ML19322B624: Difference between revisions
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R.L. Lawson Nuclear Products Group | R.L. Lawson Nuclear Products Group | ||
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Latest revision as of 21:18, 18 February 2020
| ML19322B624 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/26/1973 |
| From: | Gardner D DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19322B622 | List: |
| References | |
| NUDOCS 7912040649 | |
| Download: ML19322B624 (22) | |
Text
{{#Wiki_filter:- O DUKE POWER COMPANY OCONEE NUCLEAR STATION 1-3 , Reactor Coolant System Pressure Boundary Valves Minimum Wall Thickness Prepared by: s_ Y/ cMdrx , /s/,2# 71
% Reviewed ay: .[ .t$. IM. L / -il-73 V
lR:v. No.l Dste ?rcoaredby!Rrvicwedb;! ( l / l A 72 1 DN. EA l:M 2 %)p__ & 2 i2-u-n lBEM A- iD 3.Qk _' 89 120406 $p
,s--
TABLE OF CONTENTS REPORT AND UNIT 1 RESULTS 1 Introduction and Summary
- 2. Statement of Problem and Valve Selection 3 valve Measurement and Evaluation 4 Results and Conclusion ATTACHMENTS
- 1. List of Valves to be Measured
- 2. Ultrasonic Measurement Procedure
- 3. Wall Thickness Measurement Results (Form 72-236) 4 Engineering Analysis of Wall Thicknesses I
APPENDIX A - UNIT 2 RESULTS ATTACHMENTS A-1. List of Valves to be Measured A-2. Wall Thickness Measurement Results (Form 72-236) A-3. Engineering Analyses of Wall Thicknesses l l l \~ . Rev. 2, 3-26-73
ATTACHMENT 2 - Addendum I The attached field installation procedure 270, " Field installation Procedure for the Ultrasonic Determination of Valve Wall Thickness," describes the techinque used for ultrasonic determination of valve wall thickness. This procedure indicates that measurements were restricted to that area of the valve body within a distance t of the neck of the valve bonnet where t is the minimum acceptable wall thickness. in actual practice, readings were taken over the entire exterior surface of each valve. In all cases, with the exception of the core flood check valves, the minimum reading has been reported regardless of the location on the valve at which it was measured. In the case of the Units 1 & 2 core flood check valves, the wall thickness both within and outside the distance t of the neck of the valve bonnet was measured and recorded on Form 72-236 listed in the " Wall Thickness Measurement Results" attachment for each uni t. Minimum readings outside the distance t were found to be, in all cases, in excess of 1.15 of the pipe wall thickness. The ultrasonic technique described in F1P 270 has been demonstrated to have the capability of measurement within 2 percent of the measured thickness in accuracy and repeatability. This demonstration was performed on stainless steel (ASTM-A-276) and documentation of the results is attached. DGG/sf 3/28/73 Rev. 2, 3/28/73 l l l \-
FOR/A . 221 REYtslON I DUKE POWER COMPANY [A o G I-CollSTRVC. TION DCPARTMCtJT PP,0)ECT OcoMdC . ULTRASONIC MEASUREMENT OUAUFICATION T EST SPECIMEN UT-7 UT EQUIPMENT IN5TRvMEraT Type O#A45o4/ 43 c l C R,Y 5 Y h L. TV P g foran /~4 clue / 4'-13slql4 S17 E' OlE FRCQVw:.V 2. A 5 M H 2-IN SP ECTIOU TCCH N tQ UE Fin 2 '7 o I
. RESUt.Ts oF MEASUREMENT': M'ccet7e R , REApth/(- S % rRROR 7"Me k eo.ss
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. 500 .x 500 O
.000 g .600 o 900 _ g. . 7' 0 6~ O. 7 %
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FOR/A L 221 REV!51014 I l DUKE POWER COMPANY /':g> ,g l CONSTRUCTION DEPARTMENT v pstfurtT OcoOeC .
