Text

Rev 0 to Millstone,Unit 2 Cycle 11 Core Operating Limits Repts
	ML20058E634
Person / Time
Site:	Millstone
Issue date:	10/31/1990
From:	; NORTHEAST NUCLEAR ENERGY CO.
To:	;
Shared Package
ML20058E633	List: B13664, Forwards Rev 0 to Cycle 11 Core Operating Limits Rept & Changes to Tech Spec Bases Re Thermal Margin/Low Pressure; ML20058E634; ML20058E637;
References
	FRCC-901031, NUDOCS 9011070251
	Download: ML20058E634 (8)
	v • d • e

-t 1

Docket No. 50-336 B13664 i

'i i

-i r

i Millstone Unit No. 2 i

Cycle 11 i

Core Operating Limits Reports Revision 0 3

l r

October 1990 9011070251 901029 ADOCK0500t){p-DR p,

1 CORE OPERATING LIMITS REPORT 1.0 -CORE OPERATING LIMITS REPORT This -Core Operating Limits Report for Millstone 2 has been prepared in accor-dance with~ the requirements of Technical Specification 6.9.1.7.

.The technical 4

specifications associated with this. report are listed below:

Section Specification 2.1 3/4.1.1.1 SHUTDOWN MARGIN - T,yg > 200*F 2.2 3/4.1.1.2 SHUTDOWN MARGIN - T s 200'F 1

avg 2.3

'3/4 1.1.4 Moderator Temperature Coefficient 2.4 3/4.1.3.6 Regulating CEA Insertion Limits

..e 2.5 3/4.2.1

~ Linear Heat Rate T

2.6 3/4;2.3 Total Integrated Radial Peaking Factor - F 7 2.7 3/4.2.6 DNB Margin Terms appearing. in capitalized type are DEFINE 0 TERMS as defined in Section 1.0'of the Technical Specifications.

2.0 ' OPERATING LIMITS The cycle-specific parameter limits for_ the specifications listed in Sec-4 tion 1.0 are presented in the following subsections.

These limits have been developedsusing the NRC-approved methodologies specified in Technical Specifi-cation 6.9.1.7.

2.1 ' SHUTDOWN MARGIN - T,yg > 200*F -(Specification 3/4.1.1.1)

The. SHUTDOWN MARGIN shall be 2 3.6% AK/K 2.2 SHUTDOWN MARGIN - T s 200*F (Specification 3/4.1.1.2) avg The SHUTDOWN MARGIN shall be 2 2.0% AK/K 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.4)

The moderator temperature coefficient shall be:

a.

Less positive than 0.7 x 10 AK/K/*F whenever THERMAL POWER is s 70% of RATED THERMAL POWER, b.

Less positive than 0.4 x 10 AK/K/*F whenever THERMAL POWER is

> 70% of RATED THERMAL POWER, c.

Less negative than -2.8 x 10 AK/K/*F at RATED THERMAL POWER.

4 2.4 Regulating CEA Insertion Limits (Specification 3/4.1.3.6)

The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown in Figure 2.4-l~.

CEA insertion between the-Long Term Steady. State Insertion Limits and the Transient Insertion LimitsLis restricted to:

a.

14 hours1.62037e-4 days 0.00389 hours 2.314815e-5 weeks 5.327e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval, b,

s 5 Effective Full Power Days per-30 Effective Full Power Day interval, and c.

1 14 Effective Full Power Days per calendar year.

2.5 Linear Heat Rate (Specification 3/4.2.1)

The : linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed:

a.

15.1 kw/ft when the reactor coolant flow rate measured per Specification 4.2.6.1 2 340,000 gpm.

b.

14.5 kw/ft when the reactor coolant flow rate measured per Specification 4.2.6.1 1 325,000 gpm and < 340,000 gpm.

During operation with the linear heat rate being monitored :by the Excore Detector Monitoring System, the AXIAL SHAPE INDEX shall remain within the limits of Figure'2.5-1.

