ML17139B330
| ML17139B330 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/03/1983 |
| From: | PENNSYLVANIA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17139B328 | List: |
| References | |
| NUDOCS 8302090320 | |
| Download: ML17139B330 (6) | |
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. arne FUNCTIONAL UNIT l.
Intermediate Range Monitor, Neutron Flux-High
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2.
Average Power Range Monitor:
a.
Neutron Flux-Upscale, Setdown TRIP SETPOINT
< 120/125 divisions of full scale
< 15K of RATED THERMAL POWER TABLE 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS ALLOWABLE VALUES
< 122/125 divisions of full scale
< 20K of RATED THERMAL POWER b.
Flow Biased Simulated Thermal Power-Upscale 1)
Flow Biased 2)
High Flow Clamped c.
Neutron Flux-Upscale d.. Inoperative
.-3.
Reactor Vessel Steam Dome Pressure - High 4.
Reactor Vessel Water Level - Low, Level 3
O. 58 W+5V%
t?l?t???t, ttt a maximum of
< 113.5X of RATED THERMAL POWER
< 118'f RATED THERMAL POWER
< 1037 psig
> 13.0 inches above Tnstr ument zero*
5.s8 W+(2.%
a maximum of
< 115.5X of RATED THERMAL POWER
< 120X of RATED THERMAL POWER P
MA
< 1057 psig
> 11.5 inches above ~
Tnstrument zero.
7.
8.
9.
-10.
12.
Drywell Pressure
- High Scram Discharge Volume Water Level - High Turbine Stop Valve - Closure Turbine Control Valve Fast Closure, Trip Oil Pressure Low Reactor Mode Switch Shutdown Positiotr I
Manual Scram See Bases Figure 3/4 3-1.
6 5.
Main Steam Line Isolation Valve - Closure 6.
Main Steam Line Radiation - High
< 10X closed
< 3.0 x full power background
< 1 72 psig
< 88 gallons
< 5.5X closed
> 500 psig NA NA
< illclosed
< 3.6 x full Sackground
< 1.88 psig
< 88 gallons
< 7X closed
> 460 psig NA NA 0
power 0
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0'OWER DISTRIBUTION LIMITS 3/4.2. 2 APRM SETPOINTS
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LIMITING CONDITION FOR OPERATION
~2%3 3.2.2 The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip setpoint (SRB) shall be established according to the following relationships:
Tri Set oint Allowable Value S <
6 ~~ (aesW~Sg/)W S <
SRB
< ~6'if h%T (0.58W+Q7)~
S where:
S and S
B are in percent of RATED THERMAL POWER, M = too/recirculation flow as a percentage of the ioop recirculation flow which produces a rated core flow of 100 million lbs/hr, T = Lowest value of the ratio of FRACTION OF RATED THERMAL POWER divided by the MAXIMUM FRACTION OF LIMITING POWER DENSITY.
T is always less than or equal to 1.0.
i'o.58'wes27.)T'&E ERT.'PT APPLICABILITY:
OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or
~q R
TEO THEREAT PO EE.
ACTION:
SURVEILLANCE RE UIREMENTS With the APRM flow biased simulated thermal power-upscale scram trip setpoint and/or the flow biased neutron flux-upscale control rod block trip setpoint less conservative than the value shown in the Allowable Value column for S or S B, as above determined, initiate corrective action within 15 minutes and adjust 3 and/or S
to be consistent with the Trip Setpoint value" within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce. THERMAL PIER to less than 25K 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 />.
4.2.2 The FRTP and the MFLPD shall be determined, the value of T calculated, and the most recent actual APRM flow biased simulated thermal power-upscale scram and flow biased neutron flux-upscale control rod block trip setpoints verified to be within the above limits or adjusted, as required:
e a.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s,
~cs b.
Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15K of RATED THERMAL POWER, and c.
Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with MFLPD greater than or equal to FRTP.
With MFLPD greater than the FRTP during power ascension up to 90K of RATED THERMAL POWER, rather than adjusting the APRM setpoints, the APRM gain may be adjusted such that APRM readings are greater than or equal to 100X times
- MFLPD, provided that the adjusted APRM reading does not exceed lOOX of RATED THERMAL POWER, the req'uired gain adjustment increment does not exceed 10K of RATED THERMAL POWER, and a notice of the adjustment is posted on the reactor control panel.
SUSQUEHANNA - UNIT 1 3/4 2-5
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TABLE 3.3.6-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS e
s TRIP. FUNCTION 1.
'ROD BLOCK MONITOR TRIP SETPOINT ALLOWABLE VALUE a.
Upscal e b.
Inoperative c.
Downscale
< 0.66 W + 40X
< 0.66 W+ 43X NA NA
> 5/125 divisions of full scale
> 3/125 of divisions full scale 2.
3.
APRM a.
Flow Biased Neutron Flux - Upscale b.
Inoperative c.
Downscale d.
Neutron Flux - Upscale Startup SOURCE RANGE MONITORS o.5& w + jo7."
NA
> 5X of RATED THERMAL POWER
< 12X of RATED THERMAL POWER
- o. 58 W + 5>7.
NA
> 3X of RATED THERMAL POWER
< 14X of RATED THERMAL POWER as b.
C.
d.
Detector not full in Upscale Inoperative Downscale NA
< 2x 10 cps NA
~
) 3 cp s*'A NA
< 4 x 10 cps NA
> 2 cps*"
4.,INTERMEDIATE RANGE MONITORS a.
.Detector not full in b.
Upscale c.
Inoperative d.
Downscale 5.
SCRAM DISCHARGE VOLUME NA NA
< 108/125 divisions of full scale
< 1-10/125.divisions of full scale HA NA
> 5/125 divisions of full scale
> 3/125 divisions of full scale 6.
a.
Water Level - High
< 44 gallons
< 44 gallons REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.
Upscal e
< 108/125 divisions of full scale 111/125 divisions of full scale b.
Inoperative NA NA c.
Comparator
< 10X flow deviation 11X flow deviation The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow
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The trip setting of this function must be m
., oined in accordance with Specification 3.2.2.
initial loading and startup the count rate ma,
".-.: > 0. 5 cps.
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