ML20237B405

Amend 92 to License DPR-54,changing Tech Specs to Redefine Refueling Interval to Make Definition Consistent W/Sts & to Extend Surveillance Interval of Internal Vent Valves to Cycle 8 Refueling

ML20237B405
Person / Time
Site:	Rancho Seco
Issue date:	12/07/1987
From:	Knighton G Office of Nuclear Reactor Regulation
To:
Shared Package
ML20237B399	List: ML20237B396 ML20237B405 ML20237B414
References
NUDOCS 8712160238
Download: ML20237B405 (5)

Text

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. 'gg UNITED STATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D, C. 20555

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SACRAMENTO MUNICIPAL UTILITY DISTRICT D_0CKET NO. 50-312 RANCHO SECO NUCLEAR GENERATIjiG STATION AMENDMEN,T TO FACILITY OPERATING LICENSE Amendment No. 92 .

License No. DPR-54

1. The hucicar Regulatory Commission (the Commission) has found that:

A. The application for amendment by Sacramento Municipal l'tility District (the licensee) dated September 22, 1986, as supplemented on February 20, 1987, complies with the standards and requirements cf theAtomicEnergyActof1954,asamended(theAct),andthe Commission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in confonnity with the application, the provisions of the Act, and the 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; D. The issuance of this amendment will not be inimical to the com on 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.

8712160238 871207 12 7 DR ADOCK 0500

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2. Acccrcirgly, the license is arrended by char.ges to the Technical Specifications as indicated in the attachment to this license amendmer.t. and paragraphs 2.C.(2) of Facility Operating License No. DPR-54 is hereby amended to read as follows:

.(2) Te,chnical Specifications The Technical Specifications contained in Appendices A and B,

.as revised through Amendment No. 92, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This-license amendnent is effective as of its date of issuance.

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FOR THE NUCLEAR RECL'LATORY COMMISSION W Wi /r

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Geerce W. Knigttcn, Director '

Prcject Directorate V Divisier cf Reactor Projects - III, IV, V and Special Projects Attachn.ent:

Charges to the Technical Specifications Date of Issuance: December 7, 1987

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December 7,1987 ATTACHF.,Eh1 TO LICENSE AMENp, MENT NO. 92  ;

FACILITJ,,0PERATING LICENSE NO,. DPR-54 DOCK _ET N0. 50-312 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are icentified by An:endment number and contain vertical lines indicating the area of change.

Remove Insert 1-2 1-2 1-2b 1-2b l

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Definitions 140 F. Pressure is deffned by Specification 3.1.2. A refueling shutdown 4 refers to a shutdown to replace or rearrange all or a portion of the fuel assemblies and/or control rods.

1.2.7 Refueling Operation An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.

1.2.8 Refueling Interval

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18 months.

l 1.2.9 Startup '

l The reactorwith is reduced shall thebe considered intent of going in the startup mode when the shutdown m critical.

1.2.10 Romain Critfeal A technical specification that requires that the reactor shall not remain critical be shall mean completed withinthat an uninterrupted nomal hot shutdown procedure will 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

1.2.11 Tg At operating conditions T vg is defined as the arithmetic average of the coolant temperatures in t$e hot and cold legs of the loop with the greater number be made. of reactor coolant pumps operating, if such a distinction of loops can 1.2.12 Heatup - Cooldown Mode The heatup cooldown mode is the range of reactor coolant temperature greater than 200 F and less than 525 F.

1.3 OPERABLE A component or system is operable when it is capable of perfoming its intended function within the required range. The component or system shall be '

considered to have this capability when: (1) it satisfies the limiting conditions for operation defined in Specification 3, (2) it has been tested periodically in accordance with Specification 4, and has met its perfomance requirements. (3) the system has available its normal and emergency sources of power, and (4) its required auxf11 aries are capable of performing their intended function. When a system or component is determined to be inoperable solely.because its normal power source is inoperable or its emergency power source is inoperable, it may be considered OPERABLE for the pumose of satisfying the requirements of its applicable t,imiting Condition for Operation provided its redundant syst and emergency power source.em or component is OPERABLE with an OPERABLE nomal

• See page 1-2b i .

Amendment No. 38, 61. N/, 92 1-2

,a ome b ene =

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.- RANCHO SECO UNIT 1

, TECHNICAL SPECIFICATIONS Definitions EffUELING INTERVAL i For the following surveillance test, the " refueling interval" shall temporarily be extended to the Cycle 8 refueling outage, and the interval shall not be included in the computation of the maximum interval time combined as defined in Specification 1.9.

TS Number Description Table 4.1-2 13 Internal Vent Valve Tests

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'I This temporary definition of refueling interval shall expire upon startup l from the Cycle 8 refueling outage. l Amendment No. ES,f2,ff,E9,92 1-2b

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