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| {{Adams | | {{Adams |
| | number = ML18052A941 | | | number = ML20211L581 |
| | issue date = 04/20/1987 | | | issue date = 02/17/1987 |
| | title = Forwards Addl Info Re Insp Rept 50-255/86-32 on 870217. Issues Re Equipment Operability & Reliability Addressed. Remaining Actions Considered Enhancements to Eeq File Auditability | | | title = Forwards Safety Insp Rept 50-255/86-32 on 861208-870113. Eight Significant Deficiencies Noted in Program Implementation.Findings Classified as Potential Enforcement/ Unresolved Items & Ongoing NRC Review Being Performed |
| | author name = Johnson B | | | author name = Harrison J |
| | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | | author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| | addressee name = | | | addressee name = Buckman F |
| | addressee affiliation = NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) | | | addressee affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | docket = 05000255 | | | docket = 05000255 |
| | license number = | | | license number = |
| | contact person = | | | contact person = |
| | document report number = NUDOCS 8704270005 | | | document report number = NUDOCS 8702270158 |
| | document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC | | | package number = ML18052A873 |
| | page count = 8 | | | document type = CORRESPONDENCE-LETTERS, NRC TO UTILITY, OUTGOING CORRESPONDENCE |
| | | page count = 2 |
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| {{#Wiki_filter:* General Offices: 1945 West Parnall Road, Jackson, Ml 49201 * (517) 788-0550 April 20,-1987 * Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-255 -LICENSE DPR-20 -PALISADES PLANT -IE INSPECTION REPORT 86032, ADDITIONAL INFORMATION IE Inspection Report 86-032 dated February 17, 1987 transmitted several unresolved and open items to which a written response was not required * Subsequent to receiving the inspection report on February 20, 1987, several conversations have taken place between Consumers Power Company and the NRC regarding the status of these items. It should be noted that all issues regarding equipment-ope.rability and reliability have been addressed and that all remaining actions are considered enhancements to EEQ file auditabilit Attached are the statuses of the items identified in the inspection report and subsequently discussed with Mr ASGautam of the Region III staff, Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, NRG NRG Resident Inspector-Palisades OC0487-0039-NL02 POTENTIALLY ENFORECABLE/UNRESOLVED ITEMS Item No 86032-01 86032"'."05 Description Unqualified grease found in Limitorque actuator ASCO solenoid valves found installed without seals to prevent moisture intusio Certain_ EEQ ._files found not auditable due to incorrect acceptance criteria and and missing informatio Rockbestos Firewall III EEQ files did not establish qualification of appropriate cables. 86032-09 Effects on low IR's during LOCA testing not addressed in General Electric Cable EEQ files. 86032-10 Plant installed Viking potted connectors found unqualified for instrumen-. | | {{#Wiki_filter:m |
| tation circuit IC0487-0059B-NL02 Status . The _SUN 50 EP grease has been removed, actuators cleaned and * qualified Exxon NEBULA EP-0 grease installed in EEQ listed Limitorque Valve Actuator Conduit seals have been installed for: 1) all EEQ listed ASCO solenoid valves in containment which . need to energize after initiation of a design basis *accident (DBA), and 2) all EEQ listed ASCO solenoid valves outside of containment which were in a 100% humidity accident environment and which need to energize after initiation of a DBA. The above actions were taken as a result of a conference cail between CPCo and ASGautam on. January 12, 1987. -The new accident profiles will be completed and incorporated by July 1, 1987, per conversation between KAToner, CPCo, and ASGautam on April 3, 1987. Analyses necessary to close this item were completed April 6, 1987. Analyses necessary to close* this . item have been complete Per conversa_tion between KAToner, CPCo, and ASGautam on April 3, 1987, the analyses will be incorporated into EEQ files by July 1, 1987. Analyses necessary to close this item have been completed. conversation between KAToner, CPCo, and ASGautam on April 3, 1987, the analyses wili be incorporated into EEQ files by July 1, 198 ** * 86032-11 Rosemount transmitter EEQ files did not justify demonstrated accuracy of these instruments for plant accident condition Limitorque actuators determined to be unqualified due to blocked T-drains * IC0487-0059B-NL02 2 As presented to the NRC at Region III headquarters on March 16, 1987, analyses are complet Also completed are administrative controls necessary to assure required safety functions are achieved from equipment associated with Rosemount transmitter Actions taken are described in CPCo internal correspondence; KAT87*008 and RJF87*011, which are attache Primary coolant system pressure transmitters PT-0104A and B and and B are being evaluated for replacement.with new transmitters to significantly eliminate instrument inaccurac Motor T-drains have been installe Reference LER 87-003 for actions take OPEN ITEMS 86032-08 General Electric Cable 1 and 2 EEQ files had discrepancies in the qualification requirements for radiatio Lack of controlled procedure for replacement of "O" rings and torquing of transmitter Deficiencies in the PPACS listing of maintenance activities for containment air coolers, position limit switches and motor oil in EEQ pumps. 