L-14-241, Submittal of Steam Generator Inspection Reports- Technical Specifications 5.6.6.2.2 and 5.6.6.2.4: Difference between revisions
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{{#Wiki_filter:FENOCTM FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President August 11, 2014 L-14-241 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | {{#Wiki_filter:FENOCTM Beaver Valley Power Station P.O. Box4 FirstEnergy Nuclear Operating Company Shmomaoo~PA 15077 Eric A. Larson 724-682-5234 Site Vice President Fax: 724-643-8069 August 11, 2014 L-14-241 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 | ||
==SUBJECT:== | ==SUBJECT:== | ||
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 | |||
There are no regulatory commitments contained in this submittal. | Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Steam Generator Inspection Reports- Technical Specifications 5.6.6.2.2 and 5.6.6.2.4 In accordance with Beaver Valley Power Station, Unit No.2 Technical Specifications 5.6.6.2.2 and 5.6.6.2.4, FirstEnergy Nuclear Operating Company hereby submits three reports containing steam generator inspection results. The enclosed reports provide information required by the technical specifications that was obtained during inspections conducted during the spring 2014 refueling outage. Remaining metallurgical examination results will be submitted when available. | ||
If there are any questions or if additional information is required, please contact Mr. Thomas A Lentz, Manager-Fleet Licensing, at (330) 315-6810. | There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A Lentz, Manager- Fleet Licensing, at (330) 315-6810. | ||
!(jr-Eric A Larson | Sincerely~ | ||
~V.//JJ~ | |||
!(jr-Eric A Larson | |||
==Enclosures:== | ==Enclosures:== | ||
A Beaver Valley Unit 2 End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report B. Unit #2-2R17 Steam Generator F* (F Star) Report C. Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative}} | A Beaver Valley Unit 2 End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report B. Unit #2- 2R17 Steam Generator F* (F Star) Report C. Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative}} | ||
Latest revision as of 01:31, 4 November 2019
| ML14224A574 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/11/2014 |
| From: | Emily Larson FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14224A573 | List: |
| References | |
| L-14-241 | |
| Download: ML14224A574 (1) | |
Text
FENOCTM Beaver Valley Power Station P.O. Box4 FirstEnergy Nuclear Operating Company Shmomaoo~PA 15077 Eric A. Larson 724-682-5234 Site Vice President Fax: 724-643-8069 August 11, 2014 L-14-241 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Steam Generator Inspection Reports- Technical Specifications 5.6.6.2.2 and 5.6.6.2.4 In accordance with Beaver Valley Power Station, Unit No.2 Technical Specifications 5.6.6.2.2 and 5.6.6.2.4, FirstEnergy Nuclear Operating Company hereby submits three reports containing steam generator inspection results. The enclosed reports provide information required by the technical specifications that was obtained during inspections conducted during the spring 2014 refueling outage. Remaining metallurgical examination results will be submitted when available.
There are no regulatory commitments contained in this submittal. If there are any questions or if additional information is required, please contact Mr. Thomas A Lentz, Manager- Fleet Licensing, at (330) 315-6810.
Sincerely~
~V.//JJ~
!(jr-Eric A Larson
Enclosures:
A Beaver Valley Unit 2 End-of-Cycle 17 Analysis and Prediction for End-of-Cycle 18 Voltage-Based Repair Criteria 90-Day Report B. Unit #2- 2R17 Steam Generator F* (F Star) Report C. Generic Letter 95-05 Tube Intersection Burst Test, Leakage Test, and Morphology Conclusions cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative