Safety Evaluation Concluding That Licensee Performing Tendon Surveillance in Accordance with Requirements of Plant Ts. Recommends That Licensee Take Appropriate Actions to Avoid Problems as Described in in 99-10ML18066A668 |
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Site: |
Palisades |
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Issue date: |
10/05/1999 |
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From: |
NRC (Affiliation Not Assigned) |
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To: |
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Shared Package |
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ML18066A666 |
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References |
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IEIN-99-010, NUDOCS 9910070158 |
Download: ML18066A668 (2) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML18066A6681999-10-0505 October 1999 Safety Evaluation Concluding That Licensee Performing Tendon Surveillance in Accordance with Requirements of Plant Ts. Recommends That Licensee Take Appropriate Actions to Avoid Problems as Described in in 99-10 ML18066A6251999-08-26026 August 1999 Safety Evaluation Supporting Relief Request of Quality & Safety to License DPR-20 ML18066A6051999-08-0909 August 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves ML18066A5841999-07-26026 July 1999 Safety Evaluation Re Relief Requests 2 & Portion of 1 Are Authorized Per 10CFR50.55(a)(3)(i) on Basis That Alternative Provides Acceptable Level Od Quality & Safety.Requests 3,5 & 7 Results in Hardship.Staff Denies Requests 1,4 & 6 ML18066A5601999-07-13013 July 1999 Draft Safety Evaluation Supporting Licensee Proposed Conversion of Current TS for Palisades Plant to Its. Concludes That Public Health & Safety Will Not Be Endangered & That Activities Conducted in Compliance with Regulations ML20206J9511999-05-0606 May 1999 Safety Evaluation Supporting Amend 186 to License DPR-20 ML20205Q5511999-04-13013 April 1999 Safety Evaluation Supporting Amend 185 to License DPR-20 ML20207F2611999-02-22022 February 1999 Safety Evaluation Supporting Amend 184 to License DPR-20 ML18066A3871999-01-28028 January 1999 Safety Evaluation Accepting License Request for Staff to Authorize Consumers Energy Proposed Alternative to Requirements of ASME Section XI Article IWA-5250 for Degraded Primary Coolant Pump Casing Bolts at Plant ML18066A3591998-12-28028 December 1998 Safety Evaluation Authorizing Licensee Request to Use ASME OMa-1996,Subsection Istd, Preservice & Inservice Exam & Testing of Dynamic Restraints, as Alternative to Requirements of ASME OMa-1988,Part 4 for Plant ML18068A4571998-10-14014 October 1998 Correction to Safety Evaluation of Third 120-month Interval Inservice Insp Program & Associated Requests for Relief. Error Was Made in Preparation of Evaluation ML18068A4391998-09-25025 September 1998 Safety Evaluation 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 ML20249A8901998-06-10010 June 1998 Safety Evaluation Supporting Amend 183 to License DPR-20 ML18066A1701998-06-0404 June 1998 Safety Evaluation Accepting Pump Relief Request 11 for Palisades Plant ML20248A0551998-05-15015 May 1998 Safety Evaluation Supporting Amend 182 to License DPR-20 ML20248A0071998-05-0707 May 1998 Safety Evaluation Supporting Amend 181 to License DPR-20 ML18065B2401998-05-0505 May 1998 Safety Evaluation Accepting Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Palisades Plant Susceptible to Pressure Locking or Thermal Binding ML18065B2411998-04-29029 April 1998 Safety Evaluation Supporting Amend 180 to License DPR-20 ML20216C5831998-04-0808 April 1998 Safety Evaluation Supporting Amend 179 to License DPR-20 ML18065B1911998-03-20020 March 1998 Safety Evaluation Re Third 10-yr Interval Inservice Insp Program Plan & Requests for Relief RR-4 & RR-9 ML18065B1741998-03-0606 March 1998 Safety Evaluation Granting Inservice Testing Program.Staff Concludes That Relief Requests as Evaluated & Modified by SE Will Not Compromise Operational Readiness of Pumps & Valves to Perform Safety Functions ML18067A7231997-10-14014 October 1997 Safety Evaluation Re Unresolved Insp Issues Re Adequacy of Turbine Bldg Fire Area Barriers ML20217E8711997-10-0202 October 1997 Safety Evaluation Supporting Amend 178 to License DPR-20 ML20217G4971997-09-30030 September 1997 Safety Evaluation Supporting Amend 177 to License DPR-20 ML20149K0021997-07-21021 July 1997 Safety Evaluation Supporting Amend 176 to License DPR-20 ML18067A5721997-06-11011 June 1997 Safety Evaluation Granting Licensee Relief Request 8 Re Pump & Valve Inservice Testing Program for Plant ML18067A5411997-05-0909 May 1997 Safety Evaluation for Response to Request for Addl Info Re NRC Bulletin 96-002, Movement of