ML17333A256
| ML17333A256 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 01/04/1996 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17333A257 | List: |
| References | |
| NUDOCS 9601170071 | |
| Download: ML17333A256 (10) | |
Text
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~O UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANA HICHIGAN POWER COHPANY N
TNT N
DONALD C.
COOK NUCLEAR PLANT UNIT NO.
1 HENDHENT TO FACILITY OPERATING LICENSE Amendment No. 206 License No.
DPR-58 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Hichigan Power Company (the licensee) dated Hay 25, 1995, 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.
960117007k
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P PDR
2.
'Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to thi.s license amendment, and par agraph 2.C.(2) of Facility Operating License No.
DPR-58 is hereby amended to read as follows:
Technical S eci ications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 206
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, with full implementation within 45 days.
'FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 4,
1996 ohn B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT N0.206 TO FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 2-15 6-17 INSERT 3/4 2-15 6-17
3/4.0 LIMITINGCONDITION FOR OPERATION AND SURVEILLANCEREQUIREMENTS 3/4.2 POWER DISTRIBUTIONLIMITS A LOWABLEPOWER LEVEL-APL LIMITINGCONDITION FOR OPERATION 3.2.6 THERMALPOWER shall be less than or equal to ALLOWABLEPOWER LEVEL(APL), given by the following relationships:
APL = min over Z o 00%, or 100%, whichever is less.
CFQ x K(Z)
CFQ is the F< limit at RATED THERMAL POWER specified in the COLR for Westinghouse or Exxon fuel.
F~(Z) is the measured hot channel factor including a 3% manufacturing tolerance uncertainty and a 5% measurement uncertainty.
V(Z) is the function specified in the COLR.
Fp =
1.00 except when successive steady-state power distribution maps indicate an increase in max over Z of with exposure.
Fg(Z)
~KZ Then either of the penalties, Fp, shall be taken:
Fp =
Fp =
butnup dependent penalty specified in the COLR, or 1.00 provided that Surveillance Requirement 4.2.6.2 is satisfied once per 7 Effective Full Power Days until two successive maps indicate that the max over Z of is not increasing.
Fg (Z) o The above limit is not applicable in the following core regions.
I)
Lower core region 0% to 10% inclusive.
2)
Upper core region 90% to 100% inclusive.
APPLICABILITY'ODE1 COOK NUCLEAR PLQ T-Pi1T 1 Page 3/4 2-15 AMENDiWIENT%, 4A, 4A, 446 206
6.0 ADMINISTRATIVECONTROLS MONTHLYREACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITSREPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
a.
Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.
Rod Drop Time Limits for Specification 3/4.1.3.3, c.
Shutdown Rod Insertion Limits for Specification 3/4.1.3.4, d.
Control Rod Insertion Limits for Specification 3/4.1.3.5, e.
Axial Flux Difference for Specification 3/4.2.1, f.
Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.
Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.
Allowable Power Level for Specification 3/4.2.6.
'6'9 'I 9;2 lThe analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
a.
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985
{Westinghouse Proprietary),
WCAP-8385, "Power Distribution Control and Load Following Procedures
- Topical Report," September 1974 (Westinghouse Proprietaty),
WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control / F~
.Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),
WCAP-10266-P-A Rev. 2, The 1981 Version ofWestinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
COOK NUCLEAR PLANT-UNITI Page 6-17 AMENDMENT69, 464, kV4, 489 206
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UNITED STATES NUCLEAR REGULATORY COIVIMISSION WASHINGTON> D.C. 20555-0001 INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C.
COOK NUCLEAR PLANT UNIT NO.
2 MENDMENT TO FACILITY OPERATING LICENSE Amendment No.
19O License No.
DPR-74 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Indiana Michigan Power Company (the licensee) dated Hay 25,
- 1995, 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 iTI 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 beeh satisfied.
- 2. 'ccordingly, 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 Facility Operating License No.
DPR-74 is hereby amended to read as, follows:
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No.
190
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 4,
1996 John B. Hickman, Project Manager Project Directorate III-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
TTACHHENT TO LICENSE AMENDMENT NO. 19O FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 2-19 6-17 INSERT 3/4 2-19 6-17
3/4 LIMH'INGCONDITIONS FOR OPERATION ANDSURVEILLANCEREQUIREMENTS 3/4.2 POWER DISTRIBUTIONLIMITS ALLOWABLEPOWER LEVEL-APL LIMITINGCONDITION FOR'OPERATION 3.2.6 THERMALPOWER shall be less than or equal to ALLOWABLEPOWER LEVEL(APL), given by the following relationships:
APL = min over Z of F
Z V
x 100%, or 100%, whichever is less.
CFQ x K(Z)
FOZ xVZ x
CFQ is the F~ limit at RATED THERMAL POWER specified in the COLR for Westinghouse or Exxon fuel.
F<(Z) is the measured hot channel factor including a 3% manufacturing tolerance uncertainty and a 5% measurement uncertainty.
V(Z) is the function specified in the COLR.
Fp =
1.00 except when successive steady-state power distribution maps indicate an increase in max over Z of with exposure.
po (ni K n Then either of the penalties, Fp, shall be taken:
Fp =
burnup dependent penalty specified in the COLR, or 1.00 provided that Surveillance Requirement 4.2.6.2 is satisfied once per 7 Effective Full Power Days until two successive maps indicate that the max over Z of is not increasing.
Fo(z) o The above limit is not applicable in the following core regions.
1)
Lower core region 0% to 10% inclusive.
2)
Upper core region 90% to 100% inclusive.
APPLICABILITY: MODE 1 COOK NUCLEAR PLANT-UiiT2 Page 3/4 2-19 AMENDMENTat, NP, ~, 434 190
6.0 ADMINISTRATIVECONTROLS MONTHLYREACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation ofall challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITSREPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
a.
Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, b.
Rod Drop Time Limits for Specification 3/4.1.3.4, Shutdown Rod Insertion Limits for Specification 3/4.1.3.5, Control Rod Insertion Limits for Specification 3/4.1.3.6, e.
Axial Flux Difference for Specification 3/4.2.1, f.
Heat Flux Hot Channel Factor for Specification 3/4.2.2, g.
Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and h.
Allowable Power Level for Specification 3/4.2.6.
6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previous1y reviewed and approved by the NRC in:
aO WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985'Westinghouse Proprietary),
b.
WCAP-8385, "Power Distribution Control and Load Following Procedures
- Topical Report," September 1974 (Westinghouse Proprietaty),
C.
WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control / F<
Surveillance Technical Specification," Februaty 1994 (Westinghouse Proprietary),
d.
WCAP-10266-P-A Rev. 2, The 1981 Version ofWestinghouse Evaluation Mode Using BASH Code, March 1987 (Westinghouse Proprietary).
COOK NUCLEAR PLAINT-UNIT2 Page 6-17 AMENDMENT$4, 438) 487,~
190