ML20037B043
| ML20037B043 | |
| Person / Time | |
|---|---|
| Site: | Dresden |
| Issue date: | 01/26/1976 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Bolger R COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8009030748 | |
| Download: ML20037B043 (4) | |
Text
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JAN 2 6 '976 DISTRI E'JTIO:;
Docket NRC PDR Local FDR ORB "2 Reading 1; :.e t
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KRGoller TJCarter RMDiggs PK0'Connor fs n.It!- : il so: " n '~ nuv OELD ATi.'! :
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L. Sol,ter OISE (3)
Assistant l' ice President ESEXEfIXXI)
Post ('ffice Fox 767 ACRS (16)
Chicac.o, Illinois 60693 OPA (Clare Miles)
TBAbernathy Gentlemen:
JRBuchanan DEisenhut e are reviet:im your.iam:ary 7,1976 subnittal chich rnvi.:e9.<ilitionn1 in.or.tirn reinted to the Dresden 1 r,en tix r. i.CCF n l:, s u
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Original signcd by Dennis L Z.cmann Dennis L. ~'i cr.n
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Dicratin;: 'tcactorr iranch "2 bivision of Oeratin; ".creters
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Dresden-1 Request fer Inforestion 1.
Your response to question 2 is not sufficiently complete.
Provide the following information:
a.
Detailed drawines of the fuel assembly used during cycle 9.
b.
Detailed drawings of the fuel assembly to be used in cycle 10.
c.
All details of the ' water" rod and its contents for the cycle 9 and cycle 10 assemblies.
d.
Explain what is teant by "no credit taken for radiative heat transfer to the water red'.
Describe how the water rod was handled in the radie.tien matrix.
c.
Confirm that the quenching (rewetting) calculation <cas not
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performed for the water red.
f.
Explain how possible effects of the water red on strey coolino coefficients. tere taken into account.
Did the experimental data (APED 4927 & APED-492E) use a heater bundle with such a wcter rod?
2.
Your response to qutsticn 2 Es incomplete.
Provide the infor:aation listed tolcr.
ini: inforn:: tion rust be orc.'idad and reviewed before tne staff can r. ale a finding that tne model used for Dresden 1 is in compliance with the requircrents of Appendix K of 10 CFR 50.
a.
Provi'Je block diagrr of the inforratien '1v.: into an
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. b.
Completely describe any hand calculations performed tu cdjust er prepare input to any ccde.
c.
Provide a listing of all coding perferr.ed to modify ti.e codes to fit Dresden-l.
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d.
Provide a listing of a typical run.
This test include all areas where the Dresden-i code madel is different from the GE l'JP-Ch'R-ECCS packege. The listing of those portions of the Dresden-1 rodel that are unchen;cd frcr the stcnd:rd ECCS package may be included ty reference.
e.
Provide a complete priatout of a sample run.
Also, separately provide details and samples of any hand calculations.
3.
.Your response to Question 5 was not adequate-Provide the following inforinition :
l a.
Provide details of the " studies performed at the recirculaticn inlet (that) confirm that this approach (frictionless bic:dcun l
l flow) yields more severe results than ccses involving steam binding in the broken icop's secondary steam generatcr."
b.
For smaller breaks, cxplain why steam binding (if it occurs) would r.ci. cause some delay in depresst.rix tion, delayir.g sprcy initiation, and causing the sral'.cr brer 4 to yield higher peak cladding temperatures.
The rcsuits you presented for the Dresden break spectrum (PCT vs size) are very uniform, therefore, slight effects would change the liniting break.
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4.
Provide up-to-date PGID's and electrical scheratics of
).e Dresden 1 plant as it is today (before activation of the
!!PCI nodification) showing piping, valves, pov.er rourers, instrumentation, and controls for the Emergency Condenser ('IC) system, core spray system, and auxiliary power systen.
These PSID's and schem; tics must have sufficient detail to permit us to ecertain that no single ncchanical, power scurce, or instrumentation failure will causc ledundant trains to becoue ineperable.
For example, are valves powered by both trains A and B required Oc operate each half of the EC system, or are the two halves separated so + hat on3y divlsion A pm:cred valves are nceded to cperater onc half of the EC ; t c.a nni divishn P valves to opercte the other br.lf.
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