ML19241B155
| ML19241B155 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/06/1979 |
| From: | Bevan R, Bevan R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7907110745 | |
| Download: ML19241B155 (5) | |
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UNITED STATES
's NUCLEA'l REGULATORY COMMiss!ON f$
WASHINGTON, D. C 20555 wgp#
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JUNE 6
1979 Docket flos. 50-324 and 50-325 LICEf4SEE:
Carolina Power & Light Company FACILITY:
Brunswick Units fios. 1 and 2
SUMMARY
OF MEETT. fig 4 ELD Of4 MAY 21, 1979 1.-
2 :.
A meeting was held with representatives of Carolina Power and Light Company (CP&L), General Electric Company (GE) and United Ent 1 and Constructors (UE&C) in Bethesda, Maryland on May 21, 1979.
.ne purpose
~u of the meeting was to discuss further the results of the seismic stress reanalysis being conducted for Brunswick Units fios.1 and 2 (BSEP) in response to IE Bulletin 79-07.
The ceeting was a followup of a meeting held on May 16, 1979, at the conclusion of which CP&L agreed to provide further information at this May 21, 1979 meeting, A list of attendees at the meeting is enclosed.
Also enclosed is a CP&L letter dated May 21, 1979, with attachments, which address the items identified in the May 16, 1979 meeting to be addressed at this May 21, 1979 meeting.
CP&L reported that seismic pipe stress reanalyses using ADLPIPE-II code had been completed for 39 lines out of a total of 171 line; that are to be reanalyzed.
The recalculated loading for all lines rer.nalyzed is within allowable when using an appropriate factor to comrute NE stresses from OBE stresses (See Attachment 2 of Enclosure i.
CP&L also presented a table showing the o.iginal seismic stress and estimated total stress after reanalysis for the remaining 132 lines yet to be reanalyzed (See Attachment 3).
The priorities for the reanalyses and a discussion of the bases for the assigned priorities was given (See Attachment 4).
The reanalysis of the loading on the pipe supports for the original 10 lines whose stresses had been reanalyzed had not yet been completed, but the reanalyses are underway.
Reanalyses of these (approximately 100) pipe supports is to be completed and reported by May 25, 1979.
CP&L affirmed that the recirculation line supports reanalyses have been completed, and loading is within allowable.
30B 005
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Meeting Summary Confidence that the "as-designed" (drawing) accurately reflects the "as-built" configuration was discussed.
CP&L described in detail the QA/QC program in effect to assure that the current reanalysis from current drawings is applicable in every case to the "as-built" condition (See Attachment 6).
The staff discussed the results of the IE inspection to verify accurate "as-built" drawings.
The IE inspection results supported the licensees statements.
The staff verified in discussion with GE that, where the PISYS code had been used to reanalyze that piping within the GE scope of supply, the algegraic sunnation method had not been used. Verification of the PISYS code by benchmark problems has not been done.
CP&L presented a detailed schedule for completing tFe work on all piping and supports that are programmed for reanalysis.
The entire effort, including evaluation, licensee conclusions, and final report, will be completed by July 21,1979.
CP&L said they would provide by May 22, 1979 a letter to document and confirm several commitments made at this meeting. The letter would formalize the verbal commitment to perform inspections and compare "as-built" and "as-analyzed" for those 39 lines that have been reanalyzed and the 132 lines yet to be analyzed.
The letter would also document statements made by CP&L at the meeting concerning reanelyses of the Unit No.1/2 recirculation loop - namely, that CP&L has written verification that GE reanalyzed the pipe and supports of the recirculation loop using PISYS codes and all pipe and support loads are within allowable.
CP&L also agreed that by COB May 25, 1979, they would document the
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results of reanalysis of the approximately 100 support loadings on the
~
first ten lines analyzed by UE&C. Their May 25, 1979 submittal also would include results of line verificat.un ("as-built" verifications) conducted by IE on May 18 and 19,1979.
Finally, CP&L agreed to address in the May 25, 1979 submittal the CP&L management action to be taken in the event that a problem is identified in the caritinuing reanalysis program.
