ML20136A727

Amend 78 to License DPR-54,revising Tech Specs to Define Requirements for Calibr of power-range Neutron Instrumentation

ML20136A727
Person / Time
Site:	Rancho Seco
Issue date:	12/24/1985
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20136A719	List: ML20136A715 ML20136A727 ML20136A751
References
NUDOCS 8601020260
Download: ML20136A727 (5)

Text

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.- 'o l ' s, ,,[go UNITED STATES p> NUOLEAR REGULATORY COMMIS310N ec.

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WASHINGTOrJ, D. C. 20555 s.:....Y.

SACHAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPEpATING LICENSE Amendment No. 78 License No. OPR-54 1.

The Nuclear Regulatory Comission (the Comission) has found that:

A.

The application for amendment by Sacramento' Municipal Utility District (the licenseel dated June 6,1983, as supplemented by letters of June 29,1983; April 3. July 11 and November 28, 1984; and February 8 and April 3,1985, complies with the standards and requirements of the Atomic Energy-Act of 1954, as amended (the Act),

ChapterandI;the Commission's rules and regulations set forth in 10 CFR B.

The facility will . operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.

There is reasonable assurance (i) that the activities authori:ed 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by charges to the Technical Specifications as indicated in the attachment to this license amsndment, and paragraph 2.C.(2) of Facility Operating License No. DPR-54 is hereby amended to read as follows:

8601020260 851224 yDR ADOCK 0500033y PDR

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• Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 78 . are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

[ WL John F. Stolz.. Director PWR Pro,1ect Directorate #6 Division of PWR Licensing-B

Attachment:

Chances to the Technical Specifications Date of Issuance: December 24, 1985

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ATTACWENT TO LICEt!5E A'4Ef!D"ENT NO. 78

_ FACILITY OPERATING LICENSE-NO. DPR-54 DOCKET NO. 50-31?

Replace the following pages of the Appendix "A" Technical Specifications i

with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.

j Remove insert A-2 4-2 t

4-3 4-3 4

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RANCHO SECO UNI", 1 TECHNICAL SPECIFICATIONS Surveillance Standards Calibration

• Calibration shall be performed to assure the presentation and acquisition of accurate information. The nuclear flux (power range) channels amplifiers shall be calibrated (during steady state operating conditions) against a heat balance standard whenever the Nuclear Instrumentation indication is 10 percent or more above the corn t,hermal power or 2 percent or more below the core thensal power.

Channels subject only to " drift" errors induced within the instrumentation itself and consequently, can' tolerate longer intervals between calibrations. ..

Process system instrumentation errors induced by drift can be expected to remain within acceptable tolerances if recalibrati.on is performed at the intervals of each refueling period.

Substantial calibration s'hifts within a channel-(essentially a channel failure) will be revealed during routine checking and testing procedures.

Thus, minimum calibration frequencies set forth are considered acceptable.

Testing The frequency of on-line testing of reactor protective channels as shown in table 4.1-1 will assure the required level of performance.

The equipment testing and system sampling frequencies specified in ' table ~

4.1-2 and table 4.1-3 are considered edgquate to maintain the equipment and systems in a safe operational status.(13 Power Distribution Mapping The incore instrumentation detector system will provide a .teans of assuring that axial and radial power peaks and the peak locations are being controlled by the provisions of the Technical Specifications witnin the limits employed in the safety analysis.

REFERENCES (1) FSAR paragraph 1.4.12.

Amendment No. 78 4-2 m..

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ItMJCalU SLLO Utill I

• litil*llCAl. SPECIFICAll015

• surveillance Standards lat,le 4,1-1 IllSilttMNT StmVEILI AelCC RitglRIMINIS Channel De'scrlPtion (, heck lest Cellbrate Rrmarks Reactnr Prctective Systy

1. Sourte range channel S (1) P NA - II) When in service.

2. Intermediate range channel S, P NA .

3. Power range amplifler S.(1) NA (2) (1), Heat balance check each shif t.

a (2) lleat balance calibration will be conducted whenever the Nuclear Instrumentation indication is IDE above the core therwal power or 21 below the core thermal power.

4. Power range channel M S

M !!.2) (1) Using incore instrumentation for split detector callbration. .

4 (2) Imbalance. upper and lower chambers at equilibrium menon af ter each startup If not done the previous week.

-S. liigh reactor coolant ,

pressure channel 5 H N

6. Low reactor coolant Pressure channel 5 H R

7. Reactor coolant temperature ~

channel S H R 43 Amendment No. 78 G.

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