ML20090F967

Discusses Capability of Proposed Yellow Creek Nuclear Plant to Withstand Small LOCA.Mid-Aug Meeting Proposed to Resolve Preliminary Concerns Re Transient Analysis.Response Requested by 770805

ML20090F967
Person / Time
Site:	Crane, Yellow Creek
Issue date:	07/22/1977
From:	Patterson D TENNESSEE VALLEY AUTHORITY
To:	Lumpkin R ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY
References
TASK-06, TASK-07, TASK-11, TASK-6, TASK-7, TASK-GB B&W-0542, B&W-542, NUDOCS 8307080705
Download: ML20090F967 (5)

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,._ - la TENNESSEE VALLEY A'UTH O RITY MW DEDT 8'fd r gnoxvitte. Tcuscsser. 379o2 W1CC32.6, 400 Commerce Avenue

,3/,9/f,? N. A. g;a;g July 22,1977 77072.7 DO@

gg Combustion Incineerinc, Incorporated 10C0 Prospect Hill Road f

Windsor, Connecticut 06095 Attention:

Mr. R. L. Lu=pkin, Jr., 9460-4CO Gentlemen:

,h PROPOSED YELLOW CREEK NUCLEAR PLAUT KUCLEAR STEAll SUPPLY SYSTEMS CCHTRACT 75K60-848bo-2 IrrrER no. C-655 VERY SMALL EREAK IDCA - N802-NC

References:

1.

CE letter TD-CE-161, Septe=her 18, 1975, "s--1' Break IOCA" 2.

CE letter TD-CE-660, April 22,1977, " Evaluation of CVCS' Boration Capabilities" (ME3 770426 501)

We have been looking at the capability of the Proposei Yellev Creek Nuclear Plant (YCNP) to withstan?. a gry small IOCA (equivalent to a break less than er equal to 0.1 ft. ).

We consider the event more probable than the classic large IOCA because there are several situations, including s=all pipe tracks or failures and seal fsilures,by which it can occur; sr aller pipes (7/32 to 4-inch diameter) are also = ore susceptible to physical damage and vibration than are Ic.rger ones in

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general.

(AUS classifies these events as Condition III. )

We' consider the probability high enough, all t ?.d, to requir that the consequences be acceptable from the safety vic,, int with NRC conservative rule's.

(We are also concerned Srith steam genere.6-tube ruptures, which are similar in many respects, but, uc. will pursue ' ;se separately.)

In pursuit of our evaluation of very small LOCA's, we have looked through I

references, primari3y TD-CE-161, and developed questions that need ansvers to assure our understanding of the transients. Some of these are 1:

unt:nswered items from previous correspondence and some are new. We feel j;

confident that the answers are available to you as a result of your

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development of the RCS and ECCS desiCn.

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Combustion Engineering, Incorporated July 22,1977 Assu=ptions We would like to know more about the assumptions on which you based your ana.\\ysis:

1.

What did you assume for the evolution, both guantity cnd speed, of noncondensibles?

2.

Is the high-pressure safety injection (HPSI) throttling needed, and if so, how is this performed? (Note that CESSAR Section 6.3 and Section 8.2.3 of the SIS System Description seem to conflict with your letter TD-CE-660 on this point.)

3 How do.you account for the operation of the che:ical end volume control system (CVCS) pumps, auxilia y spray, and letdoun during these transient ?

'. Do you assume any additional losses due to increased l'eakage from 4

reactor coolant pu p seals?

Transient Analysis In regard to the transient analyces that you gave us:

5 What is the mechanism and time fra=e of heat re= oval during the transition from natural circulation to boiling?

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What are the hot and cold leg te=peratures during this transition?

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7.

What are the eff" ts if the reactor coolant pu=ps continue to operate

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phases of the transient?

8.

What happens if the operator should isolate the break during the i

transition from natural circulation to boiling, or during the boiling mode of heat transfer?

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What infc.mation (e.g., temperature, pressure, or level) is

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available to the v '.!. operator to keep him informed of what ir j

occurrin6 and what actions he should or chould not take durin; the transient?

