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| | document type = Letter | | | document type = Letter |
| | page count = 4 | | | page count = 4 |
| | | project = TAC:MF5424 |
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| | =Text= |
| | {{#Wiki_filter: |
| | [[Issue date::September 18, 2015]] |
| | |
| | Mr. Joseph Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519 |
| | |
| | SUBJECT: RE. GINNA NUCLEAR POWER PLANT -RE: SUMMARY OF THE STAFF'S REVIEW OF THE 2014 STEAM GENERATOR TUBE INSERVICE INSPECTIONS (TAC NO. MF5424) |
| | |
| | ==Dear Mr. Pacher:== |
| | By letters dated November 13, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14322A149) and June 30, 2015 (ADAMS Accession No. ML 15189A049), Exelon Generation Company, LLC (the licensee) submitted information summarizing the results of the spring 2014 steam generator tube inspections performed at RE. Ginna Nuclear Power Plant (Ginna). These inspections were performed during Ginna's refueling outage 37. The U.S. Nuclear Regulatory Commission (NRC) staff has completed its evaluation of the steam generator tube inspection summary report and concludes that the licensee provided the information required by the RE. Ginna Technical Specifications and no additional follow-up is required at this time. The results of the NRC staff's review of the report submitted by the licensee are summarized in the enclosed NRC staff's evaluation. If you have any questions, please contact me at 301-415-2020 or via e-mail at Brenda.Mozafari@nrc.gov. Docket No. 50-244 |
| | |
| | ===Enclosure:=== |
| | Staff Evaluation cc w/encl: Distribution via Listserv |
| | |
| | Sincerely,I I f' Brenda L. Mozafari, Senior P oject Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSERVICE INSPECTIONS R.E. GINNA NUCLEAR POWER PLANT DOCKET NO. 05-244 TAC NO. MF5424 By letters dated November 13, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14322A149) and June 30, 2015 (ADAMS Accession No. ML 15189A049), Exelon Generation Company, LLC (the licensee) submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Ginna Nuclear Power Plant (Ginna). These inspections were performed during refueling outage (RFO) 37. Ginna has two SGs designed and fabricated by Babcock and Wilcox International. Each SG contains 4765 thermally treated Alloy 690 tubes. Each tube has a nominal outside diameter of 0.750 inches and a nominal wall thickness of 0.043 inches. The tubes were hydraulically expanded at both ends for the full length of the tubesheet and are supported by a number of type 410 stainless steel lattice grid supports. The licensee provided the scope, extent, methods, and results of the SG tube inspections in its letters referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the tube inspections. Based on its review of the reports submitted, the U.S. Nuclear Regulatory Commission (NRC) staff has the following observations and comments: |
| | * Ten new top of tubesheet dents were identified during RFO 37. All were located in the cold-leg of steam generator B. The denting appears to be arrested based on a comparison of the voltages from current and previous outages. |
| | * Very minor to moderate flow accelerated corrosion was visually detected in approximately 65 of 85 secondary steam separator base plates. The licensee concluded that operation to the next inspection is acceptable. During the next inspection, quantitative examinations are planned. Enclosure |
| | -2 -Based on the above review of the information provided by the licensee, the NRC staff concludes that the licensee provided the information required by the Technical Specifications. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the expected objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Principal Contributor: A Huynh, NRR Date:Septernber 18, 2015 Mr. Joseph}} |
Revision as of 13:39, 15 March 2018
Letter Sequence Approval |
|---|
|
|
MONTHYEARML14322A1492014-11-13013 November 2014
Steam Generator Tube Inspection Report, End of Cycle 37 Refueling Outage, May 2014
Project stage: Request
ML15189A0492015-06-30030 June 2015
Steam Generator Tube Inspection Report Response to Request for Additional Information
Project stage: Response to RAI
ML15237A3092015-09-18018 September 2015
Summary of the Staff'S Review of the 2014 Steam Generator Tube Inservice
Project stage: Approval
2015-06-30
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Text
September 18, 2015
Mr. Joseph Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT: RE. GINNA NUCLEAR POWER PLANT -RE: SUMMARY OF THE STAFF'S REVIEW OF THE 2014 STEAM GENERATOR TUBE INSERVICE INSPECTIONS (TAC NO. MF5424)
Dear Mr. Pacher:
By letters dated November 13, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14322A149) and June 30, 2015 (ADAMS Accession No. ML 15189A049), Exelon Generation Company, LLC (the licensee) submitted information summarizing the results of the spring 2014 steam generator tube inspections performed at RE. Ginna Nuclear Power Plant (Ginna). These inspections were performed during Ginna's refueling outage 37. The U.S. Nuclear Regulatory Commission (NRC) staff has completed its evaluation of the steam generator tube inspection summary report and concludes that the licensee provided the information required by the RE. Ginna Technical Specifications and no additional follow-up is required at this time. The results of the NRC staff's review of the report submitted by the licensee are summarized in the enclosed NRC staff's evaluation. If you have any questions, please contact me at 301-415-2020 or via e-mail at Brenda.Mozafari@nrc.gov. Docket No. 50-244
Enclosure:
Staff Evaluation cc w/encl: Distribution via Listserv
Sincerely,I I f' Brenda L. Mozafari, Senior P oject Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REVIEW OF THE SPRING 2014 STEAM GENERATOR TUBE INSERVICE INSPECTIONS R.E. GINNA NUCLEAR POWER PLANT DOCKET NO.05-244 TAC NO. MF5424 By letters dated November 13, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 14322A149) and June 30, 2015 (ADAMS Accession No. ML 15189A049), Exelon Generation Company, LLC (the licensee) submitted information summarizing the results of the spring 2014 steam generator (SG) tube inspections performed at Ginna Nuclear Power Plant (Ginna). These inspections were performed during refueling outage (RFO) 37. Ginna has two SGs designed and fabricated by Babcock and Wilcox International. Each SG contains 4765 thermally treated Alloy 690 tubes. Each tube has a nominal outside diameter of 0.750 inches and a nominal wall thickness of 0.043 inches. The tubes were hydraulically expanded at both ends for the full length of the tubesheet and are supported by a number of type 410 stainless steel lattice grid supports. The licensee provided the scope, extent, methods, and results of the SG tube inspections in its letters referenced above. In addition, the licensee described corrective actions (e.g., tube plugging) taken in response to the tube inspections. Based on its review of the reports submitted, the U.S. Nuclear Regulatory Commission (NRC) staff has the following observations and comments:
- Ten new top of tubesheet dents were identified during RFO 37. All were located in the cold-leg of steam generator B. The denting appears to be arrested based on a comparison of the voltages from current and previous outages.
- Very minor to moderate flow accelerated corrosion was visually detected in approximately 65 of 85 secondary steam separator base plates. The licensee concluded that operation to the next inspection is acceptable. During the next inspection, quantitative examinations are planned. Enclosure
-2 -Based on the above review of the information provided by the licensee, the NRC staff concludes that the licensee provided the information required by the Technical Specifications. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the expected objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units. Principal Contributor: A Huynh, NRR Date:Septernber 18, 2015 Mr. Joseph
