ML17319A978

From kanterella
Jump to navigation Jump to search
Amend 48 to License DPR-58,revising Fq Peaking Factor Limit
ML17319A978
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 07/21/1981
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17319A979 List:
References
NUDOCS 8107240577
Download: ML17319A978 (13)


Text

, ~

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

'INDIANA'AND'MICHIGAN'ELECTRIC COMPANY'OCKET'NO:

50-'315

DONAL'D'C;'COOK NUCL'EAR'PLANT 'UNIT NO.

1

'AMENDMENT'TO FACIL'ITY OPERATING LICENSE Amendment No. 48 License No.

DPR-58 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

8.

C.

D.

E.

The application for amendment by Indiana and Michigan Electric Company (tFIe licensee) dated March 26, 1981, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of th.e Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with '10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

81P72~

5 pgppp3$ 5 7 81P72l PDR P

Jt

I

2 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.{2) of Facility Operating License No. DPR-58 is hereby amended to read as follows:

(2)

Technical Soecificati'ons The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

48, are hereby incorporated in the license.

The licensee shall operate the faci lity in accordance with the Technical Specifications.

\\

3.

This license amendment is effective as of the date of its issuance.

FO THE NUCLEAR REGULATORY COMMISSION Attachment!

Changes to the Technical Specifications Oate of Issuance:

July 21,

'f981 even

. Varga, Chip

> Operating Reactors B

a ch ~l Oivision of Licensing

ATTACHMENT'TO 'L'ICENSE 'AMENDMENT

'AMENDMENT'NO; 48'TO R FACIL'ITY'OPERATING L'ICENSE 'NO.

DPR-58 DOCKET 'NO; '50-'315 Revise Appendix A as follows:

3/4 2-3

'/4 2-6 3/4 2-15 3/4 2-16 3/4 2-17 3/4 2-19 3/4 2-20

  • 83/4 '2'-'.1 B3/4 2-2 3/4 2-3 3/4 2-6 3/4 2-15 3/4 2-16 37.4 2-17 3/4 2-19 3/4 2-20
  • B3/4.2-'3

'3/4 2-2

  • Included for convenience

POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS Continued 4.2.1.2 The indicated AFD shall be considered outside of its + 5X target band when at least 2 of 4 or 2 of 3 OPERABLE excore channels are indicating the AFD to be outside the target band.

Penalty deviation outside of the + 5X target band shall be accumulated on a time basis of:

a.

A penalty deviation of one minute for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50K of RATED THERMAL POWER, and b.

A penalty deviation of one-half minute for each one minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 505 of RATED THERMAL POWER.

4.2.1.3 The target axial flux difference of each OPERABLE excore c)annel shall be determined in conjunction with the measurement of F (z) as defined in Specification 4.2.2.2.C.

The provisions of Speci-fication 4.0.4 are not applicable.

D. C.

COOK - UNIT 1

3/4 2-3 Amendment No. 48

POWER. DISTRIBUTION LIMITS SURYEILLANCE RE UIREMENTS 4.2.2.1 4.2.2.2

'a

~

c ~

for P<.5 where:

F (Z)

= F~(Z,a) at a for which M

(} 's a maximum TTTE F~(Z)

= F~(E

)

at x for which

.is a maximum T

E F '(Z) and F (2) are functions of core height, 2,

and correspond L

a each Z t3 the rod s for which F (Z,s) is a maximum at that Z.

T Es V(Z) is the function defined in Figure 3 2-3 K(Z) is defined in Figure 3.2-2, T(EE) is defined in Figures 3.2-3a and 3.2-3b, P is the fraction of RATED THERMAL POWER.

Ep(Z) isLan uncer-tainty factor to account for the reduction in the F(E)t) curve due to an accumulation of exposure prior to tive next flux map.

The provisions of Specification 4.0.4 are not applicable.

F (Z,a) shall be determined to be within its limit by:

Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5X of RATED THERMAL POWER.

Increasing the measured F~(Z,a) component of the power distribu-tion map by 3X to account for manufacturing tolerances and further increasing the value by 5Ã to account for measurement uncertainties.

Satisfying the following relationship at the time of the target flux determination.

Fq(Z)

L Fg(z)

~pq 2

[K(z)j/(u(z) 3 for P

>.5 2F (Z)

F()(Z) ~Z

[K(Z))f(V(Z)1 E

(Z) = 1.0 0< E)E,<12. 0 E

(Z) = 1.0 + I..0039XFO(Z)3 12.0<EX<34.5

E (Z)

= 1.0 +

I.0085XFM(Z)]

34.5<E)t,<42.2

,)ensuring F (Z,s) in conjunction with a target flux difference determinati%In, according to the following schedule:

D. C.

COOK - UNIT 1

3/4 2-6 Amendment No.

