ML15237A309: Difference between revisions

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| number = ML15237A309
| number = ML15237A309
| issue date = 09/18/2015
| issue date = 09/18/2015
| title = R.E. Ginna Nuclear Power Plant - Summary of the Staff'S Review of the 2014 Steam Generator Tube Inservice
| title = Summary of the Staff'S Review of the 2014 Steam Generator Tube Inservice
| author name = Mozafari B
| author name = Mozafari B
| author affiliation = NRC/NRR/DORL/LPLI-1
| author affiliation = NRC/NRR/DORL/LPLI-1
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==Dear Mr. Pacher:==
==Dear Mr. Pacher:==


By letters dated November 13, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14322A149) and June 30, 2015 (ADAMS Accession No.
By letters dated November 13, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14322A149) and June 30, 2015 (ADAMS Accession No. ML15189A049), 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.
ML15189A049), 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.
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.
If you have any questions, please contact me at 301-415-2020 or via e-mail at Brenda.Mozafari@nrc.gov.
Line 40: Line 39:
Staff Evaluation cc w/encl: Distribution via Listserv
Staff Evaluation cc w/encl: Distribution via Listserv


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. ML14322A149) and June 30, 2015 (ADAMS Accession No.
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. ML14322A149) and June 30, 2015 (ADAMS Accession No. ML15189A049), 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.
ML15189A049), 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.
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.
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.

Latest revision as of 09:29, 5 February 2020

Summary of the Staff'S Review of the 2014 Steam Generator Tube Inservice
ML15237A309
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/18/2015
From: Mozafari B
Plant Licensing Branch 1
To: Joseph Pacher
Exelon Generation Co
Mozafari B
References
TAC MF5424
Download: ML15237A309 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 18, 2015 Mr. Joseph E. Pacher 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. ML14322A149) and June 30, 2015 (ADAMS Accession No. ML15189A049), 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.

Sincerely,

~~I~ ~*

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 Docket No. 50-244

Enclosure:

Staff Evaluation cc w/encl: Distribution via Listserv

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. ML14322A149) and June 30, 2015 (ADAMS Accession No. ML15189A049), 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

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

ML15189A049), Exelon Generation Company, LLC (the licensee) submitted information summarizing the results of the spring 2014 steam generator tube inspections performed at R. E. 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 R.E. 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.

Sincerely, IRA/

Brenda Mozafari, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosure:

Staff Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPL 1-1 R/F RidsRgn1 MailCenter RidsNrrDorlLpl 1-1 RidsNrrLAKGoldstein KKarwoski RidsNrrPMREGinna RidsAcrsAcnw_MailCTR CHunt RidsOgcRp AHuyn ADAMS Accession No.: ML15237A309 OFFICE NRR/DORL/LPL 1-1/PM NRR/DORL/LPL 1-1/LA N RR/DE/ESGB/BC NRR/DORL/LPL 1-1/BC NAME BMozafari KGoldstein GKulesa BBeasley DATE 9/08/2015 9/04/2015 7/23/2015 9/18/2015