308 006
Meeting Summary...
At the meeting the staff corr.luded that sufficient assurance exists regarding health and safety 'f the public to allow Brunswick Units Nos.
1 and 2 to continue operating pending receipt of the confirmatory letter of May 25, 1979.
ve, J R. Bevan Acting Project Manager Operating Reactors Branch #3 Division of Operating Reactors
Enclosures:
1.
List of Attendees 2.
Letter from CP&L to NRC dated May 21,1979 with 10 Attachments
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308 007
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Attendance NRC/ CPL Of1 BRUf1SWICK 1 AllD 2
.r.
Seismic (Response to I&E Bulleti' 79-07)
CP&L P. W. Howe B. J. Furr D. B. Kincaid
~
D. B. Waters D. L. Bensinger M. A. Connor UE&C I
H. Jreider G. Rigamonti B. J. Huselton
_CE fl. Shirley G. Mok sm f!RC R. Bevan
==
K. Herring J. Fair K. Wichman
=
J. Glynn fgtt M. Hartzman
- E==
A. Lee
!.E V. floonan B. D. Liaw E. Jordan r
T. Ippolito G. Cunningham W. Russell D. Eisenhut 308 008
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File:
NC-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 Statas Nuclear Regulatory Commission Washington, D. C.
20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 and 50-324 LICENSE NOS. DPR-71 AND DPR-62 SEISMIC ANALYSIS OF SAFETY-RELATED PIPING
Dear Mr. Ippolito:
This letter supplements our letters of April 24, 1979 and Kay 16, 1979 on the Carolina Power and Light Company's response to IE Bulletin 79-07.
It audresses 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 f rom the evaluation of the technical informatior. available.
It was determined that algebraic sum =ations were used in the seismic stress analyses portion of the computer cc.de that was used in the original analysis.
Realizing that a total reanalysis could not be completed in the time frame require 3 to respon'd to-the bE11etin ' ten ~(10)~ lines were
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selected tor reanalfs~is in order tFdete7mine the ~effect of algebraic summation.
The computer cod'e currentlf fn~Tise"bv Uni ted Fn6 f ncern A
?oHst r uc t ors _, 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 T10) lines was based on line function, size, and'ab'11ffv to project adequacy foF other lines of similar function and~sfze.
This criteria is explainedin
~
more cetaWorrArtachmeat 1.
bubseqEent to our71ay 16tn c:cErtug, addirid~nal' 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 mHRimum sels5Ic stress component of each line for the original analysis and the reanalysis.
In all cases, the calculated total stresses for the design basis earthquake are less than the allowable.
Another item discussed at our May 16th eeeting 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
~2-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 dif ferent were ider.tified and will be reanalyzed separately for each unit.
The totcl number of computer problems for Units 1 and 2 is 171 (with 39 already completed). 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 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 b
'.lt" design.
The quality assurance program used during construction, an, in effect today, uses a " walk off" of each as installed system or modification.
This inspection identifies discrepancies be: ween 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.
Af ter a thorough review of the original seismic piping design criteria, and the reanalysis of selected significant safety class piping, CP&L has concluded enat 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 proviued in the original piping design, as discussed in Attachment 7.
2.
The satisfactory results of the reanalysis of 39 selected maj or lines.
The reanalysis shown in Attachment 2 represents approximately 60% of the lines 2b" and over in the pressure boundary and approximately 40% of the lines 2b" and over in the emergency core cooling systems.
3.
An investigation of the as built versus as analyzed conditions.
308 010
,Mr.
T..A.
Ippolito May 21, 1979 SERIAL:
CD-79-1342 4.
Tne aseismic natute of the site as confirmed by an extensive on site and reg.onal seismic program.
See Attach ent 10.
3 schedule of pipe reanalysis. Tne final report 5.
The accelerated will be filed ou July 21, 1979.
Interim reports of results of reanalysis will be filed at the completion of the reanalysis of each category.
