Letter Sequence RAI |
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Results
Other: ML20202H611, ML20239A178, NRC-98-0123, Responds to 980903 RAI Re Plant Staff Qualifications.Util Requests That NRC Act in Timely Manner Toward Resolution,Re Adoption of Reg Guide 1.8,Rev 2,to Ensure That It Does Not Impede Issuance of Fermi 2 ITS SER in May 1999, 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 Instructions, 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 ITS, 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 Rev, 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 Rev
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MONTHYEARML20239A1781998-09-0303 September 1998
Requests Addl Info Re Licensee Commitments Related to Plant Staff Qualifications.Response Requested within 45 Days of Receipt of Ltr
Project stage: Other
NRC-98-0123, Responds to 980903 RAI Re Plant Staff Qualifications.Util Requests That NRC Act in Timely Manner Toward Resolution,Re Adoption of Reg Guide 1.8,Rev 2,to Ensure That It Does Not Impede Issuance of Fermi 2 ITS SER in May 19991998-10-19019 October 1998
Responds to 980903 RAI Re Plant Staff Qualifications.Util Requests That NRC Act in Timely Manner Toward Resolution,Re Adoption of Reg Guide 1.8,Rev 2,to Ensure That It Does Not Impede Issuance of Fermi 2 ITS SER in May 1999
Project stage: Other
ML20155B7191998-10-26026 October 1998
Forwards RAI Re Conversion to Improved STSs for Plant,In Order to Complete Review of Util 980403 Amend Request
Project stage: RAI
ML20196F5701998-11-20020 November 1998
Forwards RAI Re Licensee 980403 Amend Request to Convert to Improved Std TSs for Fermi 2.Mutually Agreeable Completion Schedule of 45 Days for Response Was Established
Project stage: RAI
ML20198B8741998-12-0404 December 1998
Forwards RAI Re 980403 Amend Request to Convert Improved Std TSs Sections 3.4 & 3.9.Completion Schedule of 60 Days for Response Established Per Discussion with G Ohlemacher on 981109 & 10
Project stage: RAI
NRC-98-0150, Forwards Response to NRC 981026 RAI Re Fermi 2 Conversion to Improved Std Ts.Responses Reflect Results of Series of Meetings Between Util & NRC1998-12-10010 December 1998
Forwards Response to NRC 981026 RAI Re Fermi 2 Conversion to Improved Std Ts.Responses Reflect Results of Series of Meetings Between Util & NRC
Project stage: Meeting
ML20198J6761998-12-22022 December 1998
Forwards Request for Addl Info Re Conversion to Improved STS Section 3.8.Response Requested within 60 Days
Project stage: RAI
NRC-99-0001, Forwards Response to NRC 981120 RAI Re Fermi 2 Conversion to Improved Std Tech Specs.Plant ITS Submittal Will Be Revised to Reflect Response to RAI Following Completion of Remaining RAIs Re ITS Submittal,As Agreed Upon in Meetings with N1999-01-0808 January 1999
Forwards Response to NRC 981120 RAI Re Fermi 2 Conversion to Improved Std Tech Specs.Plant ITS Submittal Will Be Revised to Reflect Response to RAI Following Completion of Remaining RAIs Re ITS Submittal,As Agreed Upon in Meetings with NRC
Project stage: Response to RAI
ML20199G7561999-01-14014 January 1999
Forwards Request for Addl Info Re Conversion to Improved Stds Tss,Section 3.3 for Plant
Project stage: RAI
ML20202H6111999-01-25025 January 1999
Requests Addl Info Re Conversion to Improved Std Tss, Section 3.5 for Fermi 2
Project stage: Other
ML20202H8881999-02-0404 February 1999
Clarifies Intent of RAI Re Plant Staff Qualifications & Reg Guide 1.8,Rev 2, Qualification & Training of Personnel for Nuclear Power Plants, Dtd Apr 1987.Staff Position on Issue Neither New Nor Different Position from Previous Position
Project stage: RAI
ML20203F6761999-02-11011 February 1999
Forwards Request for Addl Info Re Conversion to Improved Standard Ts,Section 3.6 for Fermi 2
Project stage: RAI
NRC-99-0032, Forwards Rev 4 to Fermi 2 Its,Per Submittal .Rev Provides Responses to NRC RAI Re ITS Sections 3.4 & 3.9 Contained in Ltr1999-03-30030 March 1999
Forwards Rev 4 to Fermi 2 Its,Per Submittal .Rev Provides Responses to NRC RAI Re ITS Sections 3.4 & 3.9 Contained in Ltr
Project stage: Response to RAI
NRC-99-0033, Submits Initial Responses to RAIs Re Conversion to Improved Tech Specs Contained in Noted Refs 1-5.Util Has Found Extensive Dialog with NRC That Has Taken Place to Date to Be Extremely Fruitful in Effectively Managing Fermi 21999-04-0808 April 1999
Submits Initial Responses to RAIs Re Conversion to Improved Tech Specs Contained in Noted Refs 1-5.Util Has Found Extensive Dialog with NRC That Has Taken Place to Date to Be Extremely Fruitful in Effectively Managing Fermi 2
Project stage: Response to RAI
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
Project stage: Response to RAI
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
Project stage: Response to RAI
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
Project stage: Response to RAI
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
Project stage: Other
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
Project stage: Request
ML20216D6091999-07-26026 July 1999
Rev 11 to ITS Submittal,Dtd 980403,providing Update to ITS Sections 3.5,3.6 & 3.8
Project stage: Request
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
Project stage: Other
ML20211C4761999-08-0606 August 1999
Forwards Draft Safety Evaluation Re Proposed Conversion of Current TS to Improved Standard TS
Project stage: Draft Approval
IR 05000341/19990061999-08-0606 August 1999
Insp Rept 50-341/99-06 on 990712-0716.No Violations Noted. Major Areas Inspected:Review of Various Aspects of Licensee Chemistry & Radiation Protection Programs,Specifically in Listed Areas
Project stage: Request
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
Project stage: Draft 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
Project stage: Other
NRC-99-0078, Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included1999-08-25025 August 1999
Rev 14 to Application for Amend to License NPF-43,providing Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Brief Abstract of Changes Included in Rev & Revised Pages for Submittal & Rev Instructions,Included
Project stage: Request
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
Project stage: Other
1999-02-04
[Table View] |
Similar Documents at Fermi |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N4261999-10-25025 October 1999
