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| | issue date = 04/20/1987 | | | issue date = 04/20/1987 |
| | 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 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 |
| | author name = JOHNSON B D | | | author name = Johnson B |
| | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | addressee name = | | | addressee name = |
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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 | | {{#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-. |
| -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-. | |
| 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: | | 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: |
| REGARDING ENTRY INTO SHUTDOWN COOLING Recommendations: | | REGARDING ENTRY INTO SHUTDOWN COOLING Recommendations: |
| 1. Either the strict use of PI-0104 (preferably narrow range, however either narrow or wide range is acceptable) | | 1. Either the strict use of PI-0104 (preferably narrow range, however either narrow or wide range is acceptable) |
| 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$sure would be within the acceptable bounds (see attached sketch) . IC0387-1473A-TC01 REGARDING ENTRY INTO "ONCE-THROUGH" COOLING Recommendations: | | and PTR-0125, or the average of all qualified PCS pressure indications (the aforementioned indicators as indicators PI-0105A through D) are to be used .to determine when the Shutdown Cooling System (SDCS) isolation valves M0-3015 and M0-3016 are to be manually opened to commence SDC. --2. The indica.tion-_at-which the shes-i-solation valves are to be openea should be revisedfrom 270 psia to 180 psia to ensure that the upper and lower pressure limits as described in Item 1 above are not exceede Note: The strict use of PI-0104 and PTR-0125 is preferred over averaging all tions in this case, since the shifts in output owing to transmitter error are less for these instruments than that expected for the 0105 loops previously identifie Incorporating Recommendation 2 will ensure that neither the maximum SDCS design pressure or the minimum PCS pressure to ensure subcooling will be exceeded if PI-0104 and PTR-0125 are used (see attached sketch). The 0105 loop errors result in peak-to-peak output shift variations a magnitude which exceeds the pressure band between the overpressurization and subcooling limits regardless of what pressure within the band would be fied as signifying when the operator should open the valves. As a result, using the 0105 loops for this function would require averaging all readings; a practice which would likely reduce the overall inaccuracy of the reading but would not necessarily ensure that the actual PCS pre$sure would be within the acceptable bounds (see attached sketch) . IC0387-1473A-TC01 REGARDING ENTRY INTO "ONCE-THROUGH" COOLING Recommendations: |
| 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.) | | 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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| |
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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 | | 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/ |
| -(-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/ | |
| y/ _r::.010 *:Zcf | | y/ _r::.010 *:Zcf |
| '3C! 1n frvlO * Ir'* ? ..5 010-..I.cf ft"-r:;.C'i/.o | | '3C! 1n frvlO * Ir'* ? ..5 010-..I.cf ft"-r:;.C'i/.o |
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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: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]
Category:UTILITY TO NRC
MONTHYEARML18057A4811990-09-17017 September 1990
Confirms 900718 Telcon Notification Re Westinghouse Agreement to Join Utils as Equity Investor in Plant
ML18057A4551990-09-0606 September 1990
Forwards Proprietary Info Re Dept of Labor Decision on Discharge of Former Employee of Util,Per NRC 900809 Request. No 10CFR50.7 Violation Occurred Since Job Performance Was Reason for Discharge.Encl Withheld (Ref 10CFR2.790(a)(6))
ML18057A4521990-09-0404 September 1990
Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated
IR 05000255/19900101990-09-0404 September 1990
Submits Addl Info Re Circuit & Raceway Schedule Enhancement Project,Per Insp Rept 50-255/90-10.Electrical Cable Separation & Channelization Anomalies Identified During Review of Physical Raceway Installations Will Be Evaluated
ML18057A4371990-08-31031 August 1990
Forwards Analysis Concluding That Plant Reactor Beltline Matl Upper Shelf Energy Will Remain Greater than 50ft-lbs Until Yr 2032,per 900716 Commitment
ML18057A4381990-08-31031 August 1990
Forwards Info Re Contamination of South Radwaste Area,Per 10CFR20.302,in Response to NRC 900112 Request.Approval Requested to Dispose of Low Level Radwaste in Place
ML20059E0001990-08-29029 August 1990
Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990
ML18057A4201990-08-24024 August 1990
Forwards Revised Application for Amend to License DPR-20, Changing Tech Specs Re Incore Analysis Program.Request Revised Per NRC Comments During 900709 Meeting
ML18057A4021990-08-22022 August 1990
Forwards Missing Pages from Decommissioning Funding Rept, Consisting of Pages 25 & 26 of Attachment a to Exhibit E
ML18057A4241990-08-21021 August 1990
Forwards Application for Amend to License DPR-20,changing Tech Spec 4.5.1 Re Statement on Integrated Leak Rate Test
ML18057A4071990-08-21021 August 1990
Forwards Tech Specs Change Request to License DPR-20,to Remove Redundant Requirements & Change Basis Statements No Longer Applicable
ML18057A4121990-08-21021 August 1990
Forwards Application for Amend to License DPR-20,changing Tech Specs to Revise Wording for Reactor Protective Sys Trip Setting Limits for Steam Generator Low Water Level
ML18057A4181990-08-21021 August 1990
Forwards Description of Changes Being Made to Plant Site Emergency Plan & Emergency Plan Changes.Change Allows Reduction in Shift Staffing During Cold Shutdown for Stated Staff
ML18057A3911990-08-17017 August 1990
Forwards Replacement Pages,To Palisades Second 10-Yr Interval Inservice Insp Program.
