ML17262A453

Devonrue Calculation Re Plant Turbine Driven Auxiliary Feedwater Pump Area Ambient Temp Rise

ML17262A453
Person / Time
Site:	Ginna
Issue date:	06/05/1990
From:	ROCHESTER GAS & ELECTRIC CORP.
To:
Shared Package
ML17262A448	List: ML17262A447 ML17262A449 ML17262A451 ML17262A452 ML17262A453 ML17309A460
References
NUDOCS 9104300406
Download: ML17262A453 (62)

Text

RG&E Answers To The NRC's March 21, 4991 Station Blackout Questions 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.

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Subject st 7P

/ Pl/ F'f-knht T

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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 ofthe 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 TDAFWpump 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 TDAPVpump 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 willbe treated similarly in this calculation.

5.

The initialwall temperatures are assumed to be in equilibrium with the initialair 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 of220'F.

Additional assumptions are stated throughout the body of this calculation.

Devonrue Calculation

Subject:

Project No.8-9025.00 Date: 5/28/90 Page 2 of 12

1. NUMARC87-00, "Guidelines and Technical Bases forNUMARCInitiatives Addressing Station Blackout at LightWater 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&IDDrawing No. 33013-1231, Rev. 13, Main Steam.

6. Ginna Station P&IDDrawing 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 ofAuxiliary Feedwater Pump Turbine 10.

Gilbert Associates, BillofMaterials, for Steam Driven AuxiliaryFeedwater pump and Steam Turbine Drive.

Devonrue Calculation

Subject:

Project No.8-9025.00 Date: 5/28/90 Page 3 of 12 The objective ofthis calculation is to determine the ambient temperature rise in the TDAPYV pump area of the Intermediate Building during a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SBO-induced loss of ventilation.

Because the Ginna Station Blackout coping duration is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the simplified methodology provided in NUMARC 87-00, Section 7 willbe 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 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> loss ofventilation. As stated in the previous section, the surface temperature of the solid concrete block walls willalso be assumed to remain constant.

Section 7 of NUMARC87-00 presents the followingsimplified equation for use in evaluatin'g a four hour loss ofventilation:

Tait Tw+ [QIA]3~4 where:

Tair is the resultant ambient air temperature in the TDAPVpump area(the north portion ofel. 253'-3" of the Intermediate Building}after 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; 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 NUMARC87-00:

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 TDAFWpump an:a ambient temperature:

1.

Sum the wall surface areas to obtain A in square meters. For conservatism, the surface ama ofthe ceiling willbe neglected as it is constructed of corrugated metal attached to the pouted concrete floor slab ofthe 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 willbe considered.

3.

Conservatively estimate the heat generation rate, Q, in the TDAFWpump area. This willbe done by considering heat rejected by hot piping and equipment using the equations given on p. 7-19 ofNUMARC87-00. Heat rejected by operating electrical equipment willalso 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 willbe 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

Subject:

Project No.8-9025.00 Date: 5/28/90 Page 5 of 12 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 =

113.33'herefore, length = (113.33/360) m (33.68) = 33.33 m; 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

Subject:

Project No.8-9025.00 Date: 5/28/90 Page 6 of 12 3.35 3.05 3.04 28.04 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

Subject:

Project No.8-9025.00 Date; 5/28/90 Page 7 of 12 Step 2: Determine the initial wall temperature, T; in 'C The initial wall temperature willbe 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 ofarea 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 ofthe 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

Subject:

Project No.8-9025.00 Date: 5/28/90 Page 9 of 12 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 followingconstant 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 Billof Materials, previously referenced, which gives exit steam conditions.

The results obtained when applying the above equation are summarized in Table 1.

TABLE I CALCULATIONOF INSULATED SURFACE TEMPERATURE (Ts)

Description Ti

('F) ri Ins.

( t t) thk.

(tt) rs In(rs/ri) Ts( F)

(tt) 1/2" Tb. Stm sup.

550 6"Tb. Stm sup.

550 0.02 0.125 0.145 0.276 0.2083 0.484 1.981001 0.562304 4" Tb. Exh.

240 0.188,0.125 0,313 0.509761 146

~ 51 148.47 126.93 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 Stm Turbine 550 1.17 0.083 0.203 0.292 1.462 0.52571 4 N/A 1 30.57 139

Devonrue Calculation

Subject:

Project No.8-9025.00 Date: 5/28/90 Page 10 of 12 Using the results ofTable 1, the heat generation, Q, can be calculated from the following equation found in Section 7 ofNUMARC87-00:

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 CALCULATIONOF 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.

6" Stm. sup.

1/2" Tb. exh 3/4" Tb. Exh.

4" Tb. Exh 4" Tb. Exh.

8" Tb. Exh 8" Tb. Exh.

1 1/2 Htg. Stm 8

Htg. Stm.

2-1/2" Htg Stm 28" Stm TB.

