ML19035A502: Difference between revisions
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{{#Wiki_filter:/RA/}} | {{#Wiki_filter:February 5, 2019 MEMORANDUM TO: Joseph E. Donoghue, Acting Director Division of Materials and License Renewal Office of Nuclear Reactor Regulation FROM: David L. Rudland /RA/ | ||
Senior Technical Advisor for Materials Division of Materials and License Renewal Office of Nuclear Reactor Regulation | |||
==SUBJECT:== | |||
==SUMMARY== | |||
REPORT AND ANALYSIS OF DATA FROM OPERATING EXPERIENCE SMART SAMPLE, OPESS 2018/01, EVALUATION OF LICENSEE ACTIONS TAKEN IN RESPONSE TO 10 CFR PART 21 NOTIFICATION OF THE POTENTIAL EXISTENCE OF DEFECTS RELATED TO CONTROL ROD DRIVE MECHANISM (CRDM) THERMAL SLEEVES This memorandum transmits the U.S. Nuclear Regulatory Commissions (NRCs) final summary report, Summary Report and Analysis of Data from Operating Experience Smart Sample, OpESS 2018/01, Evaluation of Licensee Actions Taken in Response to 10 CFR Part 21 Notification of The Potential Existence Of Defects Related To Control Rod Drive Mechanism (CRDM) Thermal Sleeves (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19035A503). | |||
Through a sampling of 10 of the 16 most susceptible plants to CRDM thermal sleeve wear, the staff verified that the domestic T-Cold plants are properly performing the Westinghouse Nuclear Safety Advisory Letter-recommended inspections. In addition, the data gathered through these inspections confirms the wear rate assumptions used in the staff safety analyses. | |||
Consequently, the NRC staff is satisfied that the affected plants are properly addressing the thermal sleeve flange wear issue. Therefore, the NRC requires no further action at this time. | |||
The NRC staff will continue to monitor industry operating experience. | |||
==Enclosure:== | |||
Summary report CONTACTS: David L. Rudland, Ph.D. Roger Kalikian Senior Technical Advisor Materials Engineer NRR/DMLR NRR/DMLR (301) 415-1896 (301) 415-5590 | |||
J. Donoghue | |||
==SUBJECT:== | |||
==SUMMARY== | |||
REPORT AND ANALYSIS OF DATA FROM OPERATING EXPERIENCE SMART SAMPLE, OPESS 2018/01, EVALUATION OF LICENSEE ACTIONS TAKEN IN RESPONSE TO 10 CFR PART 21 NOTIFICATION OF THE POTENTIAL EXISTENCE OF DEFECTS RELATED TO CONTROL ROD DRIVE MECHANISM (CRDM) THERMAL SLEEVES DATED: FEBRUARY 5, 2019. | |||
DISTRIBUTION: | |||
RidsNrrMailCtr RidsNrrDmlr Resource RES/DE resource BMcDermott JThompson RMcKinley DWoodyatt DRudland RLukes AHiser JKaizer DAlley RTregoning SCumblidge DMcCain CHovanec DHills RTregoning GGerond CJFong CRapp RAnzalone MGray MLeech JKulp MHolmberg PJoon SDowney MMarshfield ADAMS Accession Nos: | |||
Summary Report: ML19035A503 Transmittal Memo: ML19035A502 *via email OFFICE NRR/DMLR NRR/DMLR/LA NRR/DMLR/MPHB NRR/DMLR/MPHB NAME DRudland SLent RKalikian SCumblidge DATE 02/5/19 02/5/19 02/5/19 02/5/19 OFFICIAL AGENCY COPY}} | |||
Latest revision as of 02:54, 20 October 2019
| ML19035A502 | |
| Person / Time | |
|---|---|
| Issue date: | 02/05/2019 |
| From: | David Rudland NRC/NRR/DMLR/MPHB |
| To: | Joseph Donoghue Division of Materials and License Renewal |
| Roger Kalikian, NRR/DMLR/MPHB, 415-5590 | |
| Shared Package | |
| ML19035A397 | List: |
| References | |
| Download: ML19035A502 (2) | |
Text
February 5, 2019 MEMORANDUM TO: Joseph E. Donoghue, Acting Director Division of Materials and License Renewal Office of Nuclear Reactor Regulation FROM: David L. Rudland /RA/
Senior Technical Advisor for Materials Division of Materials and License Renewal Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
REPORT AND ANALYSIS OF DATA FROM OPERATING EXPERIENCE SMART SAMPLE, OPESS 2018/01, EVALUATION OF LICENSEE ACTIONS TAKEN IN RESPONSE TO 10 CFR PART 21 NOTIFICATION OF THE POTENTIAL EXISTENCE OF DEFECTS RELATED TO CONTROL ROD DRIVE MECHANISM (CRDM) THERMAL SLEEVES This memorandum transmits the U.S. Nuclear Regulatory Commissions (NRCs) final summary report, Summary Report and Analysis of Data from Operating Experience Smart Sample, OpESS 2018/01, Evaluation of Licensee Actions Taken in Response to 10 CFR Part 21 Notification of The Potential Existence Of Defects Related To Control Rod Drive Mechanism (CRDM) Thermal Sleeves (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19035A503).
Through a sampling of 10 of the 16 most susceptible plants to CRDM thermal sleeve wear, the staff verified that the domestic T-Cold plants are properly performing the Westinghouse Nuclear Safety Advisory Letter-recommended inspections. In addition, the data gathered through these inspections confirms the wear rate assumptions used in the staff safety analyses.
Consequently, the NRC staff is satisfied that the affected plants are properly addressing the thermal sleeve flange wear issue. Therefore, the NRC requires no further action at this time.
The NRC staff will continue to monitor industry operating experience.
Enclosure:
Summary report CONTACTS: David L. Rudland, Ph.D. Roger Kalikian Senior Technical Advisor Materials Engineer NRR/DMLR NRR/DMLR (301) 415-1896 (301) 415-5590
J. Donoghue
SUBJECT:
SUMMARY
REPORT AND ANALYSIS OF DATA FROM OPERATING EXPERIENCE SMART SAMPLE, OPESS 2018/01, EVALUATION OF LICENSEE ACTIONS TAKEN IN RESPONSE TO 10 CFR PART 21 NOTIFICATION OF THE POTENTIAL EXISTENCE OF DEFECTS RELATED TO CONTROL ROD DRIVE MECHANISM (CRDM) THERMAL SLEEVES DATED: FEBRUARY 5, 2019.
DISTRIBUTION:
RidsNrrMailCtr RidsNrrDmlr Resource RES/DE resource BMcDermott JThompson RMcKinley DWoodyatt DRudland RLukes AHiser JKaizer DAlley RTregoning SCumblidge DMcCain CHovanec DHills RTregoning GGerond CJFong CRapp RAnzalone MGray MLeech JKulp MHolmberg PJoon SDowney MMarshfield ADAMS Accession Nos:
Summary Report: ML19035A503 Transmittal Memo: ML19035A502 *via email OFFICE NRR/DMLR NRR/DMLR/LA NRR/DMLR/MPHB NRR/DMLR/MPHB NAME DRudland SLent RKalikian SCumblidge DATE 02/5/19 02/5/19 02/5/19 02/5/19 OFFICIAL AGENCY COPY