L-13-046, 2012 Annual Report in Accordance with 10 CFR 50.46(a)(3)(ii)

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2012 Annual Report in Accordance with 10 CFR 50.46(a)(3)(ii)
ML13053A219
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 02/18/2013
From: Kaminskas V
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-13-046
Download: ML13053A219 (4)


Text

Perry Nuclear Power Plant PO. Box 10 Center 97 Road FirstEnergyNuclear Operating Company Perry,Ohio 44081 Vito A. Kaminskas 440-280-5382 Vice President Fax: 440-280-8029 February 18, 2013 L-1 3-046 . 10 CFR 50.46(a)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Perry Nuclear Power Plant Docket No. 50-440, License Number NPF-58 2012 Annual Report Attached is the 2012 Annual Report for the Perry Nuclear Power Plant (PNPP). This report is submitted in accordance with 10 CFR 50.46(a)(3)(ii), and also fulfills ongoing commitments associated with License Commitment 17,contained in the PNPP Updated Safety Analysis Report, Appendix .1B.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas Veitch, Manager - Regulatory Compliance, at (440) 280-5188.

Sincerely, Vito. Kaminskas ,

Attachment:

2012 Annual Report cc: NRC Region III Administrator NRC Resident Inspector Office NRC Project Manager S00-

Attachment L-1 3-046 FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT DOCKET NUMBER: 50-440 LICENSE NUMBER: NPF-58 ANNUAL REPORT TO U.S. NUCLEAR REGULATORY COMMISSION January 1,2012 to December 31,2012 Page 1 of 3 Contents 10 CFR 50.46 Reporting of Emergency Core Cooling System (ECCS)

Model Changes and Errors Silicone Sealant Inspections and Testing

Attachment L-13-046 Page 2 of 3 10 CFR 50.46 Reporting of Emergency Core Cooling System (ECCS)

Model Changes and Errors Change or Error in an acceptable evaluation model or application of such model?

Change in an acceptable evaluation model or application of such model:

10 CFR 50.46 Notification Letter 2012-01 PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties Errors:

None The above methodology change report was investigated in Condition Report (CR) 12-18673.

The above methodology change report was reported to the USNRC in Letter L 447, December 17, 2012,

Subject:

Perry Nuclear Power Plant, Unit No. 1 Docket No. 50-440, License No. NPF-58 Report of Changes Pursuant to 10 CFR 50.46.

A review was conducted of the Corrective Action Program, correspondence/notifications from General Electric and Global Nuclear Fuels, Supplemental Reload Licensing Report for Perry Reload 13 / Cycle 14, and Perry Calculation FM -038, Perry Peak Cladding Temperatures. As described above, one methodology change was issued to Perry during the year 2012.

Attachment L-1 3-046 Page 3 of 3 Silicone Sealant Inspections and Testing License Commitment 17, "Silicone Sealant SSER 8-6.5," contained in the PNPP Updated Safety Analysis Report, requires that ESF ventilation systems be inspected for degradation of silicone sealant and that the results be summarized and reported to the NRC in the Annual Report.

2012 was a non-refuel outage year for PNPP. As such, there were no silicone sealant inspections performed in 2012. Inspection activities will be performed in refueling outage 1R14, scheduled to begin March 18, 2013.

During 1 R14, visual inspection of exposed ductwork will be performed to check for indication of sealant degradation and test specimens will be leak tested to determine if any degradation of silicone has occurred.