ML18004A527
| ML18004A527 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/19/1986 |
| From: | Zimmerman S CAROLINA POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NLS-86-310, NUDOCS 8609290385 | |
| Download: ML18004A527 (58) | |
Text
l~
I REGULA%AY'NFORj'jATIONDISTRIBUTI QYSTE)~j (R IDS>
A CESSION NBR: 8609290385.
DOC. DATE: 86/09/19 NOTARIZED:
NO DOCVET ¹ ACIL:50-400 Sheav on Hav v'i's Nuclear Power Plant>
Unit 1. Carolina, 05000400 AUTH. NANE AUTj.jORI'AFFILIATION ZZl'jj'jERI'jANiS. R.
Cav olina Powev'c Light Co.
RECIP. NANE REC'I IENT AFFILIATION DENTONp H. R.
Office of Nuclear Reactor Regulationi Div ec tov (post 851125
SUBJECT:
Advises that util pev fovmed supplementarg analyses fov v esults of, steam line bv eak in steam tunnel. Encl v ept demonstv'ates that essential components do not exceed environ levels. Analyses in v ept will be used to update FSAR.
DISTRIBUTION CODE:
SOOID COPIES RECEIVED: LTR / ENCL J SIZE:~
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 5 Related Correspondence NOTES: *pp 1 icati on fov permi t v enewa 1 +iled.
05000400 REC IP IENT ID CODE/Nhj'jE PWR-A EB PWR-A FOB PWR-A PD2 PD PWR-A PSB INTERNAL: ADlj/LFNB IE FILE IE/DGAVT/GAB 21 NRR PWR-B ADTS NRR/DHFT/NTB R('N2 EXTERNAL: BNL(ANDTS ONLY)
LPDR 03
~ NSIC 05 COPIES LTTR ENCL 1
1 1
1 1
1 0
1 0
1 3
3 1
1 1
1 RECIP IENT ID CODE/NANE PWR-A EICSB PWR-A PD2 LA BUCKLEY> B 01 PWR-A RSB ELD/j.jDSi IE/DEPER/EPB 36, NRR BWR ADTS REQ F 04 DANI/NIB DNB/DSS (ANDTS)
NRC PDR 02, PNL CRUELER COP IES LTTR ENCL 2
2 1
2 2
0 0
1 1
1 0
TOTAL NUi~jBER OF COPIES REQUIRED:
LTTR 30 ENCL 25
I l'
CSEE Carolina Power & Light Company SEP 'l 9 1986 SERIAL:
NLS-86-310 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.
1
DOCKET NO. 50-400 HIGH-ENERGY LINE BREAKS OUTSIDE CONTAINMENT
Dear Mr. Denton:
As requested by the NRC, Carolina Power
& Light Company (CP&L) has performed supplementary analyses for the results of a steam line break'n the steam tunnel at the Shearon Harris Nuclear Power Plant (SHNPP).
A physical modification of adding at least
.25 inch of insulation will be made to the valve body of ASCO solenoid valves in the main steam tunnel that are normally energized.
These analyses document the acceptability of the qualification level of equipment located in the steam tunnel.
In addition to the analyses, multiple sensitivity computer runs have been completed documenting the conservatism in the calculation.
The attached report demonstrates that essential components within the SHNPP steam tunnel do not exceed environmental levels for which they have been tested to function.
Therefore, in the analyzed
- cases, the plant can be safely shut
- down, and the health and safety of the public is assured.
Additionally, the NRC requested CP&L to confirm that the break exclusion zone for the main steam piping consists of the entire run of piping within the steam tunnel.
This is, indeed, the case and is discussed in the Final Safety Analysis Report (FSAR), Section 3.6.2.1.2.
The attached analyses will be used to update the FSAR in a post-fuel load amendment.
If you have any questions, please contact me.
JDK/pgp (4054JDK)
Attachment cc:
Mr. B.
C. Buckley (NRC)
Mr. G. F. Maxwell (NRC-SHNPP)
Dr. J.
Nelson Grace (NRC-RII)
Yours very truly,
~
~
S..
Z erman ager Nuclear Licensing Section
,ttl t
411 Fayettevilte Street o P. O. 8ox 1551
~ Raleigh, N. C. 27602 8609290385 860919 l
Qualification of Equipment; in the Shearon Harris Nuclear Power Plant Steam Tunnel following a Main Steam Line Break
INTRODUCTION The qualification of safety-related equipment in the SHNPP steam tunnel is based upon the analysis per formed by EBASCO which calculated the temperature and pressur e response of the steam tunnel following a main steamline break.
The steam tunnel is a large room adjacent to the steamline containment penetration where the main steam line isolation valves and steam header are located.
This room is vented to the atmosphere and is cooled by two safety grade 40,000 CFM fans.
EBASCO used the COMPARE computer code to evaluate the temperature and pressure pr ofile of the tunnel following a 1.4 square foot break at 102$ power.
