Similar Documents at Fermi |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N4261999-10-25025 October 1999 Forwards Amend 17 to License DPR-9 & Safety Evaluation. Amend Revises TS by Deleting SR D.3.c,which Required Weekly Observation of Nitrogen Cover Gas Pressure within Sodium Storage Tanks Located in Sodium Building NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999 Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl NRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999 Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed ML20217P1661999-10-21021 October 1999 Forwards Insp Rept 50-341/99-17 on 990927-1005.No Violations Noted ML20217M0771999-10-19019 October 1999 Confirms Discussion Between GL Shear,M Mitchell,E Kosky, D Williams,B Rumins,D Harmon & W Rutenberg in Public Meeting on 990923.Purpose of Meeting Was to Discuss Current Status RP Program at Enrico Fermi 2 ML20217N9231999-10-15015 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40 ML20217E5671999-10-14014 October 1999 First Partial Response to FOIA Request for Documents.Records in App a Already Available in Pdr.App B Records Encl & Being Released in Entirety NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999 Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal ML20217D5331999-10-0707 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39 ML20217F5931999-10-0707 October 1999 Forwards Insp Rept 50-341/99-11 on 990724-0908.Two Violations Re Failure to Follow Procedures While Sampling Standby Liquid Control Tank & Wear Dosimetry Properly Being Treated as Noncited Violations ML20217B8261999-10-0404 October 1999 Forwards Summary of Decommissioning Insp Plan for Fy 2000. Plan Will Be Updated Annually & May Be Revised at Any Time Based Upon Future Insp Findings,Events & Resource Availability ML20212J8121999-10-0101 October 1999 Discusses Plant,Unit 2 Completion of Licensing Action for GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at Npps. Ack Efforts That Licensee Have Completed to Date in Preparing Plant for Y2K Transition ML20212K8881999-09-30030 September 1999 Refers to 990928 Meeting Conducted at Fermi Unit 2 to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff ML20217A3261999-09-30030 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38 NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations ML20212J8331999-09-27027 September 1999 Responds to Licensee 990924 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3/4.6.1.8.Ltr Documents 990923 Telcon with Util in Which NRC Orally Issued NOED ML20216G9791999-09-24024 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37 NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999 Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20216H3561999-09-23023 September 1999 Informs That During 990914 Telcon,L Sanders & M Bielby Made Arrangements with NRC to Inspect Licensed Operator Requalification Program at Fermi Nuclear Station for Week of 991129 Which Coincides with Util Regularly Scheduled Exam ML20216H4541999-09-23023 September 1999 Informs That During 990914 Telcon L Sanders & M Bielby Made Arrangements for Administration of Licensing Exams at Fermi Nuclear Station for Week of Jan 31,2000.NRC Will Make Exam Validation Visit to Facility During Week of Jan 10,2000 ML20212F3241999-09-20020 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36 NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999 Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public ML20217A9421999-09-0909 September 1999 Informs That NRC Plan to Conduct Addl Resident Insps Beyond Core Insp Program Over Next 6 Months to Assess Improvements in Areas of Procedural Compliance & Quality of Work. Historical Listing of Plant Issues Encl NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999 Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev ML20211Q0991999-09-0303 September 1999 Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999 Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999 Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d) ML20211G4951999-08-24024 August 1999 Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999 Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval IR 05000341/19990131999-08-19019 August 1999 Discusses Insp Rept 50-341/99-13 & OI Rept 3-98-039 Conducted Into Potential Misconduct of Operator Formerly Employed by De.Nrc Determined That Violation of NRC Regulations Occurred.Synopsis of IO Rept Encl NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999 Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation ML20211C0521999-08-17017 August 1999 Forwards Tables for Sections 3.6 & 3.7 of Draft Safety Evaluation of Proposed Conversion of Current TS to Improved Standard TS NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999 Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev ML20217E6181999-08-13013 August 1999 FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available IR 05000341/19990011999-08-10010 August 1999 Forwards Insp Rept 50-341/99-01 on 990619-0723 & Nov. Violation of Concern Because Operators Did Not Understand License Requirements & Placed Plant in Configuration Where EDG 11 Was Removed from Service IR 05000341/19990121999-08-0606 August 1999 Forwards Insp Rept 50-341/99-12 on 990712-0716.No Violations Noted.Insp Focused on Implementation of Plant Chemistry & Radiological Environ Monitoring Programs & Operation of post-accident Sampling Sys ML20211C4761999-08-0606 August 1999 Forwards Draft Safety Evaluation Re Proposed Conversion of Current TS to Improved Standard TS NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999 Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS ML20210N5451999-08-0303 August 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33 NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999 Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS ML20210J2121999-07-23023 July 1999 Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999 Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl ML20209H7211999-07-14014 July 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32 NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999 Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal ML20209F6571999-07-12012 July 1999 Forwards Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted.Weak Procedural Guidance,Communications Issues & Configuration Control Weaknessess Were Evident NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999 Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions ML20196J5511999-07-0202 July 1999 Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & DE Responses & 980729 for Fermi 2.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 as Result of Review of Responses ML20209C6141999-07-0101 July 1999 Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999 Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999 Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999 Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl ML20217N9231999-10-15015 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40 NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999 Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999 Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal ML20217D5331999-10-0707 October 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39 ML20217A3261999-09-30030 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38 NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations ML20216G9791999-09-24024 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37 NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999 Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys ML20212F3241999-09-20020 September 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36 NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999 Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999 Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999 Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld ML20211Q0991999-09-0303 September 1999 Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999 Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d) ML20211G4951999-08-24024 August 1999 Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999 Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999 Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999 Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev ML20217E6181999-08-13013 August 1999 FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999 Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS ML20210N5451999-08-0303 August 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33 NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999 Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999 Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl ML20209H7211999-07-14014 July 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32 NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999 Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999 Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions ML20209C6141999-07-0101 July 1999 Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0049, Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure Encl NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999 Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included ML20209C1081999-06-29029 June 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 30 NRC-99-0050, Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included1999-06-24024 June 1999 Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included NRC-99-0075, Forwards Operator License Renewal Application,Nrc Forms 398 & 396 for CR Effan,License SOP-30186-3.Encl Withheld1999-06-22022 June 1999 Forwards Operator License Renewal Application,Nrc Forms 398 & 396 for CR Effan,License SOP-30186-3.Encl Withheld ML20212J3861999-06-18018 June 1999 Forwards Rev 29 to Approved UFSAR LCR That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section) NRC-99-0047, Responds to NRC 990513 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Revised Design Calculation DC-5957, GL 96-06 Calculations, Encl1999-06-0909 