48

POWER DISTRIBUTION LIMITS AXIAL P01JER DISTRIBUTION LIMITING CONDITION FOR OPERATION 3.2.6 The axial power distribution shall be limited by the following relationship:

CFj(Z)lS =

Where:

2.10 K Z (R

~ )(PL)(1.03)(l

+ aj)(1.07)

F a.

F.(Z) is the normalized axial power distribution frcm thimble j at core elevation Z.

b.

PL is the fraction of RATED THERMAL PO!JER.

c.

K(Z)"'s the function obtained from Figure 3.2-2 for a given core height location.

d.

R-, for thimble j, is determined from at least n=6 in-core flux maps covering the full configuration of permissible rod patterns at 100K or APL (whichever is less) of RATED THERMAL POWER in accordance with:

lJhere:

F '."/ T(Ea) 1j Max e.

R.. and its associated a

may be calculated on a full core or a lfkiting fuel batch basil as defined on page B3/4 3-3 of basis.

F' is the limiting total peaking factor in flux map i.

The Qia limiting total peaking factor is that factor with least margin to the Fg(Et) curve defined in Figure 3.2-3a for Exxon Nuclear Company fuel and in Figure 3.2-3b for Westinghouse fuel.

D.

C.

COOK - UNIT 1

3/4 2-15 Amendment No.

48

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION Continued T(Ea) is the ratio of the exposure dependent FQ(E) to 2.10 and is defined in Figure 3.2-3a for fuel supplied by Exxon Nuclear Company and in Figure 3.2-3b for fuel supplied by Westinghouse El ectric Corporation.

f.

LF..(Z)]M is the maximum value of the normalized axial distri-ij Max bution at elevation Z from thimble j in map i which had a limit-ing total measured peaking factor without uncertainties or densification allowance of FMeas Qia o-is the standard deviation associated with thimble j, expressed ak a fraction or percentage of R., and is derived from n flux maps from the relationship below, or 0.02, (2X) whichever is greater.

R-The factor 1.07 is comprised of 1.02 and 1.05 to account for the axial power distribption instrumentation accuracy and the measurement uncertainty associated with FQ using the movable detector system respectively.

The factor 1.03 is the engineering uncertainty factor.

g.

F is an uncertain(y factor for Exxon fuel to account for the rPduction in the F (E) curve due to an accumulation of ex-posure prior to thf next flux map.

The following Fp factor shall apply:

F

= 1.0 F

= 1.0 + [.0015 X W]

P F

= 1.0 + L0.0030 x W]

P 0<Ex<12 12<EX<34.5 34.5<Et<42.2 where W is the number of effective full power weeks (rounded up to the next highest integer) since the last full core fIux map.

D.

C.

COOK - UNIT 1

3/4 2-16 Amendment No. 4B

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION Continued APPLICABILITY: Mode 0'1 above the percent of RATED THERMAL POWER indicated Syy,......hp.

x 100K P

5 L

APL=minoverZof F Za x V Z x Ep Z) g where F (Z,a) is the measured F (Z,a), including a

3Ã manufacturing tolerance uncertainty and a

5X measurement uncertainty, at the time of target flux determination from a power distribution map using the movable incore detector.

(1)

Lower core region 0 to 10Ã inclusive (2

Upper core region 905 to 1005 inclusive ACTION:

a.

With a F (Z) factor exceeding fF.(Z)jS by

< 4 percent, reduce THERMAL POWER 1 percent for every percent by which the F -(Z) factor exceeds its limit within 15 minutes and within th3 next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either reduce the F (Z) factor to within its limit or reduce THERMAL POWER to APL or less of RATED THERMAL POWER.

b.

With a F.(Z) factor exceeding

[F.(Z)j by ) 4 percent, J

J reduce THERMAL POWER to APL or less of RATED THERMAL POWER within 15 minutes.

0 The APDMS may be out of service:

1) when incore maps are being taken as part of the Augmented Startup Test Program or 2) when surveillance for determining.power distribution maps is being performed.

D. C.

COOK - UNIT 1

3/4 2-17 Amendment No.

48

2.2 2.1 2.0 1.9 1.8 1.7 1.6 1.0

.9

.8 7.

0 I

I (0,2.07)

(12

~

I I ~

fili I

~ ~ ~

.;0 "3.

eJ 02 05 alai

+IQ

.Il!I

~ ~ i I Iaas I t

~ -

~

I

~

~ ~

~ I

~

~ I ~

~ ~

I

~ I I:I' Iit I ~ ~

e ~

~ i

~

~

~

~ ~ ~

I

~

~

1 '

I

~ ~

,I I

! I I, i;!;

I I

~ I ~ I

~

~

e

~

~ ~

~ ~ ~

~ ~ !

