Similar Documents at Fermi |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N4261999-10-25025 October 1999
Forwards Amend 17 to License DPR-9 & Safety Evaluation. Amend Revises TS by Deleting SR D.3.c,which Required Weekly Observation of Nitrogen Cover Gas Pressure within Sodium Storage Tanks Located in Sodium Building
NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999
Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl
NRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999
Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed
ML20217P1661999-10-21021 October 1999
Forwards Insp Rept 50-341/99-17 on 990927-1005.No Violations Noted
ML20217M0771999-10-19019 October 1999
Confirms Discussion Between GL Shear,M Mitchell,E Kosky, D Williams,B Rumins,D Harmon & W Rutenberg in Public Meeting on 990923.Purpose of Meeting Was to Discuss Current Status RP Program at Enrico Fermi 2
ML20217N9231999-10-15015 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40
ML20217E5671999-10-14014 October 1999
First Partial Response to FOIA Request for Documents.Records in App a Already Available in Pdr.App B Records Encl & Being Released in Entirety
NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999
Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons
NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999
Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
ML20217D5331999-10-0707 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39
ML20217F5931999-10-0707 October 1999
Forwards Insp Rept 50-341/99-11 on 990724-0908.Two Violations Re Failure to Follow Procedures While Sampling Standby Liquid Control Tank & Wear Dosimetry Properly Being Treated as Noncited Violations
ML20217B8261999-10-0404 October 1999
Forwards Summary of Decommissioning Insp Plan for Fy 2000. Plan Will Be Updated Annually & May Be Revised at Any Time Based Upon Future Insp Findings,Events & Resource Availability
ML20212J8121999-10-0101 October 1999
Discusses Plant,Unit 2 Completion of Licensing Action for GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at Npps. Ack Efforts That Licensee Have Completed to Date in Preparing Plant for Y2K Transition
ML20212K8881999-09-30030 September 1999
Refers to 990928 Meeting Conducted at Fermi Unit 2 to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff
ML20217A3261999-09-30030 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38
NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999
Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations
ML20212J8331999-09-27027 September 1999
Responds to Licensee 990924 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3/4.6.1.8.Ltr Documents 990923 Telcon with Util in Which NRC Orally Issued NOED
ML20216G9791999-09-24024 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37
NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999
Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys
ML20216H3561999-09-23023 September 1999
Informs That During 990914 Telcon,L Sanders & M Bielby Made Arrangements with NRC to Inspect Licensed Operator Requalification Program at Fermi Nuclear Station for Week of 991129 Which Coincides with Util Regularly Scheduled Exam
ML20216H4541999-09-23023 September 1999
Informs That During 990914 Telcon L Sanders & M Bielby Made Arrangements for Administration of Licensing Exams at Fermi Nuclear Station for Week of Jan 31,2000.NRC Will Make Exam Validation Visit to Facility During Week of Jan 10,2000
ML20212F3241999-09-20020 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36
NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999
Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public
ML20217A9421999-09-0909 September 1999
Informs That NRC Plan to Conduct Addl Resident Insps Beyond Core Insp Program Over Next 6 Months to Assess Improvements in Areas of Procedural Compliance & Quality of Work. Historical Listing of Plant Issues Encl
NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999
Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
ML20211Q0991999-09-0303 September 1999
Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999
Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld
NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999
Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)
ML20211G4951999-08-24024 August 1999
Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999
Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval
IR 05000341/19990131999-08-19019 August 1999
Discusses Insp Rept 50-341/99-13 & OI Rept 3-98-039 Conducted Into Potential Misconduct of Operator Formerly Employed by De.Nrc Determined That Violation of NRC Regulations Occurred.Synopsis of IO Rept Encl
NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999
Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation
ML20211C0521999-08-17017 August 1999
Forwards Tables for Sections 3.6 & 3.7 of Draft Safety Evaluation of Proposed Conversion of Current TS to Improved Standard TS
NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999
Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
ML20217E6181999-08-13013 August 1999
FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available
IR 05000341/19990011999-08-10010 August 1999
Forwards Insp Rept 50-341/99-01 on 990619-0723 & Nov. Violation of Concern Because Operators Did Not Understand License Requirements & Placed Plant in Configuration Where EDG 11 Was Removed from Service
IR 05000341/19990121999-08-0606 August 1999
Forwards Insp Rept 50-341/99-12 on 990712-0716.No Violations Noted.Insp Focused on Implementation of Plant Chemistry & Radiological Environ Monitoring Programs & Operation of post-accident Sampling Sys
ML20211C4761999-08-0606 August 1999
Forwards Draft Safety Evaluation Re Proposed Conversion of Current TS to Improved Standard TS
NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999
Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS
ML20210N5451999-08-0303 August 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33
NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999
Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS
ML20210J2121999-07-23023 July 1999
Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation
NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999
Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl
ML20209H7211999-07-14014 July 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32
NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999
Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal
ML20209F6571999-07-12012 July 1999
Forwards Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted.Weak Procedural Guidance,Communications Issues & Configuration Control Weaknessess Were Evident
NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999
Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions
ML20196J5511999-07-0202 July 1999
Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & DE Responses & 980729 for Fermi 2.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 as Result of Review of Responses
ML20209C6141999-07-0101 July 1999
Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999
Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included
1999-09-09
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Category:INCOMING CORRESPONDENCE
MONTHYEARNRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999
Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed
NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999
Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl
ML20217N9231999-10-15015 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40
NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999
Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons
NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999
Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
ML20217D5331999-10-0707 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39
ML20217A3261999-09-30030 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38
NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999
Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations
ML20216G9791999-09-24024 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37
NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999
Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys
ML20212F3241999-09-20020 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36
NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999
Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public
NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999
Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999
Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld
ML20211Q0991999-09-0303 September 1999
Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999
Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)
ML20211G4951999-08-24024 August 1999
Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999
Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation
NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999
Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval
NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999
Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
ML20217E6181999-08-13013 August 1999
FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available
NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999
Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS
ML20210N5451999-08-0303 August 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33
NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999
Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS
NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999
Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl
ML20209H7211999-07-14014 July 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32
NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999
Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal
NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999
Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions
ML20209C6141999-07-0101 July 1999
Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0049, Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure Encl1999-06-30030 June 1999
Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure Encl
NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999
Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included
ML20209C1081999-06-29029 June 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 30
NRC-99-0050, Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included1999-06-24024 June 1999
Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included
NRC-99-0075, Forwards Operator License Renewal Application,Nrc Forms 398 & 396 for CR Effan,License SOP-30186-3.Encl Withheld1999-06-22022 June 1999
Forwards Operator License Renewal Application,Nrc Forms 398 & 396 for CR Effan,License SOP-30186-3.Encl Withheld
ML20212J3861999-06-18018 June 1999
Forwards Rev 29 to Approved UFSAR LCR That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0047, Responds to NRC 990513 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Revised Design Calculation DC-5957, GL 96-06 Calculations, Encl1999-06-0909 June 1999
Responds to NRC 990513 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Revised Design Calculation DC-5957, GL 96-06 Calculations, Encl
ML20195G2001999-06-0808 June 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 28
ML20195E7391999-06-0303 June 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 27
NRC-99-0046, Forwards Rev 6 to Fermi 2 ITS Submittal ,to Provide Remaining Responses to NRC RAI Re ITS Section 3.3, & Update ITS Submittal to Reflect Responses.Brief Abstract of Changes Contained in Attachment 11999-06-0202 June 1999
Forwards Rev 6 to Fermi 2 ITS Submittal ,to Provide Remaining Responses to NRC RAI Re ITS Section 3.3, & Update ITS Submittal to Reflect Responses.Brief Abstract of Changes Contained in Attachment 1
ML20207D9631999-05-26026 May 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section)
ML20195B3381999-05-19019 May 1999
Forwards Rev 25 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section)
NRC-99-0040, Requests NRC Approval of Revs to Weld Tables of Encl Relief Requests RR-A21,rev 1 & RR-A22,rev 1.Revs Do Not Impact Basis for Original Requests for Relief Because There Is No Change to Technical Basis or Proposed Alternative1999-05-14014 May 1999
Requests NRC Approval of Revs to Weld Tables of Encl Relief Requests RR-A21,rev 1 & RR-A22,rev 1.Revs Do Not Impact Basis for Original Requests for Relief Because There Is No Change to Technical Basis or Proposed Alternative
NRC-99-0039, Requests Relief from ASME Section XI Requirement to Examine Essentially 100% of Selected Category B-J Pipe Welds,Per 10CFR50.55a(g)(5)(iii).Relief Request RR-A23,encl1999-05-14014 May 1999
Requests Relief from ASME Section XI Requirement to Examine Essentially 100% of Selected Category B-J Pipe Welds,Per 10CFR50.55a(g)(5)(iii).Relief Request RR-A23,encl
NRC-99-0041, Requests Relief from ASME Section XI Requirements to Examine Essentially 100% of Accessible Category B-D Nozzle Welds,Per 10CFR50.55a(g)(5)(iii).Rev 1 to Relief Request RR-A6,encl1999-05-14014 May 1999
Requests Relief from ASME Section XI Requirements to Examine Essentially 100% of Accessible Category B-D Nozzle Welds,Per 10CFR50.55a(g)(5)(iii).Rev 1 to Relief Request RR-A6,encl
NRC-99-0038, Requests Relief from ASME Section XI 1980 Requirement to Examine Essentially 100% If Category B-A RPV Shell Weld Lengths,Per 10CFR50.55a(g)(5)(iii)1999-05-14014 May 1999
Requests Relief from ASME Section XI 1980 Requirement to Examine Essentially 100% If Category B-A RPV Shell Weld Lengths,Per 10CFR50.55a(g)(5)(iii)
NRC-99-0045, Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl1999-05-0707 May 1999
Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl
NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses1999-04-30030 April 1999
Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses
NRC-99-0059, Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate1999-04-29029 April 1999
Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate
ML20206E2941999-04-28028 April 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 24
NRC-99-0037, Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl1999-04-26026 April 1999
Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARNRC-90-0142, Forwards Revised Semiannual Fitness for Duty Rept,Consisting of Statement Re Percentage of Individuals Tested & Revised Graph,Per G Pirtle Request1990-09-0707 September 1990
Forwards Revised Semiannual Fitness for Duty Rept,Consisting of Statement Re Percentage of Individuals Tested & Revised Graph,Per G Pirtle Request
NRC-90-0152, Forwards Rev 3 to Radiological Emergency Response Preparedness Plan.W/O Encl1990-09-0505 September 1990
Forwards Rev 3 to Radiological Emergency Response Preparedness Plan.W/O Encl
NRC-90-0139, Responds to NRC Re Memorization of Immediate Operator Actions in Abnormal Operating Procedures (Aop). Definition of Immediate Action Under Review to Provide Mechanism for Consistent Application to All AOPs1990-08-31031 August 1990