June 1999 Responds to NRC 990513 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Revised Design Calculation DC-5957, GL 96-06 Calculations, Encl ML20195G2001999-06-0808 June 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 28 ML20195E7391999-06-0303 June 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 27 NRC-99-0046, Forwards Rev 6 to Fermi 2 ITS Submittal ,to Provide Remaining Responses to NRC RAI Re ITS Section 3.3, & Update ITS Submittal to Reflect Responses.Brief Abstract of Changes Contained in Attachment 11999-06-0202 June 1999 Forwards Rev 6 to Fermi 2 ITS Submittal ,to Provide Remaining Responses to NRC RAI Re ITS Section 3.3, & Update ITS Submittal to Reflect Responses.Brief Abstract of Changes Contained in Attachment 1 ML20207D9631999-05-26026 May 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section) ML20195B3381999-05-19019 May 1999 Forwards Rev 25 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section) NRC-99-0040, Requests NRC Approval of Revs to Weld Tables of Encl Relief Requests RR-A21,rev 1 & RR-A22,rev 1.Revs Do Not Impact Basis for Original Requests for Relief Because There Is No Change to Technical Basis or Proposed Alternative1999-05-14014 May 1999 Requests NRC Approval of Revs to Weld Tables of Encl Relief Requests RR-A21,rev 1 & RR-A22,rev 1.Revs Do Not Impact Basis for Original Requests for Relief Because There Is No Change to Technical Basis or Proposed Alternative NRC-99-0039, Requests Relief from ASME Section XI Requirement to Examine Essentially 100% of Selected Category B-J Pipe Welds,Per 10CFR50.55a(g)(5)(iii).Relief Request RR-A23,encl1999-05-14014 May 1999 Requests Relief from ASME Section XI Requirement to Examine Essentially 100% of Selected Category B-J Pipe Welds,Per 10CFR50.55a(g)(5)(iii).Relief Request RR-A23,encl NRC-99-0041, Requests Relief from ASME Section XI Requirements to Examine Essentially 100% of Accessible Category B-D Nozzle Welds,Per 10CFR50.55a(g)(5)(iii).Rev 1 to Relief Request RR-A6,encl1999-05-14014 May 1999 Requests Relief from ASME Section XI Requirements to Examine Essentially 100% of Accessible Category B-D Nozzle Welds,Per 10CFR50.55a(g)(5)(iii).Rev 1 to Relief Request RR-A6,encl NRC-99-0038, Requests Relief from ASME Section XI 1980 Requirement to Examine Essentially 100% If Category B-A RPV Shell Weld Lengths,Per 10CFR50.55a(g)(5)(iii)1999-05-14014 May 1999 Requests Relief from ASME Section XI 1980 Requirement to Examine Essentially 100% If Category B-A RPV Shell Weld Lengths,Per 10CFR50.55a(g)(5)(iii) NRC-99-0045, Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl1999-05-0707 May 1999 Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses1999-04-30030 April 1999 Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses NRC-99-0059, Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate1999-04-29029 April 1999 Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate ML20206E2941999-04-28028 April 1999 Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 24 NRC-99-0037, Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl1999-04-26026 April 1999 Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARNRC-90-0142, Forwards Revised Semiannual Fitness for Duty Rept,Consisting of Statement Re Percentage of Individuals Tested & Revised Graph,Per G Pirtle Request1990-09-0707 September 1990 Forwards Revised Semiannual Fitness for Duty Rept,Consisting of Statement Re Percentage of Individuals Tested & Revised Graph,Per G Pirtle Request NRC-90-0152, Forwards Rev 3 to Radiological Emergency Response Preparedness Plan.W/O Encl1990-09-0505 September 1990 Forwards Rev 3 to Radiological Emergency Response Preparedness Plan.W/O Encl NRC-90-0139, Responds to NRC Re Memorization of Immediate Operator Actions in Abnormal Operating Procedures (Aop). Definition of Immediate Action Under Review to Provide Mechanism for Consistent Application to All AOPs1990-08-31031 August 1990 Responds to NRC Re Memorization of Immediate Operator Actions in Abnormal Operating Procedures (Aop). Definition of Immediate Action Under Review to Provide Mechanism for Consistent Application to All AOPs NRC-90-0116, Forwards Semiannual Fitness for Duty Rept1990-08-29029 August 1990 Forwards Semiannual Fitness for Duty Rept NRC-90-0117, Forwards, Fermi 2 Nuclear Power Plant Semiannual Radioactive Effluent Release Rept for Jan-June 1990. No Releases Occurred1990-08-28028 August 1990 Forwards, Fermi 2 Nuclear Power Plant Semiannual Radioactive Effluent Release Rept for Jan-June 1990. No Releases Occurred NRC-90-0118, Forwards Endorsement 35 to Maelu Policy MF-120 & Endorsement 139 to Nelia Policy NF-921990-08-24024 August 1990 Forwards Endorsement 35 to Maelu Policy MF-120 & Endorsement 139 to Nelia Policy NF-92 NRC-90-0135, Affirms That Util Intends to Conduct Insp of Low Pressure Turbine Rotor Disks During Upcoming Refueling Outage.Insp of Low Pressure Turbine 2 Carried Out During First Refueling Outage.No Evidence of Stress Corrosion Found1990-08-17017 August 1990 Affirms That Util Intends to Conduct Insp of Low Pressure Turbine Rotor Disks During Upcoming Refueling Outage.Insp of Low Pressure Turbine 2 Carried Out During First Refueling Outage.No Evidence of Stress Corrosion Found NRC-90-0137, Forwards NPDES Permit MI0037028 for Plant,Approved by State of Mi Water Resources Commission During 900719 Meeting1990-08-17017 August 1990 Forwards NPDES Permit MI0037028 for Plant,Approved by State of Mi Water Resources Commission During 900719 Meeting NRC-90-0136, Requests That NRC Administer Operator Licensing Exam in Dec 1990 & Postpone Operator Requalification Exam1990-08-17017 August 1990 Requests That NRC Administer Operator Licensing Exam in Dec 1990 & Postpone Operator Requalification Exam NRC-90-0133, Forwards Rev 5 to Security Personnel Training & Qualification Plan.Rev Establishes App D & Records Retention Matrix to Provide Central Location in Plan for Info on Records Retention Pages 3-4,3-8 & 3-9.Rev Withheld1990-08-0909 August 1990 Forwards Rev 5 to Security Personnel Training & Qualification Plan.Rev Establishes App D & Records Retention Matrix to Provide Central Location in Plan for Info on Records Retention Pages 3-4,3-8 & 3-9.Rev Withheld NRC-90-0112, Responds to NRC Re Violations Noted in Insp Rept 50-341/90-07.Corrective Actions:Review of RF01 Turbine Work Packages to Identify Where Addl Controls Should Be Placed in Similar Future RF02 Packages Conducted1990-08-0303 August 1990 Responds to NRC Re Violations Noted in Insp Rept 50-341/90-07.Corrective Actions:Review of RF01 Turbine Work Packages to Identify Where Addl Controls Should Be Placed in Similar Future RF02 Packages Conducted NRC-90-0111, Responds to Concerns Re Open Item 90-007-04,per NRC 900627 Request.Potential Enhancements to Drawings Being Reviewed & to Be Resolved by Dec 19901990-08-0303 August 1990 Responds to Concerns Re Open Item 90-007-04,per NRC 900627 Request.Potential Enhancements to Drawings Being Reviewed & to Be Resolved by Dec 1990 ML20055H8921990-07-26026 July 1990 Forwards Certification of Financial Assurance for Decommissioning of Facility,Per 10CFR50.33(k) & 50.75. Util Intends to Retain Unit 1 in Safe Storage Status Until Unit 2 Shut Down & Decommissioned NRC-90-0131, Forwards Rev 15 to Physical Security Plan.Rev Withheld1990-07-24024 July 1990 Forwards Rev 15 to Physical Security Plan.Rev Withheld NRC-90-0108, Discusses Deletion of Commitment for Temporary Mod Program, Per Insp Rept 50-341/84-25.Requirement for Operations Engineer to Approve Extensions of Temporary Mods Beyond 30 Days Being Deleted from Procedure FIP-OP1-021990-07-18018 July 1990 Discusses Deletion of Commitment for Temporary Mod Program, Per Insp Rept 50-341/84-25.Requirement for Operations Engineer to Approve Extensions of Temporary Mods Beyond 30 Days Being Deleted from Procedure FIP-OP1-02 NRC-90-0093, Submits Clarification of Design for Plant Suppression Pool Temp Monitoring Sys.Design Adequate to Ensure Suppression Pool Water Temp within Allowable Tech Spec Limits1990-07-18018 July 1990 Submits Clarification of Design for Plant Suppression Pool Temp Monitoring Sys.Design Adequate to Ensure Suppression Pool Water Temp within Allowable Tech Spec Limits NRC-90-0091, Requests Relief from Commitment to Perform 100% Audits of Tech Spec Line Items.Tech Spec Improvement Program Has Been Completed Which Provides Extensive Review of Tech Spec Line Items1990-07-0202 July 1990 Requests Relief from Commitment to Perform 100% Audits of Tech Spec Line Items.Tech Spec Improvement Program Has Been Completed Which Provides Extensive Review of Tech Spec Line Items NRC-90-0101, Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status for Each Issue Encl1990-06-29029 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status for Each Issue Encl NRC-90-0100, Discusses Installation of Motor Operated Valve Limiter Plates,Per IE Bulletin 85-003.Commitment to Install Limiter Plates Deferred Until Time When Valve or Valve Operator Would Be Disassembled for Another Reason1990-06-27027 June 1990 Discusses Installation of Motor Operated Valve Limiter Plates,Per IE Bulletin 85-003.Commitment to Install Limiter Plates Deferred Until Time When Valve or Valve Operator Would Be Disassembled for Another Reason NRC-90-0088, Discusses Changes Made to Commitment Addressing Calibr Frequency for Inservice Test Instrumentation,Per Violation 87009-03.Nine-month Calibr Frequency for Subj Instrumentation No Longer Appropriate or in Use1990-06-14014 June 1990 Discusses Changes Made to Commitment Addressing Calibr Frequency for Inservice Test Instrumentation,Per Violation 87009-03.Nine-month Calibr Frequency for Subj Instrumentation No Longer Appropriate or in Use NRC-90-0095, Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request1990-06-0606 June 1990 Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request NRC-90-0089, Submits Supplemental Response to NRC Concerns on RHR Operability from Insp Rept 50-341/89-17.Util Faced W/ Decision to Provide Addl Overheating Protection to RHR Sys Pump Vs Maintaining Necessary Water Coverage of Fuel1990-06-0404 June 1990 Submits Supplemental Response