ML19312D972

Tech Spec Change Request 86 Revising Section 1.1 Definition of Operable & Adding Section 3 Re General Limiting Conditions for Operation

ML19312D972
Person / Time
Site:	Oyster Creek
Issue date:	05/22/1980
From:	JERSEY CENTRAL POWER & LIGHT CO.
To:
Shared Package
ML19312D968	List: ML19312D967 ML19312D969 ML19312D972
References
NUDOCS 8006030014
Download: ML19312D972 (6)

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O-JERSEY CENI'RAL IOWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GEIERATING STATION (DCCKET NO. 50-219)

PROVISIONAL OPERATING LICENSE DPR-16 Applicant hereby requests the Commission to change Appendix A to the above captioned license as follows:

1. Sections to be changed 2 Section 1.1 Add Section 3.0

2. Extent of Change:

Revise secti3n 1.1 in accordance with STS definition of Operable.

Include Section 3.0 w'aich addresses General Limiting Conditions for Operation.

3. Change Requested:

The requested changes are on the attached revised Technical Specification pages 1.0-1, 3.0-1, 3.0-2 and 3.1.-l.

4. Discussion:

The changes are in accordance with an NRC request received April 22, 1980 (dated April 10, 1980). The subject request concerns Limiting Conditions for Operation relative to single failure criterion for safety systems in power reactors.

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, TABLE OF CONTENTS .. ,.

Page 9.ic.ction1 Def4nitions -

Operable 1.0-1 1.1 '

Oparating ~1.0-1 1.2 ' l .0-1 1.3 Power Operation '

Startup Mode 1.0-1 1.4 1.0-1 1.5 Run Mode .

1.6 Shutdown Condition ~l.0-1 -

1.7 Cold Shutdown -1.0-1

'.1.0-2 Place in Shutdown Condition 1.8 1.0-2 1.9 Place in Cold Shutdown Condition .

' 1.10 Place in Isolated Condition 1.0-2 1.11 Refuel Mode 1.0-2 Refueling Outage .l.0-2 1.12 1.13 Primary Containment Integrity 1.0-2 1.14 Secondary Containmr-t Integrity 1.0-2 1.15 Deleted 1.0-3 1.16 Rated Flux 1.0-3 '

1.17 Reactor Thetc.a1 F der-to-Water 1.0-3 1.18 Protective Instrumentation Logic Definitions 1.0-4 .

1.19 Instrumentation Surveillance Definitions 1.0-4 1.20 FDSAR 1.0-4 1.21 Core Alteration . 1.0-5 1.22 Minimum Critical Power Ratio 1.0-5 1.23 Staggered Test Basis 1.0-5 .

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'1.24 Surveill etce Requirements 1.0-5 i 1.25 Fire %ppression Water System 1.0-5 j l

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_Section 2 Safety Limits and Limiting Safety System Settings 2.1 Safety Limit - Fuel Cladding Integrity 2.1-1

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2.2 Safety Limit - Reactor Coolant System Pressure 2.2-1 2.3 Limiting Safety Syttem Seetings 2.2-3 Section o. Limiting Conditions for. Operation 3.0 Limiting Conditions for Ooeration (General) 3.1 Protective Instrumentation 3.1-1 3.2 Reactivity Control 3.2-1 3.3 Reactor Coolant 3.3-1 3.4 Emergency Cooling 3.4-1 3.5 Containment 3.5-1 3.6 Radioactive Effluents 3.6-1 1 3.7 Auxiliary Electtical Power 3.7-1 l 3.8 Isolation Condenser 3.8-1 l 3.9 Refueling 3.9-1 3.10 Core Limits 3.10-1 3.11 3.11-1 fm (NotUsed) 3.12-1 V 3.12 Fire Protection

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Amenchent No. J(,,2ff,#.I .

1.0-1 SECTION I DEFINITIONS The following frequently used terms are defined to aid in the uniform interpretation of the specifications.

1.1 OPERABLE-OPERABILITY A system, subsystem, train, canponent, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s).

Implicit in this definition shall be the assumption that all necessary attendent instrumentation, controls, normal and emergency electrical power sources, cooling of seal water, lubrication or other auxiliary equipment that are required for the system, subsyster, train, component or device to perform its function (s) are also capable of performing their related scoport function (s).

1.2 OPERATING Operating means that a system or canponent is perfonning its required function.

1.3 POhu OPERATION Power operation is any operation when the reactor is in the startup mode or run mode except when primary containment integrity is not required.

