ML20076B138
| ML20076B138 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/21/1979 |
| From: | Furr B CAROLINA POWER & LIGHT CO. |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NG-3514(B), NUDOCS 7905230544 | |
| Download: ML20076B138 (34) | |
Text
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File:
NG-3514(B)
May 21, 1979 SERIAL: GD-79-1342 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,
' ~ NOS. 1 AND 2 DOCKET NOS. 50-325 an 0-32 LICENSE NOS. DPR-71 Ah 2
SEISMIC ANALYSIS OF SAFETY-RELATED PIPING
Dear Mr. Ippolito:
This letter supplements our letters of April 24, 1979 and Fby 16, 1979 j
on the Carolina Power and Light Company's response to IE Bulletin 79-07.
It addresses the specific requests for additional data that were discussed in our meeting with the NRC on May 16, 1979.
This letter contains the results of the seismic pipe stress reanalyses completed to date, a compila-tion of the original seismic stress data for the pipe yet to be reanalyzed, the schedule for completing the reanalysis, and the conclusions reached from the evaluation of the technical information available.
It was determined that algebraic summations were used in the seismic stress analyses portion of the computer code that was used in the original analysis.
Realizing that a total reanalysis could not be completed in the time frame required to respond to the bulletin, ten (10) lines were selected for reanalysis in order to determine the effect of algebraic summation.
The computer code currently in use by United Engineers &
Constructors, a proprietory copy of which was given to you on May 16, 1979, does not use algebraic summations. The criteria for selection of the ten
(
)
(10) lines was based on line function, size, and ability to project adequacy
. _-a for other lines of similar function and size.
This criteria is explained in more detail on Attachment 1.
Subsequent to our May 16th meeting, additional lines have also been reanalyzed. As discussed in our meeting these lines were selected on the basis of completing the larger pressure boundary and other safety systems piping.
In addition other lines having high stress values in the original stress analysis were reanalyzed.
The results of these 39 lines are tabulated on Attachment 2.
This table shows the maximum total stress and the maximum seismic stress component of each line for the original analysis and the reanalysis.
In all cases, the calculated total stresses lor the design basis earthquake are less than the allowable.
Another item discussed at our May 16th meeting was the loads on the pipe supports as a result of the reanalysis.
These new loads are being evaluated and results for the first ten (10) lines will be filed the week of May 28.
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Mr. T. A.,Ippolito May 21, 1979 SERIAL: GD-79-1342 A total of 147 stress analyses problems have been identified for Unit 2.
Most lines are identical between Unit 2 and Unit 1 so the stress analyses are applicable to both units.
However, 24 cases where the lines are different were identified and will be reanalyzed separately for each unit. The total number of computer problems for Units 1 and 2 is 171 (with 39 already completed). Attachment 3 shows those lines that have not yet been reanalyzed with the total stress and seismic stress component for DBE from the original analysis. Also, the reanalysis priority category is shown and is based on the reanalysis priority criteria shown on Attachment i
4.
The schedule for completion of the reanalysis is given on Attachment 5.
There was some discussion on the confidence that the design analyzed for stress was the "as built" design.
The quality assurance program used during construction, and in effect today, uses a " walk off" of each as
[
installed system or modification.
This inspection identifies discrepancies between system design and installation.
These discrepancies are evaluated by the architect / engineer for acceptability.
In addition, for piping and support differences, a stress analyst ascertains whether or not the system must be reanalyzed.
If not, the isometric drawing and associated computer data deck remain unchanged.
If the analyst concludes that the differences between "as-designed" and "as-built" would require reanalyses, the isometric is revised, the data deck is changed as necessary, and the stress analysis rerun. Whether the stress analysis was rerun or not, the design engineering drawing is changed to reflect the as-built configuration.
This scenario is shown on the block diagram on Attachment 6.
After a thorough review of the original seismic piping design criteria, and the reanalysis of selected significant safety class piping, CP&L has concluded that Units 1 and 2 at Brunswick Steam Electric Plant can be safely operated without undue risk to the health and safety of the public.
This conclusion is based on:
1.
Evaluation of the conservative design margins provided in the original piping design, as discussed in Attachment 7.
2.
The satisfactory results of the reanalysis of 39 selected major lines.
The reanalysis shown in Attachment 2 represents approximately 60% of the lines 2h" and over in the pressure boundary and approximately 40% of the lines 2 " and over in the emergency core cooling systems.
3.
An investigation of the as built versus as analyzed conditions.
i l _
Mr. T. A.,1ppo11to May 21, 1979 SERIAL: GD-79-1342 4.
The aseismic nature of the site as confirmed by an extensive on site and regional seismic program.
See Attachment 10.
5.
The accelerated schedule of pipe reanalysis. The final report will be filed on July 21, 1979.
Interim reports of results of reanalysis will be filed at the completion of the reanalysis of each category.
Yours very truly, k
o i
m%.
B. J. Furr
- Manager, Generation n
cc:
Mr. James P. O'Reilly NRC Region II Office of Inspection & Enforcement OV i
i
s s'.
May 21, 1979 ATTACHMENT 1 INITIAL REANALYSIS SELECTION CRITERIA CRITERIA BASIS Function Major operating system with Primary Pressure i
Boundary (Mainsteam, Feedwater and SRV Line) or Safe Shutdown System (HPCI, RHR, Core Spray)
Size Larger lines generally have higher stresses and hence less margin to the allowable Similarity Select the line which had the highest stresses from original analyses for those groups of lines with similar function (1 of 4 Mainsteam, 4 of 11 SRV, 1 of 2 Feedwater, 2 of 4 HPCI, 2 of 14 RHR and Core Spray) if I
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C ATTACHMEhT 2 PIPE STRESS REEVAIDATION
SUMMARY
LINE EMERGENCY CONDITION (PSI)
SYSTEM ISO SIZE ORIGINAL ORIGINAL NEW NEW NAME NO.
