Similar Documents at Fermi |
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N4261999-10-25025 October 1999
Forwards Amend 17 to License DPR-9 & Safety Evaluation. Amend Revises TS by Deleting SR D.3.c,which Required Weekly Observation of Nitrogen Cover Gas Pressure within Sodium Storage Tanks Located in Sodium Building
NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999
Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl
NRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999
Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed
ML20217P1661999-10-21021 October 1999
Forwards Insp Rept 50-341/99-17 on 990927-1005.No Violations Noted
ML20217M0771999-10-19019 October 1999
Confirms Discussion Between GL Shear,M Mitchell,E Kosky, D Williams,B Rumins,D Harmon & W Rutenberg in Public Meeting on 990923.Purpose of Meeting Was to Discuss Current Status RP Program at Enrico Fermi 2
ML20217N9231999-10-15015 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40
ML20217E5671999-10-14014 October 1999
First Partial Response to FOIA Request for Documents.Records in App a Already Available in Pdr.App B Records Encl & Being Released in Entirety
NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999
Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons
NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999
Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
ML20217D5331999-10-0707 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39
ML20217F5931999-10-0707 October 1999
Forwards Insp Rept 50-341/99-11 on 990724-0908.Two Violations Re Failure to Follow Procedures While Sampling Standby Liquid Control Tank & Wear Dosimetry Properly Being Treated as Noncited Violations
ML20217B8261999-10-0404 October 1999
Forwards Summary of Decommissioning Insp Plan for Fy 2000. Plan Will Be Updated Annually & May Be Revised at Any Time Based Upon Future Insp Findings,Events & Resource Availability
ML20212J8121999-10-0101 October 1999
Discusses Plant,Unit 2 Completion of Licensing Action for GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at Npps. Ack Efforts That Licensee Have Completed to Date in Preparing Plant for Y2K Transition
ML20212K8881999-09-30030 September 1999
Refers to 990928 Meeting Conducted at Fermi Unit 2 to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff
ML20217A3261999-09-30030 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38
NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999
Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations
ML20212J8331999-09-27027 September 1999
Responds to Licensee 990924 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3/4.6.1.8.Ltr Documents 990923 Telcon with Util in Which NRC Orally Issued NOED
ML20216G9791999-09-24024 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37
NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999
Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys
ML20216H3561999-09-23023 September 1999
Informs That During 990914 Telcon,L Sanders & M Bielby Made Arrangements with NRC to Inspect Licensed Operator Requalification Program at Fermi Nuclear Station for Week of 991129 Which Coincides with Util Regularly Scheduled Exam
ML20216H4541999-09-23023 September 1999
Informs That During 990914 Telcon L Sanders & M Bielby Made Arrangements for Administration of Licensing Exams at Fermi Nuclear Station for Week of Jan 31,2000.NRC Will Make Exam Validation Visit to Facility During Week of Jan 10,2000
ML20212F3241999-09-20020 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36
NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999
Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public
ML20217A9421999-09-0909 September 1999
Informs That NRC Plan to Conduct Addl Resident Insps Beyond Core Insp Program Over Next 6 Months to Assess Improvements in Areas of Procedural Compliance & Quality of Work. Historical Listing of Plant Issues Encl
NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999
Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
ML20211Q0991999-09-0303 September 1999
Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999
Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld
NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999
Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)
ML20211G4951999-08-24024 August 1999
Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999
Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval
IR 05000341/19990131999-08-19019 August 1999
Discusses Insp Rept 50-341/99-13 & OI Rept 3-98-039 Conducted Into Potential Misconduct of Operator Formerly Employed by De.Nrc Determined That Violation of NRC Regulations Occurred.Synopsis of IO Rept Encl
NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999
Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation
ML20211C0521999-08-17017 August 1999
Forwards Tables for Sections 3.6 & 3.7 of Draft Safety Evaluation of Proposed Conversion of Current TS to Improved Standard TS
NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999
Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
ML20217E6181999-08-13013 August 1999
FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available
IR 05000341/19990011999-08-10010 August 1999
Forwards Insp Rept 50-341/99-01 on 990619-0723 & Nov. Violation of Concern Because Operators Did Not Understand License Requirements & Placed Plant in Configuration Where EDG 11 Was Removed from Service
IR 05000341/19990121999-08-0606 August 1999
Forwards Insp Rept 50-341/99-12 on 990712-0716.No Violations Noted.Insp Focused on Implementation of Plant Chemistry & Radiological Environ Monitoring Programs & Operation of post-accident Sampling Sys
ML20211C4761999-08-0606 August 1999
Forwards Draft Safety Evaluation Re Proposed Conversion of Current TS to Improved Standard TS
NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999
Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS
ML20210N5451999-08-0303 August 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33
NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999
Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS
ML20210J2121999-07-23023 July 1999
Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation
NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999
Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl
ML20209H7211999-07-14014 July 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32
NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999
Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal
ML20209F6571999-07-12012 July 1999
Forwards Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted.Weak Procedural Guidance,Communications Issues & Configuration Control Weaknessess Were Evident
NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999
Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions
ML20196J5511999-07-0202 July 1999
Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & DE Responses & 980729 for Fermi 2.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 as Result of Review of Responses
ML20209C6141999-07-0101 July 1999
Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999
Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included
1999-09-09
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARNRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999
Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed
NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999
Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl
ML20217N9231999-10-15015 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40
NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999
Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons
NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999
Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
ML20217D5331999-10-0707 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39
ML20217A3261999-09-30030 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38
NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999
Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations
ML20216G9791999-09-24024 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37
NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999
Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys
ML20212F3241999-09-20020 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36
NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999
Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public
NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999
Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999
Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld
ML20211Q0991999-09-0303 September 1999
Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999
Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)
ML20211G4951999-08-24024 August 1999
Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999
Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation
NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999
Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval
NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999
Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
ML20217E6181999-08-13013 August 1999
FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available
NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999
Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS
ML20210N5451999-08-0303 August 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33
NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999
Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS
NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999
Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl
ML20209H7211999-07-14014 July 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32
NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999
Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal
NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999
Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions
ML20209C6141999-07-0101 July 1999
Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0049, Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure Encl1999-06-30030 June 1999
Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure Encl
NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999
Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included
ML20209C1081999-06-29029 June 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 30
NRC-99-0050, Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included1999-06-24024 June 1999
Forwards Rev 7 to ITS Submittal of 980403,to Provide Remaining Responses to NRC RAIs Re ITS Sections 3.5 & 3.8. Revision Instructions Included
NRC-99-0075, Forwards Operator License Renewal Application,Nrc Forms 398 & 396 for CR Effan,License SOP-30186-3.Encl Withheld1999-06-22022 June 1999
Forwards Operator License Renewal Application,Nrc Forms 398 & 396 for CR Effan,License SOP-30186-3.Encl Withheld
ML20212J3861999-06-18018 June 1999
Forwards Rev 29 to Approved UFSAR LCR That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0047, Responds to NRC 990513 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Revised Design Calculation DC-5957, GL 96-06 Calculations, Encl1999-06-0909 June 1999
Responds to NRC 990513 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Revised Design Calculation DC-5957, GL 96-06 Calculations, Encl
ML20195G2001999-06-0808 June 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 28
ML20195E7391999-06-0303 June 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 27
NRC-99-0046, Forwards Rev 6 to Fermi 2 ITS Submittal ,to Provide Remaining Responses to NRC RAI Re ITS Section 3.3, & Update ITS Submittal to Reflect Responses.Brief Abstract of Changes Contained in Attachment 11999-06-0202 June 1999
Forwards Rev 6 to Fermi 2 ITS Submittal ,to Provide Remaining Responses to NRC RAI Re ITS Section 3.3, & Update ITS Submittal to Reflect Responses.Brief Abstract of Changes Contained in Attachment 1
ML20207D9631999-05-26026 May 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section)
ML20195B3381999-05-19019 May 1999
Forwards Rev 25 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section)
NRC-99-0040, Requests NRC Approval of Revs to Weld Tables of Encl Relief Requests RR-A21,rev 1 & RR-A22,rev 1.Revs Do Not Impact Basis for Original Requests for Relief Because There Is No Change to Technical Basis or Proposed Alternative1999-05-14014 May 1999
Requests NRC Approval of Revs to Weld Tables of Encl Relief Requests RR-A21,rev 1 & RR-A22,rev 1.Revs Do Not Impact Basis for Original Requests for Relief Because There Is No Change to Technical Basis or Proposed Alternative
NRC-99-0039, Requests Relief from ASME Section XI Requirement to Examine Essentially 100% of Selected Category B-J Pipe Welds,Per 10CFR50.55a(g)(5)(iii).Relief Request RR-A23,encl1999-05-14014 May 1999
Requests Relief from ASME Section XI Requirement to Examine Essentially 100% of Selected Category B-J Pipe Welds,Per 10CFR50.55a(g)(5)(iii).Relief Request RR-A23,encl
NRC-99-0041, Requests Relief from ASME Section XI Requirements to Examine Essentially 100% of Accessible Category B-D Nozzle Welds,Per 10CFR50.55a(g)(5)(iii).Rev 1 to Relief Request RR-A6,encl1999-05-14014 May 1999
Requests Relief from ASME Section XI Requirements to Examine Essentially 100% of Accessible Category B-D Nozzle Welds,Per 10CFR50.55a(g)(5)(iii).Rev 1 to Relief Request RR-A6,encl
NRC-99-0038, Requests Relief from ASME Section XI 1980 Requirement to Examine Essentially 100% If Category B-A RPV Shell Weld Lengths,Per 10CFR50.55a(g)(5)(iii)1999-05-14014 May 1999
Requests Relief from ASME Section XI 1980 Requirement to Examine Essentially 100% If Category B-A RPV Shell Weld Lengths,Per 10CFR50.55a(g)(5)(iii)
NRC-99-0045, Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl1999-05-0707 May 1999
Forwards Rev 5a to Fermi 980403 Submittal,Converting TS to Its.Encl Rev Provides Remaining Responses to NRC RAIs Re ITS Section 3.6 Contained in NRC 990211 Rai.Brief Abstract of Changes & Responses to Rai,Encl
NRC-99-0044, Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses1999-04-30030 April 1999
Forwards Rev 5 to ITS to Provide Responses to RAI Re ITS Section 3.6 (Except ITS Section 3.6.1.3) Contained in & Update in ITS Submittal to Reflect Responses
NRC-99-0059, Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate1999-04-29029 April 1999
Provides Notification Required by 10CFR50.82(a)(7) of Changes to Fermi 1 Decommissioning Cost Estimate
ML20206E2941999-04-28028 April 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy & Approved TRM Lcrs (Sorted by Section), Rev 24
NRC-99-0037, Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl1999-04-26026 April 1999
Forwards Rev 9 to Fermi 2 Ufsar,Per 10CFR50.71(e) & 10CFR50.4(b)(6).Summary of Changes to QA Program & Vol 1 of Technical Requirements Manual,Encl
1999-09-08
[Table view]
Category:UTILITY TO NRC
MONTHYEARNRC-90-0142, Forwards Revised Semiannual Fitness for Duty Rept,Consisting of Statement Re Percentage of Individuals Tested & Revised Graph,Per G Pirtle Request1990-09-0707 September 1990
Forwards Revised Semiannual Fitness for Duty Rept,Consisting of Statement Re Percentage of Individuals Tested & Revised Graph,Per G Pirtle Request
NRC-90-0152, Forwards Rev 3 to Radiological Emergency Response Preparedness Plan.W/O Encl1990-09-0505 September 1990
Forwards Rev 3 to Radiological Emergency Response Preparedness Plan.W/O Encl
NRC-90-0139, Responds to NRC Re Memorization of Immediate Operator Actions in Abnormal Operating Procedures (Aop). Definition of Immediate Action Under Review to Provide Mechanism for Consistent Application to All AOPs1990-08-31031 August 1990
Responds to NRC Re Memorization of Immediate Operator Actions in Abnormal Operating Procedures (Aop). Definition of Immediate Action Under Review to Provide Mechanism for Consistent Application to All AOPs
