ML17199F812
| ML17199F812 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, LaSalle, 05000000 |
| Issue date: | 06/23/1986 |
| From: | Gilbert R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8606260230 | |
| Download: ML17199F812 (20) | |
Text
Docket Nos. 50-237/249/254/265/373/374
- Commonwea 1th Edis on Company (CE Co)
LICENSEE:
- FACILITIES:
DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS NOS. 1 AND 2 LASALLE COUNTY STATION, UNIT NOS. 1 AND 2
SUMMARY
OF MEETING HELD ON MAY 13, 1986 The NRC held a meeting with CECo and their contractors, Impell, Sargent and Lundy and S. Levy, Inc. to discuss det~ils of CECri's request for approval of alternate seismic evaluation criteria and methodology for the Dresden, Quad
. Cities and LaSalle County Stations. A list of attendees is provided in and copies of the viewgraphs used by CECo and their representatives*
during the meeting*are presented in Enclosure 2.
Relative to effects on Dresden and Quad Cities, as a result of discussions with the staff during and following the presentation by CECo, et al, these conclusions were reached:
- 1.
CECO should do another seismic evaluation of the Dresden 2 recircula-tion piping *using criteria from Regulatory Guide 1.61 and the updated FSAR.
- 2.
CEC~ should also recheck the criteria used during the IE Bulletin 79-14 analysis.
- 3.
CECo should also recheck the criteria used during the Systematic Evaluation Program for Dresden 2.
- 4.
N-411 code case damping in conjunction with updated FSAR criteria is not acceptable for use in seismic analysis calculations on these stations *.
For_ LaSalle, a report submitted by CECo on April 25, 1986 for staff review and entitled "Snubber Reduction Topical Report" was discussed.
The staff and CECo determined which items in that report are acceptable for universal application at the LaSa 11 e County Sta ti on at the present time because CE Co wants to use the advanced techniques in the report during its upcoming LaSalle Unit 2 refueling'outage.
The consensus reached was the following.
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- 2.
Item Damping Peak Shifting
- 3 *. 1 ~~gh E~ergy Line Breaks JUN 2 3 1986
- .. 2 -
Agreed Criteria-ASME Code Case N-411 with the restric-tion as stipulated by letter dated April 1, 1986.
ASME Code Case N-397 No arbitrary i-ntermediate break location
--._
- 4. - *,s~ism*ic Anchor Motions (SAM)
Staff agreed to further review SAM and.
will indicate its finding.
!~
~-
Load Conibin~-tion
- 5.
'l*
- 6.
All approved FSAR methodology Hydraulic transients wi'll be decoupled from safety relief.valve (inertial) loads if time phasing can be justified. A 10 CFR 50.59 Safety Evaluation will be used tB document thfs analysis. Hydraulic transients will continue to be combined with seismic.loads by SRSS as the FSAR stipulates.
In addition_, the staff agreed that, on a case-by-case basis, it will consider allowing the use of advanced ~nalysis techniques and relaxed design criteria in a limited number of difficult cases at LaSalle.
The staff requested that in such cases a deviation :reque~t will be made' describing the extenuating circumstances and the specific methodology to be used to justify the design change.
Finally,. it was agreed that CECo would indicate in a letter its understanding of the methodology agreed* to at the meeting.' The staff would then respond to the letter.
Enclosures:
- 1. List of Attendees
- 2.
