ML17262A453
| ML17262A453 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/05/1990 |
| From: | ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML17262A448 | List: |
| References | |
| NUDOCS 9104300406 | |
| Download: ML17262A453 (62) | |
Text
{{#Wiki_filter:RG&E Answers To The NRC's March 21, 4991 Station Blackout Questions Attachment 4 Turbine Driven Auxiliary Feedwater Pump Area Heatup Calculation 9104300406 910422 PDR AGOCK 05000244 PDR
QA LPETjME 900606-0 z 1 Devonrue Calculation Cover Sheet Project No. $ - fgggy// Subject st 7P / Pl/ F'f- knht T . r~ Description n &reef Prepared by+ Reviewed Approved by Number of pages /~>2 5/s4gCd 4 Appendices Attaciunents g tt/os~ /t7//
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 1 of 12
Subject:
No computer calculations have been utilized in this analysis.
- 1. The perimeter of the Intermediate Building is assumed to be as shown on Ginna Station Drawing 33013-2113, Rev. 0
- 2. The normal maximum ambient temperature in the Intermediate Building is assumed to be 104oF
- 3. The normal maximum ambient temperature of the Containment Structure just adjacent to the south wall of the Intermediate Building is assumed to be 120'F as stated in Ginna FSAR Table 3.11-1.
- 4. The south wall of the TDAFW pump Area is assumed to be pouted concrete as shown on Ginna Station Drawing 33013-2113, Rev.0. The North, East, and West walls of the TDAPV pump area (the north portion of the Intermediate Building, el. 253) are solid concrete block as shown on Ginna Station Drawing 33013-2113, Rev.0. These walls are assumed to behave in a similar manner to poured concrete walls and will be treated similarly in this calculation.
- 5. The initial wall temperatures are assumed to be in equilibrium with the initial air temperature.
- 6. Thermal insulation on piping and equipment is assumed to be of the type and thickness defined in RGB'echnical Specification ME-269, Revision 0.
- 7. Heating Steam piping and equipment is conservatively assumed to have a normal operating temperature of 220'F.
Additional assumptions are stated throughout the body of this calculation.
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 2 of 12
Subject:
- 1. NUMARC 87-00, "Guidelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors," including Appendix E, Appendix F, and the Appendix F Topical Report, November 1987.
- 2. RG&E Technical Specification, ME-269, "Pipe, Duct and Equipment Insulation, Ginna Station," draft issue Revision 0, dated January 30, 1989.
- 3. Ginna Station Plant Arrangement Drawing No. 33013-2113, Rev. 0, Cont. Struct. &
Intermediate Bldg. Plan - Oper. Flr. E1.253'-3".
- 5. Ginna Station P&ID Drawing No. 33013-1231, Rev. 13, Main Steam.
- 6. Ginna Station P&ID Drawing No. 33013-1915, Rev. 4, Heating Steam.
- 7. Marks Standard Handbook for Mechanical Engineers, Ninth Edition, 1987.
r
- 8. Ginna/UFSAR Table 3.11-1, "Environmental Service Conditions for Equipment Designed to Mitigate Design-Basis Events."
- 9. Vendor Drawing, LD-111347, Worthington, Corp., Outline drawing of Auxiliary Feedwater Pump Turbine
- 10. Gilbert Associates, Bill of Materials, for Steam Driven Auxiliary Feedwater pump and Steam Turbine Drive.
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 3 of 12
Subject:
The objective of this calculation is to determine the ambient temperature rise in the TDAPYV pump area of the Intermediate Building during a 4 hour SBO-induced loss of ventilation. Because the Ginna Station Blackout coping duration is 4 hours, the simplified methodology provided in NUMARC 87-00, Section 7 will be applied. The Section 7 methodology is based on the fact poured concrete walls act as heat sinks and that their surface temperatures willremain essentially constant over the course of the 4 hour loss of ventilation. As stated in the previous section, the surface temperature of the solid concrete block walls will also be assumed to remain constant. Section 7 of NUMARC 87-00 presents the following simplified equation for use in evaluatin'g a four hour loss of ventilation: Tait Tw+ [QIA]3~4 where: Tair is the resultant ambient air temperature in the TDAPV pump area(the north portion of el. 253'-3" of the Intermediate Building}after 4 hours; Tw is the wall temperature; Q is the heat generation rate fthm hot piping, equipment, and electrical devices; and A is the surface area of the walls and ceiling acting as heat sinks. The effects of opening doors to allow removal of heat through natural circulation are evaluated as defined in Section 7, p. 7-15, of NUMARC 87-00: Tair Tw+ (Q3~4l[A3~" + 16.18 F 0 6 3]} where F is the "door factor" and is equal to H3< W; where H and W are the height and width of the door, respectively.
Devonrue Calculation Project No.8-9025.00 Date: 598/90 Page 4 of 12
Subject:
The following steps shall be performed to accomplish the described method for determining the TDAFW pump an:a ambient temperature:
- 1. Sum the wall surface areas to obtain A in square meters. For conservatism, the surface ama of the ceiling will be neglected as it is constructed of corrugated metal attached to the pouted concrete floor slab of the elevation above.
- 2. Determine the initial wall temperature. The effects of the higher temperature of the south waH which is exposed on its outer surface to the Containment Structure ambient temperatuie will be considered.
- 3. Conservatively estimate the heat generation rate, Q, in the TDAFW pump area. This will be done by considering heat rejected by hot piping and equipment using the equations given on p. 7-19 of NUMARC 87-00. Heat rejected by operating electrical equipment will also be considered.
- 4. Apply the results of the above and calculate the resultant ambient temperature.
- 5. Evaluate the effects of opening doors.
Step 1: Sum wall surface areas to obtain A, in sq. meters This step is accomplished using the referenced drawing, 33013-2113. As previously identified in the Assumptions Section, the solid'concrete block walls bordering the North, East, and West sides of the Intermediate building will be considered in this evaluation. The South wall borders the Containment Structure and is constructed from poured concrete. The ceiling surface area has been neglected as a heat sink since it consists of corrugated metal.