NRC-90-0116, Forwards Semiannual Fitness for Duty Rept1990-08-29029 August 1990
Forwards Semiannual Fitness for Duty Rept
NRC-90-0117, Forwards, Fermi 2 Nuclear Power Plant Semiannual Radioactive Effluent Release Rept for Jan-June 1990. No Releases Occurred1990-08-28028 August 1990
Forwards, Fermi 2 Nuclear Power Plant Semiannual Radioactive Effluent Release Rept for Jan-June 1990. No Releases Occurred
NRC-90-0118, Forwards Endorsement 35 to Maelu Policy MF-120 & Endorsement 139 to Nelia Policy NF-921990-08-24024 August 1990
Forwards Endorsement 35 to Maelu Policy MF-120 & Endorsement 139 to Nelia Policy NF-92
NRC-90-0135, Affirms That Util Intends to Conduct Insp of Low Pressure Turbine Rotor Disks During Upcoming Refueling Outage.Insp of Low Pressure Turbine 2 Carried Out During First Refueling Outage.No Evidence of Stress Corrosion Found1990-08-17017 August 1990
Affirms That Util Intends to Conduct Insp of Low Pressure Turbine Rotor Disks During Upcoming Refueling Outage.Insp of Low Pressure Turbine 2 Carried Out During First Refueling Outage.No Evidence of Stress Corrosion Found
NRC-90-0137, Forwards NPDES Permit MI0037028 for Plant,Approved by State of Mi Water Resources Commission During 900719 Meeting1990-08-17017 August 1990
Forwards NPDES Permit MI0037028 for Plant,Approved by State of Mi Water Resources Commission During 900719 Meeting
NRC-90-0136, Requests That NRC Administer Operator Licensing Exam in Dec 1990 & Postpone Operator Requalification Exam1990-08-17017 August 1990
Requests That NRC Administer Operator Licensing Exam in Dec 1990 & Postpone Operator Requalification Exam
NRC-90-0133, Forwards Rev 5 to Security Personnel Training & Qualification Plan.Rev Establishes App D & Records Retention Matrix to Provide Central Location in Plan for Info on Records Retention Pages 3-4,3-8 & 3-9.Rev Withheld1990-08-0909 August 1990
Forwards Rev 5 to Security Personnel Training & Qualification Plan.Rev Establishes App D & Records Retention Matrix to Provide Central Location in Plan for Info on Records Retention Pages 3-4,3-8 & 3-9.Rev Withheld
NRC-90-0112, Responds to NRC Re Violations Noted in Insp Rept 50-341/90-07.Corrective Actions:Review of RF01 Turbine Work Packages to Identify Where Addl Controls Should Be Placed in Similar Future RF02 Packages Conducted1990-08-0303 August 1990
Responds to NRC Re Violations Noted in Insp Rept 50-341/90-07.Corrective Actions:Review of RF01 Turbine Work Packages to Identify Where Addl Controls Should Be Placed in Similar Future RF02 Packages Conducted
NRC-90-0111, Responds to Concerns Re Open Item 90-007-04,per NRC 900627 Request.Potential Enhancements to Drawings Being Reviewed & to Be Resolved by Dec 19901990-08-0303 August 1990
Responds to Concerns Re Open Item 90-007-04,per NRC 900627 Request.Potential Enhancements to Drawings Being Reviewed & to Be Resolved by Dec 1990
ML20055H8921990-07-26026 July 1990
Forwards Certification of Financial Assurance for Decommissioning of Facility,Per 10CFR50.33(k) & 50.75. Util Intends to Retain Unit 1 in Safe Storage Status Until Unit 2 Shut Down & Decommissioned
NRC-90-0131, Forwards Rev 15 to Physical Security Plan.Rev Withheld1990-07-24024 July 1990
Forwards Rev 15 to Physical Security Plan.Rev Withheld
NRC-90-0108, Discusses Deletion of Commitment for Temporary Mod Program, Per Insp Rept 50-341/84-25.Requirement for Operations Engineer to Approve Extensions of Temporary Mods Beyond 30 Days Being Deleted from Procedure FIP-OP1-021990-07-18018 July 1990
Discusses Deletion of Commitment for Temporary Mod Program, Per Insp Rept 50-341/84-25.Requirement for Operations Engineer to Approve Extensions of Temporary Mods Beyond 30 Days Being Deleted from Procedure FIP-OP1-02
NRC-90-0093, Submits Clarification of Design for Plant Suppression Pool Temp Monitoring Sys.Design Adequate to Ensure Suppression Pool Water Temp within Allowable Tech Spec Limits1990-07-18018 July 1990
Submits Clarification of Design for Plant Suppression Pool Temp Monitoring Sys.Design Adequate to Ensure Suppression Pool Water Temp within Allowable Tech Spec Limits
NRC-90-0091, Requests Relief from Commitment to Perform 100% Audits of Tech Spec Line Items.Tech Spec Improvement Program Has Been Completed Which Provides Extensive Review of Tech Spec Line Items1990-07-0202 July 1990
Requests Relief from Commitment to Perform 100% Audits of Tech Spec Line Items.Tech Spec Improvement Program Has Been Completed Which Provides Extensive Review of Tech Spec Line Items
NRC-90-0101, Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status for Each Issue Encl1990-06-29029 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Table Listing Status for Each Issue Encl
NRC-90-0100, Discusses Installation of Motor Operated Valve Limiter Plates,Per IE Bulletin 85-003.Commitment to Install Limiter Plates Deferred Until Time When Valve or Valve Operator Would Be Disassembled for Another Reason1990-06-27027 June 1990
Discusses Installation of Motor Operated Valve Limiter Plates,Per IE Bulletin 85-003.Commitment to Install Limiter Plates Deferred Until Time When Valve or Valve Operator Would Be Disassembled for Another Reason
NRC-90-0088, Discusses Changes Made to Commitment Addressing Calibr Frequency for Inservice Test Instrumentation,Per Violation 87009-03.Nine-month Calibr Frequency for Subj Instrumentation No Longer Appropriate or in Use1990-06-14014 June 1990
Discusses Changes Made to Commitment Addressing Calibr Frequency for Inservice Test Instrumentation,Per Violation 87009-03.Nine-month Calibr Frequency for Subj Instrumentation No Longer Appropriate or in Use
NRC-90-0095, Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request1990-06-0606 June 1990
Provides Schedule for Implementation of Mods Re Compliance W/Reg Guide 1.97,Rev 2,per 900502 Request
NRC-90-0089, Submits Supplemental Response to NRC Concerns on RHR Operability from Insp Rept 50-341/89-17.Util Faced W/ Decision to Provide Addl Overheating Protection to RHR Sys Pump Vs Maintaining Necessary Water Coverage of Fuel1990-06-0404 June 1990
Submits Supplemental Response to NRC Concerns on RHR Operability from Insp Rept 50-341/89-17.Util Faced W/ Decision to Provide Addl Overheating Protection to RHR Sys Pump Vs Maintaining Necessary Water Coverage of Fuel
NRC-90-0085, Provides Plans for Eliminating Temporaary Mods at Plant,Per Insp Rept 50-341/90-051990-05-29029 May 1990
Provides Plans for Eliminating Temporaary Mods at Plant,Per Insp Rept 50-341/90-05
NRC-90-0083, Discusses Action Plan to Review Socket Weld Failures at Plant.Failure History of Socket Welds Will Be Investigated to Determine Whether or Not Significant Common Mode Failure Mechanism Evident.Plan Expected to Be Completed by 9005251990-05-18018 May 1990
Discusses Action Plan to Review Socket Weld Failures at Plant.Failure History of Socket Welds Will Be Investigated to Determine Whether or Not Significant Common Mode Failure Mechanism Evident.Plan Expected to Be Completed by 900525
NRC-90-0074, Discusses Insp of Flash Tanks & Reactor Feed Pump Strainers. No Further Evidence of Moisture Separator Reheater Debris Discovered in Strainers,Stub Tubes,Wire Mesh or Structural Members1990-05-18018 May 1990
Discusses Insp of Flash Tanks & Reactor Feed Pump Strainers. No Further Evidence of Moisture Separator Reheater Debris Discovered in Strainers,Stub Tubes,Wire Mesh or Structural Members
NRC-90-0082, Documents Commitments Made During Recent Meetings & Telcon on RHR Sys Small Bore Connections1990-05-11011 May 1990
Documents Commitments Made During Recent Meetings & Telcon on RHR Sys Small Bore Connections
NRC-90-0068, Forwards 1989 Annual Financial Repts for Detroit Edison Co & Wolverine Power Supply Cooperative,Inc1990-05-0101 May 1990
Forwards 1989 Annual Financial Repts for Detroit Edison Co & Wolverine Power Supply Cooperative,Inc
