ML17338A278
| ML17338A278 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/30/1978 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17338A277 | List: |
| References | |
| NUDOCS 7811160142 | |
| Download: ML17338A278 (12) | |
Text
TURKEY POINT NUCLEAR PO'(E'ER STATION UNITS 3 & 4 REPORT ON FRACTURE TOUGHNESS AND POTENTIAL FOR LAl'KLLARTEARING OF STEAM GENERATOR AND REACTOR COOLANT PUMP SUPPORTS (RESPONSE TO NRC QUESTIONS)
SEPTEMBER, 1978
provide engineering drawings of the steam generator and reactor coolant pump supports sufficient to show the geometry of all principal elements.
Provide a listing of materials of construction.
RESPONSE
Figures 1 through 29 provide steam generator and reactor coolant pump support details including geometry of all principal elements.
Figures 11 through 29 provide listing of materials of construction.
2, Specify the detailed design loads used in the analysis and design of the supports.
For each loading condition (normal, upset, emergency and faulted), provide the calculated maximum stress in each principal element of the support system and the corresponding allowable stresses.
RESPONSE
The support systems for the steam gnerator and reactor coolant pump are designed to satisfy the load combinations and allowable stresses as per FSAR Section 5.1 and Subsection 5.1.9.1.
The load combinations and corresponding allowable stresses are listed below:
S = (D+L+T) 1.33S =
(D + L + T + E) 1.50S
=
(D + L + T + E')
Y = (D+L+T+R)
S = Allowable Stresses as per AXSC Code D = Dead Load Stresses L = Live Load Stresses T = Temperature Stresses where they apply E = Operating Basis Earthquake Stresses (OBE)
E' Design Basis Earthquake Stresses (DBE)
R = Stresses due to pipe rupture reactions Y = Yield stresses of the materials used for the supports as allowed by the ASTM and the ASME Codes.
Design loads, calculated maximum stresses for the governing load combination and allowable stresses in elements of support system are given in"Tables 1
through 3.
2-1
TABIF. I DESICN IOADS ALLCMABIZSTRESSES AND CALCULATED STRESSES FOR LOlER STEAM CENERATOR SUPPORTS AT PL. 30'n MEHBER TYPE
& REP.
DRAWINC (f) Col~ Base Plate (Ffg. 27)
(ii)
Base Plate Anchors (Ffg. 27)
(ifi)
Collnsns N10X77 (Fig. 12, Yerk No. 39 & 158)
(fv)
Pin (2.79" 6)
Ff 11 Mark No. 58 (v)
Bracket Connecting S.C. tug &
Coinmn Cap place (Ffg. 11, Assembly 43) a) Vertical place (35" TH.)
+240
+240
+240
+240
+240 lOADS IN KIPS T
E
%60
%60
+860
+860 910
-860 DESICN IOAD KIPS 41100 620
+ 240
+1100
+1100 910
- 620 MATERIAL TYPE A516-55 A432 A588-CR. Ae AISI-4340 SA302-CRo B
SA302-CR.
B AXIAI BENDINC SUPER 30.0 60.0 20.75 50.0 90.0 30.0 30oO ALBEMARLE STRESSES KSI CALCULATED STRFASES SI AXIhL RVlDINC SllRAR 13e40 53.30 10.57 24.30 90.0 17.33 25,90 CONTROLLINC LOAD COMBINATION D + L + T + R D+L+T+R D + L + T D + L + T + R D+L+T+R D+L+T+R D+L+T+R b) Horfsontal Plate (4" TH ~ )
+240
-860
- 620 SA302-CR.
B
- 30. 0 26.31 D+ L+T+ R (vi)
Columns Cap Plate - 3$" TH.
Ff.
11 (vii)
Bolt - Bet. Bracket 6 Colo Cap Plate 3/4n lf (Ffg, 11, Yerk No. 56)
(vfii)
Bolts Connecting Bracket to Embed plate (s pl. 28'-0" Ff.2
+240
+240 860 910
-860 910 620 910
- 620 910 SA302 GRo B
CARPENTER Nl-YARE 300 A432 260 60 50.0 30.0 156oO 134.2 18.0 31.70 7.40 153.2 D+L+T+R D+L+T+R D+L+T+R D+L+T+R (ix)
Vert.place Bolted to Embed Fkte 3" TH.
Pf.
11 (x)
Ekbedhcnt WT. 10.5 x 56 (Ffg, 12, Mark No. 41) 910 910 910 910 SA302-CRo B
h588-l:R, A*
50 30.0 32.03 9.20 D+L+T+R D+L+T+R NOTE:
MAXIMUMALIOUABIE SHEAR SIRESS
~ Oe6X (MIN, YIEID OP MATERIAL)
- SEE RESPONSE TO QUESTION 5.
