ML20053E458
| ML20053E458 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/25/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20053E459 | List: |
| References | |
| NUDOCS 8206080184 | |
| Download: ML20053E458 (7) | |
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UNITED STATES 4
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NUCLEAR REGULATORY COMMISSION
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DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 Licnese No. NPF-6 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Arkansas Power and Light Company t
(the licensee) dated March 5,1981, as supplemented by letter dated May 3,1982 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; 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 (1) that the activities authorized by this amendment can be condurcted without endangering the health and safety of'the public, (ii) that such activities will be conducted in compliance with the Commission's regulations;
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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.
8206080184 820525 DRADOCK05000g
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraph 2.C.(2) of Facility Operating License No. NPF-6 to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 32 are hereby incorporated in the license.
The licensae shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 30 days of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
]RobertA. Clark,Chiefk,kt.bw Operating Reactors Branch #3 Division cf Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
May ~25,,1982
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ATTACHMENT TO LICENSE AMENDMENT NO. 32 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Cor-responding overleaf pages are provided to maintain document completeness.
Pages - Appendix A 3/4 2-8 B3/4 2-3 B 3/4 2-4 1
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POWER DISTRIBUTION LIMITS DNBR MARGIN LIMITING CONDITION FOR OPERATION 3.2.4 The DNBR margin shall be maintained by operating within the region of acceptable operation of Figure 3.2-3 or 3.2-4, as applicable.
l APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.
ACTION:
With operation outside of the region of acceptable operation, as indicated by either (1) the COLSS calculated core power exceeding the COLSS calculated core power operating limit based on DNBR; or (2) when the COLSS is not being used, any OPERABLE Low DNBR channel exceeding the DNBR~ limit, within 15 minutes initiate corrective action to reduce the DNBR to within the limits and either:
a.
Restore the DNBR to within its limits within one hour, or b.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.2.4.1 The provisions of Specification 4.0.4 are not applicable.
4.2.4.2 The DNBR shall be determined to be within its limits when THERMAL POWER is above 20% of RATED THERMAL POWER by continuously monitoring the core power distributibn with the Core Operating Limit Supervisory System (COLSS) or, with the COLSS out of service, by verify-ing at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> that the DNBR, as indicated on all 0PERABLE DNBR channels, is within the limit shown on Figure 3.2-3.
4.2.4.3 At least once per 31 days, the COLSS Margin Alarm shall be verified to actuate at a THERMAL POWER level less than or equal to the core power operating limit based on DNBR.
ARKANSAS - UNIT 2 3/4 2-7 Amendment No. 24 l
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POWEk DISTRIBUTION LIti1TS SURVEILLANCE REQUIREMENTS (Continued) 4.2.4.4 The following DNBR penalty factors shall be verified to be included in the COLSS and CPC DNBR calculations at least once per 31 days:
GWD Burnuo(t1TU}
DNBR Penalty (%)
0-30 2.0 30-40 3.5 40-50 5.5
.~T_he penalty for each batch will be determined from the batch's maximum burnu'p assembly and applied to the batch's maximum radihl power peak assembly. A single net penalty for COLSS and CPC will be determined from the. penalties associated with each batch, accounting for the offsstting margins due-to the lower radial power peaks in the higher burnup batches.
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Amendment No. 74, #, 32 i ARKANSAS - UNIT 2
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POWER DISTRIBUTION LIMITS BASES P
/P is the ratio of the power at a core location in the dit untilt presence of a tilt to the power at that location with no tilt.
3/4.2.4 DNBR t1ARGIN The limitation on DNBR as a function of AXIAL SHAPE INDEX represents a conservative envelope of operating conditions consis' tent with the safety analysis assumptions and which have been analytically demonstrated adequate to maintain an acceptable minimum DNBR throughout all anticipated operational occurrences, of which the loss of flow transient is the most limiting. Oper-ation of the core with a DNBR at or above this limit provides assurance that an acceptable minimum DNBR will be maintained in the event of a loss of flow transient.
Either of the two core power distribution monitoring systems, the Core Operating Limit Supervisory System (COLSS) and the DNBR channels in the Core.
Protection Calculators (CPCs), provide adequate monitoring of the core power distribution and are capable of verifying that the DNBR does not violate its limits. The COLSS performs this function by continuously monitoring the core power distribution and calculating a core operating limit corresponding to the allowable minimum DNBR.
Reactor operation at or below this calculated power level assures that the limits of Figure 3.2-3 are not violated.
The COLSS calculation of core power operating limit based on DNBR includes appropriate uncertainty and penalty factors necessary to provide a 95/95 confidence level that the core power at which a DNBR of less than 1.24 could occur, as calculated by COLSS, is less than or -euqal to that which would actually be required in the core. To ensure that the design margin to safety is maintained, the COLSS computer program includes an F measurement uncertainty factor of 1.053, an engineering uncertainty *Vactor of 1.03, a THERMAL POWER measurement uncertainty factor of 1.02 and appropriate uncertainty and penalty factors for flux peaking augmentation and rod bow.
Parameters required to maintaiit the margin to DNB and total core power are also monitored by the CPCs. Therefore, in the event that the COLSS is not being used, operation within the limits of Figure 3.2-4 can be maintained by utili;:ing a predetemnined DNBR as a function of AXIAL SHAPE INDEX and by monitoring the CPC trip channels. The above listed uncertainty and penalty factors are also included in the CPC.
The DNBR penalty factors listed :n section 4.2.4.4 are penalties used to accommodate the effects of rod bow. The amount of rod bow ir each assembly is dependent upon the average burnup experienced by that assembly. Fuel asscablies that incur higher average burnup will experience a greater magnitude of rod bow. Conversely, lower burnup assemblies will experience less rod bow. The penalty for each batch required to compensate for rod bow is determined from a batch's maximum average assembly burnup applied to the batch's maximum ARKANSAS - UNIT 2 B 3/4 2-3 Amendment No. 26, y, 32 e
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POWER DISTRIBUTION LIMITS BASES integrated planar-radial power peak. A single net penalty for COLSS and CPC is then determined from the penalties associated with each batch, accounting for the offsetting margins due to the lower radial power peaks in the higher-burnup batches.
3/4.2.5 RCS FLOW RATE This specification is provided to ensure that the actual RCS total flow rate is maintained at or above the minimum value used in the LOCA safety analyses.
3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATUkE This specification is provided to ensure that the actual value of reactor coolant cold leg tenperature is maintained within the range of values us 2 in
- the safety analyses.
3/4.2.7 AXIAL SHAPE INDEX This specification is provided to ensure that the actual value of AXIAL SHAPE INDEX is maintained within the range of values used in the safety analyses.
3/4.2.8 PRESSURIZER PRESSURE This specification is provided to ensure that the actual value of pressurizer pressure is maintained within the rang 5 '6f" val'uis' u' sed' In thssafitf'ansTyses.
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ARKANSAS - UNIT 2 B 3/4 2-4 Anendment No. 2A,32
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