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g ic oq'g UNITED STATES 4
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NUCLEAR REGULATORY COMMISSION o
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'... E ADVISORY COMMITTEE ON REACTOR SAFEGUARDS k% ***** /[
WASHINGTON, D. C. 20555 July 2, 1979 ACRS MEMBERS NRC COMMISSIONERS' BRIEFING ON SEISMIC DESIGN CAPABILITY OF OPERATING REACTORS AND RESPONSES TO OIE BULLETIN ON SEISMIC ANALYSIS -- MR. DARRELL EISENHUT, DEPUTY DIRECTOR, NRC/ DOR This briefing on June 28, 1979 consisted of NRC/ DOR representatives presenting status reports on the seismic concerns at operating reactors.
-Chairman Hendrie and Commissioner Gilinsky were the only Commissioners present.
NRC/ DOR has six major activities ongoing concerning seismic problems or concerns with operating reactors. These activities are:
- 1) IE Bulletin 79-02, baseplates flexibility and anchor bolts; 2) IE Bulletin 79-04, Velan valve weights; 3) IE Bulletin 79-07, algebraic summation of seismic loads; 4) Maine Yankee seismic design; 5) systematic evaluation program; and 6) Union of Concerned Scientists petition for seismic reanalysis.
Each one of these activities was specifically addressed to the Commissioners.
1)
IE Bulletin 79-02, Baseplates Flexibility and Anchor Bolts The operating reactor organizations were requested to address flexibility and factor of safety used in their baseplate and anchor bolt design for piping supports. A response is due by July 6, 1979 so only preliminary results are available at present.
It appears that some reactors have extensive installation defects such as entire supports missing, bolts missing from supports, improper alignment of supports, and inadequate thread engagement of bolts.
2)
IE Bulletin 79-04, Velan Swing Check Valve Weight This bulletin identified the fact that Velan had given an incorrect valve for the weight of some of their swing check values. This error could result in inadequate supports for piping with the Velan valves installed.
The response to the bulletin has been received from all operating reactors. A total of 48 of the 65 plants used the Velan valves.
However, only 5 plants required modification (1 hanger redesign and miscellaneous hanger adjustments). Some plants which are currently shut down have not responded to this bulletin.
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- 3) IE Bulletin 79-07, Algebraic Summation 1
This bulletin resulted from the ordered shutdown of 5 operating reactors for using algebraic sumation of seismic loads rather than the more conservative square-root-s'um-of-the-squares technique. Only Maine Yankee has been allowed to start up subsequent to the shutdown order.
However', Maine Yankee still may be required to perform additional seismic analysis of the piping supports as discussed in activity 4) below.
i Surry 1 is in the process of reanalyzing and expects to be finished l-by August 1979. Operation is expected to resume in September 1979.
l Eleven of the 42 problems identified so far have required hardware 1
modifications. Of the 11, only 1 was related to the use of. algebraic l
summation. The others resulted from as-built conditions.
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Surry 2 is down for steam generator replacement and no schedule has j
been established for response to this bulletin at present.
Beaver Valley has requested permission for operation while modifica-tions are being made. This proposal is under review and it appears
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operation may begin shortly.
I Fitzpatrick is expected to request permission for operation while l
. modifications are being made. However, they have not finished their analysis but expect completion in July.
1 A total of 25 operating reactors used the algebraic summation technique in their seismic analysis. Of the 25, only 5 were ordered l
shut down because of the extensive use of the technique. Four j
additional reactors were found to have used algebraic summation extensively; however, they were already shut down for various reasons. Those 4 units (Brunswick 1 & 2, Indian Point 3 and Salem 1) were not allowed to start up until they had satisfied NRC with the conservatism of their piping analysis. The other reactors had used the algebraic summation on only a very limited number of pipes and have therefore been allowed to continue operation. NRR has satis-factorily completed review of 16 of the 25 operating plants to date.
