ML20031G771
| ML20031G771 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/06/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20031G768 | List: |
| References | |
| TAC-43285, NUDOCS 8110230641 | |
| Download: ML20031G771 (5) | |
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A UNITED STATES "g
NUCLEAR REGULATORY COMMisslON 4
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WASHINGTON,0. C. 20558
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%t SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.36 License No. DPR-54 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Sacramento Municipal Utility District (the licensee) dated December 17, 1980, complies with the standards and re as amended (the Act)quirements of the Atomic Energy Act of 1954, and the Commission's rules and-regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confomity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) 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 comon 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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2 Accordingly, Facility Op(erating. License No. DPR-54 is hereby amended 2.
fications as indicated in the attachment to this license amendment:
2.C.(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 36, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its
. issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ohn Stolz.. Chief e ating Reactors Branch f4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: October 6,1981 T
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e ATTACHMENT TO LICENSE AMENDMENT NO.2G FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 4
Replace the following pages of the Appendix "B" Technical Specifications with the enclosed pages as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Pages 20 21 T
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Table 2.6-1 8
RADIOACTIVE LIQUID SA}1PLING AND ANALYSIS Liquid Sampling Type of Detectable Source Frequency Activity A}alysis Concentra ipns.
(pci/ml) 3J A.
Tank Batch Releasea Each Batch Individual Camma Enitters 5 x 10-7 (2)
One Batch /tfonth Dissolved Cases 10-5 Ucekly Composite Ba-La-140, I-131 10-0 8
g S r-89 5 x 10-8
-5 Honthly Composite 11-3 10
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Cross 4*
10 I1)
-8
__ Quarterly Ccmposite Sr-90 5 x 10
-7 B.
Misc'ellaneous Water Each Batch Individual Camma Emitters 5 x 10 Evaporator * (5)
-5 11 - 3 10
-8 tlouthly Composite Sr-89, 90 5 x 10 Cross a~
10 Miscellaneous Water Evaporatos release is via y,aseous pathway.
e Table 2.6-1 (Continued)
NOTES:
(1)
A composite sample is one in which the quantity of liquid sempled is proportional to the quantity of liquid waste discharged from the plant.
(2)
For certain mixtures of ga==a eritters, it may not be possible to measure radionuclides in concentrations near their sensitivity limits when other nuclides are present in the sample in much greater concentrations. Under these circumstance 3, it will be more appropriate to calculate the concentrations of such radio-nuclides using measured ratios with those radionuclides which are routinely i(entified and =easured.
(3)
The detectability li=its for activity analysis are based on the technical feasibility and en the potential significance in the
' environ =ent of the quantities released.
For sc=e nuclides, lower detection ILnits may be readily achievable and when nuclides are =easured below the stated 1Laits, they should also be reported.
(4)
The power level and cleanup or purification flow rate at the sa=ple cine shall also be reported.
(5)
The Miscellaneous Water Evaporator is a batch 1: quid process involving change of phase frem liquid to superheated steam, with least,1200 fold volunetric expansion.
The required detection at levels are =cre conservative than batch gas release criteria.
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l Amendment Ho. 36.
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