ML19340A141

to Oconee 2,Cycle 2 Reload Rept.

ML19340A141
Person / Time
Site:	Oconee
Issue date:	06/10/1976
From:	BABCOCK & WILCOX CO.
To:
Shared Package
ML19340A139	List: ML19340A138 ML19340A141
References
BAW-1425, NUDOCS 8001100606
Download: ML19340A141 (6)

Text

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O REVISION 2 TO BAW-1425 OCONEE 2, CYCLE 2 RELOAD REPORT 8001100 [O6

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• 4

. C' . . ..

Revision (6/10/76):

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' :u;ed in -the analysis are 1.087 and' 3.10 ' inches, respectively. . He results of

.l'2 Jthe 'two'ef fects' are -5.93% and '-3.47% change

• in :the minimum hot channel DNBR .

~

[.

t F

tnd peaking margi n,. respectively. The changes in .these margins are sumarized in Table 6-1, which includes comparisons of other pertinet cycle 1 and 2 data.

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We DNBR' analysis has .been based on a core configuration consisting of 177

. Mark B fue~ assemblies. We incorporation 'of - two Mark -C demonstration fuel l  ;

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'a:semblics in. batch 4 in(place: of two Mark 'B assemblies, results in 'an increase

~ in .the overall marginf to DNB, as ' discussed in reference 2.

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Change from unic. ified values. These are actually an improvement over cycle 1' densified conditions.

7 6-3 Babcock &Wilcox -

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f Table 6-1. ' Cycle 1 and 2 Maximum Design Conditions Cycle 1 1 Cycle 2 2568 {

2568 Design-power level, MWt 2200 2200 System pressure,. psia 107.6 100.0 Reactor coolant flow, % design flow Vessel' inlet coolant temperature, 554.0 555.9

• 100% power, F-Vessel outlet coolant temperature, 603.8 602.2

-100% power, F

_Ref design radial-local power - 1.78 1.78 peaking factor- 1.5 cosine

' 1.5 cosine

! Ref. design axial flux shape 141.1 (dens.)

144 (undens.)

' Active fuel length, in.

~

-Avg heat flux, 100% power, 171,470 174,995 2

Btu /h-ft Max heat flux,100% power, 457,825 467,236

- iBtu/h-ft 2 (for DNBR calc) B&W-2 W-3 CHF correlation 1.98 1.55

. Minimum DNBR (max design ~ conditions, (114% power) (112% power)

( no densif penalties)

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Hot channel factors

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1.011 1.011

- Enthalpy rise 1.014 1.014 ,

Heat flux 0.98- 0.98 Flow area

-Densification effects -5.93

-6.08 4 2

~ Change'inLDNBR margin, % -2.82 4 -3.47 Change in power peaking margin, %

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?I Ba'bcock & \Vilcox

- - 6-4^

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Revis' ion-2'(6/10/76)

'8.. PROP 0 SED MODIFICATIONS T0' TECHNICAL SPECIFICATIONS

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ne' Technical' Specifications have been revised, for cycle 2 operation. Ch'anges

. were the -results of the following:

1. Using the_ B&W CHF- correlation rather - than W-3,- as discussed in section 6.1.

2. Using a 95/95 confidence level rather than 99/95, as discussed in

'section 6.1. .

3. Using 107.6%' of ' design flow rather than 100%, as discussed in section 6.1.

4. Usir.g tns Final Acceptance Criteria LOCA Analysis for restricting peaks during operation, as discussed ,in section 7.14.

- 5. Revising' the' assumptions on which the flux flow RPS setpoint is based.

This setpoint now accounts- for signal noise on the basis of data accumulated from operating B&W reactors.

6. An analysis incorporating the effecti, of fuel rod bow on core parameters. .

7. The_ penalty on core coolant flow due to an assumed open vent valve has been eliminated based on a vent valve surveillance program performed 2 during each refueling shutdown.

Based on the Technical-Specifications derived from the analyses presented '

in this report, the Final Acceptance Criteria ECCS limits will not be exceeded, nor will the thermal ' design criteria be violated. Figures 8-1 through 8-14 illustrate revisions to' previous Technical Specification safety limits.

8 Babcock & Wilcox s

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( , , ,

, , 2600

, 2400 ,

' Acceptable {

Operation ,

w to C2.

. 2200 ,

E a

0-3 2000 t; . Unacceptable o

Operat. ion .

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-l 1800 /

1600 620 040 660 560 580 600 ,

Reactor Outlet Temperature F e

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. UNIT 2. CYCL.E 2 CORE PROTECT 10N SAFETY 1.l!AIT

• Figure 8-1 9-

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W

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2600-l s .2400 Acceptable  % sb

"' Operation D.N J

g 2200 -

- m E

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. 2000 /

0 Unacceptable Operation

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1800 .f , e 1600 560 580 600 . 620 640 660

. Reactor Outlet Temperature F REACIOR COOLANT FLOW .

-CURYE LBS/HR POWER . PUldPS OPERATING (TYPE OF LIMIT) 1 141.3 x 106 (100%) 112% Four Pumps (DNBR Limit)

.2

. 105.6 x 106 (74.7%) 86% Three Pumps (DNBR Limit) 3 3 , 69.3 x'106 (49.0%) 58% One Pump in Each loop

, -(Quality Limit)

UNIT 2 CYCLE 2

- CORE PROTECTION SAFETY LIMITS Figure 8-3 9 9 4 .

e e e

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