to NRC Concerns on RHR Operability from Insp Rept 50-341/89-17.Util Faced W/ Decision to Provide Addl Overheating Protection to RHR Sys Pump Vs Maintaining Necessary Water Coverage of Fuel NRC-90-0085, Provides Plans for Eliminating Temporaary Mods at Plant,Per Insp Rept 50-341/90-051990-05-29029 May 1990 Provides Plans for Eliminating Temporaary Mods at Plant,Per Insp Rept 50-341/90-05 NRC-90-0083, Discusses Action Plan to Review Socket Weld Failures at Plant.Failure History of Socket Welds Will Be Investigated to Determine Whether or Not Significant Common Mode Failure Mechanism Evident.Plan Expected to Be Completed by 9005251990-05-18018 May 1990 Discusses Action Plan to Review Socket Weld Failures at Plant.Failure History of Socket Welds Will Be Investigated to Determine Whether or Not Significant Common Mode Failure Mechanism Evident.Plan Expected to Be Completed by 900525 NRC-90-0074, Discusses Insp of Flash Tanks & Reactor Feed Pump Strainers. No Further Evidence of Moisture Separator Reheater Debris Discovered in Strainers,Stub Tubes,Wire Mesh or Structural Members1990-05-18018 May 1990 Discusses Insp of Flash Tanks & Reactor Feed Pump Strainers. No Further Evidence of Moisture Separator Reheater Debris Discovered in Strainers,Stub Tubes,Wire Mesh or Structural Members NRC-90-0082, Documents Commitments Made During Recent Meetings & Telcon on RHR Sys Small Bore Connections1990-05-11011 May 1990 Documents Commitments Made During Recent Meetings & Telcon on RHR Sys Small Bore Connections NRC-90-0068, Forwards 1989 Annual Financial Repts for Detroit Edison Co & Wolverine Power Supply Cooperative,Inc1990-05-0101 May 1990 Forwards 1989 Annual Financial Repts for Detroit Edison Co & Wolverine Power Supply Cooperative,Inc NRC-90-0071, Responds to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-341/90-03 Re Emergency Preparedness Exercise Weaknesses. Corrective Actions:Case Studies Will Be Developed & Presented in Licensed Operator Requalification Training1990-04-30030 April 1990 Responds to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-341/90-03 Re Emergency Preparedness Exercise Weaknesses. Corrective Actions:Case Studies Will Be Developed & Presented in Licensed Operator Requalification Training NRC-90-0078, Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Bow. Util Has Decided That Fuel Channel Boxes Will Not Be Used After First Bundle Lifetime1990-04-25025 April 1990 Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Bow. Util Has Decided That Fuel Channel Boxes Will Not Be Used After First Bundle Lifetime NRC-90-0051, Responds to SALP 11 Board Rept 50-341/90-01.Outage Critique Action Plan Issued for First Refueling Outage Identifying Lessons Learned & Areas Needing Improvement1990-04-12012 April 1990 Responds to SALP 11 Board Rept 50-341/90-01.Outage Critique Action Plan Issued for First Refueling Outage Identifying Lessons Learned & Areas Needing Improvement NRC-90-0060, Responds to 900104 Request for Supplemental Station Blackout Submittal1990-03-29029 March 1990 Responds to 900104 Request for Supplemental Station Blackout Submittal NRC-90-0061, Forwards Addl Info Re Proposed Drywell Level Instrument Line Configuration,As Followup to 890927 Tech Spec Change Request.Rept Provides Info Re Reasons for Designating Primary Containment Isolation Valve Normally Opened1990-03-27027 March 1990 Forwards Addl Info Re Proposed Drywell Level Instrument Line Configuration,As Followup to 890927 Tech Spec Change Request.Rept Provides Info Re Reasons for Designating Primary Containment Isolation Valve Normally Opened NRC-90-0055, Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47 - Safety Implications of Control Sys in Lwrs. Overfill Protection Sys Adequately Separated from Main Feedwater Control Sys1990-03-19019 March 1990 Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47 - Safety Implications of Control Sys in Lwrs. Overfill Protection Sys Adequately Separated from Main Feedwater Control Sys NRC-90-0024, Suppls Response to Violations Noted in Insp Rept 50-341/85-47 Re Security Records.Util Intends to Rely Solely on Historical Tapes to Retrieve Records Required by Physical Security Plan.Hard Copy Computer Logs Will Be Discarded1990-03-16016 March 1990 Suppls Response to Violations Noted in Insp Rept 50-341/85-47 Re Security Records.Util Intends to Rely Solely on Historical Tapes to Retrieve Records Required by Physical Security Plan.Hard Copy Computer Logs Will Be Discarded NRC-90-0045, Forwards Inservice Insp Summary Rept of 1989 Inservice Insp at Fermi 2 Nuclear Power Plant.1990-03-13013 March 1990 Forwards Inservice Insp Summary Rept of 1989 Inservice Insp at Fermi 2 Nuclear Power Plant. NRC-90-0043, Responds to NRC 900224 Ltr Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 9002021990-03-0909 March 1990 Responds to NRC 900224 Ltr Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 900202 NRC-90-0054, Responds to NRC 900212 Order Modifying License & Notice of Violation.Corrective Actions:Former Director of Nuclear Security No Longer Works for Util & Extensive Actions Taken to Improve Communications W/Nrc1990-03-0909 March 1990 Responds to NRC 900212 Order Modifying License & Notice of Violation.Corrective Actions:Former Director of Nuclear Security No Longer Works for Util & Extensive Actions Taken to Improve Communications W/Nrc NRC-90-0037, Forwards Completed Questionnaires for Types of Insps,Audits & Evaluations,In Response to Generic Ltr 90-01, Voluntary Participation in NRC Regulatory Impact Survey.1990-03-0505 March 1990 Forwards Completed Questionnaires for Types of Insps,Audits & Evaluations,In Response to Generic Ltr 90-01, Voluntary Participation in NRC Regulatory Impact Survey. NRC-90-0029, Responds to Violations Noted in Insp Rept 50-341/89-36. Corrective Action:All Personnel in Operations & I&C Viewed Professionalism Video Which Included Presentation of Facts Concerning Event1990-03-0505 March 1990 Responds to Violations Noted in Insp Rept 50-341/89-36. Corrective Action:All Personnel in Operations & I&C Viewed Professionalism Video Which Included Presentation of Facts Concerning Event NRC-90-0028, Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Revised Pages of Rept for Jul-Dec 1988, Containing Recalculated Noble Gas Releases & Doses1990-03-0101 March 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Revised Pages of Rept for Jul-Dec 1988, Containing Recalculated Noble Gas Releases & Doses NRC-90-0034, Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results1990-02-26026 February 1990 Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results NRC-90-0036, Forwards Response to NRC Survey on Nuclear Fuel Cycle Industry Future Activity,Per 900122 Request1990-02-26026 February 1990 Forwards Response to NRC Survey on Nuclear Fuel Cycle Industry Future Activity,Per 900122 Request NRC-90-0026, Forwards Monthly Operating Rept for Jan 1990 for Fermi Unit 2 & Revised Rept for Dec 1989,correcting Error in Net Electrical Generation Figure1990-02-15015 February 1990 Forwards Monthly Operating Rept for Jan 1990 for Fermi Unit 2 & Revised Rept for Dec 1989,correcting Error in Net Electrical Generation Figure NRC-90-0020, Forwards Response to Violations Noted in Insp Rept 50-341/89-31 Re Maint Support for Security Equipment.Addl Instrumentation & Control Repairmen Hired.Encl Withheld (Ref 10CFR73.21)1990-02-12012 February 1990 Forwards Response to Violations Noted in Insp Rept 50-341/89-31 Re Maint Support for Security Equipment.Addl Instrumentation & Control Repairmen Hired.Encl Withheld (Ref 10CFR73.21) NRC-90-0010, Responds to NRC 900102 Ltr Re Violations Noted in Insp Rept 50-341/89-30.Corrective Actions:Storage Area in Machine Shop closed-out & QA1 Matl Returned to Warehouse Where Positive Controls in Effect & Shift Turnover Procedure Revised1990-02-0101 February 1990 Responds to NRC 900102 Ltr Re Violations Noted in Insp Rept 50-341/89-30.Corrective Actions:Storage Area in Machine Shop closed-out & QA1 Matl Returned to Warehouse Where Positive Controls in Effect & Shift Turnover Procedure Revised NRC-90-0013, Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design. Subj Valves Not Used by Util1990-01-26026 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design. Subj Valves Not Used by Util NRC-90-0012, Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 19911990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 1991 NRC-90-0016, Responds to 10CFR26 Re fitness-for-duty Programs.Util Conducting Testing for Drugs Described in 10CFR26,App a, Section 2.1(a) & at Cutoff Levels Defined in Sections 2.7(3)(1) & 2.7(f)(2) as of 9001031990-01-26026 January 1990 Responds to 10CFR26 Re fitness-for-duty Programs.Util Conducting Testing for Drugs Described in 10CFR26,App a, Section 2.1(a) & at Cutoff Levels Defined in Sections 2.7(3)(1) & 2.7(f)(2) as of 900103 NRC-89-0297, Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp1990-01-12012 January 1990 Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp NRC-89-0240, Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches1990-01-11011 January 1990 Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches 1990-09-07
[Table view] |
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\%'f EF2 - 53,432 Mr. L. L. Kintner Division of Project Management Office of Nuclear Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Kintner:
Reference:
Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341
Subject:
Detroit Edison Response to the Licensee Qualification Audit During the exit critique of the Licensee Qualification Audit on May-21, 1981, the audit team identified five areas of concern. In addition, the team had several questions concerning a draft revision of Chapter 13 of the FSAR. The attachments document the NRC concern or request and Detroit Edison's response to each. Where appropriate, marked up pages of the FSAR have been included and will be formally amended in a forthcoming FSAR amendment. It is our understanding that the sub-mission of the attached responses satisfies the concerns and will be sufficient to allow preparation of the appropriate Safety Evaluation Report sections.