Responds to NRC Re Memorization of Immediate Operator Actions in Abnormal Operating Procedures (Aop). Definition of Immediate Action Under Review to Provide Mechanism for Consistent Application to All AOPs
NRC-90-0116, Forwards Semiannual Fitness for Duty Rept1990-08-29029 August 1990
Forwards Semiannual Fitness for Duty Rept
NRC-90-0117, Forwards, Fermi 2 Nuclear Power Plant Semiannual Radioactive Effluent Release Rept for Jan-June 1990. No Releases Occurred1990-08-28028 August 1990
Forwards, Fermi 2 Nuclear Power Plant Semiannual Radioactive Effluent Release Rept for Jan-June 1990. No Releases Occurred
NRC-90-0118, Forwards Endorsement 35 to Maelu Policy MF-120 & Endorsement 139 to Nelia Policy NF-921990-08-24024 August 1990
Forwards Endorsement 35 to Maelu Policy MF-120 & Endorsement 139 to Nelia Policy NF-92
NRC-90-0135, Affirms That Util Intends to Conduct Insp of Low Pressure Turbine Rotor Disks During Upcoming Refueling Outage.Insp of Low Pressure Turbine 2 Carried Out During First Refueling Outage.No Evidence of Stress Corrosion Found1990-08-17017 August 1990
Affirms That Util Intends to Conduct Insp of Low Pressure Turbine Rotor Disks During Upcoming Refueling Outage.Insp of Low Pressure Turbine 2 Carried Out During First Refueling Outage.No Evidence of Stress Corrosion Found
NRC-90-0137, Forwards NPDES Permit MI0037028 for Plant,Approved by State of Mi Water Resources Commission During 900719 Meeting1990-08-17017 August 1990
Forwards NPDES Permit MI0037028 for Plant,Approved by State of Mi Water Resources Commission During 900719 Meeting
NRC-90-0136, Requests That NRC Administer Operator Licensing Exam in Dec 1990 & Postpone Operator Requalification Exam1990-08-17017 August 1990
Requests That NRC Administer Operator Licensing Exam in Dec 1990 & Postpone Operator Requalification Exam
NRC-90-0133, Forwards Rev 5 to Security Personnel Training & Qualification Plan.Rev Establishes App D & Records Retention Matrix to Provide Central Location in Plan for Info on Records Retention Pages 3-4,3-8 & 3-9.Rev Withheld1990-08-0909 August 1990
Forwards Rev 5 to Security Personnel Training & Qualification Plan.Rev Establishes App D & Records Retention Matrix to Provide Central Location in Plan for Info on Records Retention Pages 3-4,3-8 & 3-9.Rev Withheld
NRC-90-0112, Responds to NRC Re Violations Noted in Insp Rept 50-341/90-07.Corrective Actions:Review of RF01 Turbine Work Packages to Identify Where Addl Controls Should Be Placed in Similar Future RF02 Packages Conducted1990-08-0303 August 1990
Responds to NRC Re Violations Noted in Insp Rept 50-341/90-07.Corrective Actions:Review of RF01 Turbine Work Packages to Identify Where Addl Controls Should Be Placed in Similar Future RF02 Packages Conducted
NRC-90-0111, Responds to Concerns Re Open Item 90-007-04,per NRC 900627 Request.Potential Enhancements to Drawings Being Reviewed & to Be Resolved by Dec 19901990-08-0303 August 1990
Responds to Concerns Re Open Item 90-007-04,per NRC 900627 Request.Potential Enhancements to Drawings Being Reviewed & to Be Resolved by Dec 1990
ML20055H8921990-07-26026 July 1990
Forwards Certification of Financial Assurance for Decommissioning of Facility,Per 10CFR50.33(k) & 50.75. Util Intends to Retain Unit 1 in Safe Storage Status Until Unit 2 Shut Down & Decommissioned
NRC-90-0131, Forwards Rev 15 to Physical Security Plan.Rev Withheld1990-07-24024 July 1990
Forwards Rev 15 to Physical Security Plan.Rev Withheld
NRC-90-0108, Discusses Deletion of Commitment for Temporary Mod Program, Per Insp Rept 50-341/84-25.Requirement for Operations Engineer to Approve Extensions of Temporary Mods Beyond 30 Days Being Deleted from Procedure FIP-OP1-021990-07-18018 July 1990
Discusses Deletion of Commitment for Temporary Mod Program, Per Insp Rept 50-341/84-25.Requirement for Operations Engineer to Approve Extensions of Temporary Mods Beyond 30 Days Being Deleted from Procedure FIP-OP1-02
NRC-90-0093, Submits Clarification of Design for Plant Suppression Pool Temp Monitoring Sys.Design Adequate to Ensure Suppression Pool Water Temp within Allowable Tech Spec Limits1990-07-18018 July 1990
Submits Clarification of Design for Plant Suppression Pool Temp Monitoring Sys.Design Adequate to Ensure Suppression Pool Water Temp within Allowable Tech Spec Limits
NRC-90-0091, Requests Relief from Commitment to Perform 100% Audits of Tech Spec Line Items.Tech Spec Improvement Program Has Been Completed Which Provides Extensive Review of Tech Spec Line Items1990-07-0202 July 1990
Requests Relief from Commitment to Perform 100% Audits of Tech Spec Line Items.Tech Spec Improvement Program Has Been Completed Which Provides Extensive Review of Tech Spec Line Items
NRC-90-0101, Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status for Each Issue Encl1990-06-29029 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status for Each Issue Encl
NRC-90-0100, Discusses Installation of Motor Operated Valve Limiter Plates,Per IE Bulletin 85-003.Commitment to Install Limiter Plates Deferred Until Time When Valve or Valve Operator Would Be Disassembled for Another Reason1990-06-27027 June 1990
Discusses Installation of Motor Operated Valve Limiter Plates,Per IE Bulletin 85-003.Commitment to Install Limiter Plates Deferred Until Time When Valve or Valve Operator Would Be Disassembled for Another Reason
NRC-90-0088, Discusses Changes Made to Commitment Addressing Calibr Frequency for Inservice Test Instrumentation,Per Violation 87009-03.Nine-month Calibr Frequency for Subj Instrumentation No Longer Appropriate or in Use1990-06-14014 June 1990
Discusses Changes Made to Commitment Addressing Calibr Frequency for Inservice Test Instrumentation,Per Violation 87009-03.Nine-month Calibr Frequency for Subj Instrumentation No Longer Appropriate or in Use
NRC-90-0095, Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request1990-06-0606 June 1990
Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request
NRC-90-0089, Submits Supplemental Response to NRC Concerns on RHR Operability from Insp Rept 50-341/89-17.Util Faced W/ Decision to Provide Addl Overheating Protection to RHR Sys Pump Vs Maintaining Necessary Water Coverage of Fuel1990-06-0404 June 1990
Submits Supplemental Response to NRC Concerns on RHR Operability from Insp Rept 50-341/89-17.Util Faced W/ Decision to Provide Addl Overheating Protection to RHR Sys Pump Vs Maintaining Necessary Water Coverage of Fuel
NRC-90-0085, Provides Plans for Eliminating Temporaary Mods at Plant,Per Insp Rept 50-341/90-051990-05-29029 May 1990
Provides Plans for Eliminating Temporaary Mods at Plant,Per Insp Rept 50-341/90-05
NRC-90-0074, 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-90-0083, 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-90-0082, 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-90-0054, 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-90-0043, 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-90-0037, 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-90-0012, 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-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-89-0297, Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp1990-01-12012 January 1990
Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp
NRC-89-0240, Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches1990-01-11011 January 1990
Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches
1990-09-07
[Table view] |
Text
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April 22, 1987 NRC-87-0033 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555
Reference:
Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Transmittal of Supplemental Information to Close Open Item 85-003-01.