Forwards Amend 17 to License DPR-9 & Safety Evaluation. Amend Revises TS by Deleting SR D.3.c,which Required Weekly Observation of Nitrogen Cover Gas Pressure within Sodium Storage Tanks Located in Sodium Building
NRC-99-0085, Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl1999-10-22022 October 1999
Forwards Rev 15 to Fermi 2 Security Personnel Training & Qualification Plan, IAW 10CFR50.54(p)(2).Without Encl
NRC-99-0094, Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed1999-10-22022 October 1999
Forwards Safeguards Event Rept 99-S01-00 for Reportable Event That Occurred on 990922.Commitments Made by Util Listed
ML20217P1661999-10-21021 October 1999
Forwards Insp Rept 50-341/99-17 on 990927-1005.No Violations Noted
ML20217M0771999-10-19019 October 1999
Confirms Discussion Between GL Shear,M Mitchell,E Kosky, D Williams,B Rumins,D Harmon & W Rutenberg in Public Meeting on 990923.Purpose of Meeting Was to Discuss Current Status RP Program at Enrico Fermi 2
ML20217N9231999-10-15015 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 40
ML20217E5671999-10-14014 October 1999
First Partial Response to FOIA Request for Documents.Records in App a Already Available in Pdr.App B Records Encl & Being Released in Entirety
NRC-99-0087, Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons1999-10-12012 October 1999
Responds to NRC Re Violations Noted in Insp Rept 50-341/99-10.Licensee Contests Subject Violation,Due to Listed Reasons
NRC-99-0083, Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal1999-10-0707 October 1999
Submits Requested Response to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal
ML20217D5331999-10-0707 October 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 39
ML20217F5931999-10-0707 October 1999
Forwards Insp Rept 50-341/99-11 on 990724-0908.Two Violations Re Failure to Follow Procedures While Sampling Standby Liquid Control Tank & Wear Dosimetry Properly Being Treated as Noncited Violations
ML20217B8261999-10-0404 October 1999
Forwards Summary of Decommissioning Insp Plan for Fy 2000. Plan Will Be Updated Annually & May Be Revised at Any Time Based Upon Future Insp Findings,Events & Resource Availability
ML20212J8121999-10-0101 October 1999
Discusses Plant,Unit 2 Completion of Licensing Action for GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at Npps. Ack Efforts That Licensee Have Completed to Date in Preparing Plant for Y2K Transition
ML20212K8881999-09-30030 September 1999
Refers to 990928 Meeting Conducted at Fermi Unit 2 to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PSA Staff
ML20217A3261999-09-30030 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 38
NRC-99-0091, Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations1999-09-27027 September 1999
Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations
ML20212J8331999-09-27027 September 1999
Responds to Licensee 990924 Request That NRC Exercise Discretion Not to Enforce Compliance with Actions Required in TS 3/4.6.1.8.Ltr Documents 990923 Telcon with Util in Which NRC Orally Issued NOED
ML20216G9791999-09-24024 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 37
NRC-99-0092, Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys1999-09-24024 September 1999
Documents Util Request for Enforcement Discretion with Respect to Requirements of TS 3/4.6.1.8 Re Drywell & Suppression Chamber Purge Sys
ML20216H3561999-09-23023 September 1999
Informs That During 990914 Telcon,L Sanders & M Bielby Made Arrangements with NRC to Inspect Licensed Operator Requalification Program at Fermi Nuclear Station for Week of 991129 Which Coincides with Util Regularly Scheduled Exam
ML20216H4541999-09-23023 September 1999
Informs That During 990914 Telcon L Sanders & M Bielby Made Arrangements for Administration of Licensing Exams at Fermi Nuclear Station for Week of Jan 31,2000.NRC Will Make Exam Validation Visit to Facility During Week of Jan 10,2000
ML20212F3241999-09-20020 September 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 36
NRC-99-0081, Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public1999-09-17017 September 1999
Submits Eight Relief Requests Associated with Containment Inservice Exam Program for Fermi 2 Plant,Per Provisions of 10CFR50.55a(g)(5)(iv).Requested Relief Does Not Adversely Affect Health & Safety of Public
ML20217A9421999-09-0909 September 1999
Informs That NRC Plan to Conduct Addl Resident Insps Beyond Core Insp Program Over Next 6 Months to Assess Improvements in Areas of Procedural Compliance & Quality of Work. Historical Listing of Plant Issues Encl
NRC-99-0079, Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-09-0808 September 1999
Forwards Rev 15 to Fermi 2 ITS Submittal,Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
ML20211Q0991999-09-0303 September 1999
Forwards Rev 35 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0090, Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld1999-09-0303 September 1999
Forwards Proprietary Operator License Renewal Application, NRC Forms 398 & 396 for SW Burt,License SOP-30199-3. Proprietary Encls Withheld
NRC-99-0066, Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)1999-08-30030 August 1999
Forwards semi-annual fitness-for-duty Rept for Fermi 2 for Period of 990101-0630,IAW 10CFR26.71(d)
ML20211G4951999-08-24024 August 1999
Forwards Rev 34 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval1999-08-19019 August 1999
Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval
IR 05000341/19990131999-08-19019 August 1999
Discusses Insp Rept 50-341/99-13 & OI Rept 3-98-039 Conducted Into Potential Misconduct of Operator Formerly Employed by De.Nrc Determined That Violation of NRC Regulations Occurred.Synopsis of IO Rept Encl
NRC-99-0056, Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation1999-08-19019 August 1999
Forwards Rev 2,change 0 to ISI-Nondestructive Exam (ISI-NDE) Program (Plan) for Piping,Components & Integral Attachments, for Second ten-year Interval of Fermi 2 Plant Operation
ML20211C0521999-08-17017 August 1999
Forwards Tables for Sections 3.6 & 3.7 of Draft Safety Evaluation of Proposed Conversion of Current TS to Improved Standard TS
NRC-99-0089, Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev1999-08-17017 August 1999
Forwards Rev 13 to Fermi 2 ITS Submittal Dtd 980403.Rev Provide Update for Remaining Open Issues Associated with NRC Review of ITS Submittal.Attachment 1 Contains Brief Abstract of Changes Included in Rev
