ML17215A782
| ML17215A782 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/01/1985 |
| From: | Thompson H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17215A783 | List: |
| References | |
| NUDOCS 8503190400 | |
| Download: ML17215A782 (5) | |
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UNITED STATES
'UCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 FLORIDA POWER
& LIGHT COMPANY ORLANDO UTILITIES COMMISSION OF THE CITY OF ORLANDO, FLORIDA AND FLOR IDA MUNICIPAL POWER AGENCY DOCKET NO. 50-389 ST.
LUCIE PLANT UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 9 License No. NPF-16 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Florida Power
& Light Company, et al., (the licensee) dated November 21, 1984 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 the provisions of the Commission; C.
-There is reasonabl by this amendment and safety of the conducted in compl operate in conformity with the application, the Act, and the rules and regulations of e assurance (i) that the activities authorized can be conducted without endangering the health public, and (ii) that such activities will be iance 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; 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 satisfied.
8503l90400 85030l PDR
,ADOCK 65000389 P
2.
Accordingly, Facility Operating License No.
NPF-16 is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and by amending paragraphs 2.C. 1 and P.C.2 to read as follows:
1.
Maximum Power level Florida Power and Light Company is authorized to operate the facility at reactor core power levels not in excess of 2700 megawatts thermal (100K power).
2.
Technical S ecifications The Technical Specifications contained in Appendices A
and 8, as revised through Amendment No.
9
, 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 GULATOR COMMISSION H ah Divi
/
>87 L. Thompson, Jr.
ion of Lice sin ector
Attachment:
Chanoes to the Technical Specifications Date of Issuance:
March I, 1985
DEFINITIONS PRESSURE BOUNDARY T
C LITY OPERATING LICENSE NO.
NPF-16 DOCKET NO. 50-389 1
E EKA~
leakage) through a non-isolable fault in a Reactor Coolant System component k@Yach"8% "@1116M'irYf~bW14e Appendix "A" Technical Specifications he n losed aae.
The revised page is identified by amendment line indicating the area of change.
The orresoondina overleaf mage is also provided to maintain document Qlep~g/UCKSS CONTROL PROGRAM shall contain the provisions, based on full sca'le testing, to assure that dewatering of spent bead resins results in a waste foray~~ the properties that meet the Iqgyyjrements of 10 CFR Part 61 (as implement~~0 CFR Part 20) and of the low~eve radioactive waste disposal site at thy gime of =disposal.
1-5 PURGE " PURGING 1.24 PURGE or PURGING is the controlled process of discharging air or'gas from a confinement to maintain temperature,
- pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 27OO MWt.
I REACTOR TRIP SYSTEM
RESPONSE
TIME 1.26 The REACTOR TRIP SYSTEM
RESPONSE
TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until electrical power is interrupted to the CEA drive mechanism.
REPORTABLE OCCURRENCE 1.27 A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specifications
- 6. 9. l. 8 and 6. 9. l. 9.
SHIELD BUILDING INTEGRITY 1.28 SHIELD BUILDING INTEGRITY shall exist when:
a.
b.
Each door is closed except when the access opening is being used for normal transit entry and exit; The shield building ventilation system is in compliance with Specification 3.6.6.1, and The sealing mechanism associated with each penetration (e.g.,
ST.
LUCIE - UNIT 2 1-5 Amendment No.
9
DEFINITIONS PRESSURE BOUNDARY LEAKAGE 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube leakage) through a non"isolable fault in a Reactor Coolant System component body, pipe wall or vessel wall.
PROCESS CONTROL PROGRAM PCP 1.23 The PROCESS CONTROL PROGRAM shall contain the provisions, based on full scale testing, to assure that dewatering of spent bead resins results in a waste form with the properties that meet the requirements of 10 CFR Part 61 (as implemented by 10 CFR Part 20) and of the low.level radioactive waste disposal site at the time of disposal.
PURGE " PURGING 1.24 PURGE or PURGING is the controlled process of discharging air or'gas from a confinement to maintain temperature,
- pressure, humidity, concentration or other operating condition, in such a manner that replacement 'air or gas is required to purify the confinement.
RATED THERMAL POWER 1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2700 MWt.
REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor" until electrical power is interrupted to the CEA drive mechanism.
REPORTABLE OCCURRENCE 1.27 A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specifications
- 6. 9. l. 8 and
- 6. 9. 1. 9.
SHIELD BUILDING INTEGRITY 1.28 SHIELD BUILDING INTEGRITY shall exist when:
b.
C.
Each door is closed except when the access opening is being used for normal transit entry and exit; The shield building ventilation system is in compliance with Specification 3,6.6. 1, and The sealing mechanism associated with each penetration (e.g., welds, bellows or 0"rings) is OPERABLE.
ST.
LUCIE - UNIT 2 1-5 Amendment No.
9
DEFINITIONS SHUTDOWN MARGIN
(
1.29 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full-length control element assemblies (shutdown and regulating) are fully inserted except for the single assembly of highest reactivity worth which is assumed to be fully withdrawn.
SITE BOUNDARY 1.30 The SITE BOUNDARY shall be that line beyond which the land is neither
- owned, leased, nor otherwise controlled by the licensee.
SOURCE CHECK 1.31 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source..
STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:
b.
A test schedule for n systems, subsystems, trains or other designated components obtained by dividing the specified test interval into n equal subintervals, and The testing of one system, subsystem, train or other designated component at the beginning of each subinterval.
THERMAL POWER
,1.33 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
UNIDENTIFIED LEAKAGE 1.34 UNIDENTIFIED LEAKAGE shall be all leakage which is not IDENTIFIED LEAKAGE or CONTROLLED LEAKAGE.
UNRESTRICTED AREA 1.35 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
ST.
LUCIE - UNIT 2 1-6