ML20029A410

Proposed Tech Spec 1.43 Re Core Operating Limits Rept & 1.42 Re APLHGR

ML20029A410
Person / Time
Site:	Oyster Creek
Issue date:	02/20/1991
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20029A409	List: ML20029A408 ML20029A410
References
NUDOCS 9102220004
Download: ML20029A410 (4)

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ENCLOSURE ' i, 5

Technical-Specification chango Requent No. 100 -9 u

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91 -TABLE OF 90NTENTS Section 1- Definitions Page 1.1 operable - operability 1.0-1 1.2 -operating 1.0-1 1.3 Power Operation 1.0-1

-1.4' Startup Mode 1.0-1 1.5' -Run Mode -1.0-1 1.6 Shutdown Condition 1.0-1 1.7 -Cold Shutdown 1.0-2 1.8 Place in Shutdown-condition 1.0-2 1.9 Place in Cold Shutdown Condition 1.0-2 1.10 Place in Isolated Condition 1.0-2 1.11 Refuel Mode 1.0-2 1.12: Refueling Outage 1.0-2

-1.13 -Primary Containment Integrity 1.0-2 1.14 Secondary containment Integrity 1.0-3

=1.15 Deleted 1.0-3 1.16- Rated Flux 1.0-3 1.17 Reactor Thermal Power-To-Water 1.0-3 1.18~ Protective Instrumentation-Logic Definitions 1.0-3 1.19 Instrumentati Surveillance Definitions 1.0-4 1.20 FDSAR 1.0-4 1.21 Core Alteratio; 1.0-4 1.22 Minimum Critical Power Ratio 1.0-4 1.23 Staggered Test Basis 1.0 l'.24 Surveillance Requirements 1.0-5 1.25 Fire Suppression Water System 1.0-5 1.26 Fraction of Limiting' Power Density (FLPD) 1.0-5 1.27 Maximum Fraction of Limiting Power Density tHFLPD)1.0-5 1.28- Fraction of-Rated Power (FRP) 1.0-6' 1.29 Top-of Active Fuel (TAF) .1.0-6 1.30 Reportable Event .1.0-6 1.31- ' Identified Leakage 1.0-6 1.32 Unidentified Leakage 1.0-6 l'.33 Process Control Plan 1.0-6

-1.34 Augmented Offgas System (AOG) 1.0-6 1.35 Member of the Public 1.0-6' 1.36 offsite Dose Calculation Manual 1.0-6

-1.37 ' Purge -1.0-7

'1.38 Exclusion Area 1.0 1.'39 Reactor Vessel Pressure Testing 1.0-7 1.40 substantive Changes 1.0-7.

1.41 ' Dose Equivalent I-131 1.0-7 l'.42 Average Planar Linear Heat Generation Rate 1.0-7 1.43 Core Operating Limits Report 1.0 1.44 Local Linear Heat Generation Rate 1.0-0 Section 2 Safety Limits and Limiting Safety System Settings Pace 2.1 Safety Limit - Fuel Cladding Integrity 2.1 2.2 Safety Limit - Reactor Coolant System Pressure 2.2-1 2.3 - Limiting Safety System Settings 2.3-1 OYSTER CREEK i Amendment No.: 64, 84, 97, 108

f I'.37- EMEGE I PURGE OR PURGING is the controlled process of discharging air or gas  ;

from a confinement and replacing it with air or gas.

1,38 EXCLUSION AREA EXCLUSION AREA is defined in 10 CFR part 100.3(2). As used in these-technical specification, the Exclusion Area boundary is the perimeter line around the OCNGS beyond which the land is neither owned, leased, nor otherwise subject to control by GPU (ref. ODCM Figure 1-1). The area outside the Exclusion Area is termed OFFSITE.

1.39 BEhCTOR VESSEL PRESSURE TESTING System pressure testing required by A3ME Code section XI, Article IWA-50CJ, including system leakage and hydrosta.ic test, with reactor vessel completal; water solid, core not critical and section 3.2.A satisfied.

1.40 SUBSTANTIVE CHANGES SUBSTANTIVE CHANGES are those which affect the activities associated with a document or the document's meaning or intent. Examples of non-substantive changes ares (1) correcting spelling, (2) adding (but not deleting) sign-off spaces, (3) blocking in notes, cautions, etc., (4) changes in-corporate and personnel titles which do not reassign responsibilities and which are not referenced in-the Appendix A Technical Specificatiors, and (5) changes in nomenclature or editorial changes which clearly do not change function, meaning or intent.

1.41 DOSE EOUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 microcuries per gram which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, 1-132, I-133, I-134, and I-135 actually present.- The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 or Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routino Releases of Reactor Effluences for the Purpose of Evaluating Compliance with 10 CFR Part 40 Appendix I".

1.42 AVERAGE PLANAR LINEAR HEAT GENERATION RATE The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the heat generation rate per unit length of fuel rod for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rode in

-the fuel bundle at that height.

OYSTER CREEK 1.0-7 Amendment No.: 108, 120, 125, 126, 138 i

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e l'.43 CORE ' OPERATING LIMITS REPORT The Oyster Creek OORE-OPERATING LIMITS REPORT (COLR) is the document that provides core operating limite for the current operating reload cycle.

These cycle-specific core operating limite shall be determined for each reload cycle in accordance with specification 6.9.1.f. Plant operation within these

' operating limits is addressed in individual specificat!ans.

1.44 LOCAL LINEAR HEAT GENERATION RATE The LOCAL LINEAR HEAT GENERATION RATE (LLHGR) ehall be applicable to a specific planar height and is equal to the AVERAGE PLANAR LINEAR HEAT

-GENERATION RATE (APLHGR) at the specified height multiplied by the local peaking factor at that height.

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OYSTER CREEK 1.0-8 Amendment No.:

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