ML17228B504
| ML17228B504 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/01/1996 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17228B503 | List: |
| References | |
| NUDOCS 9606030192 | |
| Download: ML17228B504 (13) | |
Text
St. Lucie Unit 1 Docket No. 50-335 Proposed Exigent License Amendment Thermal Mar in and RCS Flow Limits ATTACHMENT 4 ST ~ LUCIE UNIT 1 MARKED-UP TECHNICAL SPECIFICATION PAGES Page 2-1 Page 2-2 Revised Figure 2.1-1 Page 2-4 Page 3/4 2-14 Page 5-5
'606030192 960601 I
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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS REACTOR CORE l])g,pre 0 5+ZYl<~
2.1.1 The combination of THERMAL POWE, pressurizer
- pressure, and maxi-mum cold leg coolant temperature shall not exceed the limits shown on Figure 2.1-1.
APPLICABILITY:
MODES 1
and 2.
ACTION:
Whenever the point defined by the combination of maximum cold leg temper-ature and THERMAL POWER has exceeded the appropriate pressurizer pressure line, be in HOT STANDBY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
I 1
REACTOR COOLANT SYSTEM PRESSURE 2.1.2 The Reactor Coolant System pressure shall not exceed 2750 psia.
APPLICABILITY:
MODES 1, 2, 3, 4 and 5.
ACTION:
MODES 1
and 2
Whenever the Reactor Coolant System pressure'has exceeded 2750 psia, be in HOT STANDBY with the Reactor Coolant System pressure within its limit within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
MODES 3, 4 and 5
Whenever the Reactor Coolant System pressure has exceeded 2750 psia; reduce the Reactor Coolant System pressure to'ithin its limit within 5 minutes.
" For Cycle 14 operation beyond 7000 EFPH, THERMAL POWER shall not exceed 90% of,
~ 2700 Megawatts (thermal).
ST.
LUCIE - UNIT 1
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.K 4J 580 560 510 520 500 UNACCEPTABLE OPERATION REACTOR OPERATION LIMIT TO LESS THAN 580 'F BY ACTUATION0 HE MAINSTEAM LINE SAFETY VALVE VESSEL FLOW LESS MEASUREMENT UNCERTAINTIES 355.000 GPLl LIMITS CONTAIN NO ALLOWANCEFOR I NSTRUMENT ERROR OR FLUCTUATIO BASED ON THE AXIALSHAPE FIGURE B 2.1-1 UNACCEPTAB OPERATION I
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I 480 460 PRESSURE I
IA 1750 2000 2225 2400 ACCEPTABLE OPERATION I
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0.2 0.4 0.6 0.8
$.2 FRACTION OF RATED THERMAL POWER L6 FIGURE 2.1-1 REACTOR CORE THERMAL MARGIN SAFETY LIMIT
, FOUR REACTOR COOLING PUMPS OPERATING
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600 575 550 525 UNACCEPTABLE OPERATION REACTOR OPERATION LIMITED TO LESS THAN 580 Deg F BY ACI'UATION OF THE MAIN SMAll LINE SAFETY VALVES VESSEL FLOW LESS ifEASUREIKNT UNCERTAINTIES 046,000 GPM I
LIMITS CONTAIN NO ALLOWANCE FOR INSTRUMENT ERROR OR FLUCTUATIONS qr Q UNACCEPFABLE OPERATIO
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0O 500 BASED ON THE AXIAL SHAPE ON FIGURE B 2.1-1 PRESSURE IN PSIA g g
~pf 475 450 1750 2000 2225 2400 ACCEPTABLE OPERATION 0.4 0.6 O.S i.
1.2 Fraction of Rated Thermal Pox'er 1.6
TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS In m
FUNCTIONAL UNIT 1.
Power Level - High (1)
Four Reactor Coolant Pumps Operating TRIP SETPOINT Not Applicable
< 9.61K, above THERMAL POWER, with a minimum setpoint of 155 of RATED THERMAL POWER, and a
maximum of < 107.05 of RATED THERMAL POWER.
ALLOWABLE VALUES Not Applicable
< 9.61K above THERMAL POWER,~d a minimum setpoint of 15K ofMiTED THERMAL POWER and a maximum of
< 107.0X of RATED THERMAL POWER.
3.
Reactor Coolant Flow - Low (1)
Four Reactor Coolant Pumps of design reactor coolant Operating flow with 4 pumps operating*
of design reactor coolant flow with 4 pumps operating*
4.
Pressurizer Pressure
- High 5.
Containment Pressure High
< 2400 psia 3.3 psig
< 2400 psia
< 3 3 psig 6.
Steam Generator Pressure
- Low (2}
> 600 psia 7.
Steam Generator Water Level -Low
> 20.5X Hater Level - each steam generator
> 600 psia
> 19.4 Mater Level - each ~
v ~
8.
Local Power Density - High (3)
Trip setpoint adjusted to not exceed the limit lines of Figures 2.2-1 and 2.2-2 Trip set point adjusted to not exceed the limit lines of Figures 2.2-1 and 2.2-2.
- Design reactor coolant flow with 4 pumps operating is,
& gpm.
0 I ~
+0 Q1
<o
.'led Qh
~ y Cf TABLE 3.2-1 DNB MARGIN LIMITS Parameter Cold Leg Temperature Pressurizer Pressure Reactor Coolant Flow Rate AXIAL SHAPE INDEX Four Reactor Coolant Pumps
~0eratin
( 549'F
> 2225 psia*
> 955-,888 gpm Figure 3.2-4 Limit not applicable during either a
THERMAL POWER ramp incr ease in excess of 5X of RATED THERMAL POWER or a THERMAL POWER step increase of greater than lOX of RATED THERMAL POWER.
ST.
LUCIE - UNIT 1
3/4 2-14 Amendment No.~@7,
~ Qt JQ.)
F1~
a OESIGN FEATURES CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 73 full length and no part length control element assemblies.
The control element assemblies shall be designed and maintained in accordance wi th the original design provisions contained in Section 4.2.3.2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
5.4 REACTOR COOLANT SYSTEM OESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
a.
b.
C.
In accordance with the code requirements specified in Section
- 5. 2 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements, For a pressure of 2485 psig, and For a temperature of 650'F, except for the pressurizer which is 700'F.
VOLUME 5.4.2 The total water and steam volume of the react r c lant s st
'11,100
+ 100 cubic feet at a nominal T of 067' m
en flo arcoun joiy Ai'@am
~werw6r Aakplvyyl<g.
5.5 EMERGENCY CORE COOLING SYSTEMS 0
5.5.1 The emergency core cooling systems are designed and shall be main-tained in accordance with the original design provisions contained in Section 6.3 of the FSAR with allowance for normal degradation pursuant to the applicable Surveillance Requirements.
- 5. 6 FUEL STORAGE CRITICALITY 5.6.l.a The spent fuel storage racks are designed and shall be maintained with:
l.
A k ff equivalent to less than or equal to 0.95 when flooded witII unborated water, which includes a conservative allowance of 0.0065 ak for uncertainties.
ST.
LUCIE - UNIT 1
5-5 Amendment No. gg,27, 7$,
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St. Lucie Unit 1 Docket No. 50-335 Proposed Exigent License Amendment Thermal Mar in and RCS Flow Limits ENCLOSURE Siemens Power Corporation-Nuclear Division, St. Lucie Unit 1 Chapter 15 Event Review and Analysis for 30% Steam Generator Tube
- Plugging, EMF-96-135;
- May, 1996