ML20202H581

Amend 150 to License DPR-3,revising Possession Only License Through Three Changes to TS

ML20202H581
Person / Time
Site:	Yankee Rowe
Issue date:	02/03/1999
From:	Weiss S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20202H578	List: ML20202H574 ML20202H581 ML20202H587
References
NUDOCS 9902080128
Download: ML20202H581 (5)

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l p W 'o l k UNITED STATES i

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20566 0001

-YANKEE ATOMIC ELECTRIC COMPANY DOCKET NO.50-029 l YANKEE NUCLEAR POWER STATION l AMENDMENT TO POSSESSION ONLY LICENSE 1

i Amendment No.150 j License No. DPR-3 {

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1. The U.S. Nuclear Regulatory Commission (the Commission or the NRC) has found '

that:

A. The application for amendment filed by Yankee Atomic Electric Company (the licensee) dated August 20,1998, 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, l

B. The facility will be maintained in conformity with the application, 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 set forth in 10 CFR Chapter I; 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 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. Paragraph 2.C.(2) of Possession Only License No. DPR-3 is hereby amended to read as follows:

(2) TechnicaLSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.150 , are hereby incorporated in the license. The licensee shall possess and maintain the facility in accordance with the Technical Specifications.

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3. This license amendment will be effective on date of issuance.

1 FOR THE NUCLEAR REGULATORY COMMISSION l i

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f . W Seymdur H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation l

Attachment- J Technical Specification .,

Changes .

Date of issuance: February 3, 1999 )

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m ATTACHMENT TO LICENSE AMENDMENT NO.150 POSSESSION ONLY LICENSE NO. DPR-3 DOCKET NO. 50-29 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain

. vertical lines indicating the areas of change.

Remove Insert 1-2 1-2 1-3 ----

5.1 5.1 5.3 ----

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1.0 DEFINITIONS (Continued) _

l OFF-SITE 00SE CALCULATION MANUAL (ODCM) 1.6 The OFF-SITE DOSE CALCULATION MANUAL (00CM) contains the methodology and parameters used in the calculation of off-site doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.

The ODCM also contains (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Section 6.7, and (2) descriptions of the information that should be  !

included in the Annual Radiological Environmental Operating and Semiannual Radioactive Effluent Release Reports required by Specifications 6.8.2.a and 6.8.2.b.

OPERABLE - OPERABILITY 1.7 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function (s). Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, .'

electric power, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its safety function (s) are also capable of performing their necessary support function (s).

PROCESS CONTROL PROGRAM (PCP) l 1.8 The PROCESS CONTROL PROGRAM contains the current formulas, sampling, analyses, test (s), and determinations to be made to ensure that processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be occomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, state regulations, burial ground requirements, and other requirements, governing the disposal of solid radioactive waste.

REPORTABLE EVENT l

1.9 A REPORTABLE EVENT shall be any of those conditions specified in 10 1 CFR 50.73.

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YANKEE-ROWE l-2 L

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l 5.0 DESIGN FEATURES 5.1 SITE LOCATION The Yankee Nuclear Power Station is located in the town of Rowe, Massachusetts, three-quarters of a mile south of the Vermont-Massachusetts border. The site is at the bottom of a deep valley along the Deerfield River on the southeast bank of Sherman Reservoir. The geographical coordinates of the centerline of the reactor containment structure (Vapor Container) are as follows:

Latitude: N 42' 43' 41' Longitude: W 72' 55' 42' i.

5.2 FUEL STORAGE CRITICALITY

, 5.2.1 The spent fuel storage racks are designed and shall be maintained with a center-to-center distance betwebn fuel assemblies placed in the storage racks to ensure a k,gg equivalent to 0.95 with the spent fuel storage areas flooded with unborated water. The k,gg of 0.95 includes a conservative allowance of 3% Ak/k for uncertainties.

DRAINAGE 5.2.2 The spent fuel pit is designed and shall be maintained to prevent inadvertent draining of the pit.

CAPACITY 5.2.3 The spent fuel pit is designed and shall be maintained with a storage capacity limited to no more than 540 fuel assemblien.

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