ML19322B410
| ML19322B410 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 08/29/1975 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19322B407 | List: |
| References | |
| NUDOCS 7912020257 | |
| Download: ML19322B410 (5) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON D. C. 20555 DUKE P0hR ~ COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 k
License No. DPR-55 1.
The Nuclear Regulatory Commission.(the Commission) has found that:
A.
The application for amendment by Duke Power Compa-v (the licensee) dated June 10, 1975, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Coinmission's. ules 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; and 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.
2.
Accordingly, the liteense is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Facility License No. DPR-55 is hereby amended to read as follows:
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" B.
Technical Specifications
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The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the j
license. The licensee shall operate the facility i
in accordance with the Technical Specifications, as revised by issued changes thereto through Change No. 9."
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION l
' 'd Q1 i Robert A. Purple, Chief
}
Operating Reactors Branch #1 Division of Reactor Licensing 3
Attachment:
Change No. 9 to the Technical Specifications Date of Issuance:
August 29, 1975 e
6 MW p.i
e ATTACHMENT 1V LICENSE AMENDMENTS AMENDMENT NO.12 TO FACILITY LICENSE NO. DPR-38, CHANGE NO. 22 TO TECHNICAL SPECIFICATIONS; AMENDMENT NO.12 TO FACILITY LICENSE *NO. DPR-47, CHANGE NO. 17 TO TECHNICAL SPECIFICATIONS; AMENDMENT NO. 9 TO FACILITY LICENSE NO. DPR-55, CHANGE NO.
9 TO TECHNICAL SPECIFICATIONS; 1
DOCKET NOS. 50-269, 50-270 AND 50-287 e
Revise Appendix A as follows:
i Remove Pages Insert Pages 1-4 1-4 3.5-27 3.5-27 3.5-28 G
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v l'.5.5 H:ct Beirnca Chtek A heat balance check is a comparison of the ind.icated neutron power and core thermal power.
1.5.6 Heat Balance Calibration An adjustment of the power range channel amplifiers output to agree with the core thermal power as determined by a heat balance on the secondary side of the steam generator considering all heat losses and additions.
1.6 POWER DISTRIBUTION 1.6.1 Quadrant Power Tilt Quadrant power tilt is defined by the following equation and is expressed in percent.
3 )/
pouer in any core qu drant 100
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Average power of all quadrants 22/17/
9 1.6.2 Reactor Power Imbalance Reactor power imbalance is the power in the top helf of the core minus the power in the bottom half of the core expressed as a percentage of rated power.
Imbalance is monitored continuously by the RPS using input from the power range channels.
Imbalance limits are defined in Specification 2.1 and imbalance se'tpoints are defined in Specification 2.3.
1.7 CONTAlfalENT INTEGRITY Containment integrity exists when the following conditions are satisfied:
a.
The equipment hatch is closed and sealed and both doors of the personnel
hntch and emergency hatch are closed and sealed except as in b below, b.
At least one door of the personnel hatch and the emergency hatch is closed and scaled during refueling or during personnel passage through these hatches.
c.
All non-automatic containment isolation valves and blind flanges are closed as required.
d.
All automatic containment isolation valves are operable or locked closed.
e.
The containment leakage determined at the last testing interval satisfies Specification 4.4.1.
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3.5.4 Incore Instrumentation Applicability' Applies to the operability of the incore instrumentation system obj ective To specify the functional and operational. requirements of the incore instru-mentation system.
Specification 3.5.4.1 At or above 80 percent of the power allowable for the existing reactor coolant pump operating combination, incore detectors shall be operable as necessary to meet the following:
a.
For axial imbalance measurements:
At least three detectors in each of at least three strings shall lie '.n the same axial plane, with one plane in each axial core half.
The axial planes in each core half shall be symmetrical about the core mid-plane.
The detector strings shall not have radial symmetry.
b.
For quadrant power tilt measurements:
At least two sets of at least four detectors shall lie in each axial core half.
Each set of detectors shall lie in 22/17/9 the same axial planc.
The two sets in the same core half may lie in the same axial plane.
Detectors in the same plane shall have quarter core radial symmetry.
3.5.4.2 If requirements of 3.5.4.1 are not met, power shall be reduced below 80 percent of the power allowable for the existing reactor coolant pump combination within eight hours and incore detector measurements shall not be used to determine axial imbalance or quadrant power tilt.
Bases w
The operability of.the incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor l
core.
See Figures 3.5.4-1, 3.5.4-2, and 3.5.4-3 for satisfactory incore detector arrangements.
The safety of reactor operation at or below 80 percent of the power allowable for the reactor coolant pump combination (l) without the axial imbalance trip system has been detetmined by extensive 3-D calculations, and was verified during the physics startup testing program.
su (1) FSAR, Section 4.1.1.3 h? 1 3.5-27 AUG 2 9'1975 s-__.,..-..
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