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| The ORNL detailed review is a worthy study up to and including the year 1979 and represents an "external" appraisal. More emphasis needs to be given on implementation of corrective actions. | | The ORNL detailed review is a worthy study up to and including the year 1979 and represents an "external" appraisal. More emphasis needs to be given on implementation of corrective actions. |
| The summary of Escalated Enforcement Actions presents significant events through March 1981. I suggest including more "internal" reviews, including the Region III "Systematic Assessment of Licensee Performance" (SALP), and the periodic Inspection Reports by the resident inspector(s) and by the special teams. The updating might include the Licensee's Annual Report of Changes, Tests and Experiments. | | The summary of Escalated Enforcement Actions presents significant events through March 1981. I suggest including more "internal" reviews, including the Region III "Systematic Assessment of Licensee Performance" (SALP), and the periodic Inspection Reports by the resident inspector(s) and by the special teams. The updating might include the Licensee's Annual Report of Changes, Tests and Experiments. |
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| Action Plan Items, and other generic matters are to be included. The draft SEP report indicates that a supplement is to be issued which will designate the status of the USis and TMI Action Plan Items. I consider this supplement to be a *key factor in balancing overall decisions to be made on the SEP items. The magnitude of this task should not be underestimated~ | | Action Plan Items, and other generic matters are to be included. The draft SEP report indicates that a supplement is to be issued which will designate the status of the USis and TMI Action Plan Items. I consider this supplement to be a *key factor in balancing overall decisions to be made on the SEP items. The magnitude of this task should not be underestimated~ |
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| Rather than just "or", don't you mean either or both? Further, wouldn't you need to comment4 that the failure(s)' in themselves, do not produce any undue flooding ef.fects? | | Rather than just "or", don't you mean either or both? Further, wouldn't you need to comment4 that the failure(s)' in themselves, do not produce any undue flooding ef.fects? |
| This is one of the few items where the TMI Action Plan, Item I.C.l, "Guidance for the *Evaluation and Development of Procedures for Transients and Accidents," is mentioned. This. SEP topic is a part of a much broader and more complete task, with priority on Licensee's resources t6 be given to the TMI Item. | | This is one of the few items where the TMI Action Plan, Item I.C.l, "Guidance for the *Evaluation and Development of Procedures for Transients and Accidents," is mentioned. This. SEP topic is a part of a much broader and more complete task, with priority on Licensee's resources t6 be given to the TMI Item. |
| 4.10 Topic III-6 Seis"tTtic Design Considerations | | 4.10 Topic III-6 Seis"tTtic Design Considerations Once again, for an " ... integrated and balanced ..* " approach, SEP concerns need to be factored into the broader a~eas being addressed through responses to IE Bulletins. |
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| Once again, for an " ... integrated and balanced ..* " approach, SEP concerns need to be factored into the broader a~eas being addressed through responses to IE Bulletins. | |
| 4.15 Topic V-5 Reactor Coolant Pressure Boundary (RCPB) Leakage Detection | | 4.15 Topic V-5 Reactor Coolant Pressure Boundary (RCPB) Leakage Detection |
| *The rationale used by the Staff in arriving at conclusions fits the objective set forth for SEP. Is there any impact on radiation exposure to workers? | | *The rationale used by the Staff in arriving at conclusions fits the objective set forth for SEP. Is there any impact on radiation exposure to workers? |
Submits Draft Review of Integrated Plant Safety Assessment of Sep.Review of Operating Experiences Needs to Be Updated & AugmentedML18047A329 |
Person / Time |
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Site: |
Palisades |
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Issue date: |
04/23/1982 |
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From: |
Isbin H ISBIN, H. |
