ML17228B504

Proposed Tech Specs Re Thermal Margin & RCS Flow Limits

ML17228B504
Person / Time
Site:	Saint Lucie
Issue date:	06/01/1996
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17228B503	List: ML17228B502 ML17228B504 ML17228B505
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

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2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 SAFETY LIMITS '

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REACTOR CORE 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 hour.

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,

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2700 Megawatts (thermal).

ST. LUCIE - UNIT 1 2-1

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UNACCEPTABLE OPERATION 580 UNACCEPTAB OPERATION I

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I REACTOR OPERATION LIMIT TO LESS 510 THAN 580 'F BY ACTUATION 0 HE 4J MAIN STEAM LINE SAFETY VALVE VESSEL FLOW LESS MEASUREMENT UNCERTAINTIES 355.000 GPLl 520 LIMITS CONTAIN NO ALLOWANCE FOR I NSTRUMENT ERROR OR FLUCTUATIO BASED ON THE AXIAL SHAPE FIGURE B 2.1-1 500 PRESSURE I IA I

480 ACCEPTABLE OPERATION d~

D~gag 1750 2000 s y g 2225 2400 460 0.2 0.4 0.6 0.8 $ .2 L6 FRACTION OF RATED THERMAL POWER FIGURE 2.1-1 REACTOR CORE THERMAL MARGIN SAFETY LIMIT

, FOUR REACTOR COOLING PUMPS OPERATING

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600 UNACCEPTABLE OPERATION 575 qr Q UNACCEPFABLE OPERATIO

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550 REACTOR OPERATION LIMITED TO LESS THAN 580 Deg F BY ACI'UATION OF THE I '.

MAIN SMAll LINE SAFETY VALVES VESSEL FLOW LESS ifEASUREIKNT 525 UNCERTAINTIES 046,000 GPM I 0 I

LIMITS CONTAIN NO ALLOWANCE FOR I INSTRUMENT ERROR OR FLUCTUATIONS a '

0 O 500 BASED ON THE AXIAL SHAPE ON FIGURE B 2.1-1 g g PRESSURE IN PSIA ACCEPTABLE OPERATION 1750

~ pf 475 2000 2225 2400 450 0.4 0.6 O.S i. 1.2 1.6 Fraction of Rated Thermal Pox'er

TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS I

n FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES m

1. Manual Reactor Trip Not Applicable Not Applicable

2. Power Level - High (1)

Four Reactor Coolant Pumps < 9.61K, above THERMAL POWER, < 9.61K above THERMAL POWER,~d Operating with a minimum setpoint of 155 a minimum setpoint of 15K ofMiTED of RATED THERMAL POWER, and a THERMAL POWER and a maximum of maximum of < 107.05 of RATED < 107.0X of RATED THERMAL POWER.

THERMAL POWER.

3. Reactor Coolant Flow - Low (1)

Four Reactor Coolant Pumps of design reactor coolant of design reactor coolant Operating flow with 4 pumps operating* flow with 4 pumps operating*

4. Pressurizer Pressure - High < 2400 psia < 2400 psia

5. Containment Pressure High 3.3 psig < 3 3 psig

6. Steam Generator Pressure - Low (2} > 600 psia > 600 psia

7. Steam Generator Water Level -Low > 20.5X Hater Level steam generator

- each > 19.4 Mater Level - each steam generator

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8. Local Power Density - High (3) Trip setpoint adjusted to not Trip set point adjusted to not O exceed the limit lines of exceed the limit lines of v~

Figures 2.2-1 and 2.2-2 Figures 2.2-1 and 2.2-2.

• Design reactor coolant flow with 4 pumps operating is, & gpm.

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~ y TABLE 3.2-1 DNB MARGIN LIMITS Four Reactor Coolant Pumps Parameter ~0eratin Cold Leg Temperature ( 549'F Pressurizer Pressure > 2225 psia*

Reactor Coolant Flow Rate > 955-,888 gpm AXIAL SHAPE INDEX 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,

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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. 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,

b. For a pressure of 2485 psig, and C. 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

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Ai'@am 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 wi th:

l. equivalent to less than or equal to 0.95 when flooded witIIff A k unborated water, which includes a conservative allowance of 0.0065 ak for uncertainties.

ST. LUC IE - 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