ML20235C209
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j Carolina Power & Light Company Raleigh, North Carolina 27602
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March 25, 1970 4
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g Dr. Peter A. Morris, Director Division of Reactor Licensing United States Atomic Energy Commission p,gulatory File C '
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20545 Re: Docket Nos.
and 50-325.
Dear Dr. Morris:
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The Company transmits herewith additional information in support of its proposed reduction in the design pressure of the contain-i ment dry well and torus of the Brunswick units from 62 psig to 53 psig. This submittal is in response to a Staff request for specific data used in the calculation of the Brunswick contain-ment design pressure.
In order that the engineering and construction of the Brunswick units.may proceed on schedule, the Company desires to discuss this submission with the Staff at the earliest possible date.
Very truly ours,
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J. A. Jo s Vice President - Power Supply JAJ:ej
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63 MAR 261970 >j{3 REGULATORY 7
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8709240386 870921 304 PDR FOIA MENZB7-111 PDR
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In:the Matter of
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4 f CAROLINA POWER & LIGHT COMPANY )
Docket Nos. 50-324
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(Brunswick' Steam Electric Plant )-
50-325 Units 1"and 2)
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Escal;:d wittr tota Idf* 7' AFFIDAVIT OF J. A. JONES I, J. A. - Jones, being duly sworn, depose and state that I
. reside in Raleigh, North Carolina; that I am Vice President, Power Supply, Carolina Power & Light Company; that I.am fully cognizant of.the. contents of the foregoing document' entitled " Brunswick Containment Analysis. Data", and that the contents of the same are true and: correct to the best of my knowledge.
.A J.A? Joy Subscribedandsworntobeforemethisd' hay of March,1970, at Raleigh, North Carolina.
i At'f& h $W No%ry Public My conuniulon expires:
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= In the Matter of
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t CAROLINA POWER & LIGHT COMPANY -)
Docket Nos. 50-324 L
(Brunswick Steam Electric Plant )
50-325 Units 1 and 2)-
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AFFIDAVIT OF J. A.' JONES I, J. A. Jones, being duly sworn,-depose'and state that I reside in Raleigh, North Carolina; _ that I am Vice President, Power j
Supply, Carolina Power _& Light Company; that I am fully cognizant of the contents of the foregoing document entitled " Brunswick Containment Analysis Data",-and that the contents of the.same are true and correct to the best of my knowledge.
A JG L j/J. A. Jones Subscribed and sworn to before me this 2.5" day of March,1970, at Raleigh, North Carolina.
Iin f i;..,,,f. k). $2f Nopary Public 7
My conaission expires:
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BSEP 1 & 2 DOCKET Nos. 50-324 & 50-325
.c BRUNSWICK CONTAINMENT ANALYSIS DATA Group 1 Data Initial Pool Temperature F
90 Initial Wetwell Air Temperature F
90 Initial Drywell Temperature F
130 Initial Wetvell Pressure PSIG 1.3 Initial Drywell Pressure PSIG 1.3 Initial Wetwell Relative Humidity 7.
100 Initial Drywell Relative Humidity 7.
30 Downcomer Submergence Ft.
4 Wetwell Pool Volume Cu.Ft.
87300 Initial Reactor Power HWT 2550 Initial Mass of Water in Reactor Lb.
464,500 Initial Mass of Steam in Reactor Lb.
18,200 Assume Enthalpy of Water Btu /Lb.
545 Assumed Enthalpy of Steam Btu /Lb.
1191 Group 2 Data (1) Reactor pressure versus time supplied in Table 1.
(2) No feedwater flow assumed during blowdown. Feedwater enthalpy is less than sat'urated and would tend to depressurize vessel if flow included. Assuming no flow maximizes reactor pressure thereby maximizing loading on containment (effect small in any event).
(3) Steam flow versus time provided in Table 1.
This flow is handled merely as an outflow from vessel. Energy assumed dumped to main condenser.
Group 3 Data (1) Flow out of break provided in Tabic 1.
(2) Energy rate out of break also provided in Table 1.
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BSEP 1 & 2 -
~ 50-324 & 50-325-
.. DOCKET NOS.
TABLE 1 RE' ACTOR CHARACTERISTICS DURING BLOWDOWN Liquid Steam Steamline Reactor Flow
. Liquid Flow
~ Steam Time Flow Pressure Break Enthalpy Break Enthalpy h
Lb/Sec.
PSIA Lb/Sec.
Btu /lb.
Lb/Sec.
Btu /lb.
0 2513 1020 38890 545 0
1191
.944 2513.
1011 38770 543 0
1191.3 1.88-2390
.1002 38630 542 0
1191.6-2.82 1570 993 38480 540 0
1192 3.44 150 993 38490 540 0.
1192 4.07 0
999 38580 542 0
1191.7 5.32 0
1008
' 38720 543 0
1191.4
'6.57 0
1013 38790 543 0
1191.2' 8.82 0
1015 38810 544 0
1191 9.88 0
1005 16660 542 6261 1191.5
'11.07-0 876 13260 522 5843 1196.2 12.32 0
750 10460 502 5388 1200 12.94 0
689 9221 490 5131 1201.4 15.44 0
470 5203 442 3955 1204.6 19.19 0
237 1749 372 2291 1200.5 26.19 0
57 39 259 561 1176.6
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