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To: |
Russell W NRC |
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Shared Package |
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ML18047A285 |
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References |
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RTR-NUREG-0820, RTR-NUREG-820 NUDOCS 8205190072 |
Download: ML18047A329 (8) |
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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 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. 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. 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 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 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 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 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. 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 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 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 IR 05000255/19970181999-06-0909 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 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 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 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 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 ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function 1999-09-30
[Table view] Category:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20237B8051987-11-25025 November 1987 FOIA Request That Encls to Listed Documents,Including NRC Forwarding Amend 1 to License NPF-73,be Placed in PDR ML20238E3011987-06-29029 June 1987 FOIA Request for All Documents Described in App,Including Listed LERs & Revs for Plants,W/Original Attachments & Encls ML18052B1911987-06-17017 June 1987 Forwards EGG-NTA-7720, Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28,Reactor Trip Sys Vendor Interface:Calvert Cliffs-1 & -2,Millstone-2 & Palisades, Final Informal Rept. Plants Conform to Generic Ltr Item ML18052B1531987-05-0101 May 1987 Forwards Final EGG-NTA-7622, Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components:Palisades, Informal Rept ML18052B0521987-04-17017 April 1987 Forwards EGG-NTA-7439, Conformance to Generic Ltr 83-28, Item 2.2.1 -- Equipment Classification for All Other Safety- Related Components:Palisades, Final Rept.Facility Conforms to Generic Ltr on Item ML18052B0491987-03-30030 March 1987 Forwards EGG-NTA-7484, Technical Evaluation Rept for Palisades Plant,Response to NRR Generic Ltr 83-37, Interim Rept.Licensee Not in Compliance W/Control Room Habitability Requirement (III.D.3.4).Items Still Under Review Listed ML20209F8601987-01-15015 January 1987 Requests Publicly Available Copies of Handouts or Viewgraphs Used at Region III Meeting 05000255/LER-1950-255, FOIA Request for 851118 LER 50-255/85-23 on Possible Low Temp Overpressure Sys Setpoint Error to Be Placed in PDR1986-02-26026 February 1986 FOIA Request for 851118 LER 50-255/85-23 on Possible Low Temp Overpressure Sys Setpoint Error to Be Placed in PDR ML20078A1601983-06-0101 June 1983 FOIA Request for 821021 Document Re Palisades 820204 Cooling Tower Pump Trip & 821117 Document Re San Onofre 2 Auxiliary Feedwater Pump Vent Failure ML18047A6851982-12-0909 December 1982 Forwards, Sep,High Energy Line Breaks Inside Containment, Palisades Nuclear Station,Phase IV Summary of Results, Revision 0. Rept Incorporates Results of Fracture Mechanics Analysis ML17309A2771982-06-28028 June 1982 Repts Under Purchase Order DR-82-0961 Re Review of Two Draft SEP Integrated Assessments for Facilities.Ltr Comprises Rept on Ginna SEP (Draft NUREG-0821) ML18047A3291982-04-23023 April 1982 Submits Draft Review of Integrated Plant Safety Assessment of Sep.Review of Operating Experiences Needs to Be Updated & Augmented ML18047A2841982-04-15015 April 1982 Submits Review of Draft NUREG-0820, Integrated Plant Safety Assessment:Sep,Palisades Plant. Addl Matl May Be Provided at Later Date ML19343C1641980-11-0909 November 1980 Responds to ACRS 800918 Request for Comment on B Cohen Concerns Re Refueling Water Storage Tank Adequacy.Decay Heat Removal Alternatives Recommended ML18045A4521980-07-28028 July 1980 Forwards Draft of SEP Review of NRC Safety Topic VI-7.B Associated W/Electrical,Instrumentation & Control Portion of Engineered Safety Feature Switchover from Injection to