ML20247Q652

Discusses How NRC Evaluation of Radioactive Effluent Releases from Plant Affected Licensee Representatives Act & Conduct During Time of Concern,Per Request.Nrc Decision Not to Issue Variance for Continued Operation Affirmed

ML20247Q652
Person / Time
Site:	Rancho Seco
Issue date:	11/12/1987
From:	Scarano R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Marsh R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20247Q579	List: IA-89-225, Forwards Matls W/Similarities to Matters Presently Being Worked on ML20247Q576 ML20247Q652 ML20247Q683 ML20247Q702 ML20247Q732 ML20247Q751
References
FOIA-89-225 NUDOCS 8908070217
Download: ML20247Q652 (2)

Text

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MEMORANDUM FOR: Robert G. Marsh, Director i Office of Investigations, Field Office, Region V FROM: Ross A. Scarano, Director  !

Division of Radiation Safety and Safeguards

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SUBJECT:

REPORTING OF RADI0 ACTIVE EFFLUENTS RELEASED  !

FROM RANCHO SEC0 NUCLEAR GENERATING STATION I

This is in response to your request to define how our evaluation of l radioactive effluent releases from Rancho Seco was affected by the acts l and conduct of licensee representatives during the time of concern.  ;

10 CFR 50.36a requiring technical specifications on effluents from nuclear 4 power reactors states in (a)(2) "Each licensee shall submit a report to the '

Commission within 60 days after January 1 and July 1 of each year, that specifies the quantity of each of the principal radionuclides released to unrestricted areas in liquid and in gaseous effluents during the previous six l months of operation, including any other information as may be required by 1 the Commission to estimate maximum potential annual radiation doses to the public resulting from effluent releases." {

Licensee Technical Specification 6.9.2.3 Semiannual Radioactive Effluent Release Resort specifically implements this requirement on the Sacramento Municipal Utility District.

On July 21, 1984, the licensee implemented Amendment No. 53 to the RSNGS Technical Specifications (T.S.). This amendment incorporated 10 CFR 50 Appendix I, Numerical Guides for Design Objectives and Limiting Conditions-for Operation to Meet the Criterion "As low As Is Reasonably Achievable" for

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Radioactive Material in Light-Water Cooled Nucleir Power Reactor Effluents, requirements into the T.S.

l The licensee submitted Special Report No. 84-07, on September 27, 1984, (RJR 84-425) as required by T.S. 3.17.2 and 3.25 to report that the cumulative calculated radiological exposure resulting from liquid effluents exceeded the calendar quarter and calendar year dose limits of T.S. 3.17.2 and fuel cycle dose limit (40 CFR 190) of T.S. 3.25 for calendar year 1984 through August 31, 1984. In their September 27, 1984 letter, they stated that, "The District now is limitir.g its discharges so that 10 CFR 50 Appendix I limits will not be exceeded." In their " Attachment to Special Report 84-07" the licensee presented their near and long term corrective actions. In response to this licensee submittal, NRC issued a letter dated November 15, 1984 which concluded, based on the corrective actions taken and planned, that a variance for continued operation pursuant to 40 CFR 190.11 was not needed.  ;

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R. Marsh )

It is NRC Region V's responsibility to review Semiannual Radioactive Effluent j Release Reports and to verify selected dose calculations in order for the Commission to implement its responsibilities pursuant to 40 CFR 190.

a The NRC's review of Table 2A of the licensee's. Semiannual Radioactive ~ Effluent Release Report dated September 26, 1985, which stated "no releases containing i detectable fission or activation products were made in the period of January 1 through June 1985" resulted in no effort to perform a dose calculation to )

estimate the maximum potential annual radiation dose to a member of the public i from this source. )

Review and acceptance of the licensee's statement that no detectable radioactive materials were released, caused the Region to believe that the licensee was implementing the commitment to comply with the dose objectives of 10 CFR 50 Appendix 1, which is less than the 40 CFR 190 limit, thereby affirming the appropriateness of the NRC's decision not'to issue a-variance for continued operation.

Should you have any questions regarding this matter, please feel free to.

contact me directly.

Gd W Ross A. Scarano, Director Division of Radiation Safety and Safeguards i

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