ML19210A402

Forwards Addl Info Requested in NRC 760120 Ltr Re Reactor Bldg Spray Sys

ML19210A402
Person / Time
Site:	Crane
Issue date:	02/21/1976
From:	Arnold R METROPOLITAN EDISON CO.
To:	Reid R Office of Nuclear Reactor Regulation
Shared Package
ML19210A403	List: ML19210A402 ML19210A408
References
GQL-0249, GQL-249, NUDOCS 7910290627
Download: ML19210A402 (25)

Text

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. . e u.S. NUCLE AR REOULATOR) MMISSION DOCKET NUMBE A fNRCSQRM 105 l(2161  % $$ '

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NRC DISTRIBUTION FCR PART 50 DOCKET MATERI AL TO: FROM: DATE OF DOCUMENT

3 R '4 REID MEIROPOLITA*I EDISON CO 2-21-76*++"

EEADINO s EEIN DATE RECEIVE D R C AR'ICLD 6-1-76 LETTER ONOTORizEc PROP INPUT FORM NUMBER OF COPIES RECEIVE D g OORiciNAL gUNC LASSIFIE D

- i - gCC" - h Qggg, $ggp,h, DESCRIPTION

• ENCLOSU RE ADDITIONAL IITF0 'IITH LTR REF OUR 1-20-76 LTR......TPANS THE RESPONSE TO QUESTICITS CONCEPli N3 THEIR FOLLC'4IN3. . . . . . . . ANAIllS!S OF THE TMI-1 REAC"'OR EUILDIN3 SPPAY SYSTEM........

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PLANT NAME: k R E,G, % \ Q, ] Q FOR LA. . . AITACHED IS FIRST COPY REC '#ITH DATE OF 2-21-76...SUGGEST YOU COiTACT APPL FOR CO:TFIPl'ATICII 0F 2-21-76 DATE..........

. .a l FOR ACTION /INFORMATICN b~6L- % (I k l ASSIGITED AD: _ O m ASSIGITED AD:

/ERAIICH CH'EF: G) QT, D ERANCH CHIEF:

PROJECT MA?!AGER: PROJECT MANAGER:

n/ LIC. ASST.: b-[- K.LMKW s LIC. ASST.:

I INTERNAL DISTRIBUTION l

'V ~~~I'"" _J SYSTE'.'S SAFETY l PLA iT SYSTEMS E'TVIPO TECH V NRC PDR_ _ HEINETI l T EESCO  :'P;7ST I vI&E (2) SCHROEDER I PE'!AP0YA FALLARD l LMD LAINA9 ver"r ru i COSSICK & STAFF E'TGI?iEERI:tc IProLITO  !

MIPC MCCAFv SITE TEC9 i CASE ICIIquT CPEPATINa REXCIORS C;latILL  :

HANAUER owu STELIf STErP l HARLESS PAULICFI HULMAN I OPERATI?!G TECH I FFO.TECT 'M?TAGEME:r? REACTOR SAFETY 1A' EISE'; HUT SI~'E ANALYSIS j TOYD ROSS V SHA0 VCLLIER P COLLI!'S NOVAK (,,,,,,' 2AER EUNCH l HOUSTON ROSZTCCCY # SCIF..~~!C ER L,,d '" J. COLLI'!S

[ PETERSON CHECK // GRDES KREGER seIlm HELTDES AT & I SIT:' 'l'Et & ET7IRC SKOVHCLT SAL'I".JMN ANA!!:m S I R'JTEEEG DE' CON & 'CLLER 1 , O EXTERNAL DISTRIBUTION CONTROL NUMSER 1 VLPDRhgt.2 t h d Q , NATL LA3 "RC0KFAVE*! NATL LA3 -

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l Mt. I HOPOLII AN EDISON COMPANY '

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POST OF flCE COX 542 READING. PENNSYLVANI A ISG03 TELEPHONE 215 - 923 3601 February 21, 1976 GQL 02L9

- /. ~ . . ;.;.