Recirculation Mode for Palisades Nuclear Power Plant. ML18045A4511980-07-28028 July 1980 Forwards Rough Draft Rept Detailing NRC Safety Topic VII-2, Engineered Safety Feature Sys Control Logic & Design. Requests Comments & Recommendations ML18045A4501980-07-28028 July 1980 Forwards Draft Rept on Plant Detailing NRC Safety Topic III-1 Re Classifications of Structrues,Components & Sys ML20084U7531972-11-0808 November 1972 Comments on Requesting Addl Info on Main Steam Safety Valves.Angle of Discharge,Stress Analysis,Dynamic Load Factor & Header Stress Discussed ML20084U5051972-11-0808 November 1972 Comments on 721031 Response to Questions Re Main Steam Safety Valves.Response by Util Not Acceptable 1987-06-29
[Table view] Category:INCOMING CORRESPONDENCE
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 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. 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. 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 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 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 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 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 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. 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 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 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 IR 05000255/19970181999-06-0909 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 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 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 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 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 ML18066A4611999-05-14014 May 1999 Requests Approval to Use Alternative Requirements IAW 10CFR50.55a(a)(3)(i),proposing to Follow Requirements of ASME Boiler & Pressure Vessel Code Case N-566-1.IST Program Relief Request 6 for NRC Approval Encl ML18068A5831999-05-0303 May 1999 Forwards Proposed TS Section 3.5,in Response to NRC 990317 RAI Re Util 980126 TS Change Request Re Conversion to Improved Ts,Per NUREG-1432 ML20206J2411999-04-30030 April 1999 Submits Corrected Copy of Ltr Forwarding 1998 Consumers Energy Co Annual Rept. Ltr Contains Corrected Docket & License Number for Big Rock Point.With One Oversize Encl ML20217A8191999-04-29029 April 1999 Forwards Listed Matls Related to Palisades Plant June 1999 Initial License Exam ML20206E8271999-04-28028 April 1999 Forwards Palisades Plant Annual Radiological Environ Operating Rept for 1998. There Were No Reportable Events During This Period ML20207B4661999-04-23023 April 1999 Forwards Copy of Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981201 for Palisades Npp.No Deficiencies Noted.Seven New Arcas Identified ML18066A4531999-04-0707 April 1999 Forwards ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1,as Requested by NRC 990406 Telcon,Per TS Change Request Submitted 980126.Change Submitted Does Not Alter Conclusions of No Signficant Hazards Considerations ML18066A4481999-04-0202 April 1999 Responds to Violations Noted in Insp Rept 50-255/98-06. Corrective Actions:Nuclear Performance Assessment Dept Has Reviewed Observations & Agrees That Field Observations by Qualified Personnel Are Important Aspect of Program ML18066A4471999-03-30030 March 1999 Confirms Completion of Util Review of Design Engineering Contractor Cable Ampacity Evaluation.Evaluation Available at Plant for NRC Review ML18066A4411999-03-30030 March 1999 Forwards Response to NRC 990126 RAI Re TS Section 3.7 of Util 980126 LAR Request for Conversion to Its.Licensee Received Permission to Delay TS Section 3.6 Response to Allow for Addl Time for Preparation & Internal Review ML18066A4441999-03-26026 March 1999 Submits Certification of Financial Assurance for Decommissioning of Palisades Nuclear Plant.Certified Rept of Status of Consumers Energy Co Decommissioning Funding & Trust Agreement Encl as Attachments 1 & 2 ML18066A4401999-03-25025 March 1999 Forwards Revised Best Estimate Fluence Evaluation Using Industry Data, Providing Justification for Using Industry Data to Determine Best Estimate Fluence.Review of Info & SE Requested ML18066A4191999-03-23023 March 1999 Forwards 1998 Annual Radioactive Effluent Release & Disposal Rept, for Palisades Plant,Providing Summary of Quantities of Radioactive Liquid & Gaseous Effluent Releases & Solid Radioactive Waste Processed