ML20203N782

Amend 79 to License DPR-54,revising Min Required Boron Concentration in Primary Sys While Loading & Unloading Fuel from Reactor

ML20203N782
Person / Time
Site:	Rancho Seco
Issue date:	04/08/1986
From:	Stolz J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20203N776	List: ML20203N774 ML20203N782 ML20203N796
References
NUDOCS 8605060054
Download: ML20203N782 (5)

Text

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e atoq'o, UNITED STATES 8 o NUCLEAR REGULATORY COMMISSION

$ E WASHINGTON, D. C. 20555

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SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-54

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

A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated March 18, 1985, as supplemented by letter dated August 2, 1985, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the the provisions of the Act, and the rules and 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 common defense and security or to th: 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.

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

8605060054 860408 PDR ADOCK 05000312 P PDR

2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 79, 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 r hl)

/ Joi Stolz, Dire tor

P 1 Project Direc rate #6 ivision of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: April 8, 1986

1 ATTACHMENT TO LICENSE AMENDMENT N0. 79 FACILITY OPERATING LICENSE NO. DPR-54 DOCKET N0. 50-312 Replace the following pages of the Appendix "A" Technical Specifications

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

Remove Insert 3-44 3-44 3-45 3-45

RANCHO SECO UNIT 1 TECHNICAL SPECIFICATION

' Limiting Conditions for Operation 3.8 FUEL LOADING AND REFUELING Applicability Applies to fuel loading and refueling operations.

Objective To ensure that fuel loading and refueling operations are performed in a re-s'ponsible manner. .

Specification 3.8.1 Radiation levels in the reactor building refueling area shall be moni-tored by R15026 and R15027. Radiation levels in the spent fuel storage area shall be monitored by R15028. If any of these instruments becomes inoperable, portable survey instrumentation, having the appropriate ranges and sensitivity to fully protect individuals involved in refuel-ing operations, shall be used until the permanent Instrumentation is returned to service.

3.8.2 Core suberitical neutron flux shall be continuously monitored by at least two neutron flux monitors, each with continuous indication avall-able, whenever core geometry is being changed. When core geometry is not being changed, at least one neutron f tux monitor shall be in service.

3.8.3 Two decay heat removal pumps and coolers shall be operable. One decay heat removal pump and cooler shall be operable when the transfer can~al water level is above 37 feet.

3.8.4 During reactor vessel head removal and while loading and unloading fuel from the reactor, the boron concentration shall be maintained at not

' g less than 1974 ppm.

3.8.5 Direct communications between the control room and the refueling persen-nel in the reactor building shall exist whenever changes in core geome-try are.taking place. .

3.8.6 During the handling of irradiated fuel in the reactor building at least i

one door on the personnel and emergency hatches shall be closed. The equipment hatch cover shall be in place with a minimum of four bolts securing the cover to the sealing surfaces.

3.8.7 isolation valves in lines containing automatic containment isolation valves shall be operable, or at least one shall be in a safety featu*es position.

3~ 4 Amendment No. 27, Ji,79 W

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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATION Limiting Conditions for Operation 3.8.8 When two irradiated fuel assemblies are being handled si,multaneously within the fuel transfer canal, a minimum of 10 feet separation shall be maintained between the assemblies at all times. Irradiated fuel as-semblies may be handled with the auxiliary bridge crane provided no other irradiated fuel assembly is being handled in the fuel transfer canal. . .

3.8.9 If any of the above specified limiting conditions for fuel loading and

. refueling are not met, movement of fuel into the reactor core shall cease; action shall be Initiated to correct the conditions so that the specified limits are met, and no operations which may increase the re-activity of the core shall be made.

3.8.10 The reactor building purge system, including the radiation monitors, R15001A and R150018, shall be tested and verified to be operable ir.med-lately prior to refueling operations.

3.8.11 Irradiated fuel shall not be removed from the reactor until -the unit has been suberitical for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

3.8.12 No loads will be handled over irradiated fuel stored in the spent fuel pool, except the fuel assemblies themselves. A dead weight load test at the rated load will be performed on the fuel sto' rage building handl-ing bridge prior to each refueling.

Bases Detailed written procedures will be available for use by refueling personnel.

These procedures, the above specifications, and the design of the fuel handling equipment, as described in subsection 9.7 of the FSAR Incorporating built-in interlocks and safety features, provide assurance that no incident could occur during the refueling operations that would result in a hazard to public health and safety. If no change is being made in core geometry, one flux monitor is sufficient. This permits maintenance on the instrumentation. Ccntinuous mon-itoring of radiation levels and neutron flux provides immediate indication of an unsafe condition. The decay heat removal pump is used to maintain a uni-form boron concentration.3 The refueling boron concentration indicated in Spec,ification 3.8.4 will be maintained to ensure that the more restrictive of the following reactivity conditions is met:

! 1. Either a k,pf of 0.95 or less,with all control rods removed from the core.

2. A boron concentration of >1800 ppm.

The actual calculated boron concentration for item (1) above is 1974 ppm boron. Specification 3.8.5 allows the control room operator to inform the reactor building personnel of any impending unsafe condition detected from the main control board indicators during fuel movement.

The Specification requiring testing reactor building purge termination is to verify that these components will function as required should a fuel handling accident occur that results in the release of significant fission products.

Amendment No. J8y', II, 79 3-45

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