ML19345E988

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Proposed Tech Spec Page 3/4.2.3 for Power Distribution Limits Re Min Critical Power Ratio
ML19345E988
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 01/30/1981
From:
GEORGIA POWER CO.
To:
Shared Package
ML19345E986 List:
References
NUDOCS 8102060487
Download: ML19345E988 (5)


Text

.

O NRC DUCKET 50-366 OPERATING LICENSE NPF-5 EDdIN I.

HATCH NUCLEAR PLANT UNIT 2 PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS The proposed amencnent to the Unit 2

Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:

REMOVE PAGE INSERT PACE 3/4.2-6 3/4.2-6 3/4.2-7 3/4.2-7 3/4.2-7a 3/4.2-7b

\\

8102060 32

POWER DISTRIBUTION LIMITS 3/4.2.3 Miti! MUM CRITICAL POWER RATIO LIMITING CONDITION FOR OPERATION 3.2.3 The MINIMUM CRITICAL POWER RATIO (MCPR), as a function of average scram time and core flow, shall be equal to or greater than shown in Figure 3.2.3-1 or Figure 3.2.3-2 mul tiplied by the Kr shown in Figu e 3.2.3-3, where:

0 or (Tave - TB), whichever is greater, r =

n B

rA 1.096 sec (notch 36), Specification 3.1.3.3 scram time limit to

=

h Ni y (0.059),

0.834 + 1.650 T

=

B nI t;1 i=1 nE.Ntii

=

Tave i=1 n

I Nj i=1 number of surveillance tests performed to date in cycle, n =

Nj = number of active control rods measured in the ith surveillance

test, average scram time to notch 36 of all rods measured in the r =

g ith surveillance test, and total number of active rods measured in 4.3.C.2.a.

N

=

1 APPLICABILITY:

CONDITION 1, when THERMAL POWER > 25% RATED THERMAL POWER ACTION:

With MCPR less than the applicable limit determined from Figure 3.2.3-1 or Figure 3.2.3-2 initiate corrective action within 15 minutes and continue corrective action -

so that MCPR is equal to or greater than the applicable limit 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 POWER to less than 25% 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 />.

r SURVEILLANCE REQUIREMENTS s 4.2.3 The MCPR limit at rated flow shall oe determined for each type of fuel (8X8R and P8X8R) from figures 3.2.3-1 and 3.2.3-2 using a.

t 1.0 prior to the initial scram time measurements for the

=

cycle performed in accordance with Specification 4.3.C.2.a. or Hatch-Unit 2 3/4.2-6

3/4.2.3 MINIMUM CRITICAL POWER RATIO SURVEILLANCE REQUIREMENTS (Continued) b.

t as defined in Specification 3.2.3; the determination of the limit must be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the conclusion of each scram time surveillance test required by Specification 4.3.C.2.

MCPR shall be determined to be equal to or greater than the applicable limit:

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 />, b.

Whenever THERMAL POWER has been increased by at least 15% of RATED THERMAL POWER and steady state operating conditions have been established, 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 a LIMITING CONTROL R0D PATTERN for MCPR.

I s

HATCH-UNIT 2 3/4.2-7' i

i l

1.29

~~

~ - ~ ~ ~

+

1.28

- _. ---- --~

=

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5,27 1.26 = = - - -. -.

7 e

~

._= d S E31 i_

S 1.25 a

2_

1.24

-.. ~

2 1.23 1.22 e-1.21

- - - - ~

c~._

=.. _.. = = _

- _.. _.. _ _ _ _... ~ _.. -.

O.0 0.2 0.4 0.6 0.8 1.0 T

MCPR LIMIT FOR 8X8R FUEL AT RATED FLOW FIGURE 3.2.3-1 1.29

.N 1.28

/

s'

  • %=

1.27

- =.

1.26 Ef 1.25 Ed

~

1.24

^-

1.23 s

.s.

1.22 1.21

+

.-m mm 0.0 0.2 0.4 0.6 0.8 1.0 T

MCPR LIMIT FOR P8X8R FUEL AT RATED FLOW HATCH UNIT 2 FIGURE 3.2.3-2

4 i

1.4

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M ANUAl' FLOW CONTilOL

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SCOOP TUDE SETPOINT CAllDRATION

~

8

.. !:si:ii i.

N s

.i$ __ _

sd+.l.jiYi5it POSITIONED SUCil Til AT. _ _

- g#

s 1.0, MAXIMUM FLOW

= 102.5%

I

= 107.0%

i n

= 112.0%

l

= 117.0%

i y

(M

~

030 40 50 SO 70 00 00 100 110 gM Core' Flow, of Rated core Flow O

K Factor p

m..

FIGURE 3.2.3-3 W

EEE3 u

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