ML19175A292: Difference between revisions
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{{#Wiki_filter:June 28, 2019 ANO Site Vice President Arkansas Nuclear One Entergy Operations, Inc. N-TSB-58 1448 S.R. 333 Russellville, AR 72802 | {{#Wiki_filter:June 28, 2019 ANO Site Vice President Arkansas Nuclear One Entergy Operations, Inc. | ||
N-TSB-58 1448 S.R. 333 Russellville, AR 72802 | |||
==SUBJECT:== | ==SUBJECT:== | ||
ARKANSAS NUCLEAR ONE, UNIT 2 | ARKANSAS NUCLEAR ONE, UNIT 2 - REVIEW OF THE FALL 2018 STEAM GENERATOR TUBE INSPECTION REPORT (EPID L-2019-LRO-0012) | ||
- REVIEW OF THE FALL 2018 STEAM GENERATOR TUBE INSPECTION REPORT (EPID L | |||
-2019-LRO-0012) | |||
==Dear Sir or Madam:== | ==Dear Sir or Madam:== | ||
The U.S. Nuclear Regulatory Commission ( | By letter dated February 28, 2019 (Agencywide Documents Access and Management System Accession No. ML19059A440), Entergy Operations, Inc. (the licensee) submitted information summarizing the results of the fall 2018 steam generator (SG) tube inspections at Arkansas Nuclear One, Unit 2 (ANO-2). The inspections were performed during Refueling Outage 26 (2R26). The SG tube inspection report was submitted in accordance with Technical Specification (TS) 6.6.7, Steam Generator Tube Inspection Report. | ||
In addition, the NRC staff concludes that there are no technical issues that warrant followup actions at this time. Enclosed is the NRC | The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the submittal and concludes that the licensee provided the information required by ANO-2 TS 6.6.7. In addition, the NRC staff concludes that there are no technical issues that warrant followup actions at this time. Enclosed is the NRC staffs review of the ANO-2, SG tube inspection report. | ||
If you have any questions, please contact me at (301) 415-4037 or by e-mail at Thomas.Wengert@nrc.gov. | |||
/RA/ | Sincerely, | ||
Thomas J. Wengert , Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50- | /RA/ | ||
Thomas J. Wengert, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368 | |||
==Enclosure:== | ==Enclosure:== | ||
Review of SG Tube Inspection Report | Review of SG Tube Inspection Report cc: Listserv | ||
cc: | |||
ML19175A292 *by memorandum OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DMLR/MCCB/BC* | |||
NAME TWengert PBlechman SBloom DATE 06/28/19 06/25/19 06/17/19 OFFICE NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME RPascarelli TWengert DATE 06/28/19 06/28/19 | |||
STAFF REVIEW OF RESULTS OF FALL 2018 STEAM GENERATOR TUBE INSERVICE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 26 ARKANSAS NUCLEAR ONE, UNIT 2 ENTERGY OPERATIONS, INC. | |||
DOCKET NO. 50-368 By letter dated February 28, 2019 (Agencywide Documents Access and Management System Accession No. ML19059A440), Entergy Operations, Inc. (the licensee) submitted information summarizing the results of the fall 2018 steam generator (SG) tube inspections at Arkansas Nuclear One, Unit 2 (ANO-2). These inspections were performed during Refueling Outage 26 (2R26). | |||
The SG tube inspection report was submitted in accordance with Technical Specification (TS) 6.6.7, Steam Generator Tube Inspection Report. | |||
ANO-2 has two Westinghouse model Delta 109 SGs, each containing 10,637 thermally-treated Alloy 690 tubes. The tubes each have a nominal outside diameter of 0.688 inches and a nominal wall thickness of 0.040 inches. The tubes are hydraulically expanded through the tubesheet thickness and are supported by eight broached-hole tube support plates (TSPs) in the vertical region of the tube bundle. In the U-bend region, the tubes are supported by five sets of staggered Type 405 stainless steel anti-vibration bars (AVBs). | |||
In the letter dated February 28, 2019, the licensee provided the scope, extent, methods, and results of its SG tube inspections. In addition, the licensee described corrective actions it has taken, such as tube plugging, in response to the inspection findings. | In the letter dated February 28, 2019, the licensee provided the scope, extent, methods, and results of its SG tube inspections. In addition, the licensee described corrective actions it has taken, such as tube plugging, in response to the inspection findings. | ||
After reviewing the information provided by the licensee, the U.S. Nuclear Regulatory Commission ( | After reviewing the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comments or observations: | ||
In the | * In the licensees report, the three-letter codes TBP and PTP are used for to be plugged and preventive tube plug, respectively. | ||
-letter codes TBP and PTP are used for | * Service induced indications were reported from wear with anti-vibration bars, tube support plates, and loose parts; however, the loose part indications were all historical and no new loose parts were reported. | ||
Service induced indications were reported from wear with anti-vibration bars , tube support plates, and loose parts; however, the loose part indications were all historical and no new loose parts were reported. Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by ANO-2 TS 6.6.7. In addition, the staff concludes that there are no technical issues that warrant followup action at this time because the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.}} | Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by ANO-2 TS 6.6.7. In addition, the staff concludes that there are no technical issues that warrant followup action at this time because the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. | ||
Enclosure}} | |||
Revision as of 16:46, 19 October 2019
| ML19175A292 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/28/2019 |
| From: | Thomas Wengert Plant Licensing Branch IV |
| To: | Entergy Operations |
| Wengert T | |
| References | |
| EPID L-2019-LRO-00112 | |
| Download: ML19175A292 (3) | |
Text
June 28, 2019 ANO Site Vice President Arkansas Nuclear One Entergy Operations, Inc.
