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-90-0083, Discusses Action Plan to Review Socket Weld Failures at Plant.Failure History of Socket Welds Will Be Investigated to Determine Whether or Not Significant Common Mode Failure Mechanism Evident.Plan Expected to Be Completed by 9005251990-05-18018 May 1990
Discusses Action Plan to Review Socket Weld Failures at Plant.Failure History of Socket Welds Will Be Investigated to Determine Whether or Not Significant Common Mode Failure Mechanism Evident.Plan Expected to Be Completed by 900525
NRC-90-0074, Discusses Insp of Flash Tanks & Reactor Feed Pump Strainers. No Further Evidence of Moisture Separator Reheater Debris Discovered in Strainers,Stub Tubes,Wire Mesh or Structural Members1990-05-18018 May 1990
Discusses Insp of Flash Tanks & Reactor Feed Pump Strainers. No Further Evidence of Moisture Separator Reheater Debris Discovered in Strainers,Stub Tubes,Wire Mesh or Structural Members
NRC-90-0082, Documents Commitments Made During Recent Meetings & Telcon on RHR Sys Small Bore Connections1990-05-11011 May 1990
Documents Commitments Made During Recent Meetings & Telcon on RHR Sys Small Bore Connections
NRC-90-0068, Forwards 1989 Annual Financial Repts for Detroit Edison Co & Wolverine Power Supply Cooperative,Inc1990-05-0101 May 1990
Forwards 1989 Annual Financial Repts for Detroit Edison Co & Wolverine Power Supply Cooperative,Inc
NRC-90-0071, Responds to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-341/90-03 Re Emergency Preparedness Exercise Weaknesses. Corrective Actions:Case Studies Will Be Developed & Presented in Licensed Operator Requalification Training1990-04-30030 April 1990
Responds to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-341/90-03 Re Emergency Preparedness Exercise Weaknesses. Corrective Actions:Case Studies Will Be Developed & Presented in Licensed Operator Requalification Training
NRC-90-0078, Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Bow. Util Has Decided That Fuel Channel Boxes Will Not Be Used After First Bundle Lifetime1990-04-25025 April 1990
Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Bow. Util Has Decided That Fuel Channel Boxes Will Not Be Used After First Bundle Lifetime
NRC-90-0051, Responds to SALP 11 Board Rept 50-341/90-01.Outage Critique Action Plan Issued for First Refueling Outage Identifying Lessons Learned & Areas Needing Improvement1990-04-12012 April 1990
Responds to SALP 11 Board Rept 50-341/90-01.Outage Critique Action Plan Issued for First Refueling Outage Identifying Lessons Learned & Areas Needing Improvement
NRC-90-0060, Responds to 900104 Request for Supplemental Station Blackout Submittal1990-03-29029 March 1990
Responds to 900104 Request for Supplemental Station Blackout Submittal
NRC-90-0061, Forwards Addl Info Re Proposed Drywell Level Instrument Line Configuration,As Followup to 890927 Tech Spec Change Request.Rept Provides Info Re Reasons for Designating Primary Containment Isolation Valve Normally Opened1990-03-27027 March 1990
Forwards Addl Info Re Proposed Drywell Level Instrument Line Configuration,As Followup to 890927 Tech Spec Change Request.Rept Provides Info Re Reasons for Designating Primary Containment Isolation Valve Normally Opened
NRC-90-0055, Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47 - Safety Implications of Control Sys in Lwrs. Overfill Protection Sys Adequately Separated from Main Feedwater Control Sys1990-03-19019 March 1990
Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47 - Safety Implications of Control Sys in Lwrs. Overfill Protection Sys Adequately Separated from Main Feedwater Control Sys
NRC-90-0024, Suppls Response to Violations Noted in Insp Rept 50-341/85-47 Re Security Records.Util Intends to Rely Solely on Historical Tapes to Retrieve Records Required by Physical Security Plan.Hard Copy Computer Logs Will Be Discarded1990-03-16016 March 1990
Suppls Response to Violations Noted in Insp Rept 50-341/85-47 Re Security Records.Util Intends to Rely Solely on Historical Tapes to Retrieve Records Required by Physical Security Plan.Hard Copy Computer Logs Will Be Discarded
NRC-90-0045, Forwards Inservice Insp Summary Rept of 1989 Inservice Insp at Fermi 2 Nuclear Power Plant.1990-03-13013 March 1990
Forwards Inservice Insp Summary Rept of 1989 Inservice Insp at Fermi 2 Nuclear Power Plant.
