ML20128P393
| ML20128P393 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 10/07/1996 |
| From: | Markovits C STRUCTURAL INTEGRITY ASSOCIATES, INC. |
| To: | |
| Shared Package | |
| ML20128P391 | List: |
| References | |
| YAEC-25Q-301, YAEC-25Q-301-R02, YAEC-25Q-301-R2, NUDOCS 9610170246 | |
| Download: ML20128P393 (26) | |
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Mr"tcii1y CALCULATION FILE No: YAEC-25Q-301
^" cia'c5 'ac-PACKAGE PROJECT No: YAEC-25Q PROJECT NAME Evaluation of Flaw Indications Found During RPV Inspections at Vermont Yankee CLIENT: Yankee Atomic Electric Corporation (YAEC)
CALCULATION TITLE: Flaw Evaluation for UT Indication Using APPENDA Program PROBLEM STATEMENT OR OBJECTIVE OF THE CALCULATION:
Perform a detailed flaw evaluation in accordance with Section XI, IWB-3600 to determine acceptability of the flaw indication.
Project Mgr. Preparer (s) &
Document Affected Revision Description Approval Checker (s)
Revision Pages Signature & Signatures &
Date Date 0 1 - 1I Originalissue Clare C. Markovits CCM Oct 3,1996 i disk 10/3/96 Clare C. Markovits Al-A8 GLS Oct 3,1096 Gary L. Stevens I l-12 Additions based on YAEC comments, Clare C. Markovits CCM Oct 5,1996 plus minor editorial changes. 10/5/96 Clare C. Markovits GLS Oct. 5,1996 Gary L. Stevens 2 1-12 Additions based on YAEC comments.
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j 1.0 Introduction
, In accordance with the requirements of Section XI of the ASME Boiler and Pressure Vessel Code [1], reactor vessel shell and nozzle welds must be inspected once in each inspection interval (e.g.,10 years). The rules for the evaluation of flaws in reactor vessels are contained in IWB-3000, IWB-3500, and IWB-3600. Appendix A of Section XI provides specific methodology that may be used for detailed fracture mechanics evaluations. Any indications which are found during inspection must be characterized by depth, length, and surface proximity criteria. The characterized flaw is then compared to evaluation standards included in IWB-3500, if the characterized flaw is acceptable per these standards, then no further evaluation is required; if unacceptable, then additional analytical evaluation is allowed per IWB-3600.
Ultrasonic inspection of the reactor pressure vessel (RPV) at Vermont Yankee resulted in one
, indication [2] that was not acceptable by Section XI, IWB-3500 acceptance standards. The
] indication is located in Plate 1-15, below the circumferential weld whichjoins Plates 1-12 and 1-
- 15. The indication is outside of the core region and is 291 1/4" below the top flange of the vessel )
j [2]. Because the indication is located near the circumferential weld, it will be evaluated as both a l
weld and as a plate. The flaw will be evaluated as circumferential in orientation (using axial l stresses) based on the data in Reference 2. )
2.0 Geometry and Indication Characterization The following geometrical information was used in this evaluation:
i l l-15 Plate thicimess (ts,) = 5.321" [3] (tu/2 = 2.6605"). ;
l 2a = 0.35" [2] (a = 0.175")
, Depth (S) = 1.06" [2] = 1.06" S/a = 1.06"/0.175" = 6.06 (subsurface) c = (s + a - ts/2ytu, = (1.06+0.175-2.6605)/5.321) = -0.27 I dimension = 1.0" [2]
a/l = 0.175 (2a/l = 0.35) 3.0 Material Properties Flaw acceptance standards were developed in Reference 5. As in this reference, the l
APPENDA/MAPPA programs [6] will be used to determine acceptability for this indication.
Materials properties for Plate 1-15 (unirradiated) and the circumferential weld which joins Plate l l-12 and 1-15 are identical, which includes the following:
Initial RTsor = 30 F [19]
- Uncertainty in Initial RTuor = 5 F [18]
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Since the location is not irradiated, there will be no shift in the RTsor due to irradiation.
The flaw evaluations will be conducted for two cases: 1) assuming the indication is located within the plate and 2) assuming the indication is located within the weld. For both cases, the material properties will be identical.
4.0 Loading and Loading Conditions As in Reference 5, several load cases have been selected as being bounding for the flaw evaluation, based on the original stress report [17]. A derivation of their basis is included herein:
Hydrotest of the reactor pressure vessel at 1100 psig [8]. Using the current plant P-T curves which are valid through 32 EFPY, a hydrotest temperature of 192 was used.
This condition evaluates material properties at the lowest metal temperature with coincident highest reactor pressure vessel pressure. The pressure used bounds the normal pressure leak test that is conducted at the maximum normal operating pressure.
Heatup to 545 F (vessel fluid temperature) from 100 F at a rate of 100 F/hr. During this event, the outside temperature increases from 100 F to 150 F. The vessel pressure is taken to be 1000 psig. [10] This transient bounds all other heatups associated with reactor scrams.
Improper start of Recirculation Loop [17]. A rapid cooldown from operating temperature (545 F, vessel fluid temperature) to 400 F occurs as a step change. At 26 seconds, there is a step rise to 545* F. The outside temperature remains constant at 150 F. The pressure is assumed to remain constant at 1000 psig. [10] Due to technical specification limitations, the recirculation loops at Vermont Yankee can not be started if there is a temperature difference between the two loops (or between a loop and the reactor) of more than a 145 F.[9] Therefore, the minimum temperature for this event is taken as 400 F.
- Reactor blowdown transient with rapid cooldown from operating temperature of 545 F to 370 F in 10 minutes followed by further reduction in temperature at a rate of 100 F/hr. The corresponding reduction in outside temperature for the transient event is an initial temperature of 150 F reducing to 145 F in 10 minutes and then to 100 F in 160 minutes. Reactor pressure is at saturation conditions during the transient. For conservatism, the pressure at the end of rapid cooldown was taken at 247 psig ,
(corresponding to a temperature of 405 F) versus 160 psig (corresponding to 370 F at the end of the rapid blowdown). [10] This transient bounds all other cooldown transients associated with reactor scrams and normal cooldowns.
