Letter Sequence RAI |
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TAC:MA0805, Implement 10 CFR 50, Appendix J, Option B, Add Bracketed Information to LCO 3.0.4 Inappropriately Deleted by Rev. 0 Change BWR-26, Revise LCO 3.0.2 Bases to Remove Possible Confusion (Approved, Closed) |
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MONTHYEARML18065B2031998-04-0101 April 1998 Discusses Plant Initial Screening Review of CPC Request for Conversion to Improved Tss.Util Requested to Prepare Tables Formatted IAW Model Se.Tables Should Be Provided to Staff in Listed Software Format Project stage: Approval ML18066A1731998-06-0404 June 1998 Discusses Model SE Re Licensee Request for Conversion to Improved Ts.Electronic Copy of SE Encl Project stage: Other ML18066A2521998-07-27027 July 1998 Refers to 980126 Licensee Request to Convert Palisades NPP Current TS to Improved TS (Its).Rai Re ITS Sections 3.8 & 5.0 Encl Project stage: RAI ML18066A2881998-08-21021 August 1998 Forwards Request for Addl Info Re TS Change Request to Convert Improved TS for Plant Project stage: RAI ML18068A4161998-08-24024 August 1998 Forwards RAI Re 980126 TS Change Request to Convert to Improved TS for Plant.Response to Staff Comments Requested within 60 Days of Receipt of Ltr Project stage: RAI ML18066A3431998-12-0404 December 1998 Forwards Request for Addl Info Re TSs Change Request to Convert to Improved TSs for Palisades Plant.Addl Info Needed in Sections 2.0,3.1 & 3.2.Response Requested 60 Days from Date Ltr Was Established Project stage: RAI ML18066A3841999-01-29029 January 1999 Forwards Request for Addl Info Re TS Change Request to Convert to Improved TS for Plant.Mutually Agreeable Completion Date of 990331 Established Project stage: RAI ML18068A5431999-03-17017 March 1999 Forwards RAI Re Licensee 980126 Request to Convert Palisades Nuclear Plant Current TSs to Improved Tss.Response Requested by 990430 Project stage: RAI ML18066A4511999-04-0707 April 1999 Discusses 990401 Telcon Re Palisades Improved TSs Review Schedule.Encl Table Provides Agreed Upon Milestone Dates for Completion of Review & Reflects Proposed Amend Request Date of 990830 Project stage: Other ML18066A5481999-07-13013 July 1999 Forwards Draft SE Re Proposed Conversion to Its.Se Based on Review of Consumers Energy Co 980126 Application & as Supplemented by 980430,0914,1012,1109,990301,22,30,0407, 0503,0604,11 & 17 Ltrs Project stage: Draft Approval 1998-08-21
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML18066A6871999-10-19019 October 1999 Forwards Response to NRC 990908 RAI Re Inservice Insp Program Relief Request 14.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6881999-10-19019 October 1999 Forwards Rev 5 to Palisades Nuclear Plant COLR, Per Requirements of TS 6.6.5.Ltr Contains No New Commitments & No Revs to Existing Commitments ML18066A6841999-10-13013 October 1999 Forwards Insp Rept 50-255/99-10 on 990812-0921.One Violation Noted Re Adherence to Radiological Protection Procedure Requirements.Violation Being Treated as Ncv,Consistent with App C of Enforcement Policy ML18066A6781999-10-0707 October 1999 Summarizes 991005 Meeting at Region III to Discuss Radiation Protection Program at Palisades.Topics Discussed Included Management Changes in Radiation Protection Program & Actions Taken to Correct Deficiencies Identified During 1998 Outage ML18066A6651999-10-0505 October 1999 Informs of Completion of Review of Palisades Plant 25-year Tendon Surveillance Rept & Associated post-surveillance Regression Analysis Submitted by Ltrs Dtd 971218,980223 & 980925.Forwards SE Supporting Performance of Surveillance ML18066A6721999-10-0404 October 1999 Forwards Operator Licensing Exam Rept 50-255/99-301(OL) for Initial Operator Licensing Exams at Palisades NPP Completed on 990614.Two RO Applicants & Two SRO Applicants Failed One or More Portions of Respective Exams & Were Denied Licenses ML18066A6741999-10-0202 October 1999 Forwards MOR for Sept 1999 for Palisades Nuclear Plant & Operating Data Rept Sheet for Month of Aug 1999.MOR for Aug 1999 Inadvertently Had Copy of Ref Data Sheet for Apr 1999 Data ML18066A6791999-10-0101 October 1999 Provides Response to RAI Re Draft Rept, Study of Air- Operated Valves in Us Nuclear Power Plants ML18066A6691999-09-30030 September 1999 Advises of Plans for Future Insp Activities at Facility for Opportunity to Prepare for Insps & to Provide Feedback on Any Planned Insps Which May Conflict with Plant Activities ML18066A6621999-09-30030 September 1999 Notifies NRC That Util Will Implement ITS at Plant on or Before Oct 31,2000 & Attachments 1 & 2 Contains Request for License Condition Which Relates First Performance of New or Revised Surveillance Requirements to Implementation of ITS ML18066A6601999-09-29029 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Examinations ML18066A6561999-09-28028 September 1999 Discusses Closeout of GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps. Understands That Util Will Address Concerns Raised by Insp Team at Future Date ML18066A6531999-09-23023 September 1999 Forwards Insp Rept 50-255/99-14 on 990831-0901.No Violations Noted.Insp Results Indicated with Crsd on-line (Non Outage) Planning & Scheduling Program Provided Effective Coordination & Established Appropriate Radiological Control ML18066A6471999-09-17017 September 1999 Forwards Final Clean Copies of ITS & Bases Pages Which Incorporate All Changes Proposed in Listed Ltrs.Clean Copies Also Incorporate Some Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to LCOs ML18066A6441999-09-15015 September 1999 Informs That as Result of 980908 Response to RAI Re GL 92-01,Rev 1,Suppl,staff Revised Info in Rvid & Released Info as Rvid Version 2 ML18066A6431999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Operator License Applicants During Wk of 000522,in Response to Nl Haskell ML18066A6381999-09-0808 September 1999 Forwards Request for Addl Info Re ISI Program Relief Request 14 for Palisades Plant ML18066A6391999-09-0303 September 1999 Forwards Insp Rept 50-255/99-09 on 990522-0811.No Violations or Deviations Noted ML18066A6331999-09-0202 September 1999 Forwards Monthly Operating Rept for Aug 1999 & Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18066A6261999-08-26026 August 1999 Forwards Addl New Valve Relief Request as Alternative to Code Requirements That Will Provide Acceptable Level of Quality & Safety.Request Would Allow Use of App II, Check Valve Condition Monitoring Program, of ASME OM Code-1995 ML18066A6231999-08-26026 August 1999 Forwards SE Related to ISI Program Request for Relief ML18066A6091999-08-19019 August 1999 Provides Licensee with Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML20211D5661999-08-17017 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d).Attachments 1 & 2 Summarize Test Results at Palisades Plant,Big Rock Point Plant & Corporate Ofc ML18066A6111999-08-13013 August 1999 Requests Exemption from Certain Requirements of 10CFR50,App R, Fire Protection Program for Nuclear Power Facilities Operating Prior to 790101. Request Concerns Oil Collection Sys Requirements for PCP Motors ML18066A6031999-08-0909 August 1999 Forwards SE Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Movs, for Plant ML18066A5921999-07-30030 July 1999 Forwards Results of Review by Consumers Energy of Two NRC Draft Repts Entitled, Evaluation of Air-Operated Valves at Light-Water Reactors & Study of Air-Operated Valves in Us Nuclear Power Plants ML18066A5881999-07-30030 July 1999 Provides Rev to Instrument Channel Drift Measurement Submitted on 990611,in Response to NRC Comments on Util RAI Response for Sections 3.3,3.5 & 3.6 & Editorial Changes Revs Necessary for Consistency within ITS ML18066A5971999-07-30030 July 1999 Forwards Markup of Draft NRC SE Re Util Proposal to Convert to Its.Ltr Contains No New Commitments & No Revs to Existing Commitments ML20210G8351999-07-29029 July 1999 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR ML18066A5801999-07-26026 July 1999 Discusses Evaluation of Relief Requests for ISI Re ASME Section Xi,Subsections IWE & Iwl.Staff Partially Denied Relief Request 1 on Basis That General Visual Exam in Lieu of VT-3 Exam.Relief Requests 4 & 6 Denied as Listed ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE ML18066A5651999-07-19019 July 1999 Forwards Corrections to Previously Submitted TS Section 3.7, Plant Systems, Converting to Its,Per NUREG-1432.Licensee Realized That Certain Provisions of CTS Had Been Inappropriately Replaced with Provisions from STS ML18066A5481999-07-13013 July 1999 Forwards Draft SE Re Proposed Conversion to Its.Se Based on Review of Consumers Energy Co 980126 Application & as Supplemented by 980430,0914,1012,1109,990301,22,30,0407, 0503,0604,11 & 17 Ltrs ML18066A5381999-07-0808 July 1999 Forwards Insp Rept 50-255/99-08 on 990522-0630.No Violations Noted.Determined That Emergent Repairs to EDG Were Completed in Timely & Skillful Manner to Prevent Challenge to Plant Operation ML18066A5361999-07-0606 July 1999 Discusses 990629 Meeting with PRA Staff Re Initiatives in Risk Area & to Be Establish Dialog Between SRAs & PSAs Staff ML18066A5111999-06-29029 June 