ML20205J861
| ML20205J861 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/06/1986 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205J864 | List: |
| References | |
| NUDOCS 8602260595 | |
| Download: ML20205J861 (6) | |
Text
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a as2eq'o UNITED STATES 8
~g NUCLEAR REGULATORY COMMISSION o
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WASHWGTON, D. C. 20665
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY PHILADELPHIA ELEGIRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANIIC CITY ELELIMIC COMPANY DOCKET NO. 50-272 SALEM NUCLEAR GENERATING STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 71 License No. DPR-70 1.
The Nuclear-Regulatory Comission (the Comission) has found that:
r A.
The application for amendment by Public Service Electric and Gas Company, Fhiladelphia Electric Company, Delmarva Power and Light Company and Atlar. tic City Electric Company (the licensees) dated August 6,1985, complies with the star.dards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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.
Tnere is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health' T
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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 common defense and security or to the health and safety of the public; i
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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-70 is hereby amended to read as follows:
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. i (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 71, 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
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.i St ven A. V rg D rector W PW Project Directorate #3 Di sion of.PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: February 6,1986 4
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ATTACHMENT TO LICENSE AMENDMENT NO.71 FACILITY OPERATING LICENSE NO. DPR-70 DOCKET NO. 50-272 Revise Appendix A as follows:
Remove Pages Insert Pages 1-5 1-5 2-5 2-5 3/4 2-14 3/4 2-14 r
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g DEFINITIONS PHYSICS TESTS PHYSICS TESTS shall be those tests perforned to seisure tsa fundamental 1.20 nuclear characteristics of the reactor core and related instrumentation and 1) described in Chapter 14 of the Updated FSAR, 2) authorized under the provisions
.l of IT,FR50.59, or 3) otherwise by the Commission.
PRESSURE B0UNDARY LEAKAGE 1.21 PRESSURE SOUNDARY LEAKAGE shall be leakage (except steam generator tube 1eakage) through a non-isolable fault in a Reactor Coolant System cogonent l
body, pipe wall or vessel wall.
PROCE35 CONTROL PROGRAM (PCP) 1.22 The PROCESS CONTROL PROGRAM shall be that program which contains the current fornula<, samling, analyses, test, and determinations to be sede to ensure that the processing and packaging of solid radioactive wastes, based on demonstrated processing of actual or sinulated wet solid wastes, will be accoglished in such a way as to assure cog 11ance with 10 CFR Part 20,10 CFR Part 71 and Federal and State regulations and other requirements ipverning the-disposal of the radioactive waste.
l PURGE - PURGING 1.23 PURGE or PURGING shall be the controlled process 6f discharging air or gas from a confinerent to maintain tegerature, pressure, humidity, concentration, or other operating condition, in such a manner that replacenant air or gas is required to pu.-ify the confinenent.
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@ADRANT POWER TILT RATIO 1.24 @ADRAMT POWER TILT RATIO shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore de, ector t
calibrated outputs, or the ratio of the maxinum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for coguting the average.
RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3411MWt.
SALEM - UNIT 1 1-5 Amendment No. 71
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4 TABLE 3.2-1
.g DN8 PARAMETERS 9
e LIMITS Eq 4 Loops In 3 Loops in PARAMETER Operation Operation-l Reactor Coolant System T,,9
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< 572*F Pressurizer Pressure 1 2220 psla*
1 2220 psia
- 2 Reactor realant System 1 349.200 gpm 1 78.100 gpm s
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- Limit not applicable during either a. THERMAL POKR ramp incease in excess of 55 RATED THERMAL POWER per minute or a THERMAL POWER step increase in excess of 10% RATED THERMAL POWER.
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