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The above events were evaluated in the original stress report [10] using normal / upset allowable stresses. Thus, they were similarly evaluated in this flaw evaluation. Therefore, a factor of safety of /10 on stress intensity (K) and 10 on flaw size (a) was used. There are no emergency / faulted conditions that produce thermal transients or pressure more significant than the cases evaluated; and if there were, the required safety factors of /2 in stress intensity factor and 2 on flaw size would allow for much larger flaw sizes. It is also noted that more recent thermal cycle definitions for other boiling water reactors (BWRs) classify the Improper Start of Recirculation Loop and Blowdown transients as emergency conditions.
Seismic loadings were not evaluated as they are insignificant in reactor vessel shell regions away from reactor supports. This is consistent with the original stress analysis of the reactor vessel.
For consideration of crack growth, thirty-five heatups/cooldowns will be assumed to occur in every 6-year interval. Sixteen years remain for the plant's life at the time of inspection (2012-1996). Therefore,105 heatups/cooldowns are conservatively assumed to occur between the inspection and end-of-life (EFPY = 32) [15].
5.0 Stresses Stresses for this evaluation were identical to those used in Reference 7. For completeness a derivation of their basis is included herein:
The shell pressure stresses were determined with classical thick shell formulae. A linear through-wall stress distribution was calculated which included pressure, bending, and thermal stresses due to the heatup transient.
Membrane pressure stresses for the shell sections have been determined with the use of thick-shell cylindrical equations for 1000 psig: [12]
Pr,'(r,' +r )
hoop 2 2 (r(r,2-r, ))
Pr,'
O axtal 2 (r,2 -r,)
For lower pressure conditions (i.e., loading condition), the pressure stresses were reduced in accordance with the ratio for the pressure at the particular condition divided by 1000.
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Through-wall thermal stresses for heatup and improper start of recirculation loop were found l
- with PIPE-TS2 [13]. Heat transfer coefficients for the inside and outside surface of the vessel
! were obtained from Reference 10. For the heatup event (forced convection), a value 1100 !
i 2 Bru/hr-ft - F was used for the inside surface. For the blowdown and improper start of l
- recirculation loop events, a value of 250 Bru/hr-ft2 - F was used for the inside surface. This l
- was based on the assumption that recirculation pumps would be stopped for the blowdown I event and the region would be stagnant for the improper restart case. The outside heat transfer
- z coefficient was assumed to be 0.2 Btu /hr-ft - F for all three events. I l l
- For the hydrotest case, the temperature distribution was assumed to be uniform at 192 F.
j The thiough-wall temperature distribution for the remaining cases was obtained from the ;
4 output of PIPE-TS2 [13]. '
! I
- Because the indication is assumed to be located in weld metal (as well as the base metal), it is l
l also assumed that weld residual stresses could be present. A cosine-shaped distribution was '
i assumed in the base metal with a maximum surface tensile stress of 8 ksi [14]. The 8 ksi stress i 2
was conservatively extended into the cladding for purposes of evaluation. l
! I j Table 1 shows the resulting stress distributions for the analysis. Note the through-wall
- thickness reflects the base metal thickness and the cladding thickness of 0.1875" [4], as j required by the APPENDA program. However, the through-wall stresses were calculated j without the cladding thickness.
i l Cladding stresses were also determined using PIPE-TS2 [13] which determines thermal stresses j in a bi-metallic cylinder. The cladding in a reactor pressure vessel is at its maximum tensile 4
value at cold ambient temperature conditions because of the relative thermal expansion coefficients for alloy steel and stainless steel. It was assumed that the cladding tensile stress at 70 F was nominally 35 ksi (in tension), slightly higher than the minimum yield strength for stainless steel (30 ksi) obtained from the ASME Code material property tables. With an increase in temperature, the cladding tensile stress decreases. Based on material properties used for the Vermont Yankee vessel analysis, at a temperature of approximately 380 F, the cladding stress reduces to zero. This temperature is referred to as the " stress-free" tempercure. This stress level is conservative, especially when one considers that some additional yielding would have occurred during the original vessel cold hydrotest that would tend to reduce the cladding residual stress below the yield value at ambient conditions. On the inside surface and cladding interface surface, the cladding-induced stress is equal to 19.99 ksi at 192 F. At the base metal interface and outside surface, the cladding-induced stress is -
equal to -0.69 ksi at 192 F. For the heatup, improper start of recirculation loop, and i blowdown cases, the mean through-wall temperature was always significantly greater than the
" stress-free" temperature. Therefore, the cladding stress for these cases was assumed to be i negligible.
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, For use in computing the flaw shape factor, Q, the reactor vessel material, SA533 Class 1 2
Grade B has a specific minimum yield strength of 50 ksi [16] at ambient conditions. The yield i strength for the hydrotest case (temperature of 192 F) was interpolated as 47.7 ksi. For the
- heatup, improper start of recirculation loop, and blowdown cases, the maximum wall j
temperature at the time in the transient event being considered was conservatively used to
] determine the reduction in yield stress value.
4
) 5.0 APPENDA Analysis j Based on the preceding informa: an, APPENDA input files were created assuming the indication is located within the weld metal and within the base metal. These files were run using the MAPPA utility. The following file nomenclature applies:
REGAAH Hydrotest Case - without Weld Residual Stresses REGAAHR Hydrotest Case - with Weld Residual Stresses
. REGATIA Heatup Case - without Weld Residual Stresses
- REGATIAR Heatup Case - with Weld Residual Stresses REGAT2A Improper Start of Recire. Case - without Weld Residual Stresses
} REGA T2AR Improper Start of Re:. Case - with Weld Residual Stresses
! REGAT3A B!owdown Case - without Weld Residual Stresses l REGA T3AR Blowdown Case - with Weld Residual Stresses
! All input files are included in Appendix A and on the attached diskette.
! 5.0 Allowable Flaw Sizes i \
! Based on the preceding evaluation, the maximum allowable flaw depths for the end-of-life J
! (EOL) were determined. Based on the MAPPA output, the sizes were governed by the l
! improper start of recirculation loop case, assuming the indication is located in the base metal l (REGAT2A) and in the weld metal (REGAT2AR). This is due to the fact that although the j blowdown case contains higher tensile thermal stresses than does the improper start of recirculation loop case, the blowdown case contains a lower pressure stress (due to 247 psig i
pressure ) than does the improper start of recirculation loop case (1000 psig). (In reality, the 3 flaw size was limited in all cases by the Code proximity rules, where flaws greater than the i limiting end of life flaw size would have to be evaluated as surface flaws.) Predicted crack I growth was then subtracted out to determine the current allowable flaw size. The limiting flaw j size by proximity rules is determined to be:
i S+a a max =
1,4 4
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Table 2 summarizes the results of the flaw evaluation, including the fatigue crack growth evaluation, with current allowable and EOL flaw sizes. Considerable margin exists between the EOL allowable flaw size and the predicted EOL flaw size based on the current inspection results.