2 2
1hMS 2 DFRIGN LOADs ALIENABLE STRFSSES AND CALCUIATED STRESSES FOR UPPER S'TEAN CFNRRATOR SUppoRTS AT EL. 58'"
}lEMSER TAUPE 6 RFF.
DRANING LOADS IN KIPS L
T DESIGN IOAD KIPS YATERIAL TYPE ALllNABlF.STRESSFS KSI AXIhl BENDENC SHEAR CALCULATED STRFSSFS KSI AXIAL BFNDING SHFAR CONTROLLING LOAD CONBINATIO'l (i)
Stop Assenbly No' 6 No. 4 (FIF, 14> Mark No. 79) a) Cor~rcssion on ~cddcd ncnbcr b) Serous 3686 368.6 3686 368.6 SA302-CR ~
B CARPENTER Ni MARK 300 50 50 139+6 D+L+T+R D+L+T+R (ii)
Stop Asser>ly No. 3 (Fig. 14, Perk No. 85) a) Nedgc Shape Stop Block b) Bolts 2" 0 Connecting Stop to Enbed Plate (iii)
Thrust Beans N14 x 193 (Pig.
19 6
21)
(iv)
Ring Cirdcr Around Stean Generator (NEB Co~ressfon)
(Fig. 14, Yerk Nos. 61, 62, 63
& 64) 462 462 1466 1470 462 462 1466 1470 SA302-GR.
B A354-GRI BC A441 SA302-GRo B
50 30 65i40 25.86 10.63 19.25 36.76 D + L + T +
E'+
L+T+E'+
L+T+ R D+ L+T+R NOTEl MAXIMUMALIENABLE SHEAR STRESS ~ Oa6X (MIN. YIELD OF MATERIAL) 2-3
TABIZ 3 DESIGN TOADS ALLOWABTZ STRFSSKS AND CALCUIATKD STRFSSFS FOR REACTOR COOTANT PTNP SUPPORTS NEHBKR TYPE 6 REF.
DRAWINC (I) 3 3I4" 5 )Tcx. Bolt (FIS. 23, ITark hoi 21)
+73 LOADS IN NIPS 2073 1350 DESIGN LOAD IPS 2000 1350 PAIKRIAL CARPENTER Ni HARK 300 CARPENTER Ni HARK 300
- AXTAT, BFNDTNC S)IEAR 260.0 156.0 AT.TOWABTZ STRFSSFS KS CAT@ TATED.
FSS KS BKNDTNC STIKAR 181.08 122.28 COaiRO LLED Tnhn CnTCT Nhr ON D + L + T + R D+L+T+R (ii)
ColTsnT Cap Plate 5tn TH; Fi
~ 23 (iii)
WIO x 112 Colunn Fi
~ 24 Hark Nos.
8 6 164 (iv)
Base Plate Pi a 27 (v)
Base plate Anchors Fi. 27 (vi)Vertical Plate Bolted to Enbeddcd Plate Ts EL. 25'-6" (3" TH.)
PIG. 24 Hark No. 7 (vii)
Bolts Connectin8 Bracket to Ilabcd Plate Ts EL. 25'-6" (818 Bar)
(FIS. 29)
(viii)
Enbcdncnt (s EI>> 25s-6" (W12 x 190)
(FIS. 24, Perk No. 11)
+73
+73
+73
+73
+73
+73
+2073 1350 2073
+2073
+2073 2073
-2073 1350 1350 1350 1350 2150 1350
-2000 2150 2150 2000
-2000 1350 1350 1350 1350 SA302-GR.
B SA302 CR.
B A588-GR. A
- h588-CR. h e A516-55 A516 55 A432 SA302"CRa B
SA302 CR.
B A432 A588-CR. A>>
50.0 50.0 50 0 60.0 60.0 50.0 0.0 30.0 50oO
- 50. 0 30.0 30.0 30.0 7.5 30.4 32.6
- 47. 16 25o94 29 65 25.7 26.15 47.69
- 49. 7 14.83 18.62 8.05 0+L+T+R D+L+T+R D+T.+T+R D+L+T+R D + L + T + R D + L + T + R D + L + T + R D+L+T+R D + L+ T + R D+I +T+R D+ L+T+R NOTE:
PAXTHUH ALIOWABIZ SHEAR STRESS ~ Oe6X (HIM, YIEID OP HATKRIAL)
- SEE RESPONSE TO QUESTION 5 ~
2-4
3.
Describe how all heavy section intersecting member weldments were designed to minimize restraint and lamellar tearing.