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3 Co= bust.icn Engineering, Incorporated July 22,1977 Recovery In regard to recovery from the transient:

Please explain the mechanism and the time frame involved in going 10.

from the boiling mode to cold shutdown.

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If this is done in part by restoring natural circulation, 11.

What is the heat removal mechanism during the transition lla.

from boiling to natural circulation?

When is this transition to occur and when vould it be lib.

complete?

How is refilling of the steam generator tubes to be lle.

acco=plished?

If, on the other hand,the shutdown cooling system (SCS) is to be 12.

initiated directly from the boiling mode, What is the earliest time frame that this can be done?

12a.

s 12b. What instrumentation is available to operating personnel to know that they have adequate we.ter in the reactor coolant system to protect the SCS pumps?

Assuming that the refueling water tank (EUT) is e ventually du= ped 13 via the leak, and pessibly via the containment spray system (CSS),

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i' 13a. How is sCS established with water in sump instead of the E'.c?

i How is the high-pressure safety injection (HPSI) run after the 13b.

recirculation actuation signal (RAS) isolates miniflow?

13c. Mcv is throttling acecmplished to maintain the reactor coolant system sufficiently full uhile the system is' being placed on and operated on SCS?

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14. What steps =ust be taken to prevent du... ping ie.e safety injection tank (SIT) durin6 the trcnsition to SCS?

How long frem the beginning of the transient is it before the SCS 15 i

can be initiated in the vorst case (remember the limits of l

emert;cncy feeducter storage capacity)?

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h Cc::bustion Engineering, Incorporated July 22, 1977 Gencrcl Other Beneral questions that we have regarding the very small IOCA event concern varicus modes of operator action and mechanical failures:

16. Whd tre your recor= ended or prohibited operator actions during and following this event? Please send us, if available, procedures that you would have as typical for this event.

For a few scoping cases, please give us the time to actuation of the 17.

CSS.

Give us a time to the Itis for those cases with two trains of CSS 19.

c.nd one or two tre. ins of HPSI running.

please give us any ce= ents you have regarding the ability of the 19.

sten = generator tubes to withstand possible mechanical stresses associated with the trcnsition frc= natural circulation to boiling and back again.

De=enstrate (reference our letter C-578) that na,tural circulation i

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can be reestablished if required to recover frcm the transic:.t.

We have these preli=inary concerns regarding this transient analysis.

We request that our engineers and yours meet on this subject to discuss He would like to arrange it in more depth and assure timely resolution.

a meeting in =id-August, if this is convenient with you so that you and i

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ve can come to a sufficient understanding of our mutual concerns before a great deal of effort is further expended. The above concerns would i

serve as the agenda for the meeting. If you need clarification regarding our concerns, please call us.

Please notify us by August 5,1977, regarding the date and desired place for the meeting, i

Very truly yours, TE:ETESSEE VALLEY AUDIORITY dt lif

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.tv.n D. R. Pattersen, Chief Mechanical Engineering Branch In Quadruplicate cc: Mr. M. J. Epprecht 1

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Northern, T. B., Jr., Spring City (3)

Drewer, C. L:., fl.CA CuhM-C P,rcun, H. F.., 600 CmB-C fice, M.14., Dei:ntur (3)

Stack. G. G., Daisy (I4)

Cain, J. J., 77CA cut!B-C Carroll, J. D., 700 CWB -C Curry, W. C., 9hCE CWB-C resign Pro;1cet Managers Davis, The:r.as, 93tt: cUn!!-C Ellington, R. L., 720A Ctmn-C Divens, W. M., $100 MIB-K Catlin, T. E., 75CC CUDH-C IIodges, R. M., W7C126 C-K Pierce, R. M., W4Cl26 C.K (2)

Hannah, J. G., 95CG CUBil-C Helton, Anita B., 700F CUBB-C Rus:cil, H. C., WSC126 C-K IlicPenan, J. R., 9 POD CUBR-C pincyard, J. P., W6D22h C-K llud son, B. A., Th CC Ct!PP -C J aynes, C. L., 42Ce CUPR-C Branch Chiefs Kimbrcunh, T. D., 92CG CUBB-C lowe, F.

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