ML20117E733

Pressure-Temp Curves Per RG 1.99,Rev 2 for Oncpp

ML20117E733
Person / Time
Site:	Oyster Creek
Issue date:	07/31/1996
From:	Branlund B, Chu C, Salinas J GENERAL ELECTRIC CO.
To:
Shared Package
ML20117E700	List: ML20117E695 ML20117E706 ML20117E733
References
RTR-REGGD-01.099, RTR-REGGD-1.099 GENE-B13-01769, GENE-B13-1769, NUDOCS 9609030054
Download: ML20117E733 (74)

Text

!

(G3 ,,

GE Nucisar Enargy l GENE-B13-01769 l

July 1995 1 1 i l 1

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1 PRESSURE-TEMPERATURE CURVES PER

! REGULATORY GUIDE 1.99, REVISION 2 '

FORTHE OYSTER CREEK NUCLEAR GENERATING STATION  :

Prepared by: 2m ,

. A. S  ;

VIntegrity Project

.&\ lr-

.. . a -

uk B.J.B und, Senior Engineer RPVIntegrity Project VeriSed by: -_

C. L. Chu, Senior Engineer Materials Monitoring &

StrWul Anal sis Services Prepared by: b

. . um., - u. Mr Engineering & Licensing Consulting Services 9609030054 960823 PDR ADOCK 05000219 p PDR

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l IMPORTANT NOTICE REGARDING l l l

CONTENTS OF THIS REPORT l 4 )

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• PLEASE READ CAREFULLY ,

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I 1 1 This report was prepared by the General Electric Company. The information contained in j this report is believed by General Electric to be an accurate and true representation of the facts l known, obtained or provided to General Electric at the time this report was prepared.

{ The only undenakings of the General Electric Company respecting information in this j document are contained in the contract between the customer and the General Electric Company,

{ as identi6ed in the purchase order for this report, and nothing contained in this document shall be constmed as changing said contract. The use of this information except as defined by said 4

contract, or for any purpose other than that for which it is intended, is not authorized; and with f respect to any such unauthorized use, neither General Electric Company nor any of the contributors to this document makes any representation or warranty (express or implied) as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.

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TABLE OF CONTENTS i 1

PASC

1.0 INTRODUCTION

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2.0 INITIAL REFERENCE TEMPERATURES 2-1 3.0 ADJUSTED REFERENCE TEMPERATURES FOR BELTLINE 3-1 3.1 Rev 2 Methods 31 3.2 Limiting Beltline Material 3-1 3.2.1 Chemistry 3-2 3.2.2 Fluence 3-2 3.3 ART vs EFPY 3-3 4.0 PRESSURE-TEMPERATURE CURVES 4-1 4.1 Background 4-1 4.2 Non-Beltline Regions 4-1 4.2.1 Non-Beltline Monitoring During Pressure Tests 4-3

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4.3 Core Beltline Region 4-4 l 4.4 Closure Flange Region 4-4 4.5 Core Critical Operation Requirements of 10CFR50 Appendix G 4-6

5.0 REFERENCES

5-1 l l

APPENDICES l A CHARPY CURVES OF SELECTED VESSEL PLATES A-1 1 l

B BELTLINE P-T CURVE CALCULATION METHOD B-1 i

C IMPACT ON P-T CURVES OF HEATUP/COOLDOWN RATE C-1 iii

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1.0 INTRODUCTION

The pressure-temperature (P-T) curves in the Technical Specifications are established to the requirements of 10CFR50, Appendix G [1] to assure that brittle fracture of the reactor vessel is prevented. Part of the analysis involved in developing the P-T curves is to account for irradiation embrittlement effects in the core region, or beltline. The method used to account for irradiation embrittlement is described in Regulatory Guide 1.99, Revision 2 [2], or Rev 2. ,

In addition to beltline considerations, there are non-beltline discontinuity limits as nozzles,-

penetrations and flanges which affect the P-T curves. The non-beltline limits are based on generic analyses which are adjusted to the maximum reference temperature (RTwor) for the applicable Oyster Creek vessel components. The non-beltline limits are also governed by requirements in

[1], based on the closure flange region RTwor.

This report presents P-T curves incorporating irradiation effects for the beltline per Rev 2 and appropriate non-beltline limits. The curves have been developed to present steam dome pressure versus minimum vessel metal temperature. In addition, a refinement has been made l which may minimize heating requirements prior to pressure testing, specifically:

A curve has been included to allow monitoring of the non-beltline regions of the vessel, such as the bottom head, separate from the beltline.

l The report contains a description of the methods used to calculate P-T limits and has example calculations for the vessel beltline for pressure testing and heatup/cooldown conditions.

Temperature monitoring requirements and methods are available in GE Services Information Letter (SIL) 430. The specific issue of maintaining a heatup or cooldown rate of 100*F/hr, as it relates to the P-T curves, is discussed in this report.

This report is a revision to SASR 90-89, DRF 137-0010 of November 1990 and was updated to include 22,27, and 48 EFPY for the ART, P-T curves, and ART vs. EFPY curve. In 1-1 L-._ - - -_ , --

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addition, the 17 and 32 EFPY P-T curves were revised to include the changes in the ASME Code as described in Section 4.1. Changes in the report are marked with margin bars.

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I 1-2 i

2.0 INITIAL REFERENCE TEMPERATURES In order to perform a complete analysis of the vessel P-T requirements, initial RTwyr values are needed for alllow alloy steel vessel components. The requirements for establishing the vessel component tougimess per the AShE Code prior to 1972 are summarized as follows:

a. Test specimens shall be longitudinally oriented Charpy V-Notch specimens.

b. At the qualification test temperature (specified in vessel purchase specification), no impact test result shall be less than 25 ft-lb, and the average of three test results shall be at least 30 ft-lb.

c. Pressure tests shall be conducted at a temperature at least 60 F above the qualification test temperature for the vessel materials.

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l The current requirements establish a RTmyrv alue, and are significantly different. For plants  !

constructed to the ASME Code after Summer 1972, the requirements are as follows:

a. Charpy V-Notch specimens shall be oriented normal to the rolling direction (transverse).

b. RTmr is defined as the higher of the dropweight NDT or 60 F below the temperature at which Charpy V-Notch 50 ft-lb energy and 35 mils lateral expansion are met.

c. Bolt-up in preparation for a pressure test or normal operation shall be performed at or above the RTmyror lowest service temperature (LST), whichever is greater.

I 10CFR50 Appendix G states that for vessels constructed to a version of the AShE Code prior to the Summer 1972 Addendum, fracture toughness data and data analyses must be supplemented in an approved manner. GE has developed methods for analytically converting fracture toughness data for vessels constructed before 1972 to comply with current requirements.

2-1

GE developed these methods from data in WRC Bulletin 217 [3] and from data collected to respond to NRC questions on FSAR submittals in the late 1970s. In 1994, these methods of estimating RTer were submitted for generic approval by the BWR Owners' Group [10), and approved by the NRC for generic use [11]. The data used in developing the GE methods cover A533 plate material and submerged arc and shielded metal arc welds. Since the Oyster Creek vessel plates are 302B material, some supplemental evaluation of RTer has been done in this report on some.of the vessel plates. These methods and example RTer calculations for vessel plate, weld, weld HAZ, forging, and bolting material are summarized in the remainder of this section. Calculated RTer values for selected RPV locations are given in Table 2-1.