NRC-90-0071, Responds to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-341/90-03 Re Emergency Preparedness Exercise Weaknesses. Corrective Actions:Case Studies Will Be Developed & Presented in Licensed Operator Requalification Training1990-04-30030 April 1990
Responds to NRC 900316 Ltr Re Violations Noted in Insp Rept 50-341/90-03 Re Emergency Preparedness Exercise Weaknesses. Corrective Actions:Case Studies Will Be Developed & Presented in Licensed Operator Requalification Training
NRC-90-0078, Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Bow. Util Has Decided That Fuel Channel Boxes Will Not Be Used After First Bundle Lifetime1990-04-25025 April 1990
Responds to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Bow. Util Has Decided That Fuel Channel Boxes Will Not Be Used After First Bundle Lifetime
NRC-90-0051, Responds to SALP 11 Board Rept 50-341/90-01.Outage Critique Action Plan Issued for First Refueling Outage Identifying Lessons Learned & Areas Needing Improvement1990-04-12012 April 1990
Responds to SALP 11 Board Rept 50-341/90-01.Outage Critique Action Plan Issued for First Refueling Outage Identifying Lessons Learned & Areas Needing Improvement
NRC-90-0060, Responds to 900104 Request for Supplemental Station Blackout Submittal1990-03-29029 March 1990
Responds to 900104 Request for Supplemental Station Blackout Submittal
NRC-90-0061, Forwards Addl Info Re Proposed Drywell Level Instrument Line Configuration,As Followup to 890927 Tech Spec Change Request.Rept Provides Info Re Reasons for Designating Primary Containment Isolation Valve Normally Opened1990-03-27027 March 1990
Forwards Addl Info Re Proposed Drywell Level Instrument Line Configuration,As Followup to 890927 Tech Spec Change Request.Rept Provides Info Re Reasons for Designating Primary Containment Isolation Valve Normally Opened
NRC-90-0055, Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47 - Safety Implications of Control Sys in Lwrs. Overfill Protection Sys Adequately Separated from Main Feedwater Control Sys1990-03-19019 March 1990
Responds to Generic Ltr 89-19, Request for Action Re Resolution of USI A-47 - Safety Implications of Control Sys in Lwrs. Overfill Protection Sys Adequately Separated from Main Feedwater Control Sys
NRC-90-0024, Suppls Response to Violations Noted in Insp Rept 50-341/85-47 Re Security Records.Util Intends to Rely Solely on Historical Tapes to Retrieve Records Required by Physical Security Plan.Hard Copy Computer Logs Will Be Discarded1990-03-16016 March 1990
Suppls Response to Violations Noted in Insp Rept 50-341/85-47 Re Security Records.Util Intends to Rely Solely on Historical Tapes to Retrieve Records Required by Physical Security Plan.Hard Copy Computer Logs Will Be Discarded
NRC-90-0045, Forwards Inservice Insp Summary Rept of 1989 Inservice Insp at Fermi 2 Nuclear Power Plant.1990-03-13013 March 1990
Forwards Inservice Insp Summary Rept of 1989 Inservice Insp at Fermi 2 Nuclear Power Plant.
NRC-90-0043, Responds to NRC 900224 Ltr Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 9002021990-03-0909 March 1990
Responds to NRC 900224 Ltr Re Weaknesses & Violations Noted in Insp Rept 50-341/89-24.Corrective Actions:Nuclear Fire Protection Specialist Provided Training to Appropriate Personnel on 900202
NRC-90-0054, Responds to NRC 900212 Order Modifying License & Notice of Violation.Corrective Actions:Former Director of Nuclear Security No Longer Works for Util & Extensive Actions Taken to Improve Communications W/Nrc1990-03-0909 March 1990
Responds to NRC 900212 Order Modifying License & Notice of Violation.Corrective Actions:Former Director of Nuclear Security No Longer Works for Util & Extensive Actions Taken to Improve Communications W/Nrc
NRC-90-0037, Forwards Completed Questionnaires for Types of Insps,Audits & Evaluations,In Response to Generic Ltr 90-01, Voluntary Participation in NRC Regulatory Impact Survey.1990-03-0505 March 1990
Forwards Completed Questionnaires for Types of Insps,Audits & Evaluations,In Response to Generic Ltr 90-01, Voluntary Participation in NRC Regulatory Impact Survey.
NRC-90-0029, Responds to Violations Noted in Insp Rept 50-341/89-36. Corrective Action:All Personnel in Operations & I&C Viewed Professionalism Video Which Included Presentation of Facts Concerning Event1990-03-0505 March 1990
Responds to Violations Noted in Insp Rept 50-341/89-36. Corrective Action:All Personnel in Operations & I&C Viewed Professionalism Video Which Included Presentation of Facts Concerning Event
NRC-90-0028, Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Revised Pages of Rept for Jul-Dec 1988, Containing Recalculated Noble Gas Releases & Doses1990-03-0101 March 1990
Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Revised Pages of Rept for Jul-Dec 1988, Containing Recalculated Noble Gas Releases & Doses
NRC-90-0034, Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results1990-02-26026 February 1990
Forwards, 1989 Annual Operating Rept for Fermi 2 & Main Steam Piping Dynamic Response Test Results
NRC-90-0036, Forwards Response to NRC Survey on Nuclear Fuel Cycle Industry Future Activity,Per 900122 Request1990-02-26026 February 1990
Forwards Response to NRC Survey on Nuclear Fuel Cycle Industry Future Activity,Per 900122 Request
NRC-90-0026, Forwards Monthly Operating Rept for Jan 1990 for Fermi Unit 2 & Revised Rept for Dec 1989,correcting Error in Net Electrical Generation Figure1990-02-15015 February 1990
Forwards Monthly Operating Rept for Jan 1990 for Fermi Unit 2 & Revised Rept for Dec 1989,correcting Error in Net Electrical Generation Figure
NRC-90-0020, Forwards Response to Violations Noted in Insp Rept 50-341/89-31 Re Maint Support for Security Equipment.Addl Instrumentation & Control Repairmen Hired.Encl Withheld (Ref 10CFR73.21)1990-02-12012 February 1990
Forwards Response to Violations Noted in Insp Rept 50-341/89-31 Re Maint Support for Security Equipment.Addl Instrumentation & Control Repairmen Hired.Encl Withheld (Ref 10CFR73.21)
NRC-90-0010, Responds to NRC 900102 Ltr Re Violations Noted in Insp Rept 50-341/89-30.Corrective Actions:Storage Area in Machine Shop closed-out & QA1 Matl Returned to Warehouse Where Positive Controls in Effect & Shift Turnover Procedure Revised1990-02-0101 February 1990
Responds to NRC 900102 Ltr Re Violations Noted in Insp Rept 50-341/89-30.Corrective Actions:Storage Area in Machine Shop closed-out & QA1 Matl Returned to Warehouse Where Positive Controls in Effect & Shift Turnover Procedure Revised
NRC-90-0013, Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design. Subj Valves Not Used by Util1990-01-26026 January 1990
Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or Valves of Similar Design. Subj Valves Not Used by Util
NRC-90-0012, Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 19911990-01-26026 January 1990
Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Monitoring & Treatment Programs to Reduce Incidents of Flow Blockage Due to Biofouling Will Be Implemented During Early 1991
NRC-90-0016, Responds to 10CFR26 Re fitness-for-duty Programs.Util Conducting Testing for Drugs Described in 10CFR26,App a, Section 2.1(a) & at Cutoff Levels Defined in Sections 2.7(3)(1) & 2.7(f)(2) as of 9001031990-01-26026 January 1990
Responds to 10CFR26 Re fitness-for-duty Programs.Util Conducting Testing for Drugs Described in 10CFR26,App a, Section 2.1(a) & at Cutoff Levels Defined in Sections 2.7(3)(1) & 2.7(f)(2) as of 900103
NRC-89-0297, Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp1990-01-12012 January 1990
Forwards Supplemental Response to NRC Request for Addl Info on Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping. All Welds Accessible for Ultrasonic Insp
NRC-89-0240, Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches1990-01-11011 January 1990
Advises That Info in NRC 891010 Ser,Section 4.13 Re Alternate Rod Insertion/Recirculation Pump Trip Initiation Installed on Divisional Basis,Per ATWS Rule,Deemed Correct. Addl Alarm Also Provided for Arm Position of Switches
1990-09-07
[Table view] |
Text
s.
