ML20210U755
ML20210U755 | |
Person / Time | |
---|---|
Site: | Brunswick ![]() |
Issue date: | 04/30/1994 |
From: | Caine T, Contreras G, Ranganath S GENERAL ELECTRIC CO. |
To: | |
Shared Package | |
ML20210U742 | List: |
References | |
DRF-137-0010-7, DRF-137-10-7, GE-NE-523-48-04, GE-NE-523-48-0494, GE-NE-523-48-4, GE-NE-523-48-494, NUDOCS 9709220069 | |
Download: ML20210U755 (32) | |
Text
.
EE9 0080 b. O hh CCh. I O GENucIhrE ergy General Electric Company,175 Curtner Avenue, San Jose, CA 95125 GE-NE 523 48-0494 DRF 137-0010-7 April 1994, Rev. O STRUCTURAL ASSESSMENT OF THE BRUNSWICK 1 RPV FOR SCRAM EVENT bd-Prepared by:
(n G. W. Contreras, Senior Engineer RPV Integrity Verified by:
b T.A. Caine, Principal Engineer Structural Mechanics Approved by:
~ ~ ^
S. Ranganath, Manager Structural Mechanics DOhK0500b24 DR P
EER %oot4 h 0 40ch. (0 GE-NE-523 48-0494 dd DRF 137 0010-7 IMPORTANT NOTICE REGARDING CONTENTS OF "TIIS REPORT PLEASE READ CAREFULLY This report was prepared by General Electric solely for the use of Carolina Power and Light Company. The information contained in this report is believed by General Electric to be an accurate and true representation of the facts known, obtained or provided to General Flectric at the time this report was prepared.
The only undertakings of the General Electric Company respecting information in this document are contained in the contract between the cwtomer and General Electric Company, as identified in the purchase order for this report and nothing contained in this document shall be construed as changing the contract. He use of this information by anyone other than the customer or for any purpose other than that for which it is intended, is not authorized; and with respect to any unauthorized use, General Electric Company makes no representation or warranty, and assumes no liability as to the completeness, accuracy, or usefulness of the information contained in this document.
Est 94-etAq Lu O AMath rt<d 1O as.33 523-48-0494 DRF 137 0010-7
$Q)' 3R CONTENTS
- 1. INTRODUCTION 1
- 2. BRITTLE FRACTURE CONCERNS 2
2.1 Beltline 2
2.2 Bottom Head 2.
2.3 Brittle Fracture Conclusion i1
- 3. ALLOWABLE STRESS CONCERNS 13
- 4. FATIGUE CONCERNS 13 5
SUMMARY
AND CONCLUSIONS 16
- 6. REFERENCES-
~
17 APPENDIX A: Bottom Head Fabrication Data 18 I
e 4
E FE. %- co2M % 0 A4cchc4 io c,3.ns 523.u.om dCy)52 DRF 137 0010 7
1.0 INTRODUCTION
As a result of a scram with loss of recirculation pumps, which occurred on January 17, 1992, temperatures in the beltline and botton. head of the Brunswick Unit I reactor dropped to low enough levels that pressure. temperature (P.T) curves in the Technical Specifications (Tech Spec) for non-nuclear heat up/cooldown were exceeded. In addition, the RPV top head temperature exceeded the bottom head temperature by ~400'F.
Based on data received from CP&L (1), this report addresses the structural impact on the RPV of the cooldown event There are three structural concerns: (1) brittle fracture, (2) allowable stress, and (3) fatigue. These structural concerns are addressed separately below.
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GE-NE 523-48-0494 DRF 137-0010,
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2.0 BRITTLE FRACTURE CONCERNS 1
i The subject event is being evaluated because the tech. spec. P.T curves may have been i
exceeded in the beltline and bottom head regions. To alleviate any brittle fracture concerns, this event is being evaluated for compliance with 10CFR50 Appendix G fracture toughness margins. The regions of concern (the beltline and bottom head regions) are j
evaluated separately below.
