ML060230452

License Amendment, Issuance of Amendments to Delete the Power Range Neutron Flux High Negative Rate Trip Function

ML060230452
Person / Time
Site:	Cook
Issue date:	02/10/2006
From:	Tam P Plant Licensing Branch III-2
To:	Nazar M Indiana Michigan Power Co
Shared Package
ML060410600	List: ML060230452 ML060440022
References
TAC MC8805, TAC MC8806
Download: ML060230452 (13)

Text

February 10, 2006 Mr. Mano K. Nazar Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106

SUBJECT:

DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO DELETE THE POWER RANGE NEUTRON FLUX HIGH NEGATIVE RATE TRIP FUNCTION (TAC NOS. MC8805 AND MC8806)

Dear Mr. Nazar:

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 293 to Renewed Facility Operating License No. DPR-58, and Amendment No. 275 to Renewed Facility Operating License No. DPR-74 for Donald C. Cook Nuclear Plant, Units 1 and 2. The amendments change the Technical Specifications in response to your application dated August 10, 2005.

The amendments deleted the power range neutron flux high negative rate trip function from Table 3.3.1-1, Reactor Trip System Instrumentation.

A copy of the associated safety evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

/RA/

Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316

Enclosures:

1. Amendment No. 293 to DPR-58

2. Amendment No. 275 to DPR-74

3. Safety Evaluation cc w/encls: See next page

February 10, 2006 Mr. Mano K. Nazar Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106

SUBJECT:

DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS TO DELETE THE POWER RANGE NEUTRON FLUX HIGH NEGATIVE RATE TRIP FUNCTION (TAC NOS. MC8805 AND MC8806)

Dear Mr. Nazar:

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 293 to Renewed Facility Operating License No. DPR-58, and Amendment No. 275 to Renewed Facility Operating License No. DPR-74 for Donald C. Cook Nuclear Plant, Units 1 and 2. The amendments change the Technical Specifications in response to your application dated August 10, 2005.

The amendments deleted the power range neutron flux high negative rate trip function from Table 3.3.1-1, Reactor Trip System Instrumentation.

A copy of the associated safety evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

/RA/

Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316

Enclosures:

1. Amendment No. 293 to DPR-58

2. Amendment No. 275 to DPR-74

3. Safety Evaluation cc w/encls: See next page DISTRIBUTION PUBLIC T. Boyce (DRIP/IROB) G. Hill(2) LPLIII-1 r/f OGC E. Duncan, RIII ACRS P. Tam T. Harris S. Sun Package Accession Number: ML060410600 Amendment Accession Number: ML060230452 Tech Spec Accession Number: ML060440022 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/SPWB/BC OGC NRR/LPL3-1/BC(A)

NAME PTam THarris JNakoski* MSpencer TKobetz DATE 1/27/06 1/26/06 1/11/06* 2/6/06 2/10/06

• Safety evaluation of 1/11/06 used substantially unaltered.

OFFICIAL RECORD COPY

INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 293 License No. DPR-58

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Indiana Michigan Power Company (the licensee) dated August 10, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-58 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 293, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Timothy J. Kobetz, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 10, 2006

ATTACHMENT TO LICENSE AMENDMENT NO. 293 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Replace the following page of Appendix A, "Technical Specifications," with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 3.3.1-11 3.3.1-11

INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 275 License No. DPR-74

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Indiana Michigan Power Company (the licensee) dated August 10, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Renewed Facility Operating License No. DPR-74 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and Appendix B, as revised through Amendment No. 275, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Timothy J. Kobetz, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 10, 2006

ATTACHMENT TO LICENSE AMENDMENT NO. 275 RENEWED FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Replace the following page of Appendix A, "Technical Specifications," with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 3.3.1-11 3.3.1-11

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 293 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-58 AND AMENDMENT NO. 275 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316

1.0 INTRODUCTION

By application dated August 10, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML052300238), Indiana Michigan Power Company (the licensee) requested amendments to the Technical Specifications (TSs) for the Donald C. Cook (D. C. Cook) Nuclear Plant, Units 1 and 2. The proposed amendments would delete the power range neutron flux high negative rate trip function from Table 3.3.1-1, Reactor Trip System Instrumentation.