During 1998 ML18066A4231999-03-22022 March 1999 Forwards Answers to 990311 Telcon Request for Addl Clarification & Revs Re ITS Section 3.4.Markups of Previously Submitted TS Pages & Revised Pages for Section 3.4 Also Encl ML20204F2091999-03-18018 March 1999 Requests That Listed TS Change Requests (Tscrs) Be Issued with Allowance That Tscrs Be Fully Implemented within Sixty Days of Issuance.Request Will Allow Time for Completion of Final Training & Procedure Changes Associated with Amend ML18066A4141999-03-18018 March 1999 Forwards Rev 4 to COLR, Containing Limits for Fuel Cycle 14 & Future Cycles ML18066A4121999-03-18018 March 1999 Concludes That Mod to Provide Automatic Switchover of Control Room Heating,Ventilation & Air Conditioning (CRHVAC) Sys to Emergency Mode Is Not Needed to Meet Regulatory Requirements.Mod Commitment Cancelled ML20204E5861999-03-16016 March 1999 Submits Current Limits of Property Insurance Maintained at Consumers Energy Co Operating Nuclear Power Plants ML18066A4131999-03-11011 March 1999 Responds to NRC 990210 Ltr Re Violations Noted in Insp Rept 50-255/98-22.Corrective Actions:Analytical Evaluation, EA-C-PAL-98-1067-01, P-50A Case to Cover Stud Evaluation, Was Submitted to NRC on 981220 ML18068A5241999-02-12012 February 1999 Resubmits Relief Request 12,with Addl Info That Includes Specific Locations Where Relief Request Would Be Applied,Per 10CFR50.55a(g)(5)(iii) ML18068A5211999-02-11011 February 1999 Informs NRC That Implementation of Formal Industry Position on Severe Accident Mgt at Palisades Plant Was Completed on 981217 ML18066A4051999-02-10010 February 1999 Requests Copy of Consumers Energy (Palisades) Formal Response to RAI Dtd 990512 (USI A-46) ML18066A3921999-01-29029 January 1999 Forwards Licensee Interpretation of TS Requirements for Performance of SRs as Applied to Instrumentation Channel Calibr.Ltr Established No New Commitments ML18066A3891999-01-28028 January 1999 Submits Response to Concern Expressed in Insp Rept 50-255/98-06 Re Whether Palisades ISI Program Was Being Conducted IAW Applicable Requirements 1999-09-30
[Table view] |
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HERBERT S. ISBIN 281 5 MONTEREY PKWY ..
ST. LOUIS PARK, MN SS416 (61 2) 920-6417 April 23, 1982 '
To: Project Officer W. Russell Mailstop 516 7920 Norfolk Avenue Bethesda, Maryland 20014 From: H. S. Isbin Draft Review of Integrated Plant Safety Assessment Syst~atic Evaluation Program Palisades Plant Draft NUREG-0820 Enclosed please find my draft review in response to your request to 11 * . *
- an .evaluation of the adequacy of the rationale used by the staff in identifying and making recommendations for backf*i t requirements. 11 In addition to Draft NUREG-0820, I received SECY.77-561 (October 26, 1977), SECY 76-545 (November 12, 1976), a November 15, 1977 memorandum from S. J. Chilk to L. V. Gossick, and a draft Statement of Work. I have not had the benefit of any discussions with the SEP staff nor with any reviewers. Please let me know if you desire any changes in the focus of my review.
The highlights of my review are as follows:
- The planning used for SEP is outstanding from the point of view of identifying safety items.
- The objectives have been well conceived; however one major objective may have been inadvertently omitted in the NUREG report.
- The review of operating experiences needs to be updated and augmented.
- The reporting of the Topics and the ensuing approach to the decision making, in general, are well done.
- Too many events and changes have occurred in the past three years to be able to evaluate whether the SEP program is efficiently and economically using NRC and Ind~stry resources.
- An important finding is that no SEP Topic was considered to be of sufficient importance to require a prompt resolution.
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ST. LOUIS PARK, MN 55416 (61 2) 920-6417
- Attention has been focussed on achieving an " ..* integrated and balanced ... " decision, considering that the SEP program is being
.j. carried out in conjunction with major NRG and Industry efforts for implementing TMI Action Plan Items, and responding to IEBulletins and Generic Letters. Resolution of Unresolved Safety Issues remains a continuing activity along with mandated annual reports to the Congress concerning identification of any new issues.
overall assessment of safety of the plant must utilize all these inputs.
