to this response, please contact Joe Conen,
- Compliance Supervisor at (313) 586-1960.
I Sincerely, N W Enclosure
! cc: T. G. Colburn 1
H. J. Miller M. P. Phillips
! A. Vegel
. Region III 4
=
4 Enclosure to NRC-95-0105 Page1
- 1. Requirements for Which Reliefis Reauested At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on September 28,1995, all four diesel generators were declared inoperable due to missed Technical Specification (TS) surveillance requirements due to incomplete control switch and relay contact position verification during surveillance testing.
The potentially affected contacts fall into two general categories, the diesel generator output breaker re-closure circuitry that is initiated following a load shed, and the emergency 480-volt load sequencer control relay contacts.
Diesel Generator Output Breaker Re-Closure Circuitry TS Surveillance 4.3.3.2," Emergency Core Cooling System Actuation Instrumentation," requires verifying that logic system functional tests and simulated automatic operation of all channels shall be performed at least once per 18 months. Loss of power (4160-volt bus loss of voltage or degraded voltage)is one of the functions that is tested as part of this surveillance requirement. Failure to meet the minimum operable channels results in entry to TS 3.8.1.1 for onsite power system inoperabilty. The associated surveillance test procedure involves tripping of the output breaker and verifies that the associated output breakers trip, initiating a load shed followed by the re-closure of the associated output breaker. The associated bus load shedding logic contacts close to re-energize the output breaker closing coil permissive relay (relay 52XX). Closure of one of the 52XX relay contacts, coincident with other breaker closure signals, results in closure of the breaker. However, this testing does not verify that the parallel control room breaker closure (CMC) switch contacts, or the 52XX relay seal- ;
l in contacts, are not responsible for the re-energizing of the 52XX relay.
The surveillance test procedure has the CMC switch in the required l position which should result in the associated CMC switch contact )
being open, and the 52XX relay dropping out, however, there is no positive verification that these contacts are not in fact closed (i.e.,
stuck). Refer to the attached sketch for a schematic representation.
Emergency 480-volt Load Sequencer Control Relay Contacts TS Surveillances 4.8.1.1.2.e.4.b and 4.8.1.1.2.e.6.b require verifying that the diesel generator starts on the auto-start signal and energizes the emergency busses with automatically connected loads through the load sequencer. The associated surveillance test procedure involves
Enclosure to
,NRC-95-0105 Page 2 verification that the auto-connected loads are running on the 480-volt emergency busses after the diesels automatically start. However, this .
testing does not verify that the automatic digital load sequencer system I sequencing relays are responsible for actually closing the associated loads. There are parallel control switch contacts and control relay contacts that could provide for immediate connection of the loads to the 480-volt emergency bus after diesel generator starting without a closure signal from the load sequencer system. The sequence of surveillance testing establishes the conditions to open these parallel contacts, but does not include positive verification that the parallel contacts are actually open. Refer to the attached sketch for a sample l schematic representation.
i Failure to provide positive verification that the proper logic path has provided the energization of the relay coils as described above results in the diesel generators being administratively declared inoperable in accordance with TS 3.8.1.1. TS 3.8.1.1 requires two separate and t independent onsite A.C. electrical power sources, Division I and Division [
II, each consisting of two emergency diesel generators.
TS 3.8.1.1, Action d, states that with both of the required onsite A.C. l electrical power division inoperable, restore at least one of the above required inoperable divisions to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at ;
least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and cold shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. In accordance with the provisions of TS 4.0.3, the action requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowed outage time limits of the ,
Action requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
To conduct the required surveillance testing, all four diesel generators will be required to be removed from service in a sequential manner so that the associated output breaker closure switch can be manipulated. In addition, various emergency core cooling system support components (such as essential room coolers), will need to be taken out of service to perform verification that the load sequencing control relay contacts are operating properly. In order to ensure a well planned testing program and to ensure that the proper plant conditions exist for removing equipment from ,
service, longer than the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowed by Technical Specification 4.0.3 is required.
Therefore, Detroit Edison is requesting relief from the requirements of TS !
3.8.1.1.d and TS 4.0.3 with respect to the diesel generator output breaker re-closure circuitry and the 480-volt emergency bus load sequencers.
i 1
i Enclosure to l
' .NRC-95-0105 :
Page 3 Should the NRC determine not to grant this request for discretionary enforcement, a reactor shutdown will be required.
- 2. The Circumstances Surrounding the Situation. Including the Need for Prompt Action At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on September 28,1995, all four diesel generators were declared inoperable due to potentially inadequate surveillances for the diesel generator output breaker re-closure logic circuitry and the 480-volt emergency bus load sequencer control relay logic circuitry.
The existing surveillance test procedures do not provide positive verincation that the proper logic path has provided the energization of the relay coils associated with the diesel generator re-closure circuitry nor the 480-volt emergency bus load sequencer control relay logic circuitry.