4 I
2.I' Rahline i
De P-T data as summarized from Reference I are shown in Table 1, nroughout this j-cooldown event, it may be assumed that the recirculation line and bottom head temperatures were lower than that of the beltline region. Therefore, the highest of the j
recirc loop temperatures and uppermost bottom head thermocouple temperature (TC 157) l may be taken as the beltline temperature. These beltline P T conditions were compared with the " core not critical" curve for Unit 2 (the Unit 2 P-T curves are more limiting than j-those of Unit 1) in Figure 1. Under some condigns the P-T points exceed (to the left of) j the limit curve. These P-T conditions which exceeded the limits ofFigure I are shown in
{4 Table 2, along with the calculated cooldown rates. The cooldown rates were rather low j
(30*F or less). Since the hydro test curves are based upon a 30*F/hr heatup/cooldown L
rate (safety factor with respect to pressure is still 2), these conditions may more appropriately be compared with the hydro test limit curve. This compaiison is shown in l
Figure 2 (again, the more restrictive Unit 2 curve is used for comparison).
With the appropriate limit curves as discussed above, the beltline region was found to be within the limits of these curves.
i 2.2 Rottom Head i
The bottom head P-T conditions from Table 1 are compared with the " core not critical" curve in Figure 3. Most of these P-T conditions exceed this limit curve. However, the cooldown rates in this region during this period of time were small (12*F/hr max, see
[
Table 3), so the thermal stresses are negligible. Therefore, a new Hydro Test P-T curve 1
may be developed specifically for the bottom head and compared with bottom head P-T data to show 10CFR50 compliance.
1 5 i
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T. eMe 1: Sawtowlet 11717/02
- If20t92 Treneemt t
5etwatace RPV 5etweteen T/C 157 T/C 151 Top / Sot Temperstwo wowe Temperstwo A toop 9 Loop tettom tettom OostoTome 11/2 he morememet Dete Time pee
'F Terry., ' F Temp.,'F Hoodp5kert Hess ovio1, F/h, Jon 17 930 925 537 525 530 1992 1000 750 514 500 500
-44 1030 830 525 400 400 22 1100 825 524 430 450 2
1130 970 533 300 410 18 1200 750 513 300 300 40 12 %
725 500 310 330 158 120 383 e
1300 950 499 200 290 148 124 374 22 1330 e2s 524 255 200 144 ile 40e 52 1400 746 413 230 230 130 112 401
-Q 1430 840 495 210 210 139 100 309 34 1500 010 490 195 190 124 100 300 10 1930 435 404 100 100 118 98 398 8
1800 825 495 170 100 112 92 403 2
1830 590 457 100 155 106 to 397 10 1700 525 471 tot 145 107 es 303 32 1730 475 405 140 140 100 00 377 12 1800 425 454 135 130 III SS 340 22 1830 410 452 130 125 119 04 300 4
1900 375 442 125 120 110 94 350 20 1930 340 433 115 til 110 82 351
.it 2'000 300 425 110 110 114 52 343 10 2030 205 420 100 100 _
114 91 339 10 2100 201 418 100 100' 114 to 338 5
^
2130 213 393 100 100 120 to 313
-d e 2200 ISO 344 100 100 134_
78 300 10 2230 179 381 95 95 212 77 304 8
2300 159 370 95 95 200 77 293 22 2330 143 382 92 92 304 77 285 18 Jan 10 0
129 355 90 90 318 30 275 14 1982 30 124 352 90 to 320 92 200 6
100 127 354 90 90 320 132 222 4
130 117 340 to to 320 132 21e 12 200 110 34 4 90 to 318 104 100 8
230 110 339 05 85 314 212 127 10 300 99 338 to 80 313 224 114 2
330 99 331 00 to 312 210 113 14 400 71 319 90 00 300 208 110 26 430 SS 310 30 00 304 196 120 4
500 70 320 90 80 300 104 136 8
530 Se 315 80 30 290 175 140
-10 000 53 301 90 to 207 180 135 28 430 45 292 80 SO 283 104 129
-18 700 35 291 80 so 232 159 125.