NRC-90-0043, Responds to NRC 900224 Ltr Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 9002021990-03-0909 March 1990
Responds to NRC 900224 Ltr Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 900202
NRC-90-0054, Responds to NRC 900212 Order Modifying License & Notice of Violation.Corrective Actions:Former Director of Nuclear Security No Longer Works for Util & Extensive Actions Taken to Improve Communications W/Nrc1990-03-0909 March 1990
Responds to NRC 900212 Order Modifying License & Notice of Violation.Corrective Actions:Former Director of Nuclear Security No Longer Works for Util & Extensive Actions Taken to Improve Communications W/Nrc
NRC-90-0037, Forwards Completed Questionnaires for Types of Insps,Audits & Evaluations,In Response to Generic Ltr 90-01, Voluntary Participation in NRC Regulatory Impact Survey.1990-03-0505 March 1990
Forwards Completed Questionnaires for Types of Insps,Audits & Evaluations,In Response to Generic Ltr 90-01, Voluntary Participation in NRC Regulatory Impact Survey.
NRC-90-0029, Responds to Violations Noted in Insp Rept 50-341/89-36. Corrective Action:All Personnel in Operations & I&C Viewed Professionalism Video Which Included Presentation of Facts Concerning Event1990-03-0505 March 1990
Responds to Violations Noted in Insp Rept 50-341/89-36. Corrective Action:All Personnel in Operations & I&C Viewed Professionalism Video Which Included Presentation of Facts Concerning Event
NRC-90-0028, Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Revised Pages of Rept for Jul-Dec 1988, Containing Recalculated Noble Gas Releases & Doses1990-03-0101 March 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Revised Pages of Rept for Jul-Dec 1988, Containing Recalculated Noble Gas Releases & Doses
NRC-90-0034, Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results1990-02-26026 February 1990
Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results
NRC-90-0036, Forwards Response to NRC Survey on Nuclear Fuel Cycle Industry Future Activity,Per 900122 Request1990-02-26026 February 1990
Forwards Response to NRC Survey on Nuclear Fuel Cycle Industry Future Activity,Per 900122 Request
NRC-90-0026, Forwards Monthly Operating Rept for Jan 1990 for Fermi Unit 2 & Revised Rept for Dec 1989,correcting Error in Net Electrical Generation Figure1990-02-15015 February 1990
Forwards Monthly Operating Rept for Jan 1990 for Fermi Unit 2 & Revised Rept for Dec 1989,correcting Error in Net Electrical Generation Figure
NRC-90-0020, Forwards Response to Violations Noted in Insp Rept 50-341/89-31 Re Maint Support for Security Equipment.Addl Instrumentation & Control Repairmen Hired.Encl Withheld (Ref 10CFR73.21)1990-02-12012 February 1990
Forwards Response to Violations Noted in Insp Rept 50-341/89-31 Re Maint Support for Security Equipment.Addl Instrumentation & Control Repairmen Hired.Encl Withheld (Ref 10CFR73.21)
NRC-90-0010, Responds to NRC 900102 Ltr Re Violations Noted in Insp Rept 50-341/89-30.Corrective Actions:Storage Area in Machine Shop closed-out & QA1 Matl Returned to Warehouse Where Positive Controls in Effect & Shift Turnover Procedure Revised1990-02-0101 February 1990
Responds to NRC 900102 Ltr Re Violations Noted in Insp Rept 50-341/89-30.Corrective Actions:Storage Area in Machine Shop closed-out & QA1 Matl Returned to Warehouse Where Positive Controls in Effect & Shift Turnover Procedure Revised
NRC-90-0013, Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design. Subj Valves Not Used by Util1990-01-26026 January 1990
Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design. Subj Valves Not Used by Util
NRC-90-0012, Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 19911990-01-26026 January 1990
Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 1991
