ML20087P990

Proposed Tech Spec Change Request 139,replacing Pages 1-2 Re Equipment Operability

ML20087P990
Person / Time
Site:	Three Mile Island
Issue date:	03/28/1984
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20087P983	List: ML20087P982 ML20087P985 ML20087P990
References
NUDOCS 8404100178
Download: ML20087P990 (2)

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TECHNICAL SPECIFICATION CHANGE REQUEST (TsCR) No. 139 The Licensee requests that the attached changed page replace page 1-2.

II. REASON FOR CHANGE By letter dated December 30,'1983 the NRC requested that GPUN propose a Technical Specification (TS) change' addressing the definitions of Operable to replace our TSCR 95 which was withdrawn. This TSCR provides a revised definition of Operable (proposed page 1-2) which addresses the NRC position that support equipment must be considered when determining operability.

III.. SAFETY EVALUATION JUSTIFYING CHANGE *

.This TSCR is administrative in nature since it cl'arifies operability considerations and acti.on guidance.

' Operating Logs document equipment operability in accordance with existing administrative procedures. Thus no new administrative requirements are needed.

Based on the above there is no impact on safety since there will be no fundamental change in plant or equipment' operation as a result of this TSCR.

IV. NO SIGNIFICANT HAZARDS CONSIDERATION '

This change is entirely administrative in nature and serves only to codify

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a philosophy already in use. Therefore, no plant design, operation, modifi-

-cations or safety analysis are involved and thus there are no significant hazards considerations.

V. IMPLEMENTATION. .

We request that the amendment approving this TSCR be made effective 45 days after receipt.

VI. AMENDMENT CLASSIFICATION (10 CFR 170.22)

-This TSCR is administrative in nature and is therefore a Class II License Admendment subject to a fee of $1,200.00. A check for this amount is enclosed.

G 8404100178 840328 PDR P ADOCK 05000289 PDR G

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,' 140 F. Pressure is d: fined by Specification 3.1.2. A re' fueling shutdown refers to

• a shutdown to replace cr rearrange all or a portica of the fuel assemblies and/cr control rods, i E

1.2.7 REFUELING OPERATION _

An operation involvi'ng a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.  :

1.2.8 REFUELING INTERVAL Time between normal refueling's of the reactor, not to exceed 24 months without i prior approval of the NRC. ,

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1.2.9 STARTUP The reactor shall be censidered in the startup mode when the shutdown margin is reduced with the intent of going critical.  ;

1.2.10 TAyg _

TA yg is defined as the arithmetic average of the coolant temperatures in the hot and cold legs of the Icop with the greater number of reactor coolant pumps _

operating if such a distinction of loops can be mad .

1.2.11 HEATUP - CCOLDOWN MODE i .'  :

The heatup-cooldown mode is the range of reactor coolar$t temperature greater than ,

2000F and less than 525oF. , ,

1.2.12 STATICN, UNIT, PLANT AND FACILITY

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Station, unit, plant and facility as used in these technical specifications all

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refer to TMI Unit 1.

1.3 OPERABLE A system, (i.e. subsystem, train, component or device) shall be operable or have operability when it satisfies the applicable Limiting Condition for Operation specified in Section 3, it has been tested periodically as specified in Section 4, and it is capable of performing its specified function (s). All necessary attendant instrumentation, controls, normal electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system to perform its function (s) shall also be capable of performing their related support -

function (s).

1."4 PROTECTION INSTRUMENTATION LOGIC

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1.4.1' INSTRUMENT CHANNEL An instrument channel is the combination of sensor, wires, amplifiers and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of observation, control and/or protection. An instrumentation channel may be either analog or digital.

1.4.2 REACTOR PROTECTION SYSTEM The reactor protection system is shown in Figures 7-1 and 7-6 of the FSAR.~ It is that cocbination of protecticn channels and associated circuitry which 1-2