ML19341B142

From kanterella
Jump to navigation Jump to search
Amends 59 & 56 to Licenses DPR-39 & DPR-48 Respectively, Allowing Reinsertion of Four Fuel Assemblies Previously Irradiated in Both Units Back Into Unit 1 to Irradiate High Burnup Fuel for Lost Cycle
ML19341B142
Person / Time
Site: Zion  File:ZionSolutions icon.png
Issue date: 12/31/1980
From: Varga S
Office of Nuclear Reactor Regulation
To:
Shared Package
ML19341B138 List:
References
NUDOCS 8101300328
Download: ML19341B142 (7)


Text

'

i je reg 9

jo UNITED STATES g

(y g

NUCLEAR REGULATORY COMMISSION i

p WASHING TON, D. C. 20555 j

  • \\...../

I l

COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-295 ZION STATION UNIT i AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR-39 l.

The Nuclear Regulatory Commission (the i,ommission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated December 3,1980, 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; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the act'.vities authorize:s by this amendment can be conducted without andangering the health and safety of the public, and (ii) 1. hat such activities will be conducted in comnifance with the Commission's regulations; p

1 D.

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 l

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements i

have been satisfied.

\\

git 130O h

.[

I.

e i

I L

Y 2.

Accordingly, the license is amended by changes to the Technical Spe:ific'ations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No.-DPR-39 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FQRTHENUCLEARREGULATORYCOMMISSION p(s tevenA.ui M tiL0L Yarga. Chil!

Operating Reactors B nch #1 i

Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 31, 1980 f-o 4

~%

UNITED STATES 4

E ' T g(

i NUCLEAR REGULATORY COMMISSION e j.g WASHING TON, D. C. 20555 t-

%,**v p'e COMMONWEALTH EDISON COMPANY DOCKET N0. 50-304 ZION STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. DPR-48 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated December 3,1980, compli7s 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; B.

The facility will operate in conformity with the applic,ation, the provisions of the Act, and the rules and reg 11ations of the Commission; C.

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; D.

The issuance of this amendment will not be inimical to the cocunon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been fatisfied.

./

i m.-

m m-.

m 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-48 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 56, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

[L g

.Yarga,Chikg ven perating Reactors BrMeh f?+

Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: December 31, 1980 t

?

i

.. ~

=

i Y

1

?

_ATTACHMEF.T TO LICENSE AMENDMENTS j.

AMENDMENT NO. 59 TO FACILITY OPERATING LICENSE NO. DPR-39 AMENDMENT NO. 56 TO FACILITY OPERATING LICENSE NO. DPR-48 i

4 DOCKET NOS. 50-295 AND 50-304 Revise Appendix A as follows:

1 I

Remove Pages Insert Pages 61-61 70 70 i

1 f

I i

l i L ')

6 c

l i

+

._,,...a

_..,..a.

... c...

.,__.c..,_-

y

.10 - " I..Mii[il \\\\

l' [l [. I. 3.1 3 $

IIIlO hi U,li. l!! Ul. i.!.)

OP.i. ',l 1

!. W:'W UI' l

I p

. i.! IU'.

8 '

y p.h, y p n,i.g 5

i

.i.

ki, h.

.m

'4 c v n

..Y 7ty

,l.ti I I. 'r.. g

,:! I'dn.e. L..t:7y.

li. n t.

.f,l i

.I! k:.

3 I

4 3,:h M..o s.t 1.ti lI ill qi t'd p

r m r.a'

,, y

,I Hg e

r ak

.09

h. Id,a l l n

.. n

,X 401 WO./M'1 U.

}.1!d b.

h..!D h, I-: ! H.

> 'z

_.dt.Lm.1 m.

.i_a.:aut mb lit i

ip

. L. l' laut. o n!fy.

c

.a

_cifil o_.-.

i L.'o r ~Elio-fo

+; p;

- ppl

~

.a :,

I

+' +o lr.l.-+r +-

- w-n:

., r--

r '.

m u!

l

,+

n <. -

f.

r.;-

y qr. tog loa 'J. ~ l:xtx nclad; DuTnopMat eml i13 es p -- ] pr-t..

7 p:.

08 u abc vu y0400.rWD/m U...tn Un-L E 2_

u

- g u

g

a.,'.. :. n o

n

'lt:

ti

. t.

.s t.;.

u.