ML18057A3851990-08-17017 August 1990
Forwards Addl Info in Support of NRC Development of SER for full-term OL for Plant,Including Date of SER Providing Provisional OL to Plant & Summary of Valid Exemptions from 10CFR Regulations,Per Telcon
ML18057A3841990-08-17017 August 1990
Provides Addl Info Re Transfer of Plant Ownership to Palisades Generating Co,Per NRC 900725 Ltr
ML18057A3821990-08-14014 August 1990
Requests That Bechtel-KWU Rept 128901/MJS, Full Flow Testing of Motor-Operated Valve MO-1042A, Be Withheld (Ref 10CFR2.790(b)(1))
ML18057A3721990-08-0808 August 1990
Forwards Addl Info Re Util Request for Exemption from Separation Criteria of 10CFR50,App R,Section III.G.2 Re Containment Air Room
ML20055J1421990-07-26026 July 1990
Responds to Commitment Oversight Issue Resulting from Insp Rept 50-255/90-08.Commitment Mgt Seminar Training Will Be Complete Prior to 901001
ML18057A3561990-07-26026 July 1990
Forwards Certification of Financial Assurance for Decommissioning
ML18057A3411990-07-18018 July 1990
Forwards Revised Proposed Tech Spec Page 6-3,now Designated as Page 6-1b,adding Section 6.3.4,now Designated as Section 6.3.5 to Remove Organization Charts,Per Generic Ltr 88-06
ML18057A3381990-07-16016 July 1990
Advises That Util Does Not Foresee Need to Rely on Section V.C of App G to Remain in Compliance W/Upper Shelf Energy (Use) Requirements Re Use of Matl in Reactor Beltline
ML18057A3281990-07-13013 July 1990
Responds to Request for Addl Info Re Second 10-yr Interval Insp Program,Per 900418 Telcon.Util 900329 Response Revised to Reflect That Certain Components in Class 2 Sys Should Not Be Exempted,Per IWC-1220 of 1974 ASME Code Section XI
ML18057A3191990-07-0909 July 1990
Forwards Performance Indicator Trend Graphs for Jan 1989 - May 1990
ML18057A3201990-07-0606 July 1990
Discusses Reassessment of Control Room Temp Following Station Blackout Event.Results of Analysis Indicate That Control Room Temp Will Remain Below 112 F for 4 H After Onset of Blackout
ML18057A3171990-07-0303 July 1990
Provides Summary of Upgrades Made to Plant Electrical Distribution Sys,Per 870714 Loss of Offsite Power Event When Inadvertent Actuation of Water Deluge Spray Sys for 1-2 Startup Transformer Resulted in Bus to Ground Fault
ML20058K3771990-07-0202 July 1990
Forwards Rev 26 to Security Plan.Rev Withheld (Ref 10CFR73.21(c))
ML18057A3111990-06-25025 June 1990
Forwards Endorsements 116 & 117 to Nelia Policy NF-179 & Endorsements 102 & 103 to Maelu Policy MF-50
ML18057A3101990-06-25025 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements on Corrective Actions.