Sincerely,
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9 Attachment A.
4 NRC CONCERN
- 1. Plant ana Corporate Staffing NRC is concerned about the lack of proper staffing. At present-there are 160 people-in Nuclear Operations, and the planned staff should include 490 people. There are many key positions still open. The Plant' staff shculd be functional not later than six months before fuel load in order to have a smooth operating organization.
DETROIT EDISON RESPONSE In order to provide sufficient experience as an operating organization, The Detroit Edison Company will have the essential elements of its Nuclear 4 Operations Organization in place from four to six months prior to fuel loading.
The specific plan to meet this commitment is as follows-(see attached organization charts):
Chart No. Commitment 1 All positions except the Director-Quality Assurance, The Director-Outage Management and the Director-Nuclear Plant Modifications are in place as of the present time. The Director-Quality Assurance will be in place and functioning within the next several months, but the Director will '
report to the Manager-Quality Assurance until four months prior to fuel loading, at which time the Director will report to the Vice President-Nuclear Operations.
2 These functions are presently being performed by the Project Quality Assurance Organization and Fermi PMO. The functionally comparable supervisory positions will' be filled and reporting to the Director-I Quality Assurance by December 1981. The organization will;be functioning and reporting to the Vice President-Nuclear Operations four months prior to fuel loading.
3 All supervisory positions will be filled six months prior to fuel loading and the organization - functioning according to the . plan four months prior to fuel loading.
4 This organizational unit will be in place at fuel loading and is not needed until that' time because the Fermi 2 PMO is performing this i function for the project as well as for Nuclear Operations.
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5 The couplete organizational unit covering the simulator does not have to be in place until the simulator is delivered to the site (scheduled for 1983). The other supervisory positions 'will be in place by December
- 1981 in order to meet .the training requirements prior to fuel loading.
6 All supervisory positions are filled -now, and will be functioning' four months prior to fuel loading.
6A The supervisory positions in Nuclear Safety and Plant Engineering will .
be filled and functioning at least four months prior to fuel loading.
6B These positions will be , filled to about 50 percent of the specific complement six months prior to-fuel loading, and the remaining needs will be filled as they arise. A large number of - these needs are beiag covered in the interim by the Generation Engineering Department and the Engineering Research Department of Detroit Edison as well as by outside -
consultants.
6C Those supervisory positions will be in place and functioning at fuel loading. Most of the functions shown on this chart are presently being performed in the Nuclear Engineering Division of the Generation Engineering Department, and many of them will be transferred to Nuclear Operations before December 1981.
All comparable supervisory positions have been filled and functioning since 1978. Significant programs now moving under the responsibility of the Vice President-Nuclear Operations as described in the accompanlying charts have been under development during the past four years including the anticipated required procedures.
7 All key positions will be filled as indicated on the attached pages 13.1-29,30 (Part of Attachment F) of the FSAR. Basically all key positions will be filled six months prior to fuel loading except for personnel performing compatible startup activities which will continue until commercial operation. Ninety percent of the complement of Nuclear Production will be filled four months prior to fuel loading.
8 This function is now being performed by the Fermi 2 PMO. It will continue to be performed by the PMO, but organized along the lines on Chart 8, and report to the Manager-Nuclear Operations at fuel loading.
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Attachment A 6
i 9 The safety organizations (Nuclear Safety 'Consnittee, IRAG, ' NSPED) will all be staffed and functioning as shown on the chart four months prior to fuel loading. It' should be noted that ORSO has- been functioning as an organizational unit since 1977 and will continue to function through fuel loading and beyond. :IRAG will be organized -and functioning six -
months prior. to fuel loading.
The presently scheduled fuel load date is November 1982. : Most of the conunitments made are based on that schedule date; however, if for any reason that date is delayed, such as prolonged hearings, the commitments will be tied to the new fuel load date.
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General Supervisor Nuclear Fuel 3 to i I
! Supervisor Supervisor Supervisor j Nuclear Fuel Fuel Engineering Reactor Engineering 6 3 8 i
- FuelCycle Analysis - Fuel Design - Fuel Accountability l
- Uranium & Enrichment - Fuel Fabrication - Control Sod Analysis Programming f Contract Administratior i
- Fuel Bumup Core Analysis - Fuel Assurance
- Reactor Dynamics - Fuel Storage & Shipping h j) -
- Fuel Performance l u Reactor Engineer matrixed to Nuclear Production i
i l
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5 l .9
Chart 7 .
5 Plant Security Medical Superintendas Depanment Depanment Nuclear Producton
! Matrixed from 4 233 Nuclear Quality Matrixed from Assurance Administration I il 7
. Y U Supervisor Adm#nistrator Operational Nuclear Assurance Production s.
Supervisor ; Coordination i R M at s i Protection 45 .
Assistant Supemsor Supenmor Plant Security Medical Superintendent as e iss I _ l _
i I Operations Engineei' Maintenance Engineer Technical Engineer Reactor Engineer Shift Technical Advisors >
71 89 47 4 s l
' 4 4 u--- >
T---
Matrixed from .
Nuclear Engineenng i
e
e i
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Chart 8 .
Matrixed from Matrixed from
. Generation Engineenng Constructon 8
I I I
________, i , j l Nuclear j l Director i Engineering i Nuclear Pfard i I l 1 Modifications I l 2 a L__ Director______J
_____L__, l 1 I e l-- ' '
i
' t Requirements , Matrixed from 4 Matrixed from
! Nuclear Safety & Crit'oria Nuclear Quality Construction Nuclear Quality l Plant Engineenng ,
l Project Engineer Supenntendent Assurance L __y____ Assurance l
t__________J Drawings
& Specs l' 4
[ 4 8 Y
i Engineenng Constructon O/A &
Assurance inspechon 1
I Assistant Assistant Asst. Const. Supt. Asst. Const. Supt.
Project Engineer Project Engineer Edison Bechtel Contract Design Edison Design Construction Construction s
l t
.o
Nuclear Safety Organizations Board of Directors Chart 9 -
lN Nuclear Safety -
Chairman of the Committee Board Chief Executive Officer i
President Chief Operating Officer I
Executive Vice Presdent Operations l
N IRAG d Operations __
I Manager Nuclear n Operations I
I I I I I I Director Director Director Director Drector Nuclear Quality w Outage Nuclear
- D@trat Nuclear Nuclear Plant Assurance nis a l Management Training j Engineenng p Modfications 1
I I I echn. uel Satyk + OSRO Onsite Review Organization l [I^"I, wo L
m _
i
~ Attachment B NRC CONCERN'
- 2. Training Organization and Training.