Heavy Loads Over Sf,Over Fuel in Reactor Core or Over Safety-Related Equipment, for Consumers Power Co,Palisades Plant ML18067A5281997-05-0606 May 1997 Safety Evaluation Approving Rev to Pidal in-core Monitoring Code ML20137X0161997-04-18018 April 1997 Safety Evaluation Accepting Changes to Rev 17 of CPC Quality Program Description for Operational NPPs (CPC-2A) ML18066A8241997-01-0909 January 1997 Safety Evaluation Accepting Third 120-month Interval Inservice Insp Program & Associated Requests for Relief ML18066A7861996-12-20020 December 1996 Safety Evaluation Accepting 8% Reduction in Calculated Fluence Due to Physical Changes in Plant & Denying Remaining 17% Due to Spectral Adjustments ML20129K2061996-10-31031 October 1996 Safety Evaluation Supporting Amend 174 to License DPR-20 ML20128N2481996-10-10010 October 1996 Safety Evaluation Supporting Amend 173 to License DPR-20 ML20129E5551996-09-26026 September 1996 Safety Evaluation Supporting Amend 172 to License DPR-20 ML18065A9001996-08-30030 August 1996 SER Re Relief Requests for Third 120-month Internal Inservice Testing Program.One Request Denied,Three Requests Approved for Interim Period & Remaining Requests Approved ML18065A7981996-06-28028 June 1996 SE Re Third 10-yr Interval ISI Program Plan Requests for Relief PR-02 & PR-04 for Plant.Licensee Proposed Alternative to Use Code Case N-522 in Lieu of code-required Pressure Tests Authorized ML18065A7931996-06-28028 June 1996 Safety Evaluation Accepting Alternative Method to Inservice Exam Requirements of ASME Boiler & Pressure Vessel Code ML18065A7181996-05-0909 May 1996 Safety Evaluation Approving Request to Implement Code Case N-533 as Alternative to Code Requirements for Plant Re Evaluation of Third 10-yr Interval ISI Program Plan. Technical Ltr Rept Encl ML20101P9951996-04-0505 April 1996 Safety Evaluation Supporting Amend 171 to License DPR-20 ML20094F1951995-11-0303 November 1995 Safety Evaluation Supporting Amend 170 to License DPR-20 ML18065A1711995-10-12012 October 1995 Safety Evaluation Accepting Licensee 950918 Request That NRC Authorize Alternative to ASME Boiler & Pressure Vessel Code,Per Paragraph 50.55a(a)(ii) of 10CFR50 ML18064A8281995-06-27027 June 1995 SE Re Cracking of Inconel 600 Components at Plant ML18064A8241995-06-21021 June 1995 Safety Evaluation Re Review of Licensee Submittals Which Concludes That Sufficient Justification Has Been Provided for Deviation in Seismic Qualification of CST Level Instrumentation Channel Cable ML20085K3241995-06-0808 June 1995 Safety Evaluation Supporting Amend 167 to License DPR-20 ML20084Q3251995-05-22022 May 1995 Safety Evaluation Supporting Amend 166 to License DPR-20 ML18064A7541995-05-0404 May 1995 Safety Evaluation Supporting Util Request to Adopt Code Case N-474-2 to Use Alloy 690 Forging Matl ML18064A7431995-05-0202 May 1995 Safety Evaluation Approving Licensee ,Related to Approval to Apply 1989 Edition of Section XI of ASME Boiler & Pressure Vessel Code ML18064A7141995-04-20020 April 1995 Safety Evaluation Granting Relief Per 10CFR50.55(f)(6)(i) Based on Impracticality of Performing Testing in Accordance W/Code ML20082M7321995-04-20020 April 1995 Safety Evaluation Supporting Amend 164 to License DPR-20 ML18064A7041995-04-13013 April 1995 SER Accepting ASME Code Case N-416, Alternative Rules for Hydrostatic Testing of Repair or Replacement of Class 2 Piping, Allowed for Hydroctatic Testing at Nominal Sys Operation Pressure of Class 2 1999-08-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18066A6901999-11-0101 November 1999 Rev 5 to Palisades Nuclear Plant Colr ML18066A6681999-10-0505 October 1999 Safety Evaluation Concluding That Licensee Performing Tendon Surveillance in Accordance with Requirements of Plant Ts. Recommends That Licensee Take Appropriate Actions to Avoid Problems as Described in in 99-10 ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant 05000255/LER-1998-011, :on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With1999-09-0202 September 1999
- on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With
ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6251999-08-26026 August 1999 Safety Evaluation Supporting Relief Request of Quality & Safety to License DPR-20 05000255/LER-1999-002, :on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With1999-08-20020 August 1999
- on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With