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 5 of 12
Subject:
The straight walls are simply scaled directly from the reference drawing (see Figure 2) while the curved wall length is determined using analytic geometry. Using Figure 1,
*
($ 1+ g2 )/360 (x D) = length of curved wall
$ 1 = tan -1 (4 7/8 /4) = 50.63'2
= tan -1 (5 13/16/3) = 62.70'1+
g2 = length = (113.33/360) m (33.68) = 33.33 m; 113.33'herefore, where 33.68 is the measured diameter of the containment from the referenced drawing 1 2 CL Figure 1 Calculation of curved wall length
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 6 of 12
Subject:
3.04 28.04 3.35 3.05 10.06 7.92 33.33 6.40 Figure 2 North Portion of Intermediate Building, El 278'-4" (note: all dimensions are in meters) Using the dimensions in Figure 2, the perimeter of the room is calculated by summing these lengths. ZI. = 97.93 meters = Perimeter The Surface Area, A, is computed by multiplying the perimeter by the height of the walls. Review of the referenced drawing and the drawing for the elevation above (33013-2129), show that the height, h, is: h = el 278'-4" - 253'-6" = 24'-10" = 7.57 meters therefore, A = 97.93
- 7.57 = 741.33 sq. meters
Devonrue Calculation Project No.8-9025.00 Date; 5/28/90 Page 7 of 12
Subject:
Step 2: Determine the initial wall temperature, T; in 'C The initial wall temperature will be calculated by means of a weighted average of Surface area between the South wall, adjacent to the Containment Structure and all other walls, The initial temperature of all other walls is assumed to be 104'F, which is the stated FSAR value for the normal maximum ambient temperature in the Intermediate Building. The South wall surface temperature is calculated as an average between the Containment maximum normal ambient of 120'F and the 104'F Intermediate Building ambient temperature, Therefore, T (South wall) = (120'F + 104'F)/2 = 112'F the initial temperature computed by weighted average on the basis of area is: Ti = (33.33/97.93)*112 + (64.6/97.93)
- 104 = 107'F = 41.7 C Step 3: Estimate heat generation rate, Q, in watts The major source of heat in the TDAFW pump area is hot piping and equipment. A physical inspection of the area revealed the following soutces:
(1) 1/2" diam. Tb. Steam supply line (insulated), 15 ft. long (1) 6" diam. Tb. Steam supply line (insulated) 110 ft. long (1) 1/2" diam. Tb. exhaust line (uninsulated), 100 ft. long (1) 3/4" Tb. exhaust line(uninsulated), 20 ft. long (1) 4" diam. Tb. Exhaust line (insulated), 14 ft. long (1) 4" diam. Tb. Exhaust line (uninsulated), 60 ft. long (1) 8" diam Tb. exhaust line (insulated), 7 ft. long (1) 8" diam. Tb Exhaust line (uninsulated), 20 ft. long
"
(1) 1-1/2 diam. Heating Steam line (insulated), 89 ft. long (1) 8" diam. Heating Steam line (insulated), 52.4 ft. long (1) 2-1/2" diam. Heating Steam line (insulated), 69.4 ft. long (1) 28" Diam. Stm. Turbine (insulated)
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 8 of 12
Subject:
(1) 2" diam T+T valve (uninsulated), 1.25 ft. long (1) 12" diam Governor valve (uninsulated), 1.7 ft. long In order to calculate the heat generated from the above listed sources, the surface temperature of insulated components must be determined. As stated in the Assumptions section, insulation type and thickness is assumed to be as specified in RGB'hermal Insulation Spec ME-269, Table I, except in the case of AFW Turbine where the insulation thickness was scaled from the outline drawing. In accordance with paragraph 2.01 of ME-269, all insulation is assumed to be calcium silicate. The surface temperature is calculated by considering the convective heat transfer between the insulated surface and the air; q=hAdT=h(Ts T )2x rsl where h is the unit thermal surface conductance in Btu/hr. sq ft 'F, rs is the radius of the insulated surface in ft., 1 is the unit length, Ts is the insulated surface temperature,'nd T~ is the ambient air temperature the conductive heat transfer from the pipe surface through the insulation; q = (Ti - T~)
- 1/(fin (rs/ri)/2zkl] + V 2zrs 1 h};
where Ti is the pipe surface temperature and ri is the pipe radius Combining the two equations yields; Ts = [Vhrs *(Ti - T~)}/[[In(rs/ri)/k]+ 1/rs h } + T~
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 9 of 12
Subject:
A similar development is applied to the AFW Turbine which is basically treated as an insulated sphere. The final equation is: Ts = T + [(TI.T )+(I/h rs2)~/ {[(rs-ri)/(krsri)]+ (I/h + rs2)) In this evaluation, the following constant values are applied: T~ = 107'F (see p. 7 of this calc.) h = 1.6 Btu/hr sq ft 'F (Table 4.4.11 of Marks Handbook) k = 0.045 Btu/hr ft 'F (Table 4.4.6 of Marks Handbook) Note that the Tb. exhaust lines were considered to have a surface temperature of 240'F. This value is based upon the information in the AFW Steam Turbine Bill of Materials, previously referenced, which gives exit steam conditions. The results obtained when applying the above equation are summarized in Table 1. TABLE I CALCULATION OF INSULATED SURFACE TEMPERATURE (Ts) Description Ti ('F) ri Ins. rs In(rs/ri) Ts( F) ( t t) thk. (tt) (tt) 1/2" Tb. Stm sup. 550 0.02 0.125 0.145 1.981001 146 51
