ML20138J713
| ML20138J713 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/05/1997 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20138J715 | List: |
| References | |
| NPF-06-A-183 NUDOCS 9705080303 | |
| Download: ML20138J713 (5) | |
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 3086 Hoot o
'+9.....,o ENTERGY OPERATIONS. INC.
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.183 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated December 19, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.
There is reasonable assurance:
(1) 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements
.have been satisfied.
9705080303 970505 PDR ADOCK 05000368 p
. 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 Facility Operating License No. NPF-6 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 183, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance to be implemeted within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
%f Mc George Kalman, Senior Project Manager Project Directorate IV-I i
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 5, 1997
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ATTACHMENT TO LICENSE AMENDMENT NO.183 FACILITY ODERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 l
Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 3/4 3-8 3/4 3-8 3/4 3-9 3/4 3-9 h
p.
TABLE 4.3-1 (Continued)
TABLE NOTATIONS With reactor trip breakers in the closed position and the CEA drive system capable of CEA withdrawal.
(1)
If not performed in previous 7 days.
(2)
Heat balance only (CHANNEL FUNCTIONAL TEST not included):
a.
Between 15% and 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC AT power, and the CPC nuclear power signals to the calorimetric calculation.
If any signal is within -0.5% to +10% of the calorimetric calculation, then do not calibrate except as required during initial power ascension following refueling.
If any signal is less than the calorimetric calculation by more
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than 0.5%, then. adjust the affected signal (s) to within 0.0% to
+10.0% of the calorimetric calculation.
If any signal is greater than the calorimetric calculation by more than 10%, then adjust the affected signal (s) to within 8%
to 10% of the calorimetric calculation.
b.
At or above 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC AT power, and CPC nuclear power signals to the calorimetric calculation.
If any signal differs from the calorimetric calculation by an absolute difference of > 2%,
then adjust the affected signal (s) to within i 2% of the calorimetric calculation.
During PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each rajor test power plateau and prior to proceeding to the next major test power plateau.
(3)
Above 15% of RATED THERMAL POWER, verify that the linear power subchannel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators.
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(4)
(5)
After each fuel loading and prior to exceeding 70% of RATED THERMAL POWER, the incore detectors shall be used to determine the shape annealing matrix elements and the Core Protection calculators shall use these elements.
(6) -
This CHANNEL FUNCTIONAL TEST shall include the injection of i
simulated process signals into the channel as close to the sensors as practicable to verify OPERABILITY including alarm and/or trip functions.
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ARKANSAS - t.4IT 2 3/4 3-8 smendment No. G4,48,47,183 4
(7)
Above 70% of RATED THERMAL POWER, varify thst tha total RCS flow l
rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either using the reactor coelant pump differential pressure instrumentation l
(conservatively compensate for measurement uncertainties) or by j
calorimetric calculations (conservatively compensated for 1
measurement uncertainties) and if necessary, adjust the CPC addressable constant flow coefficients such that each CPC indicated flow is less than or equal to the actual flow rate.
The flow measurement uncertainty may be included in the BERR1
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term in the CPC and is equal to or greater than 4%.
1 (8) -
Above 70% of RATED THERMAL POWER, verify that the total ROS flow rate as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by calorimetric calculations (conservatively compensated for umasurement uncertainties).
1 The correct values of addressable constants shall be verified to (9) be installed in each OPERABLE CPC.
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ARKANSAS - UNIT 2 3/4 3<9 Amendment No G4,49,44,183