Based on successful operation of the diesel generators during the last refueling outage and the monthly surveillance testing, and the industry and Fermi 2 history of high reliability for the associated control switches and control relays for the functions which have not been fully verified, Detroit l Edison is confident that the diesel generators are fully functional as tested.
Prompt NRC action is required so that orderly surveillance testing of the diesel generator output breaker control switch contacts and the 480-volt emergency bus load sequencer control relay contacts can be performed without an unnecessary shutdown. Forcing the plant into a shutdown transient to verify that there is not a control switch or relay contact failure that could hypothetically have masked problems during apparently successful surveillance testing, does not provide an increased safety margin.
- 3. Why the Situation Could Not Have Been Avoided Electrical surveillance overlap drawings were created as a result of Licensee Event Report (LER)94-003. An independent review was performed in conjunction with the development of these overlap drawings.
This review identified concerns of contact ambiguity with regard to certain portions of the diesel generator output breaker and 480-volt emergency bus load sequencer surveillance tests. These concerns were reviewed and found to be valid by Fermi 2 engineering personnel. The ambiguity determined that contacts in parallel with the contacts intended to be functionally tested are not verified to be open. This could hypothetically result in a false satisfactory test of the contact function. Therefore, this
- e Enclosure to
, ' ,NRC-95-0105 Page 4 -
situation is a result of the review to improve documentation of required -
, electrical system surveillance testing. This situation could not be avoided because Fermi 2. is aggressively reviewing and documenting overlap
- requirements and is conservatively assuming that hypothetical contact failures could mask otherwise apparently successful surveillance testing.
The surveillance testing sequence establishes the required conditions to j fully test these devices, however, this testing does not include sufficient verification steps to confirm all required contacts function as intended.
- 4. The Preliminary Evaluation of the Safety Sienificance and EnvironmentalImpact i.
Granting this proposed enforcement discretion would have no adverse l impact on the public health and safety. The testing deficiencies did not, j and would not, prevent the surveillance testing which has been performed
- from demonstrating that the emergency diesel generators are functional -
- and will perform the safety functions if needed. Therefore, Detroit Edison believes that there is no unreviewed safety question, no significant hazards 4 consideration or adverse consequences to the environment as a result of this enforcement discretion. This will be futher discussed in the i
amergency Technical Specification change that will be submitted with i- regard to this issue (refer to item 6 below).
For the testing deficiencies associated with the diesel generator output
- breaker logic, the function of the inadequately tested contact is not needed
- (function bypassed) when the output breaker CMC switch is in the OPEN
- position, the normal plant operations state. Further, any hypothetical j failure of the subject contacts could have gone undetected during the surveillance testing only if a parallel contact in the output breaker CMC
- switch or the 52XX relay had failed closed. If this had occurred, the output breaker would still function as needed because the 52XX relay '
i , would reset via the failed closed parallel contact (s) and provide the required breaker closing coil permissive logic.
For the inadequately tested load sequencer contacts, any hypothetical failure of the subject contacts could have gone undetected during the surveillance testing only if a parallel contact in the associated CMC
, control switch or control relay contact had failed closed. If this had i occurred, the associated load would still function as needed because the
- logic would be completed via the failed closed parallel contact (s) and the i
480-volt emergency bus loads would load onto the bus when the diesel breaker closes. In addition, since the surveillance testing did verify that the diesels were able to respond adequately to the connection of all loads, e
I Enclosure to NRC-95-0105 ,
'Page 5 any failure which had not been detected during previous testing has had no' impact on the function of the diesels.
In a worst case, highly improbable scenario, represented by concurrent . ,
failure of all of the incompletely tested contacts (up to 15 individual contacts on 15 separate loads for the worst case diesel generator), up to 185 hp of additional load would be immediately connected to that diesel generator when the diesel generator output breaker closes. . Refer to j Attachment No. I for a listing and description of the loads. Engineering evaluations have judged that the diesels are capable of accepting the :
simultaneous connection of all of the additional loads coincident with l other loads being sequenced onto an individual diesel generator when the i diesel output breaker closes. This evaluation is based on pre-operational l testing when a core spray pump and a residual heat removal pump were simultaneously loaded onto the diesel generator (approximately 800hp :
above normal sequenced loading). ;
i
- 5. Proposed Compensatory Actions Night orders are being issued that explain the nature of the inadequate !
surveillance requirements to heighten operator awareness to diesel generator loading response and control room switch manipulations.
Because the testing deficiencies do not impact the safety functions of the diesels, no further compensatory action is necessary.
- 6. Justification for the Duration of the Reauest Detroit Edison is submitting this request to obtain deferral from limited aspects of surveillance requirements for the diesel generator output breaker re-closure logic circuitry and the 480-volt emergency bus load sequencer control relay logic circuitry until the next plant outage. The enforcement discretion is requested to begin at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on September 29,1995, and will remain in effect until an emergency Technical Specification change is approved. Detroit Edison will submit the emergency Technical Specification change request for approval by Tuesday, October 3,1995.
