ML17339B087: Difference between revisions

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{{#Wiki_filter:reactivity insertion upon ejection greater than 0.3/k/k at rated power.Inoperabl'e rod worth shall be determined within 4 weeks.b.A control rod shall be considered inoperable if (a)the rod cannot be moved by the CRDN, or (b)the rod is misaligned frcm its bank by more than 15 inches, or (c)the rod drop time is not met.c.If a control rod cannot be moved by the drive mechanism, shutdown margin shall be increased by boron addition to compensate for the withdrawn worth of the inoperable rod.5.CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm are not operable, rod positions shall be logged once per shift and after a load change greater than 1(5 of rated power.If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93$of rated power.6-POWER DISTRIBUTION LIMITS a.Hot channel factors: With steam generator tube plugging<25K,, the hot channel factors (defined in the basis)must meet the following limits at all times except during low power physics tests: F (Z)<(1.93/P)x K(Z), for P).5 Fq (Z)<(3.86)x K(Z), for P<.5 F"H<1.55 Ll.+0.2 (1-P)J Where P is the fraction of rated power at which the core is operating; K(Z)is the function given in Figure 3.2-3;Z is the core height 1'ocation of Fq.If f , as predicted by approved physics calculations, exceeds 1.93, the ower will be limited to the rated power multi:plied by the ratio of 1.93 divided by the predicted f , or augmented surveillance of hot channel factors shall be implemented.
{{#Wiki_filter:reactivity insertion     upon ejection greater than 0.3/ k/k at rated power. Inoperabl'e rod worth shall be determined within 4 weeks.
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: b. A control rod shall be considered inoperable       if (a) the rod cannot be moved by the CRDN, or (b) the rod is misaligned frcm its bank by more than       15 inches, or (c) the rod drop time is not met.
p 3'-3 6/5/80 II 4l (Q,)I~
: c. If a control rod cannot be moved by the drive mechanism, shutdown margin shall be increased by boron addition to compensate for the withdrawn worth of the inoperable rod.
b.Following initial loading before the reactor.is operated above 75$of rated power and at regular effective full rated power monthly interval's thereafter, power distribution maps, using the movable detector system shal'1 be made, to confirm that the hot channel factor limits of the specification are satisfied.
: 5. CONTROL ROD POSITION       INDICATION If either   the power range channel deviation alarm or the rod deviation monitor   alarm   are not operable, rod positions shall be logged once per shift and after a load change greater than 1(5 of rated power.           If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93$ of rated power.
For the purpose of this comparison, (I)The measurement of total peaking factor, F, shall be increased by three percent to account for q manufacturing tolerances and further increased by five percent to account for measurement error.(2)The measurement of the enthalpy rise hot channel factor, F H, shall be increased by four percent to account for measurement error-If either measured hot channel factor exceeds its limit specified under Item 6a, the reactor power shall be reduced so as not to exceed a fraction of the rated value equal to the ratio of the F or F H limit to measured value, whichever is 1'ess, and-the high neutron flux trip setpoint shall be reduced by the same ratio.If subsequent in-core mappi ng cannot, within a 2'4 hour period, demonstrate that the hot channel factors are met, the reactor shall be brought to a hot shutdown condition with return to power authorized only for the purpose of physics testing.The reactor may be returned to higher power levels when measurements indicate that hot channel factors are within limits.c.The reference equilibrium indicated axial flux difference as a function of power l.evel (called the target flux difference) shall be measured at lest once per effective full power quarter.If the axial flux difference has not been measured in the last effecti,ve full power month, the target flux di'fference must be updated monthly by linear interpolation using the most recent measured value and the value predicted for the end of the cycl'e life.d.Except during physics tests or duri ng excore calibration procedures and as modified by items 6e through 6g below, the indicated axial flux differene shall be maintained within a+5$band about the target flux difference (this defines the target band on axial flux difference).
6- POWER DISTRIBUTION LIMITS
e.If the i ndicated axial flux difference at a power level greater than 90'A of rated power devi ates.3.2-4 6/5/80 ll l HOT CHANNEL FACTOR NORMAL IZEO OPERATING ENVELOPE (for<2N steam generator tube plugging and F=1.93)(6.0,1.000)
: a. Hot channel   factors:
(11.2,.935)g 12.0,.518)~
With steam generator tube plugging <25K,, the hot channel factors (defined in the basis) must meet the following limits at all times except during low power physics tests:
'-BOTTOM 10 12 TOP CORE HEIGHT (FT.)Figure 3.2-3 6/5/80 0 I)I I 0'I~\A P I/'}}
F   (Z) < (1.93/P)x K(Z), for P ) .5 Fq (Z) < (3.86) x K(Z), for P < .5 F"H < 1.55   Ll.+0.2 (1-P) J Where P is the fraction of rated power at which the core is operating; K(Z) is the function given in Figure 3.2-3; Z is the core height 1'ocation of Fq.
If f , as predicted by approved physics calculations, exceeds 1.93, the   ower will be limited to the rated power multi:plied by the ratio of 1.93 divided by the predicted     f , or augmented surveillance of hot channel factors shall be implemented.
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: b. Following initial loading before the reactor. is operated above 75$ of rated power and at regular effective full rated power monthly interval's thereafter, power distribution maps, using the movable detector system shal'1 be made, to confirm that the hot channel factor limits of the specification are satisfied. For the purpose of this comparison, (I)   The measurement of total peaking factor,     F,     shall be increased by three percent to account for q manufacturing tolerances and further increased by five percent to account       for measurement error.
(2)   The measurement of the enthalpy rise hot channel factor, F H, shall be increased by four percent to account for measurement error-If   either measured hot channel factor exceeds its limit specified under Item 6a, the reactor power shall be reduced so as not to exceed a fraction of the rated value equal to the ratio of the F or F limit to measured value, whichever is 1'ess, and- the high neutron H flux trip setpoint shall be reduced by the same ratio.         If subsequent in-core mappi ng cannot, within a     2'4 hour period, demonstrate that the hot channel factors are met, the reactor shall be brought to a hot shutdown condition with return to power authorized only for the purpose of physics testing. The reactor may be returned to higher power levels when measurements indicate that hot channel factors are within limits.
: c. The   reference equilibrium indicated axial flux difference as a function of     power l.evel (called the target flux difference) shall be measured at lest once per effective full power quarter.           If the axial flux difference has not been measured in the last effecti,ve full power month, the target flux di'fference must be updated monthly by linear interpolation using the most recent measured value and the value predicted for the end of the cycl'e life.
: d. Except during physics tests or duri ng excore calibration procedures and as modified by items 6e through 6g below, the indicated axial flux differene shall be maintained within a + 5$ band about the target flux difference (this defines the target       band on axial flux difference).
: e. If the   i ndicated axial flux difference at   a power level greater than 90'A of rated power devi ates.
3.2-4                           6/5/80
 