NRC-90-0016, Responds to 10CFR26 Re fitness-for-duty Programs.Util Conducting Testing for Drugs Described in 10CFR26,App a, Section 2.1(a) & at Cutoff Levels Defined in Sections 2.7(3)(1) & 2.7(f)(2) as of 9001031990-01-26026 January 1990
Responds to 10CFR26 Re fitness-for-duty Programs.Util Conducting Testing for Drugs Described in 10CFR26,App a, Section 2.1(a) & at Cutoff Levels Defined in Sections 2.7(3)(1) & 2.7(f)(2) as of 900103
NRC-89-0297, Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp1990-01-12012 January 1990
Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp
NRC-89-0240, Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches1990-01-11011 January 1990
Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches
1990-09-07
[Table view] |
Text
Wryne H. Jans vice presioent f
i Nuclear Operates t orth Dute Highway ISOn < Newport, Michrgan 3:3) seu tso 48166 July 5, 1985 VP-85-0134 Director of Nuclear Reactor Regulation Attention: Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Youngblood:
Reference:
(1) Fermi 2, NRC Docket No. 50-341 NRC License No. NPF-33 (2) NRC to Detroit Edison, Generic Letter 83-28,
" Required Actions Based on Generic Imolications of Salem ATWS Events", July 8, 1983 (3) Detroit Edison Letter to NRC, " Detroit Edison Response to NRC Generic Letter 83-28",
EF2-66117, dated November 3, 1983 (4) Detroit Edison Letter to NRC, " Clarification of Detroit Edison's Resoonse to Generic Letter 83-28", EF2-72014, dated November 29, 1984
Subject:
Detroit Edison Undated Status to NRC Generic Letter 03-28 Detroit Edison is providing uodated information concerning commitments made in Reference 3. The subject items are identified below, with proper reference, along with suople-mental information on the undated Fermi 2 response.
Item 1: Page 1 of Reference 3, Item 1.1 Fermi 2 Response: The recently issued INPO " Good Practice, OP-211, Post Trip Reviews" document was reviewed by Detroit Edison and its recommendations were incoroorated, where anoropriate, into Operations Procedure -
Administrative, Number 21.000.03, " Post-Scram Evaluation and Re-Start Authorization". This orocedure controls the oost-scram review orogram used at Fermi 2. A cooy of this procedure is attached to this recort.*
8507090299 DR 850705 f ADOCK 05000341 PDR' 1\0' l
j O
Mr. B. J. Youngblood July 5, 1985 VP-85-0134 Page 2
- All of the Detroit Edison procedures referenced in this response to NRC Generic Letter 83-28 are referenced to demonstrate imolementation of the responses, but they are not referenced to document commitments to the NRC. These i procedures are controlled, living documents that may change deoending on Fermi 2 operational and organizational needs.
Item 2: Page 4 of Reference 3, Item 1.1.3 Fermi 2 Response: Training is currently being orovided to those oersonnel responsible for conducting post-scram reviews at Fermi 2. This training orovides familiarization with the techniques used during oost-scram reviews including the use of the sequence of events recorders, strio charts, the olant process computer, and other devices oroviding imoortant information.
Item 3: Page 10 of Reference 3, Item 1.2.4 Fermi 2 Response: Detroit Edison requested in a letter to NRC, EF2-71999, dated November 12, 1984 that the ODerating License reflect December, 1985 as the date required for the Emergency Response Information System (ERIS) to be functional. The date was incorporated in the Fermi 2 OL for the Safety Parameter Display System (SPDS) only. The SPDS is substantially functional at this time, including aoprooriate personnel trained. All that remains for the SPDS to be formally declared functional to satisfy the License Condition is the resolution of a few minor ooen items concerning the completion of acceptance testing. This is exnected to be completed by the end of July, 1985. Detroit Edison expects to have the entire ERIS system functional by December 1985.
