ML19322B635: Difference between revisions
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Therefore, the need for design analysis of valves was not a requirement for any valve at the time of effective code date. Specifications for B&W supplied valves sere issued to Bailey Meter on October 21, 1968; Dresser on July 3,1968; and Rockwell on October 17, 1967. It should be noted that Duke did require more than the Industry standards in that ANSI B31.7 (1968) was made part of Duke's purchase specification with respect to materials, NDT acceptance, quality assurance records and traceability. For the Cast Steel Specification 05-252, the August 1967 draft of ANSI B31.7 was a requirement and for the Forged Steel Specification OS-252A, the Trial Copy February, 1968 of ANSI B31.7 was a requirement. | Therefore, the need for design analysis of valves was not a requirement for any valve at the time of effective code date. Specifications for B&W supplied valves sere issued to Bailey Meter on October 21, 1968; Dresser on July 3,1968; and Rockwell on October 17, 1967. It should be noted that Duke did require more than the Industry standards in that ANSI B31.7 (1968) was made part of Duke's purchase specification with respect to materials, NDT acceptance, quality assurance records and traceability. For the Cast Steel Specification 05-252, the August 1967 draft of ANSI B31.7 was a requirement and for the Forged Steel Specification OS-252A, the Trial Copy February, 1968 of ANSI B31.7 was a requirement. | ||
DGG/cf 1-11-73 | DGG/cf 1-11-73 | ||
. .s | . .s | ||
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I feel that this justification is favorcble end sufficient for your expressed needs. However, if there ore further questions, direct them to my cttention or to our Chief Product Engineer, R.L . Lawson . | I feel that this justification is favorcble end sufficient for your expressed needs. However, if there ore further questions, direct them to my cttention or to our Chief Product Engineer, R.L . Lawson . | ||
; Sincerely yours, | ; Sincerely yours, | ||
-, BEH:cik b Blake E. Hildre i, Jr. [ /# | -, BEH:cik b Blake E. Hildre i, Jr. [ /# | ||
; cc: G.W. Edwards Senior Engineer - | ; cc: G.W. Edwards Senior Engineer - | ||
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Revision as of 20:18, 18 February 2020
| ML19322B635 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/12/1973 |
| From: | Gardner D DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML19322B629 | List: |
| References | |
| NUDOCS 7912040660 | |
| Download: ML19322B635 (21) | |
Text
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n-l DUKE POWER COMPANY OCONEE NUCLEAR STATION 1-3 Reactor Coolant System Pressure Boundary Valves Minimum Wall Thickness l i Prepared by: 'I - , ///b 7.8 Reviewed by: .d. O L /-f2-75 V l r Y912 04 o (AO
- - - - - - e - - - - ~y 3
s _s
.) )
p s TABLE OF CONTENTS
- 1. Introduction and Summary
- 2. Statement of Problem and Valve Selection 3 Valve Measurement and Evaluation
- 4. Results and Conclusion 1
1 ATTACHMENTS 1
- 1. List of valves to be measured
- 2. Ultrasonic measurement procedure l
_ i
- 3. Wall thickness measurement results (Form 72-236)
- 4. Engineering analyses of wall thicknesses l
l
)
l 1 s l l a
--_-p- < --
- ,. - p--
m - i f'S l. Introduction and Summary Ultrasonic measurements of valve wall thickness were performed on valves selected as described in Section 2 of this report on Oconee Unit 1. Wall thickness measurements will be performed on the same selection of valves for Units 2 and 3, and the results will be reported in appendices to this report. Seventy-four Unit i valves were measured, and several valves failed to meet the requirements set forth by the applicable codes and standards invoked by our purchase specifications. We have justified the continued use of these valves by recognizing actual material properties rather than minimum properties required by the applicable material specifications.