T+T valve Governor Vlv 146.5 148.5 240 240 1 26.9 240 128.7 240 1 29.1 125.4 130.6 139 550 550 336.767 337.856 388.706 388.706 325.889 388. 706 326.85 388.706 327.067 325.044 327.911 332.594 560.928 560.928 1 5 4.57 0.29 11 0 33.5 0.968 1 00 30.5 0.042 20 6.1 0.063 1 4 4.27 0.626 60 1 8.3 0.333 7

2.13 0.97 20 6.1 0.667 8 9 27.1 0.326 52.4 1 6 0.97 69.4 21.2 0.406 NA NA 3.05 1.25 0.38 0.167 1.7 0.52 1

0. 09

21. 95 0.3 23.04

0. 01 73.89

0. 02 73.89 0.19 11.07 0.1 73.89 0.3 12.03 0.2 73.89 0.1 12.25 0.3 10.22 0.12 13.09 0.93 17 ~ 77

0. 05 246. 1 0.3 246.1

3. 042E+09 3.209E+09 1.301E+to 1.301E+10 1.459E+09 1.301E+10 1.593E+o9 1.301E+10 1.623E+09 1.343E+09 1.742E+09 2.417E+09 8.918E+10 8.918E+10 677.39 16629 3680.4 1042.6 558.62 14620 470.98 9471.8 2171.2 2884.2 2259. 6 400 838.4 6401.8 Total Q(watts)= 62105

Devonrue Calculation Project No.8-9025.00 Date: 5/28/90 Page 11 of 12

Subject:

Review ofTable 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 Billof 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 TDAPVpump atea is:

Q = 62,105

+ 1,000

= 63,105 watts Step 4: Calculate the ambient temperature This step is accomplished by applying the NUMARC87-00 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 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> blackout duration due to its configuration and the lack ofsignificant 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 NUMARC87-00:

Tair Tw+ (Q3/4/[A3/4 + 16.18 F 0 8653)) where;

Devonrue Calculation

Subject:

Project No.8-9025.00 Date: 5/28/90 Page 12 of 12 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+

Q)Pf FbtJ /~

Table 3.11-1 ff&kAGae&Z P lg/

ENVIRONMENTAL SERVICE CONDITIONS FOR EQUIPMENT DESIGNED TO MITIGATE DESIGN-BASIS EVENTS INSIDE CONTAINMENT Normal 0 erationr Temperature Pressure Humidity Radiation 60'F to 120'F 0 psig 50X (nominal)

Less than 1 radlhr general.

Can be higher or lower near specific components.

Accident Conditions LOCA S+c~ - Mvu. ~~

Temperature Pressure Humidity Figure 6.1-2 (286'F maximum)

Figur e 6. 1-1

( 60 ps ig design) 100l 40 PSlg Radiation Tables 3.11-2 and 3.11-3; 1.43 x 10 rads gamma 7

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.

, AUXILIARYBUILDING Normal 0 eration:

Temperature Pressure Humidity Radiation 50 F to 104 F

0 psig 60X (nominal)

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 Pressure Humidity 50F to 104 F

0 psig 601 (nominal) 3 ~ 11-19 REV 4 12/88

1 ~

lI: "

V jl 4-90 TRANSMISSiON OF HEAT BY CONDUCTION AND CONVECTION

//

~/

/

~d>>~/

~

appears to be the best available. Zubcr also performed an anal-obtained at an overall temperature differcncc of 60 F. I

-0 ysis for subcoolcd liquids arid PfoPosed a modification which is this Point, the coefficient a Aux dccrcasedraPid}y, a~

ud also in cxcel1cnt agreement withcxperimcnt:,

ing the values obtained in superheating vapor, scc Eq cats 1/I Add (q/A) c m Ktp,p + Cyg, /)) [

fcrgtgAPc Pn) 1 /

Pt Pa Pl Pv>

c 1 + 5.33(pcC jk,)'/'(t, t/)[ gt(pc p,)p,]

Zuber's hydrodynamic analysis of the Leidenfrost point yields 1/a (q/A) m K~

0.144 < Ka < 0.17?

l ega'hc-P.)

. (4A.I4d) gi PP O.4 i%3 D.l 0

Berenson finds bcltcr agrcemcnt with thc data if K, m 0.09.

For very small wires, thc heat flux will cxcccd that predicted by this flat plate formula. A reliable prcdiction of thc critical tempcraturc is not available.

For nuc1eatc boiling accompanied by forced convection, the heat flux may bc approximated by thc sum of the heat Aux for pool boiling alone and the heat Aux for forced convection alone.

This proecdurc will not be satisfactory at high qualities. and no satisfactory correlation exists for thc maximum heat Aux.

For a given liquid and boiling pressure, thc nature of Ihc surface may substantial1y inAucnec the flux at a given (At),

Table 4.4.10. Thcsc data may bc used as rough approximations for a bank of submerged tubes.

Film coefficients for scaic deposits arc given in Tab1e 4.4.g.

For forced~clou eva poratoct, vapor binding is also encoun.

tered. Thus with liquid benzene cntcring a 4.pass stcam jack.

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 For comparison, in a natural convection evaporator, a In~.

mum Aux of73,000 Btu/h/ft was obtained at (ht),of 100 F ~

cotnblned convection and Radiation coetticlentb in m "@

sottte,

'ases of heat loss, such as that from bare and insulated p p" @

where loss is by convection to the air and radiation to the teafhg>>

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}

nu'oss thus becomes q m (h, + h,)A(dt),

(4A.IS) j."-

wherc (c) t), is the temperature difference, deg F, between tfte ~

surface of thc hot body and lhe walls of thc space. fn evaiuat:

ing (h, + h,), h, should bc calculated by the appropriate con vection formula [see Eqs. (4A.llc)to(4A.llg)) and h, from the ui equation h, m 0.00685c(7/100)

T Va:

ofias v

i>>ii 540.4) d, enc}ostng i

mttfj,+kI

'i'at

~ ~

1, II I

~

I~)

~

~

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~

tI~~

~

I Table 4.4.10 Maximum Flux and Corresponding Overall Temperature Difterence tor Uquidb Boiled at 1 atm with a Submerged Horizontal Steam.Heated Tube Uqutd Aluminum Chrumiom-1>lated c opt>cr I

Smt I

9'A

>/!A 1000

(

1000 ttit).