Additionally, Figures 1 and 2 show the relationship between the stress intensity factor (K)
(allowable and actual) and crack size, assuming the flaw indication is located in the base and weld metal, respectively, for the limiting case ofImproper Start of Recirculation Loop. On these figures, the fracture toughness (200 ksi-in'8) is shown, as well as the allowable stress intensity with a factor of safety of v/10, or 63.2 ksi-in. Noting that predicted EOL flaw sizes are 0.3518 and 0.3534 inches, respectively, it can be seen that significant margin exists between the -
actual stress intensity for this EOL flaw size and the allowable stress intensity.
i i
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1 Table 1 - Stress Distributions Improper Distance Pressure Start of from inside Stress for Weld Heatup Recire. Blowdown surface of 1000 psig Residual Thermal Thermal Thermal Stress j cladding (in.) (ksi) Stress (ksi) Stress (ksi) Stress (ksi) (ksi) !
0 9.487 8 -7.54 18.29 23.43 0.187 9.487 8 -6.11 10.57 17.94 1
1 0.188 9.487 8 -6.11 10.57 17.94 l 0.776 9.487 6.128 -4.1 2.76 11.24 1.364 9.487 1.393 -2.34 -0.47 5.77 1.952 9.487 -3.997 -0.82 -1.45 1.41 l 2.54 9.487 -7.517 0.46 -1.68 -1.99 3.128 9.487 -7.518 1.51 -1.72 -4.55 3.716 9.487 -4.001 2.33 -1.71 -6.4 l 4.304 9.487 1.388 2.92 -1.7 -7.63 4.892 9.487 6.128 3.28 -1.67 -8.31 l 5.48 9.487 8 3.42 -1.63 -8.46 l l
l l
l l
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Table 2 Summary of Results of Flaw Evaluation Flaw Current Current Crack Allowable Depth Predicted Location Observed Allowable Growth, in. at End-of-Life End-of-Life Flaw Size Depth (2a), (2a), in. Flaw Depth (2a),
(2a),in. in. in.
Plate 0.35 1.7622 0.0018 1.764 0.3518 Weld 0.35 1.7606 0.0034 1.764 0.3534 Note: Reported allowable depths at end oflife are limited by Code proximity rules for subsurface flaws, not by stress intensity factor. If the cladding is considered, as required by 1989 ASME Section XI, the allowable flaw depth at end oflife would be 1.81 inches.
Note: In order to satisfy the primary stress limits of NB-3000 the maximum allowable flaw size is 2.76 inches for circumferential1y oriented flaws.
Since the predicted EOL flaw size is 0.3534 inches this requirement is satisfied.
I l
l l
l l
l Revision 0 1 2 Preparer /Date CCM 10/4/96 CCM 10/5/96 10/7/96 Checker /Date GLS 10/4/96 GLS 10/5/96
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Figure 1 Stress Intensity Factor Versus Crack Size for Subsurface Indication Without Residual Stress
, 200 2 .- - - -
e U
j 150 I
.#5 E ".g 100 )
c ,
Eb 50 l
1 00;..... -''". .
G 0 - 2r; : 00:?0000 0 0.2 0.4 0.6 0.8 1 i ,
1 Crack Size (a), in '
l l
- -+- Actual -e- Allowable + Klc l t a i
Figure 2 Stress Intensity Factor Versus Crack Size for Subsurface Indication With Residual Stress
- , 200 - - - - - .
o D
9 150
- L e
! ,Ied l l
Ede 100 i
8
+
1 I.
-d j
! n
- o .
N i o
5 0
^^^^ I'20'_'''':::::::::::0^^^
_ .. .. - l l
0 0.2 0.4 0.8 0.8 1;
l <
Crack Size (a), in l
! l :-+- Actual -e- Allowable + Kic . l i
c Revision 0 1 2 Preparer /Date CCM 10/4/96 CCM 10/5/96 % 10/7/96 Checker /Date GLS 10/4/96 GLS 10/5/96 M 10/7/96 File No. YAEC-25Q-301 Page No.10 of 12_
l 6.0 References i a.
- 1. ASME Boiler and Pressure Vessel Code,Section XI,1986 Edition.
? '
"VY Vessel Flaw Info.", Fax from J. Hoffman (YAEC) to C. Markovits (SI),4 pages 4 total,10/2/96, SI File: YAEC-25Q-201.
i
l YAEC-25Q-201.
- 4. Section S19, " Main Shell Stress Analysis Vermont Yankee Reactor Vessel", CB&I Contract 9-6201, General Electric P. O. No. 205-55565-1 Reactor, 8/19/69, SI File:
YAEC-21Q-207.
- 5. SIR-95-001, " Flaw Acceptance Standards for Vermont Yankee Reactor Pressure Vessel i Shell-Weld Inspections", Rev. O, March 1995, SI File: YAEC-21Q-401.
- 6. APPENDA and MAPPA, " Computer Programs for Performing Flaw Tolerance
- Analysis of Reactor Vessel Shells," Structural Integrity Associates (QA-1800), June
, 1994.
4
- 7. SI Calculation Package, " Assessment of Alternate Thermal Transients on Allowable Flaw i,
$izes", Rev. O,4/5/96, SI File: YAEC-21Q-303.
- 8. Yankee Atomic Electric Company Analysis Calculation No. VYC-829, " Reactor Pressure Vessel Pressure-Temperature Limits", Rev. 2,2/11/91, SI File
- YAEC-21Q-206.
i l
- 9. Telecon from John Hoffman (YAEC), February 3,1995, SI File: YAEC-21Q-102.
- 10. Excerpt of Vermont Yankee Stress Report, "Section T2, Thermal Analysis, Shroud
i 11. Not used in this evaluation I
. 12. Young, Warren C., "Roark's Formula for Stress and Strain", Warren Young,6th Edition, McGraw Hill Book Co.,1989.
i
- 13. PIPE-TS2, "A computer program to compute the transient thermal and thermal stress i
response of an axisymmetric two-material cylinder," Structural Integrity Associates, Revision 0 1 2 CCM 10/4/96 CCM 10/5/96 M 10/7/96 Preparer /Date Checker /Date GLS 10/4/96 GLS 10/5/96
% 10/7/96 File No. YAEC-25Q-301 Page No.1 I of _12_
i
Version 1.01, (QA-1260), April 1991.
