ML20004C755

Amend 70 to License DPR-46,allowing Facility Operation During Cycle 7 w/112 New P8x8R Fuel Assemblies Designed by Ge,Replacing Equivalent Number of 7x7 & 8x8 Irradiated Fuel Assemblies

ML20004C755
Person / Time
Site:	Cooper
Issue date:	05/22/1981
From:	Ippolito T Office of Nuclear Reactor Regulation
To:
Shared Package
ML20004C756	List: ML20004C755 ML20004C758 ML20004C759
References
NUDOCS 8106050174
Download: ML20004C755 (11)

Text

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s h3 RfCu ETT

'o,i UNITED STATES V

E NUCLEAR REGULATORY COMMISSION

J SUGVCiLLA.idi: R S.!i'IR F. !;Xi total' core ler.stn - Id fee:

L:

=

1. - A.: i.i t

p.... i t i o n.mo v e hottou of core G = 13.5 BJ/ t t for 7x7 fuel oundles

= 13.4 MI/ f t for dxd fuel bundles

.1 = 0.038 f or 7x7 f ael bundles

= 0.0 for dx8 fuel bunules If at any time during steady state operation it is de te rmined by nor-mal surveillance tna: the limiting exce eded value fo r L.lGK is beine action shall then be initiated to restore operation to witnin the presc ribed limits. Su rve illance and curresponding action shall continue until tne presc ribed lim-its are again being me t.

C.

'unimun Critical Power Ratio (!!CPR)

C.

11nimum Critical Power Ratio 0:CPR)

During steady state power opera-fiCPR snall be uetermined daily tion tne 11CPR for each type ot fuel during reactor power operation at rated power and flow snall not be a: > 25; rated thermoi power lower that. the lini:ing value shown and following any change in in Figure 3.11-2.

If, at any One power level or distribution that durind steady state operation. t is Jould cause operati0n with a determinec by normal surrei.f lanco limiting control rod pattern as tnat tqe limiting value for !!GPR described in the bases for Spec-is being exceeded, action snall ification 3.3.B.5.

tnen ce initiated within 1) minutes to restore operation to within tue presc ribed limits.

If the s t ead y state :iCFR is not re tu rned to within tne presc ribed limits within two (2) nours, the reactor shall be brougnt to tne Cold Shutdown condition with-in 3e nours.

durveillance and corre-sponding ac t ion shall continue until the presc ribed limits are again being me t.

For core flows other than rated the *:CPR snall be the operating limit at ra t eil floe times K,,

where K, 18 au shown in Figure l

3.11-3.'

Amendment No. 70

-212-

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Applicable to MG set plants only.

3.11 Bases:

(Cunt'd)

The limiting transient shich determines the required titeady state MCPh 11 nit and thus yielos tne largent SCPR 18 discussed in Referuns.e 5.

Unen aaded to tne safety limit :tCPR of 1.07 the deturninistic tCPT.'s are obtained.

The requircd mini.aun (,perating limit 1 cpl;'s are determined by nethocs ;iven in References d and 9.

analysis uf abnormal operational tranalents an ir.ttial fuel Prior to tne oundle :ICPR was de termined. This paraneter is based on tile oundle flow flow distrioution.udel as calculated by a CE multi-enannel steg state c esc rioed in Section J. of ::EDO-240ll and on core parameters snown in Table 5-2 of Reference J.

Tne e.aluation of a given transient begins witu the system initial para-the Gd c g meters snown in Table 5-2 of Reference ' that are input to syaamic behavig transient computer progran described in !!ZDO-1sdO2 and ::DO-24154 Tne outputs of tne program along witn the initial :tcPK l

form tne input for further analyses of tne thermally limiting' hundle with the singiegannel transient thermal hydraulic SCAT code described in D E-2056o The principal result of tnis evaluation is the reduction in

"CPR caused by the transient.

O.

~tCPR Limits for Core Flows Other than Rated other than The purpase of tne K, f actor is to define operating limits at rated flow condittuns. At less than 100; flow, the required :tCPR is tne preduct of the operating limit :!CPR and the K, factor.

Specifically, the f actor provides the required thermal nargin to protect agatus t a flow u

increase transient.

Tne most limiting transient initiated f rom less than rate.1 flow conditions is the recirculation pump speed up caused oy a motor-generator speed control failure.

f actors assure For operation in tne automatic flow control mode, the Kviolatedshoukd the most limiting the operating limit MCPC will not be tnat transient occur at less than rated flow.

In the manual flou centrol mode, tne K, factors assure that the Safety Linit MCPR will not ce vio-la ted for the same postulated transient event.

Amendm nt No. 70

-214c-

3.11 bases:

(Cont'd)

Tne K, f actor curves shown in Figure 3.11-3 were developeo generically -

l wn icn' are applicable to all BWR/2, Bh./3, ana InJR/-. reactor:..

The F.

actors were de rived using the flow control line correspondin;; to raked tner,al power at rated core flow.

For tne manual flow control code, tne K, factors were calculated suen tne naximum ficw state (as linited oy the pump scoop tube set tnat at flow control putut) and tne correspunding core power (along the rated Itne), the limiting bundle's relative power was adjusted until the !!CPR was slid tly a'ouve the Safety Limit.

1* sing this relative bundle power, h

tne EPR's were calculated at dif ferent points along the rated flow control line corresponding to dif ferent core flows. The ratio of the MCPk calculated at a given point of core flow, divided by the operating limit MCPR determinec the K.

f For operstion in the automatic flow control mode, tha same procedure was em;.loyed except the initial power distribution was established such that t:ie IICPR was equal to the operating linit :1CPR at rated power and flow.

Tae K, f actors shown in Figure 3.11-3, are conservative for Cooper opera-l the operating limit MCPR's are greater than the original tion oecause 1.20 opereting limit MCPR used for the generic derivation of E.

Re f e rences f o r Bases 3.11. B, 3.11.C, 3.11.D

" Cooper Nuclear Station Channel Inspection and Safety Analyses with 1.

Sypass iloles Plugged," I;ED0-21072, October 1975.

2.

Licensing Topical Report, General Electric Boiling Water heactor, Generic Reload Feel Application, (N ED C-240ll-P), (most current approved submittal).

R. B. Linford, Analytical liethods of Plant Transient Evaluations for 3.

tne CE B'.lR, February 1973 (NEDO-10302).

General Electric Conpany Analytical Model for Loss-of-Coolant Analy-sis in Accordance with 10 CFR 50, Appendix K, 30 0-20566, dated 4

l January 1976.

" Supplemental Reload Licensing Submittal for Cooper Nuclear Station 5.

Unit 1," (mos t current approved submittal).

April IS,1978 letter from J. :1. Pilant (NPPD) to G. 2. Lear (NRC).

o.

f

!odel for 7.

" Qualification of the One-Dimensicnal Core Transient Boilin; Water Reactors," NED0-24154,. Volumes 1, 2 and 3, October 197s.

t Le t te r, R. 11. Buckhole (GC) to P. S. Check (NRC), "0DYN Adjustment 3.

1931.

etnods for Determination of Operating Limits," January 19, 9.

Le t ter (with attachment) R.11. Buckhol:: (GE) to P. S. Check (NKC),

for Information on ODYN Computer Model,"

" Response to NRC Request Septe.b r 5, 1980.

Amendment No. 70

.