9/A Ethyl acetate....

Bet>acne........

Ethyl alcohol....

h'lethyl alcohol..

Distilled icatcr..

41

$ 1 5$

80'b I 10'173 124 I I0 3$0 100 45 I IO 7$

82 1$ $

410 100 I IO 1$0 Nominal I ipe diam in.

(a/I>. tenipccatuce dill<<cence. deja F, ttoo> autiaee to room so

} 100, Iso 200 2so 300 '00 '00 e00,'700 '00 1900 I 1000 f 1100 1200 I

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$

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 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 1.76 2.06 2,29 2.60 2.89 3.20 3.88 4.68 $.57 b.eo 7.73 9.05>10.50 12.10 IS.93 1.71 2.01 2.24 2.$ 4 2.d2 3.13 3.d3 4.411$.50;6.52 7.6S 8.96'10.42 12.03 13.dc 1,64 1.93 2. IS 2.4$ 2.72 3 03 3.10 4.48 $.31'6 ~ 39 7 ~ 52 bvbS'10.28 )1.90 13.70

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2 8

12 24 FLAT Pa>>Tea vertical......

~. ~. ~."

HFU..........""" ~

}

HFD..........

~.."",

IIFU, ho>>i><>nial, (>>ting up>v aid; I IF D, hodaoniit, Acing do>>> n>> ar>L Table 4v4 1 0 Valued ol (hc + hp)

For horizontal bare or insubted star>dard steel pipe of various site:s and for fiat plates in a room at 80'F

...~re

,,V>>.Cibt '

>'Jp, 1

~

I

~

4-86 TRANSh(ISSIOX OF HEAT BY CONDUCTION AND CONVECTION 5-9'dg.

o ~

HF'M /~~ A m i~P, 2.+~

Table 4A.6 Thermal Conductlvltles of Insutatlng Materials for High Temperatures hfaterial Bulk density.

Ib per eu fs hfaa

recap, deg F 100 F 300 F 500 F 1000 F ISOO F 1000 F Asbestos paper, lacninated.......

Asbestos payer. corrugated......

Diatomaceous earth. silica, po)edec,....................

Diatocnseeous earth, asbestos and bonding material.........

Fiberglas block. PF612.........

Fiberglas block. PF614..

~ ~ ~ ~ ~ ~.

Fiberglas block. PF617..........

Fiberglas, metal caesh blanket, f900........

~..

~.. ~ ~. ~. ~....

Cellubr gbss blocks,

sve, vainest'

. ~ ~ ~ ~ ~ ~..

~ ~.

~ ~. ~

Ifydrous calcium silicate.

"ffaylo"..........~... ~...

~.

85 ra cnagnesia.......

~.. ~ ~.

~

~

~ ~

hffec~uacrs 6her, blanket....,

Potassiura titanate. fihecs...

~..

~

Roe'k wool, )oose................

22.

16.

400 0.038 0.041 300 0.031 0.042 I I.

11.

3.

71. 5 8-11 113.

3000 3000

0. 031

0. 029 O.ol I

0. 027

0. 038 0.035 0.028 0.022 0.038 0.045t 0.042 0.024 0.049

0. 108 0.075 0.030

0. ON

0. 119 Ib. 7 1500

0. 037

0. 045

0. 053

0. 074 lb.

1600 0.045 0.049 0.053 0.065 2.S 500 0.025 0.039 4.25 500 0.021 0.033 9)

, SOO 0.010 0.033 1000 0.020 0.030 0.040 0.033 0.045 0.062 O. Iolf 0.142

0. 163 0.117 Table 4,4.7 Thermal Conductance across AirSpaces Brul(h) (fr )-ReAective insulsuon Aic spare. in Direetioa of heat Oow Temp

ditf, deg F hfsan

temp, deg F Aluminum

~urfaees,

~ ~ 0.05 Ordinary

~urlaeee, non.metallic,

~ ~ 0.90 Hohsontat, I(

4 across.

Vertical, sl"4 across.........

Hocicontal. )f across...~.....

Hocisontat, 4 aecoss..........

Upward Across Downs)acd Downward lb.

20.

20.

lb.

80.

80.

75.

80.

0.60 0.49 0.30

0. 19

1. 35

l. I '9 I.08

0. 93 Values of Kfor N Rows Deep h)'

2 K

024 025 3

4 0.17

0. 29 5

6 7

10 0.30 0,31 0.31 0,33 h,

150(F/D ) cis (4A.9)

Oss Flew Normal to a Single Tube, D,G/frl from 1000 to 50.000:

030CiG s/(D)o (4A.ya)

Fluid Flow Normal to a Bank of Staggered Tubes, D,G~/frl from 2000 to 40.000:

'lrs Os

'~ K ~

'4AJ0 Water Flow Normal to a Bank of Staggered Tubes, D,G~/frl from 2000 to 40,000 h370(l + 0.0067rl) V,'s/(D )os for bafllcd cxchangers, to allow for Icakagc of fluids around thc bafllcs, usc 60 percent of the values of h from Eq. (4A2I);

for tubes in linc, deduct 25 percent from Ihe values of hgiven by Eq. (4.4.8).