For vessel plate material, the first step in calculating RTmr is to establish the 50 ft-lb transverse test temperature from longitudinal test specimen data. There are typically three energy values at a given test temperature. The lowest energy Charpy value is adjusted by adding 2*F per ft-lb energy to 50 ft-lb. For example, for plate G-309-2 in the closure head, the test temperature and lowest Charpy energy from Table 2-1 is 28.5 ft-lb at +10*F. The equivalent 50 ft-lb longitudinal test temperature is:

T3ot, = 10 F + [(50 - 28.5) ft-lb

• 2*F/ft-lb] = 53*F The transition from longitudinal data to transverse data is made by adding 30 F to the test temperature. In this case, the 50 ft-lb transverse Charpy test temperature is Tsor = 83*F. The Rfer is the greater of NDT or (T or3 - 60 F). The value based on Charpy data, (T3or - 60 F), is 23 F. For Oyster Creek materials, dropweight testing to establish NDT was not performed, but NRC Branch Technical Position MTEB 5-2 [4] recommends that NDT be estimated as the 30 ft-Ib Charpy test temperature, which in this case is 10 F. Thus, the RTmr for plate G-309-2 is 231. Note that the conservative nature of estimating Tsor will always result in the estimated (Tsoi - 60 F) value being higher than the estimated NDT.

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Some of the 302B plate materials used in the Oyster Creek vessel exhibit a rather low upper shelf energy (USE). Fortunately, there are full Charpy curves for these materials. In examining l the Charpy curves, it was found that the 2 F per fi-lb correction was not conservative for the materials with lower USE values. In these cases, the Charpy data were fit with a hyperbolic tangent relationship to determine the best-estimate T3ot. The standard deviation of the data relative to the curve-fit (by temperature) was calculated to serve as at for the beltline materials.

For non-beltline materials, the value of T3at used to determine RTer was the best-estimate value plus twice the standard deviation. Plots of the Charpy curves for all of the beltline plates and for the most limiting non-beltline plates with low USE are provided in Appendix A. The RTer

( values in Table 2-1 for these plates are based on the Appendix A curves.

For vessel weld material, the Charpy V-Notch results are usually more limiting than dropweight results in establishing RTer. The 50 ft-lb test temperature is established as for the l plate material, but the 30 F adjustment to convert longitudinal data to transverse data is not l applicable to weld metal. For example, weld heat 86054B with flux lot 4D4F has a lowest Charpy l energy of 29 fi-lb at 10 F. The 2"F per ft-lb adjustment gives a Tsor value of 52*F. The GE l procedure requires that, when no NDT is available, the resulting RTer be -50 F or higher. In j this example, (Tsor - 60 F) is -8*F, so the RTer is -8 F. Since the method of estimating RTer operates on the lowest Charpy energy value, and provides a conservative adjustment to the 50 ft-lb level, the value of ci is taken to be 0 F.

l For the vessel weld HAZ material, the RTer is assumed to be the same as for the base r

material since ASME Code weld procedure qualification test requirements and post-weld heat treat data indicate this assumption is valid.  !

1 For vessel forging material, such as nozzles and closure flanges the method for establishing l RTer is the same as for vessel plate material. For the CRD return nozzle G-319, the lowest l Charpy data at 40 F is 25 fi-lb. In this case, (T3or - 60 F) is [40 + (50-25)*2 + 30 - 60], or l 1

60 F. i l

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l For bolting material, the current ASME Code requirements denne the LST as the l temperature at which transverse Charpy V-Notch energy of 45 ft-lb and 25 mils lateral expansion (MLE) are achieved. If the required Charpy results are not met, or are not reported, but the i l

Charpy V-Notch energy reported is above 30 ft-lb, the requirements of the ASME Code at l

construction are applied, namely that the 30 ft-lb test temperature plus 60 F is the LST for the bolting materials. Charpy data for the studs did not meet the 45 ft-lb, 25 MLE requirement, but j j 30 ft-lb energies were met at 10 F. Therefore, the bolting material LST is 70 F l

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Table 2-1 INITIAL RTwr VALUES OF BELTLINE AND OTHER SELECTED RPV MATERIALS Test Charpy Ident. Heat Temp. Energy Twr-60 o, RTwr Location Number Number (*F) (ft-lb) (*F) ('F) ('F)

Bcitime Lower Shell Plates G-3071 T1937-2 see App. A 30 12.6 (a)

G-308-1 T1937-1 see App. A 21 14.2 (a)

G-307-5 P2076-2 see App. A 3 13.9 (a)

Lower Intermediate G-8-7 P2161-1 see App. A 17 10.7 (a)

Shell Plates G-8-8 P2136-2 see App. A 8 12.8 (a)

G-8-6 P2150-1 see App. A 31 12.7 (a)

Lower Long. 2-564 86054B 10 64,65,66 -50 0.0 -50 Welds A,B,C Lot 4ESF Lower-Int. Long. 2-564 86054B 10 29,31.5,32 -8 0.0 -8 Welds D,E,F Lot 4D4F Lower to Lower-Int. 3-564 1248 10 53.5,57.65 -50 0.0 -50 Girth Weld Lot 4M2F Non-Beltline:

Upper Shell Plate G-307-R1 P2112-2 see App. A 25 5.3 36(b)

Vessel Flange G-306 X-43162 10 92,143,153 -20 0.0 -20 Head Flange G-305 X-43162 10 212,261,261 -20 0.0 -20 Top Head Torus G-309-2 P2074-1 10 28.5,35,39.5 23 0.0 23 Bottom Head Torus G-301-4 A7153-2 see App. A 45 10.3 66(b)

CRD Return Nozzle G-319 BT-1676 40 25,34,38 60 0.0 60 Recire Inlet Forg. G-312-1 D-4936-2 10 28.5,30.5,31 23 0.0 23 (a) The values of(T5ar - 60) and or are used in Section 3 according to the methods in Rev 2.

(b) v The RTmr alues for these non-beltline materials are the (Tser - 60) plus 201 /

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3.0 ADJUSTED REFERENCE TEMPERATURES FOR BELTLINE The adjusted reference temperature (ART) of the limiting beltline material is used to correct the beltline P-T curves to account for irradiation effects. Rev 2 provides the methods for determining the ART. These methods, and the limiting material properties used, are discussed in this section.

3.1 REV 2 METHODS The value of ART is computed by adding the SHIFT term for a given value of effective full power years (EFPY) to the initial RTmr. For Rev 2, the SHIFT equation consists of two terms:

SHIFT = A RTer + Margin where A RTer = [CF]*f+2 -uoioso Margin = 2(c12 + 042 )u f = fluence for the given EFPY /10" Chemistry factors (CF) are tabulated for welds and plates in Tables 1 and 2, respectively, of Rev 2. The margin term c4 has set values in Rev 2 of 17'F for plate and 28'F for weld.

However, c3 need not be greater than 0.5*A RTer. Uncertainty on initial RTmr, or, is discussed in Section 2.0.

3.2 LIMITING BELTLINE MATERIAL An evaluation of all beltline plates and submerged arc welds was made, and is summarized in Tables 3-1 thru 3-5. The inputs used in determinmg the limiting beltline material are discussed in the remainder of this section.

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3.2.1 Chemistry l

The vessel material certification records provided much of the detail of the beltline material chemistries. However, critical information on copper and, in some cases nickel, were not provided with the material certificates. GPUN established values for the missing data in Technical Data Report (TDR) 725 [5]. The data from the material records and from TDR 725 are presented in Table 3-6. The copper and nickel values shown there were used in the Rev 2 calculations.

3.2.2 Fluence The Oyster Creek surveillance test report [6] presents a calculated value of 32 EFPY fluence at the inside vessel surface. GPUN made an adjustment to the value in [6] to reflect some new information on power history, resulting in a 32 EFPY fluence of 3.74x10 n/cm' reported in TDR 725. GE has just completed an evaluation of lead factor (fluence ratio between the surveillance capsule and the vessel peak) and has computed values very close to those in [6].

Therefore, the fluence value in TDR 725 is used in the Rev 2 calculations.