- 14. EPRI-TR-100251, " White Paper on Reactor Vessel Integrity Requirements for Level A and B Conditions," Electric Power Research Institute, January,1993.
YAEC-21Q-102.
- 16. ASME Boiler and Pressure Vessel Code,Section III,1968 Edition.
- 17. Except of Vermont Yankee Stress Report,"Section T3, Thermal Analysis, Shroud Support", CB&I Contract 9-6201, SI File: YAEC-21Q-218.
- 18. U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99, Rev. 2, May 1988.
- 19. " Reactor Vessel Integrity Database", U.S. Nuclear Regulatory Commission, EOL:
03/21/12, Docket No. 50-271.
/CCM Revision 0 1 2 Preparer /Date CCM 10/4/96 CCM 10/5/96 @ 10/7/96 Checker /Date GLS 10/4/96 GLS 10/5/96 h 10/7/96 i File No. YAEC-25Q 301 Page No._12_ of _l2_ l
i REGAAH.IN Mon Oct 07 12:18:30 1996 Page 1 Structured file for input of Appendix A evaluation data Blank lines and input instructions must be present or inserted where present Fellowing two lines are titles:
Yankee Atomic RPV Analysis Region A (Beltline)
Hydrctist Case, without Residual Stresses, Axial Stresses 5.321 Base Material Wall Thickness, in
.1875 Clad Thickness, in 47.7 Yield Stress, ksi 4.76 Maximimum critical crack size a or'2a, Inches 2.76 Maximum allowable crack size et end of interval, a or 2a
.025 Crack Depth Increment for Calculations 30 Initial RTNOT 5 Margin in Initial RTNOT 0 Margin in RTNOT Shift 70 Material Chemistry Factor a
211 Fluence at Reference EFPY 32 Reference EFPY 1 Current EFPY 105 Cycles for crack growth A I = inside surf /O = Outside surf /S = submerged flaw /A=all types N N= Normal + Upset; E= Emergency +Faultod; L= Local IW8-3613(a)
MAX MAX = max accept. flew size / MIN = min. accept. size /MNL = min. Long flew R Surface K R to ratio / A to add peak / N if no clad K / U if user defined Strcss and temperature distribution in wall (except clad) from inside surface First entry is load case multipliers for the individual stresses 12 Number of points Olst 10 Sm, ksi Sbend,ksi Sth, ksi Sresid, ksi 7, F 1.1 0 0 0 O.000 9.487 0.000 0.000 8.000 192.000
- 0.187 9.487 0.000 0.000 8.000 192.000
- 0.188 9.487 0.000 0.000 8.000 192.000 i 0.776 9.487 0.000 0.000 6.128 192.000 1 1.364 9.487 0.000 0.000 1.393 192.000 1.952 9.487 0.000 0.000 -3.997 192.000 2.540 9.487 0.000 0.000 7.517 192.000 3.128 9.487 0.000 0.000 7.518 192.000 3.716 9.487 0.000 0.000 -4.001 192.000 4.304 9.487 0.000 0.000 1.388 192.000 l 4.892 9.487 0.000 0.000 6.128 192.000 5.509 9.487 0.000 0.000 8.000 192.000 Cladding Stresses as multiplier and linear distribution in clad and base l Mutt CladG0, ksi CladGt, ksi Base &O, ksl Baseat, ksi '
1 19.99 19.99 -0.69 -0.69 Fellowing are no. of Sub. Flaw eccentricity ratios (8 Max) 1 Eccentricity Ratios (negative from inside of vessel to outside) are:
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REGAAHR.1% Mon Oct 07 12:18:31 1996 Page 1 Structured file for input of Appendix A evaluation data Blank lines and Input instructions must be present or inserted where present Fellowing two lines are titles:
Yankee Atomic RPV Analysis Region A (Beltline) )
Hydr 0 test Case, with Residual Stresses, Axial Stresses j 5.321 Base Material Wall Thickness, in '
.1875 Clad Thickness, in l 47.7 Yield Stress, ksi i 4.76 Maximinum critical crack size a or 2a, inches i 2.76 Maxim m allowable crack size at end of interval, a or 2a i
.025- Crack Depth Increment for Calculations !
l 30 Initial RTNOT .
l 5 Margin in Initial RTNOT 0 Margin in RTNDT Shift 70 Material Chemistry Factor 2s1 Fluence at Reference EFPY 32 Reference EFPY 1 Current EFPY 105 Cycles for crack growth )
A 1 = inside surf /O = Outside surf /S = submerged flaw /Asatt types j N Na Normal + Upset; E= Emergency + Faulted; L= Local !@3613(a) j MAX MAX = max. accept. fla.# size / MIN = min. accept. size /MNL = min. Long flaw R Surface K: R to ratio / A to add peak / N if no clad K / U if user defined .
................ l
, Stress and temperature distribution in wall (except clad) from inside surface First entry is load case multipliers for the individual stresses )
12 Number of points '
Dist ID Sm, ksi Sbend,ksi Sth, ksi Sresid, ksi T, F l 1.1 0 0 1 I 0.000 9.487 0.000 0.000 8.000 192.000 0.187 9.487 0.000 0.000 8.C00 192.000 0.188 9.487 0.000 0.000 8.000 192.000 0.776 9.487 0.000 0.000 6.128 192.000 1.364 9.487 0.000 0.000 1.393 192.000 1.932 9.487 0.000 0.000 -3.997 192.000 2.540 9.487 0.000 0.000 -7.517 192.000 I 3.128 9.487 0.000 0.000 -7.518 192.000 I 3.716. 9.487 0.000 0.000 -4.001 192.000 1 4.304 9.487 0.000 0.000 1.388 192.000 l 4.892 9.487 0.000 0.000 6.128 192.000 5.509 9.487 0.000 0.000 8.000 192.000 Cladding Stresses as multiplier and linear distribution in clad and base Mutt CladB0, ksi Cladat, ksi Basea0, ksi Baseat, ksi 1 19.99 19.99 -0.69 0.69 Fallowing are no of Sub. Flaw eccentricity ratios (8 Max) .
