ML20128Q983

Amend 89 to License DPR-40,adding Tech Specs That Require Licensee to Implement & Maintain Program to Ensure Capability to Obtain & Analyze Reactor Coolant Sample Under Accident Conditions

ML20128Q983
Person / Time
Site:	Fort Calhoun
Issue date:	05/24/1985
From:	Tourigny E Office of Nuclear Reactor Regulation
To:
Shared Package
ML20128Q965	List: ML20128Q962 ML20128Q983 ML20128R004
References
NUDOCS 8506040367
Download: ML20128Q983 (4)

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- $2 Kfg g UNITED STATES 4; g NUCLEAR REGULATORY COMMISSION

j WASHINGTON, D. C. 20555 l

OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1-AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No. DPR-40

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

A. The application for amendment by the Omaha Public Power District (the licensee) dated March 8,1985 complies with the standards and requirements 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 cperate 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 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.

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I l' 8506040367 850524 PDR ADOCK 05000285 l P ,

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2. Accordingly, Facility Operating License No. DPR-40 is amended by changes to the Technical Specifications as indicated in the attachment to this license' amendment, and paragraph 3.B. of Facility Operating License No.

DPR-40 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 89 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective within thirty days of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION (Af f,&y E. G. Tourigny,(Acting Chief Operating Reactors Branch #3 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 24, 1985

ATTACHMENT TO LICENSE AMENDMENT N0'. 89 FACILITY OPERATING LICENSE NO. DPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised page is identified by amendment number and contains vertical lines indicating -

the area of change.

Remove Page Insert Page 5-21 5-21 i

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5.0 ADMINISTRATIVE CONTROLS 5.14 Systems Integrity A program to reduce leakage from systems outside containment that would or could contain highly radioactive fluids during a serious transient or accident to as low as practical levels shall be implemented. This program shall include the following:

1. Provisions establishing preventive maintenance and periodic visual c inspection requirements, and

2. Integrated leak test requirements for each system at a frequency not to exceed refueling cycle intervals.

s 5.15 _ Post-Accident Radiological Sampling and Monitoring

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The following programs shall be implemented and maintained to ensure the capability to accurately monitor and/or sample and analyze radiological effluents and concentrations in a post-accident condition:

1. A program which will ensure the capability to accurately determine the airborne iodine concentration in vital areas under accident conditions. (Any space which will require occupancy to permit an operator to aid in mitigation of, or recovery from, an accident is designated as vital.)

2. A program which will ensure the capability to obtain and analyze radioactive iodines and particulates in plant gaseous effluents.

-3. A program which will ensure the capability to obtain and analyze a reactor coolant liquid sample under accident conditions.

4. A program which will ensure the capability to obtain and analyze a containment atmosphere sample under accident conditions.

These programs shall include the following:

l' . Training of personnel.

2. Procedures for monitoring and/or sampling and analysis.

3. Provisions for maintenance of sampling and analysis equipment.

5-21 Amendment No. 57,80,89