Viewgraph copies cc w/enclosures:
See next page DISTRIBUTION NRC PDR Local PDR BWR #1 R/F JPartlow JZwolinski ORIGIUAL SIGNED BY Robert A. Gilbert, Project Manager BWR Project Directorate #1 Division of BWR Licensing RGilbert OELD EJordan BGrimes ACRS (10)
NRC Participants FC BL
- 1:
*-----~--*-----------~*------------*------------*------------*------------*-----------
NAME :RGILBE
- JZWOLINSKI
:------------:---11-------:------------:------------:-------~----:------------:-----------
DATE :6/Jlf/86
- :6/'V/86 OFFICIAL RECORD COPY
"*r cc:
Mr. Dennis L. Farrar*
Pirector of Nuclear Licensing Commonwealth Edi~on Company P.O. Box 767 Chicago, Illinois 60690 Philip P. Steptoe, Esquire Suite 4200 One First National Plaza Chicago, Illinois 60603
-Assistant Attorney rieneral 188 West Randolph Street Suite 2315 Chicapo, Illinois 60601 Resi~ent Inspector/LaSalle, NPS ll.S. Nuclear Regulatory Commission Rural Route No. 1 P. O. Rox 2?.4 Marseilles, Illinois 61341 Chairman La Salle County Board of Supervisors La Salle County Courthouse Ottawa, Illinois 61350 Attorney General 500 South 2nd Street Springfield, Illinois 62701 Chairman Illinois Commerce Commission Leland Building 527 East C~pitol Avenue Springfield, Illinois 62706 Mr. Gary N. Wright, Manager Nuclear Facility Safety Illinois Department of Nuclear Safety 1035 Outer Park Orive, 5th Floor Sprinqfield, Illinois 62704 Regional Administrator, Reqion III U. S. Nuclear Regulatory Commission 799 Rossevelt Road Glen Ellyn, Illinois 60137 La Salle County Nuclear Power Station Units 1 & 2 John W. McCaffrev Chief, Pub 1i c ut*i l iti es Divis ion
. 160 North La Salle Street, Room 900 Chicago, Illinois 60601
~c**
Mr. Dennis L. Fnrrar Cqmmonwealth Edison Company cc:
Mr. R. C. O'Brien President Iowa-T11inois Gas and Electric Comoany
-206 Ea5t Second Avenue Davenport, lowa 52801 Robert G. Fitzqibbons, Jr.
Isham, Lincoln & RealP.
Three First National Plaza Suite 5200
- chicaqo, Illinois. 60602 Mr. Nick Kalivianakis Plant Superint~ndent Quad Cities Nuc1Par Power Station 2271n - 206th Avenue - North Cordova, Illinois 61?42 Resident Inspector U. S. Nuclear Regulatory Commission*
2?.712 ?06th AvPnUP North Cordova, Illinois 6124?.
Chairman Rock Island County Board of Suoervisors Rock Islnn~ Countv Court House Rock Island, Illinois 61?.0l
.. - f.1r. Gar.v N. Wright Nuclear Facil it.v Safet.v l1linois f'P.nartment of Nuclear Safety 1035 Outer Park Drive, 5th Floor Sorinqfield, Illinois 62704 Reqional Administrator, RP.qion III ll. S. ~uclear Requlator.v Commission 799 Roosevelt Road GlP.n Ellyn, Illinois 60137 Mr. Doug Scott Plant Superintendent Dresden Nuclear Power Station Rural Route #l Morris, Illinois 60450 Dresden Nuclear Pnwer Station Uni~s 1, 2 and 3 and Quad CitiP.s Nuclear Power Station, Units 1 and 2 U.S. Nuclear Peoulatorv Commission Resident Insoectors Office Dresden Station Rural Route #1 Morris, Jllinois 60450 Chairman Board of Supervisors of Grundy County Grundv County Courthouse Morris, Illinois 60450
r'
~
NAME M. Turbak S. Javidan ATTENDENCE LIST DRESDEN NUCLEAR POWER STATION, UNIT NOS. 2 AND 3 QUAD CITIES NUCLEAR POWER STATION, UNIT NOS. 1 AND 2 LASALLE COUNTY STATION, UNIT NOS. 1 AND 2 MEETING OF MAY 13, 1986.
AFFIL!ATION
.J. Wojnarowski Commonwealth Edison Commonwealth Edison Commonwealth Edison Commonwealth Edison Commonwealth Edison Commonwealth Edison Commonwealth Edison Impell C. Alen D. Farrar J. Marianyi J. Fox R. Wheaton J. Minichiello T. Wittig G. Kitz R. Srinivasan R. Gilbert A. Bournia E. Adensam J. Zwolinski B. Liaw G. Lainas R. Bosnak R. Bernero
- y. Li H. Shaw R. Lagrange G. Bagchi R. Riggs M. Hartzman J. Fair
. Impell lmpe 11 Sargent & Lundy S. Levy, Inc.
NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC
5 MIN.
I.
COMMONWEALTH EDISON/NRC MEETING AGENDA SEISMIC ANALYSIS TECHNIQUES MAY 13, 1986 INTRODUCTION/BACKGROUND <DENNY FARRAR-CECO) 20 MIN.
II. : OVERVIEW OF DRESDEN/QUAD CITIES. SEPTEMBER 1985 SUBMITTAL CTED WITTIG-IMPELL)
. A.
SUMMARY
OF TECHNIQUES
. B.
ALTERNATIVE 1 ENCLOSURE 2 20 MIN.
Ill.
OVERVIEW OF LASALLE 2 SNUBBER REDUCTION SUBMITTAL (JUAN MARIANYI-CECO)
- A.
BACKGROUND
' B.
SUMMARY
OF TECHNIQUES 5 MIN.
IV.
SUMMARY
CDENNY FARRAR-CECO)
V.
DISCUSSION/COMMENTS CNRC)
VI.
CONCLUSION/ACTION ITEMS CCECO) 1678K
COMPARISON OF CRITERIA/METHODOLOGIES PIPING CRITERIA FSAR CRITERIA DAt!PING
- 0.51 MODAL COHBINATION BY SRSS
~IRECTION C2~BIN&IAff" NVELOP OF
+
EW + V
~IGH FREQUENCY Mo~~s.
NLY HODES BELOW HZ (ALTERNATE 1l LICENSI~G SUBMITTAL ASME CODE CASE N-411 (51 - 211 MODAL COMBINATION BY SRSS SRSS OF NS
- EW + V CONSIDER HODES ABOVE 33 HZ PEAK SHIFIING -- NA ASME CODE CASE N-397 LOAD GENERAIION DIRECT GENERATION FOR SPECTRA DERIVED FROH TIME HISTORY ADDED DAMPING VALUES OF BUILDING
-*-******~-*-**** -***........... ***--*-..... *-
. INPUT SPECIRA SPECTRA ABOVE THE CENTER OF HASS OR STATIC SEISMIC SSE STRESS ALbffWABLES YIELD STRESS STRAINS LIMITED TO PRECLUDE FAILURE BY DEFORMATION SSE SIRESS ALLOWABLES SAHE AS ABOVE
~OAP GENERt.UON AME AS ABOVE ENERGY BALANCE -- NA
- ~TRESS ACCEPTANCE CRITERIA A"E AS ABOVE EITHER ENVELOPING SPECTRA OR ISM WITH ABS COMB. OR SRSS w/o CORRELATION (BUT NO PEAK SHIFTING)
ANSI B31.1 -1967 YIELD STRESS OR STRAINS Ll"ITED TO PRECLUDE FAILURE BY DEFORMATION
<ALTERNATE 2) 11 HAXI"U" STRAIN WITH FATIGUE Ll"ITS ON NUMBER OF CYCLES REGENERATE SPECTRA USING "ODERN SSI TECHNIOUES
<ALTERNATE 3)
USE OF ENERGY BALANCE FOR SHORT-TERM OPERATION SAHE AS ALTERNATE 2 NUREG 1061 ASME CODE CASE N-411 (VOL. 2. PG 2-5)
MODAL COMBINATION BY SRSS (VOL. 4, PG 2-3)
SRSS OF NS + EW
- V (VOL. 4, PG 2-3)
CONSIDER HODES ABOVE 33 HZ (VOL. 4, PG 2-3)
N-397 (VOL: 2, PG 2-6)
NA EITHER ENVELOPING. SPECTRA OR ISM WITH ABS COMB.