ML18057A3031990-06-22022 June 1990
Provides Addl Info Re Environ Qualification of Instrument Circuit Associated W/Steam Generator Pressure Channel PT-0752D,per Insp Rept 50-255/90-05.Circuits Spliced Directly to Pigtail from Electrical Penetration Connector
ML18057A3001990-06-21021 June 1990
Concurs W/Nrc Change in Terminology & Submits Revised Proposed Section 4.14 of Tech Specs
ML18057A2771990-06-15015 June 1990
Forwards Corrected NRC Form 474 Re Simulation Facility Certification,Indicating Exceptions to Ansi/Ans 3.5
ML18057A2901990-06-13013 June 1990
Forwards Application for Amend to License DPR-20,revising Tech Spec 3.3.1.b Re Safety Injection Tank Min Level
ML18057A2941990-06-12012 June 1990
Advises That Submittal of Second Interval Inservice Insp Program Delayed from 900615 to 900715,per 900418 Telcon
ML18057A2711990-06-11011 June 1990
Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i in Order to Maintain Plant in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Request Based on 900608 Failure of Heater Transformer 15
ML18057A2641990-06-11011 June 1990
Provides Response to NRC Requalification Exam Rept Dtd 900410 on NRC Concerns Re Facility & Training Ctr Staffing. Adequate Staffing Will Be Maintained to Ensure Operator Requalification Program Successful
ML18057A2591990-06-11011 June 1990
Forwards Palisades Simulator Certification Submittal.
ML18057A2631990-06-10010 June 1990
Requests Temporary Waiver of Compliance from Tech Spec 3.1.1i to Enable Plant to Be Maintained in Hot Shutdown While Repair Made to Pressurizer Heater Power Supply.Waiver Requested for 900611-18
ML18057A2571990-06-0808 June 1990
Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-255/90-12.Corrective Actions:Continuing Training Program Will Be Developed for Supervisors That Will Discuss Fire Protection Program Implementation Topics
ML20043D0601990-06-0404 June 1990
Forwards Rev 25 to Security Plan,Including Changes to Security Plan Drawings to Clarify Protected Area Boundary within Plant Security Bldg & Vital Area Boundaries in Other Specific Vital Areas of Plant.Rev Withheld (Ref 10CFR73.21)
ML18057A2581990-06-0101 June 1990
Forwards Revised Response to Violations Noted in Insp Rept 50-255/89-26.Concurs That Tests Performed Using Instrumented Insp Technique During 1988 Refueling Outage Considered Invalid
ML18057A2561990-05-31031 May 1990
Advises That No NPDES Notifications Required Nor Any Repts of Oil or Salt Occurred During Nov 1989 - Apr 1990
ML18057A2541990-05-30030 May 1990
Forwards Response to Technical Evaluation Rept EGG-NTA-8333 Which Evaluated Plant Compliance w/NUREG-0737,Item II.D.1 & Requested Addl Info Re New PORVs & Block Valves No Later than Jan 1990
ML18057A2511990-05-30030 May 1990
Forwards Final Response to Concerns Re Porv/Block Valve Mod, Per 900308 Meeting.Bechtel Technical Rept Withheld
ML18057A2501990-05-29029 May 1990
Forwards Investigation Rept Re Unsatisfactory Performance Testing of Fitness for Duty Program Blind Performance Test Samples
ML18057A2411990-05-24024 May 1990
Forwards Revised Application to Amend License DPR-20, Consisting of Revised Attachments 1 & 5 to 890227 Amend Request,Reflecting Transfer of Plant Ownership
ML18057A2311990-05-17017 May 1990
Forwards Analysis of Reactor Pressure Vessel Fast Neutron Fluence & PTS Ref Temps for Palisades Nuclear Plant. Rept Concludes That PTS Screening Criteria Will Be Exceeded at Axial Welds in Sept 2001 as Opposed to Mar 2002
ML18054B5861990-05-0707 May 1990
Forwards Monthly Trend Graph Rept for Jan 1989 - Mar 1990 Covering Safety Status Performance Indicators for HPSI, Auxiliary Feedwater,Emergency Ac Power,Lpsi,Containment Spray & Svc Water Sys
ML18054B5801990-04-30030 April 1990
Responds to Request for Addl Info on Proposed Administrative Changes to Tech Spec Section 3.0.4,per Generic Ltr 87-09. Licensee Will Implement Program to Assure Appropriate Level of Mgt Approval Required When Operating Conditions Changed
ML18054B5741990-04-25025 April 1990
Requests That Correspondence Re 890227 Application for Amend to License DPR-20 to Permit Transfer of Ownership of Plant Be Sent to Listed Address
1990-09-06
[Table view] |
Text
- 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-.
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:
REGARDING ENTRY INTO SHUTDOWN COOLING Recommendations:
1. Either the strict use of PI-0104 (preferably narrow range, however either narrow or wide range is acceptable)
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:
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.)
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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- 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)
have been modified to state "PCS pressure 270 psia (180 psia for degraded containment)
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