Rev 2 provides a method of calculating the vessel 1/4 T fluence based on the fluence at the vessel inside surface, fa However, Rev 2 also allows for the use of displacement per atom (dpa) analysis to determine the attenuation to the 1/4 T location. A dpa analysis was performed in [6],

i resulting in an attenuation relationship as follows:

i fiar = 0.63

• fa The resulting 1/4 T fluence is:

2 fiu r = 2.36x10 n/cm .

This 1/4 T fluence is about 3% less than the value calculated with the attenuation relationship in i Rev2.

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3.3 ART VS EFPY Combining the inputs ofinitial RTer, chemistry and fluence, Rev 2 is used to compute ART as a function ofEFPY. Table 3-1 shows ART values for 17 EFPY of operation. Tables 3-2, 3-3,3-4, and 3-5 show ART for 22,27,32, and 48 EFPY of operation, respectively. In all cases, plate G-8-6 has the highest ART, due to the fact that it also has the highest initial RTmr.

The limiting submerged arc weld has a higher SHIFT value, but a lower initial RTer such that the ART is less than that of the plate. Therefore, plate G-8-6 is the limiting material throughout the operating period of 32 EFPY. ART is plotted versus EFPY in Figure 3-1. The ART values at 17, 22, 27, 32, and 48 EFPY are used in the P-T curve development in Section 4.

3-3

Table 3-1 BELTLINE EVALUATION FOR OYSTER CREEK AT 17 EFPY OF OPERATION i

SheH Thickness = 7.125 inches Peak 1.D. fluence = 1.99E+18 Peak 1/4 fluence = 1.25E+18 Initial 17 EFPY 17 EFPY 17 EFPY COMPONENT & HEAT OR HEAT / LOT %Cu %Ni CF RTndt Siama-l Delta RTndt Marain _ Shift ART PLATES:

Lower Shell G-307-1 T-1937-2 0.17 0.11 79.5 30 12.6 36.8 42.3 792 1092 Lower Shen G-308-1 T-1937-1 0.17 0.11 79.5 21 14.2 36.8 44.3 81.1 102.1 Lower Shen G-307-5 P-2076-2 0.27 0.53 173.9 3 13.9 80.6 43.9 124.5 127.5

{ Low-int Shen G-8-7 P-2161-1 021 0.48 139.4 17 10.7 64.6 402 104.8 121.8 Low-int Shen G-8-8 P-2136-2 0.18 0.46 120.7 8 12.8 55.9 42.6 98.5 106.5 Low-int Shen G-8-6 P-2150-1 02 0.51 1382 31 12.7 64.0 42.4 106.5 137.5 WELDS:

Lower Long. 2-564 860548, ARCOS 0.35 0.2 168 -50 0 77.8 56.0 133.8 83.8 A,B,C FLUX LOT 4E5F Low-int Long. 2-564 860548, ARCOS 0.35 02 168 -8 0 77.8 56.0 133.8 125.8 D,E,F FLUX LOT 4D4F Lower to 3-564 1248, ARCOS 022 0.11 105.3 -50 0 48.8 48.8 97.6 47.6 Low-int Grith FLUX LOT 4M2F

l Table 3-2 BELTLINE EVALUATION FOR OYSTER CREEK .

AT 22 EFPY OF OPERATION

l Shell  !

TNckness= 7.125 inches Peak I.D. fluence = 2.57E+18  !

Peak 1/4 fluence = 1.62E+18  !

Initial 22 EFPY 22 EFPY 22 EFPY  ;

COMPONENT LQ, HEAT OR HEAT / LOT YQ Mtg CF RTndt Seama-1 Delta RTndt Marain SNft ART l PLATES:

I Lower Shell G-307-1 T-1937-2 0.17 0.11 79.5 30 12.6 41.4 42.3 83.7 113.7 Lower Shell G-308-1 T-1937-1 0.17 0.11 79.5 21 14.2 41.4 44.3 85.7 106.7 Lower Shell G-307-5 P-2076-2 0.27 0.53 173.9 3 13.9 90.5 43.9 134.4 137.4 ta Low-int Shell G-8-7 P-2161-1 021 0.48 -139.4 17 10.7 72.5. 40 2 112.7 129.7 0 Low-int Shell G-8-8 P-2136-2 0.18 0.46 120.7 8 12.8 62.8 42.6 105.3 113.3  ;

Low-int Shell G-8-6 P-2150-1 0.2 0.51 1382 31 12.7 71.9 42.4 114.3 145.3  :

WELDS:

Lower Long. 2-564 86054B, ARCOS 0.35 0.2 168 -50 0 87.4 56.0 143.4 93.4 A,B,C FLUX LOT 4ESF Low-int Long. 2-564 860548, ARCOS 0.35 02 168 -8 0 87.4 56.0 143.4 135.4 D,E,F FLUX LOT 4D4F Lower to 3-564 1248, ARCOS 022 0.11 105.3 -50 0 54.8 54.8 109.6 59.6 Low-int Grith FLUX LOT 4M2F

Table 3-3 BELTLINE EVALUATION FOR OYSTER CREEK AT 27 EFPY OF OPERATION Sher Thickness = 7.125 inches Peak LD. fluence = 3.16E+18 Peak 1/4 fluence = 1.99E+18 Initial 27 EFPY 27 EFPY 27 EFPY COMPONENT llL HEAT OR HEAT / LOT %Cu %Ni CF RTndt Siama-1 Delta RTndt Marain SNft ART PLATES:

Lower Shel G-307-1 T-1937-2 0.17 0.11 79.5 30 12.6 45.2 42.3 87.5 117.5 Lower Sher G-308-1 T-1937-1 0.17 0.11 79.5 21 14 2 45.2 44.3 89.5 110.5 Lower Sher G-307-5 P-2076-2 027 0.53 173.9 3 13.9 98.8 43.9 142.7 145.7 w Low-int Shen G-8-7 P-2161-1 0.21 0.48 139.4 17 10.7 79.2 40.2 119.4 136.4 E Low-intShen G-84 P-2136-2 0.18 0.46 120.7 8 12.8 68.6 42.6 111.1 119.1 Low-int Shel G-8-6 P-2150-1 0.2 0.51 138.2 31 12.7 78.5 42.4 120.9 151.9 WELDS:

Lower Long. 2-564 86054B, ARCOS 0.35 0.2 168 -50 0 95.4 56.0 151.4 101.4 A,B,C FLUX LOT 4E5F Low-int Long. 2-564 860548, ARCOS 0.35 0.2 168 -8 0 95.4 56.0 151.4 143.4 D,E,F FLUX LOT 4D4F Lower to 3-564 1248, ARCOS 0.22 0.11 105.3 -50 0 59.8 56.0 115.8 65.8 Low-int Grith FLUX LOT 4M2F

Table 3-4 BELTLINE EVALUATION FOR OYSTER CREEK AT 32 EFPY OF OPERATION Sher TNckness= 7.125 inches Peak LD. fluence = 3.74E+18 Peak 1/4 fluence = 2.36E+18 Initial 32 EFPY 32 EFPY 32 EFPY COMPONENT 1,Q, HEAT OR HEAT / LOT SQ_u %Ni CF RTndt Siama-l Delta RTndt Maren Shift ART PLATES:

Lower Sher G-307-1 T-1937-2 0.17 0.11 79.5 30 12.6 48.4 42.3 90.8 120.8 Lower Shel G-308-1 T-1937-1 0.17 0.11 79.5 21 14.2 48.4 44.3 92.7 113.7 Lower Shel G-307-5 P-2076-2 0.27 0.53 173.9 3 13.9 106.0 43.9 149.9 152.9 w Low-int Sher G-8-7 P-2161-1 0.21 0.48 139.4 17 10.7 84.9 40.2 125.1 142.1 O Low-int Sher G-8-8 P-2136-2 0.18 0.46 120.7 8 12.8 73.5 42.6 116.1 124.1 Low-int Sher G-8-6 P-2150-1 0.2 0.51 138.2 31 12.7 84 2 42.4 126.6 157.6 WELDS:

Lower Long. 2-564 86054B, ARCOS 0.35 02 168 -50 0 102.4 56.0 158.4 108.4 A,B,C FLUX LOT 4ESF Low-int Long. 2-564 860548, ARCOS 0.35 0.2 168 -8 0 102.4 56.0 158.4 150.4 D,E,F FLUX LOT 4D4F Lower to 3-564 1248, ARCOS 0.22 0.11 105.3 -50 0 64.2 56.0 120.2 70.2 Low-int Grith FLUX LOT 4M2F

Table 3-5 BELTLINE EVALUATION FOR OYSTER CREEK AT 48 EFPY OF OPERATION Sher Thickness = 7.125 inches Peak I.D. fluence = 5.61 E+18 Peak 1/4 fluence = 3.53E+18 Initial 48 EFPY 48 EFPY 48 EFPY COMPONENT 1A HEAT OR HEAT / LOT %Cu %ti GE. RTndt Siama-I Delta RTndt Marain SNft ART PLATES:

Lower Sher G-307-1 T-1937-2 0.17 0.11 79.5 30 12.6 56.7 42.3 99.0 129.0 Lower Sher G-308-1 T-1937-1 0.17 0.11 79.5 21 14.2 56.7 44.3 101.0 122.0 Lower Sher G-307-5 P-2076-2 0.27 0.53 173.9 3 13.9 124.0 43.9 167.9 170.9 y Low-int Shes G-8-7 P-2161-1 0.21 0.48 139.4 17 10.7 99.4 40.2 139.6 156.6 00 Low-int Sher G-8-8 P-2136-2 0.18 0.46 120.7 8 12.8 86.1 42.6 128.6 136.6 Low-int Shes G-8-6 P-2150-1 0.2 0.51 138.2 31 12.7 98.5 42.4 141.0 172.0 WELDS:

Lower Long. 2-564 860548, ARCOS 0.35 0.2 168 -50 0 119.8 56.0 175.8 125.8 A,B,C FLUX LOT 4E5F Low-int Long. 2-564 860548, ARCOS 0.35 0.2 168 -8 0 119.8 56.0 175.8 167.8 D,E,F FLUX LOT 4D4F Lower to 3-564 1248, ARCOS 0.22 0.11 105.3 -50 0 75.1 56.0 131.1 81.1 Low-int Grith FLUX LOT 4M2F h

Table 3-6 CHEMICAL COMPOSITION OF RPV BELTLINE MATERIALS Composition by Weight Percent Identification Heat / Lot No. C Mn P S Si Ni Mo Cu Lower Shell Plates:

G-307-1 T1937-2 0.2 1.4 0.011 0.022 0.24 0. I 1

• 0.51 0.17

• G-308-1 T1937-1 0.2 1.4 0.011 0.022 0.24 0. I 1 ' O.51 0.17

• G-307-5 P2076-2 0.2 1.28 0.019 0.030 0.21 0.53 0.52 0.27' Lower-Intermediate Shell Plates:

G-8-7 P2161-1 0.19 1.35 0.019 0.021 0.24 0.48 0.46 0.21' G-8-8 P2136-2 0.19 1.36 0.006 0.024 0.26 0.46 0.48 0.18' 5 G-8-6 P2150-1 0.2 1.25 0.013 0.026 0.23 0.51 0.46 0.20' Lower Shell Longitudinal Welds:

2-564 RACO#3,86054B 0.12 1.64 0.015 0.02 0.34 0.2 ' O.51 0.35' A,B,C ARCOS B-5 Lot 4E5F '

Lower-Intermediate Longitudinal Weld:

2-564 RACO#3,86054B 0.12 1.67 0.013 0.02 0.41 0.2 ' O.50 0.35' A,B,C ARCOS B-5 Lot 4D4F Lower to Lower-Intermediate Girth Weld:

3-564 RACO#3,1248 0.097 1.26 0.015 0.02 0.22 0.11* 0.57 0.22' ARCOS B-5 Lot 4M2F a Values reported in TDR 725.

180 PLATE G-8-6 l," - -

,s0 - -

p l~ /

c ,, /

=> ,,0 f g

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re" b /

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g 70 2- /e0 30 20 10 0

0 4 8 12 16 20 24 28 32 36 40 44 48 EFFECTIVE FULL POWER YEARS FIGURE 3-1. Limiting Beltline Material ART

4.0 PRESSURE-TEMPERATURE CURVES

4.1 BACKGROUND

Operating limits for pressure and temperature are required for three categories of operation:

(a) hydrostatic pressure tests and leak tests, referred to as Curve A; (b) non-nuclear heatup/cooldown and low-level physics tests, referred to as Curve B; and (c) core critical operation, referred to as Curve C. There are three vessel regions that affect the operating limits:

the closure flange region, the core beltline region, and the remainder of the vessel, or non-beltline regions. The closure flange region limits are controlling at lower pressures primarily because of 10CFR50 Appendix G [1] requirements. The non-beltline and beltline region operating limits are evaluated according to procedures in 10CFR50 Appendix G, Appendix G of the ASME Code [7]

and Welding Research Council (WRC) Bulletin 175 [8], with the beltline region minimum temperature limits adjusted to account for vessel irradiation.

Figures 4-1 and 4-4 have revised curves applicable, per Rev 2, for 17 and 32 EFPY of operation, respectively. Figures 4-2, 4-3, and 4-5 have curves applicable for 22, 27, and 48 EFPY, respectively. The requirements for each vessel region influencing the P-T curves are discussed below. Tables 4-1,4-2,4-3,44, and 4-5 have tabulations of the P-T values for Figures 4-1,4-2,4-3,4-4, and 4-5, respectively.

The P-T curve revisions include consideration of the change to the allowable fracture toughness equation in ASME Code Section XI, Appendix G, which occurred in 1992. The coefficient 1.233 in the Km/Kn equation in Figure G-2210-1, became 1.223. The revision adds about 1/2 F to the calculated temperature for a given pressure on the P-T curves (i.e., all curved portions of the P-T curves shift 1/2'F to the right).

4.2 NON-BELTLINE REGIONS Non-beltline regions are those locations that receive too little fluence to cause any RTer increase. Non-beltline components include the nozzles, the closure flanges, some shell plates, top 4-1

and bottom head plates and the control rod drive (CRD) penetrations. Detailed stress analyses, specifically for the purpose of fracture toughness analysis, of the non-beltline components were performed for the BWR/6. The analyses took into account all mechanical loadings and thermal transients anticipated. Transients considered included 100 F/hr startup and shutdown, SCRAM, loss of feedwater heaters or flow, loss of recirculation pump flow, and all transients involving emergency core cooling injections. Primary membrane and bending stresses and secondary membrane and bending stresses due to the most severe of these transients were used according to

[7] to develop plots of allowable pressure (P) versus temperature relative to the reference temperature (T - RTer). Plots were developed for the two most limiting BWR/6 regions; the feedwater nozzle and the CRD penetration regions. All other non-beltline regions are categorized under one of these two regions.

The BWR/6 results have been applied to earlier BWR non-beltline vessel components, based on the facts that earlier vessel component geometries are not significantly different from BWR/6 configurations and mechanical and thermal loadings are comparable.

The BWR/6 non-beltline region results we e applied to Oyster Creek by adding the highest Oyster Creek RTer values for the non-beltline discontinuities to the appropriate P versus (T - RTer) curves for the BWR/6 CRD penetration or hedwater nozzle. Table 2-1 shows the  ;

most limiting non-beltline RTer values for the non-beltline components. The CRD return nozzle RTmr of 60"F is used with the BWR/6 feedwater nozzle curve. The bottom head RTwr of 66 F is used with the CRD penetration curve.