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- 4) Maine Yankee Seismic Design l
Maine Yankee was found to have used the Housner Spectra anchored at j
0.1g in the seismic design analysis. By today's Regulatory Guide 1.60, the spectra anchor would be between 0.13g'and 0.20g. This
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raised some concern at NRC/00R, but the overall conservatism has l
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been accepted based on the fact that the Housner Spectra when combined with the Maine Yankee assumed damping values is roughly comparable with Regulatory Guide 1.60 when combined with NRC required damping values. The NRC Staff, therefore, allowed Maine Yankee to start up but they are continuing their review of this situation.
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- 5) Systematic Evaluation Program (SEP) Status The SEP revealed some interesting information about older plants being reviewed. Two of the plants have no specific seismic design basis (Lacrosse and Yankee Rowe). Two of the plants (Big Rock Point and Dresden 1) were designed to the Uniform Builders Code (UBC) which does not require seismic response spectra analysis, only static analysis.
These reactors can be expected to survive an earthquake, however, since the static pressure load design gives them an inherent resistance to seismic loads. At NRC request, the licensees are instituting analytical studies to confirm or deny the seismic capabilities of these older plants.
- 6) Union of Concerned Scientists (UCS) Petition for Seismic Reevaluation This petition is being reviewed by NRC/ DOR and a response is being prepared. The concerns raised by the petition are very similar to the concerns being addressed by NRC presently on operating reactors.
Based on the as-built problems found with the piping supports, NRC Staff is issuing an IE Bulletin for operating reactors to require a detail review of all 2" and larger safety system lines for "as-built" conformance and design assumption conformance, especially as it relates to seismic analysis. The as-built problem appears to be wide-spread and very real at operating reactors.
I NRC/ DOR also has done ongoing research into the adequacy of present day seismic analysis. The goal of the research is to estimate the conservatism in the Standard Review Plan seismic safety requirements, develop improved requirements, and develop methodologies that realistically estimate the behavior of nuclear power plants during an earthquake. This research will continue for the next 4 years, but meaningful results are expected to be produced long before the end of the 4-year period.
Chairmari Hendrie and Commissioner Gilinsky thanked the NRC/ DOR representa-tives and asked to be kept informed of their future progress.
M OL Garry G Young ACRS Fellow
Attachment:
Copies of Slides cc: ACRS Technical Staff ACRS Fellows
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79-07 ALGEBRAIC MAINE YANKEE j
SUMMATION DBE '
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l 79-04 SYSTE5'ATIC VELAN VALVES EVALUATION PROGRAM
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l UCS PETITION 79-02 i
BASEPLATES FOR i
ANCHOR BOLTS SEISMIC REANALYSIS SEISMIC GAME PLAN OTHER ACTIVITIES..)
i TAP A-40
-CHANGING SEISMIC CRITERI A r
SSMRP
-AS BUILT PROBLEMS
-COMPUTER PROGRAMS USED FOR ANALYSIS
i BASE PLATE FLEXIBILITY #8 ANCHOR BOLTS IEB79-02 (MARCH 8,1979)
(JUNE 21,' 1979)
REQUIREDACf!ON kColNT FOR FLEXIBILITY IN ANCHOR BOLT LOADS l
VERIFY PROPER FACTOR OF SAFET(
DESIGN REQUIREENTS FOR CYCLIC LOADS TESTING PROGRAM RESPONSESDUEJulY6,1979 PRELIMINARY RESULTS SOME PL#4TS WITH EXTENSIW INSTAUATION DEFECTS SOME PLANTS'WITH FEW PRTLEMS SOMEGROSSINSTALLATIONP8 LEMS (MISSING BOLTS, SLEEVES)
SOME WITH MINOR INSTALIATIQ4 PROBLEMS (MISSALIGNMENT, THREAD ENGAGEMENT)
SGE PLANTS HAVE REPORTED ENTIRE SUPPORT MISSING
VELM SWING CHECK VALE EIGHT IEB 7944 ~ N CH 30, 1979)
REQUIREDACTION IDENTIFYSYSTEMSAFFECTED VERIFYCORRECTVALVEWEIGHTS RE-EVALUATE PIPING SYSTEM IDENTIFY ANY NECESSARY MODIFICATIG4S
' - IDENTIFY #4ALYTICAL TECH 4IQUE USED RESPONSESWEREDUEMAY1,1979 FINDINGS 148 0F 65 PLANTS USED VELAN VALVES PLANTS WHICH HAVE NOT YET RESPO4DED ARE SHUTDOM4 5 PLANTS REQUIRED MODIFICAT104 (1 HANGER OVERSTRESSED PLUS MISCELLANEOUS HANGER ADJUSTMENTS)
ADDITIG4ALVELANVALVES e
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.,..~..,
f ALEBRAIC SlM%TICN IEB B-D7 (APRIL 14, B79)
REQUIREDACTIOi IDENTIFY AFFECTED SYSTEMS
% ANALYZE USING APPROPRIATE' CODE CODEVERIFICATION RESPONSES WERE DUE APRIL 24,1979 FINDINGS 25 OPERATING PLANTS REPORTED USE OF ALGEBRAIC SLM4ATION CODESINVOLVEDWERE SHOCK 2 - STONE & WEBSTER ADLPIPE - ARE UR D. LITTLE CO.