(VOL. 4, PG 2-3)
FATIGUE COMPARISON FATIGUE/STRAIN COMPARISON WITH 2% STRAIN LIMIT (VOL. 2, SEC. 2.5)
FATIGUE/STRAIN CD"PARISON WITH 21 STRAIN LIMIT (VOL. 2. SEC. 2.5)
NA NA NA REGULATORY GUIDES 11 - 3 1 DEPENDING ON PIPE SIZE (RG 1.61)
CLOSELY SPACED HODES
<RG 1.92)
SRSS OF NS + EW + V
<RG 1.92)
SUFFICIENT MODES SUCH THAT ADDED RESPONSE INCREASES BY
(
101
<SRP 3.7.2.5)
NOT ADDRESSED SYNTHETIC TH TECHNIOUES
<SRP SEC. 3.7)
ENVELOPING SPECTRA
<SRP 3.9.2)
ANSI B31. f -1967
<10CFR50. 55)
SAFETY (RG 1.29)
SAFETY !RG 1.29)
SSI TECHNIOUES
<SRP 3.7>
FSAR CRITERIA QBE ALLOWA6~f fi -- AISC OR VENDOR ES SSE ALLOWAB~E~
NOR"AL + SS 1.33 AISC BUT Ll"ITED TO YIELD STRESS OR SAFE SHUTDOWN
~NcHoR Botp ACTOR OFAFETY
- 4 (5 FOR SHELL TYPE)
MATERIAL 0VERSTREN6IH MATERIAL YIELD
- CODE "IN.
s11sMIC ANCHOR MOJIONS N
PLASIIC A8~ION -- LIMITED TO YIELD SAFE SHUTDOWN
~LASTIC ACTION AME AS ABOVE COMPARISON OF CRiTERIA/METHODOLOGIES PIPE SUPPORT CRITERIA
<ALTERNATE l>
LICENSING SUBMITTAL
.AISC OR VENDOR VALUES NORMAL + SSE< 1.33 AISC BUT LIMITED TO YIELD STRESS OR SAFE SHUTDOWN FS
- 4 FOR THE ENTIRE BASE PL A TE 1.2 CODE MINIMUM BASED ON MATERIAL DATA.
ONLY FOR NORMAL/SHEAR.
SAM + INERTIAL LOADS COMBINED BY SRSS (ALTERNATE 2)
CHECK FUNCTIONALITY WITH DUCTILITY OF 3
<ALTERNATE 3l USE EITHER ALTERNATE OR ALTERNATE 2 NUREG 1061 NA NA NA NA SAM + INERTIAL LOADS COMBINED BY SRSS (VOL. 4, PG 2-3)
NA NA REGULATORY GUIDES VARI8US CRITERIA RG 141244 1.13
[CL ASS 11, SRP -'* 9 *.))
VARIOUS CRITERIA !RG 1.124, 1.130 (CLASS 1))
FS
- 4 <IEB 79-02)
CODE MINIMUM NA CHECK FUNCTIONALITY
!RG 1.124, 1.130)
SAME AS ABOVE
/...
PRESENT LICENSING BASIS PIPING ANALYSIS INPUT MOTION - RESPONSE SPECTRA DERIVED FROM BUILDING TIME HISTORY ANALYSIS METHODS/CRITERIA *(DYNAMIC ANALYSIS) 0 0
0 0
0 0
0 DAMPING EQUAL TO 0.5%
MODAL COMBINATION BY SRSS DIRECTION COMBINATION IS THE LARGEST HORIZONTAL RESPONSE ADDED ABSOLUTELY WITH THE VERTICAL DYNAMIC ANALYSIS OF ALL MODES UP TO 33Hz SPECTRUM USED IS THAT WHICH ENVELOPES THE PIPING CENTER OF MASS ACCEPTANCE CRITERI~ IS 831.1, 1967 (08E)1 YitLD STRESS FOR SSE OR STRAINS LIMITED TO PRECLUDE FAILURE BY DEFORMATION STATIC EQUIVALENT FSAR METHODS, AS EXPLAINED IN AMENDMENTS 19/20 TO THE FSAR, ARE ALSO ALLOWED
PRESENT LICENSING BASIS PIPE SUPPORT DESIGN 0
0 0
NORMAL LOADS PLUS OBE LIMITED TO STANDARD AISC OR MANUFACTURER ALLOWABLE$
NORMAL LOADS PLUS SSE LIMITED TO 1.33 TIHES STANDARD ALLOWABLES, IN GENERAL, BUT NOT EXCEEDING HINIMUH YIELD UNLESS IT IS SHOWN TKAT SAFE SHUTDOWN CAN BE ACHIEVED ANCHOR BOLTS LIMITED TO SAFETY FACTOR OF 4 (WEDGE) OR 5 (SHELL) UNDER All LOADING CONDITIONS
Ai
- 0.