Yours very truly,
~ //L Y
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B. J. Furr
- Manager, Generation cc:
Mr. James P. O'Reilly NRC Region II Office of Inspection & Enforcement 308 011
May 21, 1979 ATTACHMEh'r 1 IhTILAL REANALYSIS SELECTION CRITERIA RITERIA BASIS Function Major operating system with Pricary Pressure Boundary (Mainsteam, Feedwater and SRV Line) or Safe Shutdown System (EPCI, 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 unalyses 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) 308 012
ATTACHMEhT 2 L,D,*
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PIPE STRESS REEVAIDATION SU' MARY N=
l 3 I Lehl Li;E, EFERGENCY CONDITION (PSIT SYSTEM 150 SIZE ORIGINAL ORIGINAL 3
NEW NAME NO.
(NPS)
TOTAL SEIS'1IC TOTAL SEISMIC ALIDWABLE Fbin Steam 1MS-15B 24 10724 3942 10640 3858 27000 Safety / Relief Valve SRVL-121 10 & 6 23012 12280 21910 11180 27000 Safety / Relief Valve SR71 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 l 24316 20270 27000 Feedwater FW-16 18 & 12 18007 12420 20028 13296 27000 Residual Heat RRR-6 20 19406 13582 12644 6820 27000 Removal Core Spray l CS-24 10 16952 10076 l 14366 7490 27000 High Press Cool HPCIS-17 14 12200 6446 12502 6748 27000 Iniet High Press Cool HPCIS-510 14 & 12 & 10 12004 7994 12092 80S2 27000 Inlet High Press Cool HPCIS-10 14 & 12 & 10 9733 3886 11152 5530 27000 Injet Residual Heat RRR-1 24 & 20 24094 18584 17972 14366 l 27000 Removal I
Residual Heat RHR-2 20 & 16 & 12 13309 7654 11471 5948 27000 Repocal Residual Heat RHR-5 24 9848 3896 9514 2960 27000 Removal Residual Heat RHR-25 4&6 18558 12904 18530 12876 27000 Removal NuclearSteamSuppl%NSS-14 24 & 10 14745 8446 16335 10036 27000 Safety / 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 Removal Reactor Core Isolat.
RCIC-21 3
7603 3588 7601 3586 27000 Cool Resid Heat Rea Draid RHR-173-B 1
3808 2186 3838 2216 27000 Line i
Residual Heat RHR-28 20 & 16 & 12 15298 8814 13626 7142 27000 Removal Nuclear Steaa Systen NSS-15 24 10974 4420 10458 3904 27000 lLine C S-20 Nuclear Steam System 10 & 6 19443 8902 17899 8298 27000 High Press Cool HPCIS-4 3 6 6 & 10 23609 20876 25481 22748 27000 Injet.
& 12 308 013
ATTACHMEIH 2 Cont'd LINE EMERGENCY CONDIT ION (PSI)
SYSTEM ISO SIZE ORIGINAL ORIG IML NEW NE'4 NAME 50.
(IPS )
TOTAL SEISMIC TOTAL SEISMIC ALIITJABIE 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)
Pesidual 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 Residual Heat RRR-13 4 & 8 & 14 12532 10018 12620 10106 27000 Removal Residual Heat RRR-59 4 & 6 & 10 12664 9970 13344 10650 27000 Removal
- Residual Heat RHR-60 4 & 6 & 10 34618 33658 32971 32012 27000 Renoval Residual Heat RHR-168 1
23580 22658 26910 26198 27000 Removal Residual Heat RHR-61 4 & 6 & 3/4 21117 17038 19393 15314 27000 Removal High Pressure HPCI-ll 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 & lk & 1 24519 24118 24559 24156 27000 Isol. Cooline NOTE:
Seismic stresses shown are obtained by multiplying the OBE Seismic Stresses by 2.
Total stresses are within allowable using applicable factor 8
014 to compute DBE stress from OBE stresses.
ATTACIIranrf 3 F I NA L S T REM,RJgORT_T_ABU IA_T_I,0)!
Sheet No.1 of 16 Job order Number IDCt T_IOj! LIITE EMERGENCY CONDITION STRESS QS_Il PRIO-PM\\_R)iS PRO 3 SYSTEM 150/
1 NO.
SilEET Ins. or SIZE RITY NO., Outside TorAL SEISMIC A LLOWA BLE SEISMIC /
CATEC
' EIEWA3hE 1
Coat.
