ML20077E660

Forwards Beaver Valley Power Station Unit 1 Cycle 9 Core Operating Limits Rept. Mechanical Design of New Region 11 Fuel Assemblies Listed

ML20077E660
Person / Time
Site:	Beaver Valley
Issue date:	05/30/1991
From:	Sieber J DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20077E664	List: ML20077E660 ML20077E666
References
NUDOCS 9106110150
Download: ML20077E660 (2)

Text

,

N Dtquesne Lkyt Company = ;;-

1, u,~ u,

1 I ed

4 May 30, 1991 O.

S.

Nuclear Regulatory Commission Attnt Document Control Desk Washington, DC 20555 l

Subjects lleaver Valloy Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Cycle 9 Hoload and Coro oporating Limits Report Beaver Valley Power

station, Unit No.

I completed the eighth cycle of operation on April 12,

1991, with a

burnup of 14,640 MWD /MTU.

This letter describes the Cycle 9 reload design, documents our review in accordance with 10 CFR 50.59, provides our determination that no technical specification changes or unreviewed sa!ety questions are

involved, and includes a

copy of the Core Operating Limits Report (COLR) in accordance with Technical Specification 6.9.1.14.

The Cycle 9

core coniiguration is arranged in a low leakage loading pattern and involves replacing sixteen (16) Region 8 and fifty-six (56)

Region 9 fuel assemblles with twenty (20) Region 11A fuel assemblies enriched to 3.6 w/o and fifty-two (52) Region llB fuel assemblies enriched to 4.0 w/o.

A Region 1 fuel accombly discharged at the end of Cycle I will be reinserted to replace the conter fuel assembly.

The mechanical design of the new Region 11 fuel assemblies is the same as the Region 10 fuel assemblies except for the following features:

l A

modified fuel assembly bottom nozzle whid includes a

reinforcing skirt to enhance reliability during postulated 3dverse handling conditionn while refueling.

The Integral Fuel Burnablo Absorber (IFBA) pollots contein enriched Boron which is chemically the same (except for a small reduction in density) as natural boron and provides flexibility in controlling core peaking factors.

The fuel rod bottom end plug has an increaseu radiuu in the transition between the chamfer and the end of the plug.

These modifications meet all fuel assembly / rod design critoria and will not adveruoly affect the coro safety considerations.

Fuel rod design ovaluations for the Cycle 9 fuel were performed using NRC approved methodology to demonstrate that all of the fuel rod design bases are satisfied.

Duquesne Light Company has performed a detailed review of the Cycle 9

reload core design including a

review of the core characteristics to determine those parameters affecting the postulated accidents described in the UFSAR.

The consequences of 91061101'l0 ? w,O'yg,a

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Neaver Valley Power Station, Unit flo. 1

• 'g Duchet flo. 50-334, Licenne flo. DPit-66 Cycle 9 Reload and Core Operating Limits Report Page ?

thone incidento dencribed in the U l'S Al-abich cou l:1 pot e"'t i al l y be attected by the reload core char Tc*' rf st ien were eval'ut(d in accordance with the t1RC approved 2t hc dol orly

,leocrited in Evaliati:n :40thodology."

WCAl'-9272-P-A "Wentinghoune l<e l oad

' r The ettecto of the reload on th.

'a' n

main and pontulated incidento analyzed in the Ul'SA"

,, e r e act ar, mod r. 4 d w i '. n. o the connervatico of the annunptions u n.;n ir, t!.e irrent n a l v.-

d

'gn

banin, or it wan demonst rated J reucf 3v. ut: on t ras t o-i, md parametern would not change the conclusions

.I ch"

lSAP.

11 0 technical specitication changes art iequired re mlt of i

the Cycle 9 reload design.

The IJRC approved dropped rod

.odology

[WCAP-102"B-A denign (non-proprietary),

June 1903) was used tur the Cycle evaluation and contirmed that the peaking tactorn did

,t e>:cr,d the

<,atety analynen limito.

The reload core denign will be veri t lerl by performing the utandard Wentincjhouse reload core phynien ntattup tents.

'I h e results of the following startup tents will be nubmitted in accordance with Technical Specification 6.9.1.3:

1.

Control rod drive tent: and rod drop time measurement.n.

2.

Critical boron concentration measurement n.

3.

Control rod bank worth meanurenento.

4, liodorator temperature coetticient meauurementn.

'i.

Startup power distribution measurements uning the incore flux mappinq nyntem.

The COLR (attached) han been updated for Cycle 9 to include new f

limits for unrodded core planen and l'iquren 3 and 4 have behe,n( RT I')

x revised to incorporate a

correction to the top of 1; ( z ) core 1imit.

The Beaver Valley Onnite Safety Committte (OSC) and the Duquenne Light Company oftuite Review Committee (ORC) have revievied the Cycle 9

Reload Safety Evaluation and Core Operating Linitn Report and determined that thin reload denign will not adversely attect the cafety of the plant and doen not involve an unreviewed nafety quention.

Sincerely, l

/

b a, -

J. B. Sieber (Vice Prenident fluclear Group cc:

'< r.

J.

Heall, Sr. Renident inspector Mr.

T.

T.

Martin, l'RC Rerjion 1 Aam i n i st rat or Mr.

A.

W.

DeAgazio, Project Manager Mr.

M.

L.

Bowling ( Vl' PCO )

. _.