(NPS)
TOTAL SEISMIC TOTAL SEI_SMIC ALIDWABLE Main Steau MS-15B 24 10724 3942 10640 3858 27000 Safety / Relief Valve SRVL-121 10 & 6 23012 12280 21910 11180 27000 Safety / Relief Valve SRVL-122 10 & 6 19685 15800 24439 13352 27000 Safety / Relief Valve SRVL-237 10 & 6 20432 12004 24588 16160 27000 Safety / Relief Valve SRVL-125 10 & 6 24270 13347 24316 20270 27000 Fcidwater FW-16 18 & 12 18007 12420 20028 13296 27000 Residual Heat RHR-6 20 19406 13582 12644 6820 27000 Rnmoval Spray
]CS-24 10 16952 10076 14366 7490 27000 llI'gh Press Cool HPCIS-17 14 12200 6446 12502 6748 27000 Iniet High Press Cool HPCIS-510 14 & 12 & 10 12004 7994 12092 8082 27000 Inict High Press Cool HPCIS-10 14 & 12 & 10 9733 3886 11152 5530 27000 Iniet Residual Heat RHR-1 24 & 20 24094 18584 17972 14366 27000 Removal Residual Heat RHR-2 20 & 16 & 12 13309 7654 11471 5948 27000 Removal Residual Heat RHR-5 24 9848 3896 9514 2960 27000 R~moval Residual Heat RHR-25 4&6 18558 12904 18530 12876 27000 Removal Muelear Steam Supply NSS-14 24 & 10 14745 8446 16335 10036 27000
,,,aty/ Relief Valve SRVL-124 6 & 10 25536 15928 25984 16376 27000 Safety / Relief Valve SRVL-126 6 & 10 23361 18000 22197 17422 27000 Residual Heat RHR-52 14 & 12 23271 17936 19539 14204 27000 l
Removal l
Reactor Core Isolat. RCIC-21 3
7603 3588 7601 3586 27000 Cool Resid Heat Rem Drain RHR-173-B 1
3808 2186 3838 2216 27000 Linn Rnsidual Heat RHR-28 20 & 16 & 12 15298 8814 13626 7142 27000 Removal Nuclear Steam System NSS-15 24 10974 4420 10458 3904 27000 Line C Nuclear Steam System fSS-120 10 & 6 19443 8902 17899 8298 27000 High Press Cool IIPCIS-4 3 & 6 & 10 23609 20876 25481 22748 27000 Injet.
& 12 j
l ATTACHMENT 2 Cont'd LINE EMERGENCY CONDITION (PSI)
SYSTEM ISO SIZE ORIGINAL ORIGINAL NEW NEW NAME NO.
(NPS)
TOTAL SEISMIC TOTAL SETSMIC ALII)WABLE Nuclear Steam System NSS-123 6 & 10 21027 16098 18577 16782 27000 (15C)
Nuclear Steam System NSS-187 10 & 6 21856 11337 23596 16424 27000 (15C)
Residual Heat RHR-42 12 & 14 18116 12976 17480 12340 27000 Removal Residual Heat RHR-3 14 & 16 & 20 25317 18328 23379 15590 27000 Removal
& 24 Rasidual Heat RHR-13 4 & 8 & 14 12532 10018 12620 10106 27000 Removal Residual Heat RHR-59 4 & 6 & 10 12664 9970 13344 10650 27000 Removal
- Residual Heat RHR-60 4 & 6 & 10 34618 33658 32971 32012 27000 R*moval A sidual Heat RHR-168 1
23580 22658
'26910 26198 27000
.moval 7esidual Heat RHR-61 4 & 6 6 3/4 21117 17038 19393 15314 27000 Removal High Pressure HPCI-11 16 & 14 & 6 21386 19790 17214 15618 27000 Coolant Injunction Reactor Core RCIC-196 1 & 3/4 22706 19504 22504 19302 27000 Injunction Cooling Residual Heat RHR-41 3&4 26802 20728 26824 20750 27000 Removal Residual Heat RHR-199 4&1&
23410 20242 23398 20230 27000 Removal lh & 3/4 Reactor Core RCIC-194 2 & 1% & 1 24519 24118 24559 24156 27000 Isol. Cooling
(
NOTE:
Seismic stresses shown are obtained by multiplying the OBE Seismic Stresses by 2.
- Total stresses are within allowable using applicable factor to compute DBE stress from OBE stresses.
ATTACHMEtTI 3
~
FINAL STRESS REPO,RllABUMT 24 W9 Job Order Number Sheet No.1.of 16 PROB SYSTEM ISO /
LOCATION LINE EMERGENCY CONDITION STRESS QS,Il PRIO-REMARKS NO.
SHEET Ins. or SIZE RITY NO. _ Outside TOTAL SEISMIC ALLORABLE SEISMIC /
CATEG Coat.
STRESS _
(DBE)
(1.8 S )
ALLDWABLE h
'~
1 Nuclear Steam Supply 32 In 3/4 11282 5198 25900 20 1
(Vent & Inst. Line Above Bulkhead)
In 4
3963 354 27000 1
In 2
10458 7672 27000 28 In 1
4316 1672 27000 6
2 Primary Steam Condensate 87, In 3
12237 9380 27000 34 Drain Inside Dry Well 128 In 2
24225 20022 27000 74 1
(East) & West)
In 1 1/2 8345 5838 27000 21 In 1
15171 12006 27000 44 76 Control System - NSS 7
In 3/4 17945 12954 25900 50 (Inst. Sensing Line) 3 Residual Heat Removal 43 Out 4
6434 3732 27000 13 Minimum Flow By-Pass Out 4
3288 1762 27000 6
RHR Pumps 2A & 2C Out 3
21856 16332 27000 60 4
Residual Heat Removal 44 Out 6
9536 6784 27000 25 Torus Sprav (South) 2 5
Residual Heat Removal 45 Out 4
14859 12378 27000 45 Drain Piping - RHR Pumps Out 4
18562 12462 27000 46 2B, 2D 6
Residual Heat Removal 46 Out 4
21248 17250 27000 63 Drain Piping - RHR Pumps 2A, 2C 7
Residual Heat Removal 47, Out 4
18944 15888 27000 58 (Cross Conn. Drain Piping 48 Out 4
20325 17512 27000 64 RHR Pumps 2A, B, C; D &
RHR Drain Conn. to Rad-waste) 8 Residual Heat Removal 65 Out 4
3335 928 27000 3
Cross Conn. Drain Piping RHR Pumps 2A, B, C, & D South Cc. 20R
Job Order Number Shec't No. 2 of 16 PROB SYSTEM IS0p/
LOCATION LINE EMERGENCY CONDITION STRESS (PSIl PRIO-RD4 ARKS NO.
SHEET Ins, or SIZE RITY NO.
Outside TOTAL SEISMIC ALLORABLE SEISMIC /
CATEC Coat.