N-TSB-58 1448 S.R. 333 Russellville, AR 72802
SUBJECT:
ARKANSAS NUCLEAR ONE, UNIT 2 - REVIEW OF THE FALL 2018 STEAM GENERATOR TUBE INSPECTION REPORT (EPID L-2019-LRO-0012)
Dear Sir or Madam:
By letter dated February 28, 2019 (Agencywide Documents Access and Management System Accession No. ML19059A440), Entergy Operations, Inc. (the licensee) submitted information summarizing the results of the fall 2018 steam generator (SG) tube inspections at Arkansas Nuclear One, Unit 2 (ANO-2). The inspections were performed during Refueling Outage 26 (2R26). The SG tube inspection report was submitted in accordance with Technical Specification (TS) 6.6.7, Steam Generator Tube Inspection Report.
The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review of the submittal and concludes that the licensee provided the information required by ANO-2 TS 6.6.7. In addition, the NRC staff concludes that there are no technical issues that warrant followup actions at this time. Enclosed is the NRC staffs review of the ANO-2, SG tube inspection report.
If you have any questions, please contact me at (301) 415-4037 or by e-mail at Thomas.Wengert@nrc.gov.
Sincerely,
/RA/
Thomas J. Wengert, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosure:
Review of SG Tube Inspection Report cc: Listserv
ML19175A292 *by memorandum OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DMLR/MCCB/BC*
NAME TWengert PBlechman SBloom DATE 06/28/19 06/25/19 06/17/19 OFFICE NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME RPascarelli TWengert DATE 06/28/19 06/28/19
STAFF REVIEW OF RESULTS OF FALL 2018 STEAM GENERATOR TUBE INSERVICE INSPECTIONS PERFORMED DURING REFUELING OUTAGE 26 ARKANSAS NUCLEAR ONE, UNIT 2 ENTERGY OPERATIONS, INC.
DOCKET NO. 50-368 By letter dated February 28, 2019 (Agencywide Documents Access and Management System Accession No. ML19059A440), Entergy Operations, Inc. (the licensee) submitted information summarizing the results of the fall 2018 steam generator (SG) tube inspections at Arkansas Nuclear One, Unit 2 (ANO-2). These inspections were performed during Refueling Outage 26 (2R26).
The SG tube inspection report was submitted in accordance with Technical Specification (TS) 6.6.7, Steam Generator Tube Inspection Report.
ANO-2 has two Westinghouse model Delta 109 SGs, each containing 10,637 thermally-treated Alloy 690 tubes. The tubes each have a nominal outside diameter of 0.688 inches and a nominal wall thickness of 0.040 inches. The tubes are hydraulically expanded through the tubesheet thickness and are supported by eight broached-hole tube support plates (TSPs) in the vertical region of the tube bundle. In the U-bend region, the tubes are supported by five sets of staggered Type 405 stainless steel anti-vibration bars (AVBs).
In the letter dated February 28, 2019, the licensee provided the scope, extent, methods, and results of its SG tube inspections. In addition, the licensee described corrective actions it has taken, such as tube plugging, in response to the inspection findings.
After reviewing the information provided by the licensee, the U.S. Nuclear Regulatory Commission (NRC) staff has the following comments or observations:
- In the licensees report, the three-letter codes TBP and PTP are used for to be plugged and preventive tube plug, respectively.
- Service induced indications were reported from wear with anti-vibration bars, tube support plates, and loose parts; however, the loose part indications were all historical and no new loose parts were reported.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by ANO-2 TS 6.6.7. In addition, the staff concludes that there are no technical issues that warrant followup action at this time because the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Enclosure