~
6"Tb. Stm sup. 550 0.276 0.2083 0.484 0.562304 148.47 4" Tb. Exh. 240 0.188,0.125 0,313 0.509761 126.93 8" Tb. Exh. 240 0.36 0.125 0.485 0.298045 128.66 1-1/2" Htg. Stm. 220 0.08 0.083 0.163 0.711724 129.05 8" Htg. Stm. 220 0.36 0.125 0.485 0.298045 125.41 2-1/2" Htg. stm. 220 0.12 0.083 0.203 0.52571 4 1 30.57 Stm Turbine 550 1.17 0.292 1.462 N/A 139
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 10 of 12
Subject:
Using the results of Table 1, the heat generation, Q, can be calculated from the following equation found in Section 7 of NUMARC 87-00: Q = (0.1[0.4 + 15.7(Ts - Ta)l/6Dl/2 + 170.3(Ts - Ta)1/3D](Ts - Ta)
+ 1.4E-7D(T4s - T4w)}L and in the case of the spherical Turbine, Q = (0.1[2 + 370(Ts - Ta)1/4D3/4I*D(Ts - Ta)
+ 1.4E-7D (T4s - T4a)}
Table 2 summarizes the inputs and results based on the above equations. TABLE 2 CALCULATION OF HEAT GENERATED by HOT PIPING & EQUIPMENT Description Ts('F) Ts('K) L(ft) L(m) Do(ft)Do(m)Ts-Ta Ts4-Tw4 Q (watts) 1/2" Stm sup. 146.5 336.767 1 5 4.57 0.29 0. 09 21. 95 3. 042E+09 677.39 6" Stm. sup. 148.5 337.856 11 0 33.5 0.968 0.3 23.04 3.209E+09 16629 1/2" Tb. exh 240 388.706 1 00 30.5 0.042 0. 01 73.89 1.301E+to 3680.4 3/4" Tb. Exh. 240 388.706 20 6.1 0.063 0. 02 73.89 1.301E+10 1042.6 4" Tb. Exh 1 26.9 325.889 1 4 4.27 0.626 0.19 11.07 1.459E+09 558.62 4" Tb. Exh. 240 388. 706 60 1 8.3 0.333 0.1 73.89 1.301E+10 14620 8" Tb. Exh 128.7 326.85 7 2.13 0.97 0.3 12.03 1.593E+o9 470.98 8" Tb. Exh. 240 388.706 20 6.1 0.667 0.2 73.89 1.301E+10 9471.8 1 1/2 Htg. Stm 1 29.1 327.067 8 9 27.1 0.326 0.1 12.25 1.623E+09 2171.2 8 Htg. Stm. 125.4 325.044 52.4 1 6 0.97 0.3 10.22 1.343E+09 2884.2 2-1/2" Htg Stm 130.6 327.911 69.4 21.2 0.406 0.12 13.09 1.742E+09 2259. 6 28" Stm TB. 139 332.594 NA NA 3.05 0.93 17 77 2.417E+09
~ 400 T+T valve 550 560.928 1.25 0.38 0.167 0. 05 246. 1 8.918E+10 838.4 Governor Vlv 550 560.928 1.7 0.52 1 0.3 246.1 8.918E+10 6401.8 Total Q(watts)= 62105
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 11 of 12
Subject:
Review of Table 2 shows that the uninsulated Tb. exhaust lines were considered to have a surface temperature of 240'F. This value is based upon the information in the AFW Steam Turbine Bill of Materials, previously referenced, which gives exit steam conditions. In addition to the 62,105 watts generated by hot piping and equipment, an additional 1,000 watts will be added to account for heat generated by emergency lighting, operating solenoids, etc. Therefore, the total heat generated in the TDAPV pump atea is: Q = 62,105 + 1,000 = 63,105 watts Step 4: Calculate the ambient temperature This step is accomplished by applying the NUMARC 87-00 correlation: Tair = Ti + [Q/A] T - = 41.7 + [63,105/741.33]3/4
= 41.7 + 28 = 697 C = 1575 OF Step 5: Evaluate the effect of opening doors This step is performed using the NUMARC 87-00 correlation for considering free convection through vertical openings. Arrangement drawing 33013-2121 shows double doors on the west side of the North wall which open to the Turbine Bldg. The'Turbine bldg area adjacent to these doors is assumed to remain at 104'F during the 4 hour blackout duration due to its configuration and the lack of significant heat sources in the area.
The effects of opening doors to allow removal of heat through natural circulation are evaluated as defined in Section 7, p. 7-15, of NUMARC 87-00: Tair Tw+ (Q3/4/[A3/4 + 16.18 F 0 8653)) where;
Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 12 of 12
Subject:
F is the "door factor" and is equal to H3/2W; where H and W are the height and width of the door, respectively. As measured from the layout drawing, W is 8 ft. (2.44m) and H is assumed to be 7ft., the standard industrial door height. Applying these relationships to the double doors yields an F of: F = (2.13) /2 * (2.44) = 7.58 therefore, Tair = 4 + 41.7 + ((63,105)3/4 / [(741.33)3/4 + 16.18 * (7.58).8653]) Tair = 4 + 41.7 + 16.91 = 62.61'C = 145'F
GINNa/vpsaR f+ ~ s py gg G+ Table 3.11-1 Q)Pf FbtJ ff&kAGae&
/~ Z P lg/
ENVIRONMENTAL SERVICE CONDITIONS FOR EQUIPMENT DESIGNED TO MITIGATE DESIGN-BASIS EVENTS INSIDE CONTAINMENT Normal 0 erationr Temperature 60'F to 120'F Pressure 0 psig Humidity 50X (nominal) Radiation Less than 1 radlhr general. Can be higher or lower near specific components. Accident Conditions LOCA S+c~ - M vu. ~~ Temperature Figure 6.1-2 (286'F maximum) Pressure Figur e 6. 1-1 ( 60 ps ig design) 40 PSlg Humidity 100l 7 Radiation Tables 3.11-2 and 3.11-3; 1.43 x 10 rads gamma 2.07 x 10 rads beta Chemical, spray Solution of boric acid (2000 to 3000 ppm boron) plus NaOH in water. Solution pH between 8 and 10. Flooding 7-ft (approximately) maximum submergence elevation is 242 ft 8 in. , AUXILIARY BUILDING Normal 0 eration: Temperature 50 F to 104 F Pressure 0 psig Humidity 60X (nominal) Radiation Less than 10 mradlhr general, with areas near residual heat removal piping less than 100 mradthr during shutdown operation. Accident Conditions includin sum recirculation LOCA one train of ESF coolin o eratin Temperature 50F to 104 F Pressure 0 psig Humidity 601 (nominal) 3 ~ 11-19 REV 4 12/88