Additional SEP supplements have been planned for the Palisades plants. The Status of the SEP Topics, presented in Appendix A, is for the date April 1977, with some having been updated to May 1981 for inclusion of *TMI tasks, USI, and severai IE Bulletins. I understand that no changes were-made in Topic definitions. Has consideration been given to updating all the SEP Topics regarding status and References?
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HERBERT S. ISBIN 2815 MONTEREY PKWY ..
ST. LOUIS PARK. MN SS416 (61 2) 920-6417 DRAFT REVIEW
'I by H. s. Isbin COMMENTS ON SECTIONS OF NUREG-0820 1.2 Systematic Evaluation Prqgram Objectives
.Only three objectives are presented. I believe that the fourth objective is essential and from the referenced material I extract "and (4) an overall evaluation of all safety topics evaluated in the SEP and other ongoing programs .*. "
I would emphasize overall, all, other ongoing programs.
I assume that the presentation of the original five SEP object~ves is to augment the present objectives. Any program that seeks " ... to make integrated and balanced decisions with respect to any required backfitting" and to
" **. efficiently us*e. available resources and minimize requirements for additional resources by NRC or industry."merits our standing ovation.
A variety of actions taken during the last three years on generic matters, including the TMI related items, have considerably altered priorities. In my review, I have chosen to focus on what elements need to be included to achieve the " *.* integrated and balanced ... " backfitting decisions.
1.4 Summary of Operating History and Experience This section is inadequate because it is not updated.
The ORNL detailed review is a worthy study up to and including the year 1979 and represents an "external" appraisal. More emphasis needs to be given on implementation of corrective actions.
The summary of Escalated Enforcement Actions presents significant events through March 1981. I suggest including more "internal" reviews, including the Region III "Systematic Assessment of Licensee Performance" (SALP), and the periodic Inspection Reports by the resident inspector(s) and by the special teams. The updating might include the Licensee's Annual Report of Changes, Tests and Experiments.
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HERBERT S. ISBIN 2815 MONTEREY PKWY.
ST. LOUIS PARK. MN 55416 (6, 2) 920-64, 7 The listing of the civil penalties and orders is not as important as the thorough evaluation of the Licensee's response in terms of corporate policies, management and staff control measures, training and requalification programs, procedures, and quality assurance. What are the lessons learned and how are the improvements being implemented? Are these actions contributing to overall plant safety?
Corrective features are embodied in the TMI Action Plan. Analysis and feedback of operating experiences must be achieved in a realistic program.
The SEP report does not reflect any improvements in training nor even the considerable augmentation of staff (which I assume must be taking place) .
In my opinion, it is too early for the NRC to reference INFO reports and documents; however, if the Licensee has made or is making improvements as a consequence of INPO evaluations, such information assists in making " ... balanced and integrated .*. "* decisions.
Programs involving SEE-IN and NOTEPAD should be checked for updating operating experiences and reference should be made to the NRC Generic Letter 82-04. Have the SEP reviewers made any use of the improvements underway on handling and managing the collation of LERs? Is the Sequence Coding and Search System operational?
A feature of the SEP program that I had expected to find, but did not, is concerned with "aging" of components and systems. Have.there been any dis-cernible trends? Not all events are reportable, and thus some important trends might be missed if recourse is made to just LERs. The cooperation of the maintenance and inspection groups is needed. Are the IE Information Notices helpful in ascertaining whether any special aging effects could h~ve an impact on safety?