1999 Provides Voluntary Confirmation of Facility Readiness as Outlined in GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Disclosure & Response Encl ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 ML20210G8791999-06-23023 June 1999 FOIA Request for All Document Communications Between NRC & Region III Involving R Landsman,B Jorgensen & R Caniano & NRC Staff Under Their Supervision & All Communications in Their Possession to & from Consumers Power Re Plant ML18066A5061999-06-17017 June 1999 Forwards Responses to NRC Questions for ITS LCOs 3.6.3 & 3.6.6 of 990126 Submittal.One Editorial Change in Addition to Those Made in Response to NRC Comments & Conforming Changes Made to Associated Bases,Encl ML18066A4991999-06-11011 June 1999 Forwards Responses to NRC Comments Re ITS Section 3.3 & Associated Revs to ITS Sections 1.0,3.3,3.4 & 3.9 of 990126 ITS Conversion Submittal.One Technical Change & Several Editorial Changes Unrelated to NRC Comments,Also Provided ML18066A4921999-06-0909 June 1999 Discusses Response of 980226 Violation Re Insp Rept 50-255/97-18 Re Failure to Take Adequate Corrective Action. Ltr Contains New Commitments & No Rev ML18068A6011999-06-0808 June 1999 Forwards Description of Recent Changes Made to Palisades Site Emergency Plan,Excluding Minor & Editorial Changes Not Requiring Further Explanation ML18066A4851999-06-0404 June 1999 Forwards Insp Rept 50-255/99-04 on 990410-0521.No Violations Noted.Radiation Dose Received During Outage Was Significantly Less than Projected Because of Radiological Personnel Efforts to Create Heightened Awareness ML18066A4881999-06-0404 June 1999 Provides Responses to NRC Questions & Associated Editorial Revs for ITS LCOs 3.6.1,3.6.2,3.6.4,3.6.5 & 3.6.7 of 980126 Submittal.Responses to Comments on Remaining Section 3.6 LCOs Will Be Submitted Separately ML18066A4811999-06-0303 June 1999 Forwards Insp Rept 50-255/99-06 on 990506-12.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML18066A4731999-05-24024 May 1999 Informs That Region III Received Fema,Region V Ltr Transmitting FEMA Final Exercise Rept for 981201 Plume Exposure Pathway Exercise.No Deficiencies Identified, However,Seven Areas Requiring Corrective Actions Identified ML18066A4801999-05-24024 May 1999 Forwards Copy of Rev to NPDES Permit Number MI0001457 Renewal Application as Submitted to Mi Dept of Environ Quality on 990513 ML18066A4681999-05-19019 May 1999 Forwards Insp Rept 50-255/99-05 on 990503-06.Determined That Violation Occurred & Being Treated as Non-Cited Violation. Insp Focused on Whether Activities Associated with GL 96-05 Were Sufficient to Ensure Continued Capability of MOVs ML18066A4721999-05-18018 May 1999 Informs That During Period from 981101-990430,there Were No NPDES Permit Violations & No Repts of Oil,Salt or Polluting Matl Losses Were Made to Govt Agencies ML18066A4651999-05-17017 May 1999 Forwards ISI Program Relief Request 14 for NRC Approval in Accordance with 10CFR50.55(a)(3) as Requirement for Which Proposed Alternative Provide Acceptable Level of Quality & Safety.Rev 0 to SIR-99-032 Rept Also Encl 1999-09-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML18066A6841999-10-13013 October 1999 Forwards Insp Rept 50-255/99-10 on 990812-0921.One Violation Noted Re Adherence to Radiological Protection Procedure Requirements.Violation Being Treated as Ncv,Consistent with App C of Enforcement Policy ML18066A6781999-10-0707 October 1999 Summarizes 991005 Meeting at Region III to Discuss Radiation Protection Program at Palisades.Topics Discussed Included Management Changes in Radiation Protection Program & Actions Taken to Correct Deficiencies Identified During 1998 Outage ML18066A6651999-10-0505 October 1999 Informs of Completion of Review of Palisades Plant 25-year Tendon Surveillance Rept & Associated post-surveillance Regression Analysis Submitted by Ltrs Dtd 971218,980223 & 980925.Forwards SE Supporting Performance of Surveillance ML18066A6721999-10-0404 October 1999 Forwards Operator Licensing Exam Rept 50-255/99-301(OL) for Initial Operator Licensing Exams at Palisades NPP Completed on 990614.Two RO Applicants & Two SRO Applicants Failed One or More Portions of Respective Exams & Were Denied Licenses ML18066A6691999-09-30030 September 1999 Advises of Plans for Future Insp Activities at Facility for Opportunity to Prepare for Insps & to Provide Feedback on Any Planned Insps Which May Conflict with Plant Activities ML18066A6561999-09-28028 September 1999 Discusses Closeout of GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps. Understands That Util Will Address