During operation with the linear heat rate being monitored by the Incore Detector Monitor System, the alarm setpoints shall be adjusted:to less than' or equal to the limit when the following factors are appropriately included in the setting of the alarms:

1*

Flux peaking augmentation factors as shown in Figure 2.5-2, 2.

A measurement-calculational uncertainty factor of 1.07, 3.

An engineering uncertainty factor of 1.03, 4.*- A linear heat rate uncertainty factor of 1.01 due to axial fuel densification and thermal expansion, and 5.

A THERMAL POWER measurement uncertainty factor of 1.02.

These factors arc only applicable to fuel batches "A" through "L".

,\\

2.6 Total Integrated Radial-Peaking Factor -- F (Specification 3/4.2.3) r The calculated value of Fr, defined as F T p (1+T ), shall be limited I

7 r

q I

e a.

0.90 < PF s l.00 F

s (11.73 - PF)((1.24 x 10 7 x FL) + 0.108) r I

-b.

0.70 < PF s 0.90 F

s (3.50 - PF)((5.18 x 10~7.x FL) + 0.449) r I

'c.

PF s 0.70-F s 1.75 ((8.28 x 10 7 x FL) + 0.718) r

where, PF = THERMAL POWER divided by RATED THERMAL POWER FL = The lesser of either:

'1 )

The ' reactor coolant flow rate measured,per Technical Specification 4.2.6.1 down to a minimum of 325,000 gpm, or 2) 340,000 gpm.

- 2.7 DNB Margin (Specification 3/4.2.6)

The DNB margin shall be _ preserved by maintaining the cold leg tempera-ture, pressurizer pressure, reactor coolant flow rate, and AXIAL ' SHAPE INDEX within the following limits:

Limits Four Reactor Coolant Parameter Pumns Goerations s-a.

Cold Leg Temperature i_549'F b.

Pressurizer Pressure 1 2225' psia *

-c.

Reactor Coolant Flow Rate 2 340,000 gpm**

c d.

AXIAL SHAPE INDEX FIGURE 2.7-1 Limit not' applicable during either a THERMAL-POWER ramp ' increase in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.

Figw reductions to 325,000 gpm are compensated for by reductions in the F

. limit (Technical Specification 3.2.3).

r 1

e.

2

'r-0B9

- g

.i 8

3..

.3

. l

..;....j. :......._.

1..

..-1

_....i.

.1.._..g,.

M, i

_.o

..I g

.a.

.s l

1 l.

i..

g:

I

. i.. i. _... _. 2 _ __'.__.

...l...:.

Si a.

g _..

i. l:

~

. i -

I-i i :..l en eamaremmi._. i. _. i........ :...

i I am m

s __I_

.l e.n oannee n e -

2 i:

i s

_.1._

.___..i....__..____._

w....

il l

i.

=

1. ;.

.i

= = en n e e s =.. l.

l.

2 i

3

...I 8

,i..... j..__

_s.s!5

[

=

eos taaseseewir essenvoose unst -.l.

e l.

Ic h s:*

1633l--.

to a5

==a g>8 -- >

l

.l..

o a.

~ = n >s..:

g..

8

a g g:

= q 4._.,

1.

t i.-

.... T..

3-

. l..

.1... F

_i..

l

3...

+_

g

._;... 3..

m.m. amaseeem i-i i

no

..o

..s :..

.. s.

.g

. v

.s.

. n l

Q.

_ g.

_.s._..:.,

gg

.J

.... l..

l g..

me.samm eeestB g

l

.i l-l

. i

,i B

1 8 I I

I I

I I s I I

B B

1 1 3 I I

I samag e

ao se ao es ses e

ao se se se eso o

me se ce so.

see a

I I

I e g g

g g

g e

ao se es es see e

as ao se es ese.