Specify the actual section thicknesses in the structure and provide details of typical joint designs.
State the maximum design stress used for the through-thickness direction of plates and elements of rolled shapes.
RESPONSE
The weld joint designs used for the steam generator and reactor coolant pump supports were those shown for thick steel members in AVS D2.0-66,
'Standard Specification for Welded Highway and Railway Bridges',
a nationally recognized
- code, considered suitable for the construction of heavy equipment supports.
Preheats were used for shop welds.
The actual thickness of members used for steam generator and reactor coolant pump supports are shown in Figures 1 thru 29.
The maximum design stresses in support components are given in Tables 1 thru 3.
3-1
Specify the minimum operating temperature for the supports and describe the extent to which material temperatures have been measured at various points on the supports during the operation of the plant.
RESPONSE
There is no official designated operating temperature for the Turkey Point supports.
The normal maximum operating temperature inside containment is 120 F. It is unlikely that the temperature of the supports would ever go below 60'F even during a startup on the coldest day in winter.
The coast of South Florida has very mild winters and the reactor coolant system gives off a lot of heat even when it is shut down.
This decay heat is from the fuel that is left in the reactor during refueling.
In addition the containment and equipment are a large heat sink that helps stabilize the temperature.
The temperature of the supports has not been measured during operation.
This was never considered critical and there was never any requirement to measure it.
4-1
5.
Specify all the materials used in the supports and the extent to which mill certificate data are available.
Describe any supplemental require-ments such as melting practice, toughness tests and through-thickness tests specified.
Provide the results of all tests that may better define the properties of the materials used.
RESPONSE
The principal materials used in the fabrication. of steam generator and reactor coolant pump supports were ASTM A441, ASTM A588-GR.
A and SA302-GR.
B with a minimum yield point of 50 ksi.
ASTM A588-GR.
A material was used in lieu of MAYARX-R50 steel shown on Babcock
& Wilcox Shop drawings.
Both materials, ASTM A588-GR.
A and MAYARI-R50, have minimum yield point of 50 ksi for structural shapes.
~ All of the materials mentioned above have excellent fracture toughness properties.
No additional requirements were invoked.
The mill certificates available in our files for these materials indicate that they met the ASTM requirements.
No special tests were run on these materials.
5-1
~ 6.
Describe the welding procedures and any special welding process require-ments that were specified to minimize residual stress, weld and. heat affected zone cracking and lamellar tearing of the base metal.
RESPONSE
Welding processes used in the fabrication of the supports were limited to the submerged arc and manual metal arc.
These processes are standard methods used for heavy fabrications.
All welding materials were of the low hydrogen type, to prevent heat affected zone cracking
, and each lot of welding material was tested in accordance with the requirements of the appropriate welding material specification.
Melding procedures were in compliance with the requirements of AMS D2.0-66.
Specification required welders and welding operators to be qualified by tests as prescribed by Section XX of the ASHE Boiler Code.
Residual stresses were relieved by requiring postweld heat treatment on all weldments.
~
~
Describe all inspections and non-destructive tests that were performed on the supports during their fabrication and installation, as well as any additional inspections that were performed during the life of the facility.
RESPONSE
During fabrication all welds were dimensionally examined for the compliance with the design drawings.
In addition, visual inspection for cracks in welds and base metal have been performed.
Additional inspections during the life of the facility have been performed.
They are:
The steam generators and reactor coolant pumps support structures were inspected in compliance with DRO Bulletin 74-3 and Supplement 74-3A.
The inspections were performed during the 1974 ISX, for Unit 3, as, reported in the M report and during the 1975 ISI, for Unit 4, as reported in the SKI report.
However, in Unit 4 only the steam generators support structures were inspected as DRO-74-3 and 74-3A dictates.
Xn addition, the reactor coolant
- pump, Loop A, integrally welded supports were examined by liquid penetrant techniques and the support structures by visual methods.
This is in compliance, with the intent of the ASHE Code Section XI, although volumetric examinations, (techniques are not available at the time of this write up) are required by the Code.
These examinations were performed by H during the 1974 ISI, for Unit 3, and by SKI during the 1975 XSX, for Unit 4.
No reportable indications were observed during the inspections.
The reactor coolant pumps integrally welded supports for both units will be examined per Section XI during future ISX's.
Also the reactor coolant pumps support structures will be examined per Section XI during future ISI's.
- However, there are no plans at this time to examine the steam generators supports during future ISI's per Section XI, because there are no integrally welded supports on the steam generators.
If deemed desirable, a visual inspection of the support structures of the steam generators might be performed in the future.
7-1