Concerns Raised by Insp Team at Future Date ML18066A6531999-09-23023 September 1999 Forwards Insp Rept 50-255/99-14 on 990831-0901.No Violations Noted.Insp Results Indicated with Crsd on-line (Non Outage) Planning & Scheduling Program Provided Effective Coordination & Established Appropriate Radiological Control ML18066A6441999-09-15015 September 1999 Informs That as Result of 980908 Response to RAI Re GL 92-01,Rev 1,Suppl,staff Revised Info in Rvid & Released Info as Rvid Version 2 ML18066A6431999-09-0808 September 1999 Informs That NRC Tentatively Scheduled Initial Licensing Exam for Operator License Applicants During Wk of 000522,in Response to Nl Haskell ML18066A6381999-09-0808 September 1999 Forwards Request for Addl Info Re ISI Program Relief Request 14 for Palisades Plant ML18066A6391999-09-0303 September 1999 Forwards Insp Rept 50-255/99-09 on 990522-0811.No Violations or Deviations Noted ML18066A6231999-08-26026 August 1999 Forwards SE Related to ISI Program Request for Relief ML18066A6091999-08-19019 August 1999 Provides Licensee with Individual Exam Results for Licensee Applicants Who Took June 1999 Initial License Exam.Without Encls ML18066A6031999-08-0909 August 1999 Forwards SE Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Movs, for Plant ML20210G8351999-07-29029 July 1999 Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR ML18066A5801999-07-26026 July 1999 Discusses Evaluation of Relief Requests for ISI Re ASME Section Xi,Subsections IWE & Iwl.Staff Partially Denied Relief Request 1 on Basis That General Visual Exam in Lieu of VT-3 Exam.Relief Requests 4 & 6 Denied as Listed ML17191B4031999-07-23023 July 1999 Informs That NRC Plans to Administer GFE Section of Written Operator Licensing Exam on 991006.Ltr Should Be Submitted to Appropriate Regional Administrator at Listed Address to Register Personnel to Take GFE ML18066A5481999-07-13013 July 1999 Forwards Draft SE Re Proposed Conversion to Its.Se Based on Review of Consumers Energy Co 980126 Application & as Supplemented by 980430,0914,1012,1109,990301,22,30,0407, 0503,0604,11 & 17 Ltrs ML18066A5381999-07-0808 July 1999 Forwards Insp Rept 50-255/99-08 on 990522-0630.No Violations Noted.Determined That Emergent Repairs to EDG Were Completed in Timely & Skillful Manner to Prevent Challenge to Plant Operation ML18066A5361999-07-0606 July 1999 Discusses 990629 Meeting with PRA Staff Re Initiatives in Risk Area & to Be Establish Dialog Between SRAs & PSAs Staff ML20209B2081999-06-29029 June 1999 Discusses Closure of Response to RAI Re GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rvid,Version 2 Issued as Result of Review of Responses.Info Should Be Reviewed & Comments Submitted by 990901 ML18066A4851999-06-0404 June 1999 Forwards Insp Rept 50-255/99-04 on 990410-0521.No Violations Noted.Radiation Dose Received During Outage Was Significantly Less than Projected Because of Radiological Personnel Efforts to Create Heightened Awareness ML18066A4811999-06-0303 June 1999 Forwards Insp Rept 50-255/99-06 on 990506-12.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML18066A4731999-05-24024 May 1999 Informs That Region III Received Fema,Region V Ltr Transmitting FEMA Final Exercise Rept for 981201 Plume Exposure Pathway Exercise.No Deficiencies Identified, However,Seven Areas Requiring Corrective Actions Identified ML18066A4681999-05-19019 May 1999 Forwards Insp Rept 50-255/99-05 on 990503-06.Determined That Violation Occurred & Being Treated as Non-Cited Violation. Insp Focused on Whether Activities Associated with GL 96-05 Were Sufficient to Ensure Continued Capability of MOVs ML18068A5951999-05-13013 May 1999 Informs That NRC Ofc of NRR Reorganized,Effective 990328. Forwards Organization Chart ML18068A5771999-04-23023 April 1999 Forwards Insp Rept 50-255/99-03 on 990226-0409.No Violations Noted.However,Weaknesses in Cold Weather Preparations Identified by Inspectors ML18066A4591999-04-21021 April 1999 Informs That,Based on Determinations That Changes in Rev 15 Do Not Decrease Effectiveness of Plant EP & That Plan Continues to Meet Stds of 10CFR50.47(b) & Requirements of App E to Part 50,NRC Approval Not Required ML18066A4491999-04-0808 April 1999 Informs That Meeting to Discuss Results of Plant Performance Review Process Scheduled for 990428 ML18066A4511999-04-0707 April 1999 Discusses 990401 Telcon Re Palisades Improved TSs Review Schedule.Encl Table Provides Agreed Upon Milestone Dates for Completion of Review & Reflects Proposed Amend Request Date of 990830 ML18066A4461999-03-26026 March 1999 Advises of Planned Insp Effort