Training organization seems weak and fragmented. The training for licensed and non-licensed personnel is behind schedule. . The NRC has asked for a training schedule and the status of training. -
DETROIT EDISON RESPONSE Nuclear Operations Training Plan is attached.
" Number of individuals to be trained" means " minimum nu-ber required at fuel -
loading". However, it is our intent to train more than the minimum numbers.
l l - .
I GED/15/6.3 I
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,.v ,-y y9-,, ,-
e,m- # y - - - - - + , . .-92,- 9 4 , , ,e,. ,- r - - - w --w y p--%g + , . , , -er ,
4 NUCLEAR OPERATIONS TRAINING PLAN DATE :. 6/1/81 MONTH PRIOR TO FUEL LOAD GROUP TO g o g g g g gg g g 7 e g , , , , , ,
BE TRAIMED CHEMISTRY "d 175.5 1217l HEALTH PHYSICS !
L3.J l582l MAlhiTENANCE N _
13 3 . 51 1694i LICENSED OPERATORS FJgt4%
C ' --
ajes'h'SN m" a'"
o*
o 3695l l2485l J s
NON-LICENSED [Li y 0PERATORS l185l l6751
- QUALITY ASSURANCE / b CONTROL L69J l645i SECURITY E
[.6J l1659l SHIFT TECHNICAL B ADv1SOR 1461 16961
~
IECHNICIANS 526 l l 409l LEGEND COMPLETED TRAINING T0-DATE TRAINING REMAINiliC
{;((.f;5 # BASE 0 ON t 0F TOTAL # BASED CN % OF TOTAL j # MAN-DAYS OF COMPLETE 0 l TRAINING T0-DATE l 4 i MAN-DAYS OF TRAINING REMAININC PRESENTLY UNDER MANAGEMENT REVIEW DUE TO:
A. NUREG - 0737 B. LETTER FROM HAROLD DENTON TO ALL POWER REACTOR APPLICANTS AND LICENSEES, DATED MARCH 29, 1980 C. CLARIFICATION OF THE N.R.C. STAFF POSITION RECARDING LICENSED OPERATOR EDUCATION D. POSSIBLE RE!CHEDULING OF LICENSED OPERATOR COLLEGE LEVI:L EDUCATION PROGRAM
- = p n y ye-9 g-w+---a-- p-g *w ---e-e w *, e - --
DATE: June 1, 1981 NUCLEAR OPERATIONS 'IRAINING PL_At4
- INDIVIDUALS 'IO BE 'IRAINED ~ IATESTlDE3E GROUT TO 'IUIAL 'IO BE 'IRAINED CURRENT 10 BEGIN RE 'iRAINED B,Y EUEL ICAD STAFF PRIMARY TPAINING
- CHEMISIIT 5 2 1/82 HEAL'lE PHYSICS 10 7 1/82 MAINIENANCE 30 9 1/82 LICENSED OPERAIORS 20 19 'IRAINING IN PRCGISS NCN-LICCNSED CPERA'IORS 10 16 9/81 CUALITY ASSURNiCE/CDNIROL 10 9 1/82 SECURITY 45 23 1/82 SHIFT TECHNICAL ADVISOR 4 , -0 7/81 THIINICIANS 10 23 TRAINING IN PROGRESS 144 108 i
- Primary training is the latest date that training nust begin to ccetpletely l~
train tne remaining minimum nturier of individuals.
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- v.--, ..,y- ,, , - -e,-- ., ,.r-, - - -
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DATE: . June 1, 1981 NAME OF GROUP: CHEMIS'IRY
'IDIAL # %
EXPECITD INDIVIDUALS 'IRAINING
- DAYS / PERSON 'IO BE 'IRAINED CCMPLETED I1OLEMENTED PROGRAMS RADIOCHEMIS'IRY 75 1 100 CARDIOPUIN0 NARY RESUSCITATICN 0.5 5 20 PROGRAMS 'IO BE IMPI2MENTED DEVEIDPED SAFEIY TAGGING 0.5 5 FIRST AID 1 5 RESPIRA'IOR 0.5 5 UNDER DEVEIDPMENT GENERAL EMPIDYE TRAINING 1 5 PLANT AININ PROCEDURES 5 5-RADIATIN PRCU5CTIN 10 5
'IO BE DEVEIDPED EME"ESKY PLAN 0.5 '5 FIFE Prom;nCN 0.5 5 SECURITY PLAN 0.5 5 FIRE BRIGADE 5 5 RESCUE TEAM 1 5 PM SEARG 2 5 OA/CC INDOCIRINATION 0.5 5 BWR CifEMISTRY 5 5 C5IEM METEDS 5 5 CFlM AEMIN PROCEDURES 5 5 J
l l
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MAN DAYS OF TRAINING CCNPLETED 'IO DATE 75.5
'IO BE CWPLEIED 217.0 .
'IOTAL 292.5 l
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LDATE: June 1, 1981 NAME OF GROUP: HEALTH PHYSICS
'IUIAL # %
EXPECIED INDIVIDUAIS 'IRAINING
- DAYS / PERSON TO BE TRAINED CmPIETED IMPLEMENIED PROGRAMS CARDIOPUIbONARY RESUSCITATIN 0.5 10 30 FIRST AID 1 10 10 PROIECTIVE TAGGING 0.5 10 10 PROGRAMS 'IO BE IMPIDENIED
. DEVEIDPED RESPIRATOR TRAINING 0.5 10 UNDER DEVEIDPMENT GENERAL EMPICIEE 'IRAINING 1 10 PLANT A MI
N. PROCEDURE
S S 10 RADIATION PROIECTION 10 10
'IO BE DEVEIOPED EMERGENCY PIAN 0.5 10 FIRE PROIECTICH PIAN 0.5 10 FIRE ERIGADE 5 <
RESCUE TEAM 1 10 BCMB SEARCH 2 10 CA/OC INCOCIRINATION 0.5 10 RADIATION PROIECTIW IEEORY 10 10 H. P. Mh 6, 15 10 SECURITY PLAN 0.5 10 H. P. ADMIN. PROC. 5 10 j
l l
MAN DAYS OF TRAINING CCMPIEIED TO DATE 3 TO BE CCMPLETED 582 l IUTAL 585 t
,g,,,,,e , - ,nn--..-- --.e~m---. - - , g-,- ~ - -
,,--,,r . - , - .-~n-,nn.,, - . , , . , ,.-nm-, , . . - - --~,n .-,----
DATE: June 1, 1981
'NAME OF GROUP: MAINrDOWCE TOTAL # %
EXPECTED INDIVIDUALS TRAINDG
- DAYS / PERSON 'IO BE TRAINED OCMPIETED IMPLDENTED PROGRAMS DE:RGDCY DIESEL GD3ERATORS 5 5 100 SAFETY TAGGING 0.5 25 28 CARDIOPUDIONARY RESUSCITATION 0.5 30 13 FIRST AID 1 30 10 PROGRAMS TO BE IMPLDENTED DEVELOPED RESPIRATOR 0.5 25 MOBILE EQUIPMENT 5 10 UNDER DEVEIOPMENT PLANT AEMIN PROCEDURES 5 25 MAINT AEMIN PROCEDURES 10 25 TORCUE hEENCH 0.5 20 IOCKWIRING 0.5 20 GENERAL DfIDYE TRAINING ~
1 30 RADIATION PRCTIECTION 2 30 TO BE DEVEIDPED CA/QC INDOCTRDUCION 0.5 20 CODES AND STANDARDS 1 5 HOUSEKEEPING 0.5 25 DERGDCY PIAN 0.5 30 FIRE PROTDCITON 0.5 30 l SECURITY PLAN 0.5 30
[ DECONDMURTION PRACITCES 1 25 l