ML20217E6181999-08-13013 August 1999
FOIA Request for Documents Re Implementing Regulations in 10CFR & Requesting That Region III Task Interface Agreement (TIA) Related to Fermi 2 Plant Be Made Available
IR 05000341/19990011999-08-10010 August 1999
Forwards Insp Rept 50-341/99-01 on 990619-0723 & Nov. Violation of Concern Because Operators Did Not Understand License Requirements & Placed Plant in Configuration Where EDG 11 Was Removed from Service
IR 05000341/19990121999-08-0606 August 1999
Forwards Insp Rept 50-341/99-12 on 990712-0716.No Violations Noted.Insp Focused on Implementation of Plant Chemistry & Radiological Environ Monitoring Programs & Operation of post-accident Sampling Sys
ML20211C4761999-08-0606 August 1999
Forwards Draft Safety Evaluation Re Proposed Conversion of Current TS to Improved Standard TS
NRC-99-0057, Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS1999-08-0404 August 1999
Forwards Rev 12 to ITS 980403 Submittal,Providing Update to Submittal for ITS Section 3.3,including Changes Associated with NRC Review of Rev 6 ITS
ML20210N5451999-08-0303 August 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 33
NRC-99-0077, Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS1999-07-26026 July 1999
Forwards Rev 11 to Fermi ITS Submittal,Dtd 980403,providing Update to Submittal for ITS Sections 3.5,3.6 & 3.8.Update Includes Changes Associated with NRC Review of Util Transmittals of Revs 5,5a & 7 to ITS
ML20210J2121999-07-23023 July 1999
Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation
NRC-99-0053, Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl1999-07-15015 July 1999
Forwards Rev 14 to Fermi 2 Security Personnel Training & Qualification Plan, Per 10CFR50.54(p)(2).Changes Do Not Decrease Effectiveness of Plan.Summary of Changes Also Encl
ML20209H7211999-07-14014 July 1999
Forwards Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section), Rev 32
NRC-99-0054, Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal1999-07-13013 July 1999
Forwards Rev 10 to Fermi 2 ITS Submittal, , Providing Update to Submittal for ITS Section 3.4,RCS.Update Includes Changes Associated with NRC Review of Util Transmittal of Rev 4 to ITS Submittal
ML20209F6571999-07-12012 July 1999
Forwards Insp Rept 50-341/99-09 on 990516-0618.No Violations Noted.Weak Procedural Guidance,Communications Issues & Configuration Control Weaknessess Were Evident
NRC-99-0052, Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions1999-07-0707 July 1999
Forwards Rev 9 to Fermi 2 ITS Submittal,Dtd 980403. Attachment 1 Contains Brief Abstract of Changes Included in Rev.Attachment 2 Contains Revised Pages for Submittal Along with Rev Instructions
ML20196J5511999-07-0202 July 1999
Discusses GL 92-01,Rev 1,Supp 1, Rv Integrity, Issued by NRC on 950519 & DE Responses & 980729 for Fermi 2.Informs That Staff Revised Info in Rvid & Released Info as Rvid Version 2 as Result of Review of Responses
ML20209C6141999-07-0101 July 1999
Rev 31 to Approved UFSAR Lcrs That Have Not Been Incorporated Into UFSAR Hardcopy (Sorted by Section)
NRC-99-0076, Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included1999-06-30030 June 1999
Forwards Rev 8 to ITS Submittal to Provide Update to ITS Submittal for ITS Section 3.7.Brief Abstract of Changes Included
1999-09-09
[Table view]
Category:OUTGOING CORRESPONDENCE
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
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
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
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
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
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
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
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
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
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
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
ML20210J2121999-07-23023 July 1999
Discusses NRC OI Investigation Rept 3-98-039 Completed on 990524 & Forwards Notice of Violation
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
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
ML20209E9991999-06-30030 June 1999
Forwards Insp Rept 50-016/99-01 on 990614-17.No Violations Noted.Potential Weakness in Airborne Effluent Concentration Assessment Identified
ML20209B2471999-06-29029 June 1999
Informs That NRR Revised Schedule for Conversion of Fermi 2 TS to Improved Std Ts.Planned Amend Date Has Been Moved to 990930 & Date for Draft Amend Has Been Moved to 990806
ML20207E4961999-06-0101 June 1999
Forwards Insp Rept 50-341/99-07 on 990402-0515.One Violation of NRC Requirements Occurred Re Failure to Keep TS Requirements Re Approval of Overtime Deviations.Violations Being Treated as non-cited Violations,Consistent with App C
ML20207D3311999-05-26026 May 1999
Forwards Insp Rept 50-341/99-04 on 990503-07.No Violations Noted.During Insp,Nrc Observation of Licensee Activities Showed Radiological Emergency Response Preparedness Program Maintained in Effective State of Operational Readiness
ML20206N7351999-05-14014 May 1999
Forwards RAI Re Plant Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During DBA Conditions
ML20206N4621999-05-13013 May 1999
Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Management Created. Reorganization Chart Encl
ML20206J9131999-05-10010 May 1999
Forwards SE Finding That Util Adequately Addressed Actions Requested in GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves,
ML20206Q7041999-05-0606 May 1999
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-341/99-02 on 990308
ML20206G4931999-05-0505 May 1999
Refers to DE 980804 Requests for Relief (PR-8,Rev 2 & PR-12) from IST Requirements of ASME Code for RHR Pumps.Review of Relief Requests Completed.Se Approving Relief Requests Encl
ML20206K4031999-04-29029 April 1999
Forwards Partially Withheld (Ref 10CFR73.21) Insp Rept 50-341/99-08 on 990405-09.No Violations Noted.Concern Expressed Over NRC Observations of Poor Performance Demonstrated During Some Contingency Response Drills
ML20205T3841999-04-23023 April 1999
Forwards Insp Rept 50-341/99-03 on 990218-0401.Two Violations Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
ML20205S8481999-04-20020 April 1999
Informs That Changes in Rev 22 Do Not Decrease Effectiveness of Emergency Plan & Plan Continues to Meet Stds of 10CFR50.47(b) & Requirements of App E to 10CFR50.NRC Approval Is Not Required