S3 ESS (DBE)
(1.8 Sh) 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, D ra in Inside Dry Well 128 In 2
24225 20022 2/000 74 1
(East) & West)
In 1 1/2 8345 5838 27000 21 In 1
15171 12006
- 7000 44 76 Control System - NSS 7
In 3/4 17945 12954 25900 50 (Inst. Sensinn Iline) 3 Residurl llent Removal 43 Out 4
6434 3732 27007 13 Minimum Flow By-Pass Out 4
3288 1762 27000 6
RHR Pumps 2A & 2C Out 3
21856 16332 27000 60 4
Residual llent Removal 44 Out 6
9536 6784 27000 25 2
Torus Spray (South) 5 Residual llent Removal 45 Out 4
14859 12378 27000 45 Drain Piping - RilR Pumps Out 4
18562 12462 27000 46 2B, 20 6
Residual lle n t Removal 46 Out 4
21248 17250 27000 63 Drain Piping - RllR Pumps 2A, 2C 7
Residual lleat Rcmoval 47, out 4
18944 15888 27000 58 (Cross Conn. Drain Piping 48 Out 4
20325 17512 27000 64 RIIR Pumps 2A, B,
C, D&
RilR Drain Conn. to Rad-waste) 8 Residual llent Removal 65 Out 4
3335 928 27000 3
CfWon s Conn. Drain Piping C3DIR Pumps 2A, B, C, &D C3huth Co. 20R CD
FINAL STRESS hEPORT TABULATION Sheet No. 2 of 16 Job order :: umber I
PROB SJSlPL ISO /
IqCA_T_I,0)J LINE HERGENCY CONDITION STRESS QSIl PRIO-RD11RK_S NO.
SilEET Ins. or SIZE RIT Y
~~~~
NO.
Outside TOTAL SEISMIC A LLD'4AB LE SEISMIC /
CATEG Coat.
STRESS (DBE)
(1.8 Sh)
ALLOWABLE 9
Residual llent Removal 51 Out 6588 3222 27000 11 2
(Torus Sprav - North)
I 10 Residual IIcat Removal 54, Out 4
14082 7416 27000 27 (liend Spray Line) 55, Out 4
5922 1946 27000 7
56 Out 4
13253 2532 28800 8
2
'/4 8048 4274 28800 14.
Out Out 3/4 8289 4914 27000 18 11 Residual llent Removal 57, Out 4
21987 17544 27000 64 2
(RllR Exchgr 2A to RCIC 58 Out 4
11899 7846 27000 29 Suct.)
12 Residual llent Removal 170 Out 1
19175 18076 27000 66 Relief Line Around Valves out 1
11735 9560 27000 35 5
F004A & C Out 14138 13930 27000 51, __
13 Residual llent Removat 171 Out 1
3005 1694 27000 6
Relie f Lines Around Valver Out 1
5232 3334 27000 12 F004B & D Out
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1446 1260 27000 4
Relief Lines From RllR Out 1
3298 1596 27000 5
Exchgr 2A, 2B Out 3/4 4063 1762 27000 6
14 Residual !! cat Removal 172 Out 1
10005 7116 27000 26 Side Vent & Sample Conn.
Out 1
12998 9904 27000 36 Exchers 2A, 2B tr4 O
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FINAL STRESS REPORT TABULATION Job Order Number Sheet No. 4of 16 I'RO B SYSTEM ISO /
IDCATION LINE EMERGENCY CONDITION STRESS QSIl PRIO-Rett \\ RKS N0 SilEET Ins, or SIZE RITY NO.
Outside TorAL SEISMIC A LLOWABLE SEISMIC /
CATEG Coat.
