ML19345F178
| ML19345F178 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 01/21/1981 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345F177 | List: |
| References | |
| NUDOCS 8102090345 | |
| Download: ML19345F178 (8) | |
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NUCLEAR REGULATORY COMMISSION
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MAINE YANKEE ATOMIC POWER COMPANY DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. DPR-36 1.
The Nuclear Regulatory Commission (the Commission) has found that:
g A.
The application for amendment by Maine Yankee Atomic Power Company, (the licensee) dated May 20, 1980, complies with the standards and requirements of the Atomic Energ;' l.ct of 1954, as amended (the Act) and the Commission's rules and regulations set forth j
in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulatfor.s of the Commission; C.
There is reasonable assurance.(i) that the activities authorized i
by this amendment can be conjucted 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.
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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.B(6)(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and 3, as revised through Amendment No. 51, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of its issuance.
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FOR THE NUCLEAR REGULATORY COMMISSION
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dobert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
i-Changes to the Technical Specifications Date of Issuance: January 21, 1981
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w ATTACHMENT TO LICENSE AMENDMENT NO. 51
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TO FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise Appendix A as follows:
Remove Page Insert Pace Table of Contents Table of Contents 4 4
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w TECHNICAL SPECIFICATIONS Table of Contents 1-Definitions
-- Pa g e 1.1 Fuel Storage 1.1-1 1.2 Site Description 1.2-1 1.3 Reactor 1.3-1 1.4 Containment 1,4-1 2.0 Safety Limits and Maximum Safety Settings 2.1 Limiting Safety Settings Reactor Protection System 2.1-1 2.2 Safety Limits - Reactor Core 2.2-1 2.3 Safety Limits - Reactor Coolant System Pressure 2.3-1 3.0 Limiting Conditions for Operation 3.0-1 1
3.1 Incore Instrumentation 3.1-1 3.2 Reactor Coolant System Activity 3.2-1 3.3 Reactor Coolant System Operational Components 3.3-1 3.4 Cocbined Heat-up, Cooldown and Press-Temp. Limits 3.4-1 3.5 Chemical and Volume Control System 3.5-1 3.6 core Cooling and Containment Spray Systems 3.6-1 3.7 Boron and Sodium Hydroxide Available for Containment Spray System 3.7-1 3.3 Reactor Core Energy Removal 3.8-1 3.9 Operational Safety Instrumentation and Control. Systems 3.9-1 3.10 CEA/ Group mid Pcwer Distribution Limits 3.10-1 3.11 Containment 3.11-1 3.12 Station Service Power 3.12-1 3.13 Refueling Operations 3.13-1 3.14 Primary System Leakage 3.14-1 3.15 Reactivity Anomalies 3.15-1 3.16
. Radioactive Liquid Waste Release 3.16-1 3.17 Radioactive Gaseous Waste Release t
3.17-1 3.18 Chemistry 3.18-1 3.19 Safety Injection Valving 3.19-1 3.20 Shock Suppressors 3.20-1 3.21 Steam Generators 3.21-1 3.22 (Reserved) 3.22-1 3.23 Fire Protection Systems 3.23-1 3.24 Secondary Coolant Activity 3.24-1 4.0 Surveillance Requirements 4.0-1 4.1 -
Instrumentation and Control 4.1-1 4.2 Equipment and Sampling _ Tests 4.2-1 4.3 Reactor Coolant Syetem Leak Tests 4.3-1 4.4 Containment Testing 4.4
- Amendment No. 38, 51
ENGINEERED SAFEGUARDS SYSTEMS (Continued)
Subsystem (Continued) safeguards manual and auto =atic initiation.
Degree of Redundancy The difference between the number of operable channels and the number of channels which when tripped will cause an automatic system trip.
INSTRUMENTATION SURVEILLANCE Channel Check A qualitative determintion of acceptable operability by observation of channel behavice during normal plant operation. This determination shall, where feasible, include comparison of the channel with other independent channels measuring the same variable.
Channel Functienal Test Injection of a si=ulated signal into the channel to verify that it is operable, including any alarm and/or trip initiating action.
Channel Calibration / Channel Adjustment Adjustment of channel output such that it responds, with acceptable range and accuracy, to known values of the parameter which the channel Calibration shall encompass the entire channel, including measu res.
i equipment action, alat a, intericcks or trip and shall include the channel functional test.
MISCELLANEOUS DEFINITIONS 0;erable A system, subsystem, train, co=penent er device shall be OPERABLE cr have OPERABILITY when it is capable of performing its specified functions (s).
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l Amendment No. 51
w MISCELLANEOUS DEFINITIONS (Continued)
Operable (Continued)
Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).
Operating A system or component is operating if it is performing its safeguard er operating functions.
Control Rods All Ball-length shutdown and regulating control elements assembl4.es (CEA).
Partial-Length Centrol Element Assemblies h
Control element assemblies (CEA) that contain neutron absorbing material only in the lower quarter of their length.
Contairiment Integrity Containment integrity is defined to exist when all of the following are I
f true:
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All non-automatic containment isolation valves and blind flanges a.
j are closed.
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The equipment hatch is properly closed and sealed.
l At Isast one hatch in the personnel air lock is properly closed c.
and sealed.
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All automatic containmer.t isolation valves are operable or are locked closed.
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The uncontrolled containment leakage satisfies Specification 4.4 Section I.3.3 1
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Amendment No. 51-
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MISCELLANEOUS DEFINITIONS (Continued)
Report.ble Occurrence A reportable occurrence is defined in Section 5.3 of these specifications.
Radio Isotoce Release Limits The Maine Yankee radio isotope release limits are as defined in Technical Specification 3.16, paragraph A, item 2, for liquid releases and Technical Specification 3.17, paragraph A, item 2 for gaseous releases.
FREQUENCY NOTATION The frequency notation specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 0.1.
Fire Suppression ' dater System A fire suppression water system shall censist of: A water source (s);
gravity tank (s) or pump (s); and distribution piping with associated sectionalizing control or isolation valves. Such valves shall include yard hydrant curb valves, and the first valve ahead of the water flow alarm device en each sprinkler, hose standpipe or spray system riser.
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LIMITING COMDITIONS FOR OPERATION When a system, subsystem, train, co=ponent or device is determined to be inoperable solely because its emergency power source is inoperable, or solely because its normal power source is inoperable, it may be
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cons 1dered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Condition for Operation, provided:
(1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s), subsystem (s), train (s), component (s) and device (s) are OPERA 3LE, er likewise satisfy the requirements of this specificatien. Unless both cond.4.tions (1) and (2) are satisfied, the unit shall commence a continuous controlled shutdown at a rate equal to l
or greater than 15 percent per hour and be in the Cold Shutdown Condition l
within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This specification is not applicable in the Cold f
Shutdown er Refueling Shutdown Condition.
This requirement delineates what additional ocnditions must be satisfied I
to per=it operation to continue. It specifically prohibits operation when one train is inoperable because its normal or emergency power source is inoperable and a system, subsystem, component or device in the other train is inoperable for another reason.
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3 0-1 Amendment No. 51 l
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