- 2. Statement of Problem and Valve Selection The AEC, Directorate of Regulatory Operations, Informed Duke Power by letter of June 30, 1972 that inspections, made by their office, revealed that several facilities were equipped with valves with wall thicknesses below the minimum requirements specified by the applicable
) codes and standards. As a result of these findings, DRO requested that Duke verify that valves important to nuclear safety at the Oconee Nuclear Station meet the code requirements for wall thickness.
Duke is proceeding in compliance with the DRO request on a unit by unit basis in the sequence of unit startup. The subject valves, within Oconee Unit 1, were tabulated under the guidelines of subsections 50.55 (a) and 50.2 (v) of 10CFR50 and included all valves over one Inch nominal pipe size which are: a) Part of the reactor coolant system, b) Connected to the reactor coolant system, up to and including ! any and all.of the following: 1 1 (1) The outermost containment isolation valve in system piping which penetrates primary reactor containment. (2) Second of two valves normally closed during normal reactor operation in system piping which does not penetrate primary reactor containment. (3) The reactor coolant system safety and relief valves. A total of seventy-four forged and cast stainless steel valves were identified as requiring wall thickness measurements (see Attachment 1) .
m
~s
. '. Valve Measurement and Evaluation m
Because all of the valves requiring measurement were already welded in line, the only feasible method of wall measurement was by ultrasonic determination. Duke personnel constructed a technical procedure for the measurements using the Bronson Model Sonaray 600 and 301T ultrasonic Instruments (see Attachment 2) . Duke valve purchase specifications invoke ANSI B16.5 (1968) as the basis for determination of wall thickness requirements. An exception was made for the core flood check valves, where the manufacturer's design calculations were used to determine required wall thickness. Each valve was scanned to determine the minimum wall readings which were recorded on Duke Form 72-236 (see Attachment 3). Several of the seventy-four valves failed to meet the purchase specification requirements by exhibiting wall thickness readings ranging from 64 to 97 percent of the requirements set forth in ANSI B16.5 or determined by detailed design calculations for the core flood check valves. These valves are IIsted in Table 1. The required wall thickness, determined as outlined above, is tabulated for each valve in column 2 of Table 1. Upon review of these valves with the manufacturers, an alternate code or standard or engineering analyses were employed to establish a revised wall thickness requirement for some of the valves. Those revised wall thickness requirements are shown in column 3. Engineering analyses, where utilized, are included in Attachment 4. The actual measured minimum wall thicknesses are presented in column 4 of Table 1. For each of the valves listed in Table 1, we have reviewed the actual yield stress of the valve body material as documented by the mill test report. The yield stress required by the applicable ASTM specification and the actual values are shown in columns 5 and 6, respectively, of Table 1. The margin in actual yield stress is shown in column 7. The ratio of measured minimum wall thickness to the alternate value (column 3) is presented in column 8. Where this ratio is less than one, the actual material yelid stress must exceed the ASTM specification minimum by an amount sufficient to compensate for the measured reduction in wall thickness. The basic equation for calculating required wall thickness shows that wall thickness is inversely proportional to allowable stress. Since the allowable stress is based on yield stress, for cases where the actual yield stress exceeds the specification minimum yield stress, the required wall thickness may be reduced by a proportionate amount. These allowable wall thicknesses, based on actual material yield stress, are listed in Table 1, column 9, and in every case the allowable wall thicknesses are less than the measured thicknesses. This demonstrates the adequacy of the valves listed in Table 1. t ! 4 Results and Conclusion Comparison of the measured actual wall thickness to the wall thickness permitted on the basis of material properties (Table 1, columns 4 and 9), demonstrates that all of the valves are adequate for service on Oconee 1.
