ML20198G827

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Safety Evaluation Supporting Amend 125 to License DPR-54
ML20198G827
Person / Time
Site: Rancho Seco
Issue date: 08/22/1997
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20198G819 List:
References
NUDOCS 9709050118
Download: ML20198G827 (5)


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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.12sTO FACILITY OPERATING LICENSE (POSSESSION ONLY) NO. DPR-54 SACRAMENTO MUNICIPAL UTILITY DISTRICT RANCHO SECO NUCLEAR GENERATING STATION DOCKET NO. 50-312 1.0 Introduction By letter dated December 9, 1993, as superseded on December 19, 1995, and as supplemented on January 22, 1996, Sacramento Municipal Utility District (the licensee), submitted proposed changes to the Rancho Seco Nuclear Generating Station Permanently Defueled Technical Specifications (PDTS) to incorporate the revised 10 CFR Part 20.

Other changes not related to 10 CFR Part 20 were also submitted.

2.0 Evaluation The licensee has revised the TS to include wording that is consistent with the revised 10 CFR Part 20, Standards for Protection Aaainst Radiation, and will retain the same overall level of effluent control required to meet the design objectives of Appendix I to 10 CFR Part 50.

The proposed TS changes and evaluations follow:

1.

Technical Spect scation D3.6 - LIQUID HOLD-UP TANKS The licensee has proposed to change the title of the " Semi annual Radioactive Effluent Release Report" to the " Annual Radioactive Effluent Release Report."

The change is administrative in nature and is acceptable because the licensee received approval to change the frequency of submitting this report to annual in the Issuance of Amendment No. 122, 2.

Technical Specification D3/4.6 - LIQUID HOLD-UP TANKS The licensee has proposed to change the bases for the liquid holdup tanks to change a 10 CFR Part 20 reference from "10 CFR 20, Appendix B, Table II, Column 2" to "10 CFR 20 Appendix B, Table 2, Column 2."

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. The change is administrative in nature to incorporate a revised reference to 10 CFR Part 20 and is acceptable.

3.

Technical Specifications D6.6 - LICENSEE EVENT REPORT ACTION The licensee has proposed to replace the 10 CFR Part 20 reference of "20.405" with "20.2203."

This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.

4.

Technical Specification D6.8.3a - RADI0 ACTIVE EFFLUENT CONTROLS PROGRAM The licensee has proposed to change a 10 CFR Part 20 reference from "10 CFR Part 20, Appendix B, Table II, Column 2d to "10 CFR Part 20, Appendix B, Table 2, Column 2."

This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 reference and is acceptable.

5.

Technical Specification D6.8.3a - RADI0 ACTIVE EFFLUENT CONTROLS PROGRAM The licensee has proposed to change the 10 CFR Part 20 reference of "20.106" to "20.1302."

This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.

6.

Technical Specification D6.8.3a - RADI0 ACTIVE EFFLUENT CONTROLS PROGRAM The licensee has proposed to revise this specification to read as follows:

" Limitations on the dose rate resulting from radioactive hiaterial released in gaseous effluents from the site to areas at or beyond the SITE BOUNDARY shall be limited to the following:

a)

For noble gases:

Less than or equal to a dose rate of 500 mrems/yr to the total body and less than or equal to a dose rate of 3000 mrems/yr to the skin; and, b) For tritium and for all radionuclides 'in particulate form with half-lives greater than 8 days:

Less than or equal to a dose rate of 1500 mrems/yr to any ccgan."

The change re-introduces the previously approved instantaneous gaseous effluent dose rate limits that once resided in the licensee's Radiological Effluent Technical Specifications and are now in the licensee's Off-site Dose Calculation Manual. The change is proposed in

3-order to retain operkt onal flexibility consistent with Appendix I to 10 i

CFR 50, concurrent v J.h the implementation of the revised 10 CFR Part 20.

The proposed change will retain the same overall level of effluent control required to meet the design objectives of Appendix I to 10 CFR 50.

The specification is based on NUREG-0133 and is acceptable as a dose rate limit for gaseous effluents. The limit applies at all times as an assurance that the dose design objectives in Appendix I to 10 CFR Part 50 are not likely to be exceeded. The licensee maintains that the proposed specification is not expected to have a negative impact on the ability to operate within the design objectives of Appendix I to 10 CFR Part 50 and 40 CFR Part 190.

A Based on the aoove, it is acceptable that the gaseous release rate TS for radioactive material be based on the stated dose rates.

7.

Technical Specification D6.9.1 - ROUT!NE REPORTS The licensee has proposed to change the reference to the NRC Regional Office from " Region V" to " Region IV."

The change is administrative in nature and is acceptable.

8.

Technical Specification D6.9.2.1 - ANNUAL litulVIDUAL MONITORING RESULT REPORT The licensee has proposed to replace the 10 CFR Part 20 reference of "20.407" with "20.2206."

This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.

9.

Technical Specificatior D6.9.5 - LICENSEE EVENT REPORT The licensee has proposed to replace the 10 CFR Part 20 reference of "20.405" with "20.2203."

This change is administratit, in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.

10.

Technical Specification D6.9.5 - LICENSEE EVENT REPORT The licensee has proposed to change the reference to the NRC Regional Office from " Region V" to " Region IV."

The change is administrative in nature and is acceptable,

11. Technical Specification D6.9.7 - SPECIAL REPORTS i

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The licensee has proposed to change the reference to the NRC Regional Office from " Region V" to " Region IV."

The change is administrative in nature and is acceptable

12. Technical Specification D6.12 - HIGH RADIATION AREAS The licensee has proposed to replace the 10 CFR Part 20 reference of "20.203" with "20.1601."

This change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.

13.

Technical Specif"ation D6.12 - HIGH %DIATION AREAS The licensee has proposed to add an upper limit for which the TS opplies by adding the words "but less than 500 rads /hr."

The change is consistent with the revised 10 CFR Part 20 and is acceptable.

14. Technical Specification 06.14 - 0FF-SITE DOSE CALCULATION AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUALS The licensee has proposed to change the 10 CFR Part 20 reference of "20.106" to "20.1302."

TMs change is administrative in nature to incorporate the corresponding revised 10 CFR Part 20 section number and is acceptable.

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15. Technical Specification D6.14 - 0FF-SITE DOSE CALCULATION AND RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MANUALS The licensee has proposed to enange the title of the " Semi annual Radioactive Effluent Release Report" to the " Annual Radioactive Effluent Release Report".

This change is administrative in nature and is acceptable because the licensee received approval to change the frequency of submitting this report to annual in the Issuance of Amendment No. 122.

3.0 STATE CONSULTATION

In accordance with the Commission's reguiations, the Caittornia State official was notified of the proposed issuance of this amendment.

The State official had no comments.

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4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes requirements with respect to recordkeeping, reporting, or administrative procedures or requirements and changes requirements with respect to the installation or use of facility components located within the restricted area as defined by 10 CFR Part 20. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (59 FR' 10015). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).

Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

5.0 CONCLUSION

The Commission 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 proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment wi not be inimical to the common defense and security or to the health ans safety of the public.

Principal Contributor: Stephen Klementowicz Date: August 22, 1997 J

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