ML15202A427: Difference between revisions

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{{Adams
#REDIRECT [[AEP-NRC-2015-63, Donald C. Cook, Unit 1 - Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection]]
| number = ML15202A427
| issue date = 07/17/2015
| title = Donald C. Cook, Unit 1 - Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection
| author name = Gebbie J P
| author affiliation = Indiana Michigan Power Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000315
| license number =
| contact person =
| case reference number = AEP-NRC-2015-63
| document type = Letter, Response to Request for Additional Information (RAI)
| page count = 3
}}
 
=Text=
{{#Wiki_filter:INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWER One Cook Place Bridgman, Ml 49106 A unit ofAmerican Electric Power IndianaMichiganPower.com July 17, 2015 AEP-NRC-2015-63 10 CFR 50.4 Docket Nos. 50-315 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 Response to Request Additional for Information Regarding 2014 Unit 1 Steam Generator Tube Inspection
 
==References:==
: 1. Letter from J. P. Gebbie, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear Plant Unit 1, 2014 Steam Generator Tube Inspection Report", dated April 13, 2015, Agencywide Documents Access and Management System Accession No.ML15105A074.
: 2. Electronic Mail from T. A. Beltz, NRC, to I&M, Donald C. Cook Nuclear Plant, Unit 1 -Requests for Additional Information re: Fall 2014 Steam Generator Inspections (TAC No. MF6090).By Reference 1, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant Unit 1, submitted the Unit 1, 2014 Steam Generator Tube Inspection Report. By Reference 2, the U. S. Nuclear Regulatory Commission transmitted a request for additional information (RAI)regarding the report.The enclosure to this letter provides I&M's response to the RAIs.There are no new regulatory commitments made in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.Sincerely, Joel P. Gebbie Site Vice President DB/ams Enclosure A40cI U. S. Nuclear Regulatory Commission AEP-NRC-2015-63 Page 2 c: A. W. Dietrich, NRC, Washington, D.C.J. T. King -MPSC MDEQ -RMD/RPS NRC Resident Inspector C. D. Pederson, NRC Region III A. J. Williamson, AEP Ft. Wayne, w/o enclosures Enclosure to AEP-NRC-2015-63 Response to Request for Additional Information Regarding 2014, Unit I Steam Generator Tube Inspection By letter dated April 13, 2015, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant Unit 1, submitted the 2014 Steam Generator Tube Inspection Report.The U.S. Nuclear Regulatory Commission (NRC) Steam Generator Tube Integrity and Chemical Engineering Branch of the Division of Engineering has determined that the additional information below is needed to complete the review. By electronic mail dated June 26, 2015, the NRC transmitted a request for additional information (RAI) regarding the April 13, 2015 submittal.
This enclosure provides I&M's response to the RAI.RAI-1 In the April 13, 2015, letter, the licensee states that "No abnormal conditions were identified" for the plug, channel head, and steam drum and upper internals examinations during the inspection outage.Please indicate if there was any degradation observed.Response to RAI-1 No degradation was observed during the plug, channel head, steam drum, or upper internals inspections.
RAI-2 During the fall 2014 outage phone call between the licensee and NRC staff, the licensee indicated that a polymer object was found in a SG. The object was approximately 1.5 to 2 inches in length and 0.5 inches in diameter.
The object was classified as "poly" based on its white color, and the licensee indicated that it would assess the chemical composition of the polymer object to determine if it was acceptable to leave in service.Please discuss the results of the assessment.
Response to RAI-2 Further review of the visual inspection results refined the estimated dimensions of the material to be bounded by a length of 10 inches, width of 0.10 inch with a conservatively estimated mass of 1.0 gram. The material observed was believed to be a shaving from a portion of the secondary side delivery tooling that had a poly (PEX) sheath. This material has a melting point less than 300 degrees Fahrenheit and therefore will melt during operation and disperse through the secondary side. The PEX was analyzed for detrimental materials and it was determined that it does not pose a threat to the tubing or other steam generator components.}}

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