.e
.. Mr. B. J. Youngblood July 5, 1985 VP-85-0134 Page 3 Item 4: Page 12 of Reference 3, Item 2.1.1 Fermi 2 Response: Detroit Edison has complited a review of the Reactor Trip System (RTS) components to ensure that these components are appropriately identified as safety-related. These components include all active components of existing plant systems that function to implement a reactor scram. The results of this review indicate'that Fermi 2 has in place sufficient administrative controls and procedural practices to meet this position.
Item.5: -Pages 12 and 13 of Reference 3, Item 2.1.2.1 Page 14 of Reference 3, Item 2.1.2.2 Pages 19 through 21 of Reference 3, Item 2.2.2.1 Pages 21 and 22 of Reference 3, Item 2.2.2.2 Pages 24 and 25 of Reference 3, Items 3.1.2 and 3.2.2 Fermi 2 Response: Detroit Edison has in place a vendor interface and information program meeting the. requirements of Items 2.1.2.1, 2.1.2.2., 2.2.2.1, 2.2.2.2, 3.2.1, and 3.2.2. See also Item 2 of Reference (4). It should be noted that the Vendor Equipment Technical Information Program (VETIP) as defined in the March 1984 NUTAC document is considered a valid response to Section 2.2.2 of NRC Generic. Letter 83-28.
Detroit Edison has implemented the program as described-therein.
Item 6: Page 28 of Reference 3, Item 4.5.3 Fermi 2 Response: Detroit Edison is actively involved in the BWROG Technical Specification group. This group recently
. completed a special study of the on-line testing intervals in Technical Soecifications which is contained in Topical Report NED C-30844, January 1985. Letter BNROG-8505, January 31, 1985, provided the results of the Group's study to the NRC for its review. When the review is complete, Detroit Edison plans to use the results of this study as a basis for requesting or not requesting changes to the existing on-line testing intervals in the Fermi 2 Technical Specifications.
e
- Mr. B. J. Youngblood July 5, 1985 VP-85-0134 Page 4 The undated information in this letter is being orovided to demonstrate that Detroit Edison has addressed all items of concern and describes the manner in which all commitments made in Reference 2 have been completed.
If you have any further questions on this matter, please contact Mr. O. K. Earle at (313) 586-4211.
Sincerely, I
M cc: Mr. P. M. Byron Mr. M. D. Lynch Mr. T. E. Taylor USNRC Document Control Desk Washington, D. C. 20555
~
~
D.
te SR k Safety Classification FERMI 2 PROCEDURE - OPERATIONS - ADMINISTRATIVE TITLE: POST SCRAM EVALUATION AND RESTART AUTHORI'ZATION REV O NU R ,
ghj Name of preparer: F. E. Abramson /s/
Technically reviewed by: Guy Reece /s/ Date03/07/85 Reviewed / concurred by: W. E. Miller /s/ Date: 05/07/85 Supv - Operational Assurance Approved by: F. E. Abramson /s/ Date: 05/07/85 k Responsible Section Head or OSRO Member / Alt Further approval Required for
- Safety-Related or Superintendent-Designated Procedures:
Recommended by: R. S. Lenart /s/ Date: 05/07/85 OSRO Chairman / Alternate Approved by: R. S. Lenart /s/ Date: 05/07/85 Superintendent - Nuclear Production I
The following approved procedure Chenge Requests are incorporated in this revision: M3094 ,
This revision lfl does l l does not constitute periodic review.
- ,rxS - i'6;r,'*lil0N SYSTEMS O\T Og I DTC If M #
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MAY 101985 MAY 101985 N C ADMtN.
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APPROV Al ll[Q'D; YES. NO 1
g 21.000.03 Riv. 8 TABLE OF CONTENTS -
Page_
1 l.0 Purpose.......................................
1 20 Discussion...................................
1 E 3.0 Reference....................................
1 4.0 Definitions..................................
2 5.0 Responsibilities............................. b 4
6.0 Functions....................................
Attachments Attachment 1 Post-Scram Data and Evaluation (050285).......
Post-Scram Investigation Statement $
Attachment 2 Sheet (050285)................................
k 100/CW19/1.0 (Temp. 121A)
(
050285 e
t em-
1 21.000.03 f
asv. 8 l Prgt I l
1.0 Purpose .
l$[
11 This procedure is to provide a systematic method diagnosing the causes of unscheduled Reactor Scrams, l t ascertainin to reactor restart and making the determination that the p an can be restarted safely.