ll l
 
HOT CHANNEL FACTOR NORMAL IZEO OPERATING ENVELOPE (for <2N steam generator tube plugging and F =1.93)
(11.2,.935)g (6.0,1.000) 12.0,.518)~
10      12
'- BOTTOM                                                     TOP CORE HEIGHT   (FT.)
Figure 3.2-3                   6/5/80
 
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Latest revision as of 11:16, 22 October 2019

Revised Tech Specs,Pages 3.2-3 & 3.2-4 for Amend to App a of Licenses DPR-31 & DPR-41.Reflects Results of Revised ECCS Analysis on Power Distribution Limits for 25% Steam Generator Tube Plugging
ML17339B087
Person / Time
Site: Turkey Point  NextEra Energy icon.png
Issue date: 06/05/1980
From:
FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17339B086 List:
References
NUDOCS 8006090393
Download: ML17339B087 (6)


Text

reactivity insertion upon ejection greater than 0.3/ k/k at rated power. Inoperabl'e rod worth shall be determined within 4 weeks.

b. A control rod shall be considered inoperable if (a) the rod cannot be moved by the CRDN, or (b) the rod is misaligned frcm its bank by more than 15 inches, or (c) the rod drop time is not met.
c. If a control rod cannot be moved by the drive mechanism, shutdown margin shall be increased by boron addition to compensate for the withdrawn worth of the inoperable rod.
5. CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm are not operable, rod positions shall be logged once per shift and after a load change greater than 1(5 of rated power. If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 93$ of rated power.

6- POWER DISTRIBUTION LIMITS

a. Hot channel factors:

With steam generator tube plugging <25K,, the hot channel factors (defined in the basis) must meet the following limits at all times except during low power physics tests:

F (Z) < (1.93/P)x K(Z), for P ) .5 Fq (Z) < (3.86) x K(Z), for P < .5 F"H < 1.55 Ll.+0.2 (1-P) J Where P is the fraction of rated power at which the core is operating; K(Z) is the function given in Figure 3.2-3; Z is the core height 1'ocation of Fq.

If f , as predicted by approved physics calculations, exceeds 1.93, the ower will be limited to the rated power multi:plied by the ratio of 1.93 divided by the predicted f , or augmented surveillance of hot channel factors shall be implemented.

OQ@609059~ 3'-3 6/5/80 p

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b. Following initial loading before the reactor. is operated above 75$ of rated power and at regular effective full rated power monthly interval's thereafter, power distribution maps, using the movable detector system shal'1 be made, to confirm that the hot channel factor limits of the specification are satisfied. For the purpose of this comparison, (I) The measurement of total peaking factor, F, shall be increased by three percent to account for q manufacturing tolerances and further increased by five percent to account for measurement error.

(2) The measurement of the enthalpy rise hot channel factor, F H, shall be increased by four percent to account for measurement error-If either measured hot channel factor exceeds its limit specified under Item 6a, the reactor power shall be reduced so as not to exceed a fraction of the rated value equal to the ratio of the F or F limit to measured value, whichever is 1'ess, and- the high neutron H flux trip setpoint shall be reduced by the same ratio. If subsequent in-core mappi ng cannot, within a 2'4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> period, demonstrate that the hot channel factors are met, the reactor shall be brought to a hot shutdown condition with return to power authorized only for the purpose of physics testing. The reactor may be returned to higher power levels when measurements indicate that hot channel factors are within limits.

c. The reference equilibrium indicated axial flux difference as a function of power l.evel (called the target flux difference) shall be measured at lest once per effective full power quarter. If the axial flux difference has not been measured in the last effecti,ve full power month, the target flux di'fference must be updated monthly by linear interpolation using the most recent measured value and the value predicted for the end of the cycl'e life.
d. Except during physics tests or duri ng excore calibration procedures and as modified by items 6e through 6g below, the indicated axial flux differene shall be maintained within a + 5$ band about the target flux difference (this defines the target band on axial flux difference).
e. If the i ndicated axial flux difference at a power level greater than 90'A of rated power devi ates.

3.2-4 6/5/80

ll l

HOT CHANNEL FACTOR NORMAL IZEO OPERATING ENVELOPE (for <2N steam generator tube plugging and F =1.93)

(11.2,.935)g (6.0,1.000) 12.0,.518)~

10 12

'- BOTTOM TOP CORE HEIGHT (FT.)

Figure 3.2-3 6/5/80

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