The results of the EBASCO analysis, as 'well as the description of the subcompartment nodalization, tunnel initial conditions, and fluid properties ar e included in Attachment 1.
The qualification of equipment in the tunnel involved adding heat sinks to EBASCO's COMPARE deck to represent the safety-related components.
The heat sink sur face temperatures were then compared to the manufacturers'quipment qualification temperatures to determine whether or not the equipment would continue to operate in the tunnel environment following the break. This methodology was applied to the spectrum of break sizes defined in Reference 1.
MASS AND ENERGX The 'Mass and Energy release used for the analysis is the generic MSLB blowdown data supplied by the Westinghouse Owners Group (Reference 1).
These tables were generated using conservative assumptions which resulted in early tube bundle uncovery.
For selected
- cases, this data was adjusted to take credit for the instrumentation at the Harris Plant which would isolate the auxiliary feedwater to the affected generator following main steamline isolation.
Because of the termination of the auxiliary feedwater into the generator, tube bundle uncovery and end of blowdown will both occur earlier.
In order,to account for the more rapid increase in the fluid enthalpy expected as a result of the loss of the cooler auxiliary feedwater flow, the enthalpy of the blowdown was r amped to the maximum value of 1290 Btu/ibm over 10 seconds.
This sudden rise in enthalpy is included whenever both auxiliary feedwater isolation and tube bundle uncovery have occurred.
The mass and energy data used in this study are provided in Tables 2A through 2D.
HEAT TRANSFER Immediately following the start of the blowdown, heat transfer to the equipment in the steam tunnel is dominated by steam condensing on the equipment surface.
This heat transfer mechanism is very efficient, and the surface temperature of the component rapidly rises to the saturation temperature of the steam.
When the surface temperature rises above the saturation temperature, or the saturation temperature falls due to a change in room pressure, the heat transfer becomes characterized by a forced convection heat transfer mechanism.
Due to the high room temperatures and low pressures in the steam tunnel following a MSLB, this transition occurs very early in the event.
The forced convection heat transfer coefficient in a flowing fluid is based on a correlation having the following form:.
where:
h k(NQ)
D Nu - C(Re)
Re VDp u
C,n Emperical constants dependent on geometry and Reynolds number provided in Table 1.
h heat transfer coefficient, Btu/hr-ft F D
component outside diameter, ft.
k thermal conductivity of fluid, Btu/hr-ft F V
fluid velocity, ft/sec p
fluid density, ibm/ft3 u
fluid viscosity, ibm/ft-sec Therefore, the heat transfer coefficient for a component in a fluid with a specific velocity and a given set of fluid properties is dependent upon the component size and geometry.
The safety-related equipment in the steam tunnel was modeled by adding heat sinks to the COMPARE deck pr epared by EBASCO.
The actual components evaluated were the ASCO solenoid valve and the NAMCO limit switch.
Since each of the safety-related components in the steam tunnel can be modeled using a similar geometry, it was not necessary to include an additional heat sink for every piece of equipment.
These particular components combine the smallest dimensions (maximizing the heat transfer coefficient) with the thinnest housing wall thicknesses to give the highest surface temperatures of any equipment in the tunnel.
The ASCO solenoid valve has a housing thickness of 0.09 inches and is energized during normal oper ation.
The body of the valve has a 0.125 inch thickness and the smallest overall dimensions.
This component was qualified in an energized condition at an ambient temperature of 306 F.
The NAMCO limit switch has a casing of 0.125 inches and a
qualification temperature of 300 F.
All of the remaining equipment is bounded by the NAMCO limit switch. Heat sinks added to model any other safety-related equipment would show lower surface temperatures.
Both heat sinks were modeled using a cylindrical geometry.
The ASCO valve housing was given an initial temperature of 305 F based on measured coil temperatures while energized in a 116 F ambient environment.
The initial temperature of the NAMCO limit switch was set at 222 F corresponding to the saturation temperature of pur e steam at 18 psia This initial condition conservatively represents the effects of condensing heat transfer with an infinite heat transfer coefficient. Following the pressure spike at 0.25 secs.,
the saturation temperature falls and convection heat transfer begins.
Heat transfer coefficients for each break size were calculated using the
correlation given above.
The velocity used in calculating the Reynolds number is based upon the blowdown rate, minimum fluid density, and the area of the first subcompartment junction in the COMPARE model.
The rated flow of the fans in the steam tunnel is approximately 3$ of the initial flow from the 1.4 ft2 break, and is not expected to contribute significantly to the average velocity in the r oom.
RESULTS AND CONCLUSIONS 1)
NAMCO Limit Switch Figures 1 through 4 show the heat transfer coefficients used in the analysis of the NAMCO limit switch.
The results of this analysis for the spectrum of br eak sizes without isolation of the auxiliary feedwater to the affected steam generator are pr esented in Figures 5 through 8.