~

.07 h.t -.9 g.,

a-

.a 1

4

. _.x

.t;.

n A

. _' I, l'..

_...{..

q

.p.

{'.

u.!..' _. h,-

h;.;

. '.a. :

.06

.i! P.

L.

ih.b l.3

_. b.

i

_P...M._,glR..U. h

.i _:

-.7. l.l: 'F /

I d:

. _s

.a m

A o,7 7,.i p

05 I

i

.3.;.w 1. g

-L

.a. aa _u i '_..iu

/.

g.

n n

p t

a

.- n. :d; 1:,

g a :.

3 7;7 g.

i in a

u g.

e.

c:

re

.._:h.

2.4.a'..' p.'

Ut _P n

U H

}

.P a

.2 u

.au

./

2

. 2. ;_

0 d,.

7; L

a;

. c. :

a:.

..a

.2..a..n.

./.

.u.

c y

w m

. 0,1

- ; av. a.=

.t

.n_

a w

..n _.

h l_

n, I*

s -.

s.

3

.;., y p_ a;

.=: y..

a.:.:. := a l..

au a

g

.a s...u:

a; a

.03.

m J.

!6

_. ~

.- 7

.F

_..t u

,a o

..: m

...p

.. _y 1)-.

I..

.... - )-

c

~-

.C..

.m. i,

c. m

..;~-

u m

I Fout Rogion 3

e

-2.e U

...n

.02 2.:;

ru o

A scumtLias; -. -

r.x ;eoJed r.u rn u.r c

?.{.

7, -

p, 7: -

j._

tuo L-Asxnb1ier n.

1 o

u"p; 0q

_.t:

...a u.. a:..-

a,..a.

.u. 22

.u.

Ao. J. - nn.h 7

-.:n :n.

e r:....

4,

. h,.P:e

.01-

. t-n m.

t-e 2

E

r. ::e p:;

n 3:i.

g.

o t..

s.

m 1

m 3-

- y [-

i.;t

_j:. :.ul; y-

_; u M

g

,E; u :.a

.a a

.za au u;: :u u

Y u.,.u.

..t o

J

" ih'

'if 9.,l

.:. lh

% :id

'? L ih ?-

2 3

ti l

I

.n

..q.

2.

e tij:

.:f.;
i; t; a:.-

, t.;..4.

1-up '.n.

l.

Lp:-

..a.;.

u!

Wi

1;! u' a.*

l.

i 0

10 20 30 10 so Region Average Durnup (2000 PNn/ttTil)

i

-In accordance with the approved Westinghouse DNB Parametn The limits on the DND related model as presented in WCAP-8381, no collapses parameters assure that each of the parameters are expected throughout the fuel cycle of is maintained within the normal steady state operation.

The predicted minimum times for envelope of operation assumed in L: e transient clad flattening are:

and accident analyses.

The limits are consistent with the initial FSAR assumptions and have been Fuel Region EFPli analytically demonstrated adequate to maintain a minimum DNDR of 1.30 throughout each analyzed 1

19,500 transient.

2

> 30,000 l

3*

>30,000 The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> periodic surveillance of these para-meters thru instrument readout is sufficient for Zion Unit 1.

The predicted minimum times to ensure that the parameters are restored within to c.11 apse for. Unit 2 are:

their limits following load changes and other expected transient operation.

The 18 month Fuel Region EPPII periodic measurement of the RCS total flow rate is adequate to detect flow degradation and ensure 3

1 27,000 correlation of the flow indication channels with 2

3630,000 measured flow such that the indicated percent 3*

>30,000 flow will provide sufficient verification.of flow rate on a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> basis.

A design criterium requires that proposed re-load fuel region. exposure levals expected at A quadrant to averagc power tilt will be indicated the time of discharge not exceed the pre-by the excore detectors.

The excore current tilt

.dicted minimum collapse time.

Operation in is indicated by the arrangement of the current the exposure range in which clad collapse is recorders on the control board.

Four 2-pen i

postulated is not permitted under these recorders are provided, the pens are grouped so technical specifications.

that, in the absence of a tilt, the twe The predicted minimum time to collapse for all reload fuel regions is greater than i

30,000 effective full power hours.

i i

  • Except that the four (4) Region 3 assemblies to be used in the Extended Burnup Program for Zion Unit 1 have a predicted minimum time to collapse greater than 41000 EFPil.

4 5

)

i i-

, l

,