22 730 32 277 80 80 232 148 129
-5 000 30 274 80 00 252 138 134 6
030 24 267 90 SO 200 130 137 14 900 21 262 SO 90 258 120 134
.to 930 10 253 80 90 255 134 117 18 1000 9
240 00 00 254 148 92 20 1030 5
229 30 SO 245 148 81 22 1100 4
224 80 00 242 140 7e 10 1130 0
228 130 125 236 144 54 8
1200 10 240 150 155 232 140 100 24 1230 12 244 105 200 222 140 104 8
1300 13 248 212 220 212 140 104 4
1330 14 248 223 232 200 152 98 4
1400 il 250 230 230 200 172 78 4
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Seewstion PW'V Seewetaan T/C 167 T/C 161 Top / tot Temeierstwo Proeowe Temperstwo A Loop 8 Loop tottom Gottom DomeTemp (1/2 he eierementet
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Date Time pas
'F Temp., 'F Temp.'F Heee99kwt Hood
'F eT fet, 'F/hr 1430 16 250 230 239 206 184 es 0
1608 1F 260 243 241 210 192 50 0
is 30 17 2s4 24e 24e 21e its se a
1900 19 260 260 260 219 200 Se e
1830 21 200 263 264 222 204 50 4
1700 24 2 04 287 268 224 200 Se e
1730 25 298 200 200 224 200 SS 4
1000 27 270 283 203 228 210 to e
1830 20 27J 205 205 230 att 80 4
1000 29 273 206 207 234 210 57 2
1930 29 273 ISS 270 234 220 S3 0
2000 30 275 200 270 240 220 SG 4
2030 31 270 270 271 240 224 62 2
2100 37 204 298 300 220 50 it 2130 43 291 295 205 220 43 14 2200 48 290 208 290 220 et 10 2 [30 53
_301 295 290 230 71 10 23co 56 303 298 300 231 72 4
hpc le 307 300
,suu 232 75 e
Jan if
'O 02 300 306 310 230 72 2
1992 30 00 316 310 310 240 75 to 100 72 310 310 310 244 74 e
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248 72 4
200 81 324 325 326' 252 72 e
230 82 328 325 326 264 72 4
300 83 327 326 325 258 71 2
330 82 320 326 32S 200 68 2
400 81-324 322 326 284 80 4
430 31 324 322 325 0
600 82 320 322 325 4
6 30 82 320 322 325 0
000 82 328 322 325 0
830 82 320 322 326 0
700 82 320 322 325 0
730 82 328 322 325 0
000 82 320 321 322 0
830 81 324 320 320 4
000 et 324 320 320 0
530 81 324 319 319 0
4 1000 90 322 319 319 1030 90 322 319 320 0
1100 90 322 318 318 0
1130 79 320 Sie 318 e
1200 79 320 310 319 12 1230 78 320 317 318 0
1300 79 320 310 318 0
1330 79 320 317 318 0
1400 77 320 310 317 0
1430 76 320 316 310 0
1600 87 314 310 310 12 1630 86 312 300 300 4
1900 85 312 306 310 0
4 1830 67 314 308 310 1700 87 328 310 316 28 1730 101 330 340 340 22 1000 103 340 340 340 2
12 1930 113 348 340 340 12 1900 112 340 340l 346 l
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Seewetion RW Setwenson T /C 157 T/C 151 T op/ tot Terroerature Prosewo T angerstwo A Leap 8 Loop tettom tonom Deeefems 1112 tv incrementen Date Time pos
'F Temp,'F T emp.,
- F Heesesert Head
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130 630 470 470 472 0
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RPV A Loop Bloop T/C 167 Assumed Bottlene Pressure Temperature Temperature Bottom Bonhne (1/2 hr sncremental Date Time pas
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'F Head @ Skrt Temperature dT/dt 'F/hr Jon 17 1630 636 100 1801 116 180 30 1992 1600 626 170 1601 112 170 20 1830 690 160 166 108 160 20 1700 626 145 146 107 146 30 1730 476 140 140 108 140 10 300 426 136 130 111 136 10 1830 410 130 126 116 130 10 1900 376 126 120 118 126 10 1930 340 116 116 116 116 18 2000 309 110 110 116 116 0
'030 296 104 104 114 114 4
4 2100 281 100 100 114 114 0
2130 213 100 100 120 120 12 Table 3: Brunswick 1 Bottom Head RPV T/C 151 Bottom Head Pressure Bottom (1/2 hr increments)
Date Time psi
+ Head dT/dt. 'F/hr Jan 17 1230 725 126
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1330 825 118 12 1400 745 112 12 1430 640 106 12 1500 610 100 E
1530 635 96 8
1600 625 92 8
1630 590 90 4