86032-03 Lack of instructions for replacement of CELMARK connector "O_" -rings. IC0487-0059B-NL02 3 Per conversation with KAToner, CPCo, and ASGautam on April 3, 1987, necessary actions to close this item will be complete by July 1, 1987. This item has been completed by adding necessary administrative controls to instrument calibration sheets associated with Technical Specifications Surveillance Procedure Actions necessary to complete these items are underway and expected to be completed by May 15, 1987. Actions considered necessary to resolve this concern are under evaluatio Details of these specific actions will be provided to the NRC by May 15, 198 * To RJFrigo, Palisades From KAToner, Palisades CONSUMERS POWER Date March 19, 1987 COMPANY Subject PALISADES PLANT -EEQ TRANSMITTER ERROR Internal ANALYSIS -IMPACT ON OPERATING Correspondence cc RAFenech, Palisades KAT87*008 .KEOsborne, Palisades Engineering Analysis EA-KAT-87-01 was performed to assess the impact on the ability to achieve safety functions during LOCA and MSLB conditions in light of transmitter errors resulting from harsh environmental condition As concluded in the analysis, required safety functions can be achieved even in the presence of such errors if the following recommended procedural revisions are incorporated:
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| REGARDING ENTRY INTO SHUTDOWN COOLING Recommendations:
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| 1. Either the strict use of PI-0104 (preferably narrow range, however either narrow or wide range is acceptable)
| | FEB 17190 Docket No. 50-255 Consumers Power Company ATTN: Dr. F. W. Buckman Vice President Nuclear Operations-212 West Michigan Avenue Jackson, MI 49201 Gentlemen: |
| and PTR-0125, or the average of all qualified PCS pressure indications (the aforementioned indicators as indicators PI-0105A through D) are to be used .to determine when the Shutdown Cooling System (SDCS) isolation valves M0-3015 and M0-3016 are to be manually opened to commence SDC. --2. The indica.tion-_at-which the shes-i-solation valves are to be openea should be revisedfrom 270 psia to 180 psia to ensure that the upper and lower pressure limits as described in Item 1 above are not exceede Note: The strict use of PI-0104 and PTR-0125 is preferred over averaging all tions in this case, since the shifts in output owing to transmitter error are less for these instruments than that expected for the 0105 loops previously identifie Incorporating Recommendation 2 will ensure that neither the maximum SDCS design pressure or the minimum PCS pressure to ensure subcooling will be exceeded if PI-0104 and PTR-0125 are used (see attached sketch). The 0105 loop errors result in peak-to-peak output shift variations a magnitude which exceeds the pressure band between the overpressurization and subcooling limits regardless of what pressure within the band would be fied as signifying when the operator should open the valves. As a result, using the 0105 loops for this function would require averaging all readings; a practice which would likely reduce the overall inaccuracy of the reading but would not necessarily ensure that the actual PCS pre$sure would be within the acceptable bounds (see attached sketch) . IC0387-1473A-TC01 REGARDING ENTRY INTO "ONCE-THROUGH" COOLING Recommendations:
| | This refers to the special safety inspection conducted by Mr. A. S. Gautam and other NRC representatives of this office on December 8, 1986 through January 13, 1987, of activities at the Palisades Nuclear Plant authorized by NRC License No. DPR-20 and to the discussion of our findings with Mr. K. E. Osborne at the conclusion of the inspectio The enclosed copy of our inspection re) ort identifies areas examined during the inspection. Within these areas, t1e inspection consisted of a selective examination of procedures and representative records, observations, and interviews with personne Although the inspection determined that you have implemented a program to meet the requirements of 10 CFR 50.49, eight significant deficiencies in the program implementation were observed. These findings are classified as Potential Enforcement / Unresolved Items and an ongoing NRC review is being performed to evaluate the findings in regard to possible future enforcement action In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC-Public Document Roo We will gladly discuss any questions you have concerning this inspection. |
| 1. A specific caution should be added to procedures to . indicate that all four wide range steam generator loop indications (LI-0757A and B for Steam Generator A and.LI-0758A and B for Steam erator B) should be scanned with an average value obtained to ascertain when to enter PCS "once-through" cooling. * 2. Core exit thermocouples should also be monitored as a backup check to the wide range level indicatio Proceeding to "once-through" cooling should be based on both: * Steam* generator low level which indicates that the generator may not be capable of serving as an effective heat sink, and 2 * Core exit thermocouples which confirm steam generator ineffectiveness by showing inadequate PCS cooldow Notes: A. In this case, the -84% indication signifying when "once-through" cooling is to be initiated is considered acceptable. (At this level, 36% of the tubes are submerged; a level at which effective heat transfer can still be achieved.)