I i.! ~

~

I

's

~ ~

~

I

~ I ~ ~

~ e

~ lal III:

I:aa

~ ~ !

~ iis

~ I I ~

~

tl f ei ~

I

~

I I I I iE'i

~ ~

~ ~

(0,. 986

~ ~

..:,9.86 1;03 (g)

='.

(12;";

~ I five

~ I

'0 1

02

~ ~ ~ ~

(E):,

1',.134 05

~

I

~

~ ~ ~ ~

10

~ I ~

~

~

~

~

~

~ I

~

IL. '..'.

<,(Q E, (E):

q.'.,(Fj);

I I ~

~

~

e

~

~ Lf li~,I J(i itj!

II I I IIII It i

~ ~ I!

,'il I

~

I I E~t ist,j ji;i I ~ e

~

~

~ I ~

l flat

~

a

~ I

~

~

~ ~ I

~ ~ ~ ~

I ~

e ~ ~ ~

e

~ ~

~ ~ ~ i

~ ~

I

~

~

~ ~

~ e

~ I I I Ij.l I.jf

.II.'

leaf

III

~ I I i

~J ii ~

I I I ~

i tl I

.a!

~ ~

~

~

~ I

~ ~ ~ I

~ I ~

sa.'.'j e

~

~

3E):('.;

34

~ i ~ ~

.!oy:

jI

~ I I I

~ t

~

city

~ I Ii'I

~ ~ ~ o I

I I I i!!i
iF

~ I I

~

~

~ I lE

a I e

jIE a ~

~

II I'I

~

~

~

~ o

~

I ~

~

~

It:

llji till et.t

~ ~

~ ~

I'I's

~ ~ ~ I I I I

asia I

~ ~

!~sf '

~ II I I ~

~

ii ~ ~

~ ~ I ~

....I..

0..:~.E

~

e

~ ~

al

~

I L

5i.c. E

~

e

~ ! ~

~

~

)/s)

~ ~

I' I( I I I

~

~

lj..'tll 2 ~.

gill t:Il

~ ~

~

~

~

~

~ ~

~ ~ ~

~ ~ ~ ~

~ I ~

~ ~

~ I ~ ~

~ I

~ I

~ I

~ I I I ~

I

~ ~

i!tj

~ ~ ~

~ ~ ~ ~

~ Ja

~

~ ~ I

~

Itti tIEII

~

~ ~ ~

':-'>4';-'<',,42.

I

'I I! s.'

I

~

I e

~

e I:It II I I h

~

~ I jf:I t

~ I I Ijjt lt'I IIJ.

..a I a I t,

~

~

~ e

~

I s

I k';tjj

~ e ~ ~ ~

~

~ h

~ ~ ~

~ I i I

I ~ ~ ~

~

~ ~

jftlt

~ !!'

~ ~ I I t

~i.'ll l

I![i ljtf i

lilj ljtl

.':. 't

!.'!i'I l

~

~ ~

~ ~ ~ ~

~ ~ ~ I

~ ~ ~ !

III I ~ ~

~ I I I '

~ I Iit

~ I I

~

ilsif I ~ I

~

lj!I I ~ ~

~

~ ~

e

~

~

~

~

~ ~ I

~

~

I ~

~

I I il'i tl

'I j

j Ifh

~

e ~

~

~

~

~

~ I

~ i

~ ~ ~ e

~ ~ I

~ ~ I I ~ ~ ~

~hJh I'i Ijtf la

~

~l

~

jj",:

~ I ~

!I!!

Ii

~

I ~

~ ~ ~

ih

~

tsas ijjl a

I

~ I ~ (3 ItJI

[!Ji

'tt

[jsl I

~

~

~

IJI htl ~

I ~ I ~

JL)E Jt.s I

~

~ I

~

e

~

Ie!

~

I

~

~

jjlj

,:Ltjj 34 i:ll ii, jill I IIi I ~

I

~ ~ ~

I ~ ~

~ e alai

~ ~ I I

~ ~

~

I I ~ I iiil IIII I tl

);:;i Ils'

~ '

~ ~ ~

~

~ I

~ ~

~

I- ~ I

~'ll jlij t lit I ~ ~ ~

~ ~ I

~ ~

~ ~ ~ ~

~ ~ ~

~ ~ ~

~ ~ ~ ~

~

e

~ I he

~ e!

~ ~ ~

~

~

tt so

~ ~ a i ~ I

~ ~ Is I ~ t ljsl jlI!