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MAN DAYS OF TRAINING COMPIETED TO DATE 33.5 TO BE CCMPIETED 694.0 TOTAL .727.5
--r , c -r , . - - - -e *= %,-- , ., , - - - - . ,,---y -, - - - 3
9 DATE: June 1, 1981 NAME OF GROUP: LICENSED OPERATORS MINIMUM TOIAL # %
EXPECTED INDIVIDUAIS TRAINING
- DAYS / PERSON TO BE 'IRAINED COMPIETED IMPLDENIED PROGRAMS ,
ACADEMIC REFRESHER 20 18 100 BASIC NUCLEAR 60 18 100 GENERIC SYSTENS AND PRCCEDURE3 10 20 100 SAFE 1Y TAGGING 1 20 100 FIRST AID /CPR 2 -20 100 RESEARCH REACICR 8 20 100 BWR TECHNOIOGY 20 20 100 BWR SIMUIATOR 40 20 100
, BWR OBSERVATION 20 20 100 BWR TRANSITICN 5 20 100 SYSTENS TRAINING 25 20 25 SYSTEMS CUAL PROGRAM 25 20 2 PROGRAMS TO BE IMPLDiENTED DEVEIDPED CE"M LEAK REPAIR 1 --
20 BmB SEARCH TEAM 1 20 UNDER DEVEIDPMENT PIANT AEMIN PROwxRES 0.5 20 OPERATIONS AIMIN PROCEDURES 0.5 20 GENERAL DiPIOYE TRAINING 0.5 20 RESPIPATOR TRAINING 0.5 20 COMPtJrER OPERATICNS 1 20 SECURITY PLAN 1 20 RADIATION PROTECTION 5 20 TO BE DEVEEOPED RADWASTE SYSTEMS 2 20 INTEGRATED PLANT OPERATIONS 10 20 INFREQUENT, ABNORMAL & DER OPS 20 20 TECHNICAL SPECIFICATICES 5 2C DERGENCY PLAN TRAINING 0.5 20 RESCUE TEAM TRAINING 1 20 TIEWODYNAMICS & HEAT TRANSFER S 20 l MITIGATE CORE DAMAGE 5 20 INSTRUMENTATION AND CONIROLS 4 20 REEUEL TRAINING 3 20 FIRE BRIGADE & LEADERSHIP 5 20 FIRE PROTECTION PLAN 2 20 QA/OC TRAINING 0.5 20 '
LEADERSHIP & CCNIROL ROCM MGff 5 20 LICENSE EXAM 2 20 l
l MAN DAYS OF TRAINDG
! CmPIEIED TO DATE - 3,695 TO BE CCMPIETED 2,485 TOTAL 6,180
-w, -- * * - * -
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4 DATE: - June 1, 1981 NME OF GROUP: NCN-LIGNSED OPEPA'IORS EXPh;1tu INDIVIDUALS TRAINING
- DAYS /PERSW 'IO BE TRAINED CWPIEIED IMPLD1ENTED PROGRAMS GRERIC SYSTD1S AND Pie.c.uum 15 10 100 SAFEIY TAGGING 0.5 10 100 FIRST AID /CPR 2 10 100 FORK LIET 1 10 100 PROGRAMS 'IO BE IMPLDENTED DEVEIDPED NWE UNDER DEVEID1HE1T SYSTD1S TRAINING 25 10 JITS (AREA CUALIFICATIN) 25 10 REEUEL TRAINEG 5 10 GENERAL D4PLOYE TRAINING 0.5 -10 DERGENCY PLAN 0.5 10 RESCOE TFAM 1 10 SECURITY PIAN 1 10 RESPIRA'IOR TRAINING 0.5 10 FIRE BRIGADE 5 10 BCNB $TAPai 1 10 CHIDRINE LE7X REPAIR 1 10 RADIATICN PRCTTECTICN 2 10
'IO BF DEVEIDPED NCtE MAN DAYS OF TRAINDG CWPLETED 'IO DATE 185
'IO BE CCNPIETED 675
'IUIAL 860 g -gg.
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DATE: June 1,1981 NAME OF GROUP: g
'IUIAL # %
EXvu;1w INDIVIDUALS TRAINING
- DAYS /PERSCN TO BE TRAINED CCNEU.TED IMPLDIENTED PROGRAMS SAbETY TAOGING 0.5 10 80
, CARDIOPUIMNARY RESUSCIATICH 0.5 10 50 AUDIT TEAM MENBER 5 10 40 PROGRAMS 70 BE IMPLDENIED DEVEIDPED -
FIRST AID 1 UNDER DEVEIDPMENT GENERAL D!PIDYE TPAINING 0.5 10 NDE LEVEL I - ALL 5 10 PLANT AENIN PBOC 5 10 RADIATION P M1u n CN 10 70 BE DEVEIDPED E4ERGmCY PLAN 0.5 10 ~'
FIRE PMiu;nCN PIAN 0.5 10 SMTY PLAN 0.5 10 QA/QC IhMIATICN 0.5 10 QA/QC AEMS PPOC 10 10 AUDIT TETE LEADER 5 10 NDE LEVEL II D.P. 2 5 NDE LEVEL II VISUAL 5 -5 LEVEL I INSPEC'IOR - ALL 10 10 LEVEL II INSPEC"OR - VARIOUS 10 3-s l~
l MAN DAYS OF TRAINING l CCNPIrrED TO DATE 60 TO BE CDMPIETED 645
'IUrAL 705 -
t
.- _- -. . _ _ . _ , _ _ . - _ _ . - _ , - .. ~ . - _ --_ _ - _ _ - . _ . . _ , . . - . . _-
DATE: June 1, 1981~
NAME OF GROUP: SECURITY
'IUIAL %
I:XPB"X INDIVIDUALS 'IRAINING
- ' DAYS / PERSON 'IO BE TIGINED COMPLt.TED IMPLD4 DEED PROGRAMS FIRST AID 1 45 7 CARDIOPUINCNARY RESUSCITATION 1 45 7 PROGRAMS 'IO BE IMPLD4EIC!D DEVEIDPED NONE UNDER DEVEIOPMENT BASIC SECURITY 'IRAINING S 45 NUCLEAR SECURITY 'IRAINING 15 45 WEAPONS & TACTICS 10 45 DRILLS & EXERCISES 2 45 GENERAL EMPIDYE 'IRAINING 0.5 45 SECURITY PIAN 0.5 45 RADIATION PROIECTION 1 45
'IO BE DEVELOPED i D4ERGENCY PIAN 0.5 45 FIRE PROTECTION PLAN 0.5 45 l
l I
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t MAN DAYS OF TRAINING I. CCNPIETED 'IO DATE 6
'IO BE CCMPIETED 1,659
'IUfAL T36T
- .- ,,n. v- ..r-- ,--,,,a.. u- -
---a - -
. DATE: June 1, 1981 NAME OF GROUP: SHIFT TECHNICAL ADVISOR-IOTAL # %
DESIRED . INDIVIDUALS TRAINEG
- DAYS /PERSCN 'IO BE TRAINED CCNPLM IMPLDECED PROGRAMS GDERIC SYSTDG & PROCEDURES 10 4 100 SAETIY TAGGING 0.5 4 100 FIRST AID 1 4 100 PROGRAMS 'IO BE IMPLDHEED DEVEIDPED EUNDAMENIAIS TRAINING 25 4 SYSTDG TRAINDU 50- 4 RESPIRATOR TRADiING 0.5 4 -
BASIC SUPERVISION PROGPAM 5 4 BWR TECHr0 LOGY 20 4 AIR QUALITY METERS 1 4 Ut: DER DEVEIOPMENT GENERAL DIPIDYE TRAINHC 1 4 SECURITY PIRI 0.5 4 -
SIMUIATOR TRAINDG 20 4 EDUCATICNAL UPGRADING
- 4 PIANT ACMIN Pid.wuw.s 1 4 CCNPUTER OPERATICES 1 4 RADIATICN Pi4J1wnON 2 4 TO BE DEVEIOPED ADMINISTRATIVE CONTROLS 2 -4 DERGDCI OPERATING PROL'ww2d 8 4 GENERAL OPERATDG PROCEDURES 10 4 TRANSIENT /ACCIDDE ANALYSIS 20 4 MITIGATING CORE DAMAGE 5 4
( DERGENCY PLAN 0.5 4
! FIRE Ple>1wnCN PLAN 0.5 4 QA/QC 0.5 4 SEURITY PLAN 0.5 4 l
- DETERMINED BY ANALYSIS CN A CASE BY CASE BASIS.