ESTDYN - WESTINGHOUSE GENERALELECTRIC DAPS PIPDYN 2 - FRANKLIN INSTITUTE NRR STAFF HAS COMPLETED TE REVIEW OF 16 PLN4TS
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STATUS OF EVIEW 0F 5 SHUTDOWN PlRfTS PIPING ANALYSIS AND MODIFICATIWS TO REDUCE PIPE STRESS SURRYl WILL BE COMPLETED 12 JULY 79 11 0F 42 PROBLEMS REQUIRE HARDWARE FIX SUPPORT ANALYSIS WId. BE COMPLETED IN AUGUST RESUfE OPERATIm IN SEP1D BER SURRY2' SHUTDOWN FOR STEAM GENERATOR REPLACENNT NOREANALYSISRESULTSYET NOSCHEDULE PROPOSAL FOR INTERIM OPERATION WDER REVIEW BEAVER VAU.EY MODIFICATIONS IN PROGRESS TO BE COMPLETED BY
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3 RECENTLY,_ IDENTIFIED ADDITIONAL PIPE SIRESS PROBLEMS
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AND ABOUT MJ SUPPORTS TO BE ANALYZED FITZPATRICK LICaISEE ESTIt%TES THAT PROPOSAL FOR RESUBPTIm 0 OPERATION WILL BE SUBMITTED ABOUT JULY 2,1979 ALL PIPING ANALYSIS AND ALL SUPPORT #1ALYSIS IN INACCESSABLE AREAS, INCLUDING ANY NECESSARY MODIFICATIONS, WILL BE COMPLETE RRIOR TO START UP MINE Y#iKEE
. APPRWAL FOR START UP ISSUED I' AY 24,1979
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ORPATING EACTORS ESPONSE TO IEB 79-07
[ NIT COE FORRKS BEAVERVALLEY SHOCK 2 EXTEiSIVE, ORDERS /D FITZPATRICK x MINE YANKEE SLRRY l SmRY 2 P0 int BEACH 1 LIM
,P rECOOLING POINTBEACH2
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x BRUNSWICK 1 ADL PIPE 8 m EXTENSIVE x BRUNSWICK 2 y
x INDIAN POINT 3 AIL PIPE 8 WESTDYN y
SALEM 1
'PIPDYN EXTENSIVE x ItoiAN POINr 2 ADLPIPE 5 LINES Co0PER SRVLINESONLY GINNA 2 LINES x MILLSTONE 1 2 LINES x MIuST@.E 2 6 LINES x NINE MILE P01gr p
LIMITED x COOK 1 WESTDYN 1 LINE COOK 2 WESTDYN X
P x POBINSON 2 RCSONLY x T W KEY POINT 3/I4 x ZION 1 d
Y x ZION 2 X PILGRIM 1 E
RCS 8 %IN SEEAM @ LY X = RESOLVED
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I MIE Y#4KEE SEISMIC ESIGi PRESENTDESIGN HOUSNERSPECTRA$NCHOREDAT0.1s IFLICENSEDTODAY LA Y
DE 1.60 SPECTRA h4 CHORED BETWEEN O/ERAli SEISMIC CONSERVATISM AT MAINE YMKEE WAS REVIEWED PRIOR TO START UP ONGOINGSTAFFACTIWS I
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STATUS OF SEP SEISMIC REVIEWS TWO PLANTS NO SPECIFIC SEISMIC DESIGN BASIS TWO PLANT.S DESIGNED TO UBC OTHER PLANTS DESIGNED TO "G VALUE SIMILAR TO CURRENT CRITERI A (EXCEPT WEST C0AST PLANT)
