ML20133M045
| ML20133M045 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 01/10/1997 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20133M037 | List: |
| References | |
| NUDOCS 9701220235 | |
| Download: ML20133M045 (19) | |
Text
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ATTACHMENT 3
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TECHNICAL SPECIFICATION MARK UP Revised Figure 3.4.11 1 i
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MINIMUM REACTOR VESSEL METAL TEMPERATURE (V) t i
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RIVER BEND 3.4-32 Amendment No. 81
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Figure 3.4.11 1 (page 1 of 1)
Minimum Temperature Required vs. RCS Pressure l
RNER BEND 3.4-32
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ENCLOSURE 1 i
Structural Integrity Associates, Inc. Letter Report Revised (12 EFPY) P-T Curves for River Bond Station Letter #GLS-96-059; SIR 96-096, Rev. 0 l
October 22,1996 l
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StructuralIntegrity Associates, Inc.
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October 22,1996 san.;ose. CA 95118-1557 GLS-96-059 pnons.os.ps.s2co SIR-96-0%, Rev. O k
806-p8-8964 sstevens@structint com Mr. Erwin J. Zoch, P.E.
River Bend Station Entergy Operations, Inc.
P. O. Box 220 St. Francisville, LA 70775
Subject:
Revised (12 EFPY) P-T Curves for River Bend Station
Dear Erwin:
In accordance with the Reference I contract, this letter repon documents the results of the i
pressure temperature (P-T) curve calculations performed by Structural Integrity Associates (SI)'
for 12 effective full power years (EFPY) for River Bend Station (RBS). The input, methodology, j
analysis, and results are described below. In addition, attached please find a copy of SI Calculation No. RBS-03Q-301, Revision 0, " Pressure-Temperature Curve Calculation for 12 EFPY," 10/16/96, and a floppy disk containing the RTeT and P-T curve EXCEL spreadsheets developed as a part of this work. The attached items, together with this letter report, constitute the complete set of deliverables for this project in accordance with Reference 1.
INTRODUCTION This report documents the development of revised P-T curves for RBS valid for up to 12 EFPY of operation. The P-T curves documented herein are intended to replace the currently existing P-T curves [2] which are valid for up to 8 EFPY of operation. The developraent of the 8 EFPY P-T curves, in accordance with Regulatory Guide 1.99, Revision 2 (RG 1.99) (3), is documented in Reference 4. The Reference 4 report includes the effects of the beltline, bottom head (CRD penetrations), and feedwater nozzle locations. The detailed specifics of precisely how the P-T curves were calculated are not included; however, all of the necessary inputs are included.
Tabulated values for the current P-T curves are provided in Reference 5.
There were three objectives to this current work, as identified in Reference 1:
l.
RTmy. Determination: The Reference 4 report provides RTer estimates for cil of the various RBS beltline materials. Since RTmi s an important and significant input i
prrameter to the development of P-T curves, an EXCEL spreadsheet specific to RBS was generated to validate the RTm7 estimates contained in Reference 4. The spreadsheet can be used in the future to provide RTm7 estimates for any EFPY.
Asses. SM
$#ser Bestas. IN PL Lamasseste. M Inesst.1 meson assesmetries. lat.
Miene 216-464-ages P%ns 301-5862323 Phons 964-444-1882 Phone 02 306-550s
$dver Sonne MD Phone 301589-2500
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i Page 2 October 22,1996 Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. O i
a 2.
Modr/Dewlqpment: A valid calculational tool (EXCEL spreadsheet) was developed for j
e l
computing P-T curves for RBS. The spreadsheet tool is convenient in that it possesses l
both computational and plotting capabilities, both of which are necessary for generating P-
~
T curves This tool provides fbrther convenience in that it can be used by Entergy for i
i future use in developing their own P-T curves, as well as to fulfill their requirement of j
providing the tabulated P T points for the developed P-T curves. The tool was
" benchmarked" by first matching it to the current 8 EFPY curves. This step ensured j
consistency with past work done for RBS in the Reference 4 repon. Of particulir interest were the thermal stress intensity factors previously used in the Reference 4 analysis. Since there can be signi6 cant variation in these factors depending upon the method of calculation used, benchmarking the model eliminated any "mconsistencies. Benchmarking against Reference 4 is considered reasonable, since it is apparent that significant effon has been expended in developing the RBS P-T curves in the past. The past work was initiated l
to address Generic Letter 88 11 requirements and implement Technical Specification 1
l changes.