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Director of Nuclear Reactor Regulatiphs- 3- ,

Attn: R. W. Reid, Chief S ','."/ 5 [- y* N #

Operating Reactors Branch #h  ! - U D' U.S. Nuclear Regulatcry Cet=ission  ;:' ,  ::] - 76 Q j . 'Q ,;/

Washington, D.C. 20555 e .A *

' C

Dear Sir:

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~~

Three Mile Island Nuclear Station Unit'l (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 By letters dated October 13 and November 12, 1975, Metropolitan Edison Ccepany transmitted the results of cur analysis of the TMI-1 Reactor Building Spray System. Your letter dated January 20, 1976 requested additional information be provided to permit ecmpletion of your review on this sub. ject. The specific informaticn requested and our response are contained below. *

1. Discuss hev the minimum static pressure at the points where the che=ical tank discharSe lines join the lines leading from the BiTST to the spray pumps was determined.

Respense: Refer to Attachment #1, Mathematical Method.

2. Describe and justify the methods used for determining the static pressure head due to the liquid in the BiTST, the aspiration force in the spray lines at the chemical tank discharge points, and the friction forces involved.

Response: Refer to Attachment #1

3. Provide system drawings showing the elevation of the chemical tanks, BiTST and connecting piping.

Response: Figures 1, 2 and 3 of Attachment #1 provide the schematic arrangement of the TMI-1 tanks and connecting piping. Table A-I of Attach ent 1 provides the elevation information requested as well as other pertinent information for each node or section of pipe identified en the above figures.

}4h9 }kh

" Note: 3 signed originals provided herewith; 37 additionally requested

' copies to fcilow under separate cover. -

s1 *n

L. Since free v;rtex for:..ation in the B'TSr could affect the static prec:ure head, provide the following information:

a. Provide the liquid heights in the BWST at the end of the injection phase.

b. Provide the maximum liquid velocity in the suction lines and the suction line diameters.

c. Describe any anti-vortex formation devices that are provided in the BWST. Provide an analysis of the effectiveness of these devices and include available emperical data which demonstrates that they vill be effective in preventing vortex formation.

Response: The end of the infection phase occurs when the liquid h?ight in the BWST reaches the tank lo-lo level alarm. This alar = is set for a level of 3 feet above the tank level tap or 1.25 ft. above the center of the outlet nozzle. Attach =ent 2 is 9 -) ,9 7 a figure showing the maximum flev rate in the suction l '; t d i' lines of the system. These flow rates are based on d

I l the four pumps, DH-P 1A/B and L2-P 1A/B, operating j, Q j k/4dLa L

'/j at design fl:,v. In addition, it was assumed that no flow exists from the chemical tanks since this represents the worst conditions which could exist at the end of the injection phase. The BWST contains no anti-vortex formation devices. As part of the startup and test program of TMI-1, a test was conducted to check sodium hydroxide-sodium thiosulfate-Borated Water Storage Tank draw down performance. During this test, the BWST was drawn down to the tank lo-lo level set point with each of the above four pumps operating at design flow conditions. Test personnel stationed by the pumps heard no indications of cavitation or vortexing during this test nor did flow indication reveal any cavitation or vortexing effects. The above test results, therefore, confirm that anti-vortex formation devices are not required in the TMI-1 BWST.

Sincerely, Signed: R. C. ARNOLD R. C. Arnold Vice President RCA:CWS:ilm e

1469 130

bec:

R. H. Hawk" -

J. J. Colitz Fr. R. A. Govers T. M. Critnins Babcock & Wilcox D. II. Grace P. O. Box 1260 J. G. Eerbein Lynchburg, VA 2h505 R. W. Hevard R. M. Klingaman L. L. Lawyer J. F. Peters J. R. Thorpe-Chairman, CORB, TNI-1 J. P. O'Hanlon-Chairman, PORC, TMI-1 '

B. M. McCutcheon*

C. W. Snyth R. S. Brown

146'l D \

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ATTACfc:E:n 1 50-289 DTD 2-21-76 C0!7fROL 5h29

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TA,'OlEMATI_ CAL MET 110D

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is codeled by deternining the steady state flou fron ihe drawdown transient The voluue of fluid drawn from the tank the tanks at their init.ial Icvel. In some during a five minute interval is calculated from the above flou.

cases a smaller interval was used because of rapidly changing steady state The tank Icvels are adjusted and another steady state balance flow rates.

is performed. This procedure is repeated until the transient is over.

The computer program performs a steady state pressure balance on an arbitrary A relaxation iterative method of network analysis, a modified piping network.