There are two nozzles in the Oyster Creek vessel which are not found in later BWR vessels. l These are the recirculation inlet nozzle and the isolation condenser nozzle. These nozzles were -

reviewed to assure that the limits developed for BWR/6 would apply.  ;

The recirculation inlet nozzle is a 1.41 inch thick ring forging welded to the outside of the vessel at the inlet penetration. Since the forging is less than 2.5 inches thick, it is exempt from fracture toughness analysis per ASME Appendix G, paragraph G-2223(c), as long as the RTmr is l

1 4-2

at least 60 F below the lowest service temperature. Table 2-1 shows the RTwr for the forging, 23 F. This is more than 60 F below the lowest service temperature for this nozzle, based on a boltup temperature of 85 F, so adequate fracture toughness is assured.

The isolation condenser nozzle is approximately the same geometry as the feedwater nozzle.

The Oyster Creek stress report [9] states that the thermal stresses for the feedwater nozzle are more severe than those for the isolation condenser nozzle. Therefore, the BWR/6 feedwater nozzle limits, adjusted to the highest RTmrr for Oyster Creek nozzles, will provide conservative P-T limits for the isolation condenser nozzle.

4.2.1 Non-Beltline Monitoring During Pressure Tests While the beltline curves are limiting for pressure test conditions, the non-beltline limits can still be applied to the other regions of the vessel. It is likely that, during leak and hydrostatic pressure testing, the bottom head or top head temperature may be significantly cooler than the beltline. This condition can occur in the bottom head when the recirculation pumps are operating at low speed, or are off, and injection through the control rod drives is used to pressurize the vessel. It is also possible that heat losses from the top head could make it difficult to maintain the same temperatures as those in the beltline.

Monitoring the bottom head or top head separately from the beltline region may reduce the required pressure test temperature by 10'F to 20 F. Some hypothetical temperatures demonstrating the potential benefit of separate bottom head monitoring are shown in Figure 4-6.

The Technical Speci6 cations currently require that all vessel temperatures be above the limiting conditions on the P-T curve. That would mean that, for a leak test, the bottom head would have to be heated above 210'F at 22 EFPY, as shown in case (a) of Figure 4-6. The bottom head temperature reading would likely be the limiting reading on the vessel during the test. If, by using the bottom head curve, the required temperature for the bottom head were only 188'F, the limiting reading would probably be near the beltline, as shown in case (b), and the actual vessel temperatures could be lowered compared to case (a).

4-3

One condition on monitoring the bottom head or top head separately is that it must be demonstrated that the vessel beltline temperature can be accurately monitored during pressure testing. An experiment has been conducted at a BWR-4 which showed that thermocouples on the vessel near the feedwater nozzles, or temperature measurements of water in the recirculation loops provide good estimates of the beltline temperature during pressure testing. GPUN may need to confirm this before implementing separate monitoring of the bottom head or top head.

First, however, it should be determined whether there are signiScant temperature differences betv;een the beltline region and the bottom head or top head regions.

4.3 CORE BELTLINE REGION The pressure-temperature (P-T) limits for the beltline region are determined according to the methods in ASME Code Appendix G [7]. As the beltline fluence increases during operation, these curves shift by an amount discussed in Section 3. Typically, the beltline curves shift to become more limiting than the non-beltline curves at some point during operating life. For the Oyster Creek vessel, the non-beltline curves were limiting through about 7 EFPY, at which point the beltline curves became more limiting at typical operating pressures.

The stress intensity factors (Kr), calculated for the beltline region according to ASME Appendix G procedures, were based on a combination of pressure and thermal stresses for a 1/4 T flaw in a flat plate. The pressure stresses were calculated using thin-walled cylinder equations.

Thermal stresses were calculated assuming the through-wall temperature distribution of a flat plate subjected to a 100 F/hr thermal gradient. The ART values shown on Figure 3-1 were used to adjust the (T - RTun) values from Figure G-2210-1 of[7]. More details on the methods used in computing beltline curves are contained in Appendix B.

The beltline P-T curves are calculated assuming an instantaneous heatup/cooldown rate of 100 F/hr. It is permitted to exceed this rate in the Technical Specification, as long as a 100 F change in any one hour period is not exceeded (also note that exceeding the 100 F/hr rate should 4-4

not be normal practice). The impact on the P-T curves of heatup/cooldown rates in excess of 100 F/hris discussed in Appendix C.

4.4 CLOSURE FLANGE REGION 10CFR50 Appendix G sets several minimum requirements for pressure and temperature, in addition to those outlined in the ASME Code, based on the closure flange region RTwor. In some cases, the results of analysis for other regions exceed these requirements and they do not affect the shape of the P-T curves. However, some closure flange requirements do impact the curves.

In addition, General Electric has compared the current requirements and the original requirements in determining the minimum boltup temperature.

The current boltup temperature of 100 F is based on the assumption that materials were qualified to meet 30 ft-lb Charpy energy at 40*F, based on the vessel purchase specification. The original Code requirement was that boltup be done at qualiScation temperature (T3ot) plus 60*F.

Current Code requirements state, in Paragraph G-2222(c) of [7], that for application of full bolt preload and reactor pressure up to 20% of hydrostatic test pressure, the RPV metal temperature must be at RTmr or greater. The approach used for Oyster Creek is to determine the highest value of(T30t + 60) and the highest value of RTer and base the boltup temperature on the more conservative value.

Table 2-1 shows the RTer values for the closure flanges, the limiting closure head plate connected to the closure head flange and the limiting upper shell plate connected to the vessel flange. Connecting weld materials are not shown because they are less limiting than the plates.

Table 2-1 shows the highest RTmr for the closure region to be 36 F for upper shell plate G-307-R1. Figure 4-7 shows the Charpy curve for G-307-R1. The value of T3ot is shown as 14 F, with 2cr = 10.6'F, so that T3at can be conservatively estimated as 25 F, and (T3ot + 60) is 85 F. Selecting the boltup temperature to be 85'F provides 49 F margin on the current Code requirement based on RTer. This margin is appropriate, because boltup is one of the more limiting operating conditions (high stress r.nd low temperature) for brittle fracture.

4-5

l 1

• )

10CFR50 Appendix G, paragraph IV.A.2, sets minimum temperature requirements for pressure above 20% hydrotest pressure based on the RTer of the closure region. Curve A j

temperature must be no less than (RTer + 90 F) and Curve B temperature no less than l

(RTer + 120 F). The Curve A requirement causes a 41 F shift at 20% hydrotest pressure i (375 psig) as shown in Figures 4-1, 4-2, 4-3, 4-4, and 4-5. The Curve B requirement has i essentially no impact on the figures because the analytical results for the non-beltline regions require that temperature be greater than 10CFR50 Appendix G requirement of(RTer + 120 F) at 375 psig.

)

4.5 CORE CRITICAL OPERATION REQUIREMENTS OF 10CFR50, APPENDIX G l

l Curve C, the core critical operation curve .shown in Figures 4-1, 4-2, 4-3, 4-4, and 4-5, is l generated from the requirements of 10CFR50 Appendix G, paragraph IV.A.3. Essentially parkgraph IV.A.3 requires that core critical P-T limits 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 ofIV.A.3, or actually an allowance for the BWR, concerns minimum temperature for initial criticality in a startup. The BWR, given that water level is normal, is allowed initial criticality at the closure flange region (RTmr + 60 F) at pressures below 375 psig.

This requirement makes the minimum criticality temperature 96 F, based on the RTer of plate G-307-RI. Above 375 psig, the Curve C temperature must be at least that required for the hydrostatic pressure test (Curve A at 1100 psig). In Figures 4-1,4-2, and 4-3, the non-beltline curves are more limiting than this requirement at 375 psig, so there is no impact on the shape of the P-T curves. However, in Figures 4-4 and 4-5 there is a step at 375 psig in Curve C due to this requirement.