[It!'Ill

~ ~ ~

~

~

~

~

~ ~

~ ha ltli Ili':

Isis iti!

a

~ J e

~ ~ I aft.'tlt I'ea'I

!jtl

~ I I

~

Hti

~ I Jjl sit

~ I) I

~ i ~

~

.5)..94 "Il I ~

e

~J ETII

~ a

~ ~

~ ~ ~

llew I

eLE s.t

'-'i'

~

~

~

~

ifi:

I

~

tJ,'I

~ ~ ~ ~

till illi III l'l.'I

~

~

~ I s I

~

e

~

~

~ i

! I ~

if'.I:

I I

~ i 42.

jit;

~ lt'.

I!i':

I ~

I '

~

I ~

I is I',:

i ~

~.

I

~

~is.

I'II:

I ~ II!ii

~

~

a I

~ ~

~

~

~

2eo

~ ~

~

~ ~

e IS ~ ~

I

~

20 30 40 44 2,1.89)

,.90)

Peak Pellet Exposure In NWD/KG Figure 3.2.3a Exposure Dependent Fq Limit, Fq (g), and Normalized Limit T (E) as a Function of Peak Pellet Burnup for Exxon Nuclear Company Fuel.

n.

C.

COOK - UNIT 1 3/4 2-19 Amendment No.

48

2.0 1.S L

F (q=1oO m

~

0 0( El 1.7 I

1.0

~

I 0.9 0.8 T(Q'= 0.9OS I

.:I I

I I

l 0.7 0

4 8

12 16 20 24 28 32 36 40 44 Peak Pellet Exposure In MWD/KG Figure 3.2 - 3b F~ Limit, F<(g, and Normalized LimitT('Q as a Function of Peak Pellet Burnup for Westinghouse Fuel D. C.

COOK - UNIT 1

3/4 2-2O Amendment No.

48

~

~

~

~

~

~

~

~ ~

4 0

~

0

~

~

~

~

~

~

~

~

C C

~

~

~

~

~

~

~ I

~

I

~

~

~

~

~

~

~

~

~ ~

~

~

I

~

~

~

~

~ ~

~

~

~

~

~

~

~

" ~

~ ~

~ ~

~

~

~

~ ~

~

~

~

~

~

~

~

~ ~

~

~

~

~

~

C

~

~

~

~

~ I

~

~

~

~

~

~ l

~

~

~

~

I

~

~

~ I ~

~

~

~ ~

0

~

e

~

0

POWER DISTRIBUTION LIMITS BASES Although it is intended that the. plant will be operated with the AXIAL FLUX DIFFERENCE within the + 5X target band about the target flux difference, during rapid plant THERMAL POWER reductions, control rod motion will cause the AFD to deviate outside of the target band at re-duced THERMAL POWER levels.

This deviation will not affect the xenon redistribution sufficiently to change the envelope of peaking factors which may be reached on a subsequent return to RATED THERMAL POWER (with the AFD within the target band) provided the time.duration of the devi-ation is limited.

Accordingly, a

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penalty deviation limit cumu-lative dur ing the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is provided for operation outside of the target band but within the limits of Figure 3.2-1 while at THERMAL POWER levels above 505 of RATED THERMAL POWER.

For THERMAL POWER levels below 505 of RATED THERMAL POWER, deviations the AFD outside of the target band are less significant.

The penalty of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> actual time reflects this reduced significance.

Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alarm. The computer determines the one minute average of each of the OPERABLE excore detector outputs and provides an alarm message if the AFD for at least 2 of 4 or 2 of 3 OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 90Ã or 0.9 x APL (whichever is less) of RATED THERMAL POWER.

During operation at THERMAL POWER levels between 15% and 90/ or 0.9 x APL (whichever is less) of RATED THERMAL POWER, the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, respectively.

The upper bound limit, 90'A or 0.9 x APL (whichever is less) of RATED THERMAL'OWER, on AXIAL FLUX DIFFERENCE assures that the F~(Z,x) envelope of 2.10 times K(Z) x T(Ea) is not exceeded during either normal operation or in the event of xenon redistribution following power changes; The lower bound limit (50% of RATED THERMAL POWER) is based on the fact that at THERMAL POWER levels below 50K of RATED THERMAL POWER, the average linear heat generation rate is half of its nominal operating value and below that value, perturbations in localized flux distribu-tions cannot affect the results of ECCS or DNBR analyses in a manner which would adversely affect the health and safety of the public.

Figure B 3/4 2-1 shows a typical monthly target band near the beginning of core life.

The bases and methodology for establishing these limits is presented in topical report XN-NF-77-57. "Exxon nuclear Power Distribution Control for PWR's-Phase II" and Supplement 1 to that report.

D.

C.

COOK-UNIT 1

B 3/4'-2 Amendment No. 48