ML20205Q7001999-04-15015 April 1999
Forwards Amend 16 to License DPR-9,allowing Possession of Nominal Amount of Special Nuclear Matl,In Response to 980717 Application.Related SER & Notice of Issuance Also Encl
ML20205P1691999-04-14014 April 1999
Forwards Insp Rept 50-341/99-06 on 990315-19.No Violations Noted.Insp Focused on Aspects of Radioactive Effluent Monitoring,Liquid Waste Processing,Esf Filtration & CR Habitability & Solid Waste Mgt & Transportation Programs
ML20204E4061999-03-19019 March 1999
Forwards Insp Rept 50-341/99-05 on 990308-11.No Violations Noted.Insp Concluded That Fire Protection Program Was Effective
ML20204E0271999-03-17017 March 1999
Forwards SE Accepting Licensee & Suppl, ,which Requested NRC Approval of Alternative Rv Weld Exam,Per 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(ii)(A)(5), for Plant,Unit 2 for 40-month Period
ML20207L7281999-03-0909 March 1999
Informs That Util Ltrs & 981026 Responding to GL 96-01, Testing of Safety-Related Logic Circuits, Completes Licensing Action for Fermi 2
ML20207J1401999-03-0808 March 1999
Forwards Insp Rept 50-341/99-02 on 990111-29 & Notice of Violation.One Violation Identified in Area of Design Control.Violation of Concern Because Errors Existed in Three of Six Calculations Reviewed
ML20207G5711999-03-0404 March 1999
Discusses 990301 Meeting Between GL Shear,M Mitchell, D Williams,C Budnik & M Clements Re Current Status of Radiation Protection Program at Facility
ML20207E2491999-02-22022 February 1999
Discusses Licensee 980617 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program for MOV Periodic Verification for Fermi-2.Forwards RAI Re Fermi-2 Response to GL 96-05
ML20207E6451999-02-22022 February 1999
Submits Correction to Insp Rept 50-341/98-15 Issued on 981207.Rept Incorrectly Documented That Loose Internal Sleeving on Turbine Control Valve Caused Power Oscillations Greater than 10% During Plant Operation
ML20203F6761999-02-11011 February 1999
Forwards Request for Addl Info Re Conversion to Improved Standard Ts,Section 3.6 for Fermi 2
ML20203F2541999-02-10010 February 1999
Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function
ML20203F6911999-02-10010 February 1999
Discusses Completion of Licensing Action for Bulletin 96-03, Potential Plugging of Emergency Core Cooling Suction Strainers by Debris in Boiling-Water Reactors,
ML20203G6411999-02-0808 February 1999
Informs of Receipt of Encl FEMA Correspondence Received 990119,transmitting FEMA Final Exercise Rept for 980608 Plume Exposure Pathway Exercise at Enrico Fermi II Npp.No Deficiencies Were Identified During Exercise
ML20202H8881999-02-0404 February 1999
Clarifies Intent of RAI Re Plant Staff Qualifications & Reg Guide 1.8,Rev 2, Qualification & Training of Personnel for Nuclear Power Plants, Dtd Apr 1987.Staff Position on Issue Neither New Nor Different Position from Previous Position
ML20202H6111999-01-25025 January 1999
Requests Addl Info Re Conversion to Improved Std Tss, Section 3.5 for Fermi 2
ML20206S1111999-01-21021 January 1999
Forwards Insp Rept 50-341/98-19 on 981110-990104.No Violations Noted.Inspectors Noted Potential Trend Re Documented Operability Assessments That May Not Have Been Performed for C/A Resolution Documents
ML20199G7561999-01-14014 January 1999
Forwards Request for Addl Info Re Conversion to Improved Stds Tss,Section 3.3 for Plant
ML20198S3101999-01-0606 January 1999
Forwards Amend 15 to License DPR-9,consisting of Changes to TS in Response to 980128 Application.Related SER & Notice of Issuance,Also Encl
1999-09-09
[Table view] |
Text
. ,
l .. . Mr. Douglis R. Gipson December 4, 1998 I
- Senior Vice Pr:sid:nt l
Nuclear Generation
- Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING CONVERSION TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS, SECTIONS 3.4 AND 3.9 FOR FERMI 2 (TAC NO. MA1465) l
Dear Mr. Gipson:
On April 3,1998, the Detroit Edison Company (DECO) submitted an amendment request to convert to the improved standard technical specifications for Fermi 2. By a letter dated September 28,1998, DECO provided a supplement to the original submittal. The staff has reviewed Sections 3.4 and 3.9 of the proposed conversion. Additionalinformation, as i discussed in the enclosure, is requested in order for the staff to complete its review.
l The enclosed request was discussed with Mr. G. Ohlemacher of your staff on November 0 and 10,1998. A mutually agreeable completion schedule of 60 days for your response was established. If circumstances result in the need to revise the schedule, please call me at th'eearliest opportunity. Note that the format and text of the questions differs from l the version discussed at the meeting. The enclosure reflects the questions as prepared by the section lead reviewer.
If you should have any questions regarding this request, please contact me at 301-415-2828.
Sincerely, ORIGINAL SIGNED BY Andrew J. Kugler, Project Manager Project Directorate lil-1 Division of Reactor Projects -lil/IV Docket No. 50-341
Enclosure:
As stated I cc w/ encl: See next page DISTRIBUTION Docket File PD3-1 RF AVegel, Rill (AXV)
PUBLIC _ OGC ACRS EAdensam (EGA1)
JZwolinski MWeston JFoster DOCUMENT NAME: G:\PD3-1\WPDOCS\ FERMI \FE-STSO4.RAI To receive a copy of th a document, indicate in the t>on *C"
- Copy without attachmr.t/ enclosure "P a Copy with attachment / enclosure "N" = No copy l OFFICE PM:PD31 E LA:PD31 , E D;PD31 l IJ NAME AKugler:db Qg4 CJamerson Q / CACarpenter CM-.
t1 -/ I /98 /
DATE lE / l /98 V \2 / 4- /98
_,,,co OFFICIAL REC @D COPY 9812210209 981204 PDR ADOCK 05000341
- 1. u
.. . Mr. Douglas R. Gipson December 4, 1998 '
- S:nior Vice Presid:;nt Nuclear Generation Detroit Edison Company '
6400 North Dixie Highway Newport, Michigan 48166
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING CONVERSION TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS, SECTIONS 3.4 AND 3.9 FOR FERMI 2 (TAC NO. MA14BS)
Dear Mr. Gipson:
On April 3,1998, the Detroit Edison Company (DECO) submitted an amendment request to convert to the improved standard technical specifications for Fermi 2. By a letter dated September 28,1998, DECO provided a supplement to the original submittal. The staff has reviewed Sections 3.4 and 3.9 of the proposed conversion. Additionalinformation, as discussed in the enclosure, is requested in order for the staff to complete its review.