. ULTRASONIC UEASUREMENT OUAUFICATION TELT SPECIMEtJ U T~ 9 UT E Q UI P MENT INSTRUMENT TVPE Brousoa 3 01
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APPENDIX A DUKE POWER COMPANY OCONEE NUCLEAR STATION - UNIT 2
.- Reactor Coolant System Pressure Boundary Valves
( Minimum Wall Thickness Prepared by: . J'2 #e 78 Reviewed by: .d.h 3 -2 8-73
'n Rev. 2, 3-26-73
The suoject Unit 2 valves were selected, examined, and evaluated as outlined in Sections 2 and 3 of this report. Wall thickness measurements were performed on seventy valves as listed in Attachment A-1. The minimum wall thickness readings were determined in accordance with Attachment 2 and recorded on Duke Form 72-236 (see Attachment A-2). Several of the valves inspected exhibited wall thickness readings below the purchase specification requirements. These valves are listed in Table A-I of this appendix. Table A-I shows information Identical to that presented for Unit 1 In Table I, and a complete explanation of the information presented in Table A-I is provided in Section 3 of this report. Engineering analyses, where utilized, are included in Attachment A-3. For all valves, the measured wall thickness is shown to exceed that required by alternate code or standard or engineering analyses (Column 3) or allowed on the basis of actual material properties (Column 9). As further 111ustration of acceptability of these valves, Table A-II of fers a comparison of the design, maximum operating and hydro test pressures. Each valve was successfully subjected to a hydro test pressure exceeding the maximum operating pressures without exhibiting evidence of damage, l 1
~DGG/cf 3-22-73 1
1
Table A-I. Comparison of the Measured and Allowable Wall Thickness 1 2 l 3 l 4 5 l 6 7 8 9
^
Valve Hin. Wall Thickness, t Mat'l Yield Strength (psi) YSR WTR Tag No. Required (*) Thickness Rev i sed (**) Measured ASTM (1972) Mill Test 2RV67 2)"-0.750" (A ) 0.470" (A) 0.650" 30,000 36,400 1.213 1.383 0.388" FS/2/51/39 0.750" (A) 0.362" (B) 0.735" 30,000 33,000 1.100 2.030 _ _ _ 0.329" FS/2/51/244 0.750" (A) 0.565" (c) 0.450" 30,000 56,100 1.870 0.796 0.302" , FS/2/51/245 0.750" (A) 0.565" (c) 0.495" 30,000 56,100 1.870 0.876 0.302" FS/2/51/259 0.375" (A) 0.342" (C) 0.370" 30,000 44,377 I.480 I.082 0.228" 2/51/a 0.875" (A) 0.625" (B) 0.690" 30,000 37,000 1.232 1.104 0.507" __ 2/53/2 2.040" (B) 2.040" (A) 1.'950" 30,000 32,000 1.068 0.956 I.913" 2/53/4 2.040" (BJ 2.040" (A) I.980" 30,000 36,250 1.210 0.971 1.690" YSR = Yleid Strength Ratio = actual yleid strength ASTM Min. yleid strength WTR = Actual Wall Thickness Ratio = measured wall thickness wall thickness required by manufacturer
- Wall Thickness Required (A) ANSI B16.5 (B) Detalled design analyses in accordance with Section III, ASME. I
- Wall Thickness Calculated in Accordance with:
(A) ASME Section III (B) ANSI B16.5 - Rerated valves (C) MSS-SP-66 TABLE A-I OGG/cf 3-22-73
Table A-11. Comparison of the Hydro Test Pressure to the Maximum Operating Pressure Valve System Design Conditions Max. Operating Shell Hydro % Margin, Hydro vs. Tag No. Press (psig) - Temp (*F) Press (psig) Test Press (psig) Max. Operating Press
- 2Rv67 2500 670 2155 9000 280 FS/2/51/39 2500 650 2155 5400 134 T FS/2/51/244 3050 200 3020 5400 79 __ ____
FS/2/51/245 3050 200 3020 5400 79 rs/2/51/259 3050 650 2155 5400 134 2/51/a 3050 200 3020 9000 187 2/53/2 2500 650 2155 5400 105 2/53/4 2500 650 2155 5400 105 (hydro) Pggp S
* ) gg )
% Margin =
P(oper.) (hydro temp) TABLE A-11 DGG/cf 3-22-73
ATTACHMENT A-3 OCONEE NUCLEAR STATION Engineering Analyses of Wall Thickness a
, y- l.