1 l Eccentricity Ratios (negative from inside of vessel to outside) are. ;
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I Prepared by: D N/Y[D Checked b - W l0/7/95 N.,. k Fi!c , .- MC48EiQ ev: R 7_,
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REGAT1A.!N Mon Oct 07 12:18:29 1996 Page 1 Structured file for input'of Appendia A evaluation data Blank lines and input instructions must be present or inserted where present Following two lines are titles:
Yankso Atomic RPJ O lysis Region A (Beltline)
Hietup Case - <without Residual Stresses - Axial Stresses 5.321 Base Material Wall Thickness, in 1875 Cted Thickness, in 44.3 Ylvld Stress, ksi 4.76- Maajoins critical crack size a or 2a, inches 2.76 Maximum allowable crack size at end of interval, e or 2a
.025 Crack Depth increment for Calculations 30 , Initial RTNOT 5 i Margin in Initial RTNOT 0 Martin in RTNDT Shift 70/ Met rial Chemistry Factor 231 FL nee at Reference EFPY 32 R forence EFPY 1 C.srrent EFPY 103 Cycles for crack growth A = inside surf /O = Outside surf /S = submerged flaw /A=all types N els Normal + Upset; E= Emergency + Faulted; L= Local IWB 3613(a)
MAX , MAX = max. accept. flew size / MIN = min. accept. size /MNL = min. Long flaw R Surface K: R to ratio / A to add peak / N if no clad K / U if user defined Stre.ss and tenperature distribution in well (except clad) from inside surf ace First entry is load case multipliers for the individual stresses 12 Number of points Dijt ID Sm, ksi Sbend,ksi Sth, ksi Sresid, ksi T, F
." 1 0 1 0 0.000 9.487 0 -7.54 8.000 541.9 0.187 9.487 0 6.11 8.000 539.5 0.188 9.487 0 -6.11 8.000 537.1 0.776 9.487 0 -4.10 6.128 530.4 1.364 9.487 0 -2.34 1.393 524.5 1.952 9.487 0 -0.82 .-3.997 519.4 2.540 9.487 0 0.46 -7.517 515.1 3.128 9.487 0 1.51 7.518 511.6 3.716 9.487 0 2.33 4.001 508.8 4.304 9.487 0 2.92 1.388 506.7 4.892 9.487 0 3.28 6.128 505.5 5.509 9.487 0 3.42 8.000 504.9 Cladding Stresses as multiplier and linear distribution in clad and base Mutt Clada0, ksi Cladat, ksi Basea0, ksi Baseat, ks!
0 19.99 19.99 0.69 0.69 Following are no. of Sub. Flaw eccentricity ratios (8 Max) 1 Eccaltricity Ratios (negative from inside of vessel to outside) are:
.27 4
i l
1 h ..
' p" -
Prepared by: MM tolvl%
's Checked by: M i File No: M' 2% I Rev: E i Page b of b a
e #
. e RECAT1AR.IN Mon Oct 07 12:18:29 1996 page 1 Structured file for input of Appendix A evaluation data Blank lines ard Input instructions must be present or inserted where present F&llowing two lines are titles Yankee Atomic RPV Analysis Region A (Beltline)
H % tup Case - with Residual Stresses - Axial Stresses 5.321 Base Material Wall Thickness, in
.1875 Clad Thickness, in 44.3 Yield Stress, ksi 4.76 Maximimum critical crack size a or 2a, inches 2.76 Maximm allowable crack size at end of interval, a or 2a
.025 Crack Depth increment for Calculations 30 Initial RTNOT 5 Margin in Initial RTNOT 0 Margin in RTNDT Shift 70 Material Chemistry Factor 231 Fluence at Reference EFPY 32 Reference EFPY -
1~ current EFPY 105 Cycles for crack growth A ! = inside surf /O = Outside surf /S = submerged flaw /Asall types N N= Normal + Upset; E= Emergency + Faulted; L= Local !W8 3613(a)
MAX MAX = max. accept. flaw site / MIN = min. accept. size /MNL = min. Long flaw I R Surface K R to ratio / A to add peak / N if no clad K / U if user defined Str:ss and temperature distribution in wall (except clad) from inside surface First entry is load case multipliers for the individual stresses 12 Nunber of points Dist 10 Se, ksi $ bend,ksi Sth, ksi Sresid, ksi T, F 1 0 1 1 0.000 9.487 0 7.54 8.000 541.9 0.187 9.487 0 -6.11 8.000 539.5 i
0.188 9.487 0 6.11 8.000 537.1 0.776 9.487 0 4.10 6.128 530.4 1.364 9.487 0 2.34 1.393 524.5 1.952 9.487 0 -0.82 3.997 519.4 2.540 9.487 0 0.46 7.517 515.1 3.128 9.487 0 1.51 -7.518 511.6 3.716 9.487 0 2.33 4.001 508.8 4.304 9.487 0 2.92 1.388 506.7 2 4.892 9.487 0 3.28 6.128 505.5 '
5.509 9.487 0 3.42 8.000 504.9 Cladding Stresses as multiplier and linear distribution in clad and base Mutt Clada0, ksi Cladat, ksi -BaseGO, ksi Baseat, ks!
0 19.99 19.99 -0.69 0.69 F4Llowing are no. of Sub. Flaw eccentricity ratios (8 Max) 1 Eccentricity Ratios (negative from inside of vessel to outside) are 0.27 1
Prepared by: cm tolt/4 Checi:od b : /dt) M/7#4 File No: T f 2cG Rev:1 -.