4-90 TRANSMISSiON OF HEAT BY CONDUCTION AND CONVECTION // ~ /
~d>>~/ ~
/
appears to be the best available. Zubcr also performed an anal- obtained at an coefficient overall temperature differcncc of 60 F. I -0 ysis for subcoolcd liquids arid PfoPosed a modification which is also in cxcel1cnt agreement with cxperimcnt:,
"
this Point, the a Aux dccrcasedraPid}y, ing the values obtained in superheating vapor, scc Eq a~ ud Add cats 1/I f crgtgAPc Pn) 1 / Pt (q/A) c m Ktp,p + Cyg , /)) [ Pa Pl Pv> 5.33(pcC jk,)'/'(t, t/) [ gt(pc p,)p,] O.4
~ 1 +
1 i%3 lI: " c Zuber's hydrodynamic analysis of the Leidenfrost point yields 1/a ega'hc- " P.) V jl (q/A) m K~l PP 0.144 < Ka < 0.17? . (4A.I4d) gi D.l 0 Berenson finds bcltcr agrcemcnt with thc data if K, m 0.09. For comparison, in a natural convection evaporator, a In~. mum Aux of 73,000 Btu/h/ft was obtained at (ht),of 100 F For very small wires, thc heat flux will cxcccd that predicted by this flat plate formula. A reliable prcdiction of thc critical cotnblned convection and Radiation coetticlentb in sottte,
~ T Va:
m "@ tempcraturc is not available. of heat loss, such as that from bare and insulated p p" @ 'ases of ias For nuc1eatc boiling accompanied by forced convection, the where loss is by convection to the air and radiation to the teafhg>> heat flux may bc approximated by thc sum of the heat Aux for pool boiling alone and the heat Aux for forced convection alone. of lhe cnclo ing sp cc it is convenient to usc a combined'".r. vection and radiation coeAicient (h, + h,). The rate of h'ca} v i>>ii 540.4) nu'oss This proecdurc will not be satisfactory at high qualities. and thus becomes d, enc}ostng kI i no satisfactory correlation exists for thc maximum heat Aux. mttfj,+ For a given liquid and boiling pressure, thc nature of Ihc q m (h, + h,)A(dt), (4A.IS) j."- surface may substantial1y inAucnec the flux at a given (At), Table 4.4.10. Thcsc data may bc used as rough approximations wherc (c) t), is the temperature difference, deg F, between tfte ~ for a bank of submerged tubes. Film coefficients for scaic surface of thc hot body and lhe walls of thc space. fn evaiuat: deposits arc given in Tab1e 4.4.g. ing (h, + h,), h, should bc calculated by the appropriate con
'".
'i 'at For forced~clou eva poratoct, vapor binding is also encoun. vection formula [see Eqs. (4A.llc) to(4A.llg)) and h, from the ui tered. Thus with liquid benzene cntcring a 4.pass stcam jack. equation cled pipe at 0.9 fps, up to thc point where 60 pcrccnt by weight was vaporized, thc maximum flux of 60,000 Btu/h/ft'as h, m 0.00685c(7/100)
~ ~
Table 4.4.10 Maximum Flux and Corresponding Overall Temperature Difterence tor Uquidb Boiled at 1 atm with a Submerged Horizontal Steam.Heated Tube Chrumiom-Aluminum opt>cr Smt I 1>lated c I ...~re Uqutd 1, 9'A >/!A 9/A ' 1000 1000
>>>>. ttit). ,,V>>.Cibt
( II Ethyl acetate.... Bet>acne........ Ethyl alcohol.... 41
$1 5$
80'b I 10'1 73 124
$$
100 45 82 100
>'Jp,
~
~
I ~ h'l ethyl alcohol .. I I0 I IO 1$ $ I IO I~) ~ Distilled icatcr.. 3$ 0 7$ 410 1$ 0 tI~~ 1 0 Valued ol (hc + hp)
~i}
Table 4v4
~
For horizontal bare or insubted star>dard steel pipe of various site:s and for fiat plates in a room at 80'F I (a/I>. tenipccatuce dill<<cence. deja F, ttoo> autiaee to room Nominal I ipe diam in. so } 100, Iso 200 2so 300 '00 '00 e00 ,'700 '00 I1900 I 1000 f 1100 1200 2.12 2.48 2.76 3.10 3.41 3.1$ 4.47 S.30 6.2117.25 d.40 9.7S}11.20 12.81'14.6$ I 2.03'2.3d 2.6$ '2.98 3.29 3.62 4.33,$ .16 6.0717.11'8.2$ 9.57111.04 12.6514,48 2 I. 93 2.27 2. $ 2 2. 8$ 3.14 3. 47 4. 18 4.99 S. 89>6.92 8.07,'I. 38 10.85 12. 44 14. 2d I.dd 2. Ie 2.41 2.12 3.01 3.33 4.02 4.83 5.7216.75 7.89 9.21,10.eb 12.27 14.09 8 1.76 2.06 2,29 2.60 2.89 3.20 3.88 4.68 $ .57 b.eo 7.73 9.05>10.50 12.10 IS.93 12 1.71 2.01 2.24 2.$ 4 2.d2 3.13 3.d3 4.411$ .50;6.52 7.6S 8.96'10.42 12.03 13.dc 24 1,64 1.93 2. IS 2.4$ 2.72 3 03 3.10 4.48 $ .31'6 ~ 39 7 ~ 52 bvbS'10.28 )1.90 13.70 FLAT Pa>>Tea vertical...... ~ .~.~. HFU..........""" }2.00 2.35
" I.dz 2.13 2.40'2.70 2.99 3.30 4.00 4.79 2.4$ 2.91 3.26 3.$ 9 4.31
} } }
$
t ( } I }
.70 6.12 7.86 9.18'lb.64'12.2S.I4.06 5.12 6.04 7.07 8.21 9.54 11.01 12.e3'14.45 HFD.......... ~ .."",1.$
~
d 1.8$ 2.09 2.36 2.63 2.93 3.61 4.38 5.21 6.27 1.40 8.7110.16 11.76 13.57 IIFU, ho>>i><>nial, (>>ting up>v aid; I IF D, hodaoniit, Acing do>>> n>> ar>L 1
~ I ~
5- 9'dg. o ~ 4-86 TRANSh(ISSIOX OF HEAT BY CONDUCTION AND CONVECTION HF'M i~P, 2.+~
/~~ Am Table 4A.6 Thermal Conductlvltles of Insutatlng Materials for High Temperatures Bulk density. hfaa hfaterial Ib per recap,F 100 F 300 F 500 F 1000 F ISOO F 1000 F eu fs deg Asbestos paper, lacninated....... 22. 400 0.038 0.041 Asbestos payer. corrugated...... 16. 300 0.031 0.042 Diatomaceous earth. silica, po)edec,.................... I b. 7 1500 0. 037 0. 045 0. 053 0. 074 Diatocnseeous earth, asbestos vainest' material.........