~
~-
0
- ** ~-
~-.
PROPOSED ALTERNATIVE 1 PIPING ANALYSIS INPUT MOTION - GENERATE ADDITIONAL IN-STRUCTURE SPECTRA AT HIGHER DAMPING VALUES DIRECTLY FROM AN EXISTING SPECTRA METHODS/CRITERIA 0
0 ENVELOPE DYNAMIC ANALYSIS INDEPENDENT SUPPORT MOTION ANALYSIS
PROPOSED ALTERNATIVE 1 PIPING ANALYSIS (CONTINUED)
METHODS/CRITERIA - ENVELOPE DYNAMIC ANALYSIS 0
0 0
0 0
0 0
N-411 DAMPING VALUES MODAL COMBINATION BY SRSS DIRECTION COMBINATION BY REG. GUIDE 1.92 MODAL ANAL~SIS TO 33Hz, WITH HIGHER FREQUENCY EFFECTS CONSIDERED SPECTRUM USED EQUAL TO THE ENVELOPE OF ALL ATTACHMENT POINTS PRESENT FSAR STRESS ACCEPTANCE CRITERIA PEAK SHIFTING PER ASME CODE CASE N397
PROPOSED ALTERNATIVE 1 PIPING ANALYSIS (CONTINUED)
METHODS/CRITERIA - INDEPENDENT SUPPORT MOTION ANALYSIS 0
PVRC DAMPING 0
0 0
0 MODAL COMBINATION BY SRSS DIRECTION COMBINATION BY REG. GUIDE 1.92 LEVEL COMBINATION BY ABS. OR BY SRSS IF THE INP~T MOTIONS ARE UNCORRELATED MODAL ANALYSIS TO 33 Hz. WITH HIGHER.
FREQUEN~Y EFFECTS CONSIDERED PRESENTj FSAR STRESS ACCEPTANCE CRITERIA
PROPOSED ALTERNATIVE 1 PIPING SUPPORT DESIGN 0
0 0
0 0
NORMAL LOADS PLUS QBE LIMITED TO STANDARD AISC OR MANUFACTURER ALLOWABLES.
NORMAL LOADS PLUS SSE LIMITED TO 1.33 TIMES STANDARD ALLOWABLES IN GENERAL. BUT NOT EXCEEDING MINIMUM YIELD UNLESS IT IS SHOWN THAT SAFE SHUTDOWN CAN BE ACHIEVED.
A FS OF 2 ANCHOR BOLTS UNDER SSE LOADING PROVIDED.
A.
THERE ARE 4 BOLTS MINIMUM IN THE PLATE. NO MORE THAN HALF IN TENSION.
B.
ADJACENT SUPPORTS IN THE SAME DIRECTION ARE QUALIFIED ELASTICALLY AND USE A FS OF 4 OR 5 ON ALL OF THEIR BOLTS.
C.
THE OVERALL FS is 4 OR 5 FOR THE BASE PLATES.
A YIELD STRENGTH OF 1.2 TIMES CODE MINIMUM YIELD FOR THOSE MATERIALS FOR WHICH STATISTICAL RESULTS ARE APPLICABLE.
NO INCREASE IN WELD STRENGTH ABOVE CODE MINIMUM IS ALLOWED~
IF APPLICABLE. SAM AND INERTIAL LOADS COMBINED BY SRSS.