Water Row in Layer Form over Horfzontat Tubes, 4P/Ir (

2100 I'or I'ranging from100to 1,0001bof water perh per f1 (each side).

Water Row In Layer down Vertical Tubes, w/xD) 500 h

120F)fs (4A.9s)

Heat Transfer to Oases Fiowing st Very High Velocities Ifa nonrcactivc gas. stream is brought to rest adiabatically, as at thc true stagnation point of a blunt body, the tcmperaturc risc willbc I, r w V'/2g+Cr (4.4.9b) where I, is thc stagnation temperature and r is the tempera.

turc of the free stream moving at velocity V. At every other point on thc body, the gas is brought to rest partly by prcssure changes and partly by viscous effects in thc boundary layer. In general, this process is not adiabatic, cvcn though the body transfers no heat. Thc thermal conductivity of thc gas will transfer heat from onc layer of gas to anolher. At an insulated surface, thc gas tempcraturc willtherefore bc ncithcr thc frcc-strcam tcmperaturc nor thc stagnation tempcralurc. In gcn.

eral, thc risc in gas tcmpcraturc will be given by thc equation

~ ~

~ ~

~

v ~ >>>>>>55

~ aJ<<VL I A ) @bed

)

P-V<A5 ~ <~ BILL OF MATERIALS

. ='-;::7 er-4l'~-

<<','V 5

gestinghcu~e Atonic Po'e'er D'nisi "n

~ CIL)SN T)

(noches.ver Gas c) Elc"iric Corgor.vion)

Peed.

Vc~te>> SJ'st~i 3oberT Et'~"-tt G~~ F-'clear Po;;ed 3'i:a<ion r

8 al SY)58OL LPa>>051)CCI)

)5C SIIEf.T HO, LocATloN:

Pi<<sburgh )

Pa, ~

oAI w. o.

4155 cLIENT w. o.

En-33COO'ni.o.

1 OI) A)5fI TY OCSCRIPTION OS QATKRIAl ISSU OROKR NO P

Q s Hewing r'"."s 1"-;> c'nrc=

stc

'3~>

chrc

- sie 1 2lfi026 slensres 1 >-,> chr

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~

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~

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~

~

Diffu"Q s Pea>><<pgs Dj.~char5 Q f~<>

5<<

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p she>>

be furni>>h o, 4Q:vh i'he folio Qng'5 St

'LLL O ve bio "}'~g on T ye S

sjngl cnxlJ. rcauxre cern a'~ 29.7 lb"/i:pzhr "+ f)60 ))si, 10 p

':"aus

"".d 5C"o..

""b"nc sh;.3 bc r"."'

450 hg at 4575 rm.

TG ul binQ

$h b

su" "Q.b fo= quick ster7~>

~

5.

5

~<<5

~

~

TL'ine chal~

bQ iann she. I t' ul a Uooidfard oil r~1y ac" 'ag cons-an'I.

I governor, go;-e "or vM-;~ inte~M stc stra>>ncr b"".".c'.-, insu)='-.on c.u gacI' for 'n") casey, i"ch-0 r u ted h ~f co'Qli) gp tw (2) 4 i]2 v 'TcssurQ

gauges,

""d. tr'p ar." i"""'-tie va':c l~t sritc'~.

Tu>>bi"c Co" i"zc"ion:

~r' 5

Casing PmfV Bucket. @heel" Blade" Cerbon stQQ A3>o'J s'uee l

Pored.

si~QQ1 Stress S.eel

~ ~.. ~'5,~

he <<5>>

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RG&E Answers To The NRC's March 21, 1991 Station Blackout Questions Containment Isolation Valves

Table 7-2 Containment Isolation lPage 1 of 6]

Penelrstlon Number Description Valve Number Posttbn At Normal Operatbn Containment Isolatbn Maintained JustNc ation

]Per 874XI]

Steam Generator Inspectbn /

Malntenaree 101 Fuel Transbr Tbbe Charglrg Une To 8 Loop Safety fn]ectbn Pump 18 0'echarge Alternate Charging To A CoM Leg Constructbn Fire Servloe Water Bird Range 3708 8708 8898 0

Yes Locked dosed vkr bind gangs Check valve.

80th camper>>nts sre check valve Locked dosed vh bind flange.

107 Containment Spray Pump 1A Reactor Coolant Punp A Seal Water Inlet Sump A Dischuge To Waste Hddup Tank Reactor Coolant Punp Seal Water Return Une snd Excess LeMown To VCT U

1723 1728 313 0

0 0

0 Check valve.

Check valve.

Both components fal dosed on loss of power.

Valve less than 3'bmeter.

Valve dosed by ECA.O.O, Step 8 110a ]top)

Containment Spray Pump 18 Reactor Coohnt Punp 8 Seal Water Inlet 8828 0

Check valve.

Check valve.

110b (bottom)

Safety In]ectbn Test Line ResMual Heat Removal To 8 Cold Leg 879 LC 0

0 Locked dosed.

MOV720 locked dosed [breaker locked open],

958 fs not considered a CIV.

112 LeMown To NonregeneraUve Heat Exchanger 20CA 2008 202 371 427 OiC OjC C

0 0

Allvabes except 427 fal dosed on foes of power. Valve 427 Is not considered a CIV.

113 Safety In]ectbn Pump 1A Discharge 870A 889A C

0 Both components sre check valve@

119 Standby Auxltary Feedwater Une To Steam Ger>>rator 1A 9704A 9705A Containment boundary b SG seoondary sMe and tubes.

No contahment Isobtbn Is required Nlrogen To Accundators 0

OJC AOV448 fels dosed on bss ol power.