STRESS (DBE)
(1.8 Sh)
ALIDWABLE 9
Residual Heat Removal 51 Out 6
6588 3222 27000 11 2
(Torus Spray - North) 10 Residual Heat Removal 54, Out 4
14082 7416 27000 27 (Head Spray Line) 55, Out 4
5922 1946 27000 7
~~
56 Out 4
13253 2532 28800 8
2 Out 3/4 8048 4274 28800 14 Out 3/4 8289 4914 27000 18 11 Residual Heat Removal 57, out 4
21987 17544 27000 64 2
(RHR Exchgr 2A to POIC 58 Out 4
11899 7846 27000 29 Suct.)
12 Residual Heat Removal 170 Out 1
19175 18076 27000 66 Relief Line Around Valves Out 1
11735 9560 27000 35 5
F004A & C Out 4
14138 13930 27000 51 13 Residual Heat Removal 171 Out 1
3006 1694 27000 6
Relief Lines Around Valves Out 1
5232 3334 27000 12 F004B & D Out 1446 1260 27000 4
Relief Lines From RHR Out 1
3298 1596 27000 5
Exchgr 2A, 2B Out 3/4 4063 1762 27000 6
14 Residual Heat Removal 172 Out 1
10005 7116 27000 26 Side Vent & Sample Conn.
Out 1
12998 9904 27000 36 Exchgrs 2A, 2B
FINAL STRESS REPORT TABULAT(
)
Sheet No. 3 of 16 Job Order Number PROB SYSTEM ISO /
LOCATION LINE EMERGENCY CONDITION STRESS QSIl PRIO-REMARKS NO. _
SHEET Ins. or SIZE RITY NO.
Outside TOIAL SEISMIC ALLOWABLE SEISMIC /
CATEC C o.it.
STRESS (DBE)
(1.8 S )
ALIDWABLE h
64 Out 8'
17652 15652 27000 57 Fuel Pool Colling &
Out 8
10658 7774 27000 28 6
Filtering (RHR Suct. to Skimmer Tanks 2A, 2B 16 Residual Heat Removal 31 Out 4
21014 17402 27000 64 (Exchgr 2B to RCIC Out 6
.t.76 4396 27000 16 2
Suction Out 4
l' 53 13516 27000 50 Out 3
7331 6696 27000 24 1/
Reactor Core Isolation 33 Out 3
8337 5668 27000 20 Cooling Out 3
15615 12356 27000 45 (Steam Supply to RCIC Turb.)
18 Reactor Core Isolation 34 Out 8
21108 16218 27000 50 Cooling (RCIC Turbine Steam Exhaust) 19 Reactor Core Isolation 35, Out 4
12793 6402 27000 23 Cooling 49 Out 4
9520 6134 27000 22 (RCIC Pump Disch-Be1.
Out 2
18881 13096 27000 48 10'6" 49, Above 10'6",
Out 2
4829 514 27000 1
35)
Out 1
3315 586 27000 2
20 Reactor Core Isolation 50 Out 4
7221 2900 27000 10 3
Cooline (Test Conn. to HPCI) 21 Reactor Core Isolation 63 Out 4
15098 9488 27000 35 Out 4
13357 6534 26100 25 Cooling i
(RCIC Conn. to Feedwater) 22 Reactor Core Isolation 66, Out 4
12805 6932 27000 25 Cooling 67 RCIC Pump Disch. Line 4
. ~..
FINAL STRESS REPORT _ TAR @lT Job Order Number Sheet No. 4of 16 PROB S YSTEM ISO /
IDCATION LINE EMERGENCY CONDITION STRESS QSIl PRIO-RE>tARKS N0 _
SIIEET Ins. or SIZE R11Y s
NO. _ Outside TOTAL SEISMIC ALLOWABLE SEISMIC /
CATEG Coat.
STRESS _
(DBE)
(1.8 Sh)
ALLOWAB LE 23 Reactor Core Isolation
- 92B, Out 1
10999 5938 27000 21 Cooling System 92C Out 2
4350 2888 27000 10 (Misc. Lines at Turbine)
Out 21144 18498 27000 68 Out 3
8015 5410 27000 20 Out 3/4 12427 10438 27000 38 24 Reactor Core Isolation 161 Out 1
11796 8352 27000 30 Cooling Out 3/4 7972 5024 27000 18 Drain From Turbine Inlet Out 1855 1260 27000 4
25 Reactor Core Isolation 164 Out 2
5559 4638 27000 17 5
Cool. Barometric Out ik 3303 3128 27000 11 Condensate Pump Disc. to Out 3/4 4471 3552 27000 13 Suppression Chamber 1
26
~' Reactor Core Isolation 195 Out 1,
l 16705 15826 27000 58 Cool. Turbine Drains &.
Relief Lines 27 Reactor Core Isolation 12 Out
' '6 19870 16526 27000 61
~
' Cool. (RCIC Pump Suction.
Out 6
4391 150 27000
.0 3
i Lines)
Out 6
16311 12594 27000 44 28
- iligh Press. Coolant Inj.
9 Out 24 10395 4268 27000 15 (Exhaust Stea,m Line)
Out 20 11629 7672 27000 28 2
Out 18 3707 1680 27000 6
Out 16 4467 614 77000 2
29 liigh Pressure Coolant Inj.
151 Out 3/4 3438 1491 27000 6
(Misc. Vents &. Drains Out 3/4_
2570 770 27000 3
Main Pump-Out 3/4 4560 1056 27000 4
5 Out 3/4 2404 522 27000 2
Out 3/4 4455 2566 27000 10 Out 3/4 5920 3706 27000 14 Out 3/4 3753 1272 27000 5
Out 3/4 3398 1258 27000 5
Out 3/4 3127 567 27000 2
l Out 3/4 2303 254 27000 1
- i -
s
'- ' /'
~
FINAL STRESS REPORT TABUIATT Sheet No. 5 of 16 Job Order NuAber PROB SYSTEM ISO /
_LOCAT,1,0 N LINE EMERGENCf CO DITION STRESS QSIl PRIO-REMARKS N0 _
SHEET Ins. or SIZE RITY s
NO.
Outside TOIAL SEISMIC ALLOWABLE SEISMIC /
CATE0 Cont.
STRESS __
(DBE)
( 1. 8 S )
ALIDWAB12 7, h
30 High Prescure Coolant Inj.
53 Out 4
6988 2300 27000 8
(HPCI Pump 2A. Min Flow By-Pas Out 4
12284 11072 27000 41 2
31 fligh Pressure Coolant Inj.
