View source for AEP-NRC-2011-25, Change to Proposed Technical Specification Page Regarding Large-Break Loss-Of-Coolant Accident Analysis Approval

{{Adams
| number = ML110950162
| issue date = 03/25/2011
| title = Change to Proposed Technical Specification Page Regarding Large-Break Loss-Of-Coolant Accident Analysis Approval
| author name = Carlson M
| author affiliation = Indiana Michigan Power Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000316
| license number = 
| contact person = 
| case reference number = AEP-NRC-2011-25, TAC ME1017
| document type = Letter type:AEP
| page count = 5
| project = TAC:ME1017
| stage = Other
}}

=Text=
{{#Wiki_filter:INDIANA MICHIGAN                                                                                  Indiana Michigan Power One Cook Place POWER                                                                                     Bridgman, MI 49106 A unit of American ElectricPower                                                           IndianaMichigan Powercom March 25, 2011                                                                         AEP-NRC-2011-25 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

==SUBJECT:==
Change to Proposed Technical Specification Page Regarding Large-Break Loss-Of-Coolant Accident Analysis Approval (TAC No. ME1017)

==References:==
: 1) Letter from L. J. Weber, Indiana Michigan Power Company (A&M), to U.S.
Nuclear    Regulatory   Commission     (NRC)    Document     Control         Desk, "Donald C. Cook Nuclear Plant Unit 2, Docket No. 50-316, License Amendment Request    Regarding   Large   Break Loss-of-Coolant     Accident Analysis Methodology," AEP-NRC-2009-23, dated March 19, 2009 (ADAMS Accession Number ML090930453).
: 2) Letter from L. J. Weber, I&M, to NRC Document Control Desk, "Donald C. Cook Nuclear Plant Unit 2, Docket No. 50-316, Response to Request for Additional Information Regarding a License Amendment Request Associated With the
* Large-Break. Loss-Of-Coolant Accident Analysis Methodology (TAC No.
ME1017)," AEP-NRC-2009-71, dated November 20, 2009 (ADAMS Accession Number ML093360524).

==Dear Sir or Madam:==

By Reference 1, Indiana Michigan Power Company (I&M) proposed to amend Appendix A, Technical Specifications (TS), to the Donald C. Cook Nuclear Plant (CNP) Unit 2 Facility Operating License, DPR-74. A&M requested NRC approval to adopt a new analysis of a postulated large break loss-of-coolant accident (LBLOCA) for CNP Unit 2, and proposed to modify the associated TSs. By Reference 2, I&M provided a response to an NRC Request for Additional Information (RAI) regarding the proposed amendment. Enclosure 5 of Reference 2 provided a revision of the mark-up of TS Page 5.6-3 originally transmitted by Reference 1. This letter transmits a mark-up of TS Page 5.6-3 with an additional change such that it refers to the expected amendment number and provides a location for the amendment date. Enclosure 1 to this letter provides an affirmation statement. Enclosure 2 provides the mark-up of TS Page 5.6-3.
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U. S. Nuclear Regulatory Commission                                             AEP-NRC-2011-25 Page 2 Copies of this letter and its enclosures are being transmitted to the Michigan Public Service Commission and the Michigan Department of Natural Resources and Environment, in accordance with the requirements of 10 CFR 50.91. This letter contains no new or modified NRC commitments.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Sincerely, Mihal .        arlo       QJ&#xfd;             -
Michael H. Carlson Site Support Services Vice President JRW/jmr

==Enclosures:==
: 1. Affirmation
: 2. Mark-up of Donald C. Cook Nuclear Plant Unit 2 Technical Specification Page 5.6-3 c:     J. T. King, MPSC S. M. Krawec, Ft. Wayne AEP, w/o enclosures MDNRE - WHMD/RPS NRC Resident Inspector M. A. Satorius, NRC Region III P. S. Tam, NRC, Washington DC

Enclosure 1 to AEP-NRC-2011-25 AFFIRMATION I, Michael H. Carlson, being duly sworn, state that I am Site Support Services Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the 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 Michael H. Carlson Site Support Services Vice President SWORN TO AND SUBSCRIBED BEFORE ME
       '  k,..___. Notar&#xfd; Puglic My Commission Expires T E PATFRCIA ANN EDDI NoAeky PljbfIcalie M,;chiqan Cr~&#xfd;'-nbfof  r'o    .
MY Cornr~:.n      -x            4 G. 20I

Enclosure 2 to AEP-NRC-2011-25 Mark-up of Donald C. Cook Nuclear Plant Unit 2 Technical Specification Page 5.6-3

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5    CORE OPERATING LIMITS REPORT (COLR) (continued)
: 5. LCO 3.1.6, "Control Bank Insertion Limits";
: 6. LCO 3.2.1, "Heat Flux Hot Channel Factor (FQ(Z))";
: 7. LCO 3.2.2, "Nuclear Enthalpy Rise Hot Channel Factor (FaNH)";
: 8. LCO 3.2.3, "AXIAL FLUX DIFFERENCE (AFD)";
: 9. LCO 3.3.1, "Reactor Trip System (RTS) Instrumentation," Functions 6 and 7 (Overtemperature AT and Overpower AT, respectively)
Allowable Value parameter values;
: 10. LCO 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits"; and
: 11. LCO 3.9.1, "Boron Concentration."
: b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
: 1. WCAP-9272-P-A, 'Westinghouse Reload Safety Evaluation Methodology," (Westinghouse Proprietary);
: 2. WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," (Westinghouse Proprietary);
: 3. WCAP-1 0216-P-A, "Relaxation of Constant Axial Offset Control/F0 Surveillance Technical Specification," (Westinghouse Proprietary);
: 4. WGAP 10266 P A, "The 198 1 Version of Westinnghouse EYaluation
                          .adaptation (approved by Amendment 297, dated XXXXX XX, 2011) ot WCAP-16009-P-A, "Realistic rLarge-Break LOCA Evaluation]
Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," Revision 0 (Westinghouse Proprietary), approvedl bY letter from H. N. Berkow, NRC, to J. A. Gresham, Westinghousel Electric Company, dated November 5, 2004;
: 5. WCAP-1 261 0-P-A, "VANTAGE+ Fuel Assembly Reference Core Report," (Westinghouse Proprietary);
: 6. WCAP-8745-P-A, "Design Bases for the Thermal Overpower AT and Thermal Overtemperature AT Trip Functions," (Westinghouse Proprietary); and 5.6-3                  Amendment No. 26Q, 270, Cook Nuclear         Unit 2 Plant Unit Nuclear Plant       2                     5.6-3                  Amendment No. 2-69, 270,}}