Resulting from Palisades PPR Review,Which Was Completed on 990203.Overall Performance at Palisades Was Acceptable IR 05000255/19980221999-03-22022 March 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-255/98-22 Issued on 990210.Corrective Actions Will Be Examined During Future Insps ML18068A5431999-03-17017 March 1999 Forwards RAI Re Licensee 980126 Request to Convert Palisades Nuclear Plant Current TSs to Improved Tss.Response Requested by 990430 ML18068A5381999-03-0505 March 1999 Forwards Insp Rept 50-255/99-01 on 990112-0225.No Violations Noted ML18066A4071999-02-10010 February 1999 Forwards Insp Rept 50-255/98-22 on 981126-990112 & Nov. Violation Identified Re Failure to Submit Engineering Analysis Pertaining to Degraded Studs on Primary Coolant Pump ML18066A4111999-02-10010 February 1999 Ack Receipt of ,Which Transmitted Changes Identified as Rev 42 to Plant Security Plan Submitted Under Provisions of 10CFR50.54(p).No NRC Approval Required IAW 10CFR50.54 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML18066A4061999-02-10010 February 1999 Informs That Requested Response Was Provided by Licensee on 980707 & That According to Nudocs,Document Should Be Available in Pdr.Informs That Staff Issued Evaluation of Licensee Response to USI A-46 by Ltr ML18068A5221999-02-10010 February 1999 Confirms 990208 Telcon Between R Bailey & R Frigo Re Arrangements Made for Administration of Licensing Exams at Palisades Facility Weeks of 990607 & 0614.NRC Will Make Exam Validation Visit to Facility Week of 990524 ML18066A3991999-02-0505 February 1999 Forwards Insp Rept 50-255/99-02 on 990119-22 & Notice of Violation.Violation Involved Failure to Mark Two Security Procedures That Contained Protected Info (Safeguards Info) & to Properly Store Some Copies of One of Those Procedures ML17191B2221999-02-0202 February 1999 Informs That NRC Plans to Administer Gfes of Operator Licensng Exam on 990407.Authorized Facility Representative Must Submit Ltr to Appropriate Regional Administrator Identifying Individuals Taking Exam ML18066A3841999-01-29029 January 1999 Forwards Request for Addl Info Re TS Change Request to Convert to Improved TS for Plant.Mutually Agreeable Completion Date of 990331 Established ML18066A3851999-01-28028 January 1999 Forwards SE Accepting Licensee 981220 Request for Staff to Authorize Consumers Energy Proposed Alternative to Requirements of ASME Section XI Article IWA-5250 for Degraded P-50A Primary Coolant Pump Casing Bolts at Plant ML18066A3711999-01-12012 January 1999 Refers to Consumers Energy 981215 Response to 980731 RAI Re Proposed Fluence Calculation Methodology.Confirms Understanding That Based on Discussions at 981207 Meeting, Licensee Does Not Expect Further Review of Methodology ML18066A3601998-12-29029 December 1998 Forwards Emergency Preparedness Exercise Insp Rept 50-255/98-21 on 981130-1204.No Violations Noted.Objective of Insp to Determine Whether Palisades Emergency Plan Adequate ML18066A3571998-12-28028 December 1998 Forwards SE Authorizing Licensee 980313 Request to Use ASME OMa-1996,Subsection Istd, Preservice & Inservice Exam & Testing of Dynamic Restraints in Light Water Reactors, as Alternative to Requirements of ASME OMa-1988 Part 4 ML18066A3501998-12-15015 December 1998 Informs That as Part of PRA Implementation Plan, Commission Assigned Two SRAs to Each Regional Ofc.Sras Will Routinely Assess Licensee Event Repts,Plant Events,Insp Findings & EAs from Risk Perspective ML18066A3471998-12-14014 December 1998 Forwards Insp Rept 50-255/98-19 on 981008-1125.No Violations Noted.Noted That Weakness in Equipment Status Control Contributed to Incident That Inadvertently Drained Hydrazine Addition Tank to Turbine Building Sump ML18066A3431998-12-0404 December 1998 Forwards Request for Addl Info Re TSs Change Request to Convert to Improved TSs for Palisades Plant.Addl Info Needed in Sections 2.0,3.1 & 3.2.Response Requested 60 Days from Date Ltr Was Established ML18066A3461998-12-0202 December 1998 Advises of Planned Insp Effort for Next 6 Months at Plant. Info Provided to Minimize Resource Impact on Staff & to Allow for Scheduling Conflicts & Personnel Availability to Be Resolved in Advance of Inspector Arrival Onsite 1999-09-08
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Text
Mr. Nathan L. Haskell Director, Licensing Palisades Plant -
27780 Blue Star Memorial Highway Covert, Ml 49043 March 17, i9
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING THE TECHNICAL SPECIFICATIONS CHANGE REQUEST TO CONVERT TO THE IMPROVED TECHNICAL SPECIFICATIONS FOR THE PALISADES PLANT (TAC NO.