146 Out 4
736 100 27000 0
- ondensate Pump Disch. Piping Out 2
2339 1252 27000 4
Out it 1228 626 27000 2
Out 1
17588 16350 27000 60 Out 283 142 27000 0
'~
32 High Pressure Coolant Inj.
152 Out 4
707 64 27000 0
(Main Pump to Esrometer Out 2
10581 9074 27000 33 Cond.)
Out 2
4893 3454 27000 12 2
Out li 23242 22760 27000 1 84 Out 3/4 638 220 27000 0
Out 5132 3769 27000 14 Out 3
17373 16790 27000 62 33.
High Pressure Coolant Inj.
153 Out 1
1489 168 27000 0
(Turbine Ring Drains)
Out 3/4 1410 120 27000 0
5 Out 3/4 5103 580 27000 2
34 High Pressure Coolant Inj.
154 Out 3/4 23191 20780 27000 26 (Misc. Vents & Drains Out 3/4 21673 20780 27000 76 Booster Pump)
Out 3/4 21782 20780 27000 76 Out 3/4 2043 760 27000 2
Out 3/4 21693 20780 27000 76 35 High Pressure Coolant Inj.
155 Out 2
23245 20990 27000 77 (Turbine Exh.)
Out 3/4 4873 2706 27000 10 Out 14831 14554 27000 53 Out 2
23346 21800 27000 80 Out 3/4 2793 1664 27000 6
Out 23762 23476 27000 86 36 iligh Pressure Coolant Inj.
156 Out 1
10838 5900 27000 21 (Turbine Drains)
Out 3/4 11067 5134 27000 19 Out 3/4 4197 2644 27000 9
37 High Pressure Coolant Inj.
157 Out 1
20511 16780 27000 62 (Turbine Steam Pot Drains)
Out 3/4 17927 14866 27000 55
l PROB SYSTEM ISO /
IDCATION LINE EMERGENCY CO!DITION STRESS QS.Il PRIO-
. REMARKS No.
SHEET ins, or SIZE RITY NO.
Outside TOTAL SEISMIC ALLOWABLE SEISMIC /
CATEC Coat.
STRESS (DBE)
(1.8 Sh)
ALLOWAB LD7, 38 High Pressure Coolant Inj.
158 Out 1
27538 25060 27000 93 (Misc. Vent, Test & Drains out 3/4 24715 22760 27000 84 Note 1 Lines)
Out 3/4 25923 22010 27000 81 Out 3/4 3896 928 27000 3
5 39 High Pressure Coolant Inj.
159 Out 1
2132 234 27000 0
(Piping for Relief, Test &
Out 1
16518 13414 27000 49 Valve Stem. Drains) 40 Core Spray & Gravity 18 Out 14 6901
'4898 27000 18 Condencate System Out 14 2073 14 27000 0
2 (Core Sprav Pump Suction 2A:
Out 12 19617 14674 27000 54 l
41-Core Spray & Gravity 18 Out 14 6901 4898 27000 18 l
Condensate System Out 14 2073 14 27000 0
(Core Spray Pump Suction 2B)
Out 12 19617 14674 27000 54 16624 27000 61 42 Core Spray Pump Dischanf' 19 Out 12 21811 (South)
Out 10 10290 5416 27000 20 Out 10 14747 9748 27000 36 43 Core Spray Pump Dischar"v.
t 20 Out 10 11112 6438 27000 23 (North)
I Out 10 7188 3120 27000 11 Out 12 14673 9400 27000 34 f _13 Out 10 19272 13462 27000 49 I
44 Core Spray Pump Discharge (South)
Out 10 9832 3826 27000 14 Out 12 17062 11662 27000 43 45' Core Spray Pump Discharge 26 Out 10 15044 9218 27000 34
~
(North Out 10 9124 3316 27000 12 2
e Out 12 22547 16786 27000 62 f
46 Core Spray System 39 Out 3
29154 26788 27000 99 2
(C.S. Mir. F1mr By-Pass Pump Out 3
25456 21860 27000 81 Note 1
~
2A)
J
FINAL STRESS REPO R TABJ QT Job Order Number Sheet No.7 of 16 PROB SYSTEM ISO /
LOCATION LINE EMERGENCY COIDITION STRESS QS,Il PRIO-RERARKS NO.
SHEET Ins or SIZE RITY NO.
Outside TOIAL SEISMIC ALLOWABLE SEISMIC /
CATEC Coat.
STRESS (DBE)
(1.8 Sh}
ALMWABLE7 47 Core Spray System 40 Out 3
16187 12944 27000 47 (C.S. Min. Flow By-Pass Out 3
20665 16720 27000 61 2
Pump 2B) 48 Core Spray System 105 Out 2
17172 13524 27000 50 (RHR Conn from C.S. Pump 2A)
Out 2
25235 22438 27000 83 48 Core Spray System 105 Out 2
17172 13524 27000 50 (RHR Conn from C.S. Pump 2B)
Out 2
25235 22438 27000 83 49 Core Spray System 166 Out 2
4185 868 27000 3
}iake-Up Demin Water for out 1
4105 2850 27000 10 Pump 2A)
Out 3/4 4898 2034 27000 7
Out 2
3234 1460 31500 4
Out 3/4 3597 1780 31500 5
6 49 Core Spray System 166 Out 2
4099 782 27000 2
(Make-Up Demin Water for out 1
1950 692 27000 2
Pump 2B)
Out 3/4 4082 1072 27000 3
Out 2
2681 226 31500 0
Out 3/4 2090 660 31500 2
1 1
_ ~.
FINAL STRESS REPORT TABUIAT i
Job Order Number
' Sheet No. 8 of.16 l
l PROB SYSTEM 150/
LOCATION LINE EMERGENCY CONDITION STRESS QSIl PRIO-REMARKS l
NO.
SHEET Ins, or SIZE RITY
[
NO. _ Outside TOTAL SEISMIC ALIDWABLE SEISMIC /
CATEC l
Coat.