/ I
%' \
e... s me,
.~. . .
. [><3tncii.t . . . ..
Ecison ..
May 30, 1979 EF2-46,147 Mr. James C. Keppler
~P Regional Director Directorate of Regulatory Operations aegion 111 U.S. Nuclear Regulatory Cornission 799 Roosevelt Road Glen Ellyn, Illinois 60137
Dear Mr. Keppler:
Subject:
Detroit Edison Resconse to IE Bulletin No. 79-07 This letter is in response to your IE Bulletin No. 79-07, dated April 14, 1979, which describes seismic stress analysis of safety-related piping.
Enclosed please find an interim response to your inquiry in our memorandum EF2-45,214 of May 25, 1979, advising you of the status of seismic analysis information received from our consultants / vendors.
Please advise us if you have any questions regarding our interim report on this matter.
Sincerely yours, h 4%W 4, RWB/Im Attachments cc: Mr. John G. Davis, Acting Director Office of Inspection and Enforcement Division of Reactor Inspection Programs U.S. Nuclear Regulatory Commission Washington D.C. 20555
"' 07, 7 908080 60 L "440 . 087
Detroit c~ - .. . .
Edison . r . . ' ENRICO FER.'!I UNIT 2 PROJECT '
ENGINEERING May 25, 1979 EC2 - 45214 To: R. W. Barr Project Quality Assurance Director .
206 Engineering Construction-Troy 7 From: F. E. Gregor (/
Principal Engineer - EF2 318 Engineering Construction-Troy ' h
Reference:
lE-Bulletin No. 79-07, dated April 14, 1979
Subject:
Fermi 2 Interie Response to NRC - Bulletin 79-07 We have reviewed the above referenced bulletin and identified six consultants / vendors that have performed seismic analysis of safety related piping systems for the Fermi 2 plant. They are:
- 1. Stone & Webster Michigan, Inc. , Cherry Hill
- 2. Sargent & Lundy Engineers. Chicago,
- 3. General Electric Company. San Jose 4 NUTECH, Inc., San Jose
- 5. Atomics International, Canoga Park
- 6. General Electric I5SE, Oak Brook, Illinois Each individual consultant / vendor was requested to respond to the infor ation request of the bulletin. In sur=ary, none of the con-sultants/ vendors utilized piping computer programs e= ploying algebraic (considering signs) summation in perfor=ing response spectrum or time history dynamic piping analyses.
The individual responses are as follows:
- 1. STONE & WEBSTER MICHIGAN. INC.
A detailed response to item (3) of the bulletin, computer program description end verification, is AAG . 088
Meno to: May 25, 1979 R . 'n'. Barr EF2 - 45213
- s. .
being provided in response to the March 13, 1979 Order to Show Cause f or the Surry !.' nits 1 and 2, (see Attachment A). A progran summary and verifica-tion data is given in the FSAR Section 3.13.4.1.
,. 2. SARCENT & LUNDY ENCINEERS The detailed response is provided in Attachment B.
Their programs are also described in FSAR Section 3.13.1.26.
- 3. GENERAL ELECTRIC COMPANY, SAN JOSE The General Electric response is provided in Attach-cent C. A generic submittal to the Coccission in July, 1979 will provide verification data for the FISYS computer program, utilizing five NRC benc.
mark problems.
- 4. NUTECH , INC.
A complete response is given in Attachment D
- 5. AT0MICS INTERNATIONAL Telegraphic response was received, stating that the methods in question have not been used in the dynamic analysis of the skid piping for the hydrogen recombiner systems. The complete assembled proto-type skid including the piping within the system have also been successfully subjected to a seismic shaker table test with a response spectra enveloping the applicable Fermi 2 seismic response spectra.
The detailed computer program description and verifi-cation will be submitted within 90 days.
- 6. GENERAL ELECTRIC I&SE The control rod drive insert and withdraw piping and the scram volume discharge piping were analyzed by CE-I&SE and subcontracted to Teledyne. A detailed response was not received in time and will be provided within 90 days. It was confirmed by telephone, that the methods in question have NOT been used.
440. 089
Memo to: Maj 25, 1979 R. W. Barr EF2 - 45213 In conclusion, we will provide a follow up report sube.itting the detailed responses of two of our consultants / vendors.
FEC/dk cc: W. F. Colbert/E. Lusis/L. Bertani M. G. Sigetich G. Butterworth T. Byrd Docu=ent Control
.J APPROVED h' / 't 6 W. F. Colbert /
Project Engineer Enrico Fermi 2 E 9 f
6
- l C- to: - - - '
s LF.- tani-3 p ~6g' C .- p6 - ! %
-i'
>8 """
i g i C e. :. e Lb c r -
l JJcsiglic
!!r . r. Cry or % ;- 2 .~ , ; < -
Syste.,s Engineer
~T.nr;co Fe r-1 *Jnit 2 i.'.'n.
J' 2000 Second Avenue S C -52C Detroit. *i1 43226 N. ':r. Crer,or:
TASK NO. Oo706 RE." .iSE TO JSMT.C 3ULLETIS 79-07
" ICO FC 's A7n1IC FOh'ER PLA.:7 - UNIT 2
Reference:
DECO Letter ::o. EF2-44,670 datei w : .. - '7-Your referenecd letter requested S&k' response *' . US'::C ;illetin ^^-74 Our respons: is as follows:
Itens 1, 2, an? 4: In response to It ens 1, 2, an:' < . n.) co :t.tcr rM 4 h.:ve been idc ntified by S&b' tb.ic'. uced a. s v t't
. tW -
described in Ite: 1 of the ',ulletin.
Itcr 3: The coeputer program ?.JPIPT., % rsions '2x li' 0.,;i'-
heen used to analyze the safet:-telatcl r t uv. c f t <
f ollouing systc=s of Enrice c r-l-2 :
- a. Standby Liquid Control Sys te--
- b. Main Stean Drain Syst.-
- c. RPV Vent Systen
- d. Main Steam Valve Lcc': e Cont r i Lycte-Verification of cenputer progra~s used by St. ' src ' i-addressed in response to the Ar:11 2 AJecn.5- to : c March 13 Order to Show Caur.c for 5arry : nits 1 a, : _.
S6t?'s in-house benchnarkin.- Ifnks all ma in ve rs i r : of
'.UPIPL to Version 0310.