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| Although maximum potential transmitter error could result in an actual level of -120% when -84% is indi:Cated, appreciable invent_ory-(-23%) will -st-ill exist in the steam generator, -a_nd tfie-likelihood of steaming the steam generator shell dry before corrective actions are taken is almost non-existen S.ince safety function status checks are performed periodically, it is expected that the operator will be aware of either low or descending steam generator level in a timely manner. B. Based on discussions conducted subsequent to completion of the analysis, it is requested that the Operations Department review emergency procedures to determine if existing guidance related to the assessment of "once-t;hrough" cooling entry conditions fulfills the intent of the above recouunendation If the existing guidance is considered effective, no procedural revision should be undertaken since unnecessary revision may render the procedures confusin IC0387-1473A-TC01 q-_s.c:>tO-zc/
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| y/ _r::.010 *:Zcf
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| '3C! 1n frvlO * Ir'* ? ..5 010-..I.cf ft"-r:;.C'i/.o
| | Sincerely |
| -..Zcl
| | ' |
| -..Le' _s
| | B702270158 870217 , |
| * 9
| | DR ADOCK0500g5 g ,3 . g ,4, g ,' g , } hy ,1 : r,- |
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| <;t/ "7*'Y_ :::I -v7.lf:"'
| | J. J. Harrison, Chief 4 Engineering Branch Enclosure: Inspection Report -- |
| S"? c -L. Of°'' (!'f""'_r o;-,o_:;;
| | No. 50-255/86032(DRS) , |
| 2 1 \ .=foc;ioE
| | See Attached Distribution 1CS |
| * 'iJ'O..:f f1' I '>c;I t, ";) ---... ,SOI-'itS'-t.s----. -----b,SI-+. .
| | }EIIISlf RI ' RIII & |
| - | | ;r so3 T ur ess H rison Gautam/nma 2/i.js7 *So Westberg An\e An f,go/ |
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| .* | | Consumers Power Company 2 FEB 171987 |
| *1 To KAToner From RJFrigo CONSUMERS POWER Date March 26, 1987 COMPANY Subject PALISADES PLANT-Internal EEQ TRANSMITTER ERRORS Correspondence cc RAFenech RJF87*0ll KEOsborne Per memo KAT87*008 the following change has been made to the EOPs in response to transmitter errors resulting from degraded containment conditions:
| | - |
| a) EOPs 4.0 (LOCA), 6.0 (ESDE), & 9.0 (Functional Recovery)
| | Distribution cc w/ enclosure: |
| have been modified to state "PCS pressure 270 psia (180 psia for degraded containment)
| | Mr. Kenneth W. Berry, Director Nuclear Licensing J. F. Firlit, General Manager DCS/RSB (RIDS) |
| OR less as indicated on PI-0104 OR PTR-0125" as a condition to go on shutdown cooling. b) No changes are warranted for the four S/G wide range instrument The use of these instruments is in conjunction with other indications (Qualified CETs & PCS pressure trends) to determine if S/G heat removal capability is lost. IC0387-0003A-OP01
| | Licensing Fee Management Branch Resident Inspector, RIII Ronald Callen, Michigan Public Service Commission n Nuclear Facilities and k Environmental Monitoring Section U. Potapovs, VPB, IE R. Lasky, VPB, IE - |
| | T. Wambach, Project Manager, NRR [- |
| | P. Shemanski, NRR R. Smeenge, RIII D. Butler, RIII M. Jacobus, Sandia National Labs D. Brosseau, Sandia National Labs D. Jackson, INEL M. Trojovsky, INEL |
| | _ _ _ _ _ _ _ _ _ . . _ - _ __ __ -_-. |
| }} | | }} |
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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:NRC TO UTILITY
MONTHYEARML20058G8921990-11-0707 November 1990
Forwards Insp Repts 50-155/90-20 & 50-255/90-20 on 900925-28 & 1015-19.Violations Noted
ML20059G5461990-09-0404 September 1990
Discusses 900816 Site Visit Re Const Activities Requiring Security Force Compensatory Measures & Security Plan
ML20058M6141990-08-0707 August 1990
Forwards Sample Registration Ltr for 901010 Generic Fundamentals Section of Written Operator Licensing Exam. Registration Ltr Listing Names of Candidates Taking Exam Should Be Submitted to Region 30 Days Prior to Exam Date
ML20056A4981990-08-0101 August 1990
Forwards Master Bwr/Pwr Generic Fundamentals Exam Section W/Answer Key.W/O Encls