STRESS (DBE)
(1.8 S )
ALLOWABLE h
50 Residual Heat Removal and 29 Out 20 4397 332 27000 1
Service Water Out 16 10822 5214 27000 19 4
(Cooling H O for Xchgr 2B) 2 31 Residual Heat Removal and 30 Out 20 7761 2086 27000 7
Service Water Out 16 8026 3650 27000 13 4
(Cooling H2O Piping, Exegr 2A) 52 Service Water 85 Out 16 11781 7292-27000 27 RHR Service Water Out 12 7503 3632 27000 13 Pumps 2B & 2D Out 8
8436 5262 27000 19 4
53 Service Water 86 Out 16 6271 3778 27000 13 RHR Service Water out 12 7062 3826 27000 14 Pumps 2A & 2C Out 8
7875 5098 27000 18 4
54 Service Water 82, Out 20 29536 25810 27000 95 Note 1 Salt Water Supply to MIR 83, Out 16 11672 9262 27000 34 Service Water Pumps (South) 84 Out 14 4760 3300 27000 12 4
Out 24 17987 15900 31500 50 Out 8
992 216 31500 0
Out 30 22964 18064 31500 57 55 Service Water System 106 Out 6
13688 11548 27000 42 6" Return Line From Pump Out 4
26139 25100 27000 92 4
Room Cooler 2A 56 Service Water System 107 Out 6
24965 17948 27000 66 6" Supply Header (South)
Out' 4
29907 28212 27000 104 Note 1 out 2
1477 66 27000 0
4 57 Service Water System 108 Out 6
15040 12450 27000 46 6" Supply Header (North)
Out 4
8112 5154 27000 19 Out 2
24300 21352 27000 79 58 Service Water (Ret. From 109 Out 6
18921 15280 27000 56 Pump Room Cooler 2B)
Out 4
14224 11798 27000 43 4
59 Service Water (Cooling 110 Out 20 19323 18532 27000 68 Water Ret. Above 39)
Out 10 12255 11526 27000 42 Out 4
10:32 7660 27000 28 Out 3
15073 13466 31500 42 4
\\
FINAL STRESS REPORT TABULAT Sheet No. 9 of 16 Job Order Number PROB SYSTEM ISO /
IDCATION LINE EMERGENCY CONDITION STRESS QS,Il PRIO-REMARKS NO.
SHEET Ins. or SIZE RITY NO.
Outside TOTAL SEISMIC ALLDRABLE SEISMIC /
CATEG h
ALLOWABLE Coat.
STRESS (DBE)
(1.8 S ),
60 Service Water System 142A Out 1
17673 15660 31500 49 Return From Motor out 3
1128 802 31500 1
Coolers R.H.R. S.W.
142B Out 1
22372 20844 31500 66 Pump s 2A, B, C, D 142C Out 1
11892 10312 31500 32 4
61 Service Water Supply and 162 out 6
1595 37 27000 0
Return Headers At RHR Pump Out 6
1373 180 31500 0
Room Coller 2A out 3
1095 158 31500 0
Out 2
2285 648 31500 2
out 6
2852 312 27000 1
Out 6
2127 296 31500 0
Out 3
1678 160 31500 0
Out 2%
2217 458 31500 1
4 s
62 Service Water Supply and 163 Out 6
1567 490 27000 1
Return Headers At RHR Pump out 6
1948 770 27000 2
Room Coller "2B" Out 3
1825 816 27000 3
Out 2
2445 1370 31500 4
Out 6
4390 3358 27000 12 Out 6
3405 2392 27000 8
Out 3
5305 4488 27000 16 Out 2
8209 7330 31500 23 4
63 Service Wa.ter RHR Pumps 214 Out 2
9846 8568 32400 26 2B, 2D Out 1
7102 4740 32400 15 Out 1
5632 3474 32400 11 Out 3/4 18217 17338 32400 54 Out 2
4304 3660 32400 11 Out 1%
6256 5630 32400 17 Out 1
18556 17610 32400 54 Out 3/4 17955 17568 32400 54 6
64 Service Water RHR Pumps 215 Out 3/4 19128 15778 33660 46 2A, 2C Out 1
11897 9012 33660 26 Out 1
15043 11032 33660 32 Out 2
6718 2708 33660 8
Out 3/4 5735 4784 33660 14 Out 1
16717 15180 33660 45 Out 1
9702 7978 33660 23 Out 2
8440 7132 33660 21 6
i
(
FINAL STRESS REPORT TABULATT Job Order Number Sheet No.
10 of'16 PROB SYSTEM ISO /
IDCATION LINE EMERGENCY COIDITION STRESS QSIl PRIO-RER\\RKS NO.
SHEET Ins. or SIZE RITY
_N0_._ Outside TOTAL SEISMIC ALIDWABLE SEISMIC /
CATEG Cont.
STRESS (DBE)
(1.8 Sh)
ALIDWAB12 65 Service Water Well Water 216 Out 1
10090 8214 31500 26 Conn. To Vital Service Out 1
2840 1182 31500 3
Header Out 2
8089 6460 31500 20 6
66 Service Water C.S. Pump 217 Out 2
1098 660 31500 2
Room Cooling Units 2C, 2D Out 2
5354 1772 31500 5
Supply and Return Out 2
1873 1304 31500 4
Out 2
7731 2578 31500 8
Out 1
3996 3730 31500 11 out 4
1389 320 31500 1
Out 2
675 196 31500 0
Out 2
2554 1576 31500 5
Out 1
649 384 31500 1
Out 2
1126 680 31500 2
Out 2
6584 1598 31500 5
Out 1
1668 1404 31500 4
Out 4
1358 306 51500 0
4 67 Service Water RHR Service 218 Out 2
1559 746 33800 2
Water Pumps 2A. 2B, 2C, 2D Out 1
18318 15052 33800 44 6
68 Service Water Supply and 300 Out 14 4791 1262 27000 5
Return Unit 1&2 301 Out 10 14310 10898 27000 40 302 Out 4
7539 4284 33228 16 Out 3
14175 10932 33228 33 Out 2
10823 7610 33228 23 Out 2
15776 12572 33228 38 Out 1
16182 13020 33228 39 Out it 10466 7318 33228 22 4
69 Service Water 62 Out 20 4515 200 27000 0
(Cooling Water Return -
Out 16 5879 3318 27000 12 South)
Out 16 4412 1822 31500 5
Out 16 9875 3948 31500 12 out 10 14230 7256 31500 23 4
70 Reactor Water Clean-up 22 In 6
24303 17134 25940
'66 1
R.W.C.U. Pump Suction 71 Reactor Water Clean-up 132 In 2
9690 6548 27000 24 (Reactor Drain & Conn. To In 2
17800 13618 25920 52 5
Reactor Water Clean-up
- ~.