STRESS (DBE)
(1.8 Sh)
A LIDWA BLE 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 3Q 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 1h 3'03 3128 27000 11 Condensate Pump Disc. to Out 3/4 4471 3552 27000 13 l
Suppression Chamber 26 Reactor Core Isolation 195 Out 1
16705 15826 27000 58 Cool. Turbine Drains &
Relief Lines 27 Reactor Core Isolation 12 Out 6
19870 16526 27030 61 Cool. (RCIC Pump Suction Out 6
4391 150 27000 0
3 Lines)
Out 6
16311 12594 27000 46 28 l!igh Press. Coolant Inj.
9 Out 24 10395 4268 27000 15 (Exhaust Steam Line)
Out 20 11629 7672 27000 28 2
Out 18 3707 1680 27000 6
Out 16 4467 614 27000 7
29 High 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 tja c:D Out 3/4 3753 1272 27000 5
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Out 3/4 3708 1258 27000 5
Out 3/4 3127 567 27000 2
Out 3/4 2303 254 27000 1
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FINAL STRESS REPORT TABUIATION Sheet No.7 of 16
. inh Ordar 'Nmber Pron SYS_TJ L ISO /
MCA_T,I,0j LINE EERGENCY CO DITION STRESS (P,SIl PRIO-RE" \\,p'E NO.
SHEET Ins, or SIZE -
RITY
~ ~ ~ ~
NO.
Outside TOTAL SEISMIC A LIONABLE SEISMIC /
CATEC Cont.
STRFSS (DBE)
(1.8 Sh)
A LIDWA B LE7, i
47 Core Spray System 40 Out 3
16187 12944 27000 4'
(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 23)
Out 2
25235 22438 27000 83 49 Core Spray System 166 Out 2
4185 868 27000 3
'Make-Up Demin Water for out 1
4105 2850 27000 10 Pump ZA)
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
tra CD CC CD N
FINAL STRESS REPORT TABUIATION
. lob order ::umbe r Sheet No.8 of 16 PROS SYSTEM ISO /
p]CA_TI_0_IJ LINE
_Fl{ERGENCY C0:DITION STRESS QS_Il PRIO-REjp_lpiS
~~~~
SHEET Ins. or SIZE RITY
- 0 NO.
Outside To rAL SEISMIC A LIDUA BLE SEISMIC /
CATEG Coat.
SErgS_
(DBE)
( 1. 8 Sh)
A LIDWA BLE 50 Residual Heat Removal and 29 Out 20 4397 332 27000 1
Service Water Out 16 10822 5214 27000 19 4
(Cooling H O f r 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 "iping, Exegr 2A) 52 Service Water 85 Out 16 11781 7292 27000 27 RHR Service Water Out 12 7503 3632 27000 13 Pumns 2B & 2D Out 8
3436 5262 27000 19 4
31 Service Water 86 Out 16 6271 3778 27000 13 tsa RHR Service Water Out 12 7062 3826 27000 14 5098 27000 18 4
c)
Pumns 2A & 2C Out 8
7875
_ 25810 27000 95 Note 1 C9 Service Water 82, out 20 29536 Salt Water Supply to RHR 83, out 16 11672 9262 27000 34 Service Water Pumps (South) 84 out 14 4760 3300 27000 12 4
CZ)
Out 24 17987 15900 31500 50 rsy Out 8
992 216 31500 0
rs)
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)
Our 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 Roam Cooler 2B)
Out 4
14224 L1798 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
10582 7660 27000 28 Out 3
15073 13466 31500 42 4
FINAL STRESS REPORT TABUIATION
.Tob Orde r :;umbe r Sheet No. 9 of 16 l' ROB SYSTEM ISO /
IDQiTION LINE EMERGENCY CO!TDITION STRESS (PSIl PRIO-RER\\RKS
- o.
SHEET Ins. or SIZE RITY
~~~~
NO.
Ourside TOTAL SEISMIC A LIDNABLE SEISMIC /
CATEC Cont.