3.
P-TCurw Dewtopment: Once the spreadsheet model was developed and benchmarked, P-T curves were developed for 12 EFPY using the RTm7 estimates established for RBS.
The curves were generated in the format shown in Reference 2 so that they are suitable for j
placement into the RBS Technical Specifications.
i j
The results of each of the objectives identified above are presented in the sections which follow.
l RTwor DETERMINATION i
i Appendix A of Reference 4 provides RTer estimates for the RBS beltline materials in i
accordance with RG 1.99 for various EFPY levels. An EXCEL spreadsheet was set up to j
perform the RTer calculations, and is shown in Table 1. The inputs used for the calculations in Table I were obtained from Appendix A of Reference 4 unless otherwise noted. All details of the calculations are identified in the notes to the table. The results in Table 1 are seen to be identical to those of Appendix A of Reference 4 for 12 EFPY, thus validating the previous RTer i
estimates and those used in the current evaluation.
f MODEL DEVELOPMENT f
In this section, the methodology used for calculating the P-T curves is detailed. This i
methodology documents the equations used in the P-T curve EXCEL spreadsheet developed for i
this work. The methodology is based on the requirements of References.6 and 7. The 1992 4
edition of Section XI, Appendix G of the ASME Code was compared to the 1989 edition, which j
is the latest NRC-accepted version of the ASME Code. Side-by-side comparison of these two j
editions of Appendix G reveals that the they are identical from a methodology point of view.
]
Therefore, this analysis fulfills the requirements of both versions of Appendix G.
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( Structurallatogrity Associates, Inc.
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Page 3 October 22,1996 Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. 0 The approach used for calculating the P-T curves is summarized below. Note that the following i
is based on developing a model that calculates P-T curves which match those previously l
developed in Reference 4:
l Assume a coolant temperature, Tw A range of temperatures are assumed that a.
resuk in P-T points appropriate for the boiling water reactor (BWR) operating l
regime.
b.
For the T%, assumed in step (a), compute the temperature at the assumed flaw tip, Tp4,(i.e.,1/4t into the vessel wall). This is accomplished by adding a through-wall temperature drop term, ATw, to Tm to account for the temperature drop due to heat transfer between the inside surface and the 1/4t l
location. The value of ATw was varied such that the resulting P-T Cuive A l
matched that previously determined in Reference 4. This eliminated any l
inconsistencies that might have arisen if ATw were determined by independent heat transfer analysis.
l Calculate the allowable stress intensity factor, Km, based on Tp4, using the l
c.
relationship from Reference 6:
l Km = 1.223 elm 44T ARM @) + 26.78 l
where: T Tp4, ('F)
=
l ART = adjusted reference temperature for limiting beltline material ('F) l Km = allowable stress intensity factor (ksi/ inch) l Note that a maximum value of 200 ksi/ inch is allowed.
d.
Calculate the allowable pressure stress intensity factor, Ky, using the appropriate i
relationship for the P-T curve under consideration:
(
Ky = Km/I.5 for Curve A (i.e., pressure test curve)
K, = (Km-Kg)/2.0 for Curves B and C (i.e., core not critical l
and core critical curves) thermal stress intensity factor (ksi/ inch) where: Kg
=
The value of Kg was varied such that the resulting P-T Curve B matched that previously determined in Reference 4. This eliminated any inconsistencies that might have arisen if Krr were determined by independent thermal stress analysis.
allowable pressure stress intensity factor (ksi/ inch) l Ky
=
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StrstctarralIntegrity Associates, Inc.