The enclosed request was discussed with Mr. G. Ohlemacher of your staff on November 9 and 10,1998. A mutually agreeable completion schedule of 60 days for your response was established. If circumstances result in the need to revise the schedule, please call me at the earliest opportunity. Note that the format and text of the questions differs from the version discussed at the meeting. The enclosure reflects the questions as prepared by the section lead reviewer.
If you should have any questions regarding this request, please contact me at 301-415-2828.
Sincerely, ORIGINAL SIGNED BY Andrew J. Kugler, Project Manager Project Directorate 111-1 Division of Reactor Projects - til/IV Office of Nuclear Reactor Regulation Docket No. 50-341
Enclosure:
As stated cc w/ encl: See next page DISTRIBUTION: Docket File PD3-1 RF AVegel, Rill (AXV)
PUBLIC OGC ACRS EAdensam (EGA1)
JZwolinski MWeston JFoster j DOCUMENT NAME: G:\PD3-1\WPDOCS\ FERMI \FE-STS04.RAI l To receive e copy of this document, indicate in the non c . copy without ottachment/ enclosure "E" = Copy wtm ettachment/ enclosure "N"
- No copy l OFFICE PM:PD31 lE LA:PD31 r E D:PD31 l LJ NAME AKugler:db Q$, CJamerson Q/ CACarpenter C(6 DATE lt / l /98 V 12 / l /98 / 12 / 4. /98 OFFICIAL REC (TRD COPY
. - . . _ . - _ . . . - - . . _ . ~ ~ . ~ . . . _ . - . . . . . . . . - . - . . . . - -.. ..
.. pm At! i g \ UNITED STATES i
- . j 2
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3000H001 k,
...../ December 4, 1998 l '
Mr. Douglas R. Gipson Senior Vice President l Nuclear Generation l Detroit Edison Company 6400 North Dixie Highway Newport, Michigan 48166 l
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING CONVERSION TO l l lMPROVED STANDARD TECHNICAL SPECIFICATIONS, SECTIONS 3.4 AND 3.9 FOR FERMI 2 (TAC NO. MA1465)
Dear Mr. Gipson:
On April 3,1998, the Detroit Edison Company (DECO) submitted an amendment request to convert to the improved standard technical specifications for Fermi 2. By a letter dated September 28,1998, DECO provided a supplement to the original submittal. The staff has reviewed Sections 3.4 and 3.9 of the proposed conversion. Additionalinformation, as discussed in the enclosure, is requested in order for the staff to complete its review.
The enclosed request was discussed with Mr. G. Ohlemacher of your staff on November 9 and 10,1998. A mutually agreeable completion schedule of 60 days for your response was established. If circumstances result in the need to revise the schedule, please call me at the earliest opportunity. Note that the format and text of the questions differs from the version discussed at the meeting. The enclosure reflects the questions as prepared by the section lead reviewer.
If you should have any questions regarding this request, please contact me at 301-415-2d28.
Sincerely, 1
Andrew J. gjer, roject Manager Project Directorate Ill-1 Division of Reactor Projects -lil/lV Office of Nuclear Reactor Regulation Docket No. 50-341
Enclosure:
As stated
! cc w/ encl: See next page i
. - . . . . ~ . . . . . . _ . - - - . - _ . . . - - - . .. .. . ..
t .
1-1 .
Mr. Douglas R. Gipson Fermi 2 l Detroit Edison Company I
cc:
L John Flynn, Esquire Senior Attorney Detroit Edison Company 2000 Second Avenue l _ Detroit, Michigan 48226 Drinking Water and Radiological Protection Division Michigan Department of Environmental Quality l 3423 N. Martin Luther King Jr Blvd -
P. O. Box 30630 CPH Mailroom Lansing, Michigan 4E309-8130 i U.S. Nuclear Regulatory Commission Resident inspector's Office 6450 W. Dixie Highway Newport, Michigan 48166 Monroe County Emergency Management l
Division 963 South Raisinville '
l Monroe, Michigan 48161 Regional Administrator, Region ill U.S. Nuc! ear Ftsgulatory Commission 801 Warrenville Road Lisle, Illinois 60532 4351 Norman K. Peterson Director, Nuclear Licensing
- Detroit Edison Company Fermi 2 - 280 TAC 6400 North Dixie Highway Newport, Michigan 48166 t
August 1997 l
._ . _. _ _ . .. _ .._. ~ . _ __ . _ . _ _ _ . __ _._
I
! REQUEST FOR ADDITIONAL INFORMATION REGARDING ;
CONVERSION TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS, i SECTIONS 3.4 AND 3.9 FOR FERMI 2 (TAC NO. MA1465) 4 General Note Throughout this request for additior.al information (RAI), references to a standard technical specification (STS) mean the standard version of the TS published by the !
NRC in NUREG-1433, " Standard Technical Specifications, General Electric Plants, BWR/4,"
Revision 1. References to an improved TS (ITS) mean the proposed converted TS submitted i by the licensee. RAI numbers (e.g., RAI 3.4.5-1) refer to the numbers used in the November 9 '
and 10,1998, meeting.
All Sections RAI 0.0-1: There is a generic issue involving a number of the Less Restrictive Administrative (LA) discussions of change (DOCS) in the Fermi submittal. Refer to RAI 0.0-1 in the !
October 26,1998, request for additional information. Additional DOCS affected by this issue are listed in the following table:
ITS LA DOC !
3.4.3 LA.2 3.4.6 ' LA.2 3.4.9 LA.2 Section 3.4 Generic flTS 3.4.5. 3.4.8. and 3.4.9)
RAI 3.4-1: DOCS LR.1 for current TS (CTS) 3.4.3.2 (ITS 3.4.5), LR.2 for CTS 4.4.3.2.2.b (ITS 3.4.5), LR.1 for CTS 4.4 9.1.2 (ITS 3.4.8), and LR.1 for CTS 4.4.9.2.3 (ITS 3.4.9) discuss the change in the context of a relocation. However, LR DOCS are supposed to be used for the deletion of information that does not need to be relocated to a licensee-controlled program with regulatory program controls. If these DOCS are meant to be deletions, the use of the term relocation is incorrect. If they are relocations, they should be LA DOCS and they should clearly state the program to which the information is relocated. Revise these DOCS to clearly state the disposition of the affected information.