y Babcock & Wilcox
% e. a ,, m m s ,
F.0 Bar 1260 Lynchburg.Va. 24505 Te'ephone (703) 384 51;l
% - , . 09 FM '
Mr. S. K. Blackley IUKE POWER CCNPANY Rgg,4iJF..-gog ^ P. O. Box 2178 R310 W Garlotte, N. C. 28201 co u DUKE POV,. - gyc - Attention: Mr. T. L. Overcash DE51G:4b
Subject:
Oconee 2 R40000 Valve Wall Thickness l
References:
- 1. B5W Letter B72-370 dated November 1, 1972,
Subject:
Valve Wall Thickness l
- 2. Duke letter dated January 17, 1973,
Subject:
Mi_nia n Wall Thickness Valve Measurements 1 l Gentlemen: I {
'Ihe following informtion is submitted in response t , the request contained in Reference 2 relative to valve wall thickness require.nents:
(2 n-47) l
- 1. 2RC-RV3: Reference 1 provided calculations made by Dresser answering l our request in this matter relative to the test results obtained on the corresponding ,
Oconee 1 valve. We have reviewed these calculations and feel that they are directly l a plicable to the results for the Oconee 2 valves. We therefore advise that you use tiese same calculations which are included as Attaclment 1, to justify the results of the tests conducted on the Oconee 2 va]ves. (2Mda)
- 2. 2HP-V23: You were provided with calculations for the corresponding Oconee 1 valve which rerated the valve to a lower ASA rating. Using the lower rating ,
which was obtained by linearly interpolating between valves in the B16.5 tables, the required wall thickness was calculated by the formula given in B16.5. This general approach is suggested for the Oconee 2 valve. However, as the measured thickness is greater than that required for a standard ASA 1500# valve we suggest , rerating to 1500f rather than interpolating. Attachment 2 sets forth, B6W's l justification of the measured wall thickness. ' I trust this infomation will be sufficient to answeryour copcerns in this matter. Should further infomation be required, please advise. Ve y yours, b LRA:ch e cc: G. M. Baccich . R. Allen l W. .Faasse . ! R. J. McConnell Associate Proj.ect Manager Attach. The Babcock & Wilcox Company / Established 1867 l
(ya/ve uhk) ram & WilC01 Febnzary 13, 1973 AIIAEEMEEI 2 Sumary: Valve 2HP-V23 is specified as an ASA 2500# valve. The body was machined and a 3" schedule 160 pipe attached to provide for reducer in order to supply butt weld and prep for 21/2" schedule 160 pipe as required by customer. As measured in field by Ur the body w211 thickness at the body-pipe joint is 0.69." Table 33 of B16.5 requires 7/8" minimum wall for a 3" valve. Justification: The valve design conditions are 3050 psig at 200 0F. The valve material is A351-CF8M. Astandard2500lbratedvalveoftgis material is acceptable for pressures up to 5830 psig at 200 F per Table 8 of B16.5. Astandard1500lbratedvalveofthg material is acceptable for pressures up to 3500 psig at 200 F per Table 7 of B16.5. Therefore, the valve design conditions (_ can be met with a standard 1500 lb rated valve. The measured wall thickness of 0.690" is in excess of the required wall thickness for a 3" 1500 lb rated valve of 0.625" as given by Table.30 of B16.5. Therefore, this valve is considered acceptable for its intented service, fk 2e c' Q:
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A T T A C H ME N T 1 [IA/vt 2fv-67 1 2..#;
- 'd..
u - k ' MINIMUM WALL REQUIREMChTS TOR 2-1/2"-31533VX W-B t, W PURCHASE ORDER 020158LS TOR DUKE POWER - DRESSUR ORDER H0. 30-62252-0 s
'. iM
.,'g% .
$,.T.N 4g-Calculation based on Secticn III ASME Boiler and Pressure Vessel < e> -
Code for Nuclear Vessels, Article 1-2, Section I-220, Paragraph t I-222 (2) Page 111. (1968) .f
.y
- 1. lower Base Wall Thickness .r
,?e Maximum Inside Diameter of Cylindrical Shell = 4.502 Ins. E, Minimum Outside Diameter = 5.484 Ins. .
Maximum Value of Primary Stress plus Secondary Stress , Intensity is Given by: . 2pY2 S =(Y2 _ 1) where p = Internal Pressure - 2500 psig Y: Ratio of Outside Radius to Inside Radius C Y = 2.742 = 1.218 and Y2 = 1.484 2.251 S = 2 x 2500 x 1.484 = 15,331 psi 484 Allowable stress intensity for ASME SA182 Gr. T316 at 70001' from Table N-421 = 16,200 psi. Therefore, since there are no other significant stresses acting at the section, the wall thickness can be reduced.
)
Assume outside diameter of 5.484 Ins. and Inside diameter of 4.56 ins. Y= 1.201 Y2 = 1.442 l l
" S = 5000 x 1.442 = 16,312 psi ,
t 442 Therefore, minimum wall thickness is ;- n~ ~ 5.500 4.560 = 0.47 ins. 2 (. ..
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- 4x.-
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1 \
G November 17, 1972 Bobcock and Wilcox Company P.O. Box 1260 Lynchburgh, Virginia 24505 Attention: Mr. Robert G. Burnley, Equipment Engineer
Reference:
Your Orders No. 80792-2 & 80793-2 Our Sales Orders No. 36-46498 & 9
- 1. 4"- Figure K3628(F316)JM - Our Sales Drawing No. P-445871 - 4/2/UNf
- 2. 4"-3628(F316)JM - Our Sales Drawing No. P-445872
Dear Mr. Burnley,
You reported that the 4" - Figure K3628 (F316)JM and the 4" - Figure 3628 (F316)JM on the subject orders were ultrasonically tested for wall thickness and that on octual (, minimum well of .735" and .695" respectively was discovered by this test. These volves were sold to you with our 1500 lb. figure numbers (3000 series), but you were given pressure and temperature ratings exceeding that of a standard commercial 1500 lb. volve. USAS B16.5 - 1968 gives o formula for calculating minimum well thickness on page No. 3. This formula is, Pd t = 1.5
$ - 1.2P Where t = Calculated thickness in inches.