This letter provides the supplemental information demonstrating that the concerns identified in Open Item 85-003-01 have been addressed and the corrective action implemented. This open item was established as a result of the inspection conducted by Messrs. S. G. DuPont and D. E. Hills of NRC Region III on January 14 through February 22, 1985.
Detroit Edison considers this atem closed with no further action required.
If any further information is required, please contact Patrick S. Thurman at (313) 586-4213.
Sincerely, M.
- F. E. Ag sti Vice President I Nuclear Operations
]
Enclosure i cc: Mr. A. B. Davis Mr. M. D. DuPont ,
Mr. E. G. Greenman !
Mr. D. E. Hills l Mr. W. G. Rogers l Mr. J. J. Stefano '
USNRC Region III l
\ i 8704270019 870422 PDR G
ADOCK 05000341 PDR M/ )
l t I ;
i
Enciccuro to NRC-87-0033 Page l' RESPONSE TO NRC INSPECTION REPORT 50-341/85-003 :
OPEN ITEM 85-003-01 Statement of Open Item 85-003-01 The inspector reviewed the following surveillance procedures for conformance with Technical Specifications. The review included acceptance criteria and requirements to determine conformance with Limiting Conditions of Operations (LCO) and determination of component or system operability:
Division I LPCI and Suppression Pool Cooling 24.204.01 Rev. 1 and Spray Pump and Valve Operability Test 24.204.02. Rev. 2 LPCI and Suppression Pool Cooling and Spray System Discharge Piping Fill and Valve Lineup Verification 24.206.02 Rev. 1 RCIC Cold Shutdown Valve Operability and Timing Test
, 24.206.03 Rev. 1 RCIC Discharge Piping Venting and Valve Lineup Verification i 24.206.04. Rev. 1 RCIC Flow Rate Test - 150 psig 24.206.05, Rev. O RCIC System Local Valve Position Indication Verification 24.307.01. Rev. 2 Emergency Diesel Generator (EDG) 11 ECCS Start with Loss of Offsite Power Test 24.404.05. Rev. 2 Standby Gas Treatment System Local Valve Position Verification 24.207.10. Rev. 1 Reactor Building Closed Cooling Water Local Valve Position Verification The above procedures perform two functions, the specific Technical l Specification surveillance for operability and the Section 4.0.5.
Inservice Testing (IST) requirements. However, the American Society !
Enclocuro to NRC-87-0033 Page 2 of Mechanical Engineers Boil'er Pressure Vessel Code (ASME)Section XI requirement for declaring a valve inoperable if a valve fails to exhibit the correct change of valve stem or disc position and cannot be collected within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is in conflict with Technical
-Specifications which requires declaring.the valve inoperable immediately.upon; discovery of the condition. .Since the Section XI '
statement is in the Technical Specification surveillance procedure's !
general instruction, confusion can exist with declaring a valve or l system inoperable and therefore a Technical Specification Action Statement to an LCO could be violated. Detroit Edison is in agreement ,
and has committed to clarify or remove the Section XI requirement '
where it conflicts with the Technical Specification. This is an open inspection ites (341/85-003-01 (DRS)) and will be inspected with the l remainder of the Technical Specification surveilbnces prior to the l unit achieving five percent power. j In addition to procedure review. the inspector reviewed the completed surveillance 24.207.10 and found the following discrepancies as part of open inspection item (341/85-003-01): The independent position. ;
verification sheet (Attachment 3 to 24.207.10) was initialed by the l same person that had also performed the surveillance. Additionally, the pen and ink corrections made during the initial run of the !
surveillance were not correctly implemented by the Temporary Change Request (Enclosure 2 of Procedure 12.000.18) was not the correct.
checklist for an initial run of a surveillance. Since these discrepancies were also identified by the licensee's Quality Assurance during a current audit. this is not an item of noncompliance and is part of open item 341/85-003-01. The inspector will verify the licensee's corrections with the review of surveillance procedures prior to Fermi 2 achieving five percent power.
Corrective Action Taken Open Item 85-003-01 had two parts. The first concern dealt with conflicting instruction regarding valve inoperability. The second concern was with the improper implementation of a particular surveillance procedure. Detroit Edison's resolution of these two concerns are discussed below.
The first concern raised in Open Item 85-003-01 was the potentially conflicting direction provided by the ASME Section XI requirements and the Plant Technical Specifications. The conflicting information was removed from the surveillance procedures as is evident in the attached documents. The procedures now direct the user to consult only the e
I
,_ _ _ . _ _ . _ _ _ _ . _ . _ _ _ _ . _ _ . _ _ _ _ . . _ . = . -
Encic:ura to NRC-87-0033 Page 3 Technical Specifications if guidance on valve inoperability is needed.
The title page and all affected pages to various surveillance procedures resolving this open item are provided for your review.
The attached procedures are as follows:
24.204.01 Rev. 8 Division I LPCI and Suppression Pool Cooling / Spray Pump and Valve Operability Test.
24.204.02 Rev. 6 RHR Valve Lineup and System Filled Verification.
24.206.02 Rev. 4 RCIC Cold Shutdown Valve Operability and Timing Test.
24.206.04 Rev. 9 RCIC Flow Rate Test at 150 PSIG.
24.206.05 Rev. 3 RCIC System Local Valve Position Indication Verification and Timing Test.
24.307.01 Rev. 5 Emergency Diesel Generator No. 11 - ECCS Start with Loss of Offsite Power Test.
24.404.05 Rev. 3 Standby Gas Treatment System Local Valve Position Indication Verification Test.
24.207.10 Rev. 5 RBCC/EECW Local Valve Position Indication Verification Test.
The second concern was with the improper implementation of surveillance procedure 24.207.10. The independent position verification sheet was initialed by the same person conducting the su rveillance. In addition, the pen and ink corrections made during the initial run of the survelliance were not correctly implemented.