ML18066A6051999-08-0909 August 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety Related Motor-Operated Valves ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With ML18066A5841999-07-26026 July 1999 Safety Evaluation Re Relief Requests 2 & Portion of 1 Are Authorized Per 10CFR50.55(a)(3)(i) on Basis That Alternative Provides Acceptable Level Od Quality & Safety.Requests 3,5 & 7 Results in Hardship.Staff Denies Requests 1,4 & 6 ML18066A5601999-07-13013 July 1999 Draft Safety Evaluation Supporting Licensee Proposed Conversion of Current TS for Palisades Plant to Its. Concludes That Public Health & Safety Will Not Be Endangered & That Activities Conducted in Compliance with Regulations ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With ML20206J9511999-05-0606 May 1999 Safety Evaluation Supporting Amend 186 to License DPR-20 ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML20205Q5511999-04-13013 April 1999 Safety Evaluation Supporting Amend 185 to License DPR-20 05000255/LER-1999-001, :on 990310,noted Failure to Perform TS Surveillance Channel Check of Auxiliary Feedwater Flow Indication.Caused by Misinterpretation of Definition of Channel Check.Implementing Procedure Has Been Revised1999-04-0909 April 1999
- on 990310,noted Failure to Perform TS Surveillance Channel Check of Auxiliary Feedwater Flow Indication.Caused by Misinterpretation of Definition of Channel Check.Implementing Procedure Has Been Revised
ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With ML20207F2611999-02-22022 February 1999 Safety Evaluation Supporting Amend 184 to License DPR-20 ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With ML18066A3871999-01-28028 January 1999 Safety Evaluation Accepting License Request for Staff to Authorize Consumers Energy Proposed Alternative to Requirements of ASME Section XI Article IWA-5250 for Degraded Primary Coolant Pump Casing Bolts at Plant 05000255/LER-1998-014, :on 981227,control Rod Drive Seal Housing Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking. Faulted Control Rod drive-2 Seal Housing Was Replaced1999-01-26026 January 1999
- on 981227,control Rod Drive Seal Housing Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking. Faulted Control Rod drive-2 Seal Housing Was Replaced
05000255/LER-1998-013, :on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With1999-01-20020 January 1999
- on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With
05000255/LER-1998-012, :on 981215,discovered That MSIVs Were Slightly Open Based on Local Stem Position.Caused by High Packing Friction Introduced by Packing Replacement During 1998 Rfo. Completed Actions to Assure MSIVs Will Fully Close1999-01-14014 January 1999
- on 981215,discovered That MSIVs Were Slightly Open Based on Local Stem Position.Caused by High Packing Friction Introduced by Packing Replacement During 1998 Rfo. Completed Actions to Assure MSIVs Will Fully Close
ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With ML18066A3591998-12-28028 December 1998 Safety Evaluation Authorizing Licensee Request to Use ASME OMa-1996,Subsection Istd, Preservice & Inservice Exam & Testing of Dynamic Restraints, as Alternative to Requirements of ASME OMa-1988,Part 4 for Plant ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 05000255/LER-1997-011, :on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced1998-10-29029 October 1998
- on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced
ML18068A4571998-10-14014 October 1998 Correction to Safety Evaluation of Third 120-month Interval Inservice Insp Program & Associated Requests for Relief. Error Was Made in Preparation of Evaluation ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18068A4391998-09-25025 September 1998 Safety Evaluation 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 ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant 05000255/LER-1998-010, :on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested1998-08-18018 August 1998
- on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested
LD-98-024, Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency1998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant 05000255/LER-1998-009, :on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of PCS Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired1998-06-30030 June 1998
- on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of PCS Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired
ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML20249A8901998-06-10010 June 1998 Safety Evaluation Supporting Amend 183 to License DPR-20 1999-09-30
[Table view] |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555--0001 OFFICE OF NUCLEAR REACTOR REGULATION STAFF EVALUATION OF THE 25-YEAR TENDON SURVEILLANCE REPORT CONSUMERS ENERGY COMPANY PALISADES PLANT DOCKET NO. 50-255
1.0 INTRODUCTION
Consumers Energy Company submitted the Palisades Plant 25-year tendon surveillance report on December 18, 1997. In the letter accompanying the report, the licensee committed to submit a* post-surveillance regression analysis of prestressing tendon forces by February 27, 1998.