E 2.0 Discussion Post-scram reviews establish a consistent, comprehensive 21 systematic method to determine the causes and conditions assoc -
i and This documented review will help '
ated with reactor scrams.
ensure events that may have had an impact on the cause of the scram and subsequentThe equipment responses review results are identified will permit a deter- and thoroughly understood. fl mination to be made as to the readiness of the plant to sa e y return to operation.
3.0 _References _ 11.000.49, Nuclear Operations Interf acing Procedures (NOIP) 31 Document Control and Records Management
[ Deviation and Corrective Action Reporting 3.2 NOIP, 11.000.52, 21.000.01, Shift 3.3 Plant Operations Manual (POM) Procedure, Operations and Cogtrol Room Documentation of Allowable Operating 3.4 POM Procedure, 21.000.06, ,
Transients 3.5 Institute of Nuclear Power Operations (INPO) Good Practice, OP-211, Post-Trip Reviews 4.0 Definitions _
4.1 Cause - The root initiator of an event (usually Whenan the equipment cause mal .
function, procedural error or personnel error).
is corrected, the possibility of the event recurring is minimized.
4.2 Diagnostics - A systematic approach to theThis identification may include of
_ problems and "K-T" selection of appropriate (Kepner-Tregoe) method. measures.a method 4.3 Post-Scram Data - A collection of inforuation The used to con investigation and review of an unscheduled reactor s
( (Attachment 1), hard-copy recorded data and written statements from personnel involved in the event.
e
.e
. 21.000.03 j
Riv. 8 Page 3 He shall also aid condition as prescribed by the NSS. fi- ~'
the NSS is determining the required Technical S event reportability. I J
Be shall also sign the Post-Scram Data ,and Evaluation form (Attachment 1) as being in agreement with the class determination event. i The OE shall also review and sign the Post-Scram dData and Evaluation package before the package is submitte6.10 to the Technical Engineer as specified in Section of this procedure.
5.1.4 Plant Personnel TA Plant personnel involved in the unscheduled d reac objective comments that describe their observations Objective an their actions relating to the reactor scram.
comments regarding the cause of the Reactor Scram are particularily important.
Plant Superintendent - Nuclear Production 5.1.5 The plant superintendent or his delegate is responsible for authorization of a plant restart following any unscheduled Reactor Scrams.
5.1.6 Shift Tdchnical Advisor (STA)
The STA is responsible for compiling the data required on theThePost-Scram Data and STA is also responsible withEvaluation form (Attachme the NSS for the 1).
investigation phase of the post-scram review.
5.1.7 Technical Engineer _
The Technical Engineer is responsible for generating h
the necessary documents and reports to ensure t at lessons learned from unscheduled reactor d to scrams are used to improve plant safety and reliability an to the transfer in-house experience of generic interest industry.
l
21.000.03
. Rsv. 8 P:ga 5 l(
- 2. The STA shall collect written statements from plant personnel who were involved in or who ,
observed the reactor scram. The written state-ments should include the following type of information:
- a. plant conditions prior to the reactor scram (for Maintenance and I&C personnel this will include the status of maintenance or 3 testing),
- b. first indication that a problem existed,
- c. individual action as a result of the indication,
- d. subsequent indications and plant response including manual actions,
- e. noted equipment malfunctions or inadequacies,
- f. procedure deficiencies identified during the situation.
- 3. The STA shall complete the Post-Scram Data and
( Evaluation form with the aid of the control room Nuclear Supervising Operator (NS0) and the Nuclear Assistant Shif t Supervisor (NASS).
f
- a. The STA shall assign an in-sequence number to
. each Post-3 cram Data and Evaluation form used. The number shall start with the present year and then a sequential number.
At the beginning of each new year, the numbering sequence shall be zeroed. (e.g.85-001, 85-002) 6.4 Post-Scram Investigation - The NSS and the STA are responsible for the initial post-scram investigation. The purpose of this investigation is to determine the cause of the scramThe and return to to assess the plant readiness to return to operation.
include verification of the following:
operation assessment must
' 6.4.1 Systems / Functions
- 1. The Reactor Protection System operated properly.