PROPOSED ALTERNATIVE 2 PIPING ANALYSIS INPUT-MOTION - REGENERATE BUILDING SPECTRA AS FOLLOWS:
0 0
DEVELOP 3 DIMENSIONAL BUILDING MODELS ACCOUNT FOR SOIL-STRUCTURE INTERACTION, CONSIDERING FREQUENCY DEPENDENT SOIL SPRINGS AND CROSS-COUPLING BETWEEN BUILDING HORIZONTAL ANO ROCKING MODES METHODS/CRITERIA ~
0 USE A 1% MAXIMUM STRAIN ACCEPTANCE CRITERIA UNDER NORMAL PLUS SSE LOADING PIPE SUPPORT DESIGN 0
0 0
NORMAL PLUS QBE LIMITED TO STANDARD ALLOWABLE$
N-ORMAL PLUS SSE LIMITED BY DUCTILITY LESS THAN 3 PIPING AND ADJACENT SUPPORTS CHECKED FOR EFFECTS OF EXCESSIVE DEFORMATION AT THE ELASTIC/PLASTIC SUPPORT SAM, IF APPLICABLE, COMBINED WITH INERTIAL LOADS BY SRSS
e PROPOSED ALTERNATIVE 3 PIPING ANALYSIS INPUT MOTION - GENERATE ADDITIONAL IN-STRUCTURE SPECTRA AT HIGHER DAMPING DIRECTLY FROM AN EXISTING SPECTRA.
METHODS/CRITERIA - FOR SHORT TERM OPERATION, USE ENERGY BALANCE TECHNIQUES TO SHOW PIPING ACCEPTANCE.
THIS MUST BE FOLLOWED BY FORMAL ANALYSIS AGAINST THE ALTERNATIVE ACCEPTED.
AT THAT TIME.
ALSO, SUPPORTS ADJACENT TO THE "FAILED" SUPPORTS MUST BE ACCEPTABLE FOR T~E INCREASED LOADS.
STRAINS IN PIPING LIMITED TO 11.
PIPE SUPPORT DESIGN 0
0 0
0
.0 LOAD COMBINATION AND CRITERIA AS IN LICENSING BASIS A YIELD STRENGTH OF 1.2 TIMES CODE MINIMUM YIELD, WITH NO INCREASE PERMITTED FOR WELDS SAM, IF APPLICABLE, COMBINED WITH INERTIA SRSS A FS OF 2 ON ANCHOR BOLTS UND~R SSE LOADING, WITH THE REQUIREMENTS NOTED PREVIOUSLY OR DUCTILITY LESS THAN 3 UNDER NORMAL PLUS SSE LOADING WITH ADJACENT SUPPORTS AND PIPING CHECKED FOR THE EFFECT OF DEFORMATION
COMPARISON OF PIPE STRESS CRITERIA ITEM PVRC DAMPING MODAL COMBINATION DIRECTION COMBINATION (THREE DIRECTIONS)
HIGH FREQUENCY MODES PEAK SHIFTING INPUT SPECTRA STRESS CRITERIA NUREG-1061 ASME CODE CASE N-411 SRSS SRSS ALGEBRAIC SUM OF HIGH f.REQ. MODES ASME CODE CASE
,._ ~N.:;397 ENVELOPE SPECTRA OR INDEPENDENT SUPPORT MOTION ABS SUM ASME SECTION III LA SALLE
- SUBMIITAL SAME SAME SAME SAME SAME
. ENVELOPE SPECTRA OR INDEPENDENT SUPPORT MOTION
-SRSS LEVEL B
-ABS LEVEL C SAME
FSAR CRITERIA ta'S"aTYe tounty ~at1on !nubber 'lfeauctron 'l'rogram Comparison of Criteria Methodologies Piping Stress Analysis LICENSING SUBMITTAL NUREG 1061 REGULATORY GUIDES.
>~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
bvmping 0.5% OBE, 1% SSE Reg. Guide 1.61 for BWR loads and load combinations.
~j_rect ion Combj nation SRSS High Frequency Modes 60 Hz (BWR load cases) 33 Hz (Seismic)
~eak Shjftjng Not Considered ASHE Code Case N-411 (approved - 4/1/86 letter Adensam to Farrar).
Modal Combination by SRSS SRSS of NS + EW + V Hodes above 33 Hz by algebraic sum ASHE Code Case N-397 lnput Spectra Envelope response spectra method Either envelope response spectra method or Independent Support Motion (ISH) SRSS - Level B
~BE Stress Allowables ASHE,Section III (1974) pSE Stress Allowables ASHE,Section III (1974)
~oad Combjnatjon (For BOP Systems)
SRV (thrust), Turbine Trip loads combined with seismic and BWR inertial loads by SRSS method.