and bonding lb. 1600 0.045 0.049 0.053 0.065 Fiberglas block. PF612......... 2.S 500 0.025 0.039 Fiberglas block. PF614.. ~ ~ ~ ~ ~ ~ . 4.25 500 0.021 0.033 Fiberglas block. PF617.......... 9) , SOO 0.010 0.033 Fiberglas, metal caesh blanket, f900........ .. .. ~ ~ . ~ . ~....
~ ~ 1000 0.020 0.030 0.040 Cellubr gbss blocks, sve, . ~ ~ ~ ~ ~ ~ .. . .
~ ~ ~ ~ ~ 0.033 0.045 0.062 Ifydrous calcium silicate.
"ffaylo".......... ~... ~... . ~ I I. 0. 031 0. 038 0.045 85 ra cnagnesia....... ~ .. .
~ ~ ~ ~ ~ ~ 11. 0. 029 0.035 t hffec~uacrs 6her, blanket...., 3. 3000 O.ol I 0.028 0.042 0.075 O. Iolf 0.142 Potassiura titanate. fihecs... .. ~ ~ 71. 5 0.022 0.024 0.030 Roe'k wool, )oose................ 8-11 0. 027 0.038 0.049 0. ON 113. 3000 0. 108 0. 119 0. 163 0.117 Table 4,4.7 Thermal Conductance across Air Spaces Brul(h) (fr )-ReAective insulsuon Direetioa Temp hf san Aluminum Ordinary
~ urlaeee, Aic spare. in of ditf, temp, ~ urfaees, non.metallic, heat Oow deg F deg F ~ ~ 0.05
~ ~ 0.90 Hohsontat, I( 4 across. Upward lb. 80. 0.60 1. 35 Vertical, sl"4 across......... Across 20. 80. 0.49 l. I '9 Hocicontal. )f across...~..... Downs)acd 20. 75. 0.30 I. 08 Hocisontat, 4 aecoss.......... Downward lb. 80. 0. 19 0. 93 Values of K for N Rows Deep h)' 2 3 4 5 6 7 10 K 024 025 0.17 0. 29 0.30 0,31 0.31 0,33 Oss Flew Normal to a Single Tube, D,G/frl from 1000 to I'or I'ranging from100to 1,0001bof water perh per f1 (each side).
50.000: 030CiG s/(D)o (4A.ya) Water Row In Layer down Vertical Tubes, w/xD ) 500 h 120F)fs (4A.9s) Fluid Flow Normal to a Bank of Staggered Tubes, D,G~/frl from 2000 to 40.000:
'~ K ~ 'lrs
'4AJ0 Os Heat Transfer to Oases Fiowing st Very High Velocities If a nonrcactivc gas. stream is brought to rest adiabatically, as at thc true stagnation point of a blunt body, the tcmperaturc risc will bc r
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RG&E Answers To The NRC's March 21, 1991 Station Blackout Questions Attachment 5 Containment Isolation Valves
Table 7-2 Containment Isolation lPage 1 of 6] Posttbn At Containment Penelrstlon Valve Normal Isolatbn JustNc ation Number Description Number Operatbn Maintained ]Per 874XI] Steam Generator Inspectbn / Malntenaree Fuel Transbr Tbbe Bird Locked dosed vkr Range bind gangs Charglrg Une To 8 Loop 3708 0 Check valve. 101 Safety fn]ectbn Pump 18 0'echarge 8708 80th camper>>nts sre 8898 check valve Alternate Charging To A CoM Leg Constructbn Fire Servloe Water Yes Locked dosed vh bind flange. Containment Spray Pump 1A Check valve. Reactor Coolant Punp A Seal Water 0 Check valve. Inlet 107 Sump A Dischuge To Waste Hddup 1723 0 Both components fal Tank 1728 0 dosed on loss of power. Reactor Coolant Punp Seal Water 313 0 Valve less than Return Une snd Excess LeMown To Valve3'bmeter. VCT dosed by ECA.O.O, U Step 8 Containment Spray Pump 18 8828 Check valve. 110a ]top) Reactor Coohnt Punp 8 Seal Water 0 Check valve. Inlet 110b (bottom) Safety In]ectbn Test Line 879 LC Locked dosed. ResMual Heat Removal To 8 Cold Leg 0 MOV 720 locked 0 dosed [breaker locked open], 958 fs not considered a CIV. 112 LeMown To NonregeneraUve Heat 20CA OiC All vabes except 427 Exchanger 2008 OjC fal dosed on foes of 202 C power. Valve 427 Is 371 0 not considered a CIV. 427 0 113 Safety In]ectbn Pump 1A Discharge 870A C Both components sre 889A 0 check valve@ 119 Standby Auxltary Feedwater Une To 9704A Containment boundary Steam Ger>>rator 1A 9705A b SG seoondary sMe and tubes. No contahment Isobtbn Is required Nlrogen To Accundators 0 AOV448 fels dosed OJC on bss ol power. VaNe 8823 Is a check valve. Pressurizer Relief Tank To Gas 0 AOV439 lais dosed Analyzer 0 onbss ol power. Manual valve 548 b not rrxtured to hotate. 121 a Nlrogen To Pressurizer ReBel Tank 0 Yes Valve 528 b a check LC valve. Manual valve 547 b bcked cbsed.