Ecrnoulli equation, and the Colebrook equation (the basis of the Moody diagra are the bases of analysis for the program. .

The two fluid properties required to calculate'the flow in a pipe are the These properties may be specific volume and the viscosity of the fluid.

inputted into the computer program as a function of temperature for any fluids desired, e.g. sodium hydroxide or sodium thiosulfate." If the fluid k in a pipe is water, ti cse properties may be inputted as above or calculated by the program.

Assuming saturated 2cer conditions exist in the pipe at a specified te=perature, the program calculates the specific volume as follows:

!3 + bT + CT V"+aT k V, =

• 1+dT

! + eT . *

/ .'.b )

where V = specific voluec at saturated water conditions (f t

• S 3 V = 3.1975 cm /g c s T =t * -t o t = Critical tecperaturc = 374.11 C.

c7 t = temperature in degrees C ~'

)h00 rs

• k cri.in:rti Assoc 4ns, t.s c.m. ---

. a u - 0.31515'.S

~3 b = - 1.203374 x 10

~

c = + 7.4890S x 10 d = + 0.1342489

~3 e = - 3.946263 x 10 k = conversion constant

= 0.0160185 (ft /lb)/(cm /g)

Again assuming saturated conditions, the viscosity of liquid water is calculated as follows:

p = k241.4 x 10

• (~ }

where p = viscosity (1b/f t-sec)

T = temperature ( K) k = conversion constant .

~

= 6.7197 x 10 (lb/f t-sec)/(micropoise) k .

'Ihe Moody friction factor is then computed by iterating the Colebrook equation

-0.5 f

= - 0.86 in (3 7d + .5 e

where f = Moody friction factor c = pipe roughnest (feet); the standard roughness of commercial pipe, 0.0018 incl.es, is assumed. .

d = inner diameter of the pipe (feet)

R = heynolds Number dV a

V,p V = fluid velocity in the pipe (f t/sec)

( .

~

. \ h69

\A Clt.BT.Rr ASSOCIATES, INC.

' To compute t!.c flow rate in a branch, the Ifne resistance of each pipe cust be knova. The line rer.istance is calculated as:

5 Rj ) = 0.03115 f Lc /d 2

where R = ihe Mshe fm fein { to Wh i (f t/gpm )

E = Moody Eriction factor L, = equivalent length of pipe (f t) '

= L + (did

- L = length of straight pipe (f t)

= total representative equivalent length in pipe diameters (h) of various valves and fittings d = inner diameter of the pipe (ft)

In addition to the data required to calculate the above properties for each pipe branch in the system, data must be supplied to the Iregram in which the branches are cocbined to form closed loops. To compute the flow rate in each branch, it is assumed that each closed loop obe, ,

Kirchoff's second law, i.e. the sum of pressure drops due to pipe losses and elevation changes around any closed loop is zero. Therefore:

H-IAP EL

~

p" where H = pump head (psc)

AP = Pressure loss due to elevation gain (psi)

EL AP. = pressure loss due to friction (psi) .

P R = residual pressure if loop is not balanced (R i 0 in a balanced loop) e and R

H-IAPg, - E ij (Q + AQ ) =0 1<33 1469 C .

• i CILDERT ASSOCIA1ES, INC.

. wherc Q = previously calculated flow between junctions i and j AQ k a fl w added to each line in the k

• loop to balance Kirchoff's equation (make residual R equal 0)

R Let a = E S V

ij b = 2E i3 15 1s ,

R Q c = H-EAP EL

~

LJ Then, using a modified form of the quadratic formula so the difference between large numbers is not caluelated, 2C og =

2 2

-b- (b -4ac)

To balance the network, the loop with the greatest error is selected, 6Qk

- calculated and the residual made zero. This process is repeated until the residual in every loop is less than 0.01 psi or the largest velocity change in all loops since the previous iteration is less than 0.05 feet /second.

Inc system being modeled is an opca system (Figure I). In order to mathematically close the system and insure the same pressure on the top of the fluid in cach tank, i.e. 14.7 psi, a control valve (which does exist in the system and is v t for the proper flow) was added to the discharge line of each pump, preset to the designated flow through the pump. The necessary pressure drop across this valve is calculated to insure the proper flow.