ML20055J4351990-07-23023 July 1990
Ack Receipt of 900702 Transmittal of Rev 26 to Physical Security Plan.Estimated Start & Completion Dates for Each Mod Project & Compensatory Measures Requested within 30 Days After Receipt of Ltr
ML20055F2271990-07-0606 July 1990
Forwards Physical Security Insp Rept 50-255/90-16 on 900618- 22 & 25.No Violations Identified
ML20059M9181990-06-13013 June 1990
Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl
IR 05000255/19890211989-09-27027 September 1989
Forwards Safety Insp Rept 50-255/89-21 on 890718-0831.No Violations Noted
ML20248C9321989-09-26026 September 1989
Advises That 890823 Rev 23 to Security Plan Meets Provisions of 10CFR50.54(p) & Acceptable.Encl Withheld (Ref 10CFR73.21)
ML20245H5331989-08-0202 August 1989
Advises That 890519 Changes to QA Program Described in CPC-2A Acceptable.Issues Addressed Listed
ML20245J6561989-06-0808 June 1989
Forwards Notice of Consideration of Issuance of Amend to Provisional Operating License DPR-20 & Opportunity for Hearing.Amend Would Add New Table 3.6.1 to Identify All Containment Isolation Valves Needed for Automatic Isolation
ML20246C8751989-05-0101 May 1989
Forwards Safeguard Insp Rept 50-255/89-11 on 890410-14 & Notice of Violation.Notice Withheld (Ref 10CFR73.21)
ML20245L3221989-04-28028 April 1989
Ack Receipt of 881223 Submittal of Rev 8 of QA Topical Rept CPC-2A Re Transfer of QA Assigned Functions to Other Plant Organizations & Continuing QA Organizations Program Control. Topical Rept Acceptable & Meets 10CFR50,App B
ML19064A3791988-11-0808 November 1988
Advises That Rev 21 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable
ML20207J9251988-09-23023 September 1988
Forwards Environ Assessments & Findings of No Significant Impact Re Temporary Exemption from Schedular Requirements of Property Insurance Rule Effective 881004 Per 10CFR50.54(W)(5)(i)
ML20207F8881988-07-27027 July 1988
Forwards Latest Rev of NRC Manual Chapter 0516, Salp. Region III Will Begin Using New Functional Areas Set Forth in Rev for All SALP Rept Periods Which Extend Beyond 880606 Effective Date of Procedure
ML20148C3591988-03-17017 March 1988
Advises That 880307 Rev 19 to Security Plan Consistent W/ Provisions of 10CFR50.54(p) & Acceptable
ML20147E9701988-03-0101 March 1988
Ack Receipt of Revs 6 & 7 of QA Topical Rept CPC-2A & Proposed QA Program Changes Described in .Revised Topical Rept Continues to Satisfy Requirements of 10CFR50, App B & Acceptable
ML20149G7601988-02-12012 February 1988
Advises of Region III Intent,If Requested,To Arrange Time & Place to Formally Present License Certificate to Newly Licensed Individuals,In Recognition of Accomplishment of Individuals Having Gone Through Study & Training
ML20149G4831988-02-12012 February 1988
Forwards Pilot Requalification Exam Given at Hb Robinson to Help Util Generate Test Questions.Review of Programs & Manpower Commitments Encouraged in Order to Make Appropriate Questions for Use on Upcoming Exams.W/O Encls
ML20235T9271987-10-0808 October 1987
Ack Receipt of Proposed Changes to Rev 7 to QA Topical Rept CPC-2A.Review Concludes Revs Acceptable
ML20235V2231987-10-0606 October 1987
Ack Receipt of 861202 Proposed Amend to Physical Security Plan in Response to Miscellaneous Amends & Search Requirements.Response to Encl Comments Requested within 30 Days of Ltr Receipt
ML20235F6641987-09-24024 September 1987
Forwards 870828 Fr Notice Stating FY88 Annual Fee for Operating Reactors,Per 10CFR171 & Calculation of Fee.Payment Due for First Quarter Once NRC Sends Bill.W/O Encls
ML20235F4221987-09-22022 September 1987
Forwards NRR Position Re Entry Into Limiting Condition for Operation Based on Inservice Testing Surveillance Results within Required Action Range.Review of Practices for Performing Inservice Testing Surveillances Recommended
ML20235M6091987-07-10010 July 1987
Forwards Insp Rept 50-255/87-16 on 870608-12.No Violations Noted
ML20214T9061987-06-0404 June 1987
Forwards Exam Rept 50-255/OL-87-01 of Exam Administered on 870504-08
ML20214U2991987-06-0404 June 1987