Table 7-2 Containment tsolation [Page 2 of 6J PosMon At Contalnmsnt Penetration Valve Normal hohtlon JustiOcatfon Number Description Number Operation Maintained [Per 87~I 121b Makeup Water To Pressurizer Relief 0 ACV40B fels dosed Tank OJC on k¹s of power. Vahre 529 Is a check valve. 121c Containment Presscxe Transmkter PT- PTAS NA Valve is k¹s than 945 1819A 0 3'hmeter. 121d Containment Pressure Transmkter PT- PT446 NA Valve h less than 948 1819B 0 3'hmeter. 123 (top) Standby Auxihry Feedwater Line To 9704B 0 Containment boNxfsry Steam Gcrnera'tof 1 B 9705B 0 b SC secondary side and tubes. No contahment Isolation req&ecL Reactor Coohra Drain Tank To Gas 1600A 0 ACV 160OA b not Analyzer Line 1655 0 cor¹kfered a CIV, but 1789 0 hh dosed on hss of power. Manual valve 1655 h not requked to bohte. Valve 1789 fels dosed on k¹s of power, 124a Excess Letdown Heat Exchanger 743 0 Valve 743 h a check Cooing Wahr Supply & Return 745 0 valve. AOV.745 fags dosed on loss of power, 124b Pc¹t Accident Alr Sarnph To 0 Fan 1569 LC Yes All four manual valves 1571 LC are locked cfoscKL 1572 LC 1574 LC Component Cooling Water From 0 Norvradkactive, Reactor Coohnt Pcznp 1B dosed4cop system. Vahre b dosed by ECA4.0, Step 8. Component Cooikql Water Rom 0 Non radioactive, Reactor Coohnt Pcznp 1A ck¹sd4oop system Vahe b dosed by ECA41.0, Step 8. 127 Component Cooing Water To Reactor 749A 0 Norvradk¹ctlve, Coohnt Pump 1A 75CA 0 dosed4oop system Component Cooling Water To Reactor 749B 0 Non radioactive, Coohnt Pump 1B 750B 0 dosed. loop system Reactor Coohnt Drain Tank And 1713 0 Yes Valve 1713 h a check Pressurizer Relief Tank To 1786 0 valve. ACVs 1788 Containment Vent Header 1787 0 and 1787 hg dosed 1793 LC on kes of power. Manual valve 1793 b hoked ckeeci Component Cooling Water From 814 0 Non.radioactive, Reactor Support Coofkvg dosed.hop system Valve b dosed by ECA41.0, Step 8. 131 Component Cooling Water To Reactor 813 0 Non.radloacUve, Support Coo0ng dosed4oop system Valve h dosed by ECA41.0, Step 8.
Table 7-2 Containment Isolation [Page 3 of 6] PosNon At Containment Penetration Valve Normal IsoMon JusNlcatlon Number Description Number Operation Maintained [Per 874N) Containment Mht-Prsge Exhaust 7970 OQ Both AOVs fal cbsed 7971 0 on k>>s ot power. Residual Hest Removal Pump Suctbn 701 MOV 701 bcked From A Hot Leg closed vb breaker behg locked open 141 Residual Heat Removal Pump 1A 850A 0 Yes MOV 850A b used for Suctbn From Srsrp 8 181 3A 0 bng.term coot ng and b normally dosed. Valve poskbn ls vertded every sNII vb 0.1LI 3, Step 5.9.71; therefore, valve kr considered locked dosed by adnfnbtrative cortroL MOV 181 3A Is bcked dosed vh Ihe breaker behg locked o pea 142 Reskfual Heat Removal Pump 18 8508 0 MOV 8508 Is used for Suctbn From Sump 8 18138 0 bng.term cooing and Is normaly dosed. Valve poskion Is verified every shift vh 0-ttt 3, Step valve b 5.9.72,'herefore, oonsldered locked dosed by adninistratlve cortroL MOV.18138 ts bcked dosed vh the breaker behg bcked opea 143 Reactor Coolant Drain Tank Discharge 1003A 0 Yes AII three AOVs fail Lhe 10038 0 dosed on k>>s ol 1721 0 power. 201 (top) Reactor Comparbnent Cooling Urete A 4757 0 Non-radbactive, 201 (bottom) And 8 4636 0 dosed.bop system 8 Hydrogen Recomblner (Rbt And 10768 LC Manual Valves 10768 Mrdn) 10848 LC snd 10848 are bcked 10211SI 0 dosed. Solenokl 1021 3SI 0 valves 10211SI and 1021 3SI fa1 cbsed on loss of power. Containment Pressure Transrnkters PT-947 NA All valves less than PT4I47 And PT~S PT4I48 NA 3'bmeter. 18190 0 1819D 0 Rost-Acckfent Air Sarrpte To 8 Fan 1563 LC Ail four manual valves 1565 LC afe locked closed. IMS LC 1568 LC Purge Supply Duct Bind Yes Locked dosed vb Fhrele bfrd Ssnge. AOV-5S69 falIs ck>>ed on k>>s of power. Hot Leg Loop Sample 0 Yes AOV4I65 b not 0 consklered a CIV. 0 Manual valve 9560 b not required to hobte. AOV~ fats dosed on bss of power.