- 2. No Emergency Core Cooling Systems were actuated with injection into the reactor vessel.
- 3. The initiating scram signal has been identified.
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21.000.03
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6.5 Scram Classification 6.5.1 Based on the results of the analysis and evaluation of
, the reactor scram and subsequent plant response, the NSS or his delegate and the STA shall classify the scram as one of the following: .
- 1. Class I - The cause of the scram is positively known and has been corrected; all safety-related and other important equipment functioned properly during and after the scram.
- 2. Class II - The cause of the scram is positively known and has been corrected; some safety-related and/or other important equipment did not function properly. However, the malfunction has been corrected or Technical Specification constraint does not prohibit a reactor start-up.
- 3. Class III - Any items specified in 6.4.1 of this procedure have not been satisfied or some safety-related and/or other important equipment functioned in an abnormal or degraded manner during the event which has not been corrected or prevents reactor start-up due to technical
[ specifications constraints.
6.5.2 If the NSS and the STA cannot agree on the scram class-ification, the Post-Scram Data and Evaluation form and associated data will be forwarded to the OSRO for eval-uation.and classification.
6.6 Notifications 6.6.1 Once the scram has been classified, the NSS or his delegate shall notify the Operations Engineer or his delegate and the Technical Engineer or his delegate to allow them an opportunity to determine thoroughness, technical accuracy and consistency of the scram investigation and sign the agreement with the scram classification.
The notification of the Technical Engineer is in addi-tion to the notification specified in 6.3.2 of this i procedure.
6.6.2 If the scram has been classified as a Class III, the OSRO chairman must also be notified.
6.7 Investigation Review 6.7.1 Class I and Class II scrams shall be reviewed by the
( OSRO during the next regularly scheduled meeting. This review is not required prior to reactor restart.
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21.000.03
6.9.2 If the cause of the scram has not been positively identified, the Superintendent - Nuclear Production shall determine if the cause and the circumstances surrounding the cause have been analyzed adequately.
He shall ensure adequate measures are taken to prevent repetitive challenges to safety systems during future power operations. .
6.10 In-House Operating Experience Review 6.10.1 The completed Post-Scram Data and Evaluation form and all associated data shall be reviewed by the OE or his delegate and sent to the Technical Engineer. The '~
Technical Engineer shall review the data and determine if the event has generic significance to plant safety and reliability. The data should also be evaluated to determine if a requirement exists for additional corrective actions such as procedure changes or design modifications. Information copies of the Post Scram Data and Evaluation form will be forwarded to Nuclear g.
Engineering and the Nuclear Safety Review Group for g their review.
The data should also be reviewed to determine if any lessons learned are applicable for incorporation into
[' Plant Staff training or for industry dissemination.
6.11 Retention 6 11.1 After the post-scram data review and evaluation has been completed, the data must be forwarded to the Record Center per reference 3.4 for record retention.
The Post-Scram Data and Evaluation form with all associated data shall be retained for the life of the plant.
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21.000.03 Attcchnert 1 Peg 2 1 cf 10
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POST-SCRAM DATA AND EVALUATION No.
1.0 Reactor Scram Data: .
1.1 Time and date of reactor scram, /
1.2 Control Room NSO on duty, . .
1.3 Initiating scram signal, 1.4 Parameter value at which initiating scram signal occurred, 1.5 Turbine trip time /date / .
1.6 Recirculation pump runback YES NO .
1.7 Recirculation pump trip YES NO .
Cause:
(
1.8 Were any control stations taken from AUTO to MANUAL YES NO .
1.8 .1 If YES, specify station and time.
2.0 Initial Condition Prior to Scram:
2.1 Reactor Mode Switch Position:
Shutdown Refuel .
Startup/ Hot Standby Run .
2.2 Reactor Power, %.
2.3 Generator Gross Load, Mwe.
2.4 Total Core Flow, Mf/hr.
2.5 Reactor Pressure, PSIG.
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050285 4
l . 21.000.03 Att chsent 1 Pegs 2 of 10
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POST-SCRAM DATA AND EVALUATION (Continued) d IN.
