L-12-059, 2011 Annual Report

2011 Annual Report

ML12062A028
Person / Time
Site:	Perry
Issue date:	02/23/2012
From:	Kaminskas V FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-12-059
Download: ML12062A028 (4)

Text

FENOCT PerryNuclear Power Plant 10 Center Road Perry Ohio 44081 FIrstEnergyNuclear Operating Company Vito A. Kaminska '  ? " - . 440-280-5382 Vice President .......... ......... Fax: 440-280-8029 February 23, 2012 L-12-059 ..-- . 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 2011 Annual Report Attached is the 2011 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. Robert B. Coad,

.Manager - Regulatory Compliance, at (440) 280-5328.

Sincerely,

Attachment:

2011 Annual Report cc: NRC Region III Administrator NRC Resident Inspector Office NRC Project Manager REIRS Project Manager AC)4ý'

0(24

Attachment L-12-059 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, 2011 to December 31, 2011 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-12-059 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?

Changes:

None Errors:

1. 10 CFR 50.46 Notification Letter 2011-02, dated July 20, 2011

Subject:

Impact of database error for heat deposition on the Peak Cladding Temperature (PCT) for 10 x 10 fuel bundles

2. 10 CFR 50.46 Notification Letter 2011-03, dated July 20, 2011

Subject:

Impact of updated formulation for gamma heat deposition to channel wall for 9 x 9 and 10 x 10 fuel bundles Both these error reports were investigated in Condition Report (CR) 11-98039.

Both these error reports were reported to the USNRC in Letter L-1 1-246, dated August 17, 2011.

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, two errors or changes were issued to Perry during the year 2011.

Attachment L-12-059 Page 3 of 3 Silicone Sealant Inspections and Testinq Maintenance Plan 41121 for Functional Location 0M46, to inspect duct sealant degradation and test duct samples has been satisfactorily completed during refueling outage 13 (1 R1 3). This report fulfills the ongoing commitment associated with Licensing Commitment 17 of USAR Appendix 1B, "the Engineering Safety Feature (ESF) ventilation systems duct work silicone sealant is to be inspected for degradation and the results reported to the NRC via-the Annual Report."

The duct specimens were individually leak tested at rated pressure (10 in. H20) in place, in the Intermediate Building Elevation 585 pipe chase. The TLD's were removed in 1R13 and given to site Dosimetry personnel for analysis after their respective identification numbers were recorded. The resulting dose (reported in mrem) recorded for specimen #1 is 290149 mrem (Deep) and for specimen #2 is 377457 mrem (Deep).

New replacement dosimetry was installed during the refueling outage.

The results of the duct specimen leak test for the GE Silpruf and Foster 30-02 sealants showed that no additional air leakage was present at sealant connections than that which was previously identified from June 28, 1989.

The ESF ventilation systems (i.e., M15 Annulus Exhaust Gas Treatment, M25/26 Control Room HVAC, and M40 Fuel Handling Building Ventilation) were walked down and a representative portion of the exposed exterior silicone sealants were inspected.

The exposed exterior sealant on all ductwork inspected during this walkdown was found to be in good condition with no observable degradation or leakage.