P = Primary service pressure in psi, d = Inside diameter of fitting or port opening of volve (as taken from tables) in inches. S = Stress of 7000 psi. f C ROCKWELL MANUFACTURING COMPANY .1900 S. SAU;iDERS ST. . RALEIGH. N.C. 27602 - P.O.1961. TELEPHONE: (919) 832-0525
In our cciculctions th2 follcwing v:lu:s will be used as cxpleined: P = 2500 psi - because volves were sold to approximately 2500 lb. volve ratings (3600 psi et 100 F and 1500 psi at 1250 F - see P-445871 & 2 and Table 8 of B16.5 - 1968). - d = 1.93" - this is actual dimension of volve port from Rockwell's detail machining drawing. The diameter of the mochined flow passages in the volves is 1.75". S = 7000 psi - given in B16.5 - 1968. THEREFORE (2500)(1.93) t = 1.5 (2)(7000) - (1.2)(2500) t =
.658" The value of minimum well is acceptable for a 2500 lb. rated volve.
Your service conditions are actually given as 3050 psig. at 200 F. A check of Table 8 of B16.5 - 1968 will show that a 2500 lb. volve is acceptoble for service up to 5830 psi. of 200 F. A further check of Table 7 of B16.5 - 1968 will reveal that a 1500 lb. volve is acceptable for service up to 3500 psi. at 200 F. These are based on F316 body material. ( Actually a 1500 lb. volve would have met your service conditions. A calculation of min-imum wall based on a 1500 lb. primary service pressure, all other values remaining con-stant, would be os follows, t = 1.5 (1500(1.93) (2)(7000) - (1.2)(1500) t = .362" This va.ue of required minimum wall for a 1500 lb. volve which you octually purchased and which meets your specified service conditions has a substantial safety factor of 1.92:1 when compared with the most unfavorable results of your ultrasonic testing conducted in - the field after the volves were installed in the line. I feel that this justification is favorable and sufficient for your expressed needs. However, if there are further questions, direct them to my attention or to our Chief Product Engineer, R.L . Lawson . Sincerely yours, BEH:eIk - Blake E. Hildre ,Jr. ' ' ! t, cc: G.W. Edwards Senior Engineer - R.L. Lawson Nuclear Products Group
TLO WGYWARD INCORPORATGD 717 EANT Hol'LEVARD c CLIARLOTTG. N. C. 2e205 ' rm m ,,,o.,nn.s.os March 8, 1973 ,, , ,,,,,, m.tw sn.sn Duke Power Company Post Of fi ce Box 2178 Charlotte, North Carolina 28201 Attention: Mr. Tom F. Wyke
Subject:
Oconee 1-3 Weld Build-Up of 4" Stainless Steel Swing Check Valves Velan Figure No. B12-311-4B-13MS (4"-1500# W/2N#2M2e Swing Check Bolted Cover) Figure No. W7-354B-13MS (1-1/2"- 1500# //.f/2N//259) Gate Bolted Bonnet) Gentlemen: ( s We reference to the many conversations on Oconee and minimum wall thickness valves and we have the following information to relate concerning the two types of valves indicated above. This letter will confirm that the valve types in question can be considered acceptable in spite of a local wall thickness deficiency, as the minimum wall thickness in this area meets the requirements for wall thickness per MSS-SP66 which applies to nuclear valves based on code case (special ruling 1329). Calculations for the minimum wall thickness is as follows: Item A:_ Figure No. B12-3114B-13MS (4" Swing Check Valve) Design Condition 3050 psi /200*F t = 1.5 x 3050 x 3.53 2 x 18.700 - 2 x 3050 x (1-0.4) + .1 = .565 Item B: Figure No. W7-354B-13MS (1-1/2" Gate Valve) Design Condition 3050 psi /650*F t = 1.5 x 3050 x 1.56 + 0.1 = .342 l{ 2 x 16.600 - 2 x 3050 (1-0.4) Continued....... l l l
Duke Power Company (Cont'd) March 8, 1973 , Oconee 1-3 Page Using actual mill test figures, this minimum can be reduced based on ultimate and yield strengths. All of the above information would be applicable to any valves at Oconee with similar figure numbers. Please advise if any additional information is required concerning this subject. Ve ry truly yours , HEYWARD INCORPORATED - for VELA ENGINEERING COMPANIES n M. lackmo JMB:dl cc: Mr. Dan Gardner, Duke Power Company b_
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