ML20207F214

Amend 62 to License DPR-34,deleting Ref in App B of Tech Specs to 10CFR51.5(b)2

ML20207F214
Person / Time
Site:	Fort Saint Vrain
Issue date:	08/05/1988
From:	Calvo J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20207F185	List: ML20207F180 ML20207F214 ML20207F241
References
NUDOCS 8808180239
Download: ML20207F214 (4)

Text

.

1. o UNITED STATES

. y

' ~,,

g E

NUCLEAR REGULATORY COMMISSION W ASHING TO N. D. C. 20665 o t s.,...../

PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. b2 License No. DPR-34

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

A. The application for atendment by Public Service Company of Colorado (the licensee) dated April 20, 1988, corplies with the standards and re asamended(theAct)quirementsoftheAtomicEnergyActof1954,

, and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in confomity with the application, as amended, the provisions of the Act, and the rules and regulations of the Comission; C. There is reasonable assurance: (1)thattheactivitiesauthorized by this arendment can be conducted without endangering the healtt.

and safety of the public, and (ii) that such activities will be conducted ~n compliance with the Comission's regulations; D. The issuance of this license amendment will not be inimical to the comon 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.

4 e

b P

2-

?. Accordingly, the Itcense is amended by changes to the Technical Specifications as indicated in the attachment to this licer.se amendment, and paragraph 2.0.(0) cf Facility Operatirg License ho. DpR-34 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 62, are hereby incorporated in the licerse. The licensee shall operate the facility in accordance with the Technical Specifications.

3. The license amendment is effective as of its date of issuance.

FOR THE HUCLEAR REGULATORY COMMISSION

'd. G< G

> Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 5,1988 4

4

1 ATTACHMENT TO LICENSE AMENDMENT NO. 62 TO FACILITY OPERATING LICENSE NO. OPR-34 DOCKET NO. 50-267 Replace the following page of the Appendix B Technical Specifications with the attached page as indicated. The revised page is identified by amendment number and contains a vertical line indicating the area of change.

Remove Insert 4 of 9 4 of 9 4

9

Fort St. Vrain #1 Non-Radiological Technical foe:ificatiens Amendment #A$,62 Page 4 of 9 expariments which do not affect the environment are not subject to this requirement.

Before engaging in construction or operational activities which may affect the environment, the licensee shall perforni in environmental evaluation of such activity.*

When the evaluation indicates that such activity involves  ;

an unreviewed environmental question, the licensee shall l provide a written evaluation of such activities and obtain prior approval from the Nuclear Regulatory Commission.

A proposed change, test, or experiment shsll be deemed to involve an unreviewed environmental question if it concerns 1)a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the FE5 as modified by staff's testimony to the Atomic Safety and Licen'sina Board, supplements to the FES, environmental impact appraisals, or in any dectsions of the Atomic Safety and Licensing Board; or 2) a l ' significant change in effluents or power level; or 3) a matter not previously reviewed and evaluated in the documents specified in 1) of this subsection, which siay have a significant adverse environmental impact.

' Activities are excluded from this requirsment if all measurable non-radiological effects are confined to the on-site areas previously disturbed during site preparation, plant construction, and previous plant operation.

.