The licensee stated that the proposed change would allow elimination of an unnecessary trip function and thereby reduce the potential for a transient due to reactor shutdown in meeting TS requirements for a limiting condition for operation (LCO) of the trip function. The Nuclear Regulatory Commission (NRC) staffs review of the application is set forth below.

2.0 REGULATORY EVALUATION

The following regulatory requirements are applicable to the proposed TS changes discussed in the license amendment application.

General design criterion (GDC) 10, Reactor Design, in Appendix A to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, requires that the reactor core and associated coolant, control and protection system be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.

Also, the NRCs regulatory requirements related to the content of TSs are set forth in 10 CFR 50.36, Technical Specifications. Specifically, 10 CFR 50.36(c)(2)(ii) specifies four screening criteria to be used in determining whether an LCO is required to be included in the TSs:

Criterion 1 - Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary (RCPB);

Criterion 2 - A process variable, design feature, or operating restriction that is an initial condition of a design-basis accident (DBA) or transient analysis that either assumes the failure of, or presents a challenge to, the integrity of a fission product barrier; Criterion 3 - A structure, system or component (SSC) that is part of the primary success path, and which functions or actuates to mitigate a DBA or transient that either assumes the failure of, or presents a challenge to, the integrity of a fission product barrier; and Criterion 4 - An SSC which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.

The licensee proposed to delete the power range neutron flux high negative rate trip function from the D. C. Cook TSs. The NRC staff evaluation of the licensees proposed change was predicated upon continued compliance with the GDC 10 requirements and the screening criteria specified in 10 CFR 50.36.

3.0 TECHNICAL EVALUATION

The power range neutron flux high negative rate trip function was designed as part of the reactor protection system (RPS) to mitigate the consequences of one or more dropped rod cluster control assemblies (RCCAs) event. The dropped RCCAs event is an anticipated operational occurrence, and is caused by a single electric or mechanical failure that results in a number and combination of RCCAs from the same group of a given bank to drop to the bottom of the core. The resulting negative reactivity insertion causes nuclear power to quickly decrease and core radial peaking factors to increase. The reduced power and continued steam generation cause the reactor coolant temperature to decrease. In the manual control mode, the positive reactivity feedback due to dropping temperature causes the reactor power to rise to initial power level at a reduced reactor vessel inlet temperature with no power overshoot. In the automatic control mode, the plant control system detects the reduction in core power and initiates control bank withdrawal in order to restore core power. As a result, power overshoot occurs, resulting in lower calculated departure from nucleate boiling ratios (DNBRs). At higher power levels, in the event of a dropped RCCA event, the RPS will detect the rapidly decreasing neutron flux due to the dropped RCCAs and trip the reactor based on the power range neutron flux high negative rate trip function, thus ending the transient and assuring that DNBR design limits are maintained. Since the dropped RCCA event is an anticipated operational occurrence, it must be shown that to satisfy GDC 10 requirements, the DNBR design limits are met for the combination of high nuclear power, high radial peaking factor, and other system conditions that exist following the dropped RCCA event.

In a topical report WCAP-10297-P-A, Dropped Rod Methodology for Negative Flux Rate Trip Plants (see ADAMS Accession No. 8304140120) Westinghouse documented a methodology for the analysis of the dropped RCCA event and concluded that the high negative flux rate trip was required only when a dropped RCCA (or RCCA bank) exceeded the threshold value of reactivity worth. Any dropped RCCA having a worth below the threshold value would not

require an automatic reactor trip to satisfy the DNBR limit. The A in the reference number of the topical report indicates that it had been previously approved by the NRC staff.