, Page of
. _ . .- - . - . . - -. _. - - - -. - - , . =
REGAT2A.IN Con Oct 07 12:18:30 1996 Pigt 1 Structured file for input of Appendix A evaluation data
=
Blank lines and Input instructions must be present or inserted where present Fellowing two lines are titles Yankee Atomic RPV Analysis Region A (Beltline)
Inproper Start of Recirc. Case - without Residual Stresses . Axial Stresses 4
5.321 Base Material Wall Thickness, in
.1875 Clad Thickness, in 45.4 Yield Stress, ksl 4
4.76 Maximina critical crack size a or 2a, inches .
2.76 Maximum allowable crack size at end of interval, a or 2a
.025 Crack Depth Increment for Calculations 30 Initial RTNOT 5 Margin in Initial RTNOT 0 Margin in RTNOT Shif t i 70 Material Chemistry Factor 221 Fluence at Reference EFPY 32 Reference EFPY -
1 Current EFPY 105 Cycles for crack growth A ! = inside surf /0 = Outside surf /S = subnerged flaw /Asalt types N N= Normal + Upset; Es Emergency + Faulted; La Local IW8 3613(a)
MAX MAX = max. accept, flew size / MIN = min. accept. size /MNL = min, long flaw R Surface K: R to ratio / A to add peak / N if no clad K / U if user defined Stress and tenverature distribution in wall (except clad) from inside surface First entry is load case multipliers for the individual stresses 12 Nurber of points Olst 10 Sm, ksi $ bend,ksi Sth, ksl Sresid, ksi T, F 1 0 1 0 0.000 9.487 0 18.29 8.000 477.7 0.187 9.487 0 10.57 8.000 491.1 0.188 9.487 0 10.57 8.000 503.6
- 0. 776 9.487 0 2.76 6.128 529.8 1.364 9.487 0 0.47 1.393 540.7 1.952 9.487 0 1.45 3.997 544.0 2.5t0 9.487 0 1,68 7.517 544.8 3.128 9.487 0 1.72 -7.518 545.0 3.716 9.487 0 -1.71 -4.001 545.0 4.304 9.4'7 d 0 1.70 1.388 545.0 4.892 9.487 0 -1.67 6.128 544.9 5.509 9.487 0 1.63 8.000 544.8 Cladding Stresses as multiplier and linear distribution in clad and base Mult CladG0, kal CladGt, ksi BaseG0, kal Baseat, ksi 0 19.99 19.99 0.69 0.69 Following are no. of Sub. Flaw eccentricity ratios (8 Max) 1 Ecc:tricity Ratios (negative from inside of vessel to outside) are: I 0.27 '
Prepared by: M O/t/$,
Checked by:_ M70 M/7/f/-
Fila No:M6C.-tsp Rev:le j Page- / 6 ef g
REGAT2AR.IN Mon Oct 07 12:18:30 1996 Page 1 Structured file for input of Appendix A evaluation data Blank lines and input instructions nast be present or inserted where present Fellowing two lines are titles Yankee Atomic RPV Analysis Region A (Beltline)
Improper Start of Recire. Case - with Residual Stresses - Axial Stresses .
5.321 Base Material Wall Thickness, in
, .1875 Clad Thickness, in 44.4 Yield Stress, kai 4.76 Maximimum critical crack size a or 2a, inches 2.76 Maximum attowable crack size at end of interval, a or 2a
.025 Crack Depth Increment for Calculations 30 Initial RIN0T 5 Margin in Initial RTND'T 0 Margin in RTNOT Shift 70 Material Chemistry Factor 221 Fluence at Reference EFPY 32 Reference EFPY 1 Current EFPY 105 Cycles for crack growth A I = inside surf /0 = Outside surf /S = subnerged flav /A=all types N Na Normal + Upset; Es Emergency + Faulted; L= Local IW8 3613(a)
MAX MAX = max accept. flaw size / MIN e min. accept. size /MNL = min. Long flaw R Surface K R to ratio / A to add peak / N {f no clad K / U if user defined Stress and temperature distribution in well (except clad) from inside surface First entry is toad case multipliers for the individual stresses 12 Ntaber of points Olst ID Sm, ksi Sbend,ksi Sth, kal Sresid, ksi T, F 1 0 l 1 0.000 9.487 0 18.29 8.000 477.7 0.187 9.487 0 10.57 8.000 491.1 0.188 9.487 0 10.57 8.000 503.6 0.776 9.487 0 2.76 6.128 529.8 .
1.364 9.487 0 0.47 1.393 540.7 !
1.952 9.487 0 1.45 3.997 544.0 2.540 9.487 0 . 1.68 7.517 544.8 3.128 9.487 0 1.72 7.518 545.0 3.716 9.487 0 1.71 4.001 545.0 4.304 9.487 0 1.70 1.388 545.0 4.892 9.487 0 1.67 6.128 544.9 5.509 9.487 0 -1.63 8.000 544.8 j Cladding Stresses as multiplier and linear distribution in clad and base Mutt CladGO, ksi CladGt, ksl BaseGO, ksi Baseat, kal 0 19.99 19.99 0.69 0.69 Following are no. of Sub. Flaw eccentricity ratios (8 Max) 1 Eccentricity Ratios (negative from inside of vessel to outside) are: I
.27 Prepared by: cw loMu
'W1/9h IChecked : _
File No: i% Rev: L Page Ne of M
RECAT3A.!N Mon Oct 07 12:18:30 1996 P gi 1 Structured file for input of Appendix A evaluation data Blank lines and Input instructions must be present or inserted where present Followir.3 two lines are titles:
Yankee Atomic RPV Analysis Region A (Beltline)
Blowdown Case - without Residual Stresses - Axial Stresses 5.321 Base Material Wall Thickness, in
.1875 Clad Thickness, in 44.7 Yield Stress, ksi 4.76 Maximimum critical crack size a or 2a, inches 2.76 Maximum allowable crack size at end of interval, a or 2a
.025 Crack Depth increment for Calculations 30 Initial RTNDT 5 Margin in Initial RTNOT 0 Margin in RTNDT Shift 70 Material Chemistry Factor 2s1 Fluence at Reference EFPY 32 Reference EFPY 1 Current EFPY 105. Cycles for crack growth A I = inside surf /O = Outside serf /S = submerged flaw /Asall types N N= Normal + Upset; Es E aergency+ Faulted; L= Local IWB-3613(a) '
