ML20086M683
| ML20086M683 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 07/20/1995 |
| From: | Wharton L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20086M686 | List: |
| References | |
| NUDOCS 9507240414 | |
| Download: ML20086M683 (6) | |
Text
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UNITED STATES l.
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2055Hm01 p
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c UNION ELECTRIC COMPANY
_CALLAWAY PLANT. UNIT 1 DOCKET NO. 50-483 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.101 License No. NPF-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Union Electric Company (UE, the licensee) dated September 8, 1994, 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; 8.
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 Specifica-tions as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No..NPF-30 is hereby amended to read as follows:
9507240414 950720 PDR ADOCK 05000483 P
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. (2)
Technical-Soecifications and Environment'al Protection ~ Plan
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The Technical. Specifications contained in Appendix'A, as' revised z
through Amendment No.101, and the Environmental. Protection Plan i
contained in. Appendix B, both of which are attached hereto, are hereby incorporated into the license.
UE shall operate.the facility.
in accordance with the Technical Specifications and the l Environmental Protection Plan.
-3.
This license amendment is effective as of its date of issuance.
The Technical Specifications are to be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/
4 L. Raynard Wharton, Project Manager l
Project Directorate 111-3 Division of Reactor. Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications l
Date of issuance:
iluly 20, 1995 t
1 i
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ATTACHMENT TO LICENSE AMENDMENT N0.101 OPERATING LICENSE N0. NPF-30 DOCKET NO. 50-483 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
t REMOVE INSERT 3/4 2-7 3/4 2-7 3/4 2-7(b) 3/4 2-7(b) 1 6-21a 6-21a i
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y POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.'2 (Continued) e.
With measurements.. indicating maximum Fj'(2) over z.
gg )
has increased since the previous determination of F,"(z), either;of the following actions shall be taken:
1.
F "(2) shall be increased over that specified in Specification o
4.2.2.2c, by an appropriate factor specified in the COLR, or 2.
F "(z) shall be measured at least once per 7 Effective Full Power D,ays until two successive maps indicate that maximum Fj'(:)
is not increasing.
over 2 gg,_,
f.
With the relationships specified in Specification 4.2.2.2c. above not being satisfied:
1.
Calculate the percent F,(z) exceeds its limit by the following expression:
F'l'(nr W(:)NO max. <nrr : q/
-1 x 100 tisr P 2 0.5 F',"'
K(:)
s t
7 F'"(:)x W(:)NO max. inrr : qf
-1 x 100 tior P < 0.5 F^[x K(:)
A 2.
Either one of the following actions shall be taken:
(a)
Within 15 minutes, control the AFD to within new AFD limits which are determined by tightening both the negative and positive AFD limits of Specification 3.2.1 by IM AFD for each percent F (z) exceeds its limits as determined in Specificationk.2.2.2.f.l.
Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />' reset the AFD alarm setpoints to these modified limits, or (b)
Comply with the requirements of Specification 3.2.2 for F,(z) exceeding its limit by the percent calculated above, or (c)
Verify that the requirements of Specification 4.2.2.3 for RESTRICTED AFD OPERATION are satisfied and enter RESTRICTED AfD OPERATION.
CALLAWAY - UNIT 1 3/4 2-7 Amendment No. 20,C,::,72.101
POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4.2.2.4 (Continued) b.
Increasing the measured F,(z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.
Verify that the requirements of Specification 3.2.2 are satisfied.
c.
Satisfying the following relationship:
F;(z) s F"" x K(z) for P > APL ^"
P x W(z)ypo where F,"(z) is the measured F,(z) increased by the allowances for manufacturing tolerances and measurement uncertainty.
K(z) is the normalized F,(z) as a function of core height.
The F, limit is F,"'.
P is the relative THERMAL POWER.
W(z),,,,, is the cycle dependent function that accounts for limited power distribution transients encountered during RAFDO.
F,"", K(z), and W(z),,,og are specified in the Core Operating Limits Report as per Specification 6.9.1.9.
d.
Measuring F,"(z) in conjnnction with target flux difference determination according to the following schedule:
1.
Prior to entering RAFD0 after satisfying Section 4.2.2.3 unless a full core flux map has been taken in the previous 31 EFPD with the relative thermal power having been maintained above APL" for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to mapping, and 2.
At least once per 31 Effective Full Power Days, e.
With measurement indicating maximum F[(z) j over z g(:)
has increased since the previous determination of F,"(z) either of the following actions shall be taken:
L F,"(z) shall be increased over that specified in 4.2.2.4.c by an appropriate factor specified in the COLR, or CALLAWAY - UNIT 1 3/4 2-7(b)
Amendment No. -20,44dS,72,101
4 a
ADMINISTRATIVE CONTROLS b.
WCAP-10216-P-A, REV. I A, " RELAXATION OF CONSTANT AXI AL OFFSET CONTROL AND FQ SURVEILLANCE TECHNICAL SPECIFICATION," February 1994 (W Proprietary).
(Methodology for Specification 3.2.1 - Axial flux Difference (Relaxed Axial Offset Control) and 3.2.2 - Heat Flux Hot Channel Factor (W(Z) surveillance requirements of F, Methodology) c.
WCAP-10266-P-A, REV. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE," March 1987 (W Proprietary).
(Methodology for Specification 3.2.2. - Heat Flux Hot Channel Factor).
The core operating limits shall be determined so that all applicable limits (e.g.. fuel thermal-mechanical limits, core thermalhydraulic limits, nuclear limits such as shutdown margin. and transient and accident analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements shall be provided upon issuance for each reload cycle. to the NRC Cocument Control Desk with copies to the Regional Administrator and Resident inspector.
SPECIAL REPORTS 6.9.2 Special Reports shall be submitted to the Regional Administrator of the NRC Regional Office within the time period specified for each report.
6.10 RECORD RETENTION in addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.1 The following records shall be retained for at least 5 years:
a.
Records and logs of unit operation covering time interval at each power level:
CALLAWAY - UNIT 1 6-21a Amendment No.-20. D 5C.72.101