4-6

Table 4-1 P-T CURVE VALUES FOR 17 EFPY Limiting Non-Beltline Curve Cune Pressure Temocrature ('A Temo ('M (esid A B C A 0 85.0 85.0  %.0 85.0 10 85.0 85.0 96.0 85.0 20 85.0 85.0  %.0 85.0 30 85.0 85.0  %.0 85.0 40 85.0 85.0 100.6 85.0 50 85.0 85.0 113.6 85.0 60 85.0 85.0 124.6 85.0 70 85.0 94.1 134.1 85.0 80 85.0 102.3 142.3 85.0 90 85.0 109.3 149.3 85.0 100 35.0 115.4 155.4 85.0 110 85.0 121.0 161.0 85.0 120 85.0 125.9 165.9 85.0 130 85.0 130.7 170.7 85.0 140 85.0 135.3 175.3 85.0 150 85.0 139.6 179.6 85.0 160 85.0 143.5 183.5 85.0 170 85.0 146.9 186.9 85.0 180 85.0 149.9 189.9 85.0 190 85.0 152.7 192.7 85.0 200 85.0 155.4 195.4 85.0 210 85.0 158.1 198.1 85.0 220 85.0 160.6 200.6 85.0 230 85.0 163.0 203.0 85.0 240 85.0 165.3 205.3 85.0 250 85.0 167.5 207.5 85.0 260 85.0 169.6 209.6 85.0 270 85.0 171.6 211.6 85.0 280 85.0 173.6 213.6 85.0 290 85.0 175.5 215.5 85.0

~,00 85.0 177.3 217.3 85.0 310 85.0 179.1 219.1 85.0 320 85.0 180.8 220.8 85.0 330 85.0 182.4 222.4 85.0 340 85.0 184.0 224.0 85.0 350 85.0 185.6 225.6 85.0 360 85.0 187.1 227.1 85.0 370 85.0 188.6 228.6 85.0 375 85.0 189.4 229.4 85.0 375 126.0 189.4 229.4 126.0 380 126.0 190.1 230.1 126.0 390 126.0 191.6 231.6 126.0 400 126.0 193.1 233.1 126.0 4-7

Table 4-1 (Continued)

P-T CURVE VALUES FOR 17 EFPY Limiting Non-Beltline Curve Cunt Pressure Temnerature (*F) _Igno. (*F)

(nsic)

A B C A 410 126.0 194.6 234.6 126.0 420 126.0 196.0 236.0 126.0 430 126.0 197.4 237.4 126.0 440 126.0 198.8 238.8 126.0 450 126.0 200.1 240.1 126.0 460 126.0 201.4 241.4 126.0 470 126.0 202.7 242.7 126.0 480 126.0 203.9 243.9 126.0 490 126.0 205.1 245.1 126.0 500 126.0 206.3 246.3 126.0 510 126.0 207.4 247.4 126.0

$20 126.0 208.5 248.5 126.0 530 126.0 209.6 249.6 126.0 540 126.0 210.6 250.6 126.0 550 126.0 211.6 251.6 126.0 560 126.0 212.6 252.6 126.0 570 126.3 213.5 253.5 126.3 580 128.5 214.4 254.4 128.5 590 130.7 215.3 255.3 130.7 600 132.9 216.1 256.1 132.9 610 134.9 216.9 256.9 134.9 620 136.9 217.7 257.7 136.9 630 138.9 218.4 258.4 138.9 640 140.8 219.5 259.5 140.8 650 142.6 220.8 260.8 142.6 660 144.4 222.1 262.1 144.4 670 146.2 223.4 263.4 146.2 680 147.9 224.6 264.6 147.9 690 149.6 225.8 265.8 149.6 700 151.2 227.0 267.0 151.2 710 152.8 228.1 268.1 152.8 720 154.8 229.3 269.3 154.3 730 157.3 230.4 270.4 155.8 740 159.7 231.5 271.5 157.3 750 162.0 232.6 272.6 158.8 760 164.2 233.7 273.7 160.2 770 166.3 234.7 274.7 161.6 780 168.4 235.8 275.8 162.9 790 170.4 236.8 276.8 164.3 800 172.4 237.8 277.8 165.6 810 174.3 238.8 278.8 166.9 820 176.2 239.8 279.8 168.2 830 178.0 240.7 280.7 169.4 4-8

x __

u Table 41 (Continued)

P-T CURVE VALUES FOR 17 EFPY Limiting Non-Beltline Curve Curve Pressure T-Me m Temo. (*F)

(osid A B C A 840 179.8 241.7 281.7 170.6 850 181.5 242.6 282.6 171.8 860 183.2 243.6 283.6 173.0 870 184.8 244.5 284.5 174.1 880 186.4 245.4 285.4 175.3 890 188.0 246.3 286.3 176.4 900 189.5 247.1 287.1 177.5 910 191.0 248.0 288.0 178.6 920 192.5 248.9. 288.9 179.6  :

930 193.9 249.7 289.7 180.7 l 940 195.3 250.6 290.6 181.7 950 196.7 251.4 291.4 182.8 j 960 198.0 252.2 292.2 183.8 j 970 199.4 253.0 293.0 184.7

)

980 200.7 253.8 293.8 185.7 990 201.9 254.6 294.6 186.7 1000 203.2 255.4 295.4 187.6 i 1010 204.4 256.2 296.2 188.6 j 1020 205.6 256.9 296.9 189.5 1030 206.8 257.7 297.7 190.4 1040 208.0 258.4 298.4 191.3 1050 209.1 259.2 299.2 192.2 1060 210.3 259.9 299.9 193.1 1070 211.4 260.6 300.6 193.9 1080 212.5 261.3 301.3 194.8

/ 1090 213.5 262.0 302.0 195.6 1100 214.6 262.7 302.7 196.4 p 1110 215.6 263.4 303.4 197.3 1120 216.7 264.1 304.1 198.1 1130 217,7 264.8 304.8 198.9 1140 218.7 265.5 305.5 199.7 1150 219.7 266.1 306.1 200.5 1160 220.6 266.8 306.8 201.2 1170 221.6 267.5 307.5 202.0 1180 222.5 268.1 308.1 202.8 1190 223.5 268.8 308.8 203.5 1200 224.4 269.4 309.4 204.3 1210 225.3 270.0 310.0 205.0 1220 226.2 270.6 310.6 205.7 1230 227.1 271.3 311.3 206.4 1240 228.0 271.9 311.9 207.1 1250 228.8 272.5 312.5 207.8 1260 229.7 273.1 313.1 208.5 4-9 i

Table 4-1 (Continued)

P-T CURVE VALUES FOR 17 EFPY Limiting Non-Beltline Curve Curve Pressure Temnerature (*B .,,.Iemo ('M (osid A B C A 1270 230.5 273.7 313.7 209.2 I 1280 231.3 274.3 314.3 209.9 1290 232.2 274.9 314.9 210.6 1300 233.0 275.5 31,5.5 211.3 1310 233.8 276.0 316.0 211.9 1320 234.6 276.6 316.6 212.6 1330 235.3 277.2 317.2 213.2 1340 236.1 277.7 317.7 213.9 )

1350 236.9 278.3 318.3 214.5 ,

1360 237.6 278.9 318.9 215.1 l 1370 238.4 279.4 319.4 215.8 1380 239.1 280.0 320.0 216.4 1390 239.9 280.5 320.5 217.0 1400 240.6 281.0 321.0 217.6 l