1.4 STAR'IUP MODE Tne reactor is in the startup mode when the reactor mode switch is in the startup mode position. In this mode, the reactor protection system scram trips initiated by condenser low vacuum and main steam line isolation valve closure are bypassed when reactor pressure is less than 600 psig; the low pressure main steamline isolation valve closure is bypassed; the IRM trips for rod block and scram are operable; and the SRM trips for rod block are operable.

1.5 RUN M3DE The reactor is in the run mode when the reactor mode switch is in the run mode position. In this mode, the reactor protection system is energizedwith APRM protection and the control rod withdrawal interlocks are in service.

1.6 SECTDOWN CONDITION The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and there is fuel in the reactor vessel. In this condition, the reactor is subcritical, a control red block is initiated, all operable control rods are fully inserted, and specification 3.2-A is met.

1.7 COLD SIR 7fDOWN The reactor is at cold shutdown when the moce switch is in the thutdow Amendment No.

1.0-le mode position there is fuel in the reactor vessel, all operable control rods are fully inserted, and the reactor coolant systen maintained at less than 212#F l and vented.

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SECTION 3 3.0-1 LIMITING CONDITIONS FOR OPERATIOti 3.0 '[IMITING CO!!DITIONS FOR CPERATICN (GENERAL)

Applicability: Applies to all Limiting Conditions for Operation.

Objective: To preserve the single failure criterion for safety systems.

Specifications: A. Ir. the event Limiting Conditions for Operation (LCOs) crd/or associated action requirements cannot be satisfied because of circumstances in excess of those addressed in the specification, the unit shall be placed in COLD SHUIDO2J within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> unless corrective measures are completed tnat permit operation under the permissible action statements for the specified time interval as measured from initial discovery or until the reactor is placed in a condition in which tne specification is not applicable. Exceptions to the requirements shall be stated in the individual specifications. I B. When a system, subsystem, train, component 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 considered CPERABLE for the purpose of satisfying tne requirements of applicable If0s., provided (1) its corresponding normal or emergency power source is OPERABLE; and (2) all of its redundant system (s), sub-system (s), train (s), component (s) and device (s) are OPERABLE, or likewise satisfy the require-ments of this specification. Unless bcth conditions (1) and (2) are satisfied, the unit shall be placed in COLD SHUIDOG within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> or within the time specified in the applicable specification.

This specification is not applicable in CCLD SHUIDOWN or the REFUEL MODE.

Bases: Specification 3.0.A delineates the action to be taken for circumstances not directly prcvided for in the systems If0s and whose occurrence would violate tne intent of the specification.

Specification 3.0.B delineates what additional conditions must be satisfied to permit operation to continue, consistent with the specifications for power sources, wnen a normal or emergency power source is not operable. It allows operation to be governed by the time limits of the specifications associated with the LCOs for the normal or emergency power source, not the individual specifications for each system, subsystem, train, component or device that is determined to be inoperable solely because of the inoperability of its nortral or emergency power source. In addition, it specifically prohibits operation when one division is inoperable because its normal or emergency power source is inoperabic and a safety subsystem, train, component, or device in another division is inoperable for another reason.

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3.1 PROTECTIVE INSTRUMENTATION

• Applicability: Applies to the operating status of plant instru' entation which performs a protective function. .

_ Objective: To assure the operability of protective instrumentation.

c Specifica tion _s : A. The follouing operating requirc=cnts for plant protective instrumentation are given in Table 3.1.1:

1 The reactor node in which a specified function qust be operable including allowable bypass conditions.

2. The minimum number of operable instrument channels per operable trip systen. .

3. The trip settings which initiate automatic. protective action.

4 The action required when the liciting conditions for

' operation are not satisfied.

B. 1 Failure of four chambers assigned to any ,one APRM shall take the APRM inoperable.

2 Failure of two chambers from one radial core location in any one APRM shall cake that APRM inoperable.

C. 1 Any two (2) LPRM assemblics which are input to the APRM system and are separated in distance by less than three (3) ti=es the control rod pitch cay not centain a cocbi-nation of more than three (3) inope'rable detectors (i.e.,

APRM channel failed or bypassed, or LFRM detectors failed or bypassed) out of the four (4) detectors located in cither the A and B, or the C and D levels.

2. A Travelling In-Core Probe (TIP) cha=ber say be used as an APEM input to meet the criteria of 3.1.3 and 3.1.C.1, provided the TIP is positioned in close proximity to one of the failed LPRM's. If the criteria of 3.1.B.2 or 3.1.C.1 cannot be men power operation may continue at up d to rated power level provided a control rod withdrawal block is operating or at power levels less than 61% of rated power until the TIP can be connected, p6sitioned and satisfactorily tested, as long as Specification 3.1.B.1 and Table 3.1.1 are satisfied. .

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Amendment No. * *

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