ML19329B701
| ML19329B701 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/14/1976 |
| From: | Chris Miller Office of Nuclear Reactor Regulation |
| To: | Deyoung R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002060711 | |
| Download: ML19329B701 (4) | |
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14 1976 NRR reading files -
EICSB reading files
}ilDMMI FOR:
R. C. DeYoung, Assistant Director Light Water Reactor, EPN FPO!:
C. F. Miller, Section Leader D*
D Electrical, Instrtrentation and Control Systems Dranch, T6S
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T. A. Ippolito, Chief Electrical, Instrtrentation and V
U Control Systems " ranch, DSS SUAECr:
SUPPIDC1TAL QUESTIQ';S FOR OFF;SC PCbER SYSTE'S Plant Na:ne:
Davis rasse - Unit 1 IYcket No. :
50-346 Licensing Star.o:
CL Filostene *o.:
12-22 Pestensibic Branch:
EICSS and Project Smar.or:
L. Engle P.cqtested Cerrietion Date:
N/A P.cvicu Statt:s:
Awaiting Inicratien P12ase transmit the attached information request to tha a:mlicant.
This infonnation is required for cc:.pleticn of our review.
These cencems are being unifornly applied to all CL's presently inder raview. ' e reqtrst that the arplicant's response te s'f ritted to us so that our evaluation cay be incorporated in the st:ppic:xnt to the safety evaluation report.
CS C. F.." iller, Sectien Le,: der Electrical, Instr. rent ition and Centrol Syste*.s 3ranc:1, TSS cc:
- 9. P. Hanauer, TA T. A. Ippolito, EICSB R. E. Heineran, TES
'i. G. "cDcnald, "IFC R. S. Doyd. DPM C. F..Viller, EIGD P.
L. Tehsco, PS J. C. Glynn
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@D ENCLO5URE
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Supolerental Guestiotu for Of f-si e Power Syste:.3 on Davis l' esse 1
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7 100 Stct3 Based on;the grid syst.n sta'.:llity 2n21510 L'3 2
1.
the nemiasi vales and the mania:: and. cinix.: Sytcod val'.:a c7 vol;;c;2 and frequ2ncy of the oilsite pwer sca. a tItst nssura sat;ishetory o,carability of all clect.rical equi.7mant
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of the station during all = odes o? plant opsratien.
ila requir that a review be ye:So=ed on the design. =ad..
2.
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installa:icn oi tha'statioa electrical systru to provMa..:
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' assuranca that all oc.ui :ent.3111.fc.ction c ntinususi-r at tha tinai=:2 ar.d sini== altetrical.chais:teris:ic:s duri.n3 -
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all codes of "lant o.esntien idan:ified in the first c.uestion. -
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a Provida a libt. identifying each cireait n=d/or c1 W al
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s device that does not satis 9 th= above. The ::sults of such
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a revi 9 c'uuld also specifically include the follow.in3:}.
A.
The nominal and tha :sxtr.:2/=1nimis values of volt:3a ct ths s22. ty := lated busas for offsite power syste:
2 s
voltaga sp; mads dafined in firs: qu.: tion.
The capability of all safety r:1sted ioads, " con:. a1 s=2
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B.
inst: =nnts ion circuits to parfor= their safety E=::".lon:.
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in. der tha offsita power system voltsga spiends d'afined in. -
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first,qu.etion.
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. C.
Spacific design f:20.:r.e5 incorpor: tad in the pl:nt eld =r."T.,
. system, i.e., t:c sformer en losi/ offload t=p changers, y-1:aga Tc3:12:o :, etc., to assure that ceceptabic. voltsga.
levals are nainte.ined at the safa 7 relat:d buses for all I
3 of p10;'.C c,~'r&O on.
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3.
Provide a descriction of the procedures used to maintain
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a grid configuration and operation in a condition which alway, satisfias the limits identified in Questi n 1.
Also, provida - '
the following; based on the grid systen stability analyses results:
A.'
Describe how the operator is cada aware of the operation of ths grid in regard to the limits identified in~ Question 1.-
B.
The effects of loss of the nuclear g:narating unit en off
'sita power scure.s while operating at the li=its identified 7
in Question 1.
C.
The efficts of loss of ths largest grid load on offsite
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powar sourca whila oparating at the IN:s identified in A
Quastion 1.
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D.
Identify any restrictions placed on the grid operation.
that reg' ires spe:1fi: spinning reserve (either real or u
reactive power) to be availabla within a dedicated distanca
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,from the nuc12ar stati:n in order to maintain the of site.
pcuer sour =a uithin the limits identifed in q=estion 1 s
during grid dist=rbances.
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4.
Describe the specific design provisions included in the plant
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Class IE power systems, to assure continued operability of 7
safety equipr::ent, shculd the offsite power system charchyeristic's,,,
exceed the limits identified in first questica due to abnormai.
systen co-Ai.-lons. The response should also specifically include
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the fol'. wins:
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A.
The design basis and criteria for identifying the offsite Power syste:: degradation and isolation of the plant electrical pc or syste=s from the offsite power systen.
B.
The design bases and criteria of systems used by the control room operator to identify the coniition.of 211 safety relatedbuses and other safety related equi;=ent during an
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offsita power system degradation.
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C.
A list identifying those'i:onitors used by the control room
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operator in- (3) above. This shou 18 also specifically include meters, indicator types, alaru setpoints, and
.s recordars.
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5.
Provida a desciiption of the method,4hich will be employed,-
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to ver'ify the adequacy of the Plant design befose reactor operation.
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