AEP-NRC-2014-79, Supplemental Response to a Request for Additional Information Regarding the License Amendment Request to Change the Reactor Coolant System Pressure and Temperature Limits

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Supplemental Response to a Request for Additional Information Regarding the License Amendment Request to Change the Reactor Coolant System Pressure and Temperature Limits
ML14273A258
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 09/25/2014
From: Gebbie J
American Electric Power, Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2014-79
Download: ML14273A258 (4)
v • d • e


Text

INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWERO One Cook Place A unit ofAmerican Electric Power Indiana Michigan Power1com September 25, 2014 AEP-NRC-2014-79 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 Change the Reactor Coolant System Pressure and Temperature Limits

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 Unit 1 and Unit 2, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits," AEP-NRC-2014-24, dated April 9, 2014, Agencywide Documents Access and Management System (ADAMS) Accession No. ML14101A367.
2. Email from T. A. Beltz, NRC, to H. L. Etheridge, I&M, "Draft Requests for Additional Information Vessels & Internals Integrity Branch and Technical Specifications Branch of the Office of Nuclear Reactor Regulation Regarding the Donald C. Cook Nuclear Plant, Units 1 and 2, License Amendment Request to Change Reactor Coolant System Pressure and Temperature Limit Curves to Address Vacuum Fill Operations (TAC Nos. MF4280 and MF4281)," dated July 21, 2014, ADAMS Accession No. ML14217A325.
3. Letter from J. P. Gebbie, I&M, to U. S. NRC, "Donald C. Cook Nuclear Plant Units 1 and Unit 2, Response to a Request for Additional Information Regarding the License Amendment Request to Change the Reactor Coolant System Pressure and Temperature Limits," AEP-NRC-2014-63, dated August 15, 2014, ADAMS No. ML14230A677.

By Reference 1, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant Units 1 and 2, submitted a request to amend the Technical Specifications (TS) to Facility Operating Licenses DPR-58 and DPR-74. I&M proposes to change TS 3.4.3, "RCS Pressure and Temperature (P/T) Limits," to address an issue regarding the applicability of Figure 3.4.3-1, "Reactor Coolant System Pressure versus Temperature Limits - Heatup Limit, Criticality Limit, and Leak Test Limit (Applicable for service period up to 32 EFPY)" and Figure 3.4.3-2, "Reactor Coolant System Pressure versus Temperature Limits - Various Cooldown Rates Limits (Applicable for

U. S. Nuclear Regulatory Commission AEP-NRC-2014-79 Page 2 service period up to 32 EFPY)," during vacuum fill of the Reactor Coolant System.

By Reference 2, the Nuclear Regulatory Commission (NRC) transmitted a Request for Additional Information (RAI) regarding the proposed amendment. By Reference 3, I&M provided a response to Reference 2.

In Reference 3, as part of the response to RAI-EVIB-1, I&M proposed to add a License Condition to both the Unit 1-and Unit 2 License. Subsequent to submitting Reference 3 to the NRC, I&M has determined additional specificity is needed in the language of the proposed License Condition. I&M proposes the following License Condition be added to Unit 1 and Unit 2 Facility Operating Licenses DPR-58 and DPR-74 in response to RAI-EVIB-1 in Reference 2:

Unit 1:

"Operation with vacuum fill:

The licensee is authorized to operate the facility using Reactor Coolant System (RCS) vacuum fill operation in accordance with TS 3.4.3, "RCS Pressure and Temperature (P/T) Limits," with corresponding revisions to Figure 3.4.3-1, "Reactor Coolant System Pressure versus Temperature Limits - Heatup Limit, Criticality Limit, and Leak Test Limit (Applicable for service period up to 32 EFPY)," and Figure 3.4.3-2, "Reactor Coolant System Pressure versus Temperature Limits -

Various Cooldown Rates Limits (Applicable for service period up to 32 EFPY)," as approved in License Amendment No. _

to Renewed Facility Operating License No. DPR-58. This includes an approved extension to -14.7 pounds per square inch gage to bound the RCS conditions required to support vacuum fill operation. The licensee shall submit an analysis of the P/T curves in Figures 3.4.3-1 and 3.4.3-2 within one year of the date of issuance of License Amendment No. _,

which demonstrates consideration of all ferritic reactor vessel materials as defined in Appendix G to 10 CFR Part 50, including non-beltline ferritic reactor vessel materials."

Unit 2:

"Operation with vacuum fill:

The licensee is authorized to.operate the facility using Reactor Coolant System (RCS) vacuum fill operation in accordance with TS 3.4.3, "RCS Pressure and Temperature (P/T) Limits," with corresponding revisions to Figure 3.4.3-1, "Reactor Coolant System Pressure versus Temperature Limits - Heatup Limit, Criticality Limit, and Leak Test Limit (Applicable for service period up to 32 EFPY)," and Figure 3.4.3-2, "Reactor Coolant System Pressure versus Temperature Limits -

Various Cooldown Rates Limits (Applicable for service period up to 32 EFPY)," as approved in License Amendment No.

to Renewed Facility Operating Licens6 No. DPR-74. This includes an approved extension to -14.7 pounds per square inch gage to bound the RCS conditions required to support vacuum fill operation. The licensee shall submit an analysis of the P/T curves in Figures 3.4.3-1 and 3.4.3-2 within one year of the date of issuance of License Amendment No. _,

which demonstrates consideration of all ferritic reactor vessel materials as defined in Appendix G to 10 CFR Part 50, including non-beltline ferritic reactor vessel materials." to this letter provides an affirmation statement.

U. S. Nuclear Regulatory Commission AEP-NRC-2014-79 Page 3 Copies of this letter and its enclosures 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 regulatory commitments associated with this response. 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 TLC/kmh Enclosure 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 to AEP-NRC-2014-79 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

, 2014 My CmNm Publir

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DANIELLE BURGOYNE Notary Public, State of Michigan County of Berrien My Commission Expires 04-.%4-2018 Acting In the County of

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