Table 7-2 Containment Isolation lPage 4 of 6] PoslUon At Containment P<<netratlon Valve Normal IsotsUon JusUUcatlon Number Descrf ptbn Number OpefaUon Maintained (Per 67410) 206a (top) Steam Generator Inspecton I Locked Cbsed Via MaIntenance gt1nd Range Fuel Trar¹fer Tuba Bird Locked Cbsed Via Range Bgnd Range 207a (top) Chargkrg Une To B Loop 0 Check Valve 207b (bottom) Safety In(ectbn Pump 1B Discharge 870B 0 Both Components Are 889B 0 Check Valves 209 (top) Alternate Charging To A Cold Leg Check Valve 209 (bototm) 210 Oxygen Makeup To A 8 B 1080A LC Yes Marwal valve 1080A R~rs 1021 4S 1021 481 0 0 bckad dosacL Solenokl valves 1021 SS C 1021 4S, 1021 4SI ~ 1021 SSI 0 1021 5S, and 1021 5S1 fal dosed on loss ol power. Locked dosed vb bind flange AOV. 5879 fels ck¹ad on k¹s of power. Auxtbry Steam Supply To 8151 LC Both manual vahes Containment 81 65 LC are kxked dosed. Auxlbry Steam Condensata Retrsn 81 52 LC Both manual valves 8175 LC are locked dosecL A Hydrogen Racombiner (Riot 8 Main) 1076A LC Mawal valves 1078A 1084A LC snd 1084A are bcked 10205SI 0 dosed. Sdenokl 1020981 0 valves 10205SI and 10209SI fai cbsed on bss ol power. 1598 0 Manual valve 1597 b 1597 0 not rrxtukad to bdate. AOV.1 597 fels ebs ed on bss of power. 305b (top) Conbdnment Alr Sampb lrtet 1598 0 Both AOVs fal dosed 1599 0 onbss of power. Contrdnment Alr Sample Post.Accklent 1554 LC All six manual valves 1556 LC ara locked dosed. 1557 LC 1559 LC 1560 LC 1562 LC Fire Servke Water AOV-9227 fels ck¹ed onbss of power. Valve 9229 Is a check valve. Servloe Water To A Fan Coobr LO Yes Non-radk¹ctlva, dosed-bop system. Mkrl.Ptsge Srsrply 7445 OrC Both AOVs fal dosed 7478 OrC on k¹s of power. 31 Oa (bottom) Service Alr To Corralnment 7141 LC Msrwal valve 7141 Is 7226 0 bckad cbsrxL Valve 7228 b a check valve.
Table 7-2 Containment Isolation [Page 5 of 6] Posltfon At Containment Penetration Valve Normal Isobrtlon JustNcatlon Number Description Number Opefathn Maintained ]Per 87~] 310b (top) I strument Air To Containment 0 ADV5392 fels cbred 0 on loss ol power. Valve 5393 Is a check valve. 311 Servke Water From B Fan Coohr LO Non rsdkectlve, dosed 4oop system 312 Servke Water To 0 Fan Cooler LO Yes Non radlosctire, dosed 4oop system 313 Leakage Test Depressurlzstkn Bind Locked cbsed vh Range bind fbnge. 7444 315 Servk>> Water From 0 Fsn Cooler LO Non-radhacUve. cfosed4oop system. 318 Service Water To B Fan Cooler LO Non radioactive, cbsed4oop systera 317 Le4ulge Test Supply Bind Locked dosed vh Range bind fhnge. 7443 318 Deadw4gtd Tester Locked dosed. Penetrathn k welded shut. 319 Servke Water From A Fsn Cooler LO Non-radioactive, chsed4oop system. Servke Water To C Fan Cooler 4641 LO Non-radloacUve, dosed-loop system A Steam Generator B~ 5701 5738 0 0 Manual valve 5701 ls not requLred to Isohtm ADV4738 fels cbsed on bss of power. B Steam Generator Bhwdown 5702 0 Manual valve 5702 5737 0 not requked to Isohte. AOV4737 fats cbsed on bss ol power. Servke Water From D Fsn Cooler LO Non-radhacUve, closed-loop system Demheratked Water To Contahment 8418 ADV 8418 fals cbsed 8419 on loss of power. Valve 8419 kd a check valve. Cont4nment Pfess lte Trans Intters PT-944 NA All valves are less Pl'-944. PT.949, and PT-950 PT-949 NA than 3'tsmeter. PT-950 NA 1819E 0 1819F 0 1819G 0 Hydrogen Manner Instnrnerdatbn 921 All fora adenoid Lhes 922 valves fsl chsed cn 923 bss ol power. 924
Table 7-2 Containment Isolation [Page 6 of 6] Posttkm At Containment Penstratton Valve Normal hohrtlon JustNcaOon Number Descrlptkm Number Operation Malnlalned Pre r 97410) 401 Mstn Steam From Steam Generator A 3505A 0 Contr4nment boundary 3507 0 h SG secondary dde 351 7 0 snd tubes. No 351 9 0 contahment holation 3521 0 h requlr<<l, Main Steam From Steam Generator 8 3504A 0 Containment botsvlary 3509 0 h SG secondary side 351 B 0 and tubes. No 351 9 0 contahment Isohtion 3520 0 h required, Feedwster Une To Steam Generator A 3993 0 Containment boundary 3995 0 h SG secondary side 40000 0 snd tubes. No 4003 0 contshment Isolathn 4005 0 h required. 4011 0 Feedwater LIne To Steam Generator 8 3992 0 Containment boundary 3994 0 h SG secondary side 4000D 0 snd tubes. No 4004 0 contahment lsoladon 400B 0 h requtred. 4012 0 Personnel Hatch Locked dosed. Penetration ls leak tested. Equfpment Hatch Locked dosed. Penetration h leak tested.
RG&E Answers To The NRC's March 21, 1991 Station Blackout Questions Attachment 6 TREAT Analysis of Station Blackout
STATION BLACKOUT TREAT SIMULATION Summary of Signif icant Events and Operator Actions During the Analysis. Time (sec) Event/Action 0.0 Loss of all AC resulting in reactor trip, RCP coastdown, loss of main
'feedwater, and turbine trip.
500 (8.3 min.) RCS loop flow reaches NC flow and remains there for duration of the analysis. 1000 (16.7 min.) Pressurizer empties, RCS pressure decreases to P of hot leg. SG NR level returns on scale. 1300 (21.7 min.) Aux. feedwater reduced, from 400 gpm per SG to 25 lb/sec. (180 gpm) per SG. 2000 (33.3 min.) RCS pressure reaches P for T Aux. feedwater reduced to 5lb/sec. (36 gpm) per SG. RCS begins heatup and re-pressurization to ARV setpoint. 2500 (41.7 min.) Aux. feedwater reduced, to 0. 3000 (50 min. ) ARVs open; terminates heatup. ARVs remain open for duration of the analysis removing decay heat. 3500 (58 min.) RCS pressure reduced to P of T Upper Plenum "collapsed" level decreases as voids appear. 5000 (1.4 hr.) Aux. feed increased to 36 gpm per SG. 5500 (1.53 hr.) Aux. feed increased to 72 gpm per SG. 7200 (2.0 hr.) Aux. feed reduced to 57 gpm per SG. 8000 (2.2 hr.) Aux. feed stopped. Upper Head reaches saturation and. "collapsed" level decreases as voids appear. 14,400 (4.0 hr.) Analysis terminated by starting of one SI pump.
