ML20094C811
| ML20094C811 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/27/1984 |
| From: | Rivenbark G Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20094C815 | List: |
| References | |
| DPR-51-A-083 NUDOCS 8408080158 | |
| Download: ML20094C811 (9) | |
Text
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 l
License No. DPR-51
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- 1.. The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated February 27, 1984, complies with the stas,dards 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.
LThere 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-amendment will not be inimical to the common defens'e 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 4
been satisfied.
.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. DPR-51 is hereby amended to read as follows:
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-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 83, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l') L 1 ll du l+1 f~
t George W. Rivenbark, Acting Chief Operating Reactors Branch No. 4 Division of Licensing
Attachment:
Changes to the Technical
' Specifications Date of Issuance: July 27,1984 e'
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ATTACHMENT TO LICENSE AMEEDMENT NO. 83 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
I Remove Insert 18a-18a
'19 19 20 20
'20a 20a 20b 20b 20c 20c t
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3.1.2.7 Prior to reaching fifteen effective full power years of operation,
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Figures 3.1.2-1, 3.1.2-2 and 3.1.2-3 shall be updated for the next service ~ period in accordance with 10CFR50, Appendix G, Section V.8.
The service period shall be of sufficient duration to permit the scheduled evaluation of a portion of the surveillance data scheduled in accordance with Specification 4.2.7.
The highest predicted adjusted reference temperature of all the beltline region materials shall be used to determine the adjusted reference Ltemperature at the end of the service period. The basis for this prediction shall be submitted for NRC staff review in accordance with Specification 3.1.2.8.
The provisions of Specifications 3.0.3 &nd 3.0.4 are not applicable.
3.1.2.8 The updated proposed technical specifications referred to in 3.1.2.7 shall be submitted for NRC review at least 90 days prior to the end of the service period. App-opriate additional NRC review time shall be allowed for proposed technical specifications submitted in accordance with 10 CFR Part 50, Appendix G, Section V.C.
t Amendment No. A T, B3 18a d
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All reacter coolant system components are designed to withstand of cyclic loads due to system temperature and pressure changes.ge effects These cyc1tc loads are introduced by unit load transients, reactor trips, and unit heatap and cooldown operations.
The number of thermal and loading cycles used for design purposes are shown in Table 4-8 of the FSAR. The maximum unit heatup and down rate of 100F per hour satisfies stress limits for cyclic operation The 200 psig pressure limit for the secondary side of
'the steam generator at a tempergre less than 100F satisfies stress levels for temperatures below the DTT The mejor components of the reactor coolant pressure boundary have been
- analyzed in accordance with Appendix G to 10CFR50.
Results of this analysis including the actual pressure-temperature limigions of the reactor coolant pressure boundary, are given in 8AW-1440 and BAW-1698N.
The limiting weld material is being irradiated as part of the B&W Owners Group Integrated Reactor Vessel Material Surveillance Program and the
. identification and locations of the capsules containing the 11
~ material is discussed in the B&W report, BAW 1543, Revision 1.ging weld The chemical compositi of the limiting weld material is reported in the 84W Report, RAW 1511P.
The effect of neutron irradiation on the RT of the limiting weld material is reported in the B&W Report, BAW 1436.(8)
NOT Figures 3.1.2-1, 3.1.2-2, and 3.1.2-3 present the pressure-temperature limit
. curves for hydrostatic test, normal heatup, and normal cooldown respectively. The limit curves are applicable through the fifteenth effective full power year of operation.
These curves are adjusted by 25 psi and 10F for possible errors in the pressure and temperature sensing instruments. The pressure limit is also adjusted for the pressure differential between the point of system pressure measurement and the limiting campenent for all operating reactor coolant pump combinations.
The pressure-temperature limit if nes shnwn on Figure 3.1.2-2 for reactor criticality and on Figure 3.1.2-1 for hydrostatic testing have been provided
. to assure compliance with the minimum temperature requirements of Appendix G to 20CFR50 for reactor criticality and for inservice hydrostatic testing.
The actual shift in RT of the beltline region material will be establishedperiodica1hTduring operation by removing and evaluating, in accordance with Appendix H to 10CFR50, reactor vessel material irradiation surveillance specimens which are installed near the inside wall of this or a similar reactor vessel in the core region.
The spray temperature difference restriction based on a stress analysis of the spray Ifne nozzle is imposed to maintain the thermal stresses at the pressurizer spray line nozzle below the design limits. Temperature requirements for the steam generator correspond with the measured NOTT for the snell.
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l Amenement No. 22, 18, F,03 19 i
The heatup and cooldown rates stated in this specification are intended as the maximum changes in temperature in one direction in a one hour period.
The actual temperature linear ramp rate may exceed the stated limits for a time period provided that the maximum total temperature difference does not exceed the limit and that a temperature hold is observed to prevent the total temperature difference from exceeding the limit for the one hour period.
REFERENCES (1) FSAR, Section 4.1.2.4 (2) ASME Boiler and Pressure Code,Section III, N-415 (3) FSAR, Section 4.3.11.5 (4) BAW-1440 (5) 8AW-1698 (6) BAW-1547, Revision 1 (7) B4W-1511 P (8) BAW-1436 Amendment No. 2, 22, l#,,81 20 6
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