The maximum surface temperatures are as follows: 1) 368.5 F for the 1.4 ft2 break, 2) 332.6 F for the 0.86 ft2 break,
- 3) 310.9 F for the 0.5 ft2 case, and 4) 307.1 F for the 0.1 ft2 case with a constant heat transfer coefficient and no steamline isolation.
The NAMCO limit switch surface temperature exceeded its EQ limit of 340 F only for the 1.4 ft2 break. Credit is not taken here for the automatic auxiliar y feedwater isolation which occurs with steamline isolation.
Auxiliary feedwater isolation will cause the blowdown to terminate at an earlier time thus mitigating the effects of the break.
Additional cases were analyzed which included the auxiliary feedwater isolation and the rapid increase in blowdown enthalpy described earlier.
This conservative adjustment to the mass and energy becomes more conservative with smaller break sizes because these cases have smaller blowdown rates and require a much longer time to lower the steam generator levels to where superheat becomes significant.
The same heat transfer coefficients were used here as with the previous cases, and flow is terminated upon steam generator dryout.
The results of these cases are shown in Figur es 9 through 11, and the maximum surface temperatures of NAMCO limit switch are as follows: 1) 287.2 F
for the 1.4 ft2 break,
- 2) 304.9 F for the 0.86 ft2 break, and 3) 333.7 F for the 0.5 ft2 break.
The reverse trend of increased surface temperature with smaller break size is not an expected physical phenomenon, but a result of the excess conservatism associated with the ramped enthalpy r ise in the model.
One additional case has been analyzed to demonstrate the conservatism in the methodology used above.
This case is identical to the 0.5 ft2 break with auxiliary feedwater isolation except that the heat transfer coefficient used in the model more accurately reflects the actual value as shown in Figur e 12.
This results in a maximum surface temperatur e of 315.7 F shown in Figure 13; A summary of the results from all of the cases analyzed is provided in Table 3.
For those cases analyzed which reflect plant operation, the surface temperature of the NAMCO limit switch does not exceed the 340 F EQ limit.
2)
ASCO Solenoid Valve The solenoid housing and the valve body of the ASCO solenoid valve were analyzed separ ately to account for the internal heat generated by the
energized coil in those ASCOs positioned on the MSIVs.
These solenoid valves de-energize upon the MSIV closure signal, which occurs late in the event for the limiting oases involving small break sizes.
Qualification of the ASCO valves was performed with the coils energized in an oven at 346 F and 100$
relative humidity.
This becomes the EQ limit for the portions of the Valve without internal heat generation,
- however, the energized coil and coil housing will have temperatures in excess of 346 F.
In order to establish an acceptance criteria for the coil, the qualification test conditions were analyzed with a COMPARE model which included a heat sink with internal heat generation.
The results of this model (shown in Figure
- 14) establish a
reference temperature for comparison to the analysis of the same model in a blowdown environment.
Three cases were analyzed:
- 1) 0.5 ft2 with AUX FW isolation,
- 2) 0.5 ft2 without AUX FH isolation, and 3) 0.1 ft2 without AUX FH isolation.
The larger break cases cause de-energization of the coil to occur'early in the event which would result in lower housing surface temperatures.
The 0.5 ft2 case with AUX FH isolation is the limiting case without considering internal heat generation.
Heat transfer coefficients for these cases are shown in Figures 15 through '17.
These coefficients are designed to be lower than the expected Value when the surface temperature of the coil housing is higher than the atmosphere temperature, and greater than the expected value when the reverse is true and heat is being conducted onto the surface.
The surface temperature of the heat sink was selected as a point of reference for comparison between the tunnel conditions and test environment.
The maximum surface temperature calculated in the analysis of the test environment was 411 F.
Maximum surface temperatures calculated for the blowdown environments are's'follows:
1) 386 F
for the 0.5 ft2 case with AUX FH isolation,
- 2) 390 F for the 0.5 ft2 case without AUX FH isolation, and 3) 389 F for the 0.1 ft2 case.
These cases are presented in figures 18 through 20.
This analysis demonstrates that the solenoid coils will not experience temperatures higher than achieved during the qualification testing.
The second part of the evaluation of the ASCO solenoid valves considered the valve body.
This component is of particular concern because of its extremely small dimensions which reduce the metal mass available to absorb heat and maximize the heat transfer coefficient.
The ASCO valve body was analyzed for the 0.5 ft2 case with AUX FH isolation identified previously as the most limiting using the heat transfer coefficient shown in Figure 21.
The resulting maximum surface temperature was calculated to be 357.1 F, this
'xceeds the 346 F
EQ limit.
Because of the complex internal structure of the valve mechanism and the difficulty in modeling component detail with the limited heat sink features available in the COMPARE code, analyzing the temperature of the most sensitive element within the valve was determined not to be the most straight forward solution to this problem.
The maximum sur face temperature of the ASCO valve body can be most easily reduced by covering the component with pipe insulation.