4-10

. - . . - _ - . ~ _ - - - - . . . . . . - - . . - - . .. . . . __

l Table 4-2 P-T CURVE VALUES FOR 22 EFPY l

Limiting Non-Beltline 1 Curve Curve i Pnessure Temnerature ('F) Temo. ('F) l (nsid A B C A 0 85.0 85.0 96.0 85.0 10 85.0 85.0 96.0 85.0 20 85.0 85.0 96.0 85.0 30 85.9 85.0 96.0 85.0 40 85.0 85.0 100.6 85.0 50 85.0 85.0 113.6 85.0

.60 85.0 85.0 124.6 85.0 70 85.0 94.1 134.1 85.0 80 85.0 102.3 142.3 85.0 90 35.0 109.3 149.3 85.0 100 85.0 115.4 155.4 85.0 110 85.0 121.0 - 161.0 85.0 120 85.0 125.9 165.9 85.0 130 85.0 130.7 170.7 85.0 140 85.0 135.3 175.3 85.0 150 85.0 139.6 179.6 85.0 160 85.0 143.5 183.5 85.0 170 85.0 146.9 186.9 85.0 180 85.0 149.9 189.9 85.0 190 85.0 152.7 192.7 85.0 200 85.0 155.4 195.4 85.0 i I

210 85.0 158.1 198.1 85.0 220 85.0 160.6 200.6 85.0 j 230 85.0 163.0 203.0 85.0 240 85.0 165.3 205.3 85.0 250 85.0 167.5 207.5 85.0 260 85.0 169.6 209.6 85.0 270 85.0 171.6 211.6 85.0 280 85.0 173.6 213.6 85.0 290 85.0 175.5 215.5 85.0 300 85.0 177.3 217.3 85.0 310 85.0 179.1 219.1 85.0 320 85.0 180.8 220.8 85.0 330 85.0 182.4 222.4 85.0 340 85.0 184.0 224.0 85.0 350 85.0 185.6 225.6 85.0 360 85.0 187.1 227.1 85.0 370 85.0 188.6 228.6 85.0 375 85.0 189.4 229.4 85.0 375 126.0 189.4 229.4 126.0 380 126.0 190.1 230.1 126.0 390 126.0 191.6 231.6 126.0 400 126.0 193.1 233.1 126.0 4-11

Table 4-2 (Continued)

P-T CURVE VALUES FOR 22 EFPY Limiting Non-Beltline Curve Curve Pressure Temocrature Pn Temo en (osin)

A B C A 410 126.0 194.6 234.6 126.0 420 126.0 1%.0 236.0 126.0 430 126.0 197.4 237.4 126.0 440 126.0 198.8 238.8 126.0 450 126.0 200.1 240.1 126.0 460 126.0 201.4 241.4 126.0 470 126.0 202.7 242.7 126.0 480 126.0 203.9 243.9 126.0 490 126.0 205.1 245.1 126.0 500 126.0 206.3 246.3 126.0 510 126.0 207.4 247.4 126.0 520 126.0 208.8 248.8 126.0 530 126.0 210.4 250.4 126.0 540 126.0 212.1 252.1 126.0 550 126.0 213.7 253.7 126.0 560 126.0 215.2 255.2 126.0 570- 126.3 216.7 256.7 126.3 580 128.5 218.2 258.2 128.5 590 130.7 219.7 259.7 130.7 600 132.9 221.1 261.1 132.9 610 134.9 222.5 262.5 134.9 620 136.9 223.9 263.9 136.9 630 138.9 225.2 265.2 138.9 640 140.8 226.5 266.5 140.8 650 142.6 227.8 267.8 142.6 660 144.9 229.1 269.1 144.4 670 148.0 230.4 270.4 146.2 680 151.0 231.6 271.6 147.9 690 153.9 232.8 272.8 149.6 700 156.6 234.0 274.0 151.2 710 159.3 235.1 275.1 152.8 720 161.8 236.3 276.3 154.3 730 164.3 237.4 277.4 155.8 740 166.7 238.5 278.5 157.3 750 169.0 239.6 279.6 158.8 760 171.2 240.7 280.7 160.2 770 173.3 241.7 281.7 161.6 780 175.4 242.8 282.8 162.9 790 177.4 243.8 283.8 164.3 800 179.4 244.8 284.8 165.6 810 181.3 245.8 285.8 166.9 820 183.2 246.8 286.8 168.2 830 185.0 247.7 287.7 169.4 4-12

Table 4-2 (Continued)

P-T CURVE VALUES FOR 22 EFPY Limiting Non-Beltline Curve Curve Pressure Temocrature (P Temo ('n (osid _

A B C A 840 186 8 248.7 288.7 170.6 850 188.5 249.6 289.6 171.8 860 190.2 250.6 290.6 173.0 870 191.8 251.5 29,1.5 174.1 880 193.4 252.4 292.4 175.3 890 195.0 253.3 293.3 176.4 900 1%.5 254.1 294.1 177.5 910 198.0 255.0 295.0 178.6 920 199.5 255.9 295.9 179.6 930 200.9 256.7 296.7 180.7 940 202.3 257.6 297.6 181.7 950 203.7 258.4 298.4 182.8 960 205.0 259.2 299.2 183.8 970 206.4 260.0 300.0 184.7 980 207.7 260.8 300.8 185.7 990 208.9 261.6 301.6 186.7 1000 210.2 262.4 302.4 187.6 1010 211.4 263.2 303.2 188.6 1020 212.6 263.9 303.9 189.5 1030 213.8 264.7 304.7 190.4 1040 215.0 265.4 305.4 191.3 1050 216.1 266.2 306.2 192.2 1060 217.3 266.9 306.9 193.1 1070 218.4 267.6 307.6 193.9 1080 219.5 268.3 308.3 194.8 1090 220.5 269.0 309.0 195.6 1100 221.6 269.7 309.7 196.4 1110 222.6 270.4 310.4 197.3 1120 223.7 271.1 311.1 198.1 1130 224.7 271.8 311.8 198.9 1140 225.7 272.5 312.5 199.7 1150 226.7 273.1 313.1 200.5 1160 227.6 273.8 313.8 201.2 1170 228.6 274.5 314.5 202.0 1180 229.5 275.1 315.1 202.8 1190 230.5 275.8 315.8 203.5 1200 231.4 276.4 316.4 204.3 1210 232.3 277.0 317.0 205.0 1220 233.2 277.6 317.6 205.7 1230 234.1 278.3 318.3 206.4 1240 235.0 278.9 318.9 207.1 1250 235.8 279.5 319.5 207.8 1260 236.7 280.1 320.1 208.5 4-13

Table 4-2 (Continued)

P-T CURVE VALUES FOR - 22 EFPY Limiting Non-Beltline Curve Curve Pressure Temnerature ('F) Temo. (*19 (osid A B C A 1270 237.5 280.7 320.7 209.2 1280 238.3 281.3 321.3 209.9 1290 239.2 281.9 321.9 210.6 1300 240.0 282.5 322.5 211.3 1310 240.8 283.0 323.0 211.9 1320 241.6 283.6 323.6 . 212.6 1330 242.3 ' 284.2 324.2 213.2 1340 243.1 284.7 324.7 213.9 1350 243.9 285.3 325.3 214.5 1360 244.6 285.9 325.9 215.1 1370 245.4 286.4 326.4 215.8 1380 246.1 287.0 327.0 216.4 1390 246.9 287.5 327.5 217.0 1400 247.6 288.0 328.0 217.6 1

l 4-14

.-, - . . . - - a -s - ~

k Table 4-3 ,

P 'I CURVE VALUES FOR 27 EFPY Limiting Non-Beltline Curve Curve Pressure Temnerature ('F) Temo. ('F) I losii)