/"%.
m
,4 FINAL STRESS REPORT TABUIAT
~
Job Order Number Sheet No.11 of.16 PROB' SYSTEM ISO /
LOCATION LINE EMERGENCY CO!DITION STRESS QS_Il PRIO-REE\\RKS No.
SHEET Ins. or SIZE RITY NO., Outside TOIAL SEISMIC A LLORABLE SEISMIC /
CATEC Cont.
STRESS _
(DBE)
(1.8 S )
ALLDWAB12 h
72 C.R.D. Hydraulic System 27 In 3
8217 4408 27000 16 (Drive Water Pump Disch.
In 3
4653 982 28260 3
1 73 Standby Liquid Control 36 In 1
18419 14068 27900 52 1
(Liquid Control Pump Disch.)
74 Fuel Fool Cooling and
- 138, Out 8
8110 4350 27000 16 Filtering System (Line to 139 Out 8
21071 17094 27000 63 Fuel Storage Pool) (From Out 6
21127 16736 27000 61 RHR System)
Out 6
8910 2718 31680 8
6 75 Fuel Pool Cooling and
- 144, out 12 15604 13712 27000 50 Filtering System (Surge 145 out 10 4180 2452 27000 9
Tank Outlet) (Pumps 2A, 2B Out 8
15862 11428 27000 42 Suction Piping Out 6
6196 4428 27000 16 Out 4
2300 1476 27000 5
6
l i
O FINAL STRESS REPORT TABULAIS m/
i Iob Order Number Sheet No. 12 of 16 l
PROB SYSTEM ISO /
LOCAT,I,0 N LINE EMERGENCY COIDITION STRESS QSIl PRIO-RER\\RKS l
NO.
SHEET Ins. or SIZE RITY NO., Outside TOTAL SEISMIC ALLOWABLE
' SEISMIC /
CATEC Coat.
STRESS (DBE)
(1.8 Sh)
ALIDWABIE 77 Cont. Atmos. Control Sys.
148 Out 24 8101 1868 27000 6
Ventilation System Out 20 5106 1222 27000 4
Vent Purge Line 149 Out 30 11924 10408 27000 38 Standby Gas Treatment Out 24 2059 1278 27000 4
Filters 2A, 2B Out 18 20687 18166 27000 67 6
78 Ventilation Sys. (SBGT) 150 Out 24 13333 12762 27000 47 Exhaust From Gas Purge Out 18 9531 8588 27000 31 6
79 Cont. Atmospheric Control 209 In 24 1997 272 27000 1
Supply to Drywell In 20 10870 8650 27000 32 In 18 1372 254 27000 0
Supply to Suppression Pool 210 Out 8
5988 4404 27000 16 6-80 Cont. Atmospheric Control 211 Out 1
5923 1702 27000 6
Valve By-Pass Piping Out 2
26825*
24396*
27000 90 Out 1
10654 3436 27000 12 Out 5244 3686 27000 13 Out 1
14428 6834 27000 25 6
Note:
- Stress Based on.75L in lieu of 1.0 l. See para. 104.8.1 and 104. 3.2 Power P: ping Code 81 Cont. Atmospheric Control 212 out 4
23948*
21750*
27000 80 6
Vent Purge Line From Drywell 82 Cont. Atmospheric Control 2 13 Out 2
2109 654 27000 2
Relief Valve Piping Out 1
2404 1596 27000 5
Out 3/4 4102 3734 27000 13 Out 11831 6408 27000 23 Out 1
1138 620 27000 2
Out 3/4 2723 2464 27000 9
Out 2
118 6
27000 0
Out 1
6932 4642 27000 17 Out 3/4 2842 2322 27000 8
6 83 Containment Venting 230 Out 25268*
14896*
27000 55 Out 1
3012 966 27000 3
6 Note:
- Stress Based on.751 in lieu of 1.0 1.
See Para. 104.8.1 and 104.8.2 Pos 'er Piping C )de
FINAL STRESS REPORT TABUIAj Job Order Number Sheet No.13 of 16 PROB SYSTEM ISO /
LOCATION LINE EMERGENCY CONDITION STRESS QS,Il PRIO-REMARKS NO.
SHEET Ins. or SIZE RITY NO.
Outside TOTAL SEISMIC ALLOWABLE SEISMIC /
CATEG Coat.
STRESS (DBE)
(1.8 S )
ALLOWABLE h
Instrument Air System 174 Out 2
2496 2492 27000 9
6 84 Inlet Line To Air Receiver 85 Instrument Air System 175 Out 2
4698 3448 27000 12 Outlet Line from Air Out 3/4 14973 1J812 27000 51 6
Receiver 86 Instrument Air System 176 Out 2
2454 1204 27000 4
6 Supply Line (South) 87 Instrument Air System 177 Out 2
16406 15036 27000 55 Supply Line (South)
Out 3/4 3153 2028 27000 7
East of Col. "P" Out 2
12534 12284 27000 45 6
88 Instrument Air System 178 Out 1
11851 10710 27000 39 Main Steam Valves out 1
3749 2542 27000 9
Accumulators - Piping Out 2
8328 7078 27000 26 89 Instrument Air System 179 Out 2
24598 23348 27000 86 Supply Line (North) West Out 3/4 2687 1562 27000 5
6 Note 1 n to 90 Instrument Air System 180 Out 2
9614 8364 27000 30 Supply Line (North) East out 3/4 2679 1554 27000 5
6 n tu 91 Instrument Air System 182 Out 2
20284 19034 27000 70 6
Supply to Air Reevr Col."R" 92 Instrument Air System 183 Out 2
9398 8148 27000 30 Supply Line (North)
Out 3/4 14961 13836 27000 51 6
93 Instrument Air System 184 In 2
30632 29382 27000 108 Supply Header (North)
In 3/4 9353 8228 27000 30 Note 1 185 In 2
15820 14570 27000 53 In 3/4 6469 5344 27000 19 6
94 Instrument Air System 186 In 2
16026 14776 27000 54 6
Supply Header (South) 95 Instrument Air System 188 In 2
9596 8346 27000 30 Pipe to Accum. A1001C&D 189 In 1
25719 24512 27000 90 Pipe to Accum A1001A&B In 1
16209 15068 27000 55 6
96 Instrument Air System 190 Out 2
20860 19610 27000 72 Supply Lines to Filters Out ik 7629 6422 27000 23 Note 1 D-0005 and D-0006 Out 3/4 30507 29382 27000 108 6
FINAL STRESS REPORT TABUIAT, Sheet No.