STRiiSS (DBE)
(1.8 Sh)
A LTDWA BLE 60 Service Water System 142A Oat 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 Pumos 2A,
B, C,D 142C Out 1b 11892 10312 31500 32 4
61 Service Water Supply and 162 Out 6
1595 37 27000 0
Return IIcaders At RllR Pump out 6
1373 1
31500 0-Room Coller 2A Out 3
1095 15, 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 Wuter Supply and 163 Out 6
1567 490 27000 1
Return tieaders At RIIR 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 Water RllR Pumps 214 Out 2
9846 8568 32400 26 2B, 2D t,a Out 1
7102 4740 32400 15 c:D out 1
5632 3474 32400 11 CI)
Out 3/4 18217 17338 32400 54 Out 2
4304 3660 32400 11 Out ik 6256 5630 32400 17 7)
Out 1
18556 17610 32400 54 ps3
(,a Out 3/4 17955 17568 32400 54 6
64 Service Water RllR Pumps 215 Out 3/4 19128 15778 33660 46 2A, 2C Out 1
11897 9012 33660 26 Out 1h 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
FINAL STRESS REPORT TABUIATION Job Order umber Sheet No.
10 of 16 PR03 SYSTEM ISO /
IACATION LINE EMERGENCY C0!P'ITION STRESS (P_S I,),
PRIO-REM \\RKS NO.
SilEET Ins. or SIZE RITY NO.
Outside TOTAL SEISMIC A LLOWA BI.E SEISMIC /
CATFf3 Coat.
STRESS (DBE)
(1.8 Sh)
ALIEUAULE 65 Service Water Well Water 216 Out 1
10090 8214 31500 26 Conn. To vital Service out 1
2840 1182 31500 3
lleader 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 31500 0
4 67 Servica Water R11R Service 218 Out 2
1559 746 33800 2
Water Pumps 2A, 2B, 2C, 2D out 1b 18318 15052 33800 44 6
68 Service Water Supply and 300 Oum 14 4791 1262 27000 5
Return linkt 1&2 301 Out 10 14310 10898 27000 40 c:p 302 Out 4
7539 4284 33228 16 C%)
Out 3
' '+ 17 5 10932 33228 33 Out 2) 10823 7610 33228 23 Out 2
15776 12572 33228 38 c)
Out 1
16182 13020 33228 39 ps) 22 Out Ih 10466 7318 33228 22 4
69 Service Water 62 Out 20 4515 200 27000 0
(Coolinr,.Jater Return -
Out 16 5879 3318 27000 12 South)
Or.:
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 Cle,-up 13 2 In 2
9690 6548 27000 24 (Reactor Drain & Cenn. To In 2
17800 13618 25920 52 5
Reactor Water Clean-up
FINAL STRFSS REPOR. TABUIATION Sheet No. 11 of.16 Ioh O rde r ';umbe r O PA B' RY3 REM ISO /
IDCATION LINE EMERGENCY CONDITION STRESS (2S_I_1 PRIO-RER\\RNS
- 21. _
SilEET Ins, or SIZE RITY NO.
Outside TorAL SEISMIC A LIDWABLF SEISMIC /
CATEG Coat.
STRESS (DBE)
(1.8 Sh)
A LIDWABLE 72 C.R.D. Ilydraulic 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 Ib 18419 14068 27900 52 1
(Liquid Control Pump Disch.)
74 Fuel Pool 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 RilR Sys tem)
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 W
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FINAL STRESS REPORT TABUIATION Sheat No.13 of 16 Toh Oriter ':nnb e r PROB S YST EM ISO /
IDCATION LINE EMERGENCY COIDITION STRES' (PSI)
PRIO-REM \\RKS
,a, SllEET Ins, or SIZE RIT Y
~~~~
NO, Outside TorAL S tit SNIC A LI AWABLE SEISMIC /
CATEC Coat.