Forwards Requalification Exam Rept 50-255/OL-87-02 of Exam Administered on 870504-08
ML20214U9841987-06-0303 June 1987
Forwards Revised NRC Form 398,personal Qualifications statement-licensee & NRC Form 396,certification of Medical Exam by Facility Licensee.Forms Revised to Reflect Changes to 10CFR55 Effective on 870526.W/o Encls
ML20214S6101987-06-0303 June 1987
Forwards Description of Allegation Re Past Conviction for Possession & Distribution of Controlled Substance by Employee Supposedly Granted Unescorted Access to Facilities. Appropriate Action Requested.Encl Withheld (Ref 10CFR2.790)
ML20214R8761987-06-0101 June 1987
Forwards Plant Readiness Team Insp Rept 50-255/86-35 on 861216-870213 & Notice of Violation.Matl Condition of Plant Will Be Adequate to Support Restart Upon Completion of Outstanding Prestart Commitments.W/O Notice
ML20214J5301987-05-22022 May 1987
Provides Conclusions Based on Review of Informing NRC That Shareholders Approved Restructuring Plan Creating Holding Company.Nrc Consents to Proposed Ownership of Util by CMS Energy Corp
ML20214J3591987-05-19019 May 1987
Advises That 870422 Rev 5 to Stability Training & Qualification Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable
ML20214F5281987-05-14014 May 1987
Requests Schedule for plant-specific Implementation of USI A-46, Seismic Qualification of Equipment in Operating Plants No Later than 871201,per Encl Granting 870410 Request for Schedular Relief
ML20215M5761987-05-11011 May 1987
Informs of Processing of 870416 Request for Approval Under 10CFR50.80.NRC Consideration of Approval Requires Notice to Interested Persons.Due to Notice requirement,870506 Action Cannot Be Approved Prior to 870529,dependent Upon Review
ML20215M3921987-05-11011 May 1987
Forwards Fr Notice of Proposed Corporate Restructuring Per Util
ML20212R5831987-04-21021 April 1987
Advises That 870414 Rev 16b to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable
ML20213A4131987-04-21021 April 1987
Forwards Physical Security Insp Rept 50-255/87-07 on 870320- 30.No Violations Noted
ML20205J5591987-03-27027 March 1987
Confirmatory Action Ltr Re Util Stating That All pre-start Commitment Actions Completed & Certain Other Actions Will Be Completed During Startup & Power Operation of Plant.Augmented Insp Coverage During Restart Continues
ML20205F7711987-03-17017 March 1987
Forwards Safety Insp Rept 50-255/87-04 on 870121-0302
ML20207T3211987-03-17017 March 1987
Advises That 870304 Rev to Site Emergency Plan Consistent W/ Provisions of 10CFR50.54(q) & Acceptable
ML20212P8281987-03-0909 March 1987
Forwards Safety Insp Rept 50-255/86-30 on 860724-1231 & Notice of Violation.Util Will Be Notified by Separate Correspondence of Decision Re Enforcement Action Based on Findings of Insp
ML20212N4671987-03-0909 March 1987
Forwards Safety Insp Rept 50-255/87-03 on 870121-22, 0217-19 & 0303.No Violation Identified
IR 05000255/19860281987-03-0505 March 1987
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-255/86-28.Addl Info Re Listed Violations Requested within 30 Days of Ltr Date
ML20212L9971987-03-0505 March 1987
Advises That All But One Item in Rev 16 to Security Plan Transmitted on 870227 Consistent W/Provisions of 10CFR50.54(p) & Acceptable.Comments on Unacceptable Item Encl.Encl Withheld (Ref 10CFR73.21)
ML20211R0381987-02-24024 February 1987
Advises That 870114 Rev 4 to Site Emergency Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable
IR 05000255/19860321987-02-17017 February 1987
Forwards Safety Insp Rept 50-255/86-32 on 861208-870113. Eight Significant Deficiencies Noted in Program Implementation.Findings Classified as Potential Enforcement/ Unresolved Items & Ongoing NRC Review Being Performed
ML20211G4031987-02-14014 February 1987
Forwards Safety Evaluation & EGG-NTA-7463, Reactor Trip Sys Reliability..., Supporting Response to Generic Ltr 83-28,Item 4.5.2 Re Periodic on-line Testing of Reactor Trip Sys.Plant Designed to Permit on-line Testing
ML20211A9531987-02-13013 February 1987
