ML18094A381
| ML18094A381 | |
| Person / Time | |
|---|---|
| Site: | Salem |
| 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