ITS 3.4.1
- 1. RAI 3.4-2: Because of the many changes from the STS and the CTS, this specification is considered beyond scope and will be reviewed by the technical staff. No comments are provided.
ENCLOSURE
_ ., ~ . _ . . _ , __ _- , _ _ _ _ - _ _ - --
d j ... . ... ._ _ _ .
No comments.
ITS 3.4.3
- 2. RAI 3.4-3: CTS 3.4.2.1 Action c provides Action requ'rements for inoperable safety relief valve (SRV) position indicators and CTS 4.4.2.1.1 specifies surveillance requirements for SRV valve position indicators. These are not contained in ITS 3.4.3. DOC LA.2 justification states that the position indicators do not impact Operability of the SRVs but CTS 3.4.2.1 Action c and CTS 4.4.2.1.1 had valid justification for their inclusion in the CTS such that COLD SHUTDOWN is required if one or more position indicators can not be restored to OPERABLE status within the given time frame. Pocsibly the reason for CTS 3.4.2.1 Action c, and CTS 4.4.2.1.1 Surveillance is to support CTS 3.4.2.1 Action :
b which has been eliminated from the ITS. The justification for deleting CTS 3.4.2.1 Action c and CTS 4.4.2.1.1 Surveillance from ITS 3.4.4 that counters the reason why j SRV position indicator requirements were previously included in CTS 3.4.2.1, has not been addressed by DOC LA.2. Provide additionaljustification for removing SRV position indicator requirements from ITS 3.4.3 that counters the reason why they were included in the CTS and are no longer required in the ITS.
In addition, see RAI 0.0-1 for an issue related to DOC LA.2.
ITS 3.4.4
- 3. RAI 3.4-4: CTS 3.4.3.2.c and CTS 3.4.3.2.e specify limits on reactor coolant system !
(RCS) leakage "within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period." ITS 3.4.4.c and ITS 3.4.4.d change the l wording for this limiting condition for operation (LCO) to "within the previous 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period" which is consistent with the STS. However, there is no DOC addressing this wording change. Provide discu1sion and justification for the equivalency of this wording change.
- 4. RAI 3.4-5: STS 3.4.4 Action B1 requires " Reduce LEAKAGE to within limit in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />."
ITS 3.4.3 Action B deletes this requirement per Justification For Difference (JFD) P.S.
JFD P.5 states that when there is an acceptable compensatory action to take (in this case l STS Required Action B.2), the NUREG does not include actions that provide an explicit '
option to restore LCO compliance. This justification in JFD P.5 is in error because STS 3.4.4 Required Action B.1 does exist in the NUREG (STS) but is deleted from the ITS in <
the STS markup. This would be a generic change. Make ITS 3.4.4 Required Actions consistent with the STS.
I
- 5. RAI 3.4-6 & 7: CTS 4.4.3.2.1.a requires monitoring the primary containment atmospheric gaseous radioactivity at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. ITS surveillance requirement (SR) 3.4.4 requires verifying RCS leakage is within limits each 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This change to the frequency of monitoring for gaseous radioactivity is justified by DOC L.1. However, the l
1
o .
I i
3-l 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> only applies to MODE 1. MODES 2 and 3 are 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Provide discussion and justification for the differences.
ITS 3.4.5
, 6. RAI 3.4-8: ITS SR 3.4.5.1 specifies pressure isolation valve (PlV) leakage limits that are based on valve size. ITS SR 3.4.5.l insert 3.4.5-1 is added to it and provides exceptions l by stating "for PlVs other than LPCI [ low pressure coolant injection] loop A and B injection isolation valves." ITS 3.4.5.1 insert 3.4.5-2 provides these exceptions with specific leakage limits for both the LPCI loop A and B injection isolation valves and the LPCI loop A and B inboard injection isclation testable check valves. Shoulo ITS SR 3.4.5.1 Insert 3.4.5-1 include the LPCI loop A and B inboard injection isolation testable check valves. If so, provide additional wording in insert 3.4.51 that includes the LPCI loop A and B inboard injection isolation testable check valves. Some of these changes appear to be different than the CTS and the STS. Also, SR 3.4.5.1 is not clear, perhaps restructuring might help.
~
- 7. RAI 3.4-9 & 10: With one or more RCS PlVs not within limit, STS 3.4.5 Action A specifies Required Action A.1 as well as Required Action A.2. ITS 3.4.5 Condition A contains Required Action A.1 which is correctly derived from CTS 3.4.3.2 Action c, but STS 3.4.5 Required Action A.2 is deleted including the reference to it in the ITS 3.4,5 NOTE for Required Actions. In addition, the NOTE for STS 3.4.5 Required Actions contains the sentence "and be in the reactor coolant pressure boundary (or the high pressure portion of the system)." This sentence is also deleted from the ITS 3.4.5 Required Action NOTE . The justification for these deletions is shown as JFD P.1 which is fundamentally a generic justification and does not specifically address these deletions.
There is no justif: cation for why the Note should not apply to you. Retain the one or the other of the phrases "and be in the reactor coolant pressure boundary [or the high
. pressure portion of the system]." include an explanation of what "at least one other closed manual...." means in 3.4.3.2 ACTION c. Does this imply two valves. Also, the asterisk refers only to the " Check Valve. Is this the only valve in question here.
- 8. See generic RAI 3.4-1 for an issue related to DOCS LR.1 and LR.2.