STRESS (D"E)
(1.8 Sh)
A LIDUA B LE Instrument Air System 174 Out 2
2496 2492 27000 9
6 84 Inlet Line To Air Receiver 85 Instrument Air System 17 5 Out 2
4699 3448 27000 12 Outlet Line f rom Air Out 3/4 14973 13812 27000 51 6
Receiver 86 Instrument Air System 176 Out 2
2454 1204 27000 4-6 Supply Line (South) j Instrument Air System 177 Out 2
16406 15036 27000 55 87 Supply Line (South)
Out 3/4 3153 2028 27000 7
East o f 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 - P! ping Out 2
8323 7078 27000 26 89 Instrument Air System 179 Out 2
2459 23348 27000 86 l
f Supply Line (NorthT West out 3/4 2687 1562 27000 3
6 Note 1
" L" 90 Instrument Air System 180 Out 2
9614 8364 27000 30 Supply Line (North) East Out 3/4 2679 1554 27000 5
6 i
n y,n 91 Instrument Air System 182 Out 2
20284 19034 27000 70 6
Supply to Air Reevr Co R"
92 Instrument Air System 1E 3 Out 2
9398 8148 27000 30 Supply I.ine (North)
Out 3/4 14961 13836 27000 51 6
93 Instrument Air System c:2
__1!i4 In 2
30632 29382 27000 108 I'd In 3/4 9353 8228 27000 30 Note 1 Supply Ucader (North) 183 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 lle, der (South) 95 Instrument Air System 188 In 2
9596
~~ 8346 27000 30 Pipe to Accum. A1001C&D 189 In 1
3719 24512 27000 90 Pipe to Accum A1001A&B In 1
__ o209
_15068 27000 55 6
96 Instrument Air System 190 Out 2
20860 19610 27600 72 Note 1 Supply Lines to Filters Out 1
7629 6422 27000 23 D-0005 and D-0006 Out 3/4 30507 29382 27000 108 6
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2 22 4200 75 00 7
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FINAL STRESS REPORT TABUIATION
.Toh Order : umber Sheet No. 15 of 16 PROB MTF1 ISO /
M Q TI_Ojj LINE Fy:RGENCY CODITION STRESS QS,Il PRIO-RE51\\RFJ d1._ _
SHECT Ins, or SIZE RIT Y No.
Outside TOTAL SEISStIC A LLONAB LE SEISMIC /
CATEC Coat.
STRr2SS (DUE)
(1.8 Sh)
A LTONA B LE 109 L re 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
Cat 4
17334 15000 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
112 RHR Pumps - 1A & 1C 546 4
20416 17624 27000 65 RllR Pumps - 2A,B,C & D 565 4
13146 11930 27000 44 6
113 RllR 1A,B,C & D 547 4
12445 9072 27000 34 RHR Drain to RW 548 4
23806 21690 27000 80 6
114 RCIC Conn. to P.J 563 4
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 RIIR Pumps 1A & IB 605 2
24752 20878 27000 77 1
Suction Lines 117 S e rv ic e ya4p r Sys.
606 6
26321 23760 27000 88 1
cc?
4 7198 4738 27000 18 118 Se rv ice WsI2r Sys.
607 6
15932 13604 27000 50 5
4 19645 17400 27000 64 2
2611 116 31500 4
7) 608 6
12432 10180 27000 38 7) mr) 4 6125 3872 27000 14 2
9931 8314 11500 31 119 Se rvice Wate r Sys.
609 6
18163 15348 27000 57 2
4 14771 12518 27000 46 120 ligh Pressure Coolant 657 1
12239 10234 27000 38 Injection System 3/4 5496 4619 27000 17 5
\\
261 168 27000 1
121 service Water 662 6
1486 32 27000 1
4 6
2469 78 33120 3
3 880 116 33120 4
25 1457 310 33120 1
UNIT #1 FI'ul STRESS REPORT TABULATION Sheet No.16 of 16
!ob Order tmher PROB SYSTEM ISO /
LO MTIO:: LINE EMERGENCY CO:DITION STRESS QSIl PRIO-REMARKS
- 0 SHEET Ins. or SIZE RITY
~~~~
No.
Outside TOTAL SEISMIC A LLOL'A B LE SEISMIC /
CATEC Coat.
