ML20085F047
| ML20085F047 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/16/1991 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20085F048 | List: |
| References | |
| NPF-06-A-126 NUDOCS 9110220016 | |
| Download: ML20085F047 (5) | |
Text
,,
+[it* ** %o,,
UNITED STATES
-[
'.ca NUCLEAR HEGULATORY COMMISSION e-7.
W AsHINoT ON, D. C. 70%s e,
%,*..*,/
ENTERGY OPERATIONS, INC.
DOCKET NO. $0*368 ARKANSAS NUCLEAR ONE, UNIT NO. 2 MENDMENT TO FACILITY OPERATlHG LICENSE Ac.endment No.126 License No. NPF-6 1.
lhe Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc.
(the licensee) dated February 25, 1991, 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 i, 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of tre Act, and the rules and regulations of the Commission; C.
There is r0asonable assurance:
(i) that the activities authorized by this amendu nt can be conducted without endangering the health and safety of the public, end (ii) that such activities will be conducted in complianc.e with the Commission's regulations; D.
The issucce of this license sm?ndment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The isi9ance of this amendment in in accordance with 10 CFR Part 51 of the Conaission's regulations and all applicable requirements have been satisfied.
[1[2$0h$ b >
[
1 P
4 g
.g.
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:
i 2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 126, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective 30 days after its date of issuance.
FOR THE NUCLEAR REGULATORY C0kHISSION y'.~/ /3..>
John T. Lartins, Director Pioject Directorate IV-1 Division of Reactor Projects Ill IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 16, 1991 1
ATTACHMENT 10_ LICENSE AMEN 0 MENT NO.126 i
FACILITY OPERATING LICENSE _NO. NPT-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment nuinber and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 3/4 1-4 7/A 1-4 8 3/4 1-1 B 3/4 1-1 4
-.-.,,nn e-
,rr<
,-,----n..
en-- - - - -
v
.-n,-,-
-ve--v,
d 4
jiE&CTIVITY CONTRQL SYSTEMS EQRON DILUTION 3.1.1.3 The flow rate of reactor coolant through the. reactor coolant system shall be 22000 gpm whenever a reduction in Reactor Coolant System l
boron concentration is being made.
APPLICABILITY: ALL MODES.
ACIION:
With the flow rate of reactor coolant through the reactor coolant system
<2000 gpm, immediately suspend all operations involving a reduction in l
boron concentration of the Reactor Coolant flyst.em, 4.1.1,3 The flow rate of reactor coolant through the reactor coolant system shall be deteroined to be 22000 gpm within one hour prior to the j
start of and at least once per hour during a reduction in the Reactor Ceolant System boron concentration by either:
a.
Verifying at least one reactor coolant pump is in operation, or b.
Verifying that at least one low pressure safety injection pump or centainment spray pump is in operation as a shutdown cooling pump and supplying e2000 gpm through the reactor coolant system.
i l
l ARKANSAS - UNIT 2 3/4 1-4 Amendment No. 126
e 3/jk1_EL&CTIVITY CONTROLMilf35 31 1 ) 1 BORATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUIDOWy3Ajg}h A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subtritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg.
The most restrictive condition occurs at EOL, with Tavg at no load operating temperature,
" t '. associated with a postulated steam line break iting uncontrolled RCS cooldown. In tae analysis of this accident, arc ee' accident, a minirum SHUTDOWN *iARGIN of 5.5% ak/k is required to control the reactivity transient.
Accordingly, the SHUTOOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With Tavg s200*F, the reactivity transients resulting from any postulated accident tre minimal and a 5% ak/k shutdown margin provides adequate protection.
3 / 4._1.1. 3 BORON DLLullDB A minimum flow rate of at least 2000 GPM provides adequate mixing, l
prevents stratification and ensures that reactivity changes will be gradual during bcron concentration reductions in the Reactor Coolant System. A flow rate of at least 2000 GPM will circulate an equivalent Reactor Coolant System volume of 6,650 cubic feet in approyimately 25 minutes. The reactivity change rate associated with boron concentration reductions will therefore be within the capat,ility of operator recognition and control.
J/_411.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC)
The limitations on MTC are provided to ensure that the av mptions used in the accident and transient analysis remain valid through each fuel cycle.
The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MIC value since this coefficient changes slowly due principally to tha reduction in RCS boron concentrations ascociated with fuel burnup.
The confirmation that the measured MTC value is within its limit provided assurances that the coef ficient will be maintained within acceptable values throughout each fuel cycle.
l ARKANSAS - UNIT 2 B 3/4 1-1 Amendment No. H, SJ, 126
-