- 9. RAI 3.4-11: See RAI 3.4-1 for a generic issue related to LR DOCS. In addition, CTS 3.4.3.2 Action d, CTS 4.4.3.2.3, and CTS Table 3.4.3.2-2 contain actions, surveillance details, and a specific list of PlV leakage pressure monitors related to alarm-only functions. DOC LR.1 justification states that the alarm functions do not relate directly to the Operability requirements for the RCS but, CTS 3.4.3.2 Action d had valid justification for inclusion in the CTS such that COLD SHUTDOWN is required if one or more pressure interface valve leakage pressure monitors can not be restored to OPERABLE status within the given time frame. Should this requirement be retained in the instrumentation Section? This question will be referred to the reviewer for Section 3.3.
l
.. . l l i l
- 10. RAI 3.4-12: CTS 3.4.3.1.a requires the Operability of the primary containment atmosphere gaseous radioactivity monitoring system channel. ITS 3.4.6. b changes the wording of this requirement to one channel of primary containment atmosphere gaseous radioactivity monitoring system. ITS 3.4.6 and its bases do not indicate that this equipment has two channels, rather in most plants it has one channel as identified (gaseous) and the other channelis an " atmospheric particulate monitoring" channel. The reworded term "one channel of" in ITS 3.4.6.b can be misleading giving rise to an error of using the atmospheric par 1iculate channel as the "one channel of". Consider rewording ITS 3.4.6.b consistent with and equal to CTS 3.4.3.1.a.
l
- 11. See generic RAI 0.0-1 for an issue related to DOC LA.2.
)
- 12. RAI 3.4-13: ITS 3.4.6, Condition C, is missing the word " inoperable" at the end of the -
sentence as shown in the STS 3.4.6, Condition C, markup. Correct the wording of !
ITS 3.4.6, Condition C.
- 13. RAI 3.4-14: CTS 3.4.3.1 Action requires two leakage detection systems to remain Operable and allows a 30 day restoration time for any individual system inoperability. ITS 3.4.6 Action statements change this requirement to allow unlimited continued operation with either the primary containment atmosphere gaseous radioactivity monitor or drywall floor drain sump level monitoring system inoperable. STS 3.4.6 does not allow this less restrictive requirement and requires restoration within 30 days of any inoperable system even if only one system is inoperable. ITS 3.4.6 Action statements are a less restrictive change that is also a deviation from the STS.
DOC L.1 provides explanation by stating that the primary system for identifying and quantifying unidentified leakage in the containment is the drywell floor drain sump flow monitoring system and thus restoration within 30 days of the other two systems is only required if both of them are inoperable at the same time. This change is not consistent with the ST.S and appears to be a less restrictive Required Action and presentation preference. Provide additional discussion and justification for the less restrictive change and a justification for deviation from the STS. This item is under review by the technical staff as a beyond scope issue.
ITS 3.4.7
- 14. RAI 3.4-15: CTS Table 4.4.5-1 item 5 requires isotopic Analysis of an off-gas sample including Quantitative Measurements for at least Xe-133, Xe-135 and Kr-88 each 31 days. ITS 3.4.7 does not retain this requirement. DOC A.3 states that deletion of CTS Table 4.4.5-1 item 5 is acceptable because it is the same surveillance requirement as ITS S'R3.7.5.1 and therefore this deletion is an administrative change. This change does i not appear to be administrative because ITS SR 3.7.5.1 requires verification that the
(
gross radioactivity rate of noble gases is less than 340 millicuries /second after decay of
30 minuterr These two surveillances do not appear to be the same or equivalent sample l
analyses. Clarify the justification.
- 15. RAI 3.4-16: CTS 3A.5 Action c requires sdbpiing and analysis br lodine per item 4.b of CTS Table 4.4.5-1 when in Operational Condition 1 or 2 following changt:s in thermal power or off-gas level. ITS 3.4.7 eliminates this requirement. DOC A.2 states Sat the sampling requirements of CTS Table 4.4.51 item 4.a encompasses the requirements of item CTS Tab!9 4.4.5-1 item 4.b and CTS 3.4.5 Action c, because it requires lodine sampling each 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when activity exceeds a limit. This justification seems to be in error because the basic lodine sampling requirements, per ITS SR 3.4.7.1, is required only once per 7 days and then it is only required in Mode 1. There is no requirement within the 7-day interval, or during changing power levels, or increasing off-gas levels, to determine it lodine levels are increasin2. The proactive CTS sampling requirement in response to transient precursors such as power changes and increasing off-gas levels is thus eliminated without justification of why they are no longer needed. Provide additional discussion and justification for this less restrictive change.
- 16. RAI 3.4-17: CTS 3.4.5, Action c, Note
- states "Not applicable during the startup test program." This note is deleted in ITS 3.4.7 with justification per DOC A.2 However, DOC A.2 doesn't address this d<3letion. Provide discussion and justification for deleting CTS 3.4.5 Action c Note *
~
- 17. RAI 3.4-18: DOC L.1 provides a lengthy justification for deleting CTS LCO 3.4.5.b and its associated Actions and Surveillance Requirements. This involves the 100/E bar microcuries per gram limit and translates into deleting the sampling requirements of CTS Table 4.4.5-1 item 3 (Radiochemical for E bar determination). DOC L.1 does not address deleting CTS Table 4.4.51 item 1 (Gross Beta and Gamma Activity Determination) although the CTS markup shows DOC L.1 as the justification. While the change appears to be acceptable, provide the discussion and justification for deleting CTS Table 4.4.5-1 item 1.
ITS 3.4.8
- 18. See generic RAI 3.4-1 for an issue related to DOC LR.1.
ITS 3.4.9
- 19. RAI 3.4-19: CTS 3.4.9.2 Applicability states " Operational Condition 4 when irradiated fuel is in the reactor veasel and the water level is less than 20 feet 6 inches above the top of the reactor pressure vessel flange". This requirement is eliminated from ITS 3.4.9 Applicability. DOC A.3 provides discussion and justification for deleting the water level requirement but it does not address deleting the phrase "when irradiated fuel is in the t reactor pressure vessel". Provide additional discussion and justification for deleting the l phrase "when irradiated fuel is in the reactor pressure vessel" from ITS 3.4.9 i Applicability. This is a less restrictive change.
. 1
- 20. See generic RAI 0.0-1 for an issue related to DOC LA.2.
- 21. See generic RAI 3.41 for an issue related to DOC LR.1.
- 22. RAI 3.4 20: STS 3.4.10, RCS Pressure and Temperature (P/T) Limits, is written with the actual pressure / temperature limits being specified in the Pressure / Temperature Limits Report (PTLR). ITS 3.4.10 does not use the PTLR to specify limits but does not provide reference to the source that is used (e.g., Figure 3.4.10-1, etc.). Add the appropriate references.