Figure 22 demonstrates that 1/4 inch of insulation will reduce the maximum temperature from 357.1 F to 247.7 F, well below the 346 F
EQ limit.
This analysis presented cases covering a spectrum of break sizes with and without steamline isolation and continous auxiliary feedwater flow to the affected steam generator.
The results of this analysis demonstrate that for a main steam line break in'which the tube bundle is uncovered and superheated
steam is released, the maximum surface temperature of the safety-. elated equipment in the SHNPP steam tunnel will not exceed the temperature reached during the manufacturers'quipment qualification program.
Therefore the equipment is not, expected fail as a result of a MSLB environment.
REFERENCES (1)
Westinghouse Owners Group Letter, WOG-84-235, dated September 11,
- 1984, HELB Superheated Mass/Energy Release Outside Containment, Guidelines for Evaluation.
(2)
Kr eith, Frank, Principles of Heat Transfer, 3rd edition, Harper 8
Row Publishers, 1973.
MSLBEQ
FIGURE 1
20.0 19.0 18.0 17.0 16.0 15.0 14.0 1a.O 12.0 11.0 10.0 9.0 8.0
()
7.0 z
6.0 5.0 4.0 3.0 2.0 1.0 0.0 1.4 FTB MSLB NAMCO HEAT TRANSFER COEFF. vs TIME 0
20'0 60 80 100 120 140 160 180 200 TIME (SEC) o ACTUAL o
USED
FIGURE 2 15.0 14.0 13.0 12.0 11.0 10.0 5
9.O Ix 8.0 z
7.0 6.0 5.0 z
4.0 3.0 2.0 1.0 0.0 40 0,86 FTP.
MSLB NAMCO HEAT TRANSFER COEFF. vs TIME 80 120 160 200 240 280 TIME (SEC) o ACTUAL o
USED
FIGURE 3 10.0 0,50 FTP.
MSLB NAMCO HEAT TRANSFER COEFF. vs TIME 9.0 8.0 70 I
6.O IK 5.0 4.0 0
z 3.0 2.0 1.0 0.0 200 400 600 800 TIME (SEC) o ACTUAL o
USED
FIGURE 4 5.0 O,io FTP.
MSLB NAMCO HEAT TRANSFER COEFF. vs TIME 4.0 3.0 IKz 2.0 0
z 1.0 0.0 0.2 0.6 0.8 (Thousands)
TIME (SEC) o ACTUAL o
USEO
FIGURE 6 600 NAMCO LIMIT SWITCH 1.'4 FT2 MSLB (W/0 AUX. FW ISOLATION) 500 400 WK 300 0'
Q.
200 EQ LIMIT 100 200 400 600 TIME (sec) o ATMOSPHERE o
SURFACE
FIGURE 6 600 NAMCO LIMIT SWITCH 0.86 F12 MSLB (W/0 AUX FW ISOLATION) 500 400 W
300 4J 200 EQ LIMIT 100 0
0.2 0.4 0.6 0.8 1
1.2 1 4 1.6 1.8 2
(Thousands)
TIME (sec)
D ATMOSPHERE o
SURFACE
FIGURE 7 600 NAMCO LIMIT SWITCH 0.5 FT2 MSLB in (5/0 AUX. FW ISOLATION) 500 400 300 Q5 200 EQ UMIT 100 0
'0.2 0.6 0.8 1
(Thousands)
TIME (sec) o SURFACE OA o
ATMOSPHERE
FIGURE 8
600 NAMCO LIMIT SWITCH 0.10 FT2 MSLB (W/0 AUX FW ISOLATlON) 500 400 IJJ 300 fL 1LI 200 EQ LlMIT 100 0.2 0.4 1.2 1,4 0.6 0.8 (Thousands)
TlME (sec) o ATMOSPHERE o
SURFACE
FIGURE 9 600 NAMCO LIMIT SWITCH 1.4 FT2 MSLB (WITH AUX FW ISOLATION) 500 400 K
300 li IJJ 200 EQ LIMIT 100 20 40 60 80 100 120 140 160 TIME (sec) 0 ATMOSPHERE c
SURFACE
FIGURE 10 600 NAMCO LIMIT SWITCH 0.86 FT2 MSLB (WITH AUX FW ISOLATION) 500 400 300 ILJ 200 EQ LIMIT 100 40 80 120 160 200 240 280 TIME (sec)
D ATMOSPHERE o
SURFACE
F I GURE 11 600 NAMCO LIMIT SWITCH 0.5 FT2 MSLB {NITH AUX FN ISOLATION) 500 400 K
300 tL 200 100 200 400 600 800 TIME {sec) a ATMOSPHERE o
SURFACE
'F I GURE 12
]0.0 0.50 FT2 MSLB NAMCO 5-PART HEAT TRANSFER COEFF.