Advises That Financial Info Submitted for 1987 in Util Satisfies Requirements of 10CFR140.21 That Each Licensee Maintain Guarantee of Payment of Deferred Premiums for Operating Reactors Over 100 Mwe
ML20211M8651987-02-12012 February 1987
Forwards Safety Insp Rept 50-255/87-02 on 870114-0205.No Violations Noted
ML20210T7741987-02-10010 February 1987
Confirms 870220 Meeting W/Util in Glen Ellyn,Il to Discuss Violations Involving Containment Escape Hatch Equalizing Valves,Containment Air Coolers,Svc Water Sys Flow,Component Cooling Water Flow & LPSI Pumps
1990-09-04
[Table view]
Category:OUTGOING CORRESPONDENCE
MONTHYEARML20210G8351999-07-29029 July 1999
Final Response to FOIA Request for Documents.Records in App a Encl & Will Be Available in PDR
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
ML20203F2541999-02-10010 February 1999
Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function
ML20155J1471998-11-0303 November 1998
Informs That on 981007,NRC Administered GFE Section of Written Operator Licensing Exam to Employees of Facility. Exam Answer Key for Forms a & B,Grading Results & Individual Answer Sheets Encl.Without Encl
ML20155A2311998-10-16016 October 1998
Ltr Contract:Mod 4 to Task Order 1 Entitled, Technical Assistance in Review of Cask Unloading Procedures for Palisades Plant (VSC-24 Cask) Under Contract NRC-02-95-003
ML20154A9651998-09-25025 September 1998
Forwards SE Re Licensee 950523 Submittal of Rept Which Summarizes Results of USI A-46 Implementation Program, Established in Response to Suppl 1 to NRC GL 87-02 Through 10CFR50.54(f) Ltr
ML20155A5521998-09-18018 September 1998
Forwards Insp Rept 50-255/98-15 on 980702-0821.No Violations Noted.Operating Crew Demonstrated Positive Command & Control While Implementing Emergency Operating Procedures in Response to Inadvertent Main Feedwater Pump Trip
ML20237B4571998-08-13013 August 1998
Ack Receipt of ,Which Transmitted Changes Identified as Rev 41 to Palisades Physical Security Plan, Submitted Under Provisions of 10CFR50.54.Changes Do Not Decrease Effectiveness of Plan.Plan Withheld
IR 05000255/19980101998-07-30030 July 1998
Forwards Insp Rept 50-255/98-10 on 980507-0701 & Notice of Violation
ML20236T6231998-07-22022 July 1998
First & Final Response to FOIA Request for Records.Records in App a Being Made Available in PDR & Encl.Records in App B Partially Withheld Per Exemption 6
ML20236K8271998-06-30030 June 1998
First Partial Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl
ML20249C3291998-06-23023 June 1998
Ltr Contract,Task Order 007, Palisades Engineering & Technical Support Inspection, Under Contract NRC-03-98-021
ML20248C0971998-05-28028 May 1998
Forwards Partially Withheld Insp Rept 50-255/98-08 on 980504-08 (Ref 10CFR73.71).No Violations Noted.Insp Effort to Determine Whether Activities Authorized by Licensee Conducted Safely & in Accordance W/Nrc Requirements
ML20247P6361998-05-27027 May 1998
Ack Receipt of & Fee in Listed Amount Received on 980427,in Payment for Civil Penalty Proposed by NRC in Ltr .Corrective Actions Will Be Examined During Future Insp
ML20248B3981998-05-26026 May 1998
Ltr Contract:Task Order 231, Review Palisades Conversion of TS to Improved TS Based on Std TS, to Contract NRC-03-95-026
ML20217Q4401998-05-0505 May 1998
Refers to Generic Fundamentals Exam Section of Written Operator Licensing Exam Administered by NRC on 980408 to Facility Employees.Forwards Answer Keys for Forms a & B, Grading Results & Individual Answer Sheets.W/O Encls
ML20217Q5411998-05-0404 May 1998
Discusses Licensee Response to GL 92-01,Rev 1,Supplement 1, Rv Structural Integrity, Issued by NRC in May 1995. Requests That Ceco Reevaluate RPV Weld Chemistry Values That Ceco Previously Submitted as Part of Licensing Basis
ML20217J2131998-04-0202 April 1998
Forwards Copy of Each Revised Forms 398,personal Qualifications Statement & 396,certification of Medical Exam by Facility Licensee.Due to Error on Instructions for Form 398,addendum for Completing Form Are Provided
IR 05000255/19970141998-04-0202 April 1998
Discusses Insp Rept 50-255/97-14 on 971028-1119 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $55,000
ML20236L0601998-03-23023 March 1998
