ML20236K501
| ML20236K501 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/24/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236K503 | List: |
| References | |
| NUDOCS 8708070141 | |
| Download: ML20236K501 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION o
WASHWGTON. D. C. 20666 f
5 ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT 1 i
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 l
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License No. DPR-51 f
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Arkansas Power and Light Company (the licensee) dated January 17, 1986 as supplemented June 24, 1986 and January 15, 1987, 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 j
Commission;
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There is reasonable assurance (i) that the activities
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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 i
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 1
Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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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:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
, 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 g a Ch Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 24, 1987 I
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1 ATTACHMENT TO LICENSE AMEN 0 MENT NO.108 TO FACILITY OPERATING LICENSE NO. DPR DOCKET NO. 50-313 Replace the following pages of the Appendix."A" Technical Specifications with the attached pages.
The revised pages are identified by Amendmant number and contain vertical lines indicating' the areas of change.
Remove Insert 49 49 50 50
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' 3. 5. 3 Safety Features Actuation System Setpoints Applicability This specification applies-to the safety features actuation system actuation setpoints.
Objective To' provide for automatic initiation of the safety features actuation system in the event of a breach of reactor coolant system integrity.
Specification The safety features actuation setpoints and permissible bypasses shall be as f;'1,0ws :
Functional Unit Action Setpoint-HighReactbhBuilding Reactor Building Spray
$30 psig (44.7 psia)
Pressure
- High Pressure Injection 54 psig (18.7 psia)
Start of Reactor Building Cooling and Reactor Building Isolation 54 psig (18.7 psia)
Reactor Bldg. Ventilation 54 psig (18.7 psia)
Low Pressure ~ Injection
$4 psig (18.7 psia)
Penetration Room Ventilation 54 psig (18.7 psia)
Low Reactor Coolant High Pressure Injection 21526 psig System Pressure **
Low Pressure Injection 11526 psig Start of Reactor Building Cooling and Reactor Building Isolation 11526 psig
- May be bypassed during reactor building leak rate test.
- May be bypassed below 1750 psig and is automatically reinstated above 1750 psig.
With the safety features actuation setpoints less conservative than the above values, declare the cTannel inoperable and apply the applicable Action requirements of Table 3.5.1-1 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the trip setpoint value.
Amendment No. 49.p/,,108 49
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~c Bases High Reactor Building Pressure The basis for.the 30 psig and 4 psig setpoints for the high pressure signal is to establish a setting which would be_ reached in adequate time in the event of a DBA, cover a spectrum of break sizes and yet be far enough above normal operation maximum internal pressure to prevent spurious initiation.
Low Reactor Coolant System Pressure Thi basis for the 1526 psig low reactor coolant pressure setpoint for high l
and low pressure injection initiation is to establish a value which is high enough such that protection is provided for the entire spectrum of break sizes and is far enough below normal operating pressure to prevent spurious initiation. (1)-
REFERENCE (1) FSAR, Section 14.2.2.5 (2) B&W Calculation 32-1158581 1
1 AmendmentNo.pp,108 50
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