- 2. Review Method 2.2 Sel~ction of Topic List The identification of the more than 800 candidate items took place in 1976 and 1977~ and the methods used are impressive. The process of reducing this number to 90 topics applicable for the Palisades SEP review has an acceptable rationale, providing all current items involving Unresolved Safety Issues, TM~
Action Plan Items, and other generic matters are to be included. The draft SEP report indicates that a supplement is to be issued which will designate the status of the USis and TMI Action Plan Items. I consider this supplement to be a *key factor in balancing overall decisions to be made on the SEP items. The magnitude of this task should not be underestimated~
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HERBERT S. ISBIN 281 5 MONTEREY PKWY *.
ST. LOUIS PARK. MN SS416 (612) 920-6417 2.3 Topic Evaluation Procedures The two methods used for the preparation of the final Safety Evaluation Reports for the 90 topics have involved Licensee participation to ascertain that correct information was used. I have not seen any of t~e SERs, but I
-think that the approach used is good.
The finding by the NRC Staff that no topic identified in the.SEP review required immediate action is significant.
Topics were grouped into categories regarding no further action, action initiated by the Licensee which is acceptable to the NRC, and finally those which require d~cisions on whether backfitting is needed. This approach is logical.
2.4 Integrated Plant Safety Assessment.
The overall planning of the SEP. review to achieve a " .*. balanced and integrated .*. " decision on each topic appears to be good. The approach used by the NRC Staff appears to be consistent with the designated objectives.
I was not able to judge how the SEP work loads have impacted on the Licensee's resources. Nor have I been able to judge how the NRC plans to mold the backfitting decisions with decisions made and to be made on the USis and TMI Related Safety Items. Perhaps this subject will be treated in a. supplement.
COMMENTS ON SELECTED TOPICS 3.3 Topics for Which Plant Design Meets Current Criteria
- Based on Modifications I~plemented by the Licensee 3.3.1 Topi*c III-6 Seismic Design Considerations The Licensee must be responding to IE Bulletins, dealing for example with structural integrity of masonry walls and safety related piping systems. The report would be improved if the relationships of the programs involved for the IE Bulletins to the SEP concerns were clearly presented.
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HERBERT S. ISBIN 281 5 MONTEREY PKWY.
ST. LOUIS PARK, MN 55416 (6, 2J 920-64, 7 Integrated Assessment 4.6 Topic III-2 Wind and Tornado Loadings 4.6.1 Safety Injection and Refueling Water (SIRW) and Condensate Storage Tanks The approach taken by the Staff is good.
" .*. if the SIRW tank or condensate storage tank is lost **. "
Rather than just "or", don't you mean either or both? Further, wouldn't you need to comment4 that the failure(s)' in themselves, do not produce any undue flooding ef.fects?
This is one of the few items where the TMI Action Plan, Item I.C.l, "Guidance for the *Evaluation and Development of Procedures for Transients and Accidents," is mentioned. This. SEP topic is a part of a much broader and more complete task, with priority on Licensee's resources t6 be given to the TMI Item.
4.10 Topic III-6 Seis"tTtic Design Considerations Once again, for an " ... integrated and balanced ..* " approach, SEP concerns need to be factored into the broader a~eas being addressed through responses to IE Bulletins.
4.15 Topic V-5 Reactor Coolant Pressure Boundary (RCPB) Leakage Detection
- The rationale used by the Staff in arriving at conclusions fits the objective set forth for SEP. Is there any impact on radiation exposure to workers?
4.16.2 Use of Safety-Grade Systems for Safe Shutdown On page A-42, modification of the Branch Technical Position RSB5-l is being suggested. What is th~ current status?
4.19 Topic VI-3 Containment Pressure and Heat Ra~oval Capability The emphasis of this resolution is on the capability of the containment to withstand the increased pressure resulting from a two-steam generator blowdown.
A " ... balanced and integrated ..* " approach should avoid exacerbating other possible issueG.* For e~ample, would there by any impact on resolving the con-cerns presented in IE Bulletin 79-0lB, d~aling with the* environmental *
- conditions for the qualification of safety-related electrical equipment?