0} (!
$h h l
A
If you have any questions, pIbase call.
Verj truly yours, N
sf/W C. E. Thorr.es Exoject Enr,ineer ECD:DJR u
092
ATT ACH ME MT@
S A R G ENT & LUNDY ENGINEERM
,co.o..-.................,
5 5 C AST MON ROC STOC CT CHICAGO,lLLINol5 606 03 Tt.c.=c=t -
32-269 2000 CASwE ACQ8f $$
- SARW% CMicaOO May 15, 1979 Project Nc. 5285-16
.- SLM-1011 The Detroit Edison Company Enrico Fermi - Unit 2 Reply to NRC IE Bulletin No. 79-07 Mr. F. E. Gregor, System Engineer Enrico Fermi - Unit 2 The Detroit Edison Cocpany 2000 Second Avenue Detrcit, Michigan 48226
Dear Mr. Gregor:
We have responded to your request in EF2 - 44, 674, dated May 10, 1979 by Mr. R. F. Scheibe 's letter of May 2, 1979 addressed to Mr. W. F. Colbert. Attached is a copy of Mr. Scheibel's letter and Sargent & Lundy's response.
If there are any questions, please contact me.
Yours very truly,
)hm D. R. Larson Project Manager DRL/dm In du-11cate Attacbent Copies:
W. F. Colbert 1/1 C. R. Seibert 1/1 R. F. Schelbel (1/ )
F. P. Tsai (1/1) 440 093
i * *
.Y <
&&Q
- g bAROENTS$*1JUNDT 2:n oi.n:s na rh= cts o' entorm :n samocat eses
,,, 5 5 E A S T MONROC ST ACE?
CHiOAGC,tLLf NOf 5 60603
';,,f,, , 7 toto-o=t - 312 263-2000 212 2ss.3s7o caett as:stss - Samo s =.e .c.4 o s May 2, 1979
.The Detroit Edisen Company Reply to NRC IE Bulletin Nu:.ber 79-07 Mr. W. F. Colbert Project Engineer The Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226
Dear Mr. Colbert:
The attached enclosure is in response to NRC IE Bulletin 79 Seismic Stress Analysis of Safety-P. elated Piping.
This is for your transmittal to the NRC.
Please contact us if there are any questions.
- Very truly yours, C
( .-E~~= CLM WD hk R. F. Scheibel Project Director RFS:klm In quadruplicate Encicsure .
Cocies:
/ D . ' R. Larson (1/1)
.. .- -g 440 .094
-e me e -e e.
s '
._ c N GlN E E R S EMD File MO. 017
, emcaco ;
s 25 PRELIMINARY RI?LY
-TO NRC IE BULLETIN -
NO. 79-07
, April 23, 1979 SEISMIC STEZSS ANALYSIS OF ,
_ SAFETY-RILATED PIPING In IE Bulletin No. 79-C7, dated April 14, 1979 the NRC raised questions concerning the methods of ccmbination of earthquake directional response used for piping analysis for safety related piping systems in both operating nuclear plants and plants under ccas tructic:.. As the result of an investigation of stress analysis performed by an. eastern based AE, the NRC ordered the shutdown of five nuclear stations when it was found that earthquake directional response (X,Y,Z direction) in the piping analyses were added algebraically at the modal level i.e., =oda by mode. This resulted in some cancelling effect.for the signed modal respenses for a given local component of 1 cad. In sc=e cases the calculated piping stresses and restraint and support loads were reportedly underestimated by as much as C01. .
The Dynapipe and PIPSYS programs that Sargent & Lundy used or currently uses for the seismic analysis of piping systems were developed independently of programs used by other AE's nd other programs that'were and are co==ercially available. Therefore, it is unlikely that any similar errors would be repeated in the Sargent & Lundy piping analysis.
Further=cre, the Sargent & Lundy programs werk first with
. each direction of response (X, Y or Z) and combine modal respenses for a given direction per applicshle regulatcry guide requirements. The combined responses for each direction are then added by the SRSS method. Thus the cancelling effect experienced in the piping analysis fcr the plants the NRC shut down dces not occur in the Sargent & Lundy seismic analysis. -
In Bullerin No. 79-07 the NRC requests responses to four . .
specific action ite=s regarding the seismic analysis of safety related piping. These action ite=c along with appropriate respenses are provided in the following: '
(1) .
095 e %
. 4 es e. a . g . ..
s -
ed
~s NRC Item (1) Identify which if an.v, of the methods specified below were empicyed er were used in computer codes.for the scismic a:.alysis of safety related piping'in your plant systems (or scrtions and thereof)provide a list of safety affected:
Response Spectrun .Model Analysis:
a.
Algchraic (considering signs) su= ration of th e C o m. 3..- . . .. m, .3 s ,_ ,.._4 a . --_
~. --._.c..___
_ _ . ( . o. . ,
algebraic sumnation of :he maximur .2 ;ec of _
the codirectional responses caused by each of the components of earthquake motien at a particular point in the cathematical codel) .
b.
, Algebraic (considering signs) st==ation of the codirecticnal inter =cdel rescensec (i.e.,
for the number of modes censidered, the maxinun values of response fc each =cde si- ed algebraically). .
Time History Analysis:
A. Algebraic st==ation of the codirectional caximum respcnses or the time dependent responses due to each of the cc ponents of earthquake notien acting sinultaneous.y when the earthquake directional moticas are not statistically independent.
Reply:
The Dynapipe and pip'SYS pregrans used by Sargent & Lundy for the response spectra scismic analysis of safety related piping do not employ algebraic su==2 tion routines for combining responsas, co . .";. ". . . .~ ~. . '. o '.
either internod al cr fer any c:hcr
-'c.......=_. **--~~.~_e'
- r. 'u'_'..=*- ' ~. ~. 3 not use the time history methcd for the seistic .
analysis of piping.
NL' Item (2) Provide complete c c=puter program listings for
- the dynamic resper se analysis portiuns for tha
'* ccdes which emple;.d the techniquas idancified
, in Item 1 above. - ~
Reply:
None of the computer programs used by Sargent & Lundy for the seismic analysis of safety related piping employ the algebraic techniques described in item (1) , therefore we are not required to submit our computer program. listings. ..- t 440 096 sIt d egy g
, m -
(2) .h: j,t r N
( j 5$%. J)f{<i[W E
.ea 1 y{-,
e . . eg. * **
l
~2l NRC ! ten (3) Verify that all piping corputer programs were checked against ei.;.her piping benchmark problems.. cr cc=:arec to other piping cc puter prc;rans. You are requested to identify the bench. ark pr:blems and/or the c =puter programs ths: were used fer such verificati:.s cr c2::rit
( in detail h w it was determined that these cre:rans yielded app opriate results (i.e., gave results wh::.-
correspended to the correct perfor=ance of their intended methodology).