- 23. RAI 3.4-21: CTS 3.4.1.4.a begins with the conditional phrase "When both loops have 4
been idle" and CTS 3.4.1.4.b begins with the conditional phrase "When only one loop has been idle" These phrases are deleted in the CTS markup and are marked with DOC A.2
- for justification. DOC A.2 provides discussion and justification for the combination of
- these CTS section requirements being equivalent to ITS SR 3.4.10.4 but does not address deleting these conditional phrases. In addition, ITS SR 3.4.10.4 is more restrictive than CTS 3.4.1.4.a because it applies at all times, not only when both loops have been idle. Provide discussion and justification for deleting the CTS 3.4.1.4.a and CTS 3.4.1.4.b phrases "When both loops have been idle" and "When only one loop has been idle" from ITS SR 3.4.10.4. J
- 24. RAI 3.4-22: CTS Figure 3.4.1.4-1 and reference to it, is contained within the CTS 3.4.1.4 markup under ITS specification ITS 3.4.10 and are deleted with DOC LR.1 shown as the justification. DOC LR.1 for ITS 3.4.10 addresses deleting this table with reference to
- ITS 3.4.1 " Scram" and " Exit" regions. Use of the terms " Scram" and " Exit" regions will j be reviewed under comment #1 for ITS 3.4.1. Although the justification contained in DOC LR.1 is reasonable, the power to flow map (CTS Figure 3.4.1.4-1) should be retained.
4 25. RAI 3.4-23 and RAI 3.4-24: CTS 3.4.6.1 Action requires that when in MODES 1,2, or 3, if any of the CTS 3.4.3.1 limib are exceeded, porform an engineering evaluation to determine tho effects of the out-of limit condition on the structuralintegrity of the RCS and determine that the RCS acceptable for (continued) operation, but the CTS does net );
establish a specific completion time. ITS 3.4.10 Required action A.2 establishes 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to determine that the RCS is acceptable for continued operation when in MODE 1, 2, or 3 and for other than MODE 1,2, or 3, ITS 3.4.10 Required Action C.2 establishes, !
prior to entering MODE 2 or 3. These changes are justified by the discussions in DOC !
A.S. These changes are more restrictive and not administrative. I in addition, ITS 3.4.10 Required Actions A.2 and C.2 only require determining that the RCS is acceptable for [ continued] operation. The CTS phrase " perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the RCS"is deleted without discussion. This appears to be a less restrictive change.
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. o Provide appropriate discussion and justification (more/less restrictive) for CTS 3.4.6.1 Action requirements changing to ITS 3.4.10 Required Actions A.2 and C.2.
- 26. RAI 3.4-25: CTS 4.4.6.1.2 specifies being to the right of CTS Figure 3.4.6.1-1 curve C which makes clear the safe area of the criticality limit curve. By implication the same applies (being to the right) to curve A and B although CTS 3.4.6.1 does not explicitly state to the right. ITS 3.4.10, as well as ITS Figure 3.4.10-1 (which is exactly.the same as CTS figum 3.4.6.1-1), and ITS 3.4.10 Bases do not specify anywhere that the safe area relative to curve A, B, or C is to the right. ITS 3.4.10 simply requires maintaining pressure and temperature within limits. The clarification previously contained in the CTS is not carried forth in ITS 3.4.10. Provide clarification in ITS 3.4.10 of the safe area relative to ITS Figure 3.4.10-1 curves A, B, and C.
num:s ITS 3.4.11
- 27. RAI 3.4-26: CTS 3.4.6.2 requires reactor steam dome pressure "less than" 1045 psig and CTS 3.4.6.2 Action applies with pressure " exceeding" 1045 psig. The CTS Action statement with pressure " equal to" 1045 psig is not specifically addressed in the CTS but CTS 4.4.6.2 surveillance also specifies pressure shall be verified to be "less than" 1045 psig. ITS 3.4.11 LCO and ITS SR 3.4.11.1 require reactor steam dome pressure "less than or equal to" 1045 psig. Adding " equal to" to ITS 3.4.11 LCO and ITS SR 3.4.11.1 is discussed within DOC A.2 as a resolution of a discontinuity within CTS 3.4.6.2 Action presentation. However, adding " equal to"in the ITS LCO and Surveillance is less
. restrictive and not administrative based upon the requirements of CTS 3.4.6.2 LCO and CTS 4.4.6.2. DOC A.2 does not state that the condition of being " equal to" 1045 psig is analyzed within safety bounds as acceptable and CTS 3.4.6.2 LCO and CTS 4.4.6.2 4
imply otherwise. Provide additional discussion and justification for adding " equal to" to ITS 3.4.11 LCO and ITS SR 3.4.11.1 as a less restrictive change.
Section 3.9
] iTS 3.9M
- 1. RAI 3.91: Bases insert B 3.9.4.-1 indicates that the insert is to clarify detail (see JFD P.6). The actual wording provides exception to the SR. This is a generic change because it is not in the CTS. Use the STS wording or obtain generic approval for the change.
ITS 3.9.5
- 2. RAI 3.9-25 in the Bases for ITS 3.9.5, the reference to LCO 3.1.2 is deleted. JFD P.4 indicates that LCO 3.1.2 does not contain requirements for control rods. However, SR 3.1.2.1 does referenEe frequency requirements following control rod replacement. Retain the reference.
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- 3. RAI 3.9-3: In JFD P.5, the licensee indicated that the changes to the Bases for ITS 3.9.5 are consistent with other ITS Bases. The BWR/6 has the same language. Further, the control rods are not a system. Specifications 3.9.1,3.9.2,3.9.3, and 3.9.4 refer to control rods. Any correction should be made consistently.
ITS 3.9.6
- 4. RAI 3.9-4: Are all of the changes to the first paragraph of the Applicable Safety Analysis justified by P.47 in general, clarify which JFDs apply to which changes in this section l (e.g., does JFD P.2 apply to all of the changes in the latter half of the first paragraph on l STS Bases page B 3.9-20). Should the reference to 23 feet of water in this section be your licensing basis as opposed to the references to 20 feet 6 inches elsewhere?
l ITS 3.9.7 '
- 5. RAI 3.9-5: The Applicability statements for ITS 3.9.7 and 3.9.8 include a note describing l an exception to the stated applicability. In the STS/ITS, exceptions are addressed directly in the Applicability statement. Relocate the information in the notes into the Applicability statements.
ITS 3.9.8
- 6. See RAI 3.9-5.
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