The pump discharge lines then converge to a comon junction (Junction 1, Figures Ir and III). A " dummy" fluid of low density and viscosity, is used to close the loop from Junction 1 to the top of the fluid in each tank. A large pipe (ID = 100 iriches) is assumed so no pressure loss occurs and the low density insures no pressure loss due to the cicvation change. Thus, the same pressure exists on the fluid surface in each tank.

(. -

1469 156 i

- ---- of ter.hr Assucliits.1.4c.-

0:her parameters calculated by the program are:

\

1. Junction Pressure R Q + AE P = P S Ab S-1 3 ij v

s AE = elevation change between junctions i and j

= specific volume in the branch between junctions i and j

{'3 ,

2. Fluid velocity (ft/sec)

'N V =

e v(f)2 k = conversion constant

.f

• ' O.13368 ft 1 tain.

gal 60 see i

1469 'i57

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-- CfLiir. fit AssuCf.ttrs, f ac.-- -

\T.i:1FIC-\TIO:t OF A:!ALYTICA1. :10 DEI.

As part of the start up and test program of TMI fl, a test was conducted In 1973 to check the sodium hydroxide-sodium thiosulfate - EUST drawdova by pumping water to the fuel transfer canal. The test and results of both the full flow and half flow tents are recorded in Test Procedure 204/3 of TMI Unit 1.

A comparison of the observed and calculated resul*.s of the full flow test is presented in Table I and Figures IV a, b, c. The computer model is shown in Figure II.

The calculated level drop per five minutes was comparable to that observed for the three tanks. It should be noted that since a steady state analysis is being done, there exists a larger discrepancy between the observed and calculated results during the startup of the test. The discrepancy at the end of the test is due to the manner in which the liquid levels were recorded; the automatic print-out device used was set to record the levels every five minutes.

When the LO-LO level alarm in the BWST was tripped, the pumps were throttled to terminate the test. The liquid levels and time were not recorded; the levels were recorded at the end of the five I minute interval, thereby causing the tail-off shown in Figures IV a, b, and c.

Test personnel stationed by the pumps heard no indication of cavitation or vortexing during the tests.

Further verification cf the program is provie o ty comparison to the half flow water test in which pumps DH-Pl3 and BS-PlB did not operate. (Figure III).

In contrast to the full flow test, the flow rates through the pumps were not constant. This effe-t was included in the analysis. Good agreement between the observed and calculated results is shown in Table II and Figures V a, b, *c.

1469 4e8 3 Gest.c,mme.nu cme.n Revision 1 - 2/11/76

FIGURE I MET t!OPOLIT At1 EDI5ON COMP At1Y TilF:EE tilLE ist AND HUCLE AR ST AT!Ott . UtilT 1 SCilEMATIC OF DECAY llEAT AND REACTOR BUILD;SG SPRAY SYSTEMS

(

85-11 ,

- 50DIO4 -

THIO 5UL ATE TANK 3

BS-PIB g3

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BS-T2 -

RBSPRAY E5 k' , PUMP 5

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.BS PIA WATER

' STORAGE

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DH- 3

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DECAY HEAT PUMPS OH-PIA -

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s FIG U R E 11 UETI!OPOLIT AN E DISON COnP ANY THR E E MIL E 15L AN's tiUCLE AR ST ATIOri U:llT 1 i It0 DEL OF DECt.Y HE AT AND RE/.CTOR EiUILDING SPRAY SYSTEMS FOR FULL FLOW DRAhDO'dN AN ALYSIS L E C E ti D l

• WATER N CH

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s FIGUR E 111 HETROPOLIT AN EDISON COMPANY ,

THREE MILE ISL AND NUCLE AR STATION - UNIT 1 LtODEL OF DECAY HE AT AMD RE ACTOR BUILDtHG SPR AY SYSTEMS FOR HALF FLOW DRAWDDWH ANALYSIS L E C E H D:

WATER HeCH

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o o o o o M N r.4 W <T (a003) dUJ. } DAD'l DAOqy ]DAO] WU3, 1469 167

^ r* %

• TABLE I Metropolitan Edison Company ,

Three Mile Island Nuclear Station L' nit I .