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,...5-281 S MONTEREY PKWY.
ST. LOUIS PARK, MN 55416 (6, 2) 920-6417 4.23 Topic VII-1.A. Isolation of Reactor Protection System from Nonsafety Systems, Including Qualification_ of Isolation Devices.
No reference is given to the completion of Technical assignment Control No. 6696, nor whether there have been any continuing studies.
4.24 Topic VII-3, Systems Required for Safe Shutdown I had expected to find a discussion on what can be done outside the control room " ... to achieve and maintain a safe shutdown condition of the plant ..* "
(See A~66) .
The SERs started with the general topic and then determined specific items. Using this Topic as an example, I suggest that both the specific and overall conclusion be stated.
4.27 Topic IX-3, Station Service and Cooling Water Systems Again, as noted in 4.24, not all the safety objectives given for this topic (see pages A-77 and -78) are addressed. Further, under the heading of Status, reference is made to pr'oposed generic reviews and technical *activities.
Were these proposals carried out? Additionally, are there any current probabilistic studies of flood hazards and flooding effects which should be noted?
4.29 Topic IX-6, Fire Protection The application of 10CFRSO, Appendix R, concerning fire protection and safe shutdown analysis and compliance, is a major undertaking. All that is noted is that associated circuits will be reviewed generically and outside the context of the SEP.
Additional Comments on Achieving An
" *.. integrated and balanced ... " Decision From the descriptions given of the methods used to identify topics of safety significance in Phase I of SEP, I conclude that the identification process was thorough, at least for the conditions known up to and including 1977. I appreciate the need for restricting expansion of the topics so that designated goals can be assigned. The developers of SEP recognized that resolution of generic items would proceed independently of SEP, but that some-how there would be an integrationof emerging NRC positions into an effective and efficient molding for the " ... final safety assessment of the plant." Since
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I HERBERT S. ISSIN 281 5 MONTEREY PKWY.
ST. LOUIS PARK, MN S5416 (6, 2) 920-64, 7 the approach to the "final" safety assessment may be asymptotic, I recommend deletion of "final".
Supplements. are to be issued to present the status of the generic i terns.
Additionally, the NRC, in special reports to the Congress, prepares the "Identification of New Unresolved Safety Issues Relating to Nuclear Power Plants." For example, NUREG-0705, March 1981, identified four new USis and listed a number of candidate issues for consideration as USis. (I have not seen the 1982 report.) Along with the moving target of USis, SEP reviewers need to include the TMI Action Plan Items, a variety of IE Bulletins, and Generic Letters. Attention *has to be given to the man~gement and incorporation of the information being generated into overall safety assessments.
The ...... integrated and balanced approach ... " should recogni~e the concerns
- of the Licensees regarding any possible unwarranted diversion of engineering staff from needed tasks. For example, see NUREG-0839, "A Survey by Senior NRC Management to Obtain Viewpoints on the Safety Impact of Regulatory Activities from Representative Utilities Operating and Constructing Nuclear Power Plants,"
August 1981. On the other hand, a dissenting viewpoint within the NRC, such as given by Demetrious L. Basdekas (published in the Minneapolis Star and Tribune, April 9, 1982) cannot go unchallenged, particularly when he writes that " .** the government and industry are unable or unwilling to deal honestly and urgently with far reaching nuclear-safety problems." I know in .the past that dissenting views were acknowledged and answered. Perhaps this has already been done for the present case.
Peripheral issues may need to be included. For example, proposed changes for Technical Specifications purport to reduce the number and level of detail in the technical portion and permit the use of a supplementary category. The criteria being developed for these changes should be consulted before implementing resolution of SEP Topics through added Tech Specs.
Only a limited, but useful, application could be made of the probabilistic risk assessment study for this plapt. Considering the large NRC budgeted research in this area for the past several years, the emphasis on development of methodologies, and the various current applica.tions, I expect more feedback into the SEP activities.
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