ML17301A038
| ML17301A038 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/22/1983 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17213B342 | List: |
| References | |
| NUDOCS 8305060303 | |
| Download: ML17301A038 (10) | |
Text
p7 FLORIDA POWER AND LIGHT COYiPAHY ORLANDO UTILITIES CONNISSION OF THE CITY OF ORLANDO, FLORIDA FLORIDA NUHICIPAL POWER AGENCY DOCKET tl0. 50-389 ST. LUCIE PLANT, UNIT 2
'ANEHDMEHT TO FACILITY OPERATItlG LICENSE Amendment Ho.
1 License No. NPF-16 1.
The tluclear Regulatory Commission (the Coaeission) has found that:
A.
The application for amendment filed by the Florida Power and Light
- Company, on behalf of. itself and Orlando Utilities Commission of the City of Orlando, Florida and Florida ttunicipal Power Agency (licensees) dated April 20, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, as
- amended, the provisions of the Act, and the regulations of the Commission; CD 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 Commission's regulations set forth in 10 CFR Chapter I; 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; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisified.
,8305060303 830422
'DR ADOCK 05000389
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NRC FORM 318 00.80) NRCM 0240 0 F FIClAL R ECOR D COPY USOPO: 1981~960 I
I J
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 Ho. HPF-16 is hereby amended to read as follows:
2.
Technical Specifications I
The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix 8, as revised through Amendment Ho. 1, are hereby incorporated in this license.
The licensees shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGUlATORY CONPISSIOH Date of Issuance:
APR p g '1983 isl George H. Y.nighton, Chief Licensing Branch Ho.
3 Division of Licensing OFFICE/
SURNAME/
DATE 5 NRG FORM 318 u0-80) NRCM 0240 DL:
JWilso D
OFFlCIAL RECORD COPY j
USOPO: 1981~960
0 P
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3 ATTACHMENT TO LICENSE AHENDtlEIIT NO.
1 FACILITY OPERATING LICENSE HO. NPF-16 DOCKET NO.60-389 Replace the following pages of the Appendix A Technical Specifications >>ith the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Also to be replaced is the following overleaf page to an amended page.
Amendment Pages 3/4 3-8 3/4 3-9 3/4 3-10 Over'leaf Pa e
3/4 3-7 OFFICE/
SURNAME/
DATE$
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NRC FORM 318 n0-80) NRCM 0240 OFFICIAL R ECOR D COPY USGPO: 1981~~990
TABLE 3.3-2 Continued)
REACTOR PROTECTIVE INSTRUHENTATION RESPONSE TIHES FUNCTIONAL UNIT
RESPONSE
TIHE 10.
Loss of Component Cooling Mater to Reactor Coolant Pumps Not Applicable ll.
Reactor Protection System Logic 12.
Reactor Trip Breakers 13.
Wide Range Logarithmic Neutron Flux Honitor 14.
Reactor Coolant Flow - Low 15.
Loss of Load (Turbine Hydraulic Fluid Pressure
- Low)
Not Applicable Not Applicable Not Applicable 0.65 second Not Applicable Neutron detectors are exempt from response time testing.
Response
time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.
Based on a resistance temperature detector (RTD) response time of less than or equal to 8.0 seconds where the RTD response time is equivalent io the time interval required for the RTD output to achieve 63.2X of its total change when subjected to a step change in RTD temperature.
TABLE 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS I
C Mfll FUNCTIONAL UNIT 1.
Manual Reactor Trip CHANNEL CHECK N.A.
CHANNEL CALIBRATION N.A.
CHANNEL FUNCTIONAL TEST S/U(1)
MODES FOR WHICH SURVEILLANCE IS RE UIRED 3*
4A 5*
Ca) 4l I
CO 2.
Variable Power Level - High a.
Nuclear Power b.
AT Power 3.
Pressurizer Pressure
- High 4.
Thermal Margin/Low Pressure 5.
Containment Pressure - High 6.
Steam Generator Pressure - Low 7.
Steam Generator Pressure Difference - High 8.
Steam Generator Level Low 9.
Local Power Density - High 10.
Loss of Component Cooling Water to Reactor Coolant Pumps N.A.
D(2),M(3),Q(4)
M D(5) Q(4)
M M
N.A.
1 2
1 1,
2 1
2 1
2 1
2 1
2 1
2 N.A.
11.
Reactor Protection System Logic N.A.
N.A.
M(7) 3*
4*
5*
h
TABLE 4. 3-1 (Continued)
'EACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE RE UIREMENTS InM Pal M
FUNCTIONAL UNIT CHANNEL CHECK CHANNEL CALIBRATION CHANNEL FUNCTIONAL TEST MODES FOR WHICH SURVEILLANCE IS RE UIRED 12.
Reactor Trip Breaker s 13.
Wide Range Logarithmic Neutron Flux Monitor 14.
Reactor Coolant Flow-Low 15.
Loss of Load (Turbine Hydraulic Fluid Pressure - Low)
N.A.
N.A.
N.A.
S/U(l),M,R(6) 1, 2, 3", 4", 5*
S/U(1),R 1, 2, 3, 4, 5
1 2
TABLE 4.3-1 Continued TABLE NOTATION Only if the reactor trip breakers are in the closed position and the CEA drive system is capable of CEA withdrawal.
(1)
Each startup or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, if not performed in the previous 7 days.
(2)
(3)
Heat balance only (CHANNEL. FUNCTIONAL TEST not included),
above 15K of RATED THERMAL POWER; adjust "Nuclear Power Calibrate" poten-tiometer to null "Nuclear Power - dT Power".
During PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and prior to proceeding to the next major test power plateau.
Above 15K of RATED THERMAL POWER, recalibrate the excore detectors which monitor the AXIAL SHAPE INDEX by using the incore detectors or restrict THERMAL POWER during subsequent operations to < 90K of the maximum allowed THERMAL POWER level with the existing reactor coolant pump combination.
(4)
Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5)
Adjust "hT Pwr Calibrate" potentiometers to make 4T power signals agree with calorimetric calculation.
At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include verification of the independent OPERABILITY of the undervoltage and shunt trips.
(7)
The fuse circuitry in the matrix fault protection circuitry shall be determined to be OPERABLE by testing with the installed test circuitry.
ST.
LUCIE - UNIT 2 3/4 3-10 AMENZMENT NOo 1 I