Sorated Water Storac'. Tank Dravdown Transient Analyefs Comparison of Analytical ?.sults to Tull Flow Vater Test LSWT Na0!! NaThio Time observed Calculsted observed calculated observed calculated (Minutes) Level

• Drop Level

• Drop Level

• Drop Le'.el* Drop Level

• Drop Level

• Dro; O 45.2 - 45.20 - 36.0 - 36.0 - 36.47 - 36.47 -

5 39.4 5.80 3'.49 6.71 32.16 3.84 32.98 3.02 32.34 4.13 32.59 3.E!

10 32.8 6.60 31.86 6.63 27.30 4.86 28.77 4.21 27.49 4.85 26.13 4.46 15 26.3 6.50 25.27 6.59 22.33 4.97 23.94 4.83 22.57 4.92 23.25 4.*7 20 19.88 6.42 18,71 6.56 17.46 4.87 18.71 5.23 17.65 4.92 18.09 5.17 25 13.5; 6.37 12.17~ 6.54 12.60 4.86 13.18 5.53 12.70 4.95 12.69 5.40 30 7.10 6.41 5.65 6.52 7.60 '5.00 7.44 5.74 7.73 4.97 7.09 5.60 35 3.19 3.91 -0.86 6.51 4.24 3.30 1.53 5.91 4.48 3,25 ,

1.34 5.75

• Levels are relative to tank level tap.

I s .

N CB

.D . .

M CJ' CO

R f~s TABLE II

, Metropolitan Edison Company Three Mile Island Nuclear Station Unit I Borated Water Storage Tank Drawdown Transient Analysis

• Comparison of Analytical Results to Half Flow Water Test BSWT NaOH NaThio Time Obse rved Calculated Observed Calculated Observed Calculated Level

• Level

• Drop Level

• Drop Level

• Drop Level

• Drop Levc1* Drop (Minutes) Drop' 0 54.08 -

54.08 - 48.5 - 48.50 -

49.0 - 49.00 -

5 52.58 1.50 50.82 3.26 43.0 5.50 46.00 2.50 43.5 5.50 45.94 3.06 10 49.58 3.00 47.57 3.25 42.0 1.00 43.26 2.74 41.0 2.50 42.84 3.10 15 46.29 3.29 44.33 3.24 39.4 2.60 40.36 2.90 37.9 3.10 39.73 3.11 20 43.06 3.23 41.09 3.24 37.0 2.40 37.37 2.99 35.2 2.70 36.60 3.13 25 39.92 3.14 37.91 3.18 34.1 2.90 34.38 2.99 32.4 2.80 33.51 3.09

~

36.83 3.09 34.73 3.18 31.0 3.10 31.35 3.03 29.4 3.00 30.40 3.11 30 33.74 3.09 31.57 3.16 28.0 3.00 28.30 3.05 26.) 3.10 27.31 3.09 35 30.38 3.36 28.45 3.12 24.8 3.20 25.26 3.04 23.2 3.10 24.24 3.07 40 45 17.31 3.07 25.33 3.12 23.4 1.40 22.19 3.07 20.2 3.00 ,' 21.18 3.06 I 27 3.04 22.21 3.12 21.6 1.80 19.14 3.05 17.9 2.30 18.09 3.09 50 3.31 19.09 3.12 18.7 2.90 16.05 3.09 15.5 2.40 15.01 3.08 55 l r, 3.00 12.96 3.09 13.9 1.60 11.95 3.06 60 17.'fr 3.00 15.98 3.11 15.7 2.99 12.92 3.06 12.25 3.45 9.91 3.05 10.8 3.10 8.92 3.03 65 44.t's 9.86 3.06 9.5 2.75 6.86 3.05 7.85 2.95 3.89 3.03

7) 11.64 3.33 6.80 3.06 6.2 3.30 3.83 3.03 4.45 3.40 2.83 3.06 25 8.67 2.97 1

J==

s t3

• Levels are relative to tank level tap.

s .

CJ' .

W

~ .

O TABLE A-Y .

