ML20116F280

Cycle 4 Core Operating Limits Rept

ML20116F280
Person / Time
Site:	Braidwood
Issue date:	11/05/1992
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20116F277	List: ML20116F274 ML20116F280
References
NUDOCS 9211100255
Download: ML20116F280 (5)

Text

.

ATTACHMEN1 B Bw1C4 Core Operating Limits Report (COLR) 9211100255 921105 PDR ADOCK~05000456 P

PDR

.ZNLD/2278/7-

Braidwood Unit 1 Cycle 4

-Operating Limit Report - fxy-Portion

+-

This_ Radial Peaking-Factor Limit Report-is provided in accordance with Paragraph 6.9;1.9 of the Braldwood Unit l' Nuclear Plant Technical Specifications.

The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 4 shall be:

a.

For the lower core region from greater than or equal-to 0% to less tt.an or equal to 50%:

1.

For all core planes containing bank "D" control rods:

RTP f

1 2.1384 for Bu 1 8000 MHD/MTU xy 1 2.1384 for Bu > 8000 MHD/MTU 2.

For all unrodded core planes:

RTP f

1 1.9114, for Bu 1 8000 MHD/MTU xy 1 1.6922, for Bu > 8000 MHD/MTU b.

For the upper core region from greater than 50%.to less than or equal to 1001:

1.

For all planes containing bank "D" control rods:

F 1 2.1384, for BU 1 8000 MHD/MTU l

1 2.1384, for Bu > 8000 MHD/MTU-t 2.

For all unrodded core planes:

RTP l

F 1 1.8310, for Bu 1 8000 MHD/MTU xy j

1 1.8544, ror Bu > 8000-MHD/MTU l

These Fxy(z) limits were used to confirm that the heat flux hot channel factor FQ(z) will be limited to the Technical Specification values oft Fg(z)1(2JD] [K(z)]

for P

> 0.5 and, P

Fg(z)1[5.001 [K(z)]

for P 1 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of Control Banks C and D during operation, including the accompanying variations in the axial xenon and power distributions as described in the " Power Distribution Control and Load Following Procedures",

HCAP-8403, September, 1974.

Therefore, these F limits provide assurance thattheinitialconditions-assumedintheLOCA$nalysis-aremet,alongwith

-the ECCS_ acceptance criteria of-10 CFR 50.46.

Se Figures 1 and 2 for plots of IF.Pp,j] vs. Axial Core Height.

l-DRL:me.

L ZMJC:66:5 l

^

Figure 21 Braidwood Unit 1 Cycle 4 Fxy Limit ' Analysis - Burnup s 8000 mwd /MTU 2.60 l

i (6.0, 2.5C ).

2.50 x

i

(? 2.0,. 2.31) x

^

2.40 w

g'.r

-x,,

N

=,

2.30 5

4 2:20 ;

l-

}

- 2.10 l l

l o.

2.00:

e 1.90 l

l 11.80 !

l

. o.-

E 1'70 :

X Ei

- 1.60 :

m s

1.50 5 l

l E.

j x

l 1.40 :

E l

CAOC Analysis Points x

.1.30 :

^

1.20 {

LOCA UmlHng Envelope f

x j,10 l

-- Boffom Surveillance Limit l

~

1.00 ;

.[

-- Top Surveillance Limit l

0.90''''l'''''''''''''''''''''''''''''''''''''''''

- 0 1.

2:

.3.

4 5

6 7

'8

- 9 10.

11 12 BOTTOM TOP Core Height (ff)

f. -

4, 9

s 3

m E

~N,.

e

,__________._____.______._..__.___._m

. L.

.m

Figure 2 Braidwood Unit 1 Cycle 4 Fxy Limit Analysis - Burnup > 8000 mwd /MTU 2'60 j

.l-(6.0, 2.50) l 2.50

^

(' 2.0, 2.31) 2.40 x

w

,x g

7x 2.30 :

l x

x E

x b

2.20 ;

l x x 2.10 !

{

{

fx o_

2.00 :

o 1.90 l l

'1.80 !

1.70 !

l l

x 1.60 i l

l m.s l

1.50 5 l

• 1 E

1.40 :

l l

CAOC Analysts Points E

x 1.30 :

1 20 g LOCA Limiting Envelope l

1.10 5 l

-- Bottom SurvelNnce Limit l

1.00 l*

l

-- Top Surveillance Limit l

E'

E

0. 9 0 O

1

.2 3

4 5

6 7

8 9

10 11 12 BOTTOM TOP-Core Height-(ff)

,f

__- _ ~ _..

4 ATTACHMENT C References 1.)

Westinghouse WCAP-9272 P-A, dated October 1985;" Westinghouse Reload Safety Evaluation Methodology", (originally issued March 1978).

2.)

CE^, submittal, J.A. Sllady to T.E. Murley dated July 13,1990; entitled

' Commonwealth Edison Com 3any Topical re > ort on Benchmark of PWR Nuclear-Design Methods Using The P1oenix P and A9C Computer Codes, NRC Docket-Nos. 50-295/304,50-454/455, and 50-456/457".

3.)

NRC SER on CECO's Neutronics Topical (Ref.2) dated March 11,'1991.

4.)

CECO submittal, F.G. Lentine to H.R. Denton dated July 27,1983; entitled " Zion -

Stations Units 1 and 2, Byron Station Units 1 and 2, Braldwood Station Units 1 and 2, Commonwealth Edison compar'y Topical, Report on Benchmark of PWR-Nuclear Design Methods," NRC Docket Nos. 50-295/304,50-454/455, and 50-45G/457".

S.)

NRC SER on CECO's Neutronics Topical (Ref. 5) dated Deember 13,1983.

6.)

NRC Letter from S.P. Sands to T.E. Kovach, " Amendment No. 23 - Use of VANTAGE 5 Fuel", dated April 19,1990.

7.)

CECO submittal, S.C. Hunsader to T.E. Murley "Braldwood Stations Unit 1 and 2 Application to Facility Operating License NPF-72 and NPF-77 dated October 1_4, 1989.

~

8.)

Letter from T. Simpkin (CECO) to Dr. T. Murley (NRC), " Boron Dilution Protection

- System License Amendment Request," dated July 28,1992.

9.)

Letter from J.B. Hickman (NRC) to T.J. Kovach (CECO), " Issuance of

- Amendments, Braidwood Technical Specification Amendment 40 and Byron Technical Specification Amendment 51, to reflect changes to the current Boron Dilution Analyses, dated October 5,1992.

o 4

I a

_ZNLD/2278/8

.