MAX MAX = max. accept. flaw size / MIN = min. accept. size /MNL = min. Long flaw j
'"'!!*!.S ".!!.'!!' ' ^ * 'dd P"' ' " " " ***d *'"" "**'d'""'d l
Striss and temperature distribution in wall (except clad) from inside surface First entry is load case multipliers for the individual stresses 12 Number of points Dist ID Sm, ksi $ bend,ksi Sth, ksi Sresid, ksi T, F
.247 0 1 0 0.000 9.487 0 23.43 8.000 419.8 I 0.187 9.487 0 17.94 8.000 429.1 1 0.188 9.487 0 17.94 8.000 438.1 l 0.776 9.487 0 11.24 6.128 460.5 i 1.364 9.487 0 5.77 1.393 478.7 i 1.952 9.487 0 1.41 3.997 493./. l 2.5t0 9.487 0 1.99 7.517 504.8 I 3.128 9.487 0 -4.55 7.518 513.5 3.716 9.487 0 -6.40. 4.001 519.9 4.304 9.487 0 -7.63 1.388 524.2 4.892 9.487 0 8.31 6.128 526.6 l
5.509 9.487 0 8.46 8.000 527.3 '
Cladding Stresses as multiplier and linear distribution in clad and base Mult CladWI, kai Cladat, ksi Basea0, ksi Baseat, ksi O 19.99 19.99 -0.69 0.69 Fcliowing are no. of Sub. Flaw eccentricity ratios (8 Max) 1 Eccentricity Ratios (negative from inside of vessel to outside) are:
.27 Prepared by: @/k40
' Checked y:_ [MP F/ 7/96 Filo No:- 22GQ 3ew 2--
lPago- RM ef
8 ,
REGAT3AR.IN Mon Oct 07 12:18:30 1996 page 1 Structured file for input of Appendix A evaluation data Blank lines and Input instructions must be present or inserted where present Fcliowing two lines are titles:
Yankee Atomic RPV Analysis Region A (Beltline)
Blowdown Case - with Residual Stresses - Axial Stresses 5.321 Base Material Wall Thickness, in
.1875 Clad Thickness, in 44.7 Yield Stress, ksi 4.76 Maximimum critical crack size a or 2a, inches 2.76 Maximum allowable crack size at end of interval, a or 2a
.025 Crack Depth increment for Calculations 30 Initial RTNOT 5 Marefn in Initial RTNDT 0 Margin in RTNOT Shift 70 Material Chemistry Factor 231 Fluence at Reference EFPY 32 Reference EFPY
- 1 Current E*PY 105 Cycles for crack growth A I = inside surf /0 = Outside surf /S = submerged flaw /A=all types N N= Normal + Upset; Es Emergency + Faulted; La Local IWB-3613(i.)
MAX MAX = max. accept. flaw size / MIN = min, accept. size /MNL = min. Long flaw R Surface K R to ratio / A to add peak / N if no clad K / U if user defined Str:ss and temperature distribution in wall (except clad) from inside surface First entry is load case multipliers for the individual stresses 12 Number of points Dist ID Sm, ksi $ bend,ksi Sth, ksi Sresid, kal T, F
.247 0 1 1 1 0.000 9.487 0 23.43 8.000 419.8 0.187 9.487 0 17.94 8.000 429.1 l 0.188 9.487 0 17.94 8.000 438.1 '
O.776 9.487 0 11.24 6.128 460.5 1.364 9.487 0 5.77 1.393 478.7 1.952 9.487 0 1.41 -3.997 493.4 2.5LO 9.487 0 1.99 -7.517 504.8-3.128 9.487 0 4.55 7.518 513.5 3.716 9.487 0 -6.40 4.001 519.9 I 4.304 9.487 0 7.63 1.388 524.2 4.892 9.487 0 8.31 6.128 526.6 5.509 9.487 0 -8.46 8.000 527.3 Cladding Stresses as multiplier and linear distribution in clad and base Mult CladGO, ksi Cladat, ksi Basea0, ksi Baseat, ks!
0' 19.99 19.99 -0.69 0.69 Fstlowing are no. of Sub. Flaw eccentricity ratios (8 Max) 1 Eccentricity Ratios (negative from inside of vessel to outside) are:
.27 Prepared by: Ul%lO Checked b : Nfd)l/7/94 Fi!c No: M iGQ Rev 2- '
Page /4 0f M
A
. 4 ,
Attachment 2 Comparison of Original Design Basis Transients and Transients Considered in Flaw Evaluation l
l i
i l
l
3 The following four pages, which are excerpted frorn the original reactor pressure vessel design specification, describe the thermal transients for which the vessel was designed.
The transients applicable to the flaw evaluation for the vessel shell are given under the '
heading " Closure Flange & Adjacent Shell".
The original vessel analysis evaluated 200 heat ups at 100 F/hr,199 cool'; owns at 100 F/hr and one rapid cool down at 1000F/hr to 375F.
The flaw evaluation considered 105 remaining heat ups at 100F/hr and conservatively
- enveloped the normal cool downs by considering 105 rapid cool downs.
In addition the evaluation considered two additional transients: 105 hydrotests at 1100 psig and 105 improper starts of a recirculation system pump.
4
, a 12 GENER AL h ELECTRIC Document Wo, 2fA1115 Rev. 1 NUCLEAR ENERGY OlVI$ ION General Electric Class TRANSMITTAL VERMONT YANKEE PROJECT (S) l TITLE OF REACTOP PRESSURE VESSEL DOCUMENT TYPE OF M PURCHASE SPECIFICATION REPLACES DOCUMENT:[] SYSTEM DESIGN SPECIFICATION DOCUMENT NO.-
[] INSTALLATION SPECIFICATION Il PIPINC. OR COOLING SYSTEM INVOLVED DR HEISING ISSUED BY JA MAST DAT!007 2 : msg RESPONSIBLE ENGIMEER REFERENCES l 2-1-1 MASTER PA3TS LIST (MPL) NOS.
SPECIFICATIONS 21A9821 and 21A9825 l 1
DRAWINGS 107c51n9 RR9n411 e4 Q1on?QA OTHER FIVISION RECORD
( REVISED PER REK, ECN, KTEX) #NE21400 16_20 47 thru 52 REVISION IDENTIFIED WITH &
SHEETS AFFECTED COMMENTS: ._
DT STitTRifTTON COPIES NAME MAIL CODE COPIES NAME MAIL CODE DR HF.ISING 743 1 AC DE LOACH 621 1 GRU ( 74 6 1 ,
Alexander 366 9 Petersen 376 1 Schlinger 355 2 Roof 320 4 Cifford 632 1 375 1 591-100 1 595 1 624 1 711 1 713 1 722 1 723 1 743 3 743-A 1
. l n /ta f f n
i I
I TEMEERATURE TRANSIENTS . .