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Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. 0 i
-c.
Compute the pressure, P. The relationship for the pressure, P, to the allowable pressure stress intensity factor, K,, is as follows:
Ky = M, o, + Mg g I
where:
M, = membrane stress correction factor from Figure G-2214-1 of Reference 6. The bounding upper line for M. (corresponding to e/o = 1.0)in Figure G-2214-1 was used. Note, however, p
that any differences introduced by this assumption were i
effectively removed by adjusting ATw and Krr such that the resulting P-T limits matched the previous RBS P-T curves, as 4'
mentioned above.
i e,
membrans stress due to pressure (ksi)
=
PR/t for a thin-walled vessel
=
l P
pressure (ksi)
=
R vesselinside radius (inches)
=
vessel minimum wall thickness (inches) i t
=
b bending stress correction factor = (2/3)M.
M o,
bending stress due to pressure (ksi)
=
0 for a thin-walled vessel
=
i l
- Thus, P = Kyt/(RM.)
i 1
f.
Repeat steps (s) through (e) for other temperatures to generate a series of P-T i
points.
g.
Subtract any applicable instrument errors for temperature and pressure from 4
T and P, respectively. The resulting pressure and temperature series constitutes the P-T curve Instrument errors were assumed to be zero for RBS, as j
they were not used in the prior P-T curve work. The P-T curve relates the i
.n T.
required reactor fluid temperature in the beltline region to the reactor pressure in the beltline region. For the purposes of this evaluation, it was assumed that the minimum reactor metal temperature and the minimum reactor fluid i
temperature were equal. This assumption is consistent with prior P-T curves developed for RBS.
1 The following additional requirements were used in the Reference 4 report to define the lower i
portion of the P-T curves. These limits are established by the discontinuity regions of the vessel (i.e., flanges, nozzles, etc.), and were retained throughout the current analysis (i.e., they were j
assumed correct and do not change since the discontinuity regions are not affected significantly by fluence):
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Mr. Erwin J. Zoch GLS-%-059/ SIR-96-096, Rev. O i
Fw Cum A:
Thermal stresses were assumed to be negligible during the pressure test condition and were therefore not considered.
If P is greater than 20% of the pre-service hydro test pressure, the temperature must be greater than RTmy of the limiting flange material plus 90'F [7). The pre-service hydro test pressure was assumed to be 1562.5 psig (=312.5/0.20),
based on the fact that the current 8 EFPY P-T curves establish this limit at 312.5 psig [5).
If P is less than 20% of the pre-service hydro test pressure, the temperature must be greater than RTer of the limiting flange material plus 60'F. This has been a standard recommendation by GE for the BWR industry [4). For the RBS flange material, this minimum temperature is 70*F [5).
j Fw Cum B:
If P is greater than 20% of the pre-service hydro test pressure, the temperature must be greater than RTer f the limiting flange material plus 120'F [7).
o If P is less than 20% of the pre-service hydro test pressure, the temperature must be greater than RTer f the limiting flange material plus 60*F. This has been a o
standard recommendation by GE for the BWR industry (4). For the RBS flange material, this minimum temperature is 70*F [5).
Fw Cum C:
}
Per the requirements of Paragraph IV.A.2 of Reference 7, the core critical i
(Curve C) P-T limits must be 40*F above any Curve A or B limits. Curve B is more limiting than Curve A, so Curve C is Curve B plus 40'F.
Another requirement of Paragraph IV.A.2 of Reference 7 (or actually an allowance for the BWR), concerns minimum temperature for initial criticality in a startup.
Given that water level is normal, BWRs are allowed initial criticality at the closure j
flange region temperature (RTer + 60*F) if the pressure is below 20% of the t
pre service hydro test pressure. This corresponds to 70*F for RBS.
