ML20005A175
| ML20005A175 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/23/1981 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005A174 | List: |
| References | |
| NUDOCS 8106290486 | |
| Download: ML20005A175 (4) | |
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NUCLEArt RcGULATORY COM'.'!c3 TON
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.j WASHING TON, 0. C. 20555 SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312
'RAftCHO SEC0 NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 34 License No. OPR-54 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by sacranento flunicipal Utility District (the licensee) dated June 5,1981, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be cor. ducted 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.
ATTACHMENT TO LICENSE AMENDMENT NO. 34
-FACILIT_Y OPERATING LICENSE NO. DPR 54 DOCKET NO. 50-312 Replace the following pages of the Appendix "B" Technical Specifications. -
with the enclosed pages. The revised pages are identified by Amendment number and contain vertical-lines indicating the areti of change.
t Pages 11 lla (new) t l'
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n 1
I C.
Sampling and analysis of liquid radioactive waste shall be per-formed in accordance with Table 2.6-1.
Prior to taking sa=ples from a monitoring tank, at lasst two tank volumes shall be recirculated or the agitator shall be operated sufficiently to achieve co=plete mixing.
The liquid radioactive vastes shall be continuously monitored and D.
recorded during release. Whenever these monitors are inoperable for a period not to exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, two independent sa=ples of each tank to be discharged shall be analyzed and two plant personnel shall independently check valving prior to the discharge.
If these monitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no liquid waste shall be released and any release in progress shall be terminated.
E.
The flow rate of liquid radioactive waste after dilution shall be measured and recorded during release. The flow of undiluted liquid radioactive vaste shall be established using installed instrumentation. That flow rate shall be entered in the plant records for the liquid waste release.
F.
All liquid radiation monitors shall be calibrated at least quarterly by means of a radioactive source which has been calibrated to a National Bureau of Standards source.
Each monitor shall also have a functional test monthly and an instrument check prior to making a release.
Bases The release of radioactive materials in liquid waste to unrestricted areas shall not exceed the concentration Itnits specified in 10 CFR Part 20 and should be as low as practicable in accordance with the requirements of 10 CFR Part 50.36a. These specifications provide reasonable assurance that the resulting annual exposure to the total body or any organ of an individual in an unrestricted area vill not exceed 5 arem. At the same time, these specifications permit the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power under unusual operating conditions which may temporarily result in releases higher than the design objective levels but still within the concentration limits specified in 10 CFR Part 20.
It is expected that by using this operational flexibility under unusual operation conditions, and exerting every effort to keep levels of radioactive material in liquid wastes as low as practicable, the ann'ual releases will not exceed a small fraction of the concentration j
limits specified in 10 CFR Part 20.
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The design objectives have been developed based on operating experience taking into account a combinttion of variables including def ective fuel, primary system leakage, primary to secondary system leakage and the performance of the various waste treatment systems, and are consistent with Appendix I to 10 CFR Part 50.
- The last sentence in Specification 2.6.2.D is replaced by the following paragraph dur'ing the period June 6, 1981 through June 30, 1981 (cont. pg. lla).
Amendment Mo. El, 34 - _.
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(footnote cont. from pg.11)
If these monitors are inoperable for a period exceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, tank dis-charges may be continued up to 14 days provided that discharges are collected in a retention basin. The mixed retention basin will be sampled and analyzed.
Retention basin valving will be verified to prevent further additions to the basin and diluted discharges from the retention basin will be sampled and analyzed every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> during release.
-- Amendment No. 34
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