ML19345C773

Proposed Changes to Tech Specs,Section 3.10 Re Safety Injection Actuation & Power Distribution Limits

ML19345C773
Person / Time
Site:	Prairie Island
Issue date:	12/02/1980
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML19345C765	List: ML19345C764 ML19345C770 ML19345C773
References
NUDOCS 8012080329
Download: ML19345C773 (4)

Text

t.- ,

EXHIBIT B Revision No. I to License Amendment Request dated May 6, 1980 Exhibit B consists of revised pages of Appendix A Technical .,jecifications as listed below:

Pages TS.3.10-1 TS.3.10-2 TS.3.10-3 8012080 .3 29

TS.3.10-1 REV 3.10 CONTROL ROD AND POWER DISTRIBUTION LIMITS Applicability Applies to the limits on core fission power distribution and to the limits on control rod operations.

Objective To assure 1) core subcriticality af ter reactor trip, 2) acceptable core power distributions during power operation, and 3) limiced potential reactivity in-sertions caused by hypothetical control rod ejection.

Specification A. Shutdown Reactivity The shutdown margin with allowance for a stuck control rod assembly shall exceed the applicable value shown in Figure TS.3.1')-1 under all steady-s tate operating conditions, except for physics tests, frou. ero to full power, including ef fects of axial power distribution. The shutdown margin as used here is defined as the amount by which the reactor core would be suberitical at hot shutdown conditions if- all control rod assemblies were tripped, assuming l th at the highest worth control rod assembly remained frily withdrawn, and s assuming no changes in xenon or boron concentration.

B. Power Distribution Limits

1. At all times, except dgring lgw power physics testing, measured hot channel factors, F and F as defined below and in the bases, sha19 meet he, following limits:

x 1.03 x 1.05 < (2.21/P) x K(Z) x BU(E.)

F"Q -

J N

F AH x 1.04 < 1.55 x [1+ 0.2(1-P)]

where the following definitions apply:

(a) K(Z) is the axial dependence function shown in Figure TS.3.10-5.

(b) Z is the core height location (c) E. is the mgximum pellet exposure in fuel rod j for wdich the F is being measured.

Q (d) BU(E.) is the normalized exposure dependence function for Exxod Nuclear Company fuel shown in Figure TS.3.10-7. For Wes tingh ouse fuel, BU(E.) = 1.0 J

(e) P is the fraction of full power at which the core is operating.

N In the F limit determination when P <0.50, set P = 0.50.

, TS.3.10-2

. REV N

s deHned as the measured FN or F N N (f) F or F , res pect ive ly ,

wkth the#Hsmallestmarginorgreatestex0essoblimit E

(g) 1.03 is the engin ering hot channel f actor, F to the measured to account for manufacturibg,tolerance.

applied (h ) 1.05 is applied to the measured F" to account for measure-ment uncertainty N N

(i) 1.04 is applied to the measured F to account for measure-ment uncertainty N N

2. Hot channel f actors, F and F4H, s a e m asu M and the target flux difference determined, at equilibrium conditions according to the following conditions, whichever occurs first:

(a) At least once per 31 ef fective full power days in conjunction with the target flux difference determination, or (b) Upon reaching equilibrium conditions af ter exceeding the reactor power at which target flux difference was last determined, by 10%

or more of rated power.

F" o9(equil)shallmeet the core: the following limit for the middle axial 80%

(equil) x V(Z) x 1.03 x 1.05 < (2.21/P) x K(Z) x BU(E )

where V(Z) is defined in Fi dure 3.10-8 and other terms are defined in 3.10.B.1 above.

3. (a) If either measured hot channel f actor exceeds its limit specified in 3.10.B.1, reduce reactor power and the higg neutgon flux trip setpoint by 1% for each percent that the measured F-' o exceeds the 3.10.B.1 limit . Then follow 3.10.B.3.kc)r F (b) If the measured F (equil) exceeds the 3.10.B.2 limits but not the 3.10.E.1 limit, t9ke one of the following actions:

1. Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> place the reactor in an equilibrium configuration for which Specification 3.10.B.2 is satisfied, or

2. Reduce reactor power and the high neutron flux trip setpoint by 1% for each percent that the measured F x1.05xV(Z)exceedsthe(2.21/P)xK(Z)k(equil)x1.03 BU(E.) limit.

J

3 TS.3.10-3 REV (c) If subsequent in-core mapping cannot', within a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, e demonstrate that. the hot channel factors are met, the reactor

.shall be brought. to a hot shutdown condition with return to power _ authorized up to 50% power for the purpose of physics-

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testing. Identify and correct the cause of the out of limit condition prior to increasing thermal power aboge 50% Npower. g Thermal power may then be increased provided F or F is demonstrated through in-core mapping to be with9n its Yimits.

(d)- If two successivg measurements indicate an increase in the peak pin power F with exposure, either of the follow-ingactionsshalbetaken:

1. . F (equil) shall be multiplied by 1.02 x V(Z) x

.1903 x 1.05 for comparison to the limit specified-in 3.10.B.2, or

2. F e9(equil) fectiveshall full be measured power at' least days until once per seven tw successive maps N

' indicate that the peak pin power, Fg, is not

-increasing.

4. Except during physics tests, and except as provided by Specifications 5 through 8 below, the indicated axial flux difference for at least three operable excore channels shall be maintained within a +5% band about the

-target flux dif ference.

5. Above 90 percent of rated thermal power:

If the indicated axial flux difference of=two' operable excore channels

' deviates from its target band, within 15 minutes either eliminate such deviation, or reduce l thermal power to less than 90 percent of rated thermal power.

6. Between 50 and 90 percent of rated thermal power: I

a. The indicated. axial flux difference may- deviate from its +5%

target band for a maximum of one* hour '(cumulative) in any 24-h'our period provided that the difference between the indicated axial flux difference about .the target flux difference does not l exceed the envelope shown in Figure TS.3.10-6.

b. If 6.a-is violated for two operable excore channels then the reactor power shall be reduced to less than 50% power and

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the high neutron flux setpoint reduced to less than 55%

of rated power.

• May be' extended to 16' hours during incore/excore calibration.