9.0 8.0 7 0 I
6.0 IK 5.0 3I-4,0 u
z 3.0 l-2.0 1.0 0,0 200 400 600 800 TIME (SEC) a ACTUAL o
USED
F IGURE 13 600 NAMCO LIMIT SWITCH 0.5 FT2 MSLB {5-STEP HTC W/ AFW ISO.)
500 400 0'00 lL 200 EQ LIMIT 100 200 400 600 800 TIME (sec) 0 ATMOSPHERE 0
SURFACE
FIGURE 14 420 ASCO (UALIFICATION TEST 346 F AMBIENT WHILE ENERGIZED 410 400 390 380 370 360 350 0
340 330 320 310 300 100 200 TIME (MINuTES) 300 400
FlGURE 15 10.0 0.50 FTP.
ASCO COIL HOUSING HEAT TRANSFER COEFF.
9.0 8.0 70 6.O IK 5,0 C
0 z
3.0 2.0 1.0 0.0 200 400 600 TIME (SEC) o ACTUAL o
USED
F I GURE 16 10.0 0.50
ASCO COIL HOUSING HEAT TRANSFER COEFF.
9.0 8.0 7 0 I
e.o IK 5.0 4,0 0
z 3.0 2.0 1.0 0.0 0.2 0.4 0.6 (Thousands)
TIME (SEC) o ACTUAL o
USED
FIGURE 17 5.0 0.10 FTP.
MSLB ASCO CO(L HOUSING HEAT TRANS. COEFF.
4.0 I
3.0 I
tLz 2.0 0
z 1.0 0.0 1.2 1.4 1.6 1.8 0.2 0.4 0.6 0.8 1
(Thousands)
TIME (SEC) o ACTUAL o
USED
FIGURE 18 600 DISCO COIL HOUSING 0.5 FT2 MSL8 (WITH AUX FW ISO.)
500 400 K
300 0
200 EQ LIMIT 100 200 400 600 TIME (sec)
D ATMOSPHERE c
SURFACE
FIGURE 19 600 DISCO COIL HOUSING 0.5 FT2 MSLB (0//0 AUX FVf ISO.)
500 400 K
300 200 EQ LIMIT 100
'0.2 0.4 0.6 0.8 (Thousands)
TIME (sec) o ATMOSPHERE o
SURFACE
FIGURE 20 600 ASCO COIL HOUSING 0.10 FT2 MSLB 500 400 IL' 300 Q.
200 EQ UMIT 100 02 04 06 08 1
12 14 16 18 (Thousands)
TIME (sec) 0 ATMOSPHERE o
SURFACE
FIGURE 21 12.0 0.50 FT2 MSLB WITH AUX FW ISO.
ASCO VALVE BODY HEAT TRANSFER COEFF.
11.0 10.0 S.O 8.0 bl 7.0 IK 6.0 m
5.0 4.0 3.0 2,0 1.0 0.0 200 400 600 800 TIME (SEC) o ACTUAL o
USED
FIGURE 22 600 ASCO VALVE BODY 0,5 F72 MSLB (WITH AUX FW ISO.)
500 400 0'00 UI 0
200 EQ LIMIT 100 200 400 600 800 o
ATM.
TIME (sec)
+
NO INSUL.
0.25 in. INSUL.
TABLE 1
O'A OF Ay=RAG"=:":"=A::3='%SF:-R C =FF:Ci"=4"ES Coett='c=ents C::1'ace" 'n a Gas F1ov'ng ho
. a to the E-.om R->>.
ence 2
C~~t.
oe:::c -.." 0 a
C'
..ce>>
P'c~ s C
MM aj V
Do Re Df
à 0.4 4
4-40
- 0. 891 0.821 0.330
- 0. 385 40 -',000 0.":.5 0.-'6o 4,000 40,000 0.'74 0.618 0 000 '00 000 OoO 39 0.805
TABLE 2A I
1.4 FT2 BREAI< W/AFW ISO.
TIME FLOW EiilTHALPY (SEC)
(LBH/SEC)(BTU/I BH)
Oia 5.0 10.0 15ia 20ia 2 'isa 30.0 40ia 50.0 60oa 70.0-80.0 90,a 94ia 9'
99 '
2975.0 2320.0 2756.0 2058.0 1699.0 1383.0 1232.0 1098ia 1023ia 973.2 937.7 909 F 9 859.6 778i8 684 '
0+0 1192 1202 1204 1204 1204 1204 1204 120/
1204 1203 1203 1245 1290 1290 1290 STEAHI IHE ISOLATION = 11 SEC AUX FW ISOLATION = 37 SEC TUBE UHCGVERY = 83.6 SFC
TABLE 2A ii 1 ~ 4 FT2 BREAK W/0 AFH ISO'ass Energy Blowdown Data of Reference 1 was used.