Metropolitan Edison Company -

Three Mile Island Nuclear Station - Unit 1 BVST Dravdown Transient Analysis Branch Data Total Total Equivalent Equivalent Elevatten Diameters Length Change From To Pipe ID Straight Pipe _ (r_cc: L J F,ce,:)_

No. Junction Junction (Inch) (Feet) 900 Elbov 450 Elbow Cate Valve Check Valve Tee Run Tee Branch __ (t/D) 0 72 237.50 -12.16 0 0 0 98 2 2 24* 43.00 0.0 2 22 23.25 0 0 0' 0 1

0 0 209.50 -13.25 2

3 22 3

3 4

13.25 13.25 16-1/2 8

5 2

2 1

0 1

0 1

0 0

0

, 1 0

264 40 189

.17 25u.30

- 6.75

-11.42 -

lh 4 4 5 13.13 1 0 0 1 44 5 1 5 5 6 13.13 -13.25 1 1 284 324.03 1

2 1 1 20 35.8S - 7.25 6 3 8 13.25 10-1/2 0 0 0 0 1 0 169 225.41 -10.92 7 8 9 13.13 14 1 0 0 1 13.13 40-1/2 4 1 8 9 10 0 0 340 267.57 - ?.0 5 0 0 -16.75 4.026 153-1/2 13 5 1 474 131.23 9 18 19 3 1 -16,75 7 0 490 191.14 19 4 4.026 22-1/4 3 2 10 4.026 26-3/4 6 1 3 1 1 176 226.07 -10.50 11 19 8 0 0 2 1.5 13.13 33-1/2 3 1 1 248 211.08 12 5 23 0 1 1 10.02 4 1 1

0 0 120 120.70 - 3.5 13 23 15 0 0 0 10.02 20-1/2 6 15 16 14 2 240 312.10 -10.0 0 0 0 1 1.5 13.13 49-1/2 5 1 248 211.03 15 9 24 0 1 1

- 3.5 1 121.70 16 24 12 13 10.02 10.02 4

21-1/2 6 1

0 0(jjjj) 0 0 0. 120 17 12 =- 251.49 - 7.75 257 0 0 0 304

• 12 4 0 202.57 -33.75 149-1/2 454 18 20 21 21 12 4.026 4.026 50-1/4 8 0 3{}[jj) 3 1

1 3

2 1

2 494 225.91 -33.75 19 60-1/6 8 0 20 21 15 4.026

?-b c_ 4

• Note - The effect of a 24"-14" reducer vaa included. c5-, :J'0 c za (h[b, c-

__)

E_CC C~ ^ .~)

• CD I

. _Cd w

h3 W f3

RM78S3i55 1.

Keenan and Keyec, Thermodyncraic Properties of Steam, John Ulley and Sons, Inc. (1936).

2. ASME Steam Tables, 1967

3. Vennard, J.K., Elenentary Fluid Mechanics, John Wiley & Sons, Inc.

(1961).

4. Flow of Fluids Through Valves, Fittings, and Pipe, Crane Technical Paper No. 410.

5. Letter from J. F. Fritzen, Met Ed, to R. F. Ely, Jr., GAI dated 3 June 1975, Number GEL 1115.

1469 171

( -

s Cll.Dt'ItT ASSOCIATES, INC.

Aetachment 2 Metropolitan Edison Company Threc !!ile Island 5.'uclea r Station Unit 1 Decay 11 eat and Reactor Building Spray Systems Maximum Flote and Velocitics in Suction Lincs NO&

DH-n 1

i

.M- ja Pio 9000 GPr\

4S00 GM

10. 01" T.b .

31 i.s o o cm nyor ,' s, L ll 4j1 go, o t* .2. o L // Sys "

as- g 1500 C'n p1a Io .ct' Z. b.

1S0 o 6/'1 L.It fps to.ot.' 7 b. 'I "24 ,IT b.of 4ps IS'Co Gpm Gpn

~

13. /3 " -4 D. 9000 E'SS E#l 13 1 S ' Z. b .

bn-

.10.9 5 QC p3g ' ygoo 3 03 boo, Ch1 9 5 13 .13 T /foo ffp yspo cpm ,3,23,cy 7 g,,

7. f r 4.71b. 73,7y+ - 3_ 13.,3 a y,o. ,, y

/b.67 fpr

'/S00 (,Pps 3.56 .f ps /3. 2S ' T,b.

Da. /O. YT /ps P3 4 ~,

• /SD D 6Pm 4 3000 GAn 13.!3* T.b. /3.13 ' r.h.

7 '/ 5 S 10.L7 .(9s 1469 172

.