ML17215A661
| ML17215A661 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/21/1984 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17215A660 | List: |
| References | |
| NUDOCS 8412010121 | |
| Download: ML17215A661 (7) | |
Text
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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 Sys em component body, pipe wall or vessel wa11.
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 aeet the requirements of 10 CFR Part 61 (as implemented by 10 CFR Part 2D) 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 Iaintair temperature,
- pressure, humidity, concentration or other opera.ing condition, in such a aanner that replacement air or gas is required to purify the confinement.
RATED THERMAL NEER 1.25 RATED THERMAL KWER shall be a total reactor core heat transfer rate to the reactor coolant ofASRt HWt.
it7ob REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the tioe interval from when the aonitored paraaeter exceeds its trip setpoint at the channel sensor crntil electrical power
$ s interrupted to the CEA drive acchanisl.
REPORTABLE OCCURRENCE 1.27 A REPORTABLE OCCURRENCE shall be any of those conditions specified in Specifications 6.9. 1.8 and 6.9.1.9.
SHIELD BUILDING INTEGRITY 1.28 SHIELD BUILDING INTEGRITY shall exist when:
a.
Each door is closed except when the access opening is being used for noraal transit entry and exit;
. b.
The shield building ventilation system is in compliance with Specification 3.6.6.1, and c.
The sealing aechanism associated with each penetration (e.g,, welds, bellows or O-rings) is OPERABLE.
84i20iOi2i 84ii2i PDR ADOCK 05000389 P
PDR 1
r'II 1
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ENCLOSURE 2
NO SIGNIFICANT HAZARDS CONSIDERATION ST.
LUCIE UNIT' OPERATION AT 2700 Mdth Docket:
50-389 License:.
NPF-16 November 1984
The requested amendment to the St. Lucie Unit 2 operating license increases the presently licensed rated core power level of 2560 MWth to 2700 MWth.
,An evaluation of this request for amendment has been performed to demonstrate that no significant hazards consideration exists, based on a
comparison with the criteria of 10CFR50.92(c).
The acceptability of increasing the licensed rated core power to 2700 MWth, measured against. the significant hazards considerations of 10CFR50.92(c) is discussed below:
The requested change does not increase the probablility or consequences of accidents previously analyzed.
As the plant, configuration and mode of operation remains unchanged, the probability of accidents previously analyzed remains unchanged.
The consequences do not increase as demonstrated in the Reload Safety Report where the entire spectrum of anticipated operational occurrences and postulated accidents were analyzed for a rated core power level of 2700 MWth and were found to have acceptable consequences.
The extent of these analyses can be characterized within the following six categories:..
- l. Increase in heat removal by the secondary system.
(section 3.2.1)
- 2. Decrease in heat removal. by the secondary system.
(Section 3.2.2)
- 3. Decrease in reactor coolant flow rate.
(Section 3.2.3)
- 4. Reactivity and power distribution anomalies.
(Section 3.2.4)
- 5. Decrease in reactor coolant system inventory.
(Section 3.2.6)
- 6. Loss of Coolant events.
(Section 3.3)
Note:. Section numbers refer to the sections in the Reload Safety Report.
I The requested change does not increase the potential for accidents different from any accident previously considered because the plant configuration and the manner in which it is operated remain the same.
iii. The requested change does not reduce the safety margin because it has been shown in the Reload Safety Report that operation at the 2700 MWth rated core thermal power level can be accomplished within acceptable safety limits and design criteria.
These limits include:
Specified Acceptable Fuel Design
Limits(SAFDL), LOCA criteria specified in 10CFR50.46, offsite dose limits, reactor coolant pressure
- limits, and containment design criteria.
Since the acceptability of,the. proposed change has been demonstrated in the previously approved reload safety evaluation for cycle 2 '
the change is similar to the following examples presented in the staff guidance on determination of no significant hazards amendments that are considered not likely to involve significant hazards considerations:
"(iii).... This assumes that no significant changes are made to the acceptance criteria for the technical specifications, that the analytical methods used to demonstrate
'conformance with the technical specifications and regulations are not significantly
- changed, and that NRC has previously found such methods acceptable.
(iv)... This assumes that the operating restriction and the criteria to be applied to a request for relief have been established in a prior review and that it is justified in a satisfactory way that the criteria have been met.
The potential environmental impact of operating at a rated core power level of 2700 MWth was considered in the St.
Lucie Unit 2 Final Environmental Statement and found acceptable.
Therefore, the requested amendment will not result in any environmental impacts other than those previously evaluated.
From the considerations detailed above it is concluded that the proposed amendment to the St. Lucie Unit 2 operating license of increasing the rated core thermal power to 2700 MWth does not represent a significant hazard as discussed in 10CFR50.92.
Furthermore, in accordance with the provisions of 10CFR50.59 the requested amendment does not constitute an unreviewed safety question.
J.W. Williams, Jr. letter to D.
G. Eisenhut, Docket No. 50-389, St. Lucie Unit 2 Proposed License Amendment Cycle 2 Reload, L-84-148, June 4,
1984.
St. Lucie Plant Unit 2 Amendment to Facility Operating License; Amendment No. 8; License No. NPF-16; November 9,
1984
'inal Environmental Statement Related to the Operation of St. Lucie Plant Unit No.2, NUREG-0842, April 1982
STATE OF FLORIDA
)
)
ss.
COUNTY OF DADE
)
J.
M. Milliams, Jr.,
being first duly sworn, deposes and says:
That he is Group Vice President of Florida Power 5 Light Company, the licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and
- belief, and that he is authorized to execute the document on behalf of said Licensee.
J.
W. Williams, Jr.
Subscribed and sworn to before me this day of
, 1984.
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I.';NOIAI~Y PUBl.IC, in and or the County of Wade~ St'aCe'of Florida.
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