By letter dated April 25, 1990, the Westinghouse Owners Group submitted an updated topical report WCAP-11394-P-A, Methodology for the Analysis of the Dropped Rod Event (see ADAMS Accession No. 9005090249). This methodology provides a means to be used to demonstrate that DNBR limits are met during a dropped RCCA event. The analysis using this methodology takes no credit for any direct trip due to the dropped RCCAs, and assumes that no automatic power reduction features are actuated by the dropped RCCAs. The conclusion reached in WCAP-11394-P-A was that sufficient margin is available in all Westinghouse core designs and fuel types, such that the high negative flux rate trip is not required, regardless of the worth of the dropped RCCA (or bank), subject to a plant cycle-specific analysis. The NRC had previously reviewed the Westinghouse analysis and result (as is indicated by the A in the reference number), and concluded that the approach in WCAP-11394-P-A was acceptable for analyzing the dropped RCCAs event for which no credit is taken for any direct trip or automatic power reduction features. In the approval, the NRC noted that further review by the NRC staff for each cycle is not necessary, subject to a licensee verification that the analysis described in WCAP-11394-P-A has been performed, and the comparison specified in the topical report has been made and favorable results were obtained.

In support of the proposed amendment, the licensee reviewed the D. C. Cook safety analyses of record and confirmed that:

(1) The power range neutron flux high negative rate trip is not credited in the loss-of-coolant accident (LOCA) and LOCA-related analyses, the containment integrity analysis, the main steamline break mass and energy release analysis, steam generator tube rupture analysis, and control system analysis. The non-LOCA analyses do not take credit for the power range neutron flux high negative rate trip function. The analysis of record for the dropped RCCA event was performed using the methods in WCAP-11394-P-A.

(2) The power range neutron flux high negative rate trip has no impact on the safety system setpoints, the emergency operating procedures, and the reactor coolant system component integrity.

Based on its review of the licensees evaluation discussed above, the NRC staff agrees with the licensee that the proposed deletion of the power range neutron flux high negative rate trip function does not affect the analyses for design basis events, nor have an impact on safety system setpoints, procedures, or reactor coolant system component integrity.

In addition, the NRC staff finds that the deletion of the power range neutron flux high negative rate trip function from the TSs satisfies the four screening criteria specified in 10 CFR 50.36(c)(2)(ii) for TS LCO, since the subject trip function is:

(a) Not an installed instrumentation used to detect and indicate a significant abnormal degradation of the RCPB (Criterion 1);

(b) Not a process variable, design feature, or operating restriction that is an initial condition of a DBA or transient analysis (Criterion 2);

(c) Not an SSC that is part of the primary success path and which functions or actuates to mitigate a DBA or transient (Criterion 3);

(d) Not an SSC which operating experience or probabilistic risk assessment has shown to be significant to public health and safety (Criterion 4).

Therefore, the NRC staff finds it acceptable to delete the power range neutron flux high negative rate trip function from Table 3.3.1-1.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendments. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (70 FR 72674). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: S. Sun Date: February 10, 2006

Donald C. Cook Nuclear Plant, Units 1 and 2 cc:

Regional Administrator, Region III Michigan Department of Environmental U.S. Nuclear Regulatory Commission Quality Suite 210 Waste and Hazardous Materials Div.

2443 Warrenville Road Hazardous Waste & Radiological Lisle, IL 60532-4351 Protection Section Nuclear Facilities Unit Attorney General Constitution Hall, Lower-Level North Department of Attorney General 525 West Allegan Street 525 West Ottawa Street P. O. Box 30241 Lansing, MI 48913 Lansing, MI 48909-7741 Township Supervisor Lawrence J. Weber, Plant Manager Lake Township Hall Indiana Michigan Power Company P.O. Box 818 Nuclear Generation Group Bridgman, MI 49106 One Cook Place Bridgman, MI 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office Mr. Joseph N. Jensen, Site Vice President 7700 Red Arrow Highway Indiana Michigan Power Company Stevensville, MI 49127 Nuclear Generation Group One Cook Place James M. Petro, Jr., Esquire Bridgman, MI 49106 Indiana Michigan Power Company One Cook Place Bridgman, MI 49106 Mayor, City of Bridgman P.O. Box 366 Bridgman, MI 49106 Special Assistant to the Governor Room 1 - State Capitol Lansing, MI 48909 Mr. John A. Zwolinski Safety Assurance Director Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106