(4054JDK/pgp)
TABLE 2B I
0.86 FT2 BREAI< M/AFM XSQ.
TXHE FLOM ENTI.IALPY
<SEC>
<LBH/SEC)<BTU/LBH) 0.0 1+0 loin 20.0 30in 40' 50.0 60.0 7n,o 80in london 3 ~">in 150.0 2no,o 209 i 2 212.0 218.0 224.0 230 '
236io 241.2 242in 1739+0 1717.0 1579on 1898io 1802.0 1/05.0 1608.0 1518.0 1435,0 1357 i 0 1223.0 1073in 951 t5 535 t 4 530i2 528+6 506 '
469.0 415.4 339' 260o4 Oio 1191 1191 1194 1189 1191 1193 1195 1197 1198 1199 1201 1203 1204 1203 1203 1230 1290 1290 1290 1290 1290 1290 STEAHLXNE XSOLATXQN = 150.8 SEC AUX FM XSOLATXON = 176.8 SEC TUBE UNCQVERY = 209.2 SEC
TABLE 2B ii 0.86 FT2 BREAK 8/0 AFW ISO.
Mass Energy Blowdown Data of Reference 1 was used.
(4054JDK/pgp)
TABLE 2C 0.5 FT2 K<REAK W/AFM ISQ, TIME FLOW ENTHALPY
<SEC>
<Lax/BEC><S<TU/LIW>
Oio 1 io 10.0 2oia 30io 40
~ 0 50.0 60.0 8O,a loooo 125,a 150io 20O.O 250io 300.0 400.0 448.0 480oo 51o,a 530io 534' 540.0 545 '
550eo 580oa 600.0 666.3 667io 1024io 1016 '
961i4 977.0 1163.0 1136ro 1105.0 1072,0 1007.0 946+5 875+9 809
~ 6 763.8 632.9 554e7 5O4,0 489.1 471.6 457.1 319
~ 9 311.9 300.4 2~i'Oi 6 280.9 224 i3 173+ 7 115
~ 4 Oio 1191 1191 1193 1193 1187 1188 1189 1190 1193 1195 1197 1199 1200 1203 1204 1204 1204 1213 i~).)1 2 5 156n 1290 1290 1290 1290 1290 1290 STEAmLIvE ISQi ATIQN = 5a8,1 SFC AUX FM IBQLATIQH 534 1
SE('UE<E UNCQVERY
'= 450 BEC
TABLE 2C ii 0.5 FT2 BREAK M/0 AFW ISO.
Mass Energy Blowdown Data of Reference 1 was used.
(4054JDK/pgp)
TABLE 2D O.l FT2 BREAK W/0 AFH ISO.
Mass Energy Blowdown Data of Reference l was used.
(4054JDK/pgp)
TABLE 3 BREAK SIZE NAMOO TEMP{F) 1.4 ft2 h
15 0
< t 70 s
h 7
70 s
< t
< end w/o AFW iso.
368.5 0.86 ft2 h
10 0
< t 150 s
h7150s
< t
< end w/o AFW iso.
332.6 0.5 ft2 h-8 0
< t
< 300 s
h-5 300 s
< t
< end w/o AFW iso.
310.9 0.1 ft2 h 4 0
< t
< end w/o AFW 'iso.
307.
1 1.4 ft2 h
15 0
< t 70 s
h 7
70 s
< t
< end w/ AFW iso.
287.2 0.86 ft2 h
10 0
< t 150 s
h 7
150 s
< t end w/ AFW i so.
304.9 0.5 ft2 h
8 0
< t
< 300 s
h-5 300 s
< t
< end w/ AFW iso.
333.7
TABLE 3 (cont.)
BREAK SIZE NAMCO TEMP(V) 0.5 ft2 h
7 0
< t 100 s
h 6 100 s
< t
< 200 s
h5200s<
t <510s h 4510 s
< t
< 550 s
h 3 550 s
< t
< end w/ AFW iso.
315. 7 BREAK S I ZE ASCO COIL HOUSING TEMP(F)
(ENERGIZED) 0.50 ft2 h 4 0
< t
< 650 s
h 1 650 s
< t
< end w/o AFW iso.
396.0 0.5
$ t2 h 4 0
< t
< end w/
AFW iso.
390.3 0.1 ft2 h
2 0
< t 1200 s
h-1 1200 s
< t
< end w/o AFW iso.
389.8 ASCO QVALIFICATION h-2 0
< t 6 hrs AMBIENT TEMP 346>> F 411.0
TABLE 3 (cont.)
BREAK SIZE ASCO VALVE BODY TEMP(F)
(0.25 in.
INSULATION) 0.5 Vt2 h100<
t h 9 80 s
h 8
150 s
h 7 250 s
h 5 530 s
h 4 600 s
w/ AFW iso.
80 s
t 150 s
t
< 250 s
t
< 530 s
t
< 600 s
t
<- end 247.7
ATTACHMENT 1
CARO INA ?Oi'"=R
& LIGHT CO~:- SY
- ":"= DON F='ZRIS
%3C
".AR. O~'"-R PL~ST Ti:44:-'USCO..?D~NT Pn.