m s
.j
. For all valves, the measured wall thickness exceeded the allowable I^ '
wall thickness, by a margin of 6 to ill percent. It should also be realized that the method and principles utilized in reducing the l required wall thickness are more stringent than a simple one-to-one 1 relationship of wall thickness to stress and are a valid engineering justification for the acceptability of these valves. To further demonstrate the adequacy of these valves, the design, maximum operating and hydro test pressures are tabulated and compared in Table II. These comparisons 111ustrate the conservatism found in the design of i these valves and the ability to meet service conditions. Also, it is emphasized that a hydro test is a proof test much more severe than the valves will ever incur in actual service with respect to Internal pressure. The effective date of Duke Power Company's Cast Steel Valve Specification 0S-252 is March 25, 1968 and the effective date of Duke Power Company-s Forged Steel Valve Specification OS-252A is July 19, 1968. At the time of placing valve orders R-92454 and T-30086 respectively for Cast Steel and Forged Steel Valves, the only standards available for valves were: ANSI B16.5 Steel Pipe Flanges and Flanged Fittings (1968) ANSI B16.25 Buttwelding Ends (1964) ANSI B16.11 Forged Steel Fittings, Socket Welding and Threaded (1966) MSS SP61 Hydrostatic Testing of Steel Valves (1961) ANSI 331.1 Code for Pressure Piping (1955)
~ ?
Therefore, the need for design analysis of valves was not a requirement for any valve at the time of effective code date. Specifications for B&W supplied valves sere issued to Bailey Meter on October 21, 1968; Dresser on July 3,1968; and Rockwell on October 17, 1967. It should be noted that Duke did require more than the Industry standards in that ANSI B31.7 (1968) was made part of Duke's purchase specification with respect to materials, NDT acceptance, quality assurance records and traceability. For the Cast Steel Specification 05-252, the August 1967 draft of ANSI B31.7 was a requirement and for the Forged Steel Specification OS-252A, the Trial Copy February, 1968 of ANSI B31.7 was a requirement. DGG/cf 1-11-73
. .s
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Comparison to the Measured and Allowable Wall Thickness 8 9 Table 1. ' l 6 7 2 l 3 l 4 5 '
- i y Nat'l yield Strength (psi)
** Min. Wall Thickness, t Thickness Heasured ASTM (1972) Mill Test Required (*) Revised (**) 1.362 0.388" 36,400 1.213 '
0.640" 30,000 2P'-0.750"(A) 0.470"(A) 1.920 0.329" IRv-67 30,000 33,000 1.100 0.750"( A) 0.362"(B) 0.695" 0.992 0.302" FS/l/SI/159 30,000 56,100 I.870 0.750"(A) 0.565"(C) 0.560" 0.920 0.302" FS/1/51/244_ 30,000 56,100 1.870 0.750"(A) 0.565"(c) 0.520" 1.052 0.228" .
)
FS/l/51/245 44,377 1.480 FS/l/51/261 0.375 I'( A) 0.M2"fc} ' -n un"___ _30.000 1.317 1.0cc 0.4 2' " 30.000 39.s00 0,825"fA) 0,652"fB) 0.560" 0.881 1.690" l/SI/a 36.2s0 1.210
!.800" 30.000 1.690" 2.040"(B) 2.040"(A) 36,250 1.210 0.971 1/53/1 30,000 2.040"(B) 2.040"(A) 1.980" 0.956 1.690" 1/53/3 30,000 36,250 1.210 .
2.040"(B) 2.040"(A) 1.950" .. 1/53/4 id strength YSR = Yleid Strength Ratio = actual yleid strength f ASTM min. yle ik ired by manufacturer WTR = Actual Vall Thickness Ratio = measured wall thickness i wall th c ness requ
- Wall Thickness Required (A) ANSI B16.5(B) Detailed design analyses in accordance with Section III, ASME.
** Wall thickness calculated in accordance with: t )
(A) ASME Section III (B) ANSI B16.5 - Rerated valves (C) MSS-SP-66 TABLE I DGG/cf I-11-73 r-. - - _q _-'F
/
I I . Table II. Comparison of the Hydro Test Pressure to the Maximum Operating Pressure j System Design Conditions Max Operating Shell Hydro [ % Margin, Hydro vs.