FOR OLDEST Six SEP PLANTS - LICENSEES INSTITUTING ANALYTICAL STUDIES NEWER'FIVE SEP PLANTS BEING EVALUATED BY STAFF AND CONSULTANTS DRESDEN 2 EVALUATION NEARING COMPLETION - SEVERAL ISSUES REQUIRE EITHER RETROFITTING OR DETAILED STUDIES LESSWS LEARED FI0M EIVEW 0F SEP PIKfS STRUCTURES GENERALLY ' ADEQUATE TORISON MUST BE ADDRESSED PIPING GENERALLY ADEQUATE IF INELASTIC EFFECTS CONSIDERED SUPPORTS REQUIRE CASE BY CASE REVIEW FRAGILE EQUIPMENT (BATTERIES, SMALL LINES WIm IDVS) REQUIRE CASE BY CASE REVIEW OPERABILITY AND FuNCTImABILDY OF EQUIPMENT REQUIRES MORE
. DETAILED EX#41NATIW LOWER QUALITY ASSURANCE E AN REQUIRED TODAY PROCUREENT PROBLEMS i
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i UCS PETITIm RR SEISMIC EEVAUJATIm FOR ALL OPERATING 'RE-EVALUATE THE FOLLOWING:
MAGNITUDE (INTENSITY)0FSSE DETERMINE FREE-f'IELD GROLND MOTIM DETERMINE MOTION OF STRUCRJRES DETERMINE MOTICH OF PLANT EQUIPtENT COMPARE SEISMIC LOADS, LNDER APPROPRIATE LOAD COMBINATIONS, CN STRUCTURES, SYSTEMS AND COMPONENTS WITH ALLOWABLE LOADINGS INSPECT THE PLANT TO DETERMINE WHETIER "AS BUILT PLANT CONFORMS TO DESIGN SPECIFICATION 9
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SEISMIC ISSUES EFFECTING OPERATING PLANTS 1.
CRITERIA CHANGES THAT HAVE TAKEN PLACE DURING THE PAST 15 YEARS HAVE MADE SOME PLANTS MORE CONSERVATIVE THAN OTHERS:
SOIL-STRUCTURE INTERACTION RESPONSE SPECTRA
, DAMPING VALVES 2.
COMPUTER CODES:
M,ETHODS UTILIZED TO PERFORM CALCULATIONS 3.
QUALITY ASSURANCE:
t FACILITIES NOT CONSTRUCTED AS DESIGNED CALCULATIONS DO NOT REFLECT "AS BUILT" CONDITION EQUIPMENT NOT PROCURED AS SPECIFIED i
PROP 09L TO RESOLVE SEISMIC ISSU]
1.
DETAILED STUDY OF CRITERIA USED FOR EACH OPERATING PLANT, BASED ON IHIS STUDY DETERMINE PRIORITY OF UPERATING FACILITIES WHICH SHOULD BE ANALYZED FIRST.
SAMPLE EXAMPLES OF THE CRITERIA IHAT CAN BE USED TO ASSESS THE PLANTS ARE:
SEISMIC INPUT RESPONSE SPECTRA DAMPING VALUES
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LOAD COMBINATIONS ETC.
2.
UTILIZE FINDINGS FROM SYSTEMATIC EVALUATION PROGRAMS INCORPORATE SEISMIC ISSUES THAT ARE GENERIC TO THE STUDIED PLANTS STUDY MODIFICATIONS THAT SHOULD BE IMPOSTED ON OTHER OPERATING FACILIITES USING FINALIZED SEP RESULTS TO DEVELOP LONG RANGE PROGRAMS 3.