Also per Paragraph IV.A.2 of Reference 7, at pressure above 20% of the pre service hydro test pressure, the Curve C temperature must be at least that required for the pressure test (Curve A at 1,100 psig). As a result of this requirement, Curve C must have a step at a pressure equal to 20% of the i
pre-service hydro pressure to the temperature required by Curve A at 1,100 psig, or 40*F, whichever is greater. (For the curves covered in this analysis through 12 EFPY, the 40'F step is limiting.)
l i
An EXCEL spreadsheet was developed to perform the necessary calculations described abovc.:.d generate the P-T curves. A " benchmark" case was run in the spreadsheet for 8 EFPY. The limiting ART value of 60.5'F for 8 EFPY, and the vessel dimensions for the RBS plate matenal I
f SNcturalIntegrityAssociates,Inc.
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i Page 6 October 22,1996 l
Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. 0 documented in Reference 4 were used as input to the spreadsheet for this case. The results i
generated by the spreadsheet were identical to those contained in the Reference 4 report after appropriate" adjustment" of the ATw and Krr values. This comparison of the two sets of curves demonstrated that the spreadsheet results are consistent and accurate.
P-T CURVES FOR 12 EFPY The P-T curve EXCEL spreadsheet was next used to generate the 12 EFPY P-T cunes. 'The l
. limiting ART value used comes from Table 1 for 12 EFPY, and is 72.3*F. This value was entered into the spreadsheet to generate the 12 EFPY P-T cunes. The results are shown in Table 2 and Figure 1. Also contained within this table and figure are the current 8 EFPY Tech. Spec. curves
[2,5] for comparative purposes.
SUMMARY
AND CONCLUSIONS l
The analysis documented in this report develops RTm7 estimates and P-T curves for the RBS reactor pressure vessel. EXCEL spreadsheets were developed for each of these items.
1 l
Table i provides the results of the RTmT estimations. Those results are identical to estimates previously developed in the Reference 4 report, thus confirming the past results and the spreadsheet used for the current analysis.
The P-T cune spreadsheet developed for RBS was benchmarked against the results previously developed in Reference 4. Comparison of the calculated results for 8 EFPY to those contained in the current Tech. Spec. P-T curves for 8 EFPY [2,5] demonstrate the validity of the spreadsheet, as the two sets of results were identical. -
Finally, Table 2 and Figure 1 provide the results of the P-T curve spreadsheet for 12 EFPY. The l
results are seen to be reasonable based on the " shift" in results from those at 8 EFPY. This, coupled with the results of the " benchmark" test case, conclude the Figure 1 P-T limits to be appropriate for RBS for 12 EFPY of operation.
i It should be noted that the 12 EFPY P-T cune is also applicable for power uprate conditions.
Actually, the implementation of power uprate has no effect on the development of the P-T curves, other than in determining the length of time the curves are applicable for (i.e., implementation of l
power uprate may cause 12 EFPY to be achieved sooner than if power uprate were not implemented). In calculating the full power operating time after power uprate implementation, it I
is important that the EFPY value be determined using methodology which is consistent with that f
used to estimate fluence. Otherwise, developed P-T limits will not be reflective of the assumed Suence level. Based on this, both the fluence estimate and the EFPY value should be based on the 100% core thermal power value of 2894 MWt.
Structural Integrity Associates, Inc.
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SPREADSHEET LIMITATIONS J
It should be noted that although the spreadsheet tool for generating P-T curves has been j
validated, each future use of this spreadsheet should be validated on a case-by-case basis. All possible temperature limitation requirements were not placed into the spreadsheet for " automatic" j
imphmentation. For example, the minimum temperature described above for Curve C that
]
requires the minimum Curve C temperature to be equal to the temperature of Curve A at 1,100 i
psig was not necessary for this analysis (i.e., Curve A @ 1,100 psig = 168'F whereas C'urve A
{
plus 40*F at pressuresjust above 312.5 psig = 170*F which is more limiting). At some point in the near future (i.e., beyond 12 EFPY), this requirement will be necessary (it was implemented in the 32 EFPY curves in Reference 4). Therefore, modifications of the spreadsheet to account for j
this and other requirements may have to be made as a part of future use of the spreadsheet.
i OTHER OBSERVATIONS A few observations were made during the course of performing this work that may be worthy of.