MAN DAYS OF TRAINING CCNPLETED TO DATE 46 TO BE COMPIETED 696
'ICIAL T47 y y w, we ~ -, --- y+ga.ep *--,y --%,- - - - - 7 y , - - - y-ay- * --e '
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DATE: June 1, 1981 NAME OF GROUP: TEGNICIANS TOTAL %
EXPECIED DOIVIDUAIS TRAINDG
- DAYS / PERSON TO BE TRAINED CCNPLETED IMPLDEEED PROGR7NS INDOCIRINATION 1 10 100 GENERIC SYSTD4S AND PROCEDURES 15 10 100 NUCLEAR INSTRI.PERATION 10 10 100 PROCESS INST M E EATION 10 10 100 GD4AC 5000 INSTRUMEICATICN 5 10 100 REACIOR MANUAL CONTROL SYSTEM S 10 100 GIORINE LEAK REPAIR 1 10 100 QUALIFY W PLANT ADMIN PROCEDURES 2 10 100 SAFELY TAGGING 0.5 10 100 CARDIOPUIhmARY RESUSCITATICN 3.5 10 90 QUALIFY CN I&C AMIN PROCEDURES 2 10 9u FIRST AID 1 10 50 QUALIFY ON TEST EQUIPMENT 10- 10 3 PROGRAVS TO BE IMPLEME2EED DEVEIDPED BCNB SEARCH 2 10 UNDER DEVEIDPME2C GENERAL EMPLOYE TRAINDG 1 10 RESPIRATOR TRAINDG 0.5 10 SECURITY PIAN 0.5 10 RADIATICN PBuluinCN 1 10 10 BE DEVEMED EMERGENCY PLAN 0.5 10 RESCUE TEAM 1 10 FIRE Pit.nu;nCN PIAN 0.5 10 FIRE BRIGADE TRAINING 5 10 PPACTICAL DDONSTRATICNS 5 10 QA/QC DOOCTRINATION 0.5 10 QUALIFY ON PLANT DUTRUMENIS 10 10 INSERVICE INSPECTICN 2 10 CONTAINMEIE LEAK RATE 1 10 MAN DAYS OF TRAINDG COMPLETED TO DATE 526 - -
-'IO BE COMPLETED 409 TOTAL 935 p- --e e, w- - ,--,- ,,y, y- , , - , - . , -.,y
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Attachment C NRC CONCERN
- 3. Operators with Commercial Nuclear Experience The NRC has found that none of the operators have com:nercial experience on the same type of plant (BWR). They. request that at least one operator on each shift have this experience.
DETROIT EDISON RESPONSE-Detroit Edison will provide at least one additional person per operating shift with at least three months of BWR operating experience from fuel loading until consnercial operation, or 9 months, whichever is shorter. - This person will _be
, provided by a suitable contractor such as General Electric.
The contract person will have no responsiblity for reactor. operation, will be -
assigned duties by the Nuclear Shift Supervisor, and will provide guidance and assistance to the licensed Detroit Edison operators as required. The duties.and responsibilities of this contract employee will be similar to those of the Shif t ,
Technical Advisor.
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9
Attachment D NRC CONCERN
- 4. Staffing of Rad-Chem Section The NRC is concerned about the skeletal staffing of the Rad-Chem section and the apparent weak status of the radiation protection training program.
It is their opinion that only the Health Physicist qualifies for the position as Radiation Protection Manager (RPM). They suggested that Detroit Edison have a backup for the RPM.
DETROIT EDISON RESPONSE STAFFING Detroit Edison recognized Radchem staffing.as a priority problem about nine months ago. Since that tiac the 'following ' positive steps . have been taken.
- 1. Exceptions to the Detroit Edison administrative procedures which can facilitate the hiring of Radchem personnel have been adopted.
- 2. The President of Detroit Edison signed authorizations giEing blanket approval to hire 29 Radchem personnel in 1981.
- 3. An aggressive recruiting campaign was started in about February 1981.
Since then, approximately 24 prospective employes have ~ caen interviewed.
Offers of employment have been made to about 17 of these people and about eight of these individuals will be starting work within the next.two months. These eight individuals include one Water Plant Technician, one-
- Chemistry Technician, one Ph.D. Haalth Physicist, one Environmental Engineer, three Health Physics Technicians and one degreed Chemistry / Health Physics training specialist.
The recruiting effort has included contact 1with numerous nationwide
! employment agencies, direct contact with associates in the nuclear industry, recruiting trips to various conferences, San. Francisco and Seattle.
l A recruiting trip by the Radchem Engineer to San Diego is scheduled for June 11. _. recruiting trip by the Health Physicist to the Annual Meeting of the Health Physics Society is planned for mid-June.
l GED/15/6.5 w -
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Attachment D 4.
~
Three summer school Health Physics professionals (two . Bachelors candidates and one Masters Degree candidate) are_ working at the plant this summer.
All will be available for potential employment in May cf 1982.
- 5. See the Radchem staffing plan and timetable (attached). We intend to follow this plan to accomplish the staffing goal.
- 6. Detroit Edison is presently in the process of selecting _a contract technician company or companies'from which the Radchem staff can be supplemented if necessary.
We believe that the necessary personnel will be hired to support the plant schedule.
RADCHEM TRAINING The Radchem training program is. included in the overall training program described in Attachment B.
Internal to Radchem, we will soon have two individual who will; dedicate the majority of their time to developing Radchem training in cooperation with our Nuclear Training Department. One individual has a B.S. Degree (Chemistry) with two years of experf ince in developing and conducting Health Physics and Chemistry training for the General Electric Company.
The other individual is a Ph.D. Health Physicist and will dedicate much of his time to providing subject. matter for the Health Physics theory and analysis.
BACKUP RPM It is Detroit Edison policy that there will be backup for all important company positions. A long term r.atomated personnel management program is in operation to meet this policy. The Radiation Protection Manager is considered a very important company position. Two indivir als presently in the Radchem section l can quality as the backup RPM in the absence of the General Supervisor-Health Physics. These individuals are the Radchem Engineer and one technician who will l soon be promoted to Health Physics Supervisor-Operations (this individual should be qualified in six to nine months).
We are presently attempting to recruit two people with at least a B.S. Degree in Health Physics and/or as much practical and professional operating experience as possible. These individuals would, in time, meet the requirements of the RPM.
In addition, we have already hired a Ph.D. in Health Physics whose educational .
background will be of great support to those in the organization with practical experience.
I GED/15/6.6 l
. ~ . . . . . . ., . _ , -.,. , _ . ~ . . . . , , _ , , _ .
PROPOSED RADCHEM SECTION COMPLEMENT AT FUBL LOAD 0"
POSITIONS TOTAL 6/1/81
- 1. RadChem Engineer 1 1
- 2. General Supervisor-Chemistry 1 1
- 3. General Supervisor-Health Physics 1 1
- 4. General Supervisor-Radwaste 1 1
- 5. Chemical Engineer 1
- 6. Chemist 1 1
- 7. Supervisor-Health Physic's (Operations) . 1
- 8. Supervisor-Health Physics (Dosimetry) 1
- 9. Specialist-Health' Physics' 1
- 10. Radwaste Superviror (Operations) 1
- 11. Radwaste Supervisor (Decontamination) 1
- 12. Special ist-Shipping 1
- 13. Enviror. mental Engineer 1 1
- 14. Senior Equipment Technician 2
- 15. Senior !(ater Treatment Technician 1 1
- 16. Water Treatmant Technician 2 1
- 17. Senior Chemical Technician 4
- 18. Chemical Technician 5 1
- 19. Health Physics Aide 2 1
- 20. Senior Health Physics Technician 4 1
- 21. Health Physics Technician 12
- 22. RadChem Supervising Operator 5' TOTAL 50 11 Current plans would also include appropriate numbers of decontami-nation / cleaning personnel not reflected in the above complement.
I
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n Attachment E NRC CONCERN 5.- Status'of Shift Technical Advisors While the FSAR does not state that an STA will be available on all,. shifts, the quidelines of NUREG-0731 state that an STA should be avail.able on each ~
, shift.
DETROIT EDISON RESPONSE A qualified shift technical advisor will be available on each ' shift as outlined in the following FSAR Appendix H section:
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H.I.A l.1 Shift Technical Advisor H.I.A.l.l.1 Statement of Concern For an off-normal event in reactor operations, the shift-supervisor's primary responsibility is the command and control '
function. The other control room operators assume a manipula-tive, reactionary role in response to commands from the shift ,i '
supervisor and in response to the various alarms and other indi-cators of plant conditions caused by the event. _Having reviewed l
the facts available on the accident at TMI-2 and the general i
state of training and qualifications for present operators and senior operators, the Task Force has concluded that additional technical and analytical capability, dedicated to concern for the safety of the plant, needs to be provided in the control room to support the diarnosis of off-normal events and to advise the shif t supervisor on actions to terminate or mitigate the ..