VaNe 8823 Is a check valve.

121 a Pressurizer Relief Tank To Gas Analyzer Nlrogen To Pressurizer ReBel Tank 0

0 0

LC Yes AOV439 lais dosed onbss ol power.

Manual valve 548 b not rrxtured to hotate.

Valve 528 b a check valve.

Manual valve 547 b bcked cbsed.

Table 7-2 Containment tsolation [Page 2 of 6J Penetration Number Description Valve Number PosMon At Normal Operation Contalnmsnt hohtlon Maintained JustiOcatfon

[Per 87~I 121b Makeup Water To Pressurizer Relief Tank 0

OJC ACV40Bfels dosed on k¹s of power.

Vahre 529 Is a check valve.

121c 121d Containment Presscxe Transmkter PT-945 Containment Pressure Transmkter PT-948 PTAS 1819A PT446 1819B NA 0

NA 0

Valve is k¹s than 3'hmeter.

Valve h less than 3'hmeter.

123 (top)

Standby AuxihryFeedwater Line To Steam Gcrnera'tof 1 B 9704B 9705B 0

0 Containment boNxfsry b SC secondary side and tubes.

No contahment Isolation req&ecL Reactor Coohra Drain Tank To Gas Analyzer Line 1600A 1655 1789 0

0 0

ACV 160OA b not cor¹kfered a CIV, but 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 Cooing Wahr Supply & Return 743 745 0

0 Valve 743 h a check valve. AOV.745 fags dosed on loss of

power, 124b Pc¹t Accident AlrSarnph To 0 Fan Component Cooling Water From Reactor Coohnt Pcznp 1B 1569 1571 1572 1574 LC LC LC LC 0

Yes Allfour manual valves are locked cfoscKL Norvradkactive, dosed4cop system.

Vahre b dosed by ECA4.0, Step 8.

127 Component Cooikql Water Rom Reactor Coohnt Pcznp 1A Component Cooing Water To Reactor Coohnt Pump 1A Component Cooling Water To Reactor Coohnt Pump 1B 749A 75CA 749B 750B 0

0 0

0 0

Non radioactive, ck¹sd4oop system Vahe b dosed by ECA41.0, Step 8.

Norvradk¹ctlve, dosed4oop system Non radioactive, dosed. loop system Reactor Coohnt Drain Tank And Pressurizer Relief Tank To Containment Vent Header 1713 1786 1787 1793 0

0 0

LC Yes Valve 1713 h a check valve. ACVs 1788 and 1787 hg dosed on kes of power.

Manual valve 1793 b hoked ckeeci Component Cooling Water From Reactor Support Coofkvg 814 0

Non.radioactive, dosed.hop system Valve b dosed by ECA41.0, Step 8.

131 Component Cooling Water To Reactor Support Coo0ng 813 0

Non.radloacUve, dosed4oop system Valve h dosed by ECA41.0, Step 8.

Table 7-2 Containment Isolation [Page 3 of 6]

Penetration Number Description Valve Number PosNon At Normal Operation Containment IsoMon Maintained JusNlcatlon

[Per 874N) 141 Containment Mht-Prsge Exhaust Residual Hest Removal Pump Suctbn From A Hot Leg Residual Heat Removal Pump 1A Suctbn From Srsrp 8 7970 7971 701 850A 181 3A OQ 0

0 0

Yes Both AOVs fal cbsed on k>>s ot power.

MOV701 bcked closed vb breaker behg locked open MOV850A b used for bng.term cootng and b normally dosed.

Valve poskbn ls vertded every sNIIvb 0.1LI3, Step 5.9.71; therefore, valve kr considered locked dosed by adnfnbtrative cortroL MOV 181 3A Is bcked dosed vh Ihe breaker behg locked opea 142 143 Reskfual Heat Removal Pump 18 Suctbn From Sump 8 Reactor Coolant Drain Tank Discharge Lhe 8508 18138 1003A 10038 1721 0

0 0

0 0

Yes MOV8508 Is used for bng.term cooing and Is normaly dosed.

Valve poskion Is verified every shift vh 0-ttt 3, Step 5.9.72,'herefore, valve b oonsldered locked dosed by adninistratlve cortroL MOV.18138 ts bcked dosed vh the breaker behg bcked opea AIIthree AOVs fail dosed on k>>s ol power.

201 (top) 201 (bottom)

Reactor Comparbnent Cooling Urete A And 8 8 Hydrogen Recomblner (Rbt And Mrdn) 4757 4636 10768 10848 10211SI 1021 3SI 0

0 LC LC 0

0 Non-radbactive, dosed.bop system Manual Valves 10768 snd 10848 are bcked dosed.

Solenokl valves 10211SI and 1021 3SI fa1 cbsed on loss of power.

Containment Pressure Transrnkters PT4I47 And PT~S PT-947 PT4I48 18190 1819D NA NA 0

0 Allvalves less than 3'bmeter.

Rost-Acckfent AirSarrpte To 8 Fan 1563 1565 IMS 1568 LC LC LC LC Ailfour manual valves afe locked closed.

Purge Supply Duct Bind Fhrele Yes Locked dosed vb bfrd Ssnge.

AOV-5S69 falIs ck>>ed on k>>s of power.

Hot Leg Loop Sample 0

0 0

Yes AOV4I65b not consklered a CIV.

Manual valve 9560 b not required to hobte.

