ML20206B225

Amend 106 to License DPR-40,changing Tech Specs to Modify Surveillance Requirements for Hydrogen & Oxygen Monitoring Sys for Waste Gas Decay Tanks to Clarify That Daily Channel Check Required for Sys When in Svc

ML20206B225
Person / Time
Site:	Fort Calhoun
Issue date:	03/26/1987
From:	Thadani A Office of Nuclear Reactor Regulation
To:
Shared Package
ML20206B224	List: ML20206B219 ML20206B225 ML20206B239
References
TAC-64445, NUDOCS 8704090029
Download: ML20206B225 (4)

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<f o,, UNITED STATES

! o NUCLEAR REGULATORY COMMISSION

, h s WASHINGTON. D. C. 20555

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OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. DPR-40

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

A. The application for amendment by the Omaha Public Power District (the licensee) dated January 7, 1986 [ Sic](1987) 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 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 wfll 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 i have been satisfied. j l

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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. 105 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

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3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B

Attachment:

Changes to the Technical Specifications Date of Issuance: March 26,1987 1

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ATTACHMENT TO LICENSE AMENDMENT NO.106 FACILITY OPERATING LICENSE NO. OPR-40 DOCKET NO. 50-285 Revise Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Peges Insert Pages 3-71 3-71 l

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3.0 SURVEILLANCE REQUIREMENTS 3.12 Radiological Waste Sampling and Monitoring (Continued) 3.12.1 ~ Liquid and Gaseous Effluents'(Continued)

(iii) Quarterly channel functional test.

(iv) Channel calibration at "R" frequency (every 18 months).

d. The hydrogen and oxygen monitoring system for the gas decay tanks shall have a:

(i) Daily channel check (when in service).  !

(ii) Monthly cross comparison with a grab sample.

! (iii) Quarterly channel calibration using gas mixtures with concentrations in the range of interest.

e. Records shall be maintained and reports of the sampling and

, results of analyses shall be submitted to the Comission in accordance with Section 5.9.4.a of these specifications.

1 Basis The surveillance requirements given under Specification 3.12.1(2) provide assurance that radioactive gaseous effluents from the station are properly controlled and monitored over the life of the station in conformance with the requirements of General Design Criteria 60 and 64 of 10 CFR Part 50, Appendix A. These surveillance requirements provide the oata for the licensee and the Comission to evaluate the perfonnance of the station relative to radioactive gaseous wastes released to the environment. The existing minimum sensitivity of airborne effluent monitor RM-062 is SE-06 mci /cc/100 cpm and this minimum sensitivity shall be maintained if the monitor is replaced. Reports on the quantities of the radioactive materials released in gaseous effluents shall be furnished to the Comis-sion on the basis of Section 5.9.4.a of these Technical Specifications.

On the bas.is of such reports and any additional information the Commission i

may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Commission deems appropriate.

i The surveillance requirements given under Specification 3.12.l(1) provide assurance that liquid wastes are properly controlled and monitored in confonnance with the requirements of General Design Criteria 60 and 64 of 10 CFR Part 50, Appendix A, during any planned release of radioactive i

materials in liquid effluents. These surveillance requirements provide the data for the licensee and the Commission to evaluate the station's performance relative to radioactive liquid wastes released to the environ-ment. Reports on the quantities of radioactive materials released in liquid effluents shall be furnished to the Comission on the basis of Section 5.9.4.a of these Technical Specifications. On the basis of such reports and any additional information the Comission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such action as the Comission deems appropriate.

3-71 Amendment No. g/, 106

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