MA0805)
Dear Mr. Haskell:
On January 26, 1998, Consumers Energy submitted its request to convert the Palisades Nuclear Plant current technical specifications (CTS) to improved technical specifications (ITS).
Additional information, as discussed in the enclosure, is requested in order to complete our evaluation of ITS Section 3.5. The staff requests that you provide your response using the enclosed comment format, adding your responses where indicated in the enclosure.
The enclosed request was discussed with Mr. B. Young of your staff on March 15, 1999. A mutually agreeable completion date for your response of April 30, 1999, was established. If circumstances result in the need to revise this schedule, please call me at the earliest opportunity.
Should you have any questions regarding this request, please do not hesitate to contact me at (301) 415-1312 or Mary Lynn Reardon of the Technical Specifications Branch at (301) 415-1177.
Docket No. 50-255
Enclosure:
As stated cc w/encl: See next page Distribution {w/encl):
ACRS Sincerely, ORIGINAL SIGNED BY Robert G. Schaaf, Project Manager Project Directorate 111-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation A. Vegel, Rill OGC m~
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Mr. Nathan L. Haskell Consumers Energy Company cc:
Mr. Thomas J. Palmisano Site Vice President Palisades Plant 27780 Blue Star Memorial Highway Covert, Michigan 49043 Mr. Robert A. Fenech, Sr Vice Pres Nuclear, Fossil, and Hydro Operations Consumers Energy Company 212 West Michigan Avenue Jackson, Michigan 49201 Arunas T. Udrys, Esquire Consumers Energy Company 212 West Michigan Avenue Jackson, Michigan 49201 Regional Administrator, Region Ill U.S. Nudear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Jerry Sarno, Supervisor Covert Township P. 0. Box35 Covert, Michigan 49043 Office of the Governor P. 0. Box 30013 Lansing, Michigan 48909 U.S. Nuclear Regulatory Commission Resident Inspector's Office Palisades Plant 27782 Blue Star Memorial Highway Covert, Michigan 49043 Palisades Plant Drinking Water and Radiological Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P. 0. Box 30630 CPH Mailroom Lansing, Michigan 48909-8130 Michigan Department of Attorney General Special Litigation Division 630 Law Building P.O. Box 30212 Lansing, Michigan 48909 August 1998
3.5, ECCS-Generic Palisades Plant Improved TS Review Comments Section 3.5, Emergency Core Cooling Systems 3.5.G-1 CTS 3.3.1, 4.6.3.a, & 4.6.4.a DOCs 3.5.1-LA.1 & LA.2, 3.5.2-LA.1 & LA.2 Comment: Generally, requirements moved to licensee-controlled documents should be moved to documents that are covered by some type of regulatory control such as 1 O CFR 50.59, 1 O CFR 50.54a, or the ITS Bases Control Program. The DOCs noted above state that the subject requirements are being moved to plant procedures. The staff considers CTS requirements moved to plant procedures to be essentially deleted requirements since there is no longer a regulatory control mechanism associated with the requirements. Therefore, please review the subject changes and move the requirements to licensee-controlled documents covered by some type of regulatory control or reclassify the changes as less restrictive changes describing deletion of CTS requirements.
Consumers Energy Response:
3.5.1, Safety Injections Tanks (SITs) 3.5.1.;1 CTS 3.3.1 ITS 3.5.1 Applicability and Required Actions C.1 and C.2 DOC A.2, L.1 and JFD #5 CTS 3.3.1 states that "The reactor shall not be made critical... unless all of the following conditions are met:" Item b is applicable for the Safety Injection Tanks. ITS 3.5.1 Applicability is proposed to be Mode 1 and 2. STS 3.5.1 Applicability is Mode 1 and 2, and Mode 3 with RCS pressure greater than 700 psia.
Comment: JFD #5 explains that the SITs are pressurized to greater than 200 psig and filled using the HPSI pumps and injection lines and that attempting to fill the SITs with PCS pressure below the HPSI shutoff head would result in flow opening the loop check valves and entering the PCS. The JFD also explains how the parameters of the SITs are currently verified within limits after plant heatup and before the approach to criticality.
The Applicability of SITs should be based upon when they are needed to mitigate the assumed accident when the PCS is at elevated temperatures and pressures. Therefore, shouldn't SITs have a similar Applicability to the ECCS trains in ITS 3.5.2 which begins in Mode 3 after PCS reaches 325°F or an Applicability based on when PCS pressure exceeds the SIT cover pressure of 200 psig? The resolution of the Applicability issue may require the addition of Required Action C.2 to "Reduce PCS temperature to < 325°P' or "Reduce PCS pressure. to <
200 psig"with a technically justified Completion Time.
Consumers Energy Response:
ENCLOSURE
3.5.1-2 Palisades Plant Improved TS Review Comments Section 3.5, Emergency Core Cooling Systems CTS 3.3.2, *cTS 3.3.2 e and f ITS 3.5.1 Action A, B, C, and D DOC A.5 CTS 3.3.2 states that "During power operation the requirements of (CTS) 3.3.1 may be modified to allow one of the following conditions to be true at any one time". ITS 3.5.1 has converted these requirements into the improved STS format.