{.
consideration by Entergy in future P-T curve work. These items are as follows:
i Se Kg and AT,,a values usedare slightly conservative. Based on observations I
made during this effort for RBS, as well as other evaluations done for other BWRs I
by SI, the values for Kg and ATw that had to be used to match the previously developed P-T curves for 8 EFPY are slightly conservative. Less conservative i
values could be technicallyjustified, thereby improving P-T limits. Although the
{
magnitude of this improvement is not precisely known, it is estimated to be on the orde of a few degrees in temperature. This may be of benefit for RBS operation in the future when shifts in material properties become more significant and the P-4 l
T operating window shrinks.
j De vessel dscontinuity limitsportion of the P-Tcurves may be conservative.
l Typically, GE uses stresses available from Design Stress Reports or computes stresses using conservative stress concentration factors for geometric i
l discontinuities for application to vessel discontinuity regions (i.e., nozzles, i
penetrations, flanges, etc.). Based on analysis SI has performed for other BWRs l
using more re6ned plant-specific stress analysis, these assumptions can lead to overly conservative P-T limits. This would only be applicable for the lower curved i
portions of Curves B and C (i.e., between 70'F and 100*F for Curve B, and between 70*F and 140*F for Curve C) since the other discontinuity limit portions j
of these curves are set by the requirements of Reference 7. If these limits are too l
restrictive for RBS operation, further evaluation may provide relief. This issue
]
affects regions of the P-T curve that are not typically a problem for BWR operation; thus, it is mentioned for future reference purposes only.
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( SfructuralIntegrity Associates, Inc.
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Page 8 October 22,1996 Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. O We would like to thank you for the opportunity to complete this work for Entergy, and hope you find it to your satisfaction. Ifyou have questions, please contact me.
Prepared by:
b I-L MN%
Verified by:
Gary f. Stevens, P. E.
H. L. Gusti(P. E. -
is attachments i
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f StructuralIntegrityAssociates,Inc.
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l Page 9 October 22,1996 Mr. Erwin J. Zoch GLS-96-059/ SIR-96-096, Rev. O l
j REFERENCES 1.
Entergy Contract No. NRSM1469 dated 9/26/96.
2.
RBS Technical Speci6 cations, Amendment No. 81, Figure 3.4.11-1," Minimum l
Temperature Required vs. RCS Pressure," SI File No. RBS-03Q-202.
3.
USNRC Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactot Vessel Materials," U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, (Task ME 305-4), May 1988.
4.
GE Report No. SASR 89-20, Revision 1, " Implementation of Regulatory Guide 1.99 Revision 2 for River Bend Station Unit 1," March 1990, (LAR90-02, SCRB-14842 dated l
3/20/90), SI File No. RBS-03Q-203.
'5.
Letter No. G-LD-2-085 from W. D. Arndt (GE) to Mr. J. C. Deddens (GSU), " Tabulated Values from 8 EFPY Curves River Bend Station," May 26,1992, (EOI File
- 3221.110-000-004A), SI File No. RBS-03Q-201.
6.
ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components, Nonmandatory Appendix G, " Fracture Toughness Criteria for Protection Against Failure," 1992 Edition.
l 7.
U. S. Code of Federal Regulations, Chapter 10, Part 50, Appendix G, " Fracture Toughness Requirements," l-1-% Edition.
l i
( structuralIntegrity Associates, Inc.
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Table 1 e
RT Estimates for RBS for 12 EFPY NDT h
(Data Source Appen&r A of SASR 89-20. Rev.1. ~8mplemenlahon of Regulatory Guide 1.99 Rewsion 2 Sar Rwer Berni Stahon thut 1.~ hearch 1990p 1
g RPV thickness =
5 41 enches Reference Fluence =
6 600E+18 necm' at 32 Reference EFPY (nonunal peak value at RPV ID)
Deswed EFPY lor RT er Pressw*nn =
12.0 EFPY i
Estimated Fluence * =
2.475E+18 n/cm'(nonunal peak value at RPVID)
L Attenuated Fluence at 1MT * =
1.789E+18 nicm' i
~
Fluence Factor * =
0.5431 h
^
,, f.