~jgh Energy Line Break (HELB) Criteria Tenninal Ends and two arbitrary intennediate locations tlternate Stress/Strain Criteria Not addressed t.906a*/ji ABS - Level CID ASHE Section Ill, 1974 ASHE Section Ill, 1974 Decouple*SRV (thrust) Turbine
- Trip Loads from BWR inertial loads No new HELB*locations will be added unless necessary to satisfy cumulative usage factor (CUF) limits. - CUF 0.4
-Strain Criteria similar to NUREG - 1061 ASHE Code Case N-411 (Vol. 2, pg. 2-5)
Modal Combination by SRSS (Vol. 4, pg 2-3)
SRSS of NS + EW + V (Vol. 4, Pg 2-3)
Modes above 33 Hz by "missing mass" correction (Vol. 4, pg 2-3)
N-397 (Vol. 2, pg 2-6)
Either enveloping spectra or IBM with SRSS comb.
(Vol. 2, Sec. 2.7)
Fatigue/strain comparison with 2% strain limit (Vol. 2, Sec. 2.5))
Fatigue/strain comparison with 2% strain limit (Vol. 2, Sec. 2.5))
NA NA Strai.n Crj teria (~,; 1 i~i t>...
with fatigue check 1% - 3% depending on pipe size RG. 1.61)
Closely spaced modes (Rg. 1.92)
(RG 1.92)
SRSS of NS + EW + V (RG 1.92)
Sufficient modes such that added response increases by 10%
(SRP 3.7.2.5)
Not addressed Enveloping spectra (SRP 3.9.2) 10CFR50.55 (RG 1.29)
NA NA NA
FSAR CRITERIA QBE Allowables - AISC or vendor values SSE Allowables Normal +SSE 1.33 AISC but limited to yield stress Aric.hor Bolts rdctor or safety = 4 l S tor shell type)
M<i_t;._erial Overstrength M~lerial yield = code min.
Seismic Anchor Motions
-NA Ductility Criteria Not addressed 2906a*/2/rr LaSalle County Stat;on Snubber Reduction Program Comparison of Criteria Methodologies Piping Stress Analysis LICENSING SUBMITTAL AISC or Vendor Values Normal + SSE SRP 3.8.4 except for unsymmetr;c sections FS = 2 under certain conditions Actual Yield Strength SAM + ;nert;a1 loads comb;ned by SRSS
- Ductility Factor of 3
- No increase in Material yield strength NUREG 1061 NA NA NA NA SAM & inertial loads combined by SRSS
. (Vol. 4, pg. 2-3)
NA REGULATORY GUIDES Various criter;a (RG 1.124, 1.130 (Class 1), SRP 3.9.3)
FS = 4 (IEB 79-02)
NA
--t
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\\.
- *- jl'._'
- A o**
00
~*
- e RECIRCULATION PUMP SNUBBER LOADS DRESDEN 2 COMPARISON OF COMBINATION TECHNIQUES (ALL LOADS IN KIPS)
PUMP S~UBBEB A
B c
Q A
SS1 7
7 8
16 SS2A 12 12*
12 13 SS2B 22 22 23 35 SS3A 16 15 19 34 SS3B 5
4 7
39 SS4 14 18' 18 22 B
~~~A 12 12 12 20 15 16 16 16 SS28 17 22 22 29 SS3A 17 17 21 39 SS38 10 9
12 44 SS4 9
9 11 14 "A" = DIRECT GENERATION PVRC DAMPING SPECTRA, SRSS OF MODES, NO HIGHER MODE EFFECTS, NO SAM, MAXIMUM HORIZONTAL AND VERTICAL (PVRC WITH FSAR).
"8" = "A" WITH SRSS OF BOTH HORIZONTALS AND VERTICAL.
"C" = "8" WITH SAM INCLUDED BY SRSS.
"D" = "C" WITH HIGHER MODE EFFECTS (PVRC WITH SUBMITTAL).