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{{#Wiki_filter:INDIANA Indiana Michigan PowerMICHIGAN Cook Nuclear PlantPOWER One Cook PlaceBridgman, Ml 49106A unit ofAmerican Electric Power IndianaMichiganPower.comJuly 17, 2015 AEP-NRC-2015-6310 CFR 50.4Docket Nos. 50-315U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555-0001Donald C. Cook Nuclear Plant Unit 1Response to Request Additional for Information Regarding2014 Unit 1 Steam Generator Tube Inspection
{{#Wiki_filter:INDIANA Indiana Michigan PowerMICHIGAN Cook Nuclear PlantPOWER One Cook PlaceBridgman, Ml 49106A unit ofAmerican Electric Power IndianaMichiganPower.com July 17, 2015 AEP-NRC-2015-63 10 CFR 50.4Docket Nos. 50-315U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1Response to Request Additional for Information Regarding 2014 Unit 1 Steam Generator Tube Inspection


==References:==
==References:==
: 1. Letter from J. P. Gebbie, Indiana Michigan Power Company (I&M), to U. S. NuclearRegulatory Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear PlantUnit 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 NuclearPlant 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. GebbieSite Vice PresidentDB/amsEnclosure A40cI U. S. Nuclear Regulatory Commission AEP-NRC-2015-63Page 2c: A. W. Dietrich, NRC, Washington, D.C.J. T. King -MPSCMDEQ -RMD/RPSNRC Resident InspectorC. D. Pederson, NRC Region IIIA. J. Williamson, AEP Ft. Wayne, w/o enclosures Enclosure to AEP-NRC-2015-63Response to Request for Additional Information Regarding 2014, Unit I Steam GeneratorTube InspectionBy letter dated April 13, 2015, Indiana Michigan Power Company (I&M), the licensee forDonald C. Cook Nuclear Plant Unit 1, submitted the 2014 Steam Generator Tube InspectionReport.The U.S. Nuclear Regulatory Commission (NRC) Steam Generator Tube Integrity and ChemicalEngineering Branch of the Division of Engineering has determined that the additionalinformation 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, 2015submittal. This enclosure provides I&M's response to the RAI.RAI-1In the April 13, 2015, letter, the licensee states that "No abnormal conditions were identified" forthe plug, channel head, and steam drum and upper internals examinations during the inspectionoutage.Please indicate if there was any degradation observed.Response to RAI-1No degradation was observed during the plug, channel head, steam drum, or upper internalsinspections.RAI-2During the fall 2014 outage phone call between the licensee and NRC staff, the licenseeindicated that a polymer object was found in a SG. The object was approximately 1.5 to 2inches in length and 0.5 inches in diameter. The object was classified as "poly" based on itswhite color, and the licensee indicated that it would assess the chemical composition of thepolymer object to determine if it was acceptable to leave in service.Please discuss the results of the assessment.Response to RAI-2Further review of the visual inspection results refined the estimated dimensions of the materialto be bounded by a length of 10 inches, width of 0.10 inch with a conservatively estimated massof 1.0 gram. The material observed was believed to be a shaving from a portion of thesecondary side delivery tooling that had a poly (PEX) sheath. This material has a melting pointless than 300 degrees Fahrenheit and therefore will melt during operation and disperse throughthe secondary side. The PEX was analyzed for detrimental materials and it was determinedthat it does not pose a threat to the tubing or other steam generator components.}}
: 1. Letter from J. P. Gebbie, Indiana Michigan Power Company (I&M), to U. S. NuclearRegulatory Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear PlantUnit 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 NuclearPlant 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. GebbieSite Vice President DB/amsEnclosure A40cI U. S. Nuclear Regulatory Commission AEP-NRC-2015-63 Page 2c: A. W. Dietrich, NRC, Washington, D.C.J. T. King -MPSCMDEQ -RMD/RPSNRC Resident Inspector C. D. Pederson, NRC Region IIIA. 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 forDonald 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 ChemicalEngineering 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, 2015submittal.
This enclosure provides I&M's response to the RAI.RAI-1In the April 13, 2015, letter, the licensee states that "No abnormal conditions were identified" forthe 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-1No degradation was observed during the plug, channel head, steam drum, or upper internals inspections.
RAI-2During the fall 2014 outage phone call between the licensee and NRC staff, the licenseeindicated that a polymer object was found in a SG. The object was approximately 1.5 to 2inches in length and 0.5 inches in diameter.
The object was classified as "poly" based on itswhite color, and the licensee indicated that it would assess the chemical composition of thepolymer object to determine if it was acceptable to leave in service.Please discuss the results of the assessment.
Response to RAI-2Further review of the visual inspection results refined the estimated dimensions of the materialto be bounded by a length of 10 inches, width of 0.10 inch with a conservatively estimated massof 1.0 gram. The material observed was believed to be a shaving from a portion of thesecondary side delivery tooling that had a poly (PEX) sheath. This material has a melting pointless than 300 degrees Fahrenheit and therefore will melt during operation and disperse throughthe 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.}}

Revision as of 21:48, 30 June 2018

Donald C. Cook, Unit 1 - Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection
ML15202A427
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 07/17/2015
From: Gebbie J P
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2015-63
Download: ML15202A427 (3)
v • d • e


Text

INDIANA Indiana Michigan PowerMICHIGAN Cook Nuclear PlantPOWER One Cook PlaceBridgman, Ml 49106A unit ofAmerican Electric Power IndianaMichiganPower.com July 17, 2015 AEP-NRC-2015-63 10 CFR 50.4Docket Nos. 50-315U. S. Nuclear Regulatory Commission ATTN: Document Control DeskWashington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1Response 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. NuclearRegulatory Commission (NRC) Document Control Desk, "Donald C. Cook Nuclear PlantUnit 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 NuclearPlant 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. GebbieSite Vice President DB/amsEnclosure A40cI U. S. Nuclear Regulatory Commission AEP-NRC-2015-63 Page 2c: A. W. Dietrich, NRC, Washington, D.C.J. T. King -MPSCMDEQ -RMD/RPSNRC Resident Inspector C. D. Pederson, NRC Region IIIA. 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 forDonald 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 ChemicalEngineering 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, 2015submittal.

This enclosure provides I&M's response to the RAI.RAI-1In the April 13, 2015, letter, the licensee states that "No abnormal conditions were identified" forthe 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-1No degradation was observed during the plug, channel head, steam drum, or upper internals inspections.

RAI-2During the fall 2014 outage phone call between the licensee and NRC staff, the licenseeindicated that a polymer object was found in a SG. The object was approximately 1.5 to 2inches in length and 0.5 inches in diameter.

The object was classified as "poly" based on itswhite color, and the licensee indicated that it would assess the chemical composition of thepolymer object to determine if it was acceptable to leave in service.Please discuss the results of the assessment.

Response to RAI-2Further review of the visual inspection results refined the estimated dimensions of the materialto be bounded by a length of 10 inches, width of 0.10 inch with a conservatively estimated massof 1.0 gram. The material observed was believed to be a shaving from a portion of thesecondary side delivery tooling that had a poly (PEX) sheath. This material has a melting pointless than 300 degrees Fahrenheit and therefore will melt during operation and disperse throughthe 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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