1700 525 88
-4 1730 475 88 0
1800 425 86
-4 1830 410 84 4
1900 375 84 0
1930 340 82 4
2000 309 82 0
2030 295 81 2
2100 281 80 2
2130 213 80 0
2200 190 78 4
2230 179 77 2
2300 159 77 0
2330 143 77 0
2400 129 80 6
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a=a m as Wo. 172 gagyggtcg. Uutt 2 3/4 6 15 Figure,1 Bottom Head Region
EEP %ooM Rw 0 M Mh. ID iusz GE NE 523-48 0494 V
DRF 137 0010 7 2.2.1 P T Curve Development Consistent with previous CP&L submittals as licensing bases for P T curves and surveillance summary information, the RTndt values for the bottom head 'lates were I
assumed equal to the NDT values. These NDT vdues were extracted from material certl5 cations which were retrieved from GE QA records (the appropriate CB&l contract number for the Brunswick 1 RPV is #2471). The material certs are included in Appendix A. 'Ihese NOT values range from OT to 10T (See Table 4). A conservative estimate for the bottom head welds is 07, based on the NRC's Branch Technical Position MTEB 5 2.
Therefore. the highest RTndt is 107, which provides the basis for the bottom head P T curve development.
As a check, the GE methodology for establishing an appropriate RTndt was used for the plates. These calculations are summarized in Table 4. In all cases, the NDT was higher than the(TCV50-60) temperature. Therefore, the NDT temperature is appropriately used as RTndt for the Brunswick 1 bottom head.
Table 4: Plate RTMnT Determination Charpy Test Long 3 Trans.4 Calculated Piece Heat / Slab NDTI Valuf Temp Tcvsn Tcvsn Tcvsn-60 RTwnr5 101 C4654 3
+10T 61Rlbs 10T 10T 40 4
-20T 10T 102 C4613-3
+0T 59 R lbs 10 4 10T 40T
-20 4 OT 103 C49013
+10T 37 R-lbs 10T 36 7 66 7 6T 10T 152 C4510-1
+10T 38 R lbs 10 7 34T 64T 4T 10T 151-1 C4694 3
+10T 43 R lbs 10 7 24T
- 54T 6T 10T 151-2 C4694 3
+10T 43 R lbs 10 7 24T
- 54T
-6T.
10 7 151 3 C4(%3
+10T 43Rlbs 10T 24T 54 4
-6T 10 7 151-4 C4689-3
+10T 60 R lbs 10 7 10 7 40 7 20 7
- 10T 151-5 C4689-3
+10T 60 R lbs 10T IOT 40 7
-207 10T
- 1 und tempermure or lower.
S 2 Lowest test value (of three) from material certs conservatively taken as representative value.
3 For longitudinal Charpy values greater than 50 A Ib, TCV50 aken as equal to test temperature.
t For longitudinal Charpy values less than 50 A.lb, TCV50 calculated assuming consenative 2'F/A Ib.
4 For convers.on oflongitudinal TCV50 otransverseTCV50,30'F added to long. TCV50 t
5 RT d
WT enned as greater of NDT and TCV504'F.
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DRF 137 0010 7
.,+4 The bottom head region P.T curves are based on a generic analysis that was performed using BWR/6 vessel design analyses as a basis. The BWR/6 analyses of the bottom head CRD penetrations provided the basis for developing P.T curves as a function of RTndt.
l The bottom head geometry of the BWR/6 is very similar to earlier vessels, such as l
Brunswick. In fact, the BWR/6 results are conservative because BWR/6 designs do not have stub tubes (Brunswick does), which lessen thermal stresses caused by CRD water Sowing in the housings. The generic bottom head P.T curves were adjusted to the
[
(
Brunswick RTndt of 10'F.
b (The bottom head P T curve provided in Figure 4 is valid for the operating life of the -
vessel, as long as relevant regulations do not change. Therefore, the curves can be used to evaluate any similar ibture events, and could be added to the Tech Spec curves to simplif'y the process, if desired. Ifit is established that the highest RTndt of the Brunswick 2 bottom head is 10*F or lower, the Figure 4 bottom head P.T curve may also be applied to Brunswick 2.)
