ML18094A381

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Proposed Tech Specs Pages 3/4 2-14,3/4 2-9 & 3/4 2-17
ML18094A381
Person / Time
Site: Salem  PSEG icon.png
Issue date: 04/19/1989
From:
Public Service Enterprise Group
To:
Shared Package
ML18094A374 List:
References
NUDOCS 8905020486
Download: ML18094A381 (3)


Text

PARAMETER Reactor Coolant System T avg Pressurizer Pressure Reactor Coolant System TABLE 3.2-1

~

DNB PARAMETERS 4 Loops In Operation

~ 582°F

~ 2220 psia*

LIMITS

~ 357,200 gpm/I 3 Loops In Operation

~ 572°F

~ 2220 psia*

~ 284,500 gpm/I

  • Limit not applicable during either THERMAL POWER ramp increase in excess of 5% RATED THERMAL POWER per minute or a THERMAL POWER step increase in excess of 10% RATED THERMAL POWER.

/IIncludes a 2.2% flow measurement uncertainty plus a 0.1% measurement uncertainty due to feedwater venturi fouling.

SALEM - UNIT 1 3/4 2-14 Amendment No. '

POWER DISTRIBUTT.

LIMITS 3/4.2.3 NUCLEAR ENTHALPY HOT CHANNEL FACTOR F~H LIMITING CONDITION FOR OPERATION 3.2.3 N

F6H shall be limited by the following relationship:

N F6H ~ 1.55 [1.0 + 0.3 (1.0-P)]

where:

p THERMAL POWER RATED THERMAL POWER APPLICABILITY:

MODE 1 ACTION:

N With F6H exceeding its limit:

a.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and reduce the Power Range Neutron Flux-High Trip Setpoints to ~

55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b.

Demonstrate thru in-core mapping that F~H is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding the limit or reduce THERMAL POWER to less than 5%

of RATED THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and

c.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER above the reduced limit required by &* or b.

above; subsequent POWER OPERATION may proceed provided that F6H is demonstrated through in-core mapping to be within its limit aE a nominal 50% of RATED THERMAL POWER prior to exceeding this THERMAL POWER, at a nominal 75% of RATED THERMAL POWER prior to exceeding this THERMAL POWER and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after attaining 95% or greater RATED THERMAL POWER.

SALEM - UNIT 2 3/4 2-9 Amendment No.

.j.

f]

PARAMETER Reactor Coolant System T avg Pressurizer Pressure Reactor Coolant System TABLE 3.2-1 DNB PARAMETERS LIMITS 4 Loops in Operation

~ 582°F

~ 2220 psia*

> 357200 gpm/f

  • Limit not applicable during either a THERMAL POWER ramp in excess of 5% RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% RATED THERMAL POWER.

/fincludes a 2.2% flow uncertainty plus a 0.1% measurement uncertainty due to feedwater venturi fouling.

SALEM - UNIT 2 3/4 2-17