Chemistry "i -
._ For1M T o
Port flame &
- j. Nest..,
.Lat InIgelRTuer FacterM ARTeer IAerg in ARTm j
m
^^
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" see.'
- "m cu(es%)
en(at %)
m m
m
e, m m
i esenereas so pse.'
[
Vessel Place 22-1-3 C3138-2 9
0.08
_ 0 63_
51 27.7 13.8 0.0 64.4 Vessel Piste 22-1-1 C3054-1
-20 0 09 0 70 58 31.5 15.7 0.0_ _
43 0 VesselPloes 22-1-2 C3054-2 2
0.00 0.70 58 31.5 15.7 00 65 0 VesselWald BE BF. BG 492L4871 A421827AE
-60 0.04 0.95 54 29.3 14.7 0.0_
-1.3 i
1 O
Vessel Wold
_BE, BF, BG 492L4871 A421827AF
-50 0.03 0.98 _
41 22.3
___11.1 00
-5.5 VeseelWold BE, BF. BG EP6756 0342 (Tandem [
-50 0.00 0.92 122 68.3 28.0 0.0 72.3 _
t VesselWold BE, BF, BG 5P6756 0342 (Smgle)
-60 0.00 0.93 122 66.3 28 0 00 62.3 Limleing geIINne ART =
72.3 Notes:
1.
Esemated Fluence = (Reference Fluence) * (Desired EFPY)f(Reference EFPY).
l
- 2. Altonusted Fluence = (Estunated Fluence) e * ** where x = IMT distanca per Secton 1.1 of RG 1.99.
3.
Fluence fedor = f "'"*
- where f = (Allenueled Fluence at 1MT)A(1x10") per Secton 1.1 of RG 1.99.
4.
Obteened from RG 1.99, Table 1 (Welds) and Table 2 (Base Metal) 5.
ART,, = (Chemestry Factor)*(Fluence Factor)' er Sechon 1.1 of RG 1.99.
j p
- 6. o = 17*F for base metal and 28*F for welds, except that a. need not exceed 0.50* ART,.y per Sechon 1.1 of RG 1.99.
- 7. Adjusted Reference Temperature (ART) = Initial RTwo, + ART,e1 + 2*(o ' + s,#)"' per Sechon 1.1 of RG 1.99.
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Table 2 (continued)
P-T Calculation Results for 12 EFPY O
ess I
tename sameCampenseea vasessemuseorgFeegetspee,Tenemme e
Y EFPv =
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1 SOO A A'S C
1.400 s.
e, se en e,
e', l*
l*
1.200
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es as ll l l
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$ 1.000
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.' l N.B', C'=
CORE BELTLINE AFTER
, '/
.E
=#
- e AN ASSUMED 122.3*F j
, ', ',' a SHIFT FROM AN INITIAL
,e WELD RTc OF.50*F.
.o ta 600 A=
SYSTEM HYDROTEST LIMIT WITH e
8/
'/
FUEL IN VESSEL E
/
/
8=
NON-NUCLEAR HEATING LIMIT.
C=
NUCLEAR (CORE CRITICAL) LIMIT.
l 400 VESSEL DISCONTINUITY l
LIMITS I
312.5 PSIG CORE BELTLINE LIMITS
***
A WITH 122.3*F SHIFT B
200 7
I CURVES A', B', AND C' ARE VALID FOR BOLTuP C
12 EFpy OF OPERATION.
70*F CURVES A. 8, AND C ARE VALIO FOR 8 EFPY OF OPERATION.
0 0
100 200 300 400 500 600 Minimum Reactor Vessel Metal Temperature (*F)
Figure 1. P-T Curves for 12 EFPY l
GLS-96-059/ SIR-96-096, Rev. 0 15
.