1 consequences of such events.
l H.I.A.1.1.2 NRC Position Each licensee shall provide an onshift technical advisor to the
- l shift supervisor. The shift technical advisor may serve more i
than one unit at a multiunit site, if c,ualified to perfocm the advisor function for the various units.
( ) The shift technical advisor shall have a bachelor's degree or
, equivalent in a scientific or engineering discipline and have -
1 received specific training in the response and analysis of the
- plant for transients and accidents. The shift technical advisor l shall also receive training in plant design and layout, includ'-
l ing the capabilities of instrumentation and controls in the control room. The licensee shall assign normal duties to the.
shift technical advisors that pertain to the engineering aspects of ensuring the safe operation of the plant, including the review and evaluation of operating experience (Reference 1) .
1 l
H.I.A.l.1.3 Detroit Edison Position Detroit Edison agrees with the intent of the NRC to upgrade the accident assessment and the operational experience assessment.
and u;11 I
ncure that addi*innal *arhnical and-en:1ytic:1 capabil-itics arc provided ir th centrol reem for the diagneci Of abner-
-mal evente $nd *n ad" ire the operstccs on actions to Lerminet.
or-mitig e Le the concagnancer cf cuch event..-
a.
This will be provi,ded by the assignment of ither qualified shif t technical advisor er nuclear shift j educaticn:1 qualigications.on each shift.rup'ercicor; with cpgrad:d Shift tcchnical advicors will serve ir er advisory cepseity to-l
' [p] the nuclear shift supervisuc. Ihc shift technical 2A"irer ch:11-(L Anua a bacheler'e degree in engineering Sv ralated sciences, I
. H.I.A.l.1-1 Amendment 33 - March 1981 l ,
/ .
e/
/4
,. EF-2-FSAR
- --including 50 ;c;;stc; heur: Of ;cliege-le'rel math = tics, scovius -
-phy;ics , ccactcc themmodynami ., end wicui4.iual engiuccuing. k f "pgraded nucleat snifc supervisors, in addlLica to =;intainini;i--
2
- eaior resc'ur operator's license, snali aave a Lechnical
. ; collega-1=eral adire n +-i nn af =hnue gn samacter h.eur; in mothcact .
j
. ics: reactee physics, .eocics th::medyn: ics, oud clavisival -
8 H.I.A.l.l.4 Reference '
1
- 1. U.S. Nuclear Regul.ory Commission, Clarification of TMI-2 I Action Plan Requirements, NUREG-0737, p. l.A.l.1-1, October 5
1980. '
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H.I.A.1.1-2 Amendment 33 - March 1981 1 .
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%1techmant F NRC Concern Chapter 13 " Conduct of Operations"
, Page 13.1-29 Question -
Several key positions are scheduled to be filled 'in 1982.'
- 1. Why so late?
2.- When are these people (specify. month) coming on board in 19827 Answer -
- 1. These positions were scheduled for staffing based on a scheduled Fuel
, Load date of November 1982.. Several of the' positions in question will be filled by empicyes who are presently in our organizaticn and are in various phases of training.
- 2. A marked up copy of 13.1-29,30 is attached which indicates the schedule ~
.to which these positions will ba fi'. led. This information will be _ >
included in a forthcoming FSAT. amendment.
Page 13.1-30
. Question -
- 1. Why have only 19 key positions out of 29 been filled?
- 2. How many of the back-up people (maintenance, etc.) are still missing in the organization?
- 3. How many people are now in the Nuclear Operation Organization (Projected 490)?-
- 4. Plant Staff prcjected for 233 people. How many are aow on board?
i Answer -
- 1. As mentioned previously, several of these positions will be filled by employes presently within the organization. ' We are actively recruiting internally and outside the Company to fill the ' remaining' positions to meet the need of our stated schedule.
- 2. In our op.nion, there are qply two key positions that lack back-up.
l (Asst. Maintenance Engineer and Reactor Engineer).
- 3. There are presently 131 people in Nuclear Production which are plant staff.
For further information, see Attachment A regarding staf fing. .
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i EF-2-FSAR i
- Fermi 2 Staff Position ANSI N18.1 Classification
! Assistant Maintenance Engineer Maintenance Manager
,j (Section 4.2.3) f Maintenance General Foreman Supervisor not requiring NRC license (Section 4.3.2)
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! Maintenance Foreman Supervisor not requiring NRC license (Section 4.3.2) l Journeyman Repairman (Section 4.5.3) i Randynan None Technical Engineer Technical Manager (Section 4.2.4)
Equipment Performance Engineer Technical Manager (Section 4.2.4) .
- Nuclear Instrument and Control Instrumentation and Control Eng ineer (Section 4.4. 2)
Nuclear Instrument Foreman Supervisor not requiring NRC license (Section 4.3. 2) 35 l Nuclear Assistant Instrument Super 71sor not requiring
! Foreman NRC license (Section 4.3.2) l Nuclear Instr .ent Repairman Repairmen (Section 4.5.3)
- l Engineer - General Non-Engineering Technicians Technicians (Section 4.5.2) 13.1.4.3.4 Accointment to Plant Positions a
Listed below are the positions that are filled as of this fil-ing date and a schedule for filling the other positions. See Subsection 13.1.4.3.5 for the qualifications of the assigned plant personnel.
Position Status Superintendent - Nuclear Production Filled Assistant Superintendent - Nuclear Filled Production Administrator - Nuclear Production Filled Supervisor - Operational Assur'ance Filled O
13.1-29 Amendment 35 - May 1981
EF-2-FSAR Position Status Radiation Protection - Chemical Filled Engineer
" June.
Environmental' Engineer Scheduled,4-1981 ,
Chemical General Supervisor Filled N Dece 4 er r9s t Chemical Engineer Scheduled, 11HH!
Chemist -
Filled Health Physics General Supervisor Filled 6 mm% Prior do Health Physics Supervisor Dosimetry Scheduled, -h999 .fue.\ load. -
Health Physics Supervisor Scheduled, N D.c.4ev Wal Opeeations
- c. lI eA Radwaste General Supervisor S'c;.cduled,
. 1^01 .
fo Reactor Engineer Scheduled, m.4%.& ,\plrior
,4 35 Operations Engineer Filled Assistant Operations Engineer Filled 6 months prior io Nuclear Fuel-Handling Supervisor Scheduled, itSt .Cuel l aci Nuclear Shift Supervisor Filled (o mon % p rior 4o Assistant Nuclear Shift Scheduled, -1909.pyg { jed Supervisor Maintenance Engineer Filled Novemb e r Assis ant Main,enance Engineer Scheduled,+1981 Maintenance General Foreman Filled Technical Engineer Filled l Equipmen't Performance Engineer Filled l Nuclear Instrument Control Engineer Filled i tecemb ec 1991 l Evaluation Engineer 1cheduled, -1999 Nuclear Instrument Foreman Filled December 148 l Surveillance Engineer Scheduled, 1992-l l To n e. 19 e *i Technical Engineering Supervisor Scheduled, 1999 i
l 13.1-30 Amendment 35 - May 1981 1 ~
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EF-2-FSAR '
The SPEG makes detailed recommendations for revised procedures, J.
equipment modifications, and other means of improving unit safety to the Director - Nuclear Engineering. Although this group interfaces with the onsite QA Organization, it is not an integral.part of the QA Organization.
4 Minimum qualifications for the nuclear SPEG engineers include the following: -
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- a. Education: Bachelor's degree in engineering or related sciences. The group will have a varied back-ground to cover the fields of mathematics, reactor physics, chemistry, materials, reactor thermodynam- 35 ics, fluid mechanics, heat transfer, and electrical ,
and reactor control theory.
- b. Experience: ] N$ yearsof professional-level nuclear power plant experience. Six months experience shall be associated with .the Fermi 2 plant. -
- c. Training: Knowledge in the details of design, function, arrangement, and operation of the plant l systems, control room instruments, and control
! functions.
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13.4-11 Amendment 35 - May 1981
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