Forwards Sample Insp Rept.Provides First Cut at Basic Outline
ML20203D7281998-02-23023 February 1998
Ack Receipt of ,Which Transmitted Changes Identified as Rev 40 to Security Plan,Submitted Under Provisions of 10CFR50.54(p).NRC Approval Is Not Required
ML20199K5671998-02-0303 February 1998
Ack Receipt of Ltr Dtd 971218,which Transmitted Changes Identified as Rev 17 to Safeguards Suitability,Training & Qualification Plan,Submitted Under Provisions of 10CFR50.54(p)
ML20197C4091997-12-18018 December 1997
Discusses Review of Revs to Sections 3 & 4 of Plant Emergency Plan.Nrc Approval Not Required,Based on Determinations That Changes Do Not Decrease Effectiveness of Emergency Plan
ML20198Q8921997-11-0707 November 1997
Ack Receipt of ,Transmitting Changes Identified as Rev 8 to Safeguards Contingency Plan,Submitted Under Provisions of 10CFR50.54(p).Changes Do Not Decrease Overall Effectiveness of Safeguards Contingency Plan
ML20217C6631997-09-25025 September 1997
Ack Receipt of Ltr Transmitting Changes Identified as Rev 39 to Security Plan.Encl Contains Safeguard Info & Will Be Withheld from Public Disclosure
ML20137X0031997-04-18018 April 1997
Forwards SE Re Proposed Changes to Rev 17 of, Quality Program Description for Operational NPPs (CPC-2A), IAW 10CFR50.54(a)(3)(ii)
IR 05000315/19960041997-03-25025 March 1997
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-315/96-04 & 50-316/96-04
DD-97-05, Denies 970307 Request for Commission Review of Director'S Decision DD-97-05.NRC Staff Will Respond to Concerns Re Further Use of VSC-24 Casks1997-03-19019 March 1997
Denies 970307 Request for Commission Review of Director'S Decision DD-97-05.NRC Staff Will Respond to Concerns Re Further Use of VSC-24 Casks
ML20136A7521997-03-0505 March 1997
Forteenth Partial Response to FOIA Request for Documents. Records in App W Encl & Available in Pdr.App X Records Withheld in Part (Ref FOIA Exemption 6)
ML20134Q0981997-02-21021 February 1997
Ninth Partial Response to FOIA Request for Documents. Forwards Documents Listed in App P.App Q Documents Partially Withheld (Ref FOIA Exemption 6).Documents Also Available in PDR
ML20134F2461997-02-0505 February 1997
Ack Receipt of Which Transmitted Changes Identified as Rev 38 to Palisades Security Plan Submitted Under Provisions of 10CFR50.54(p)
ML20147B7321997-01-24024 January 1997
Forwards SALP Rept 50-255/96-01 for Palisades Nuclear Plant,Covering Period from 950528-961123
ML20134B0951997-01-16016 January 1997
Advises That Rev 39 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable
ML20132G9111996-12-18018 December 1996
Ack Receipt of Ltr Dtd 961119,transmitting Changes Identified as Rev 16 to Plant Suitability,Training & Qualification Plan,Submitted Under Provisions of 10CFR50.54(p)
ML20132G9011996-12-18018 December 1996
Ack Receipt of Ltr Dtd 961119,transmitting Changes Identified as Temporary Change to Security Plan,Submitted Under Provisions of 10CFR50.54(p)
ML20132D9131996-12-12012 December 1996
Ack Receipt of Ltr Dtd 961016,transmitting Changes Identified as Rev 37 to Security Plan,Submitted,Per 10CFR50.54(p)
ML20135B2661996-11-27027 November 1996
Discusses 960723-24 Evaluation of Physical Protection Program.Mods to Protection Program Resulting from 1992 Operational Safeguards Response Evaluation Were Evaluated
ML20129K1131996-11-0505 November 1996
Forwards Copy of Master Bwr/Pwr Gfes Exam W/Answer Key for Info.W/O Encl
ML20134C9161996-10-0909 October 1996
Requests Info That Provides NRC Added Confidence & Assurance That Plants Operated & Maintained within Design Bases & Any Deviations Reconciled in Timely Manner Per 10CFR50.54(f)
ML20128N6701996-10-0808 October 1996
Ack Receipt of 10CFR50.54(a) Submitted on 960625 Re Proposed Changes to QAP Description.Submittal Proposed Changes to Evaluation on Program,Qualification Requirements for Lead Auditors & Record Retention Requirements Submitted
ML20129F0521996-10-0202 October 1996
Ack Receipt of & Check in Amount of $50,000 for Payment of Civil Penalty Proposed by NRC in .Addl Response Requested to Confirm New Schedule for MOV Mod Completion