2.2.2 Comparison of Event to P.T Curve The bottom head P-T data for the event from Table 3 are plotted along with the bottom head specinc P.T curve ir Figure 4. As seen in Figure 4, the bottom head P.T event data are to the right of the bottom head curve, indicating that 10CFR50 Appendix G requirements were met in the bottom head during the event.
2.3 Brittle Fracture Conclusion The fracture toughness margins required by 10CFR50 Appendix G were maintained during the event, and the transient created no concern of brittle fracture of any vessel components.
j 11
cER 94.Oogy gqq o AHath. lO 154 52 5
1600 CURVEA 1400 1200 INITIAL RTndt VALUE IS 10*F FOR BOTTOM HEAD g1000 A. SYSTEM HYDROTEST LIMIT
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3 g LIMITS AND 10CFR50 3
APPGREQMTS g
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Figure 4:
Bottom llead Region
EER 94 oot4 Rev 0 M40th.10 GE.NE 523-48-0494 ig g) 3g DRF 137-0010 7 3.0 ALLOWABLE STRESS CONCERNS The transient created top to bottom temperature gradients of as much as 406'F. This is above the 145'F gradient required prior to recirculation pump start up. However, throughout tnis event the recirculation pumps remained off until the gradient was less than 145'F (see Table 1).
This event may be compared with previously analyzed events. The design basis thermal cycle diagram (729E762, Figures 5 and 6) shows a loss of feedwater event, Event 11, which las a top to bottom thermal gradient of 470*F, d. ring a 600'F/ hour cooldown. The Event 11 top to bottom delta T is sufficiently larger than the subject cooldown event to assure Event 11 is bounding. Therefore, it is concluded that the subject cooldown event is bounded by an analyzed transient with acceptable maximum stress.
4.0 FATIGUE CONCERNS The subject transient is less severe than the design basis cooldown analyzed for feedwater pump loss. Therefore, this event should be counted as one loss of feedwater pumps event for fatigue purposes. Ten loss of feedwater pump events are allowed per the thermal cycle diagram. The contribution to fatigue usage of one event may be extracted from Reference 2.
13
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SUMMARY
AND CONCLUSIONS ~ A SCRAM event resulted in P T conditions which exceeded the P T limits in the Tech Spec. At lower temperatures, beltline conditions were compared with the more appropriate hydro test curve (since the cooldown rates were small). A Brunswick specific bottom head P T curve was developed, based on the limiting bottom head RTndt of 10'F, for comparison with the event data. The results showed that the appropriate limits for these regions were not exceeded. Therefore,10CFR50 Appendix G fracture toughness requirements were met during the event. In summary, the vessel pressures a d temperatures during the trunswick cooldown event created no concern for brittle fracture. Furthermore, the impact on maximum stress and fatigue of the transient were less severe than those evaluated for other design basis events, which were shown to be acceptable. Therefore, there are no structural integrity concerns with continued operation. The event should be counted as one loss of feedwater event and a normal shutdown event for fatigue purposes. e \\ -16 I
EE8 94- 0084 Rw 0 AMath.10 GE.NE.523a8 0494 20g32 oar i37.ooio.7
6.0 REFERENCES
[1) Memo dated 3/i8/94, Charlie Griffin (CP&l.) to Gary W. Contreras (GE), containing P T data for the subject event (T/C strip chart and control room log). [2] Whitling, R.W.,
- Reactor Pressure Vessel Thennal Cycle Fatigue Evaluation for Brunswick Steam Electric Plants Units 1 and 2," NEDO.221%, March,1983.