! Valve Test Press (psfg) Max Operation Press
- Tag No. Press (psig) - Temp (*F) Press (psig)
~
i 2155 9000 280 IRV-67 2500 670 200 3020 5400 79
, FS/1/51/159 3050 200 3020 5400 79 FS/1/51/244 3050 200 3020 5400 79 i )
F S /1/51/2_45,_ 3050 s. 650 3020 5400 70
.f1LII51/261. _30_50 200 3020 9000 187 E SI/a 3050 2155 5400 119 4 1/53/l 2500 300 .
I 300 2155 5400 I19 1/53/3 2500 *
2155 5400 l19 I/53/4 2500 300 I P(hydro) - p(oper.) S (oper. temp)
* % Margin =
P(OPer) S (hydro temp) i
? .
t ) e E V . 1 i TABLE DGG/cf l-11-73 - . .
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j 1 -~, l ATTACHMENT 4 OCONEE NUCLEAR STATION Engineering Analyses of Wall Thicknesses 1 I l
.- m ATTACHMENT A.
*2 L November 17, 1972
%/ae: Mb/nnn 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
- 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 well thickness and that on octual i 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 rotings exceeding that of a standard commercial 1500 lb. volve. USAS B16.5 - 1968 gives a formula for calculating minimum wall thickness on page No. 3. This formula is, Pd t = 1.5 25 - i .2P Where t = Calculated thickness in inches. P = Primary service pressure in psi. d = Inside diameter of fitting or port opening of volve 1 (os token from tables) in inches. S = Stress of 7000 psi. ROCKW[LL MANUFACTURING COMPANY .1900 S SAb.40CRS ST. . R ALEIGH. N C. 27602 --.,a P.O.1961 TELEPHONE;(019) 832 0525 . - - -
f) Q . In our calculations the following values will be used cs explained: i P = 2500 psi - because volves were sold to opproximately 2500 lb. volve ratings (3600 psi at 100 F cnd 1500 psi et 1250 F - see P-445871 & 2 and Tcble 8 of B16.5 - 1968). d = 1.93" - this is actuct dimension of vcive port from Rockwell's .' detail machining drawing. The dicmeter of the machined flow
; pcssages in the valves is 1.75".
j S = 7000 psi given in B16.5 - 1968. , i *
? THEREFORE 1
i (2500)(1.93) j t = 1.5 (2)(7000) - (1.2)(2500) t = .658" The value of minimum wall is acceptcbie for a 2500 lb. rated volve. Your service conditions cre actually given cs 3050 psig. at 200 F. A check of Tchle 8
.' of B16.5 - 1968 will show that c 2500 lb. valve is ceceproble for service up to 5830 psi.
at 200 F. A further check of Table 7 of B16.5 - 1968 will reveal thct a 1500 lb. velve is acceptable for service up to 3500 psi. at 200 F. These cre bcsed on F316 body material. Actually a 1500 lb. velve would have met your service conditions. A calculation of min-imum wall bcsed on a 1500 lb. primcry service pressure, all other values remaining con-stant, would be os follows, (1500(1.93) t = 1.5 {2)(7000) - (1.2)(1500) t = .362" This value of required minimum wall for c 1500 lb. vcive which you actually purchased and which meets your specified service conditions hcs a substantial safety fcetor of 1.92:1 when compared with the most unfavorable results of your ultrasonic testing conducted in the field after the volves were insrolled in the line. I feel that this justification is favorcble end sufficient for your expressed needs. However, if there ore further questions, direct them to my cttention or to our Chief Product Engineer, R.L . Lawson .
; Sincerely yours,
-, BEH:cik b Blake E. Hildre i, Jr. [ /#
; cc: G.W. Edwards Senior Engineer -
R.L. Lawson Nuclear Products Group I
7 . . . .