STRESS (DBE)
(1.8 Sh)
A LIONA BLE 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 0112 27000 37 124 Instrument Air 677 2
21584 20244 27000 75 6
125 Ins t rument Air 690 2
13912 12662 27000 47 1
3675 2468 27000 9
6 3/4 26655 25529 27000 95 126 Instrument Air 679 2
1.1940 3676 27000 14 6
3/4 8660 506 27000 2
127 Instrument Air 680 2
8153 4817 27000 18 6
682 2
12316 10975 27000 41 6
128 Instrument Air Ik 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
205/4 14480 27000 54 6
Relie f Valve Piping 2
5408 4000 27000 15 3/4 5180 4000 27000 15 5168 4000 27000 15 132 Se rv i c e Water 716 li 23143 18610 27000 69 6
1\\
1457 276 27000 1
Note 1:
Total stress below allow tble usit g "gr. ater of 1.E Sh r.9 S s v4 O
CO Ova O
May 21, 1979 ATTACIDIENT 4 REANALYSIS PRIORITY CRITERIls 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-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 3.
Other RCIC lines 2V' and larger 4.
Service Water lines 2 " and larger 5.
Pressure boundary, CSCS, RCIC lines 2" and smaller 6.
Other support syt
'-tandby gas treat-cent, diesel generation fuel oil and cooling water, fuel pool cooling line to RHR, containment atmospheric control system, noninterruptibic air).
?> 08 03I
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REQ U t RED blO STRESS R EPORT
}Oh U P D AT E tF R E Q u t R ED l
ATTACFDELT 7 REAGALYSIS EVAIL. TION SD' MARY Reanalysis of pipe stress has been completed for 39 lines.
All the results are within applicable allowable limits.
In Attachment 2 ce have tabulated the results associated with the caergency condition to ad iress 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 t!.e variance between the original analysis and the reanalysis.
Specifically the ratio between the piping scistic stress obtained from the reanalysis and the original analysis have been evaluated and the sum =ary 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 ihe evaluation is legitimate since the Brunswick Units and the Indian Point 3 Unit used a) identical computer programs in both the original analysis and the reanalysis, b) identical approach to combine seismic excitation components (i.e. one horizontal and 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 Re",
re-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-tien 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 numbe r of compute r runs re qu i red 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 factar of two is very _onservative and therefore the stresses shown in for the lines yet to be reunalyzed 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) use..) 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-vide plots of portions of ARS for the frequency range generally affecting piping systems. These ARS are representative fcr those ele eations of the reactor building which contain most of the piping systems under investiga-tion.
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 C3E and DBE ARS.
303 034
ATTACIDE!7T 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 costly by the first fundacental frequency code and a representative range for the first fundamental frequency is 4-10 cps, it was c
- luded that a conservative value of 1,2 for the ratio R ns A
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 cultiplyir; the values shown in Attachment 4 by the f actor:
E IE MC ARS g
2 The factor 2 above brings the DBE stress values shown in Attaclu:ent 3 back to the computer evaluated OBE results.
The RjaS factor accounts for the realistic difference between the DBE and OBE ARS and the Rgc factor givec consideration to the ef fects introduced by using a square root of the sun; of the squares approach rathe; than an algebraic su==ation for the earthquake cocponent response combinatio:u within each mode.
Since O( is approximately 1 and the values shown in Attachrent 3 in effect will not change, we conclude that the original values for the total stressas are still : 2presentative and therefore the capability of the plant ;o safely withstand a scismic even in the interim is not impacted
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BSEP SEISMIC MONITORING PROCPJOi ATTACHMENT 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.
Af ter nearly two years of seismic analysis, applying state-of-the-art techniques, the NRC granted CP&L's request to terminate the seismic program, stating that "The data reported does not indicate dilatency or other earthquake precursory phenomena is occurring in the k'ilmington-Southport area." -(Letter:
A. Schwenscer to J. A. Jones, December 28, 1977).
The stars safety evaluation further stated, "The lack of detection oi
.n 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 example, an event with Richter magnitude 5 is preceded by an anomaly spanning about 4 months, whereas a major earthquake et about magnitude 7 would be preceded by an anomaly lasting about 14 years.
Thus,,q if ]Iy k a precursor were detected this week, the maximum earthquak_ a
.itude 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 f or 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.
t' "3 fi
9' No seismic events have been recorded by the BSEP or SliNPP Network, or the USGS network in South Carolina; and the SliNPP monitoring program continues to support the conclusion that the Southport area is unusually aseismic.
042 308