2.6 Reactor Water Level. _
GPM. .
2.7 Reactor Recirculation Loop A Flow - i GPM.
2.8 Reactor Recirculation Loop B Flow ,
g 2.9 RRR Division I Mode / Status -
2.10 RRR Division II Mode / Status 2.11 Reactor Feedwater Control:
2.11.1 Master Control, MAN AUTO .
Elements selected, SINGLE THREE .
2.11.2 Reactor Feed Pump A, MAN AUTO .
2.11.3 Reactor Feed Pump B, MAN AUTO .
2.11.4 2.12 Reactor Pressure Regulator in Service, A _B .
(l( 2.13 CRD Pump in Service, A B . (
2.14 Off normal status of any trains / portions of a safety systems:
Details 2.14.1 RPS 2.14.2 ECCS 2.14.3 SBGTS
' 2.14.4 Emergency Buses /
(Diesels) 2.14.5 DC Buses 2.15 Testing /Surveillances in Progress Status / Step Test Number
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21.000.03 l Attachment 1 l Page 3 of 10 1 POST-SCRAM DATA AND EVALUATION _(Continued)
)
I 3.0 Post-Scram Data _ YES NO .
31 Did all operable control rods fully insert?
3 List control rod number and notch for all operabia 3.1.1 control rods not fully inserted.
_ , Notch _
_ , Notch _
Rod __
Rod _
_ , Notch __
Rod _ _ , Notch _
Rod _ , Notch
_ , Notch _
Rod __ _
Rod _ _ , Notch Rod _ , Notch _
Rod 3.2 SRMs fully inserted YES _ NO _ .
3.3 IRMs fully inserted YES _ NO _ .
3.4 SRM Count Rate and
__ CPS, __
' 3.4.1 SRM A _ _ CPS, _ __
3.4.2 SRM B___
_ CPS, _ _
3.4.3 SRM C _
. _ CPS, __
3.4.4 SRM D YES NO .
3.5 Did any SRVs open?
d 3.5 1 List Safety Relief Valve letter, opening mo if known. PSIG Valve _, Mode _, lif t _ PSIG, Reseat _ PSIGIG, Reseat _ PSIG Valve _
_ _, Mode _, lif t _ PS G Valve
_, Mode _, lif t _ PSI , Reseat _ PSIG Valve _, Mode _, lif t _ PSIG, Reseat _ PSIG Valve Valve
_, Mode _, lif t _, Mode _, lif t _ PSIG, Reseat _ PSIG Valve _, Mode _, lif t _ PSIG, Reseat _
- Include date if different from scram date.
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21.000.03
Attechnent 1 Page 4 of 10
( f' '
l POST-SCRAM DATA AND EVALUATION (Continued) t 3.5.2 List SRVs which cycled and number of cycles, if known.
t
' 3.6 Did any isolations occur? YES NO .
3.6.1 List any isolations which occurred by group number.
1
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5 3.7 Describe, if any, the actuation of any Safety Systems and the 4 reason for their actuation.
4
- *Use additional attached description, if necessary.
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- :. _ a 21.000.03 Attcchment 1 Page 5 of 10
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POST-SCRAM DATA AND EVALUATION (Continued) 3.8 Did any process radiation monitors indicate increases in reading?
YES NO .
If YES, list parameter and attach recording chart. -
3.9 The following hard copy data is attached:
NOTE: Where data is not device recorded, a logged record of observation may be used.
(check) 3.9.1 Sequence recorder printout.
3.9.2 Process computer rod position printout.
3.9.3 Copy of the applicable pages of the NSO log.
3.9.4 Copy of the applicable pages of the NSS log.
. ( 3.9.5 APRM - A, B, C, D, E, F.
3.9.6 Reactor vessel water level.
3.9.7 Recirculation pump section temperature.
3.9.8 Core flow.
3.9.9 Reactor vessel pressure.
3.9.10 Main steam flow.
! 3.9.11 MTG control valve position.