Comment: DOC A.5 appears to be composed of several change issues and should be re-written to separate these issues. Issue #1 - DOC A.5 appears to apply to Action B for justification of the one hour Completion Time. The one hour is retained which is acceptable and it is an administrative change as explained in the 7th through 10th sentences. The 11th sentence discusses a relaxation of the Completion Time to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> which is not identified in the ITS, nor is it discussed in DOC L.1, as noted in this DOC A.5. The 11th sentence appears to be extraneous and should be deleted. Issue #2 - The fifth and sixth sentences explain how the reformatting of these CTS requirements have resulted in a "generic... less restrictive technical change for several ITS 3.5 LCOs. The concurrent inoperability permitted by separate ITS LCOs would invoke a CTS LCO 3.0.3 plant shutdown under the CTS 3.3.2 requirements.
This is a less restrictive change which should be separately identified. Issue #3 - CTS 3.3.2 e and f have been removed per the CTS markup as only applicable for ITS 3.5.2. It appears that these two CTS requirements would still be applicable to the SITs under ITS 3.5.1. Provide a new DOC for these CTS requirements to explain how they are converted into the ITS 3.5.1 requirements.
Consumers Energy Response:
3.5.1-3 CTS 4.2, Table 4.2.2, Item #10 ITS SR 3.5.1.3 DOC LA.3 and JFD #7 CTS Table 4.2.2 Item #10 verifies the pressure in the SIT is between a high-high and a low pressure alarm setpoint. ITS SR 3.5.1.3 only verifies the pressure is above a minimum limit; whereas, STS SR 3.5.1.3 also defines an upper pressure limit.
Comment: DOC LA.3 states that neither the CTS (3.3.1 b) nor the ITS specify a high pressure limit for the SITs since a maximum pressure is not an assumption in the safety analysis.
However, the staff believes that, as evidenced by CTS Table 4.2.2 Item #10, the high pressure limit is an operability requirement for the SITs under the CTS. As the STS Bases state, the maximum nitrogen cover pressure limit ensures that excessive gas will not be injected into the RCS after the SITs have emptied. Please revise the submittal to retain the high pressure limit in conformance with the STS and the CTS.
Consumers Energy Response:
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Palisades Plant Improved TS Review Comments Section 3.5, Emergency Core Cooling Systems 3.5.1-4 CTS 4.6.4.a ITS SR 3.5. 1..5 JFD#6 CTS 4.6.4.a verifies each SIT flow path is Operable by verifying each motor-operated isolation valve is open and locking open the circuit breakers. ITS SR 3.5.1.5 verifies power is removed from each SIT isolation valve operator.
Comment: STS SR 3.5.1.5 only requires this verification whenever the pressurizer pressure is greater than 2000 psia". Per JFD #6, this phrase was not retained in ITS SR 3.5.1.5 because of the change to the Applicability. When the ITS 3.5.1 LCO Applicability is resolved (See Comment #3.5.1-1), this ITS SR may also need to be revised for consistency.
Consumers Energy Response:
3.5.2, ECCS - Operating 3.5.2-1 CTS 3.3.2.b, C, d, and f ITS 3.5.2 Action A DOC L.2 CTS 3.3.2.b, c, d, and fall require the separately listed LPSI, HPSI, shutdown cooling heat exchanger and all valves associated with the safety injection and shutdown cooling system to be restored Operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. ITS 3.5.2 Action A permits 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for any component
. that renders an ECCS train inoperable providing that 100% equivalent flow is still available from a single train.
Comment: Issue #1 - DOC L.2 as written only applies to CTS 3.3.2.c; whereas; the CTS markup indicates it is also applicable for CTS 3.3~2.b, d, and f. Revise this DOC to apply to all CTS changes. Issue #2 - The CTS 3.3.2.b and c markup states a second part to Condition B is added when this is not found in the ITS. Is this is an error and should the reference be to Condition A instead?
Consumers Energy Response:
3.5.2-2 CTS 3.3.1.e ITS 3.5.2 Action A DOC LA.1 CTS 3.3.1.e requires Operability of the shutdown cooling heat exchanger and all valves associated with the shutdown cooling system. ITS 3.5.2 simply requires that two ECCS trains be operable.
Comment: DOC LA.1 also applies to CTS 3.3.1.c, d, f, and g, and 3.3.4, which is acceptable.
However, CTS 3.3.1.e requirements are not discussed in the Bases as stated in DOC LA.1.
The inoperability of the shutdown cooling heat exchanger directly affects the ECCS train capability on recirculation flow. Bases insert to page B 3.5-10 and the LCO discussion do not 3
Palisades Plant Improved TS Review Comments Section 3.5, Emergency Core Cooling Systems provide complete description of the components in the ECCS trains that must be maintained Operable. Revise the ITS Bases accordingly to ensure these components are covered in ITS 3.5.2 and there is agreement with the CTS requirements relocated per DOC LA.1.