14 of.'16 Job Order Number PROS SYSTEM ISO /
LOCATION LINE EMERGENCY COIDITION STRESS QSI,1 PRIO-REMA RKS_
N0 SHEET Ins. or SIZE RITY NCL___ Outside TOTAL SEISMIC ALLOWABLE SEISMIC /
CATEG Cont.
STRESS (DBE)
(1.8 Sh)
A LIDWABLE 9/
Instrument Air System 181 Out 2
28127 26922 27000 99 Outlet from RCVR at "18R" Out 3/4 3573 2448 27000 9
1 Supply West Col.
"T" 191 Out 2
17274 16024 27000 59 6
98 Instrument Air System Inner 192, In 2
28344 27094 27000 100 6
Air Supply Header 193 Note 1 Outer Air Supply Header 99 Instrument Air System 2 0 ~.
In 3/4 25822 18666 25920 72 6
Recire. Pump 2B 100 Instrument Piping Recire.
T.02 In 1
2916 732 25920 2
Pump 2A Disch.
3/4 11476 5764 25920 22 6__
101 Instrument Piping 206 In 2
11088 9598 27900 34 Piping at Temp. Equalizird In 1
4252 3546 27900 12 D003B In 1
15627 13970 27900 50 In 3/4 24990 22410 27900 80 6
l 102 Instrument Piping 207 In 3/4 20130 17540 26028 67 Lines 2E21-701 & 702 In 3/4 21655 19622 26028 75 6
104 Instrument Air Sys' tem 231 Out 3/4 6436 5372 27000 l
20 10 6
N2 Supply From CAC to Instr Out 3/4 3825 2700 27000 Air Line (South) 232 Out 3/4 8281 7204 27000 27 6
105 Igstrument Air System N Supply From CAC to Instr Air Line (East) 106 Instrument Air System 233 Out 3/4 8901 7824 27000 29 6
2 N Supply From CAC to Instr.
Air Line (North) 107 Instrument Air Supply 306 Out 1
12183 9043 27000 33 6
Header From CAD Storage Tank Unit 1&2 108 Nitrogen & Off Gas Services 309 Out 3/4 27170 24018 27000 89 Bldg. Instr. Air Interrupt-Out 2
15349 15062 27000 56 able Out 1%
1976 1744 27000 6
6
FINAL STRESS REPORT TABUIAI Sheet No.15 of 16 Job Order Number PROB SYSTEM ISO /
TACATION LINE EMERGENCY CONDITION STRESS [PSIl PRIO-
_REE RKS_
NO, SHEET Ins. or SIZE RITY NO, Outside TOTAL SEISMIC ALLORAELE SEISMIC /
CATEG Coat.
STRESS (DBE)
(1.8 Sh)
ALIDWABLE 109 Core Spray Sys.
524 In 10 13226 6232 26000 23 1
In 10 13770 7362 27000 27 In 10 15824 8830 26000 33 In 10 12642 6234 27000 23 110 RHR 545 Out 4
23765 18128 27000 65 6
Out 4
17334
.t 5000 27000 54 111 RCIC 535 Out 4
13755 7606 27000 28 549 Out 4
5160 794 27000 2
Out 2
8896 5100 27000 18 3
Out 2
6603 1290 27000 4
Out 1
4591 1324 27000 4
Out 1
6080 2662 27000 9
20416 17624 27000 65 RHR Pumps - 2A,B,C & D 565 4
13146 11930 27000 44 6
113 RHR 1A,B,C & D 547 4
12445 9072 27000 34 RHR Drain to RW 548 4
23806 21690 27000 80 6
19799 14074 27000 52 3
RCIC 568 4
17477 8958 28901 31 4
17137 10310 28901 36 115 Condensate Drain N.S.S.
571 3
11374 9420 27000 35 6
116 RHR Pumps 1A & IB 605 2
24752 20878 27000 77 1
Suction Lines 117 Service Water Sys.
606 6
26321 23760 27000 88 1
4 7198 4738 27000 18 118 Service Water Sys.
607 6
15932 13604 27000 50 5
1 4
19645 17400 27000 64 2
2611 116 31500 4
608 6
12432 10180 27000 38 4
6125 3872 27000 14 2
9931 8314' 31500 31 119 Service Water Sys.
609 6
18163 15348 27000 57 2
4 14771 12518 27000 46 120 High Pressure Coolant 657 1
12239 10234 27000 38 Injection System 3/4 5496 4619 27000 17 5
4 261 168 27000 1
121 Service Water 662 6
1486 32 27000 1
4 6
2469 78 33.120 3
3 880 116 33120 4
2 1457 310 33120 1
n FI%\\L E CRESS REPOETABUM Job Order Number Sheet No.16 of i6 PROB S YSTEM ISO /
IDCATION LINE F.MERGENCY CONDITION STRESS QSIl PRIO-RE5%_RKS No.
SHEET Ins. or SIZE RITY NO.
Outside TOIAL SEISMIC ALLOWABLE SEISMIC /
CATEC Coat.
STRESS (DBE)
(1.8 Sh)
ALLOWABLE 122 Instrument Air 674 2
6405 5065 27000 19 1
2053 756 27000 3
6 3/4 2773 1560 27000 6
123 Instrument Air 675 2
10007 8730 27000 32 6
3/4 11262 10112 27000 37 124 Instrument Air 677 2
21584 20244 27000 75 6
125 Instrument Air 690 2
13912 12662 27000 47 1
3675 2468 27000 9
6 3/4 26655 25529 27000 95 126 Instrument Air 679 2
11940 3676 27000 14 6
3/4 8660 506 27000 2
127 Instrument Air 680 2
8153 4817 27000 18 6
128 Ins t rumen t Air 682 2
12316 10975 27000 41 6
lb 1299 2
27000 0
129 Cont. Atmos. Control Sys.
709 24 2962 464 27000 2
6 Sup. Lines 710 20 12551 9450 27000 35 18 2522 298 27000 1
8 15579 11038 27000 41 130 Instrument Air 681 2
11483 10142 27000 38 691 6
)
131 Cont. Atmos. Control Sys.
713 1
20574 14480 27000 54 6
Relie f Valve Piping 2
5408 4000 27000 15 3/4 5180 4000 27000 15 5168 4000 27000 15 132 Service Water 716 1
23143 18610 27000 69 6
1 1457 276 27000 1
Note 1: Total stress below allowable usir g " greater of 1.8 Sh or.9 S,
I
~
May 21, 1979 I
i ATTACHMENT 4 REANALYSIS PRIORITY CRITERIA The following is the criteria that was used to establish the priority for the reanalysis for seismic stress of the safety related piping:
CATEGORY DESCRIPTION Complete 4/24/79 Initial reanalysis of 10 lines Complete 5/21/79 Large pressure boundary lines in speci-s_,/
fled systems and lines with high stress from original analysis.