Plant Operations Manual (POM) Procedure 12.000.18. " Surveillance Program" was revised to incorporate the correct checklist as well as other improvements. Surveillance 24.207.10 was conducted again using the proper checklists and the independent position verification was performed by someone other than the person who performed the surveillance.
Based on the procedural changes and additional audits. Detroit Edison considers this open item closed.
.j ..
FERMI 2 PROCEDURE - OPERATIONS SURVEILLANCE TITLE: Div I LPCI and Suppression Pool Cooling / Spray Pump and Valve Operability Test PROCEDURE NUMBER: 24.204.01 REVISION: 8 SAFETY CLASSIFICATION: SR i B. G. Catanese Name of preparer Anna D. Wells /s/ Date 07-08-86 Administrative Format Reviewer R. M. O'Sullivan /s/ Date 07-08-86 Technical Reviewer (s)
Date Date W. E. Miller /s/ Date 07-11-86 Supervisor, OA M. W. Shields /s/ Date 07-11-86 Resp Section Head or OSRO Member / Alternate Further Approval Required for SR or SP Procedures:
J. D. Leman /s/ Date 07-11-86 OSRO Chairman or Alternate J. D. Leman /s/ Date 07-11-86 Plant Manager The following approved Procedure Change Requests are incorporated in this revision:
T3991 This revision l l does lX)doesnot constitute periodic review.
Revision Sumusary: [if used]
WALK THROUCH SICNATURES:
R. Eberhardt /s/ 07-11-86 Joseph !!. Plona /s/ 07-11-86 ARMS - INFORMATION SYSTEMS DTC TPPADM DSN 8 ddNd/ Rev 7 Date IhD PIS PIS File 1703.02 Recipient 9N
r 1 POM 24.204.01
- Revision 8 Page 6 .
3.0 REQUIRED EQUIPMENT 3.1 Vibration Analyzer Equipment (to be provided by and operated by the Technical Group).
3.2 A hose with connectors, suitable for venting the Drywell Spray discharge piping.
3.3 Stopwatch with 1/10th second timing capability.
3.4 Two 0-15 PSIG Test Gauges 3 2% accuracy or better (to be provided by the Tech Group).
4.0 PRECAUTIONS AND LIMITATICNS 4.1 The Surveillance Test should be terminated.promptly ugan indication of: Excessive pump vibration, binding, unusual noise, overheating or other erratic operation. Notify the NSS and take corrective action before resuming the test.
4.2 Ensure that no other testing or maintenance is in progress that will adversely af fect the performance of_ this test._
g 7 4.3 Refer to applicable Technical Specification Limiting Condition for Operation for required action if a pump or valve is declared ,
INOPERABLE.
4.4 If test results v0 a ical Specification Limits, notify the NSS immediately.
4.5 When using the heat exchanger as [w maintain a flow rate of < 11000 GPM and when in thi no vice water must be maintained at > 3500 GPM through heat e er.
5.0 PREREQUISITES 5.1 The NSS has given permission to perform this test on the surveillance performance form.
5.2 Verify the RHR System is properly filled and vented prior to operating the RMR Pumps by performing applicable sections of Operations Procedure - System #23.205 " Residual Heat Removal System".
5.3 Record the following:
Stop Watch Serial f Cal Exp. Date
s
- FERMI 2 PROCEDURE - OPERATIONS - SURVEILLANCE TITLE: RHR Valve Lineup and System Filled Verification PROCEDURE NUMBER: 24.204.02 REVISION: 6 SAFETY CLASSIFICATION: SR -
W. Black Name of preparer W. McKee /s/ Date 09/24/86 Administrative Format Reviewer S. V. Heard /s/ Date 10/04/86 Technical Reviewer (s)
Date Date N/A Date Supervisor, OA S. J. Booker /s/ Date 12/09/86 Resp Section Head or OSRO Member / Alternate Further Approval Required for SR or SP Procedures:
W. M. Tucker /s/ Date 12/09/86 OSRO Chairman or Alternate W. M. Tucker /s/ Date 12/09/86 Plant Manager The following approved Procedure Change Requests are incorporated in this revision:
M4883 This revision lXldoes lldoes not constitute periodic review.
Revision Summary:
Add valves Format Title Change ApMS - INFORMATION SYSTEMS DTC TPPADM DSN U SM ODYMRev 6 Date /c)*h
- PIS PlS File 1703.02 Recipient /N[
m
=
a
- POM 24.204.02 Revision 6 Page 4 ,
4.0 PRECAUTIONS AND LIMITATIONS 4.1 Observe standard radiological control practices when venting water from the RHR system piping.
4.2 If tests results violate Technical Specification limits, notify the Nuclear Shift Supervisor (NSS) immediately. -
4.3 Ensure that no other testing or maintenance is in progress that will adversely affect the
~
performance of this test.
f 4.4 Refer to applicable Technical Specifications Limiting Cond; tion for Operation for required acticrtif a valve is declared inoperable.
N ~ _ %
4.5 During the valve lineup verif! cation,if a valve is found out of position do not change its position without permission from the NSS.
4.6 The test should be terminated promptly upon indication of any test related abnormality.
The NSS should be notified before resuming.
4.7 When performing Attachment 2. verify the LPCI System discharge piping is filled with water in accordance with Technical Specifications 4.5.1.a.1.s. and 4.5.2.1. Any venting operation which int cates that the system was not filled should be reported to the NSS, the cause investigated and corrected.
5.0 PREREQUISITES j '
5.1 The NSS has given permission rm this test on the Surveillance Performance Form.
5.2 The Residual Heat Removal (RHR) s aligned to the Standby Mode or shutdown cooling mode in accordance with app ortions of System Operations Procedure 23.205,
5.3 Verify all radiation protection requirements a s listed on the RWP, if required.
54 The Domineralized Water System in service in accor with System Operations Procedure 23.104, " Condensate Storage and Transfe
.k .