SSuR:-
T:-~P:.."=-'.Ti:R:- A';iALYSIS COWSHED"-R:~C S'".R:-:"=AT".D ST:--'u C04DIT'O'8<
Ray 6, 1985
CAROLINA POWER
& L.G".":T COYZANY SHEARON I'ORRIS NUCLEAR POWER PLANT PROPOSED R
SPONSE TO NRC QUESTION CONCE.";?i NG LINE BRE.-'3: ANALYSIS CONS!DER:NG SUPERHEAT COND!TIONS BAC::GROG".D Description of Stea Tunnel i."e Rain Stea=
Tunnel is located i.n the Reactor Auxiliary Building (RAB) ac'.acent to the Reactor Containmen Building at azimuth 270 (See FS~R Figures 1.2.2 - 27, 31, 35, 39
& 43).
!ne floor of the t'-..nel is at e'.evat on 253.00, the tunnel roof is at e'.eva on 305 00' c the penthouse roof is at e'.evat on 318.00.
The tunnel is bounded on the vest sice by the containment eall, the north side by a vali at column 29, the east side by a
vali at column D, and the south side by a vali at colu=n 25.
All valls floors and roofs a
e constructed of concre e and are at least 4'-0 thick.
Description of Subcomnartment Nodel The pressure and temperature subcompartment analysis vas performed using the CO~BARE computer code.
The steam tunnel +as subdivided into subcompartment volumes and connecting Junctions as presented in the nodalization model provided in Figures lA and 1B.
The tunnel vas divided into eleven (ll) subcompartments for the pressurization aralysis and four (4) eubconpartments for the temperature analysis.
The division of the subcompartments vas based upon the physical structure vhich makes"up the tunnel,,and the arrangement of the main steam piping.
Descri tion of the Bass Ener v Blovdoia Data The mass energy blovdoww data used in the subcompartment analysis corresponds to the data provided by the Westinghouse Cheers Group (WOG) provided via reference 3 for WOG member utilities in perfo~ing an interim evaluation of the effects of superheat steam blovdo~w outside of containment.
The data presented by the WOG in Table 2 are based upon a four-loop plant and result in early steam generator tube bundle uncovery and, therefore, the earliest superheat initiation time.
Descri tion of the Postulated HSLB Break Size and Coincident Sin Ie Failure Previous licens ing commitments and hRC acceptance of a steam tunnel subcompartment pressure/temperature analysis based upon a non-mechanistic pipe crack, equal in area to one cross-sectional pipe area of the largest main line in the steam tunnel vas considered in this analysis (See FSAR Sections 3.6. 1, 3.6.2, 3.6A and SH?HAPP SER Sections 3.6. 1, 3.6.2)
It should be noted that the mass/energy release data for a 1.4ft break used in the analysis corresponds to the total floM area of the SH?'PP steam generator floe restrictor located in the steam generator discharge nozzle (See FSAR Sections 5.4.4 and
- 15. 1.5,).
No additional single active failure vas assumed in the analysis of the postulated pipe break.
CAROLINA POt:ER
& L1GHT COY A4Y SHEARON F~RR:S h""CLEAR POQ R PLANT PROPOSED
RESPONSE
TO NRC QUESTION CONCERNING STE.-'
L1NE BREA>t; ANALYS1S CO'lSiDERING StlPERHEAT COND':.!ONS (Cont'd)
S>"-Cl C
'L=< 'O':
Rn ~~ON<=
The following prcvices the resporse to the s"ecific questio..s "resented ir.
the reference 4 letter.
Vith respect tc the pipe to be brokens ve reed tc
%ncaa-the:
a.
Type of flusd (7-ater or steam):
Hain Steam
- b. Te=perature:
Tsaturation
~ 540.2 F (Shearon Harris Plant Specific) 0
- c. pressure:
~964 si (Shee:nn n -.ris Plane Spec'fic S cal d.
Source of the fluid:
Hain Steam
- e. Flol: rate (or assumed floe rate) versus time*:
See Table 2
- f. Enthalpy versus time*!
See Table 2
- This Vestirghouse generic data may not correspond to SHNPP plant specific temperature and pressure.
- 2. Vith respect to the compartment being analyzed:
a.
t'umber of compartments analyzed!
Subcom artment Tem erature
=
~ Volumes Subcom artment Pressure
~ ll Volumes b.
For each compartment, including contiguous compartments:
0 i.
initial temperature
~ 116 F
ii.
inirial p.essure
~14.7 sia iii. initial humidity
"20-907. relative humiditv iv.
total floor area and floor space occupied by equipment (square feet):
v ~
See Figure 4
number of vents and vent areas (square feet) for each vent:
See Figures 1A & 1B vi.
compartment vali height (feet):
See Figures lA & 1B c.