ML20129B7851996-09-18018 September 1996
Discusses 960731 10CFR50.54(a) Submittal for Review Re Changes in Quality Assurance Program Description.Will Notify of Results When Review Completed
ML20149J3001994-12-28028 December 1994
Ack Receipt of Which Transmitted Changes Identified as Rev 6 to Plant Contingency Plan Submitted Under Provisions of 10CFR50.54(p).Changes Acceptable
ML20149J2591994-12-23023 December 1994
Ack Receipt of ,Which Transmitted Changes Identified as Rev 13 to Plant Suitability,Training & Qualification Plan Submitted Under Provisions of 10CFR50.54(p).Changes Acceptable
ML20149J3601994-12-21021 December 1994
Requests That Concerns Be Reviewed by Someone Independent from Security Organization,As Noted in Encl.Nrc Concerned That Chilling Effect on Contractor Personnel May Have Also Occurred
ML20236T6881993-12-21021 December 1993
Ack Receipt of Which Transmitted Correspondence from a Fredian,Requesting NRC to Do Environ Impact Statement Re Storage of Spent Nuclear Fuel Rods at Palisades NPP
ML20058G7121993-12-0202 December 1993
Ack Receipt of Transmitting Rev 12 to Suitability,Training & Qualification Plan,Submitted Per 10CFR50.54(p).Changes Consistent W/Provisions of 10CFR50.54(p) & Acceptable Except as Noted in Encl
ML20058G0691993-12-0101 December 1993
Forwards SALP 12 Rept 50-255/93-01 for 920401-931030.Concurs W/Ratings of SALP Board Assessment
ML20058E6581993-12-0101 December 1993
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 940209.Informs That Facility Must Submit Ltr Identifying Individuals Who Will Take Exam
ML20058D3531993-11-22022 November 1993
Responds to to DW Riegle Re Gaseous & Liquid Effluent Comparisons for PWRs & BWRs from 1970 to 1989
1999-07-29
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Text
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FEB 17190 Docket No. 50-255 Consumers Power Company ATTN: Dr. F. W. Buckman Vice President Nuclear Operations-212 West Michigan Avenue Jackson, MI 49201 Gentlemen:
This refers to the special safety inspection conducted by Mr. A. S. Gautam and other NRC representatives of this office on December 8, 1986 through January 13, 1987, of activities at the Palisades Nuclear Plant authorized by NRC License No. DPR-20 and to the discussion of our findings with Mr. K. E. Osborne at the conclusion of the inspectio The enclosed copy of our inspection re) ort identifies areas examined during the inspection. Within these areas, t1e inspection consisted of a selective examination of procedures and representative records, observations, and interviews with personne Although the inspection determined that you have implemented a program to meet the requirements of 10 CFR 50.49, eight significant deficiencies in the program implementation were observed. These findings are classified as Potential Enforcement / Unresolved Items and an ongoing NRC review is being performed to evaluate the findings in regard to possible future enforcement action In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC-Public Document Roo We will gladly discuss any questions you have concerning this inspection.
Sincerely
'
B702270158 870217 ,
DR ADOCK0500g5 g ,3 . g ,4, g ,' g , } hy ,1 : r,-
,
J. J. Harrison, Chief 4 Engineering Branch Enclosure: Inspection Report --
No. 50-255/86032(DRS) ,
See Attached Distribution 1CS
}EIIISlf RI ' RIII &
- r so3 T ur ess H rison Gautam/nma 2/i.js7 *So Westberg An\e An f,go/
..
._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
L1
.
.
Consumers Power Company 2 FEB 171987
-
Distribution cc w/ enclosure:
Mr. Kenneth W. Berry, Director Nuclear Licensing J. F. Firlit, General Manager DCS/RSB (RIDS)
Licensing Fee Management Branch Resident Inspector, RIII Ronald Callen, Michigan Public Service Commission n Nuclear Facilities and k Environmental Monitoring Section U. Potapovs, VPB, IE R. Lasky, VPB, IE -
T. Wambach, Project Manager, NRR [-
P. Shemanski, NRR R. Smeenge, RIII D. Butler, RIII M. Jacobus, Sandia National Labs D. Brosseau, Sandia National Labs D. Jackson, INEL M. Trojovsky, INEL
_ _ _ _ _ _ _ _ _ . . _ - _ __ __ -_-.