1.
Other pressure boundary lines 2 " and larger 2.
Other core standby cooling system lines 2 " and larger i
3.
Other RCIC lines 2 " and larger i
4.
Service Water lines 2 " and larger 5.
Pressure boundary, CSCS, RCIC lines
?" and smaller 6.
Other support systems (standby gas treat-ment, diesel generation fuel oil and cooling water, fuel pool cooling line to RHR, containment atmospheric control system, noninterruptible air).
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ATTACHMENT 7 REANALYSIS EVAWATION
SUMMARY
Reanalysis of pipe stress has been completed for 39 lines. All the results are within applicable allowable limits.
In Attachment 2 we have tabulated the results associated with the emergency condition to address in detail the ability of these lines to safely withstand the design basis seismic (DBE) event. A tabulation of original pipe stresses for the combination of all the applicable loading conditions (i.e. pressure, dead weight, seismic, transient, etc.) and the individual seismic loading conditions is provided to determine the variance between the original analysis and the reanalysis.
Specifically the ratio between the piping seismic stress obtained from the reanalysis and the original analysis have been evaluated and the summary is presented in Attachments 8 and 9.
In this evaluation, the results obtained from a reanalysis of ten lines in the Indian Point Nuclear Unit #3 has been considered.
Inclusions of these lines in the evaluation is legitimate since the Brunswick Units and the Indian Point 3 Unit used a) identics1 computer programs in both the original analysis and the reanalysis, b) identical approach to combine seismic excitation components (i.e. one horizontal and f~,}
one vertical component simultaneously) and c) comparable piping configura-
\\_ /
tion complexities.
From this evaluation we believe that a value of 1.5 for the ratio RMC
'*~
presents a realistic upper bound.
To properly evaluate the ability to safely withstand the design basis seismic event for those lines which have not yet been reanalyzed, the above considera-tion on the ratio RMC must be reviewed together with the conservatism used to evaluate the pipe seismic stresses for the DBE conditions. As shown in the foot note, the DBE seismic stresses were obtained by multiplying the values obtained for the OBE condition by 2 (two). This approach was used to minimize the number of computer runs required to a) generate Amplified Response Spectra (ARS) and b) to evaluate pipe stresses. This approach was modified only in those rare cases where the pipe stresses exceeded the appli-cable limits.
/( )
The factor of two is very conservative and therefore the stresses shown in for the lines yet to be reanalyzed for DBE stress are very con-servative.
Since pipe stresses evaluated with a computer code using a modal approach and ARS input (such as the code (s) used) are directly dependent on the values of the ARS, a more realistic approach must consider the actual difference between the ARS for the OBE and DBE.
Figure 7-1, 7-2, 7-3 pro-I vide plots of portions of ARS for the frequency range generally affecting piping systems. These ARS are representative for those elevations of the l
reactor building which contain most of the piping systems under investiga-l tion.
l From these figures it can be seen that the two curves do not significantly differ. This is due primarily to the difference in structural and equipment damping values allowed in the computation of the OBE and DBE ARS.
ATTACHMENT 7 Cont'd A review of these figures indicate that piping with different fundamental frequencies may be affected differently and, in certain cases, DBE stress results may be even less than the OBE stress results. Since, in general, pipe stresses are affected mostly by the first fundamental frequency mode and a representative range for the first fundamental frequency is 4-10 cps, it was concluded that a conservative value of 1.2 for the ratio EARS between the DBE and OBE curves was more representative.
With the above considerations in mind, realistic (but still conservative) values for the DBE pipe stresses can be calculated by multiplying the values shown in Attachment 4 by the factor:
R XR MC
- ARS, g
2 The. actor 2 above brings the DBE stress values shown in Attachment 3 back to the computer evaluated OBE results. The R RS factor accounts for the A
realistic difference between the DBE and OBE ARS and the RMC factor gives g,
,T consideration to the effects introduced by using a square root of the sums F
\\~ /
of the squares approach rather than an algebraic summation for the earthquake component response combinations within each mode.
Since c4 is approximately 1 and the values shown in Attachment 3 in effect will not change, we conclude that the original values for the total stresses are still representative and therefore the capability of the plant to safely withstand a seismic event in the interim is not impacted.
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BSEP SE1SMIC MONITORING PROGRAM ATTACIIMENT 10 An intensive seismic monitoring program was conducted at the Brunswick site under NRC direction and review for approximately 2 years, ending in December, 1977.
The BSEP seismic monitoring program was directed at predicting an earthquake by identifying precursory phenomena.
After nearly two years of seismic analysis, applying state-of-the-art techniques, the NRC granted CP6L's request to terminate the seismic program, stating that "The data reported does not indicate dilatency r
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or other earthquake precursory phenomena is occurring in the Wilmington-Southport area." -(Letter:
A. Schwenscer to J. A. Jones, December 28, 1977).
The staff's safety evaluation further stated, "The lack of detection of such local earthquake activity by the network combined with the low level of recorded historical earthquake activity in this region suggest a low earthquake potential for the region."
The lack of precursory anomalies is significant, in that the duration of a precursor anomaly is related to earthquake magnitude.
For
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example, an event with Richter magnitude 5 is preceded by an anomaly spanning about 4 months, whereas a major earthquake at about magnitude 7 would be preceded by an anomaly lasting about 14 years.
Thus, even if a precursor were detected this week, the maximum earthquake magnitude that would be expected by August 21 would be less than magnitude 5.
This is_ equivalent to a ground acceleration of about 0.04g's, The OBE is 0.08g, and the DBE for BSEP is 0.16g.
The ongoing seismic monitoring program at our Shearon Harris site, (which commended in September 1977) has a detection threshold such that it can detect seismic precursors in the Southport area.
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No seismic events have been recorded by the BSEP or SilNPP Network, or the USGS network in South Carolina; and the SilNPP monitoring program continues l
t to support the conclusion that the Southport area is unusually aseismic.
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