FERMI 2 PROCEDURE - OPERATIONS - SURVEILLANCF, TITLE: RCIC Cold Shutdown Valve Operability and Timing Test PROCEDURE NUMBI.R: 24.206.02 REVISION: 4 SAFETY CLASSIFICATION: SR D. Powel Name of preparer R. E. Webb /s/ Date 01/22/87 Administrative Format Reviewer Robin D. Blair /s/ Date 01/04/d7 Technical Reviewer (s)
Date Date J. J. Wald /s/ Date 02/02/87 Supervisor, OA Stephen J. Book 2r /s/ Date 02/01/87 Resp Section Head or OSRO Member / Alternate Further Approval Required for SR or SP Procedures:
R. S. Lenart /s/ Date 02/02/87 OSRO Chairman or Alternate R. S. Lenart /s/ ,
Date 02/02/87 Plant Manager The following approved Precedure Change Requests are incorporated in this revision:
T4687 This revision l ldoes ht}/oesnot constitute periodic review.
Revision Summary:
Step 5.5 - Change Te:S Group to I&C Attachment 1, Step 1.5 - Change Tech Group to I&C Attachment 1 - Add steps to close the E51-F012, and reopen Attachment 3 - Add step in Second Verification to Check Open WALK THROUGH SIGNATURES R. Eberhardt /s/ 02/02/87 L. D. DeLucia /s/ 02/02/87
- 0. K. Earle /s/ 02/02/87 ARMS - INFORMATION SYSTEMS DTC TPPADM DSNh/'44 24 )fl c/~) Rev 4 Date ? 757 PIS PIS Tile 1703.02 Recipien 3k
onlylpor AP'11.00$d7!8 CdPY'.l3 pqproved foriemporary issue FERMI 2 PROCEDURE - OPERATIONS - SURVEILLANCE i TITLE: RCIC Flow Rate Test at 150 PSIG PROCEDURE NUMBER: 24.206.04 REVISION: 9 SAFETY CLASSIFICATION: SR R. Blair Name of preparer R. E. Webb /s/ Date 01/27/87 Administrative Format Reviewer Milton E. Nichols /s/ Date 01/31/87 Technical Reviewer (s)
Date Date
- 3. Wald / Pen Merdeent /,/ Date 02/19/87 Supervisor. OA R. A. May /./ Date 02/10/87 Resp Section Head or OSRO Member /Atternate Further Approval Required for SR or SP Procedures:
P. S. Lenart /s/ Date 02/19/87 OSRO Chairman or Alternate R. S. Lenart // Date 02/19/87 Plant Manager The following approved Procedure Change Requests are incorporated in this revision:
T4759 This resision lldoes kldoes not constitute periodic review.
Revision Summary:
Change flow controller set point to incorporate worst case Instrument drift.
This PCR written to replace original PCR T4699 WALK THROUGH SIGNATURES:
Farzin N. Ghodsi /s/ 02/19/87 John Bobba /s/ 02/19/87 John R. Bass /s/ 02/19/87 F. E. Abramson /s/ 02/19/87 ARMS - INFORMATION SYSTEMS DTC TPPADM DSN Rev_ 9 Date PlS PIS File 1703.02 Recipient
k POM 24.206.04
- *- R;visicnaf Pcgo 4 3.0 REQUIRED EQUIPMENT NONE 4.0 PRECAUTIONS AND LIMITATIONS 4.1 The test should be terminated promptly upon indication of any test related abnormality. The NSS notified before resuming.
, m 4.2 Refer to applicable Technical Specifications Limiting Conditions for Operations for required action if a pump or valve is declared INOPERABLE. ___
_j
. _/- -~
4.3 The Turbine Bypass Valves must be open at least 1-2%, to absorb the pressure transient, to prevent a Reactor Scram due to a RPV water level transient.
4.4 Concur with the NSS that no other testing or maintenance is in progress that will adversely affect the performance of this test.
4.5 If test results violate Technical Specification limits, notify the MSS imediately.
4.6 During operation, the RCIC System steam lines contain radioactive steam at Reactor pressure. Observe proper radiological controls.
4.7 Minimize RCIC Turb ey id N00 oY<edecethe dtegJ \fndb71 x'hinf valve possibility of low l dolfdd d3 ut And s laming .
4.8 The Suppression Pool water level and maximum average temperature shall be maintained in accordance with Fermi 2 Technical Specifi:ations, Section 3.6.2.1.
5.0 PREREQUISITES 5.1 The NSS has given permission to perform this test on the Surveillance Performance Form.
5.2 Condensate Storage Tank level is >18 feet, Condensate Storage Tank Level Recorder LRE-Pll-R801 TCOP Hll-P805).
5.3 Perform Operations Surveillance Procedure 24.206.03, "RCIC Discharge Piping, Venting and Lineup Verification" Section, "RCIC System Discharge Piping Fill Verification", prior to Operating the RCIC Systen to verify that the discharge oiping is full of water.
c . .
POM 24.206.02 Revision 4 '
Page 4 2.2.6 Drawings 6M721-5709-1 Reactor Core Isolation Cooling (RCIC) System Sketch, Functional Operating Sketch 61721-2231-3 Schematic Diagram - RCIC Stm. Line Inboard Isol. Viv. and Trip &
Throttle Viv. F.5150-F007 & F059 61721-2231-5 Schematic Diagram - RCIC Pump Disch Valves to F.W. Header E5150-F012 &
F013 2.2.7 N.E.-5.6-IST Inservice Testing Program (Plan) for Pumen and Valves - Fermi 2 Power Plant.
3.0 REQUIRED EQUIPMENT 3.1 A stopwatch with a 1/10 second timine, capabilitv.
3.2 Communication equipment as required.
3.3 Jumper (s) 3.4 Screwdriver 3.5 Key 841 and Key #141 for Relay Room Cabinets H11-P820 and H11-P822 respectively.
4.0 PRECAUTIONS AND LIMITATIONS 4.1 The surveillance test should be terminated promptly upon indication of any test related abnormality. The Nuclear Shift Supervisor (NSS) should be notified before resuming.