g Reply:
l The S &L cc=puter program DYMAPI?I (09. 7.0 5 2) and PI?SYS (09.5.065) were used in .einine. seismic analyses. . These programs have a long history of use within S&L -
e.g.,
DYNAPIPE since 1969 and PIPSYS since 1972. They have been validated several times during their long histeri of tse. For the seismic pcrtions of the progrs=, this has been done by checking cc puter results by hand calculations, enecking reruits against public d: rain programs, and by checking results from PIPSYS against DYUAP IPE . Each new versi:n of the program is extensively checked against the cider version thrcugh a series of
~
test problers. The folicwing validatica pr cedure was follcwed in the initial validation:
A. Check A:ainst DYNAL I1 1 (1969) *
. A typical hot reheat t, icing s.ystem was an21'.:ec
. on DYNAPIPI and DYSALt- . The elemen: forces for a specified responsq spectra were compared and were found to be comparable. The frequencies o' modes 1 through 6 were also in c; ' agreement B. Check Against MIC-21 I2)(1969)
In 1963, no public-demain seismic analysis code had the capability of curved elements to =cdel
. pipe elbows. Tc validate this feature of the S&L programs, the piping systen given in 2xample
- . problen No. 2 cf the MIC-21 computer ccde was annly:ed by the S&L program. Seismic analysis was performed using the respense spectrun ne:hcd. Mcmber forces, joint displacements, and joint inertia fcrees e
- y. ,e p ., .t. . . . ..a .a .s .-
. --a a_, .u.....%,. . .u. c g , .. ..- g..-=... .....,.
. a. . ..,2s.-
analyzed using the MIC-21 code with a static lea 4 equal to the =cdal inertia-free forces, and jcin:
displacements obtained frem the two codes were ec=parcd and found to be in good agreement.
C'h -
pi M 'fn
.i t M
' 'L t Md
)Cp, i ,..p H (Q" a 1
[ [MN J
-4_47 097 .
3b
~ -
e C. PIPSYS & DYNAP:PE Cercarison (1972)
In 1971, wher the P:PSYS program was deve10,:cd, it was extensively bench- arW 'rai- the DY:!APIPE program. Typical piping systers were run on the two programs and found c 2 : eld the sa. e respenses en the two ecdes. -
D. PI"r S v. e- & D .^. .:_a '1. t _e e..u. . -l. ...._=_4..e.-
. . D .'. . . . f 1 ) = .#.
( .1.c. , 2 )
- h. . ,. S .~
,,, . . t , ,
In 1972 the medal periods and ti: 2 history of response to pipe transients using the : dal time histo:1 =ethod on ?!PSYS and DYNAP:PE were chec?.ed against i.ho se obtained frc= DY';A*., and ';ASTP_U: .
Good agreement was obtained in respenses from the four codes.
Rerc ances
- 1. ICES DYNAL User's Manual, McDonnell-D0uglas Aut0:2: ice
- 2. MEC-21, 7094, "A Piping Flexibility Analysis Prcgran for the IBM 7090 and 7094," Les Alancs Scian ific Laboratory, University of California, 1964.
- 3. NASTP.W User's Manual, NASA SP-221.
In addition Sargent & Lundy would welecce a generic review of our piping progran by the NRC Licensing Staff. This review could most effectively be ccnducted in our offices where all'dec=ertation and key personnel would be available to the staff.- .
NRC pg(4) If any of the =ethods listed in iten 1 are identified, submit a plan cf action and an estimated schedule for kh ere *J the re-evaluation Of the caf2ty relatef picing, supp:r s.
6yn-m and eprovide Also uinmentan af estimate fected b.vofthese analv. sis the degree to technic.us:.
which the en m :s
- F capability of the plan: to safely withstand a sais=ic
% rid event in the interi 1. 5 i= acted.
L"' 8"7.3
-Reply: , F-
.zk<,_ i.
A None of the conputer prcgrams used by Sargent & Lundy for scismic analysis of safety related piping empicy the algebraic technicues described in iten (1) , '
Ad um therefore, no reanalysis of any safety related piping is necassary.
a eq w'.
. . // AS U A
~ E. B. Branch 1 e- K* Sl"9h Associate, Head n Supervisor Structural Analytical
. Enginecring Mechanics Divisica 4 g g ision (4)
.. ..... - .~..--i .
4.
u u ci.c a n cuenov GENERA! } ELEC1RIC !
PR OJE C TS DIVI $f 0N 175 C.URTNED sVE. %N ./ lie. OJ L:FCF tJA l ED 3ENEFAL Et!OTAC CCUP&N%' g HC 391, (1CS 925-2MF ls'T 'T / r ' . V. :_ 7.
O[
U May 2n, 157c '
TDEC- 36):
Mr. F. E. Gregor, Sytten Degf r cer e Enrico fed 2 Project ;
The Detroit Edision Corge.3 Decusentation Conteci - Reu:t 361 20C0 Second Ave.
Detecit, NI 43226 Desr Hr. Gregor:
SU3 JECT: GF RESPONSC TO HAC IE - BULLf7Ih 79-07 Red erence: EFF-44672 dated 5.'10/79 As re4ccated in the refes enecc letter, the GE res onse to itess 1 throup. 4 of IE-Bulictin 79-07 is as follows:
Its 1 & 2 None of the cos:puter codes used for tt,e sef snic onsiysu 1. of pioing sys*.ans i:apertant tc Safety ee;icyed the technicues identit ed in itert Iten 3 The SAP /P!SY3 cenputer pregraes wtN used fo- seisr.ic piping enaiy:is.
A descriptien >< these progrars and the verification procecure is presented below.
SA,D40 Vecificatic,9 ffte E .a.g ggsg_ @ on was ori2i na;1y deveicc*c fe General ilectric SAP 4G, a version of SAPsby F. A. Peterson ard K. J. Bathe of the at Berkele3 Tr.e SAP progran is s genero? pe:pese swt.cture prog used to perfors static ani:
corponents by the finite elesent methed.
b i 40 099
--mmm,--r -mmmmmmy
- 6-CENfA4t h E*tCTRIC Mr. F. E. Gregor Ps::a 2 @,
liay 24, 1979 v ve*1 ficatice Ali GE pro:Jectbnr ve*siens of SAP are n' if'.e d using a special t,e nch sset, proble t. hat exercises a! the irocrtant features of 1.tr procrv The bench urt pret t er. hers been analyzed for %e ef fec .s of cons t.n.* n:
of f ree end, cf stritect ed forces , and is dyr airica)1r analyred t c. rfr e rr-i r L mace shapes and nettzral fre:a;encies using 5 4nr.on 5.nter : s AWii pitgcar . -
ANSYS was also used te predict dyearde respense of the Dench art prot,iem.
' acing tr e respcnse spectra and ti:se Mstcry integration me%ces. T7c predicted f reciucoc ies , mace shapes , anc lodos wd.t's r.;os. pared tc the -
corre>pending 5>.? oredictions The DP prograrx orecteticii nec tc tm cnnsistent witti tJeese of ANSYS before LAP was quait f ted for produr*. ion its e. I .) order te test unique fea.2rrt6 of SAP thet cannet be cosparea to the results of another program, a special prenlen is cov' sed cicie has
! an equiva:ent com;'9ter or naccaily calcu'atea rab.stion. Be#cre any new version of SAP ii, verifisid, for product 1re oppiir.ation, the benen s<iric pretler is etanalyzert to verify that she prograc. chanoes have nct char.ged pretfictiorts or reduced the r accuracy.