AOV~fats dosed on bss of power.

Table 7-2 Containment Isolation lPage 4 of 6]

P<<netratlon Number Descrfptbn Valve Number PoslUon At Normal OpefaUon Containment IsotsUon Maintained JusUUcatlon (Per 67410) 206a (top) 207a (top) 207b (bottom)

Steam Generator Inspecton I MaIntenance Fuel Trar¹fer Tuba Chargkrg Une To B Loop Safety In(ectbn Pump 1B Discharge Bird Range 870B 889B 0

0 0

Locked Cbsed Via gt1nd Range Locked Cbsed Via Bgnd Range Check Valve Both Components Are Check Valves 209 (top) 209 (bototm) 210 Alternate Charging To A Cold Leg Oxygen Makeup To A 8 B R~rs 1080A 1021 4S 1021 481 1021 SS 1021 SSI LC 0

0 C

0 Yes Check Valve Marwal valve 1080A bckad dosacL Solenokl valves 1021 4S, 1021 4SI ~

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 Containment AuxlbrySteam Condensata Retrsn A Hydrogen Racombiner (Riot 8 Main) 8151 81 65 81 52 8175 1076A 1084A 10205SI 1020981 LC LC LC LC LC LC 0

0 Both manual vahes are kxked dosed.

Both manual valves are locked dosecL Mawal valves 1078A snd 1084A are bcked dosed.

Sdenokl valves 10205SI and 10209SI fai cbsed on bss ol power.

305b (top)

Conbdnment AlrSampb lrtet Contrdnment AlrSample Post.Accklent 1598 1597 1598 1599 1554 1556 1557 1559 1560 1562 0

0 0

0 LC LC LC LC LC LC Manual valve 1597 b not rrxtukad to bdate.

AOV.1597 fels ebs ed on bss of power.

Both AOVs fal dosed onbss of power.

Allsix manual valves ara locked dosed.

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.

31 Oa (bottom)

Mkrl.Ptsge Srsrply Service AlrTo Corralnment 7445 7478 7141 7226 OrC OrC LC 0

Both AOVs fal dosed on k¹s of power.

Msrwal valve 7141 Is bckad cbsrxL Valve 7228 b a check valve.

Table 7-2 Containment Isolation [Page 5 of 6]

Penetration Number Description Valve Number Posltfon At Normal Opefathn Containment Isobrtlon Maintained JustNcatlon

]Per 87~]

310b (top)

I strument Air To Containment 0

0 ADV5392 fels cbred on loss ol power.

Valve 5393 Is a check valve.

311 312 313 Servke Water From B Fan Coohr Servke Water To 0 Fan Cooler Leakage Test Depressurlzstkn Bind Range 7444 LO LO Yes Non rsdkectlve, dosed 4oop system Non radlosctire, dosed 4oop system Locked cbsed vh bind fbnge.

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 Range 7443 Locked dosed vh bind fhnge.

318 Deadw4gtd Tester Locked dosed.

Penetrathn k welded shut.

319 Servke Water From AFsn 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 5737 0

0 Manual valve 5702 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 8419 ADV8418 fals cbsed on loss of power.

Valve 8419 kd a check valve.

Cont4nment Pfess lte Trans Intters Pl'-944. PT.949, and PT-950 PT-944 PT-949 PT-950 1819E 1819F 1819G NA NA NA 0

0 0

Allvalves are less than 3'tsmeter.

Hydrogen Manner Instnrnerdatbn Lhes 921 922 923 924 Allfora adenoid valves fsl chsed cn bss ol power.

Table 7-2 Containment Isolation [Page 6 of 6]

Penstratton Number Descrlptkm Valve Number Posttkm At Normal Operation Containment hohrtlon Malnlalned JustNcaOon Pre r 97410) 401 Mstn Steam From Steam Generator A 3505A 3507 351 7 351 9 3521 0

0 0

0 0

Contr4nment boundary h SG secondary dde snd tubes.

No contahment holation h requlr<<l, Main Steam From Steam Generator 8 3504A 3509 351 B 351 9 3520 0

0 0

0 0

Containment botsvlary h SG secondary side and tubes.

No contahment Isohtion h required, Feedwster Une To Steam Generator A 3993 3995 40000 4003 4005 4011 0

0 0

0 0

0 Containment boundary h SG secondary side snd tubes.

No contshment Isolathn h required.

Feedwater LIne To Steam Generator 8 3992 3994 4000D 4004 400B 4012 0

0 0

0 0

0 Containment boundary h SG secondary side snd tubes.

No contahment lsoladon h requtred.

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 TREAT Analysis of Station Blackout

STATION BLACKOUT TREAT SIMULATION Summary of Significant Analysis.

Events and Operator Actions During the 0.0 Time (sec)

Event/Action Loss of all AC resulting in reactor trip, RCP coastdown, loss of main

'feedwater, and turbine trip.

500 (8.3 min.)

1000 (16.7 min.)

1300 (21.7 min.)

2000 (33.3 min.)

2500 (41.7 min.)

3000 (50 min. )

3500 (58 min.)

5000 (1.4 hr.)

5500 (1.53 hr.)

7200 (2.0 hr.)

8000 (2.2 hr.)

14,400 (4.0 hr.)

RCS loop flow reaches NC flow and remains there for duration of the analysis.

Pressurizer

empties, RCS pressure decreases to P of hot leg.

SG NR level returns on scale.

Aux. feedwater reduced, from 400 gpm per SG to 25 lb/sec. (180 gpm) per SG.

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.

Aux. feedwater reduced, to 0.

ARVs open; terminates heatup.

ARVs remain open for duration of the analysis removing decay heat.

RCS pressure reduced to P of T Upper Plenum "collapsed" level decreases as voids appear.

Aux. feed increased to 36 gpm per SG.

Aux. feed increased to 72 gpm per SG.

Aux. feed reduced to 57 gpm per SG.

Aux. feed stopped.

Upper Head reaches saturation and. "collapsed" level decreases as voids appear.

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

II 2288.8 2888.8 c

1688.8 M

Vl

'V L

N IN9,8 0.

Pfp ] ~lt 1488.8 1289.8 fi fjo<

1898.8 2888.6 4668.8 666B.S 866B.S TIIK (SEC)

ISSGG.S 12669.9 14668.8 IQS,S

118e.e PKSTNS - PKSTNm<2) 1888.8 iI II we.e I'g IIl li 1848.8 I

I 1828.8 M

I I

1688.8 I

I I

968.8 I

i I

968.8 948.8 928.8 2668.8 46ee.e 6689.8 6888.8 TI% <SEC)

STATIOH ELNXOUT 12866.8 14668.8

88.8 78.8 N.B n

V J

58.8 48.8 A.B 28.8 Ie.e 2666.8 4668.8 6668.8 8888.6 T1% (KC)

STATION IUlXOUT 12666.8

188.8 ERR%. EKQDL(2>

88.8 N.B 58.8 48.8 KB'8.8 I

I 18.8 i

I I

l 2888.8 4888.8 aWB 8888.8 TltK (SEC)

STATION IUtXOUT 12688.8

I I

I I

I 5888.8 I

I I

I I

g ceee.e

'V I

M8.8 1800.8 18 2000.8 4880.0 we.e 8000.0 TIIIE CKC)

STAT10H ELACKNT 14880.8 IWB.B

@.6 RGFL(71) 58.8 48.8 if III0 PlJ'V 20 KB X3 C

28.8 18.8 ee 2888.8 4888.8 6888.8 8866.8 TIN <SEC)

STATIOH MXOUT 12668.8

I.BOER P-S.BBE@7 Cz'V 0

0 6,BOER?

2.88ER7 Le 2668 8 4888,8 6B68.8 8888.8 TIIK (SEC)

STATION EUtm1T 12688.8

'h 1

668.8 648.8 628,8 C

Vl I

I A

ae.e I

I II I

0x I

588.8 568.8 548.8 528.8 se.e 2888.8

.4888.8 6888.8 TIE (SEC)

SATIN ELAMN 12888.8 l4888.8 i6888.8

55.8 I'L

'V J

58s8 Id LUJ I

blr I

I8 45.8 J

IA2 J

48.8 III I

X3 35.8 X.a zs 2888.8 4888.8 aeee.e TINE (SEC)

STATION IU(XOUT I2888.8 I4ae.e

IIQFL<BI>

r.e 6,5 6.8 5.5 4,5 4.8 3.5 25$,8 6888.8 8%8.8 TIJOU (SEC)

STATIN RNXON 12888.8 16888.8

58.8 48.8 38.8 28.8 18.8 4688.8 6888.8 Tl/E (SEC)

STATIOH MXOUT 16668.8 12668.8 14688.8

INfL(55) 48.8 z.e 58.8 15.8 18.8 5.8 259.8 4668.8 6868.8 8668.8 TIE (KC)

STATIOH ELACKGUTlRECKGY 14NN.e

1 22M.B c

IS88.8 0

G.

Q t698.8 l488.8 l288.8 M8.8 2888.8

/~ 0

• e ~

~

oaoq 8 TltjE (KC)

STATIOH ILACKOUMEN",ElN

!HN8.0 l2888 8

1188.8 PKSTAP8 - PKSTNN(2) 1888.8 Ia

)I II IB68.8 I' Is I>

li 1848.8 I

I 1828.8 A

I 0

I 1888.8 I

I I

988.8

]

I i

9N.8 948.8 9f!8. 8 2888.8 4888.8 6%8.8 8888.8 TINE (SEC)

STATI(jH ELNXM4E(3lW 12888.8 14888.8

88.8 N.S 948 48.8 A.S 28.8 18.8 ee 2888.8 4888.8 68%.8"

'888.8 TINE (SEC)

STRTION ELNXOUT4ECMP IBNN.B neee.e 14888oB 1688B.S

7008.0 6888oB I

I I

I I

58$.0 I

I I

I I

g 48%.8 Pl 00 3008,0 2008.0 1088.0 ee 2008.0 4808.8 awe 8000,0 TIIK (SEC)

STATI(N ELNX(NT4EGNERY 14888,0

688.8 648.8 628.8 A

8$.8 0x I

588.8 568.8 548.8 528.8 988 2888.8 4888.8 6NN.B 8888.8 TIN (SEC)

STATION ELNXOUT4EISGN 14se.e 166M.B

55.8 I

U.