1LOF CE A see5ER790N CEA Insertion Limit vs. THERMAL POWER with Four Reactor Coolant Pumps Operating FIGURE 2.4-1

mm z

2 I

0; y

m s

E

~

j Z

ro M-UNACCEPTABLE OPERATING REGION 199 -

C A-goe.

8 D

R

{ "~

ACCEPTABLE OPERATING REGION g

[ eo-1 Break Points

~

A.ll-0.30,65;>

E '

8 A B.'I,-0.04.100i

- ee-C. I,0.00,102)

O. I 0.08.100)

E. (,0130,65)

Note: Point "C" is pr(vided for setting plant 40-instrumentation only. Operation is not allowed above 100% of rated power.

~

-o.4

-o.3 5.2 6.1

.o 5.1

.2 3

c.4 FIGURE 2.5-1 AXIAL SHAPE INDEX vs. PERCENT OF ALLOWABLE POWER LEVEL

y 4

1 r-tsee r-i w

.I,

g I-t e

s z

s l

m J.

.i

.j

!ii.

s.ses..

.t I

--4 g:

I",_.

i

. g.

m s.

t

.i l

l.

t

$ses.

o i.

i g

l_

~,

L.

l...

~,

g sme

.2 u

..l.. i 1 J.

V...

11.

L t

m e,

i s

.8 gase

=.;

i..

.r I.

e

~.

,e.

- a.

k s

-.: n

.~

.t,ie, ii

..i:.l.:3

.:is. ;.p:

s.

i~

g

~

ggg g

e

..:.s,

. xl m...

s

, 4

.,:..l; :n bg: :l....eg g

.i.

8;.

s.:; :.,.,

3.-

i3 :g..

l.

.. a

)

,,g, g;

g.

1.

[.

(

l t

ggg, e

2e es es se too no see esevassca encasserviuser cesse.a'ecsets t

1 FIGURE 2.5-2, Augmentation Factor vs. Distance from Bottom of Core

-(only applicable to fuel batches "A" and "L")

y l

-a

'It r

4 12

.1 r

t i

i q-i i-1

,,,q

.I, j..

-l

..l j..

l..-

"l zic

'l-i-

't i

i 1

1.1

l j

-l -

l aj i

.t.

i.

1.

.:p.:

l-

j..

j i

i l-

-l

-l j

..]

i t.

-l _

i 4

l s-- -

1.0

~

i e

1 h.0.15.1.01

)

- ( 4.1 0. 1.01 1

l:

i i

-i j/

j

{\\

3 d,' -

e/i !

l "I

e i-t

" UN ACCEPT AB LE [

UN ACCEPT ABLE ~~

OPE R ATION

' f 9

- 43

~

,,i L-OPE R ATl0N i

Ii-Ii

'i I

\\

REGION

.lm *:EGION l.'

,;.l.j

.:t i

\\

l

s.e q -

l

.?

j[

1 i

i 1

-1 1

' g 1-i

/.

i

..i

\\

ACCEPTABLE -

Y (0 30.0 E

[l I

.4 j.

4 I

l(

h 0.8

.(.C.30. 0.M -

8 i

(

I -

g

.l F-1 t.

i

-. - - --i. -

e OPE R ATION g' -

gg gggy

+

J.

3

i i

I 0.7 t

i i

l

.i o

i.

t l

l i

l-1 a

i e

r g

I

.i i

j-8.6 l-

.t t'

I I

i i-1 I

i-

.i i,

-li i

l 1

i i

i l

?

i i

I i-l

i. l I

- -r

--r-i es l

t

{

t i

t l

l-

l -

-l j..-

i i

l i

e i.

i i

l-i.

.s l

l 3

1 3

i-

- e.4 8.2 0.4 c.6

=0.6 ae.4

=0.2 0-Y g L

JIGURE 2.7-1 AXI AL SHAPE INDEX Operating Limits with Four-Reactor Coolant Pumps Operating

+

MILLSTONE - UNIT 2

'*P--*

T-t wre w*

m m-

-.

ML20058E634

Text

Navigation menu

Search