8 PI Sh e Veri' cation Peor;ren Deser Jt_i_on DD.YS is a cc:rm.f er pre;rae wecialized T.c ansiyre peng syste.Tr. The P15YS picgrar. pms'ces a nighly fieziole user o-,enies nnut f orna !ce '
piping rystert ordeling. Tne analysis twdules o+ *15rs are .av:en c1rt :.if fers the *>APtG prograry.
Verificat'or Since PISYS enalysis nrodules are istentkai' to SAP 4G. a 5AF Fialysis af a typics1 B).R stear. stoi,N syste:: is arsed as a Dench rLace orobles. for PiSYS ve:ificatfor:. The stear line is ar,aly cd for ;he :_11 er ans sn, ceac weignt, ano e va*iety of dynernic learfs in order to e.xe cise al! tt:e features of P!515. P75f5 was not verif;.sef M a prcr:uction pecgrar, urtdi tf:e predictions of SAF ad PISYS were shcsa to 3c icernica? f or pr:ci.ical purpcses.
Before any new versten of P25YS is verified 'or p eauctfor; at: 21catien.
the bench mark pectigia is rear.e!yzed te veri fv the the prograr enseces have not c!rrr'ged the precfictions or -eda.:eo their eccurscy.
Five liRC benc5 cart oroolens wiil aise he ar.alyzeo as a fut*her ver.* cst w) vf the PI3YS code. This analysh is espec .ed to se cosa!+ta.f anc subnitt.ed to the Co nission for rewi n by Jul 13, 1979.
p.ete 4 No further ea:scanse is regLrired.
fH l00 h
Unhn uduN4L.
\
~
.g y
n v.m . r.m y s ew. g.m. > r. . w , ..g 9
.s.; .. ..u n.
b k
- 'A G!b E R at (f f LIC1 Aic W F. E. Gregcr p Page 2 . -
Ny N,1979 Pleas = cal! t.' yev have any.ouestic s,
\ery tNly yen *s ,
,. .s j /
.$ . .<cr * %% ,
C. K. .:ciwscn fr-PTCitCt Mat:A*p r
~~
L:araco Fe.~ 2 0,mject C% pats /39?-3? A c:: C. R. Swanscr,. GF. Detr it F. Gregct, Ectscn K . o'. . Kxr.M e . G' S i t.e D. R . Pankra .1, ~,E Lite file: 10.'5/07-15 i
e p.
ab8 a&uuuud o -
.n, , .o . . 10.;1 a
,. .c s'e . ,
e s *, T 9 4
erem,emestismsgg, guesw..te;ud.ed.w.M. sE:isigg, et'
.-- - - - --- , _ _ _ ~ , . . = __ _ _ _ _ ,. _ _ _ _ _ u;._
. L ATTACHMEN3T @
i Ow 145 M A ATiwat,E, L ANE . s N ;osE. cAu s op a,2 9019 . PqQNE < a;E G.?E Y.
I. ,
>2y 18, 1979 DET-01-199
__Mr. F. E. Gregor Detroit Edison Company 333 Engineering Construction - Troy 2000 Seconda Avenue Detroit MI 48226
Subject:
Response to NRC IE Bulletin 79 Seismic Analysis of Safety-Related Piping for Enrico Fer=i Atomic Power Plant , Unit 2.
References:
- 1. Seismic Stress Analysis of Safety-Related Ploina, NRC IE Bulletin 79-07, datec April 14, 1979.
- 2. PISTAR Verification Recort, NUTECH Topical Report IR-76-001, Revision 0.
3 PISTAR User 's Manual NUTECH Topical Report TR-76-002, Revision 1.
- 4. Pressure Vessels and Picine, 1972 Cocouter Program Verification, Ine American Society of Meenanical Engineers, 1972, 72-94235.
- 5. A:;SYS Engineerine Analysis User's thnual Swanson Analysis Systems , Inc., 1975.
- 6. Enrico Fercio Power Plant, Unit 2, Pri=ary Containment Stress Report for Pool Swell and Safetv/ Relief Valve Discharze Loa c s , NUIECh Report DET-01-157 (in preparation).
Dear Frank:
In response to the Detroit Edison letter of thy 10, letter EF2-44671, the following information is provided concerning analysis of safety-related piping perfor=ed by NUTECH for the Enrico Fermi Atomic Power Plant, Unit 2. NUTECH performed seismic analysis for the following safety-related piping within the suppression chamber:
o Vacuum Breaker Pneu=atic Piping o HPCI Turbine Exhaust Piping o RCIC Turbine Exhaust Piping o HPCI Condensate Line o RCIC Condensate Line o RHR Test Line o Core Spray Test Line AA0 102
T-F. E. Gregor tby 18, 1979
_ DET-01-199 The results of these analyses are documented in Reference 6.
NUTECH's piping program PISTAR was used to perform the analysis.
PISTAR is a NUTECH proprietary computer progra= developed to perform the analysis of power piping. The progra= is based on the well-known computer program, SAP-4, developed at the
-University of California at Serkeley. Complete user documentation for PISTAR, which includes a user's =anual (Reference 3) and verification report (Reference 2), is available.
The concerns addressed in the NRC Bulletin (Reference 1) involved methods used in perfor=in6 seismic analysis of safety-related piping. Specifically, the NRC is concerned with the =ethods used in combining the codirectional and modal responses due to earthquake =otion, using either response spectru= or time-history techniques. A description of the response spectrum tect.nique used in the analysis of the safety-related piping previously listed is given below. No seis=ic analysis was performed usin6 time-history techniques and therefore this option need not be discussed.
Response to each item listed in Reference 1 is given below:
Ite= 1- The combination methods used in perforcing the seis=ic analysis of the safety-related piping listed above was Square-Roo -Su=-of-the Squares (SRSS) method for both the co-directional responses, and =odal responses due to earthquake motion.
Item 2: A complete listing for the dynamic response analysis portion of the co=puter progra= is required to be submit:ed to the NRC only if direct combination of codirectional or modal responses due to earthquake cotton was used. Since the SRSS combina:icn method was used, the listing of the program will not be submitted to the NRC at this time.
Item 3: The response spectrum analysis technique e= ployed in PISTAR was verified using the ANSYS computer program (Reference 5). Proble: No. 6, as defined in Reference 4, was solved on both PISTAR and ANSYS to verify the SRSS combination techniques. The FISTAR Verification Report (Reference 2) provites more detailed information on the progra verification and is available upon request.
Item 4. No reevaluation of the safety-related piping listed above is required since the SRSS co=bination method was used.
440 ;g3 MM
D
[e Mr. F. E. Gregor -3 May 18, 1979 DET-01-119 If you have any other questions concerning this matter, please don't hesitate to call either of the undersigned.
Very truly yours ,
~
TFaJ. R. Arterburn, P.L.
Engineer A. B. Higginbotham, .E.
Project Engineer AEH/JRA:ba cc: 'W . F. Colbert D. F. Lehnert File 50.301.0001 440 104 nutech