58.8 QlJ I

W 3I-I 45.8 J

I 0.3, 48.8 I

E3 35.8 x.e 25.9 2666.8 4668.6 NS.B 8688.8 TltK (SEC)

STATIN MNXNT4ECOVERY 18666.8 12668oB 14888.8 16B8L8

58.8 n0 III PlJ 48.8 348 28.8 18.8 88 I

I I

I 2888.8 4888.8 T1% <SEC)

STATIN TUKKQIT4EN'ERY 12888.8 14888.8 16888.8

~rL(58) 6.5 6.8 5.5 4.5 4.8 3.5 14488,8 38 14688.8 14888,8 INS.S 152M.S TI% (SEC)

STATIN MXOUT4ECOVERY IMS.S 15688.8 15888.8 16888.8

h

RG&E Answers To The NRC's March 24, 1991 Station Blackout Questions Quality Assurance Classification Of Station Blackout Equipment

Station Blackout Coping Equipment QA Status [Page 1 of 2]

Equipment ID Descrlpdon Quality Asswance Classtrrcsthn Condense'te Storage Tanks AFW Supply To SGs Satety Significant AFW Supply To SGs Safety Chas 3 PLOII MOVs 3504A, 3505A MOV~

TDAFWP DC Lube Oil Pump TDAWFP Steam Supply TDAFWP Discharge Valve AFW Supply To SGs AFW Supply To SGs AFW Rcw To SGs Safety Chas 3 Safety Chas 2 Safety Chas 3 AOVs 4297, 4299 AOVs 351 6, 3517 TDAFWP Fhw Control Valves hen Steam Isolation Valves AFW Fkrw To SGs Decay Hest Removal Safety Class 3 Safety Chas 2 SVs 3509.351 5 PCVs 3410, 3411 SG Steam Retef Valves SG Atmcspherh Relief Valves Decay Heat Removal Decay Hest Removal Safety Chas 2 Safety Chas 2 Nr Ihckup To ARVs 3410S, 3411S PCVs 9012, 9013 PCVs 3410A, 3411A PCVs 15003, 15004 Backup Gas Supply To SG ARVs ARVSolsnolds Nr Supply Presstze Rag tfadng Valves Nr Supply Preset!a Rag tfagng Valves N, Supply Presstze Regrfsgng Valves Decay Heat Removal Decay Hest Removal Decay Heat Removal Decay Hest Removal Decay Heat Removal Safety Signlgcant Safety Slgni6cant Safety Slgrvgcant Safety Slgn5cant MORI 3 RC Pump Seal Return Isolagon Valve RC Pump Seal Protection Safety Chas 2 Batteries 1A, 18 DC Power Distrhuthn Panels IA, 18 125 VDC Power Dhtrfbubon Emergency Power Supply Safety Chas 3 Emergency Power Supply Safety Chas 3 Irrverters IA, 18 Instrument Buses 1A, 18 TEs 409A. 8 and 4'IOA, 8 PT~

LTs 426, 433 Inverters 120 VACVital Buses RCS Hot 5 Cold Leg Temperature Pressurtzer Presswe Pressurizer Level Emergency Power Supply Safety Chas 3 Ffark Status Monitoring Safety Class I Safety Chas 2 Safety Chas 2 Emergency Power Supply Safety Chas 3 LTs 460, 470 PTs 469, 479 NE-31 ~ NM2 LTs 2022A, 20228 SG IA. 18 Level SG 1A, 18 Pressure Source Range Rux Detectors CST Level Rant Status Monkorlng Rant Status Monkofng Pbnt Sbtr>> Monkorlng Rara Status Monkorlng Plant Status Monkorfng Safety Chas 2 Safety Chas 2 Safety Chss 3 Safety Chas 3 Safety Class 3

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Station Blackout Coping Equipment QA Status tPage 2 of 2]

Eqtiprnent ID Qualky Asstsar>>e Casa@cation PCH01 8 R&gfC Bus 18, Unit 158 Bus 18, Unit 15C Chargkig Pump 18 Charging Pump 1C Charghg Pump 18 Crcuit Breaker Charging Pump 1C Croit Breaker Maktn4r To RCS Makeup To RCS Power To PCH01 8 Power To PCH01C Safety Cbss 2 Safety Cbss 2 Safety Cbss 3 Safety Cess 3 Bus 18 Bus 18, Urit 128 480 V AC Bus Bus 15/Bus 18 Tle Clrctit Breaker Power To Charging Pump Power To Charging Puirp Safety Cbss 3 Safety Casa 3 Bus 15 Bus 15, Unit 3A 480VAC Bus Bus 15/TSC Ile Crcuft Breaker Power To Charging Pump Power To Charging Purrp Not Nudear Safety Not Nudear Safety Technical Support Center Diesel Power To Charging Pump Safety Significant TSC1 Technical Support Center Generator TSC Static Transfer Switch Power To Charging Puny Power To Charging Pump Safety Slgniscsnt Safety Significant 957aa, 9573A, 958BA, 9584A, 9586G, 9584G, 9510A, 4048, 9509C, 9516D, 9509F, 95098 Diesel Driven Rre Water Pump Outside Condensate Storage Tank PAuwsl Valves Alternate Coosng Water To Tistine Driven AFW Pump Alternate AFWSupply To SGs Alternate AFW Sip ply To SGs From TCD03 Safety Slgnigcant Not Cbssffbd Not CbssiY>>d 4078, 4079 2291, 7310, 4318A, 2313 2ih'ose(s)

Hydrants, Hose Statlcns 1'ose Manual Vabes Manual Valves Fire Hoses Fire Water Supply Points Alternate AFW Sg>pfy To SGs From Fire Water System Alternate AFW Steeply To SGs From City Water System Alternate AFW Stpply To SGs From Fire Water System Alternate AFW Stppfy To SGs From Fire Water System Alternate AFWSis>ply To SGs From Ciity Water System Appendic R