-17
pun um lm EER 94-0084 Rev 0 A406 10 on.NE.523 48 0494 2.1.g& DRF 137 0010 7 APPENDIX A Bottom Head Fabrication Data 18
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G P E 9ti-u Rev LUKENS STEh0MPAW 16-15-63 ah l l TEST CERTIFICATE Saso l Chiesgo B:icco 2: Ir n Co. Boyles, Ala. ( *... I w ou'* ** 3:ses C Th20. men, Fur.2tcr. 28650-2 2471, ch. Je ~ ShtoLS2 Of 2 IJ'CO .e.,oue as nu CHE MIC AL AP ALY5t$ TTT e .,,,,,,,1,,,_ r. s. u. c. a i,c4654-3 I i f? c.- PHYSIC AL P R O P E R T I E 5-oescastTaoN a sm u a.a. mee w L anar wo. g g I I 259., hqld 1.hr. per incM nin, and v.g. iar 27 nisates. l i .e. lates cc2 tosts h::sted '1650*2.'. Ad 14.r. Scr inch minJ and air coc 3ad. tc= pared 180*P,210*y., bc I I I i relieved 11;)0*F,$*F.j held #1/2 bz. per inct min, l l 1 t-3ates gas cut hot as.1 otress I i I i I 'F., ni air cooled. of Sg'F. Paa hr. to 11g0*F,600 F. ar air cooled. ~L ' straat roli ved by he ting within a rate r 50 mes.'and nace cooled wittin a rste cf 74 J. por jhr. tc ed in accor o with irspectica syr tem zoquir nts hr M22-845208A, 1 i '. c-I l TJ.e-. g g 1 I I I 1 i i 1 I l l e I I D er [ /*
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== caose ee. cowomea e o 12 l Same Ecylesa 11a. I~ f 2C650-1 2471a Eheet 4 peor r.ame .- = CHE MIC AL AN ALY585 en-5 'T 5 ee. Ce u. v f. As a Kl [C4613-3 1 [ I v.'* 1 t { ~ t ~~~ PHYSIC AL PROPERTIES 5 i.e.cs oE5CaePTION - s w.s msA m pos . astLt No. Plates and itects Aostoc: 1650-F.1F., hrinhmin. and W.Q. for 27 minutes. Than toppered 121G*F. !10*F., hold 1 hr. held I hr.per ihch nfn. and air cooled. 25 tes cas, cut hot and tresa relic od 11$0*F.,# . held 1/2 hr. Par ir ch stin. I I and air cooled. F*k hr..to 1150*F. iests'stro:s rolioved b'y heating within a, rata. of 59'F. p d air cooled. i h=1d 50 hrd. and,ntrasco cool'on.tithin a irate of 74T. pas hr. to 600*F. an l l I I requiz'c:nontd of MIL-S-45208A. h':ced inl accardanco with i nspection stes 7 i I I I I I I i 1 i I ~ '~'l 1 I l 1 ~1 l t n:tJJ M. 8:. X., 7 ~~
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- 10 7,, hol,d I hr.1 per { inch :iin, and air cooled.
Then tes;c ed 12 tross relioYod 1$50'? A, Yh*. heNd 1/2 . por 1Ech =in. !71stos gas cut ho.t and I ~ i +2 '?. t 'and,alr coolod. g
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=
ad wo I a;2 .; = 3 l i , + 1 h W or 22 minutes. @n }t.eeperiod 1220*F. )650*F. -257., held 1 h. pe!r inchl min. and W.Q. f ~ ~ Plates tr.dasts h'ested-Op.,heldibr.'par inch mih..and air cooled. I 3 j l l t hon and ,.2M*. *', hYd J/2 hr. Per i + t nch min. tresa relieved 1150*F. Plates z,ma &nd air ed. 1 +25*F.; 1 of 7 hr. to 1150*F. -50*F., ~. g, a of90l*F. 6sts'streags relieved by tLag within a rata F. ps hr. to 600*F. and air cooled. d 50 hrs. and carnace cimoled within a ' ate r i repts of MIL-I 45208A ..i f p ~ is accordance with inspection system if.n;+. f s. at 1 I I 'st g 74 I I i .)
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