4.2 Ensure that no other testing or maintenance is in progress that will adversely affect the performance of this test.
~ - .s %
4.3 Refer to applicable Technical Specification Limiting conditions I for Operation for required action if a valve is declared INOPERABLE. p 4.4 If test results violate Technical Specification ilmits, notify the MSS immediately.
i l
5.0 PREREQUISITES I 5.1 The NSS has given permission to perform this test on the l Surveillance Performance Form. l
w
, ,.:s . ;u s -- ~ ~-
e o
o OPERATIONS - SURVEILLANCE PERMI 2, PROCEDURE -
RCIC SYSTEM LOCAL VALVE POSITION INDICATION TITLE: VERIFICATION AND TIMING TEST 24.206.05 PROCEDURE NUMSER: f 3 '
REVISION:
SR SAFETY CLAS$1FICATION:
Name of preparer Richard J. Heck Date __ Administrative Format Reviewer N/A Technical Reviewer (s)
Date 07-29-86 M. Nye /s/ Date Date Supervisor OA Date 07-29-86
!! E. Miller /s/ _ Resp Section Head or OSRO Date 07.29-86 R. J. Filipek / s/ Member / Alternate Further Approval Required for SR or SP Procedures:
OSRO Chairman or Alternate Date 07-29 86 R. S. Lenart /s/ Plant Manager Date 07-29 86 R. S. Lenart /s/
i evision:
The following approved Procedure Change Plequests are incorporated M4780 constitute periodic review.
This revision lldoes Kldoes not Revision Summary; This Procedure has a Title Change Walk Through Signatures:
07-29 66 R. Eberhardt /s/ 07-29-86 Farrin N. Chodst /s/
ARMS - INFORMATION SYSTg/ Detej-/E 3 D OSN , t M. 2R2)(s.5f Revy7 I DTC TPPADM _ Recipient-44MS
_Fele 1703 02 _
_PIS_
PlS l
.. +
4
.y POM 24.206.05
. Revision 3 Page 5 4.0 PRECAUTIONS AND LIMITATIONS 4.1 The test should be terminated promptly upon indication _of any test related abnormality.. The NSS shall be notified, the cause investigated and cleared before the test is resumed.
4.2 Ensure that no other testing or maintenance is in progress that will adversely affect the performance of this test.
4.3 If test results violate Technical Specification limits, notify the NSS immediately. _
4.4 Refer to applicable Technical Specification Limiting Conditions for Operation for required action if a valve is declared I
INOPERABLE.
N 7 5.0 PREREQUISITES 5.1 The NSS has given permission to perform this test on the Surveillance Performance Form.
5.2 TheReactorPJant is in Condition 5, REFUELING, or Condition 4, COLD SHUTDOWN.'
5.3 All radiation protection requiremen h met, as listed on the RWP, if required. L 5.4 Technical Grou available to install jumpers and liftleaj ring the performance of Attachment.1.
6.0 PROCEDURE 6.1 General Instructions 6.1.1 Any problems encountered during the performance of this test shall be noted on the Surveillance Performance Form (SPF). This includes problems in meeting specific pump and valve acceptance criteria.
6.1.2 To time the stroke of the valve, start the stopwatch J
when the CLOSED (OPEN) pushbutton is depressed. Stop <
the stop watch when the red (green) backlit OPEN (CLOSED) light goes out. Inter the closing time to the nearest 1/10th second.
6.1.3 Compare all test results with the given acceptance criteria at all times throughout the test period.
6.1.4 All controls and indications for the RCIC System are located on COP H11-P601, unless otherwise noted.
]
.s e.
O FERMI 2 PROCEDURE - OPERATIONS - SURVEILLANCE TITLE: Emergency Diesel Generator No. 11 - ECCS Start With Loss of Offsite Power Test PROCEDURE NUMBER: 24.307.01 REVISION: 5 b\I lylN ~lO*db i
M I5rr ,Lk35P~ltu U WL SAFETY CLASSIFICATION: SR J. F. Fix Name of preparer 1
Richard Webb /s/ Date 02/11/87 Administrative Format Reviewer Walter Schumitsch /s/ Date 02/18/87 Technical Reviewer (s)
Date Date n/a Date Supervisor, OA F. J. Svetkovich /s/ Date 03/10/87 Resp Section Head or 05i10 Member / Alternate Further Approval Required for SR or SP Procedures:
R. S. Lenart /s/ Date 03/10/87 OSRO Chairman or Alternate i
R. S. I.enart /s/ Date 03/10/87 Plant Manager The following approved Procedure Change Requests are incorporated in this revision:
i M4551 4
i This revision l ldoes lXl does not constitute periodic review. I i
! Revision Summary:
Make ch maes per DER-NP-85-0663 and NP-85-0113 Change format, DER NP-86-0278 i
ARMS - INFORMATION SYSTEMS DTC TPPADM DSN RCM 9,% 3 fl.ClRev 5 Date 3 - ~1-0 PIS PIS File 1703.02 Recipient M N 8 1
N S
'i Revision 5 Page 5 C 4.6 If test results violate Technical Specification limits, notify y immediata1v.
4.7 Refer to applicable Technical specification Limiting Condition for Operation for required action, if an EDG is declared INOPERABLE.
/
4.8 Do not synchronise EDG #11 to the electrical grid under conditions of grid instability to assure plant safety is not degraded.
4.9 If the engine has been prelubed and not started, the engine must be hand barred one revolution.
4.10 Ensure that EDG fil Engine Control Mode Switch (43) is in Maintenance Pull-Out when connecting or disconnecting the visicorder connection lead wires at terminals inside of the local control panel to prevent an inadvertent start of the diesel. EDG
- 11 will be inoperable while in Maintenance Pull-Out.