CONTINUE TO QUANTIFY SEISMIC CONSERVATISM:
SSMRP TAKS ACTION PLAN (TAP) A-40 EFFECTIVE g LEVEL VS PEAK ACCELERATION i
OTHERS 4.
DEVELOP CAPABILITIES IN VERIFICATION OF COMPUTER CODES IN THE MAJOR DESIGN OF STRUCTURES, SYSTEMS, EQUIPMENT AF,0-COMPONENTS BENCHMARK PROBLEMS TO TEST THE VALIDITY OF COMPUTATIONAL METHODS UTILIZED IN THE COMPUTER CODES.
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4 5.
REVIEW THE IMPACT DUE TO THE' DIFFERENCE BETWEEN "AS BUILT"'AND
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DESIGNED CONDITIONS AND OTHER QUALJTY ASSURANCE PROBLEMS
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PROPER ACTIONS WILL BE IAKEN ACCORDINGLY 6.
USE FOREIGN DATA TO BETTER ASSESS AND'QUALTIFY SEISMIC
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CONSERVATISM THE FINAL SEISMIC PROGRAM SHOULD BE FORMULATED BASED ON THE EXPERIENCES AND RESULTS GAINED PROM THE PRESENT SYSTEMATIC EVALUATION PROGRAM AND SEISMIC SAFETY MARGIN RESEARCH PROGRAM e
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PLMS WITli SIMIFICNR DIFEENES E1MBl ORIGINAL ESIGN AND "AS BUILT. CmDITION OF PIPING SYSIDS M
DIFFERENCE REMARKS SURRYl
- MISLOCATEDSUPPORTS "AS BUILT" C01DITIO4 CAUSED IN
' WR04G SUPPORT TYPE MMORITY.0F. PIPE OVERSTRESS PRG-
- DIFFERENTPIPEGECMETRY LEMS, NOT ALGEBRAIC Sttt% TION BEAVERVALLEY NOT SPECIFICALLY INNTIFIED "AS BUILT" C0iDITION RESULTED IN
' LICENSEE REPORTED "AS BUILT BOTH PIPE NO SUPPORT OVERSTRESS C00lT10NS DIFFER SIGNIFICArm.Y FROM m IGINAL DESIGN" DIFFERENGS SIMILAR TO SURRY LICENSEE IS USING "AS BurLT" FITZPATRICK e
CONFIGlRATION FOR RENIALYSIS SNUBBER SIZING WR04G PLN4T SHUTDOW TO RESTORE.
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PILGRIM SNUBBER PIPE ATTACHMENT WELDS ORIGINAL ESIGN CQiDITION
$NUBBERSUPPORT,STEELASSEMBLY, PIPESUPPORTSLt4TRSIZE BOTH LtilTS SHlmXH1 TO RESTORE BRlf1SWICK U2 ORIGINAL ESIO1 C01DITIQ4 PIPESUPPORTSNOTBUILTTO SUPPORTSWEREREPAIREDDURING GINNA ORIGINAL DESIGN REFUELING OUTAGE MISSINGSEISMICSUPPORTS INSTALLED / CORRECTED SUPPORTS ST. M IE SUPPORTS 01 WR04G PIPING BEFORE START UP FROM REFLELING MISSINGSEISMICSUPPORTS INSTALLEDSUPPORTSBEFORESTART NINEMILEPOINT UP FROM REFLELING MISLOCATEDSUPPORTS LICENSEEPERFORMING"ASBulLT" INDIN4 P0ltrT 3 SUPPORTC04STRUCT101 VERlFICA"104 TO BE C0iPLETED BY JULY..
@PAIRSWILLBEC0fLETEDP PORTS WOULD BE OWRSTRESSED.
MIN STEAM LINE SUPPORTS DAVIS-BESSE1 NE MISSING GUSSETS TO START UP
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i TASK ACTION PLAN A-40 THE OBJECTIVE OF THE TASK ACTION PLAN A-40 IS TO RESOLVE SOME OF THE SEISMIC ISSUES ON A SHORT TERM BASIS.
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