ML20141F695

Amend 45 to License DPR-45,authorizing Addition of New Paragraph 4.1.6 to Tech Specs,Requiring Reactor Shutdown When Plant in Conditions 1,2 or 3 & Mississippi River Level Expected to Exceed 640 Ft

ML20141F695
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	01/06/1986
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20141F681	List: ML20141F678 ML20141F695 ML20141F983
References
NUDOCS 8601090517
Download: ML20141F695 (4)

Text

4 UNITED STATES p 't, NUCLEAR REGULATORY COMMISSION g

o

,y CASHINGTON, D. C. 20555 e

s , , , s

• DAIRYLAND POWER COOPERATIVE DOCKET NO. 50-409 LA CROSSE BOILING WATER REACTOR AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 45 License No. DPR-45

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

A. The application for amendment by Dairyland Power Cooperative (the licensee) dated December 19, 1983 as revised June 25, 1985 complies with the standards and requirement: of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 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 (1) 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 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.

l 8601090517 860106 PDR ADOCK 05000409 P PDR

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 Provisional Operating License No. DPR-45 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A issued October 31, 1969, with Authorization No. DPRA-6, as revised through Amendment No. 45, 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 the date of its issuance.

FOR THE NUCLEAR REGULATORY C(plSSION kk1 John A. Zwolinski, Director

(,

BWR roject Directorate #1 Division of BWR Licensing

Attachment:

5 Changes to the Technical Specifications

Date of Issuance

Janua:y 6,1986 8

e - - - , , - ,

ATTACHMENT TO LICENSE AMENDMENT NO. 45 PROVISIONAL OPERATING LICENSE N0. DPR-45 DOCKET NO. 50-409 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 28 28 1

4.1 CENERAL ,

I 4.1.3 During periods when the reactor is in CONDITION 3, 4, or 5, either )

Channel 1 or 2 of the Nuclear Instrumentation System shall be in operation and shall be monitored by the operator.

4.1.4 Whenever the reactor contains one or more fuel elements, any operations from points outside the control toom of equipment which may affect the reactor shall be conducted under the direction, or with the knowledge, of the control room operator.

4.1.5 If the plant is operational during a tornado warning, the Shift Supervisor on duty shall keep informed of the actual tornado activity which may approach the plant. In the event that reports indicate an imminent tornado strike at or near the LACBWR plant, the Shift Supervisor shall reduce reactor power to a level which permits prompt reduction of power generation to station load. However, the Shif t Supervisor shall be instructed to -

discontinue plant operation if, in his judgment, this action is required to ensure plant safety.

4.1.6 If the plant in in CONDITION 1, 2, or 3 and the Mississippi River level adjacent to the plant reaches 639.2' and is predicted to exceed 640', commence reactor shutdown and be in CONDITION 4 prior to the river level exceeding 640'.

4.2 OPERATING LIMITS 4.2.1 Reactor Building 4.2.1.1 CONTAINMENT INTEGRITY shall be maintained in Conditions 1, 2, 3 and during:

(a) CORE ALTERATIONS, (b) handling of irradiated fuel, or (c) there is fuel in the reactor and any control rod is withdrawn.

Amendment No. 25, 34, 45

. .._ _ _ __ _ _. __-.- _ .