Simple compartment and interconnection diagram:
See'Figures lA & 1B
C'BOLTS,A POV,:-R 6 L1GH, COYZAhY SH:-AROil P-'.RRi Yt:CLF..-'~ POi'-R PLAilT PROPOS:D R" SPOhS:-
TO NRC Ql:-ST10?:
CObC"RhTNG ST:-A.. I.l'.::-
BR:--'.!'. AHA. 81S COBS1D:.Ri YG S'O'P:RH"=AT CO"D1T1O!'.
(Cont'd)
SP"=C1..1C Ol".STTON R""SPO?:S".
(Cont'd)
- 3. Al assumptic..s used)
'ncluding but not lim'tec to the Orifice coef ficient:
- b. Fiuid expansion.actor:
c.
Heat transfer coeffic ent for heat through the valls:
Uchica Conc,ensation Heat Trans:er Coefficients Generic Pass anc ".rergy Release of HOG-8<-235, 9/11/84 used free convect ion or
- d. Single active failures that vere considered in the analysis:
No coincident single active failure vas assumed.
- 4. Jtilities analysis results:
- a. Temperature versus time curve (peak temperature specified)
See figure 2:
437 F
- b. Pressure versus time curve (peak pressure specified)
See figure 3:
c.
Peak humidity speci fied:
~18
.1 100"-
I SiEF iUNMEL NDDALIZATIONYODEL SUBCOY'PORTMENT TEt 'PER@.l URE ANALYSl5 FIGURE I A VOL.Q l29 FT.'
J3 VOL%
EL 300 Aifi VOL.3 I I 2pp'FT~
L.3 05.00 J2 VOL.2
/
'r0385FT.
EL,Z78.S VOL. I 3ISI 6FT.
EL.Z63.00 R=F g.'~ TC TA-'
fb. F'CR
~~K <r 8'PT104 OP VC'-'h/c.g AL'+
~NCTlC'9 c c
J i'll'lf S.
STEAVI UNNEL NODALIZPTION MODEL SUBCONFf-'.RTt.ENT PRESSURc. A.N4.'SI S FIGURF I 8 VOLUME 12
(~TMCS.-Haa E)
EL. 316 "c J19 J20 J18 J17 VOL.
9 VOL.
J2E EL 31'.OO J15 VOLUME 10 EL. 305 00 J12 J13 VOL.
6 VOL.
7 VOL.
8 EL. 278.50 J10 VOL 2
VOL.
3 VOL.
4 E L. 263.00
CAROI.INA POWER ANn I.IrllT COHPANV SllEARON IIARRIS NllCI.I.AR I'OWFR I'IDENT HSI.ll SllPERlll'.AT CONS II)l:.RATION IN STEAH TNNNFI, TFIIPERATllRF.
VS TTHF. RFSPONSF.
(I.~i ft HSI.ll)
F>GENRE 2
Coo
>00 I
I g
~
I l<O COO 5oo gvo Qvo 700 QVO 1IHE (Sl'.CONnS)
%pl ~ ~ muamua
~ tea
~ &Wl~ Ih I'Lllll I ~ I \\ ~tl I
'lrh>S
~ i
~ ~ ~ ~
~
SllFARON llARRIS HUCI.EAR POWER P I>NT MSI.H SUPERIIEAT COHSII)ERATION IH STEAN TUHHEI.
PRFSSURE VS TINE RESPOHSE
( I.~i f t.
MSI.II) 2 FIGURE 3
P~<m = 18 psla. (p 0 I)+F~)
loo
)yO QvO TI>IE (SFCONnS)
(V U
YiAIN STEAN 8, FFEDhVTER PIPE TUNNEL FC. Et
.2e3.00'lGURF 4
Cgv.
A,'y,~~~EuT 9'-DG.
Pl '-0 Fx~
I p,inc.7. PU'd. 8 X I
E I
0
+I 0
i Eie<x. ~
Dul.l 5cx
'g pR,Ah.E AL Fi.0"R 4~%A= /<~0 g P(.
5
~ S~p F cd% AR,'E l, 0c~u P QQ bW 5, ~'e ~5aTc c> R 5g W
SiiA
~ TUME:L NODAL1ZA! Oti..OD:L SL'SCOYZARTi4"-hi T-"YZ:.RATUR:. ANALYS1S TAMIL"= lA vt $1C Qf QQi TOVO'UNC;10'5 1<0<.00 780. 00 390.00 400.00 100.00 Refer to Figure 1A for Junction and Volume descriptions.
STiAN TUNNEL SUiCONPART~NT PR".SSUR:.
ANALYSIS JUNCTION DEFINITION TAiL:. 13
'ON
." RG~
VOL TO VOL JUNCTION 5
6 10 10 0
10 6
10 10 10 10 12 12 12 12 12 70'.25 691.7 70.25 1115.00 1099.00 1115.00 366.73 335.46 335.46 366.73 194.75 194.75 194.75 194.75 195.00 195.,00 100.00 100.00 100.00 100.00
- l. 00 100.00 Junction r to Figure li fear Junction and Volume Descriptions
t