The licensee provided the analysis by letter dated February 23, 1998. The licensee submitted additional information on September 25, 1998, in response to the staff's July 27, 1998, request.
This staff evaluation addresses the adequacy of the report and the regression analysis performed by the licensee.
2.0 EVALUATION Precision Surveillance Corporation, as contractor for the licensee, performed the surveillance of the post-tensioning tendon system at the Palisades Plant. The contractor developed the surveillance report that was submitted to the NRC in the December 18, 1997, letter. The report inqicated that the surveillance consisted of a number of separate.inspections including:
(1) sheathing filler inspection and chemical *analysis, (2) tendon anchorage inspection,*
(3) tendon lift-off testing, (4) inspection and tensile test of wire samples removed from the detensioned tendons, and (5) resealing of tendons after all inspections were completed. The staff's. review of the inspection procedures finds that the inspections were performed in accordance with the existing prac~ice to comply with the plant's technical specification requirements.
The lift-off testing of the randomly-sampled tendons was performed as part of the sur..,;;:;::c.::*;;;.
The lift-off testing gave the measured prestressing forces in the selected tendons. The licensee compared the measured prestressing forces against the predicted forces for these tendons as required by the technical specificatk'.'!ns. The technical specifications also require the licensee to perform trending analysis based on the available measured prestressing forces, from all the surveillances. The trending analysis allows the licensee to ensure that the future trend of prestressing forces in the tendons will be above the predicted forces. The trending analysis is
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9910070158 991005 PDR ADOCK 05000255 P
PDR I I ENCLOSURE In performing the regression analysis, the licensee assumes that the regression curve is a straight line on a semi-log plot with the tendon force (y-axis) on a linear scale and the time (x-axis) on a logarithmic scale. This relationship is recommended by Regulatory Guide 1.35.1,
. "Determining Prestressing Forces for lnservice Inspection of Prestressed Concrete Containments," due to the known variation of time-dependent factors (i.e., creep of concrete and relaxation of prestressing steel). The staff therefore considers the licensee's assumption acceptable.
At each surveillance when the tendon forces were measured, the licensee considered an average of the measured tendon forces as representing the tendon forces in all the tendons in the population. Because of the small sample size (2 percent of the tendon population), the staff considers that this practice might not be representative of the actual variation in the tendon forces. The licensee should consider use of the individual measured forces in the regression analysis as discussed in Attachment 3 of NRG Information Notice (IN) 99-10, "Degradation of Prestressing Tendon Systems in Prestressed Concrete Containments," dated April 13, 1999.
The IN also discusses other issues (e.g., wire failures at Calvert Cliffs Nuclear Power Plant, tendon anchorage failures at Farley Nuclear Plant, and temperature effects on relaxation of prestressing steel). These issues may be relevant to the post-tensioning tendon system at Palisades. Thus, the staff recommends that the licensee take appropriate action if any of these findings are applicable to the post-tensioning tendon system at Palisades.
3.0 CONCLUSION
Based on the information provided in the report and in response to the staff's request for additional information, the staff concludes that the licensee is performing the tendon sur\\ieillance in accordance with the requirements of the plant's technical specifications. Due to the relevance of the issues described in IN 99-10 to the tendons at the Palisades Plant, the staff recommends that the licensee take appropriate actions to avoid similar problems.
Principal Contributor: H. Ashar Date:
October 5, 1999