3.9.12 Drywell pressure.
3.9.13 Torus water level.
3.9.14 Torus water temperature.
3.9.15 LPCI, CS, HPCI, RCIC flow.
3.9.16 Condenser vacuum.
l 3.9.17 Vessel metal temperature.
3.9.18 Reactor coolant chemistry ' sample results.
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. _ . , . . - . . _ . _ . _ . s . ,,__..
21.000.03 Attachment 1 Page 6 of 10
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POST-SCRAM DATA AND EVALUATION _(Continued) 4.0 Post-Scram Evaluation 4.1 Chronological Series of Events _ B
(
I 4.2 Probable Cause of Trip 1
41 l 050285
J 21.000.03 Attachment 1 i Page 7 of 10
- j (*
' POST-SCRAM DATA AND EVALUATION (Continued) ll g.
4.3 Unexpected Aspect of Transient Behavior (If event compared with previous similar transient, note the transient with*which com- '
<li
- p..;l pared.)
l Compared With PSAR transient page number Previous trip on /
r i
i 4.4 Identification of Systems with Inadequate Performance System / Component Description of Probles
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Signature Date Time ,
7 NSS ,
/
Signature Date Time STA 1
/
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21.000.03
, Attachment 1
(( Page G of 10 POST-SCRAM DATA AND EVALUATION (Continued) 5.0 Preliminary Safety Assessment ,
5.1 Transient Data for Pertinent Plant Parameters -
! '.
- 5.1.1 RCS pressure as measured Loop A B Loop A B in steam done.
5.1.2 Reactor vessel water level. in. in.
5.1.3 Reactor coolant flow. Loop A B Loop A B 5.1.4 Reactor core thermal power.
5.2 Preliminary Safety Assessment 5.2.1 RPV pressure remained above 825 psig. YES NO 5.2.2 Reactor isolation occurred. YES NO k
5.2.3 RCS pressure increased to safety / relief valve operating
< pressure. YES NO 5.2.4 RCS temperature decrease less than 100* F/hr. YES NO 5.2.5 HPCI/RCIC initiated. YES NO 5.2.6 ADS timer initiated. YES NO 5.2.7 Primary containment. press temp (ave) 5.2.8 Torus water. level temp (ave) 5.3 Scram Class Classify scram as I, II or III according to 6.5 in this procedure.
The scram on at : is a Class .
Date Time I, II, III 050285 B
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21.000.03 Attachment 1
- [ Page 9 of 10 POST-SCRAM DATA AND EVALUATION (Continued)
Signature indicates agreement with class. ,
/
NSS Date Time
/
STA Date Time
/
OE/ Delegate Date Time
/
TECH. ENG./ Delegate Date Time l Notification
{
Superintendent - Nuclear Production notified of event classification.
/
Person notified Date Time 6.0 Permission to Start-up 6.1 Class I, II Events ,
6.1.1 Superintendent - nuclear production notified and permission granted to start-up the reactor.
/
Nuclear Shift Supervisor Date Time
/
STA Date Time
/
OE/ Delegate Date Time COMMENTS k
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Attachment 1
,( Page 10 of 10 POST-SCRAM DATA AND EVALUATION (Continued) 6.2 Class III Event ,
6.2.1 OSRO review of event on , meeting number 6.2.2 Permission is granted to start-up the reactor.
/
OSRO Chairman Date Time i
Supt. -Nuclear Production Date Time 6.2.3 COMMENTS i
s 7.0 OE Review
/
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.. p 21.000.03 Attachment 2
- Page 1 of 1 POST-SCRAM INVESTIGATION STATEMENT SHEET
. 1 Name .
Time
- It
- 1. Plant conditions prior to the reactor scram (for maintenance and IEC personnel. This will include the status of maintenance or testing.)
- 2. First indication that a problem existed
- 3. Individual action as a result of the indication
- 4. Subsequent indications and plant response including manual actions
- 5. Noted equipment malfunctions or inadequacies Procedure defficiencies identified d; ring the situation fh 6.
- 7. Additional comments Signature Time - Date if additional space is required to answer the above questions, use blank paper and number the answers.
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050285 END
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