No. Fluid Fluid Fluid State Vessel Part of Temp. Start End of Fluid Vessel '. l l Cycles Rate Temp. Temp. Fluid Velocity Pressure Notes , , , , , , , , , , , ,
Recire. Outlet 200 100 F/hr 100 546 Water 25 ft/see Saturated 1000 F/hr 546 370 Water 25 ft/see Saturated Followed hv 200 100 F/hr 370 100 5 Step 546 (Step 546 (Step Water 5 ft/sec 1000 psig 26 seconds duration !
to 130) fr om 130) (reverse flow) at 130*F j i
Recire. Inlet 200 100 F/hr 100 546 Water 32 ft/see Saturated Nozzle ... .
200 0 546 5L6 Water 32 ft/sec Followed by 0 90 90 Water 10 ft/see 170 peig ,
t
- ~rs n assman Steam Outlet 532 100 F/hr 100 546 Steam 5 ft/see Saturated condensing Steam 1 N6zzle in nozzle 531 100 F/hr 546 346 Steam 5 ft/see Saturated Followed by 1000 F/hr 346 296- Water 14 ft/see Saturated Followed by 100 F/hr 296 100 Water 0 Saturated 1 1000 F/hr 546 370 Steam 25 ft/sec Saturated Followed by-100 F/hr 370 100 Steam - 0 Saturated i Water '
Feedwater 0 376 376 Water 10 ft/see 1100 psig Steady State 546' Nozzle
. Water in Ve99el !
1500 100 F/hr 100 546 Water 0 1100 psig Followed by Step To O 100 100 Water 5 ft/see 1100 psig FollowedbyStepTol. >
250 F/hr 260 376 Water 5* ft/sec 1100 psig ,
c) Core Spray 250 100 F/hr 100 546 Water 0 Saturated C7 Nozzle ' 250 0 546 Water 0 1000 psig Followed by (Steam ' g, 80 ** 11 0 Water 20 ft/sec 0 psig in Thermal Sleeve u,p Annulus) ' ua _m --
- Velocity changes linearly 5 ft/see to 20 ft/sec >
** Water reaches this temperature in 15 seconds A7TACTIMENT D _. ,, ..
TEMPERA'ITRE TRANSIENTS cm , No. Fluid Fluid Fluid State Start End of Fluid Vessel Vessel Part of Temp. Notes Temp. Temo. Fluid Velocity Pressure Cycles Rate Water 0 Saturated Followed by Jet Pump 200 1000 F/hr 546** 370 '- 100 F/hr 370 100 0 Saturated Instrument Nozzles . 45* 45' Water 15 ft/see 1000 psig steady State 546* CRD Hydraulic 200 0 Return Nozzle Water in vessel 10 0 80 EO Water 15 ft/sec 1000 psig Nozzle at 546*** Core Diff. & *** Isothermal at Liquid Control Start Nozzle 200 1000 F/hr 546** 370 Water 0 Saturated Followed by 100 F/hr 370 100 Water- 0 Saturated 2 Inch In- 200 100 F/hr 330 100 Water 0 Saturated Nozzle at 546* Iso-thermal at Start strument Nozzle Followed by 200 1000 F/hr 546** 370 Water 0 Saturated 100 F/hr 370 100 0 Saturated Core Support 200 100 F/hr 100 546 Water 5 ft/sec* Saturated Structure 199 100 F/hr 546 346 Water 5 ft/sec* Saturated Followed by 1000 F/hr 346 296 Water 5 ft/sec* Saturated Followed by 100 F/hr 296 100 Water 5 ft/sec* Saturated 1 1000 F/hr 546 370 Water 5 ft/sec* Saturated Followed by 100 F/hr 370 100 Water is on all sides of Core Support structure and on inside surface of Reactor Vessel for both the above transients. 5 Step 546 546 Water See Recire 1000 psig 26 seconds duration Step to 130 Step from 130 Outlet of 130*F C3, c to
- Water velocity above the support plate, on the vertical surface of the shroud cylinders, 'and on the underside of the FA support plate is essentially zero and natural convection heat transfer coefficient may be used. The 5 ft/see velocity c3 is directed against the vessel bottom head but by using natural convection heat transfer coefficients a conservative g (( c.nalysis should result.
** Water reaches this temperature at a fluid terperature rate of 100F/hr.
*** see 919D294 , Sht. 3 for location of liquid c:n:rol ficw.
TEMPERATURE TRANSIEhrS No. Fluid Fluid Fluid State Vessel Part of Temp. Start End of Fluid Vessel . Cvcles Rate Temp. Temp. Fluid Velocity Pressure Notes .
*)
Closure Flanges 200 100 F/hr 100 546 Steam 0 Saturated Condensing Steam
& Adjacent Shell Heat Transfer
~
and Refueling I
- Bellows Support 199 100 F/hr 546 350 Steam Saturated Followed by Skirt Flooding with water at 330*F Free Followed by 100 F/hr 300 150 Water conv. Saturated 1 1000 F/hr 546 375 Steam Free Saturated Followed bv 100 F/hr 375 103 Steam Conv. Saturated Bottom Head & 200 100 F/hr 100 545 Water 5 ft/sec Saturated i Support Skirt 199 100 F/hr 546 375 Water 5 ft/sec Saturated Followed by 300 F/hr 375 330 Water 5 ft/sec Saturated Followed by 100 F/hr 330 100 Water 5 ft/see Saturated 1 1000 F/hr 546 370 Water 5 ft/sec Saturated Followed by 100 F/hr 370 100 Water 5 ft/see Saturated Control Rod 370 0 50' 50* Water
- 1000 psig Penetration As-Drive Penetra-
- Heat transfer coefficients throur,h a thermal 10 ft/see sembly at 546*
tion Peripheral sleeve within the housir.g arei outside ** 3**fE Location and Central Locatior (a) h = 75 Btu /hr ft2*F above stub tube assembly (b) h = 193 Btu /hr f t2
- F at s tub tube (c) h = 40 Btu /hr ft2.F below stub tube NOTE: For the purposes of demonstrating for other parts of the vessel applicable exception from Detailed Stress i Analysis according to Paragraphs N-415.1 and N-451 of the ASME Code Section III, the following values may be used.
(a) Total design pressure cycles from atmospheric pressure to operating pressure and back to f( atmospheric pressure is 200 cycles. {$ (b) The number of significant pressure fluctuations (200 psi full range) during normal opera-p, tion is 280. C$ (c) The number of major temperature fluctuations is 400
$3 g ATTAC'ijgNT D Sht. 1 Cont. on Fist,
__ . - _ - _ -_-__________ - _______________________-_-__- _____-__ _-_ __ - _____ - ____- _-_-_____-_________}}