Detroit Edison will develop and perform necessary tests, including evaluating whether performing on-line testing is consistent with prudent risk' management.
Furthermore, a preliminary look at probabilistic risk analysis shows that removal of some of the affected equipment from service during operation to complete the surveillance testing would increase the instantaneous core damage risk. Some example risk increases would be 72% for removing
l
.NRC-95-0105 Page 6.
l the Division I Non-Interruptable Air System (NIAS) or 57% for removing l the Diesel Generator 11 from service during operation to verify the j position of the associated impacted component contacts. j Based on successful operation of the diesel generators during the last refueling outage and the monthly surveillance testing, and the industry and Fermi 2 history of high reliability for the associated control switches and control relays for the functions which have not been fully verified, Detroit l Edison is confident that the diesel generators are fully functional as tested.
Therefore, for the period that this enforcement discretion is in place, to avoid strictly compliance related operational restraints, the diesel generators will be declared administratively operable with respect to the above described surveillance requirements. ,
- 7. Onsite Review Oreanization (OSRO) ADDroval On September 29,1995, the OSRO approved the justification and supporting documentation for this request for enforcement discretion.
OSRO approved the revision to this information on October 2,1995.
Attachment I to
,NRC-95-0105 Page1 TABLE NO.1 480-Volt Emergency Load Sequencer List l
LOAD DESCRIPTION LOAD l (Grouped by connected Diesel Generator) 480V MCC RATING (HP)
Drywell Cooling Fan #1 72B-3A 30.0 l RCIC & CSS Room Cooler 72B-3A 15.0 Div. I Control Air Compressor Room Cooler 72B-3A 5.0 Div. I Switchgear Room East ESS Cooler 72B-2B 5.0 Div. I Switchgear Room West ESS Cooler 72B-2B 5.0 )
Div. I Control Air Compressor 72B-3A 30.0 j Div. I Battery Charger Room Cooler 72B-2A 5.0 i Drywell Cooling Fan #2 72C-3A 30.0 Div. I Thermal Recombiner Cooling Unit 72C-3A 5.0 Div. I RHR Room Cooler 72C-3A 20.0 Div. I EECW Room Cooler 72C-3A 5.0 Div. I SGTS Room Cooler 72C-2A 3.0 Div. I CCHVAC Recirc/ Emergency Makeup Fan 72C-2A 20.0 Div.1CCHVAC Return Air Fan 72C-2A 25.0 Div. I CCHVAC Chill Water Pump 72C-2A 7.5 Div. I CCHVAC Supply Fan 72C-2A 40.0 Div. I A/C Equipment Room Cooling Unit 72C-2A 1.0 Div. I CCHVAC Chiller Compressor Oil Pump 72C-2A 0.25 Div. I CCHVAC Emergency Makeup Filter Heater 72C-2A 16.1 Cable Tray Cooling Fan 72C-2A 1.0 Drywell Cooling Fan #3 72E-5A 30.0 Div.11 Control Air Compressor Room Cooler 72E-5A 5.0 Div. II Core Spray Room Cooler 72E-5A 15.0 HPCI Room Cooler 72E-5A 7.5 Div. II Control Air Compressor 72E-5A 30.0 Drywell Cooling Fan #4 72F-4A 30.0 Div. II Switchgear Room East ESS Cooler 72F-2A 5.0 Div.11 Switchgear Room West ESS Cooler 72F-2A 5.0 Div. II EECW Room Cooler 72F-4A 5.0 Div.11 Thermal Recombiner Room Cooler 72F-4A 5.0 Div.11 RHR Room Cooler 72F-4A 20.0 Div. II SGTS Room Cooler 72F-5a 3.0 Div.11 CCHVAC Recirc/ Emergency Makeup Fan 72F-5A 20.0 Div.11 Battery Charger Room Cooler 72F-2A 2.0 Div.11 CCHVAC Chill Water Pump 72F-5A 7.5 Div. II A/C Equipment Room Cooling Unit 72F-5A 1.0 Div.11 CCHVAC Supply Fan 72F-5A 40.0 Div. II CCHVAC Return Air Fan 72F-5A 25.0 Div. Il CCHVAC Chiller Comp Oil Pump 72F-5A 0.25 Div. Il CCHVAC Em Makeup Filter Heater 72F-5A 16.1
> i
. 1
- l Attachment 1 to
,NRC-95-0105 l Page 2 i TABLE NO.1 480-Volt Emernency Load Secuencer List (Cont'd) 1 1
NOTE: 480V MCC's prefixed 72B are associated with Diesel Generator No. I1 480V MCC's prefixed 72C are associated with Diesel Generator No.12 l 480V MCC's prefixed 72E are associated with Diesel Generator No.13
, 480V MCC's prefixed 72F are associated with Diesel Generator No.14 4
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