ML19317G826
| ML19317G826 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 10/22/1975 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19317G822 | List: |
| References | |
| NUDOCS 8004010654 | |
| Download: ML19317G826 (5) | |
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UNITED STATES fJUCLEAR REGULATORY COMMISSION WASHINGTON, o. C. 205S5 O
SACRAMENTO MUNICIPAL UTILITY DISTRICT DOCKET NO. 50-312 RANC110 SECO NUCLEAR GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1 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 October 2,1975, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulctions set forth in 10,CFR Chapter I; B.
The facil-ity will operate in conformity 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 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; and D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of t,he public.
2.
Accordingly, the license is amended by a change to the Tec'hnical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility License No. DPR-54 is hereby amended to read as fol'Iows:
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. "(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, as revised by isst.ad changes t;.ereto through Change No.1."
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This license amend ~cnt is effective as of the date of its issuance.
FOR Tile NUCLEAR REGULATORY CO>NISSION J' -
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.c Robert W. Reid, Chief Operating Reactors Branch #4 Division of Reactor Licensing
Attachment:
Change No. I to the Technical Specifications Date of Issuance October 22, 1975 e
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3 ATTACl! MENT TO LICENSE AMENDMENT NO.1 CIIANGE NO.1 TO THE TECIINICAL SPECIFICATIONS FACILITY OPERATING LICENSE NO. DPR-54 DOCKET NO. 50-312 Remove pages 4-39,and 4-40 from the Appendix A Technical Specifications and insert the attached pages bearing the same nwnbors. The changed on the revised page is shown by a marginal line.
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4 RANCHO SECO UNIT 1 TECICiICAL SPECIFICATIONS Surveillance Standards 4.8 AUXILIARY FEEDh'ATER PUMP FERIODIC TESTING '
, Applicability Applies to the periodic testing of the torbine and motor driven auxiliary feedwater pumps.
Objective To verify that the auxiliary feedwater pump and associated valves are operabic.
Specification 4.8.1 At 1 cast every 92 days at a time when the average reactor coolant system temperature is >3050F, the turbine / motor driven and metor driven. auxiliary feedwater pumps shall be operated on recirculation to the condenser to verify proper operation.
The 92 day test frequency requirement shall be brought current within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the average reactor coolant system temperature is
>3050,F Acceptable performance will be indicated if the pump starts and operates for fifteen minutes at the design flow of 780 gpm.
This flow will be verified using tank IcVel decrease and pump differentici pressure.
Bases The quarterly test frequency will be sufficient to verify that the turbine /
motor driven and motor driven auxiliary feedwater pumps are opernh'a. Veri-fication of correct operation will be r.ade both. from the control room instru-mentation and direct visual observation of the pumps.
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4-39 CCT 2 2 *a75 y
RANCHO SECO UNIT 1 i dCHNICAL SPECIFICATIONS Surveillance Standards 4.9 REACTIVITY ASOMALIES Applicability Applies to potential reactivity anomalics.
Obj ective To require the evaluation of reactivity anomalics of a specified magnitude occurring during the operation of the unit.
Specification Following a normalization of the computed boron concentration as a function of' burnup, the actual boron concentration of the coolant shall be monthly compared with the predicted value.
If the difference between the observe'd and predicted steady-state concentrations reaches the equivalcat of one per-cent in reactivity, an evaluation will*be made to determine the cause of the disctcpancy and reported to the Atomic Energy Commission.
Bases To climinate possibic errors in the calculations of the initial reactivity of the core and the reactivity depiction ra'ec, the predicted relation between fuel burnup and the boron concentration, necessary to maintain adequate con-trol characteristics, must be adjusted (norcalized) to accurately refJ ect actual core conditions. When full power is reached initially, and with the contro) rod groups in the desired positions, the boron concentration is measured and the predicted curve is adjusted to this point. As power opera-tion proceeds, the ceasured boron concentration is compared with the predicted concentration and the slope of the curve reJating burnup and reactivity is compared with that predicted. This process of normalization should be com-plcted after about 10 percent of the total core burnup. Thereafter, actual boron concentration can be compared with prediction, and the reactivity status of the core,can be continuously evaluated. Any reactivity anomaly greater than 1 percent would be unexpected, and its occurrence would be thoroughly investigated and evaluated.
The'value.of 1 percent is considered a safe limit since a shutdown margin of at least 1 percent with the most reactive rod in the fully withdrawn position is always maintained.
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