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, //che: /XV-47
,s MINIMUM WALL REQUIREMCHTS FOR 2-1/2"-31533VX B C W PURCilASC ORDER 020158LO TOR DUKE POWER DRESSCR ORDER HO. 30-62252-0 Calculation based on Section III ASME Boiler and Pressure Vessel Code for Nuclear Vessels, Article 1-2, Section I-220, Paragraph I-222 (2) Page 111. (1968)
- 1. Iower Base Wall Thickness Maximum Inside Diameter of Cylindrical Shell = 4.502 Ins.
Minimum Outside Diameter = 5.484 Ins. Maximum Value of Primary Stress plus Secondary Stress Intensity is Given by: 2 S :--pY 2 (Y2 _ 1) where p= Internal Pressure - 2500 psig Y: Ratio of Outside Radius to Inside Radius Y= *
= 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. F316 at 700*F from Table N-421 = 16,200 psi.
The re fo re , 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 o f 4.5G ins. Y= 1.201 Y2 = 1.442 S = 5000 x 1.442 = 16,312 psi '
.442 Therefore , minimum wall thickness is 5.500 - 4.560
= 0.47 ins.
2
, y,
= }
~
DSS 1-lGYVARD INdORPORATGD 717 EAST llOULEVARD T CMARLOTTG N. C. 28205 AT///st/22 runn .vo.,an..... December 11, 1972 r.o. => .... nux. svs.av. Duke Power Company Post Office Box 2178 Charlotte, North Carolina 28201 - Attention: Mr. T. F. Wyke Principal Engineer
Subject:
Oconee Units 1-3 Weld Build-up of 4" S.S. Swing Check Valves Tag Numbers: FS/1/51/244, 245 (a) FS/2/51/244 (a) FS/1/51/261 (b) Gentlemen: Reference recent conversations between Mr. Tom Wyke and Mr. Dave Hillen of Velan, the following is a confirmation of information passed on: Invoking of ref. (MSS-SP-66 perand a) is 0.565", Code of case ref. 1329 wall0.342. (b) is thickness Latter is 0.K. at 0.36. Using actual mill test physicals, ref. (a) is reduced to 0.445 if based on ultimate, and 0.302 if based on yield, vs actuals of 0.56, 0.52 and 0.45 respectively. Cameron certificate for heat 54331 in your p'ossession l covers ref. (a). I In Velan's view, the present. valve bodies had adequate wall thickness. 4 i i l Please advise if additional information is required concerning ! this subject. Very truly yours , HEYWARD INCORPORATED - for l l VELAN ENGINEERING COMPANIES ( '.Y J~~--
,4 % n M . Blackmon JMB:d1 /
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L, CASE 1329 INTERPRETATIONS OF ASME BOILER AND PRESSURE VESSEL CODE Approved by Council February 26, 1964 This Case Interpretorion is not opplicable to Closs A Nuclear Vesse,Is of Section ill Case 1329 (Specsal Ruling) Roting of Steel Bute Welding End Volves Section i Inquiryr Par. PC-42 of the ASME Code, Section I, requires th at steel butt welding end valves for Code application conform to thickness and pressure rating limits of the applicable American Standard (USAS B16.5). On what basis may steel butt welding end valves built to pressure ratings and ( thicknesses other than those in the American Standard be used in Code construction? May steel butt welding end valves having minimum me tal thickness the same as those given for the various pressure classes in the standard be used in Code construction for pressure temperature ratings other than those given in the standard? Replyr It is the opinion of the Com. mittcc tha t steel e butt wcIding en d valves which comply with all the requirements of Stand ard Practice SP-66 developed and approved by th e Manufacturers Standardization Society of the Valve and Fittings Indu stry may be used in construction with;n the scope of Section I of the Code at pres-sure temperature ratings established in accordance with procedures listed in that Standard Practice (MSS-SP-66 1964 Edition). as..enas of January le.1964 ! 121 1
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