ML19351A375
| ML19351A375 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/12/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19351A376 | List: |
| References | |
| NPF-06-A-100 NUDOCS 8910200143 | |
| Download: ML19351A375 (5) | |
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ARKANSAS POWER AND LIGHT COMPANY c
DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 100
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License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
. A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated June 15, 1989, 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; 1
B.
The._ facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; 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 'Comission's regulations; D.
'The' issuance of this license amendment will not be inimical to the
. common defense and security or to the health end safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 i
of the Comission's regulations and all applicable requirements have been satisfied.
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8910200143 891012 PDR ADOCK 05000368 P
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Accordingly, the license is anended 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 reed as follows' 2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.100, are hereby incorporated in the license. The licensee shall operate the facility in i
accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMilISS10N
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Frederick J. Hebdon, Director Project Directorate IV Division of Reactor Projects - 111, IV, V and Special Projects Office of Huclear Reactor Rcgulation
Attachment:
Changes to the Technical Specifications Date of Issuance: October 12, 1989 0
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I' op, t TTA_CHMENT T0_ llc, ENS,E, AMEND,MEijT,,NO.100 FACl_LITY,0,PERATI,NG LICENSE NO. NPF-6 DOCKET NO. 50-3,68 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.
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i REMOVE PAGES INSERT PAGES-t 3/4 1-23 3/4 1-23 8 3/4 1-5 B 3/4 1-5 i
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REACTIVITY CONTROL SYSTEMS CEA DROP TIME
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LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual full length (shutdown and control) CEA drop time, from a fully withdrawn position, shall be 5 3.5 seconds and the arithmetic average of the CEA drop times of all full length CEAs, from a fully withdrawn position, shall be 5 3.2 seconds from when the electrical power is interrupted to the CEA drive mechanisms until the CEAs reach their 90 percent insertion positions with:
T,yg.t $25'F, and a.
b.
All reactor coolant pumps operating.
APPLICABILITY:
MODES 1 and 2.
ACTION:
1 a.
With the CEA drop times determined to exceed either of the above limits, restore the CCA drop times to within the above limits prior to proceeding to MODE 1 or 2.
b.
With the CEA drop times within limits but determined at less than full reactor coolant flow, operation may pro:eed provided THERMAL POWER is restricted to less than or equal to the maximum THERMAL l
POWER level allowable for the reacter coolant pump combination operating at the time of CEA drop time determination.
SURVEILLANCE RE0VIREMENTS 4.1.3.4 The CEA drop time of full length CEAs shall be demonstrated through measurement prior to reactor criticality:
a.
For all CEAs following each removal of the re6ctor vessel
- head, b.
For specifically affected individuals CEAs following any maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c.
At least once per 18 months.
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ARKANSAS - UNIT 2 3/4 1-23 Amendment No. 84, 9f 100
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j REACTIVITY CONTROL SYSTEMS RASES 1
l CEA positions and OPERAB]LITY of the CEA position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with more frequent verifications required if an automatic monitoring channel is inoperable.
i These verificat. ion frequencies are adequate for assuring that the applicable LCO's.are satisfied.
T 7he average CEA drop time restriction is consistent with the assumed l
CEA strop time used in the accident analysis.
The maximum CEA drop time restriction is used to limit the CEA drop time distribution about the u
average.to that used in the accident analysis.
Measurement with T k
I 525'FandwithallreactorcoolantpumpsoperatingensuresthatthlVEeasured drop times will be representative of insertion times experienced during a reactor. trip at operating conditions.
The establishment of LSSS and LCOs require that the expected long and
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short term behavior of the radial peaking factors be determined.
The long
. term behavior relates to the variation of the steady state radial peaking I
l factors with core burnup and is affected by the amount of CEA insertion assumed, the portion of a burnup cycle over which sa:h insertion is assumed
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and the expected power level variation throughout the cycle.
The short term behavior relates to transient perturbations to the steady-state radial l
peaks due to radial xenon redistribution.
The magnitudes of such perturbations depend upon the expected use of the CEAs during anticipated
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power reductions and load maneuvering.
Analyses are performed based on the i
L expected mode of operation of the NSSS (base load, load following, etc.)
l-and from these analyses CEA insertions are determined and a consistent set l
of radial peaking factors are defined.
The Long Term Steady State and Short Term Insertion Limits are determined based upon the assumed mode of
' operation used in the analyses and provide a means of preserving the l
assumptions on CEA insertions used.
The limits specified serve to limit the behavior of'the radial peaking factors within the bounds determined l
from analysis.
The actions specified serve to limit the extent of radial xenon redistribution effects to those accommodated in the analyses.
The Long and Short Term Insertion Limits of Specifications 3.1.3.6 and 3.1.3.7 are specified for the plant which has been designed for primarily base loaded operation but which has the ability to accommodate a limited amount of load maneuvering.
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The Transient Insertion Limitt of Specification 3.1.3.6 and the Shutdown CEA Insertion Limits of Specification 3.1.3.5 ensure that 1) the minimum SHUTDOWN MARGIN is maintained, and 2) the potentici effects of a CEA ejection accident are limited to acceptable levels.
Long term operation at the Transient Insertion Limits is not permitted since such operation could have effects on the core power distribution which could invalidate assumptions used to determine the behavior of the radial peaking factors.
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ARKANSAS - UNIT 2 B 3/4 1-5 Amendment No. 37,100 l
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