Consumers Energy Response:
3.5.2-3 CTS 3.3.2 ITS 3.5.2 Required Action B.2 DOC L.1 and JFD #15 CTS 3.3.2 allows an ECCS component to be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and then requires the reactor placed in a Cold Shutdown condition within an additional 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> (84 total) if the component cannot be restored. ITS Action A permits 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for restoring an inoperable ECCS train and an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (96 total) for placing the reactor in Mode 3 with PCS ~
325°F.
Comment: As discussed in JFD #15, a change to the Completion Time of Required Action B.2 may be appropriate to reach a lower operating temperature in Mode 3. However, no technical justification has been provided for the 24-hour Completion Time proposed for ITS 3.5.2, Required Action B.2. How does this Completion Time relate to similar Actions in other specifications requiring the plant to be placed in a similar operating condition? Please provide a justification for the 24-hour Completion Time for Required Action B.2.
Consumers Energy Response:
3.5.3, ECCS - Shutdown 3.5.3-1 No CTS ITS 3.5.3 DOC M.1; JFD #6 & #7 The CTS does not contain any ECCS requirements when the reactor is not critical. ITS 3.~.3 requires one LPSI train to be Operable in Mode 3 when PCS is < 325°F and in Mode 4; whereas, STS 3.5.3 requires one HPSI train Operable during Mode 3 when pressurizer pressure is < 1700 psia and in Mode 4.
Comment: Issue #1 - This change in not consistent with either the CTS or the STS and is beyond the scope of the conversion review, and, therefore, will require additional review by the NRC technical staff. STS 3.5.3 requires at least one HPSI train operable during shutdown operations. To the contrary, ITS 3.5.3 requires that one LPSI train is required operable. JFD
- 6 states that this reflects the Palisades design. Is this difference solely due to L TOP? If so, why isn't this explained in the Applicable Safety Analysis? The Applicable Safety Analysis Bases developed for ITS 3.5.3 directly state that the Bases for ITS 3.5.2 are applicable which still references analyses that credit only the HPSI pumps for the various sizes of LOCA breaks.
There is no discussion or explanation regarding this difference from the STS. There is no discussion or explanation in the ITS 3.5.3 Bases for Applicable Safety Analyses pertaining to why one sole LPSI train is acceptable for the Palisades design. ITS 3.5.2 Bases for Applicable 4
Palisades Plant Improved TS Review Comments Section 3.5, Emergency Core Cooling Systems Safety Analyses, paragraph 5, states that for all LOCA analyses, injection flow is not credited until PCS pressure drops below the shutoff head of the HPSI pumps. How do these analyses apply or how are they bounding for ITS 3.5.3 that now relies on only the LPSI pumps? Revise the DOC and JFD, and ITS Bases to further explain and provide technical justification for changes to reflect the Palisades design.
Consumers Energy Response:
3.5.3-2 CTS 3.3.1 ITS SR 3.5.3.1 JFD#9 CTS 3.3.1 provides no specific requirements for determining the Operability of the ECCS system components during the shutdown modes of Operation. ITS SR 3.5.3.1 provides direct reference to those surveillances from ITS 3.5.2 that are applicable to the Operability requirements of ITS 3.5.3.
Comment: Based upon the information contained in the Bases for ITS 3.5.2 and ITS 3.5.3, the STS SRs 3.5.2.1, 3.5.2.3, 3.5.2.6, 3.5.2.7, and 3.5.2.9 are still applicable to ITS 3.5.3 as follows: (1) The ESF Pump Mini Flow valves (CV-3027 and CV-3056) preclude damage to all ECCS pumps (as stated in Bases inserts 1, 2, and 3 on page B 3.5-16) and not just to the HPSI. Therefore, the position of these valves should be verified per SR 3.5.2.1. (2) The ECCS pumps and valves are automatically actuated per the design which does cease to exist, even though the slower evolution of the design basis event in these Modes happens a rate that permits a manual response. The design has not changed; therefore, STS SRs 3.5.2.6 and 3.5.2.7 should apply, as indicated in the STS. (3) Similar to the previous item, the LPSI flowpaths should be verified as Operable with the stops in the correct position. In addition for both items (2) and (3), in order to enter normal power operation mode for ITS 3.5.2, SR 3.0.4 requires that these SRs must be met prior to entry into the Modes of Applicability; so, it will be necessary to fulfill these SR requirements during the Applicability of ITS 3.5.3 to ensure the safety function is met prior to entering the Applicability of ITS 3.5.2. The staff requests that you revise the ITS to adopt these STS SR requirements.
Consumers Energy Response:
3.5.4, Safety Injection Refueling Water Tank (SIRW!)
No comments.
3.5.5, Trisodium Phosphate (TSP)
No comments.
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