ML20154A675

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Safety Evaluation Supporting Amend 113 to License DPR-40
ML20154A675
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 05/04/1988
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20154A667 List:
References
NUDOCS 8805160089
Download: ML20154A675 (3)


Text

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g NUCLEAR REGULATORY COMMISSION W ASHINGTON, D. C. 20556

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENCMENT NO.113TO FACILITY OPERATING LICENSE NO. OPR-40 OMAHA PUBLIC POWER DISTRICT FORT C/ d IN STATION, UNIT NO.1 DOCKET NO. 50-285

1.0 INTRODUCTION

By letter dated February 8,1988, Omaha Public Power District, the licensee for Fort Calhoun Station Unit No. 1, requested a license amendment to revise their Technical Specifications (TS) (Ref. 1). The proposed arendrent concerns the release of radioactive effluents from Fort Calhoun.

The amendment would: (1) relax the current TS requirement to control airborne radioactive effluents on an instantaneous basis; (2) allow the licensee to use a non-standard fonnat for reporting radioactive effluent releases; (3) allow the licensee to use annual average (rather than real-time) meteorological dispersion factors to calculate doses; and (4) correct and clarify some parts of TS 2.9.1 and 5.9.4. However, items I and 2 were not approved by the staff.

2.0 EVALUATION Iten 1 - Instantaneous Releases TS 2.9.1 (page 2-40) currently requires that the concentrations of radioactive materials released to unrestricted areas shall be kept within i

the limits of 10 CFR Part 20. ne licensee has proposed amending this TS (and a corresponding change to the Basis for TS 2.9.1 on page 2-46) to state that "to ensure that these releases result in an annual dose frer radioactive materials in liquid and gaseous effluents released to unrestricted areas that are within the limits specified in 10 CFR Part 20." The effect of this change (and a corresponding change to TS 2.9.1(2)a(i) on page 2 43 to delete "instantaneous") would be to allow the licensee to exceed the concentrations specified in 10 CFR Part 20 l en the "instantaneous basis."

l The staff finds the proposed change unacceptable because it would allow the licensee to exceed the concentrations in 10 CFR Part 20 on an instan-teneous basis; this wculd not be consistent with the standard technical specifications.

Iten 2 - Radioactive Effluent Reports l

The licensec propos::s to change TS 5.9.4.a to delete the phrase "as I outlined in Regulatory Guide 1.21. Revision 1" from the Radioactive Effluent Release Reporting requirements. The proposed change would allow 8e05160089 080504 5 PDR ADOCK 050 l P

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the licensee more flexibility in fonnatting their radioactive effluent release reports. The staff finds this change unacceptable since the licensee would no longer be required to use a standard fonnat to report the quantities of radioactive effluents released from Fort Calhoun.

Item 3 - Meteorological Dispersion The licensee proposes to add a sentence to TS 2.9.2(2)a(i) (page 2-43) that states: "Unrestricted area concentrations shall be calculated based on the annual average Chi /Q [i.e., the symbols for a reteorological disperson factor]." A corresponding change is proposed for TS 2.9.1(2)b on page 2-43. The change would delete the reference to calculating doses in "each of the 16 cardinal sectors" since the licensee states that doses for each calendar quarter will be calculated to an individual in the mest limiting sector. The staff has previously approved the use of an annual average Chi /Q as an alternative to real-time meteorology for estimating doses from exposure to radioactive effluents released from nuclear power plants. The staff finds the proposed changes acceptable.

Item 4 - Corrections and Clarifications The 'icensee proposes to correct a typographical crror in TS 2.9.l(1)a(i)

(page 2-41) by changing "millicure/ milliliter" to microcurie / milliliter."

The licensee proposes to calrify TS 2.g.1(2)a(1) on page 2-43 so that it refers to "Table 2" of 10 CFR Part 20, Appendix B. Another clarification consists of changing TS 5.9.4a on page 5-15 so that it refers to the "requirerents of 10 CFR 50.36a." The staff finds these typographical changes acceptable.

3.0

SUMMARY

The staff has reviewed Omaha Public Power District's proposed arendrent regarding the release of radioactive effluents from Fort Calhoun. The staff finds Items 1 and 2 unacceptable for the reasons noted in the report. The staff finds that Iter.s 3 and 4 meet the applicable regulatory guidance and recuirements and are therefore acceptable.

4.0 ENVIPONMENTAL CONSIDERATION The amendment involves a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.

The staff has determined that the amendrent involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposures.

The Comission has previously issued a proposed finding that the arendrent involves no significant hazards consideration and there has been ne public comrent on such finding. Accordingly, the amendment reets the eligibility criteria for categorical exclusion set forth in 10 CFR Section 51.22(c)(9).

Pursuant to 10 CFR 51.22(b), no environmental impact statement or environ-rental assessment need be prepared in connectio'i with the issuance of the amendt.ent .

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5.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that:

(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the preposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

6.0 REFERENCES

1. Letter from R. L. Andrews, Omaha Public Pcwer District, to U. S.

Nuclear Regulatory Connission, dated February 8,1988.

Date: May 4,1988 Principal Centributors: Edward F. Branagan, Jr.

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