Conclusion Break flow decreases from 6.6 lbs/sec. (63 gpm) to 3.45 lbs/sec. at 4 hr. following changes in RCS pressure. Voiding appears in the upper head and upper plenum. The voids are condensed in the SG. Natural circulation flow is never lost. Voiding in the upper head is approximately 50.5% by volume after 4 hr. Voiding in the upper plenum is approximately 46.5% by volume after 4 hr. aWa~l74
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58.8 48.8 38.8 28.8 18.8 4688.8 6888.8 16668.8 12668.8 14688.8 Tl/E (SEC) STATIOH MXOUT
48.8 INfL(55) z.e 58.8 15.8 18.8 5.8 259.8 4668.8 6868.8 8668.8 14NN.e TIE (KC) STATIOH ELACKGUTlRECKGY
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h RG&E Answers To The NRC's March 24, 1991 Station Blackout Questions Attachment 7 Quality Assurance Classification Of Station Blackout Equipment
Station Blackout Coping Equipment QA Status [Page 1 of 2] Quality Asswance Equipment ID Descrlpdon Classtrrcsthn Condense'te Storage AFW Supply To SGs Satety Significant Tanks AFW Supply To SGs Safety Chas 3 PLOI I TDAFWP DC Lube Oil AFW Supply To SGs Safety Chas 3 Pump MOVs 3504A, 3505A TDAWFP Steam Supply AFW Supply To SGs Safety Chas 2 MOV~ TDAFWP Discharge AFW Rcw To SGs Safety Chas 3 Valve AOVs 4297, 4299 TDAFWP Fhw Control AFW Fkrw To SGs Safety Class 3 Valves AOVs 351 6, 3517 hen Steam Isolation Decay Hest Removal Safety Chas 2 Valves SVs 3509.351 5 SG Steam Retef Valves Decay Heat Removal Safety Chas 2 PCVs 3410, 3411 SG Atmcspherh Relief Decay Hest Removal Safety Chas 2 Valves Nr Ihckup To ARVs Backup Gas Supply To Decay Heat Removal SG ARVs 3410S, 3411S ARV Solsnolds Decay Hest Removal Safety Signlgcant PCVs 9012, 9013 Nr Supply Presstze Decay Heat Removal Safety Slgni6cant Rag tfadng Valves PCVs 3410A, 3411A Nr Supply Preset!a Decay Hest Removal Safety Slgrvgcant Rag tfagng Valves PCVs 15003, 15004 N, Supply Presstze Decay Heat Removal Safety Slgn5cant Regrfsgng Valves MORI 3 RC Pump Seal Return RC Pump Seal Protection Safety Chas 2 Isolagon Valve Batteries 1A, 18 Emergency Power Supply Safety Chas 3 DC Power Distr huthn 125 VDC Power Emergency Power Supply Safety Chas 3 Panels IA, 18 Dhtrfbubon Irrverters IA, 18 Inverters Emergency Power Supply Safety Chas 3 Instrument Buses 1A, 18 120 VAC Vital Buses Emergency Power Supply Safety Chas 3 TEs 409A. 8 and RCS Hot 5 Cold Leg Ffark Status Monitoring Safety Class I 4'IOA, 8 Temperature PT~ Pressurtzer Presswe Safety Chas 2 LTs 426, 433 Pressurizer Level Safety Chas 2 LTs 460, 470 SG I A. 18 Level Rant Status Monkorlng Safety Chas 2 PTs 469, 479 SG 1A, 18 Pressure Rant Status Monkofng Safety Chas 2 NE-31 ~ NM2 Source Range Rux Pbnt Sbtr>> Monkorlng Safety Chss 3 Detectors Rara Status Monkorlng Safety Chas 3 LTs 2022A, 20228 CST Level Plant Status Monkorfng Safety Class 3
w Ig. Station Blackout Coping Equipment QA Status tPage 2 of 2] Qualky Asstsar>>e Eqtiprnent ID Casa@cation PCH01 8 Chargkig Pump 18 Maktn4r To RCS Safety Cbss 2 R&gfC Charging Pump 1C Makeup To RCS Safety Cbss 2 Bus 18, Unit 158 Charghg Pump 18 Power To PCH01 8 Safety Cbss 3 Crcuit Breaker Bus 18, Unit 15C Charging Pump 1C Power To PCH01C Safety Cess 3 Croit Breaker Bus 18 480 V AC Bus Power To Charging Pump Safety Cbss 3 Bus 18, Urit 128 Bus 15/Bus 18 Tle Power To Charging Puirp Safety Casa 3 Clrctit Breaker Bus 15 480VAC Bus Power To Charging Pump Not Nudear Safety Bus 15, Unit 3A Bus 15/TSC Ile Crcuft Power To Charging Purrp Not Nudear Safety Breaker Technical Support Power To Charging Pump Safety Significant Center Diesel Technical Support Power To Charging Puny Safety Slgniscsnt Center Generator TSC1 TSC Static Transfer Power To Charging Pump Safety Significant Switch Diesel Driven Rre Water Alternate Coosng Water Safety Slgnigcant Pump To Tistine Driven AFW Pump Outside Condensate Alternate AFW Supply To Not Cbssffbd Storage Tank SGs 957aa, 9573A, 958BA, PAuwsl Valves Alternate AFW Sip ply To Not CbssiY>>d 9584A, 9586G, 9584G, SGs From TCD03 9510A, 4048, 9509C, 9516D, 9509F, 95098 4078, 4079 Manual Vabes Alternate AFW Sg>pfy To SGs From Fire Water System 2291, 7310, 4318A, 2313 Manual Valves Alternate AFW Steeply To SGs From City Water System 2ih'ose(s) Fire Hoses Alternate AFW Stpply To SGs From Fire Water System Hydrants, Hose Statlcns Fire Water Supply Points Alternate AFW Stppfy To SGs From Fire Water System 1'ose Alternate AFW Sis>ply To Appendic R SGs From Ciity Water System}}