4.11 EDG fil will rable during performance of steps 71.1 through 77.0. 1 4.12 During this test, clo p A/B Discharge Crosstie Valve E11-F010 will place i an ACTION statement per Reference 2.1.10. ,
4.13 During this test, the following systems the affected by an initiation of Containment Isolation signals 'and/or ESF system actuation signals resulting from a loss of power (includes Reactor Protection System Power). /
4.13.1 Residual Heat Removal System 4.13.2 Drywell Floor and Equipment Drains i; 4.13.3 Traversing Incore Probe System 1
4.13.4 Reactor Water ' Cleanup System 4.13.5 Torus water Management System
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/
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24.404.05 Rav. 3 Safety-Related Safety-Designation FERMI 2 POM PROCEDURE - OPERATIONS TITLE: STANDBY GAS TREATMENT SYSTEM LOCAL VALVE POSITION INDICATION VERIFICATION TEST ,
PROCEDURE NUMBER: 24.404.05 REVISION NUMBER: 3 Vili00l\NiAT;0N Oh113 PREPARED BY: C. Fazio DATE:2/9/85 TECHNICAL REVIEW BY: [ f / u wd ATE: .9/) 04'f
//
SUBMITTED BY: F. E. Abra..ison /s/ DATE: 02 /25 /85 (P.esponsible Section Head / Delegate RECOMMENDED BY: W. E. Miller / E. Mordecai /s/ DATE: 02 /25 /85 (Supervisor-Operational Assurance / Delegate)
APPROVED BY: F. E. Abramson /s/ DATE: 02 /25 /85 (Responsible Section Head / Delegate)
- RECOMMENDED BY: J. A. Nycuist /s/ DATE: 02 /25 /85 (OSRO Chairman / Alternate)
- APPROVED BY: J. A. Nvouist /s/ DATE: 02 /25 /85 (Superintendent-Nuclear Production / Delegate)
- Signatures required for Safety-Related or Superintendent-Designated procedures.
ARMS - INFORMATION SYSTEMS 3
h EDLSog N.
oTc.1[f.dk/h 0$n.2LC1 M - WY O'O
. Pact nEv.:. J. c6 MAR 011985 gtm01 1385 P.I.S.:
P.I.S.- NOC ADM Hgg APPROVAL REQ'D: Y ES.. ... .. N0. tHFORMAVO
./' -
24.404.05 R2v. 3 l e Page 2 ,
2.10 Drawings i 7M721-2709 Diagram - Standby Gas Treatment and Primary Containment Purge System -
Reactor Building GM721-5737- Standby Gas Treatment System FOS 2.11 Functional System Description, Standby Gas Treatment System, T46-00-SD 1
2.12 N.E.-56-IST Inservice Testing Program (Plan) for Pumps and Valves
- - Fermi 2 Power Plant.
1 3.0 Required Equipment 3.1 None 4.0 Precautions and Limitations
- 4.1 The test should be terminated promptly upon indication of any
{
test related abnormality. The NSS should be notified before resuming. ,
t ,
I 4.2 Refer to applicable Technical Specification Limiting Conditions I
for Operation for required action if the valve is declared INOPERABLE. _
J 4.3 D' -
If test resqL v : c ir i ,Sp 1 L :alflon limits, notify ,
the NSS immedi d.e . < .-
4 l, i
1 4.4 Ensure that no other testing or maintenance is in progress that will adversely affect the performance of this test.
5.0 Prerequisites 5.1 The NSS has given permission to perform this test on the Surveillance Performance Form.
5.2 The Reactor Plant is in Condition 5, REFUELING, or Condition 4, COLD SHUTDOWN and the Drywell is deinerted.
5.3 Verify all radiation protection requirements are set, as listed on the BWP, if required.
5.4 The Standby Gas Treatment System is in the Standby Mode.
f
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e ,
. I FERMI 2 PROCEDURE - OPERATIONS - TECHNICAL !
RBCCW/EECW Local Valve Position Indication g
,-3 TITLE:
() Verification Test [
}
PROCEDURE NUMCER: 24.207.10
' i REVISION: 5 t
/
SAFETY CLASSIFICATION: SR r
l K. LeCompte Name of preparer ?
i W. J. Black /s/ Date 07/11/86 Administrative Format Reviewer l
{
C. H. Schuman /s/ Date 07/17/86 Technical Reviewer (s) i Date -
Date 8 t
J. J. Wa'd /s/ Date 07/19/86 Supervisor, O A
}
M. W. Shields /s/ Date 07/19/86 Resp Section Head or OSRO Member / Alternate Further Approval Required for SR or SP Procedures: .,
R S Lenart /s/ Date 07/19'86 OSRO Chairman or Alternate R. S Lenart /s/ Date 07/19/86 Plant Manager ,
The following approved Procedure Change Requests are incorporated in this revision:
M4747 This revision lldoes [Xldoes not constitute periodic review. ,
1 Revision Summary:
l
%FORg0% OMO I
l ARMS - INFORMATION SYSTEMS DTC TPPADM DSN M M M ,/d Res 5 Date 74 b _
PIS Pts File 1703 02 Recapient wf4[
/
O
POk24.207.10 R:visi:n 5 Page5 t
3.0 REQUIRED EQUIPMENT None 4.0 PRECAUTIONS AND LIMITATIONS 4.1 The surveillance test should be terminated promptly upon indication of: excessive valve vibration, jerky valve motion, binding, unusual noise, overheating or other erratic
! operation. Notify the NSS and take corrective action before resuming that test.
4.2 Ensure that no other testing or maintenance is in progress that will adversely affect the performance of this test. - ~
I 4.3 Refer to applica nical Specification Limiting Conditions for operation for required action if a pump or valve is declared inoperable. N -
~ _ _ _ -
4.4 If test results violate Technical Specification limits, notify the NSS immediately.
. 4.5 Ensure that no other E.E CW testing is being peformed while this test is being conducted.
4.6 Ensure that no other Drywell Pressure testing is being performed while this test is being conducted.
4.7 Do not perform this test with t or Recirc Pumps in operation.
5.0 PREREQUISITES 5.1 The NSS has given permission to peform this test in accordance w th General Administrative Proceduro 12.000.18, Surveillance Program.
5.2 Verify the plant is in Condition 5, REFUELING, or in Condition 4, COLD SHUTDOWN.
5.3 The RBCCW System operating and EECW System in standby,in accordance with System Operations Procedure 23.127. Reactor Bldg. Closed Cooting Water / Emergency Equip Cooling Water System.
54 A Radiation Work Pemit has been issued, if required. In accordance with General Administrative Procedure 12.000.13. Radiation Work Permit.
5.5 The Reactor Recirc System must be shutdown in accordance with System Operations Procedure 23.138.01, Reactor Recirculation System b
I
