ML20099H542
| ML20099H542 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/04/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Arkansas Power & Light Co |
| Shared Package | |
| ML20099H545 | List: |
| References | |
| DPR-51-A-095 NUDOCS 8503190405 | |
| Download: ML20099H542 (7) | |
Text
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j/ ""'*v't UNITED STATES p-NUCLEAR REGULATORY COMMISSION g
WASHING TON, D. C. 20555 k..v f
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE v
Amendment No. 95 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated August 15, 1984, 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; B.
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 (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 Commission's regulations; 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.
2.
AO:ordfrgly, the license is amended by changes to the Todr,1 cal 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:
8503190405 850304 PDR ADOCK 05000313 P
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7 2-Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.95 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 s
Joh'n F. Stolz, Ch ef f
pe ating Reactors Branc
.4 ision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 4,1985 F
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ATTACPMENT TO LICENSE AMENDMENT NO. 95 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 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 chance.
Remove Insert 18a 18a 20 20 72d 72d 73b 73b e
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v 3.1.2.7 Prior to reaching fifteen effective full power years of operation 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.B.
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.
predicted adjusted reference temperature of all the beltlineThe highest region materials shall be used to determine the adjusted reference temperature 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.
3.0.3 and 3.0.4 are not applicable.The provisions of Specifications 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.
Appropriate additional NRC review time shall be allowed for proposed technical specifications submitted in accordance with 10 CFR Part 50, Appendix G, Section V. C.
3.1.2.9 With the_ exception of ASME Section XI testing and when the core flood tank is depressurized, during a plant cooldown the core flood tank discharge valves shall be closed and the circuit breakers for the motor operators opened before depressurizing the reactor coolant system below 600 psig.
3.1.2.10 With the exception of ASME Section XI testing, fill and vent of the reactor coolant system, and to allow maintenance of the valves, when the reactor coolant temperature is less than 280 F the four High Pressure Injection motor operated valves shall be closed with their opening control circuits for the motor operators disabled.
3.1.2.11 The plant shall not be operated in a water solid condition when Operating Procedures and during System Hydrotest.th T
AMEN 0 MENT NO. 67, 83, 95 18a ARKANSAS - UNIT 1
The heatup and cooldown rates stated in this specificaticn 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 no 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.
Specification 3.1.2.9 is to ensure that the core flood tanks are not the source for pressurizing the reactor coolant system when in cold shutdown.
Specification 3.1.2.10 is to ensure that high pressure injection is not the source of pressurizing the reactor coolant system when in cold shutdown.
Specification 3.1.2.11 is to ensure that the reactor coolant system is not operated in a manner which would allow overpressurization due to a temperature transient.
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
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(5) BAW-1698 (6) BAW-1547, Revision 1 (7) BAW-1511P (8) BAW-1436 AMENDMENT NO. 2, 22, 75, $3, 95 20 ARKANSAS - UNIT 1
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g TABLE 4.1-1 (Cont'd) e e,
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$I Channel Description Check Test Calibrate
_rmarks o
w
?"
d.
SG A high range level S
M R
high-high u,
t e.
SG B high range level S
M R
high-high I'
- 57. Containment High Range Radiation D
H R
Monitors
- 58. Containment Pressure-High H
NA R
- 59. Containment Water Level-Wide Range M
NA R
- 60. Low Temperature Overpressure NA R
R I
Protection Alarm Logic l
Note:
5-Each Shift T/W-Twice per Week R-Once every 18 months
(
W-Weekly Q-Quarterly PC-Prior to going Critical if not M-Monthly P-Prior to each startup done within previous 31 days 0-Daily if not done previous NA-Not applicable week 8/M-Every 2 Months
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r-TABLE 4.1-2 (Continued)
Minimum Equipment Test Frequency item Test
-Frequency
- 16. RCS Vent Paths Demonstrate At least once per 18 operability by months during cold flow verification shutdown
- 17. PORV Exercise End of each' refueling outage l
4
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Am:ndment No. H, 95
-73b-
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