AEP-NRC-2014-10, Supplemental Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 5.5.14, Containment Leakage Rate Testing Program, to Use NEI-94-01, Revision 3-A.

Supplemental Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 5.5.14, Containment Leakage Rate Testing Program, to Use NEI-94-01, Revision 3-A.

ML14352A232
Person / Time
Site:	Cook
Issue date:	12/16/2014
From:	Gebbie J American Electric Power, Indiana Michigan Power Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2014-100
Download: ML14352A232 (4)

Text

INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant p'hIWER One Cook Place Bridgman, MI 49106 A unit ofAmerican Electric Power Indiana Michiga nPower.com December 16, 2014 AEP-NRC-2014-100 10 CFR 50.90 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 Supplemental Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 5.5.14, "Containment Leakage Rate Testing Program," to use NEI-94-01, Revision 3-A as Regulatory Guidance Versus the Current NEI 94-01, Revision 0

References:

1. Letter from J. P. Gebbie, Indiana Michigan Power Company (I&M), to U. S. Nuclear Regulatory Commission (NRC), "Donald C. Cook Nuclear Plant Units 1 and 2, License Amendment Request to Revise Technical Specification 5.5.14, 'Containment Leakage Rate Testing Program'," AEP-NRC-2014-09, dated March 7, 2014, Agencywide Documents Access and Management System (ADAMS) Accession No. ML14071A435.

2. Email from T. A. Beltz, NRC, to H. L. Etheridge, I&M, "Draft Requests for Additional Information Mechanical & Civil Engineering Branch of the Office of Nuclear Reactor Regulation Regarding a License Amendment Request for the Donald C. Cook Nuclear Plant, Units 1 and 2, to Revise Technical Specification Section 5.5.14. "Containment Leakage Rate Testing Program" Indiana Michigan Power Company Docket Nos. 50-315 and 50-316 (TAC Nos. MF3568 and MF3569),"

dated August 25, 2014.

3. Email from T. A. Beltz, NRC, to H. L. Etheridge, I&M, "Draft Requests for Additional Information Mechanical & Civil Engineering Branch of the Office of Nuclear Reactor Regulation Regarding a License Amendment Request for the Donald C. Cook Nuclear Plant, Units 1 and 2, to Revise Technical Specification Section 5.5.14. "Containment Leakage Rate Testing Program" Indiana Michigan Power Company Docket Nos. 50-315 and 50-316 (TAC Nos. MF3568 and MF3569),"

dated August 26, 2014.

U. S. Nuclear Regulatory Commission AEP-NRC-2014-100 Page 2

4. Letter from J. P. Gebbie, I&M, to NRC, "Donald C. Cook Nuclear Plant Units 1 and 2 Response to a Request for Additional Information Regarding the License. Amendment Request to Revise Technical Specification 5.5.14, "Containment Leakage Rate Testing Program," to use NEI-94-01, Revision 3-A as Regulatory Guidance Versus the Current NEI 94-01, Revision 0,"

AEP-NRC-2014-73, dated September 30, 2014, ADAMS Accession No. ML14275A454.

This letter provides Indiana Michigan Power Company's (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP) Units 1 and 2, supplemental response to Requests for Additional Information (RAI) by the U. S. Nuclear Regulatory Commission (NRC) regarding a license amendment request to change Technical Specification (TS) Section 5.5.14, "Containment Leakage Rate Testing Program."

By Reference 1, I&M submitted a request to amend the TS to Facility Operating Licenses DPR-58 and DPR-74. I&M proposes to change TS 5.5.14, "Containment Leakage Rate Testing Program,"

to use Nuclear Energy Institute (NEI) 94-01, Revision 3-A as regulatory guidance versus the current NEI 94-01, Revision 0. By Reference 2, the NRC transmitted RAIs (RAI-EMCB-1,-2,-3, and -4) regarding the proposed amendment. By Reference 3, the NRC transmitted an additional RAI (RAI-SCVB-1) regarding the proposed amendment. Reference 4 provided I&M's response to References 2 and 3, but also included a new commitment for I&M to provide results of examinations related to the condition described in RAI-EMCB-1 (Reference 2) to the NRC. These examinations were to be performed during CNP's U1C26 refueling outage. This letter provides the remainder of I&M's response to RAI-EMCB-1 (Reference 2). The enclosure to this letter provides an affirmation statement.

Supplemental Response to RAI-EMCB-1 During the fall 2014 U1C26 refueling outage, an augmented VT-1 visual examination was performed on Unit 1 containment penetration 1-CPN-56. The VT-1 examination revealed no change from the previous examination performed in the 2011 ULC24 refueling outage.

There was minor pitting on the west side of the penetration with less than 1/32 inch (")

material loss and minor pitting on the non-safety related weld pressurization channel with less than 1/16" material loss. Additional ultrasonic testing thickness readings were taken on the penetration at 45 degree (0) increments from top dead center with the lowest reading at 1800 (bottom) 0.486". The examination results were evaluated as acceptable and did not impact the leak tightness or structural integrity of the Unit 1 containment structure.

Copies of this letter and its enclosure are being transmitted to the Michigan Public Service Commission and Michigan Department of Environmental Quality, in accordance with the requirements of 10 CFR 50.91. There are no new or revised 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 JMT/amp

U. S. Nuclear Regulatory Commission AEP-NRC-2014-100 Page 3

Enclosure:

Affirmation c: M. L. Chawla, 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-2014-100 AFFIRMATION I, Joel P. Gebbie, being duly sworn, state that I am Site Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the U. S. Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.

Indiana Michigan Power Company Joel P. Gebbie Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS DAY OF Z p__.[\)o,(, 2014 M m otary Public(_)

My Commission Expires QdallQ106*