ML19291B166
| ML19291B166 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/24/1979 |
| From: | Utley E CAROLINA POWER & LIGHT CO. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| GD-79-2110, NUDOCS 7908290566 | |
| Download: ML19291B166 (5) | |
Text
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Caro.ina Power 3 L:gnt Comcany August 24, 1979 FILE: NG-3514(B)
SERIAL: GD-79-2110 Office of Nuclear Reactor Regulation Attention: Mr. T. A. Ippolito, Chief Operating Reactors Branch No. 3 United States Nuclear Regulatory Commission Washington, D.C.
20555 BRUNSWICK STEAM ELECTRIC PLANT DOCKET NOS. 50-325 AND 50-324 OPERATING LICENSE NOS. DPR-71 AND DPR-62 SEISMIC ANALYSIS OF SAFETY RETiTED PIPING
Dear Mr. Ippolito:
Our letter of July 23, 1979 transmitted a summary of results of all lines that had been reanalyzed at Brunswick Units 1 and 2.
In that letter we informed you that there still remained some lines on BSEP 1 and 2 that were being reanalyzed to account for valve operator eccentricity. Reanalyses of these lines has now been completed, and the results are shown in Table 1.
The results of isometrics 61, 146, 194, 199 and 230 were reported verbally to your staff on August 2, and line 56 was reported on August 17.
Lines 56, 61, 146, 194 and 199 will have long term fixes implemented as discussed in our July 23 letter. Prompt modifications on line. '130 were completed earlier this month.
This submittal completes all of the commitments made by CP&L with regard to the original issue of reanalysis of safety related piping. Information requested by your staff concerning modeling.of piping elbows and large radius piping sections is being addressed in separate correspondence. If you have any questions concerning this material, please contact our staff.
Yours very truly,
%e W YE.E.Utley E@xecutiveVicePresident Power Supply & Customer Services DLB/jeb cc: Mr. James P. O'Reilly United States Nuclear Regulatory Commission - Region II 7908290gg
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I EMERGENCY STRESS CABLE 1 1
FOR LINES WITil VALVE OPERATORS i
I s
i NEW i
EMERGENCY l
SildET NO.
SYSTEM SIZE NEW DBE CONDITION ALLOWABLE l
t 4
liigh Pressure Coolant Injection 3"
9,088 14,933 27,000 8
Nuclear Steam Supply 1/2" 34,010 35,181 36,000(3)(5) 21 Reactor Core Isolation Cooling 3"
5,018 9,033 27,000 25 Residual lleat Removal 4"
9,358 15,012 27,000 39 Core Spray 3"
8,893 11,487 27,000 40 Core Spray 3"
8,896 12,841 27,000 41 Residual lleat Removal 3"
12,131 18,205 27,000 43 Residual lleat Removal 3"
9,960 15,484 27,000 47 & 48 Residual lleat Removal 4"
10,378 13,812 27,000 53 liigh Pressure Coolant Injection 4"
5,484 8,580 27,000 56 Residual lleat Removal 3/4" 28,163 37,348 44,880(4)(5) 57 & 58 Residual lleat Removal 4"
9,140 13,583 27,000 l
211 Containment Atmospheric Control 1"
6,398 13,992 27,000 212 Containment Atmospheric Control 4"
13,487 15,685 27,000 f
146 liigh Pressure Coolant Injection 1"
23,826(2) 30,120 36,000(3) U)
N 152 liigh Pressure Coolant Injection 1 1/2",
2" 13,624 14,-960 27,000 f
a
[']
157 liigh Pressure Coolant Injection 1"
15,616 19,347 27,000 i
NEW EMERGENCY SHEET NO.
SYSTEM SIZE NEW DBE CONDITION ALLOWABLE 547 & 548 Residual lleat Removal 4"
9,764 13,137 27,000 657 liigh Pressure Coolant Injection 1"
25,810 27,815 36,000(3)(5) 87 Nuclear Steam Supply 1"
16,169 20,466 27,000 61 Demineralized Water 3/4" 31,553 36,079 44,880(4)(5) 146 liigh Pressure Coolant Injection 1"
23,826 30,120 36,000(3)(5) 194 Reactor Core Isolation Cooling 1"
33,034 33,271 36,000(3)(5) 199 Residual lleat Removal 1"
30,356 34,817 36,000(3)(5) 230 Standby Cas Treatment 1/2" 22,825 U1 25,340 27,000(3)(5) 32,040 U2 39,606 36,000 1
Residual lleat Removal 24" 10,189 14,432 27,000 2
Residual Heat Removal 16", 20" 5,241 10,764 27,000 6
Residual lleat Removal 20" 4,093 11,225 27,000 i
10 liigh Pressure Coolant Injection 10", 14" 3,362 9,170 27,000 11 liigh Pressure Coolant Injection 16" 15,618 17,214 27,000
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i 14 Nuclear Steam Supply 24" 10,036 16,335 27,000 14A Nuclear Steam Supply 24" 4,768 11,123 27,000 l
15B Nuclear Steam Supply 24" 3,858 10,640 27,000
(
N l
CD 15C Nuclear Steam Supply 24' 3,904 10,458 27,000
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17 liigh Pressure Coolant Injection 14" 2,732 8,341 27,000 m
C l 1
i
NEW S11EET NO.
SYSTEM SIZE NEW DBE(1)
CONDITION ALLOWABLE -
18 Core Spray 14" 7,066 12,009 27,000 f
19 Core Spray 10" 3,335 9,899 27,000 20 Core Spray 10" 5,616 10,889 27,000 22 Reactor Water Cleanup 6"
10,133 16,723 27,000 l
23 Core Spray 10" 5,260 10,660 27,000 26 Core Spray 10" 7,827 13,568 27,000 28 Residual lleat Removal 16", 20" 4,413 10,897 27,000 42 Residual lleat Removal 14" 12,340 17,480 27,000 44 Residual lleat Removal 6"
3,877 6,629 27,000 51 Residual lleat Removal 6"
2,132 5,498 27,000 52 Residual lleat Removal 14" 10,728 16,063 27,000 82 & 83 Service Water 20", 24" 6,024 9,397 27,000
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107 Service Water 6"
8,793 13,360 27,000 108 Service Water 6"
5,818 8,408 27,000 i
24 & 524 Core Spray 10" 6,471 13,347 27,000 510 liigh Pressure Coolant Injection 10", 14" 4,055 8,553 27,000 l
i 609 Service Water 6"
10,123 12,938 27,000 l
I N
i I
CD f
" ~
a r;w U1
NEW EMERGENCY SilEET NO.
SYSTEM SIZE NEW DBE CONDITION ALLOWABLE '
l 709 & 710 Containment Atmospheric Control 18", 20",
24" 7,112 8,653 27,000 716 Service Water 1 1/2" 22,879 25,340 27,000 l
l i
l NOTES:
(2) DBE Seismic Computer Run (3) Structural Integrity for Carbon Steel (4) Structural Integrity for Stainless Steel (5) Previously Reported N
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