ML20236P534
| ML20236P534 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/07/1987 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| ULNRC-1571, NUDOCS 8708120407 | |
| Download: ML20236P534 (6) | |
Text
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^ UNION
. Etscraic ETA
(
1901 Gratiot Street St. Louis Donald F. Schnell
. Vce President August 7, 1987 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C. 20555 Gentlemen:
ULNRC-1571 DOCKET NUMBER 50-483 CALLAWAY PLANT RESPONSES'TO QUESTIONS ON CYCLE 3 RELOAD USING WESTINGHOUSE VANTAGE 5 FUEL
Reference:
ULNRC-1561 dated July 28, 1987 In the reference letter, Union Electric responded to a set of questions concerning the application for Callaway cycle'3.
These. questions and responses addressed the spent fuel pool thermal hydraulic analysis and the performance of the component-cooling water system.
Provided herewith is a revised Table 3 which lists the design component cooling water loads which are expected to be applicable during normal plant operation.
This information is provided in response.to a phone call with the Staff on August 5, 1987.
If there are any further questions, please contact us.
Very truly.yours, 1
0./m D OC Don Schnell DS/plh cc:
J. H. Raval (NRC) 8708120407 870B07 PDR ADOCK 05000483 L
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PDR 0\\
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Mading Address: P.O. Box 149, St. Louis, MO 63166
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STATE OF MISSOURI.)
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CITY OF'ST. LOUIS )
Robert J.
Schukai, of lawful age, being first duly sworn upon. oath says that he is General Manager-Engineering (Nuclear) for Union Electric' Company; that~he has read the foregoing document-and-knows the content thereof; that he. has executed the same for and on behalf of said company with. full power and authority to do so; and that the f acts therein stated are true and correct to the best of his knowledge, information and belief.
By Robe (t JJ. SchuYai Gener W Manager-Engineering Nuclear SUBSCRIBED and sworn to before me this day.of 1989 STEVE SULL%N h0TARY Pugue, start or wssount Q
Otto M4 MY COMMl% BION CXPIRES 014/9Q"
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ST. LOUIS COUNTX /, '[]
1 cc:
Gerald Charnoff, Esq.
Shaw, Pittman, Potts & Trowbridge 1
2300 N. Stree t, N.W.
Washington, D.C.
20037 Dr.
J. O. Cermack CFA, Inc.
4 Professional Drive (Suite 110)
Gaithersburgh, MD 20879 W. L.
Forney j]
Chief, Reactor Project Branch 1 U.S. Nuclear' Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Of fice U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077 Tom Alexion (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 316 7920 Norfolk Avenue Bethesda, MD 20014 Ron Kucera, Deputy Director Department of Natural Resources P.O. Box 176 Jefferson City, Mo 65102 Manager, Electric Department Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 i
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Attachment'1, Page 1 of-3 ULNRC-1571 Component' Cooling Water'(CCW) Heat Loads
- The original submittal showed a normal' total-load of 90.63
'MBTU/HR for one CCW heat exchanger.
The enclosed modified Table 3-shows a normal total load of 74.43 MBTU/HR.
Changes are as noted and. basically represent a more realistic, though still conservative, combination of heat loads.
The total-of 74.43 MBTU/HR is~below the design case duty capacity of 77.18 MBTU/HR per heat exchanger.
Therefore, the assumed CCW exit' temperature of 105 F (with 95 F service water) will be met.
The. conclusion remains that w e CCW system will adoquately cool the involved safety related systems and components, including.the spent fuel pool cooling system, at the 3411 MWt and 3565 MWt' reactor core power levels with the use of VANTAGE-5 fuel.
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Attechment 1, Pagn 2 of 3 ULNRC-1571
.(revised from ULNRC-1561, 7/28/87)
TABLE 3
)
REVISED COMPONENT COOLING WATER (CCW) HEAT EXCHANGER (HX) LOADS CCW HX Train A Heat Loads (MBTU/HR)
)
Shutdown Component Normal
(@ 4 hrs)
(118
)
(195
)
RHR Pump Seal Cooler 0.03 0.03 0.03 CCP Bearing Oil Cooler 0.08 0.08 0.08 l
SI Bearing 011 Cooler 0
0 0.06 I
Fuel Pool Cooling HX (20.95) 0 0
Excess Letdown HX 0
0 0
RCP Coolers 9.28 2.32 0
Letdown HX 10.4*
5.0*
O l
Ser.1 Water HX 2.40 2.40 0
Recycle Evaporator Package 8.81**
8.81**
O l
Waste Gas Compressors 0.25 0.25 0
PDP Oil Cooler ***
0.81 0.81 0
l Aux. Steam Rad Monitor 0.23 0.23 0
PASS Sample Coolers 0.10 0.10 0.10 Catalytic Hydrogen Recombiners 0.30 0.30 0
NSS Sample Cooler 0.59 0.59 0
Waste Evaporator Package 0**
O**
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Secondary Waste Evap. Pack.
17.8 0
0 Reverse Osmosis Unit 0.16 0.16 0
Total (74.43)
(144.32)
(195.27) l CCW HS Train B Heat Loads (MBTU/HR)
Shutdown Component Normal
(@ 4 hrs)
(118
)
(195
)
RHR Pump Seal Cooler O
O.03 0.03 CCP Bearing Oil Cooler 0
0.08 0.08 i
SI Bearing Oil Cooler 0
0 0.06 Total 0
(118.11)
(195,17)
(
) represent values changed from Table 2.
E' Attachment l~,
Paga 3.of 3
+'
ULNRC-1571
' TABLE 3 (continued)
Plant Heatup (max) 16.0 Normal Letdown (max) 10.4 Normal Letdown (nom) 6.6 4 Hr After Shutdown 5.0 Both the Recycle Evaporator Package and the Waste Evaporator Package'have calculated loads of'8.81_MBTU/HR.
Only.one of' these loads is added in the table due tcr the infrequent operation of the' units and the-low likelihood of both-operating simultaneously:
Recycle Evap. Pack-4' days operation /1 month' Waste Evap. Pack.
4' days operation /1-month'
. Secondary Waste Evap. Pack.
1 day /3 days
~***
Tha PDP Oil Cooler load was given incorrectly in the l
l original submittal.
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