A B C A 0 85.0 85.0 96.0 85.0 10 85.0 85.0 96.0 85.0 20 85.0 85.0  %.0 85.0 30 85.0 85.0 96.0 85.0 40 85.0 85.0 100.6 85.0 50 85.0 85.0 113.6 85.0 60 85.0 85.0 124.6 85.0 70 85.0 94.1 134.1 85.0 80 85.0 102.3 142.3 85.0 90 85.0 109.3 149.3 85.0 100 85.0 115.4 155.4 85.0 110 85.0 121.0 161.0 85.0 120 85.0 125.9 165.9 85.0 130 85.0 130.7 170.7 85.0 140 85.0 135.3 175.3 85.0 150 85.0 139.6 179.6 85.0 160 85.0 143.5 183.5 85.0 170 85.0 146.9 186.9 85.0 180 85.0 149.9 189.9 85.0 190 85.0 152.7 192.7 85.0 200 85.0 155.4 195.4 85.0 210 85.0 158.1 198.1 85.0 220 85.0 160.6 200.6 85.0 1

230 85.0 163.0 203.0 85.0 l 240 85.0 165.3 205.3 85.0 250 85.0 167.5 207.5 85.0 260 85.0 169.6 209.6 85.0 270 85.0 171.6 211.6 85.0 280 85.0 173.6 213.6 85.0 290 85.0 175.5 215.5 85.0 300 85.0 177.3 217.3 85.0 310 85.0 179.1 219.1 85.0 320 85.0 180.8 220.8 85.0 330 85.0 182.4 222.4 85.0 340 85.0 184.0 224.0 85.0 350 85.0 185.6 225.6 85.0 360 85.0 187.1 227.1 85.0 370 85.0 188.6 228.6 85.0 375 85.0 189.4 229.4 85.0, 375 126.0 189.4 229.4 126.0 380 126.0 190.1 230.1 126.0 390 126.0 191.6 231.6 126.0 400 126.0 193.1 233.1 126.0 4-15

Table 4-3 (Continued)

P-T CURVE VALUES FOR 27 EFPY Limiting Non-Beltline Curve Curve Pressure Temocrature (*F) Temo. (*F)

(osic)

A B C A 410 126.0 194.6 234.6 126.0 420- 126.0 196.4 236.4 126.0 430 126.0 198.6 238.6 126.0 440 126.0 200.7 240.7 126.0 450 126.0 202.8 242.8 126.0 460 126.0 204.8 244.8 126.0 470 126.0 206.8 246.8 126.0 480 126.0 208.7 248.7 126.0 490 126.0 210.5 250.5 126.0 500 126.0 212.3 252.3 126.0 510 126.0 214.1 254.1 126.0 520 126.0 215.8 255.8 126.0 530 126.0 217.4 257.4 126.0 540 126.0 219.1 259.1 126.0 550 126.0 220.7 260.7 126.0 560 126.0 222.2 262.2 126.0 570 126.3 223.7 263.7 126.3 580 128.5 225.2 265.2 128.5 590 130.7 226.7 266.7 130.7 600 132.9 228.1 268.1 132.9 610 134.9 229.5 269.5 134.9 620 137.7 230.9 270.9 136.9 630 141.6 232.2 272.2 138.9 640 145.2 233.5 273.5 140.8 650 148.6 234.8 274.8 142.6 660 151.9 236.1 276.1 144.4 670 155.0 237.4 277.4 146.2 680 158.0 238.6 278.6 147.9 690 160.9 239.8 279.8 149.6 700 163.6 241.0 281.0 151.2 710 166.3 242.1 282.1 152.8 720 168.8 243.3 283.3 154.3 730 171.3 244.4 284.4 155.8 740 173.7 245.5 285.5 157.3 750 176.0 246.6 286.6 158.8 760 178.2 247.7 287.7 160.2 770 180.3 248.7 288.7 161.6 780 182.4 249.8 289.8 162.9 790 184.4 250.8 290.8 164.3 800 186.4 251.8 291.8 165.6 810 188.3 252.8 292.8 166.9 820 190.2 253.8 293.8 168.2 830 192.0 254.7 294.7 169.4 4-16

l Table 4-3 (Continued) j P-T CURVE VALUES FOR 27 EFPY '

l l

Limiting Non-Beltline Curve Cunt Pressure Tenusetme m Temn m (risis A B C A 840 193.8 255.7 295.7 170.6 850 195.5 256.6 2%.6 171.8 860 197.2 257.6 297.6 173.0 870 198.8 258.5 298.5 r'4.1 880 200.4 259.4 299.4 . 3.3 890 202.0 260.3 300.3 176.4 900 203.5 261.1 301.1 177.5 910 205.0 262.0 302.0 178.6 920 206.5 262.9 302.9 179.6 930 207.9 263.7 303.7 180.7 940 209.3 264.6 304.6 181.7 950 210.7 265.4 305.4 182.8 960 212.0 266.2 306.2 183.8 970 213.4 267.0 307.0 184.7 980 214.7 267.8 307.8 185.7 990 215.9 268.6 308.6 186.7 1000 217.2 269.4 309.4 187.6 1010 218.4 270.2 310.2 188.6 1020 219.6 270.9 310.9 189.5 l 1030 220.8 271.7 311.7 190.4 I 1040 222.0 272.4 312.4 191.3 1050 223.1 273.2 313.2 192.2 1060 224.3 273.9 313.9 193.1 I 1070 225.4 274.6 314.6 193.9 1080 226.5 275.3 315.3 194.8 1090 227.5 276.0 316.0 195.6 1100 228.6 276.7 316.7 196 4 ,

1110 229.6 277.4 317.4 197.3 l 1120 230.7 278.1 318.1 198.1 1130 231.7 278.8 318.8 198.9 1140 232.7 279.5 319.5 199.7 1150 233.7 280.1 320.1 200.5 1160 234.6 280.8 320.5 201.2 1170 235.6 281.5 321.5 202.0 1180 236.5 282.1 322.1 202.8 1190 237.5 282.8 322.8 203.5 1200 238.4 283.4 323.4 204.3 1210 239.3 284.0 324.0 205.0 1220 240.2 284.6 324.6 205.7 1230 241.1 285.3 325.3 206.4 1240 242.0 285.9 325.9 207.1 1250 242.8 286.5 326.5 207.8 1260 243.7 287.1 327.1 208.5 4-17

Table 4-3 (Continued)

P-T CURVE VALUES FOR 27 EFPY Limiting Non-Beltline Curve Curve Pressure T-...m e - (*F) Temo (*F)

(osie A B C A 1270 244.5 287.7 327.7 209.2 1280 245.3 288.3 328.3. 209.9 1290 246.2 288.9 328.9 210.6 1300 247.0 289.5 329.5 211.3 1310- 247.8 290.0 330.0 211.9 1320 248.6 290.6 330.6 212.6 1330 249.3 291.2 331.2 213.2 1340 250.1 291.7 331.7 213.9 1350 250.9 292.3 332.3 214.5 1360 251.6 292.9 332.9 215.1 1370 252.4 293.4 333.4 215.8 1380 253.1 294.0 334.0 216.4 1390 253.9 294.5 334.5 217.0 1400 254.6 295.0 335.0 217.6 l

l l

! l I

4-18

Table 4-4 P-T CURVE VALUES FOR 32 EFPY Limiting Non-Beltline Curve Curve Pressure Temocrature FF) _ Temo. FF)

(osin)

A B C A l 0 85.0 - 85.0  %.0 85.0 10 85.0 85.0  %.0 85.0 20 85.0 85.0  %.0 85.0 30 85.0 85.0  %.0 85.0 l

40 85.0 85.0 100.6 85.0 50 85.0 85.0 113.6 85.0 I 60 85.0 85.0 124.6 85.0 70 85.0 94.1 134.1 85.0 80 85.0 102.3 142.3 85.0 90 85.0 109.3 149.3 85.0 100 85.0 115.4 155.4 85.0 110 85.0 121.0 161.0 85.0 120 85.0 125.9 165.9 85.0 130 85.0 130.7 170.7 85.0 140 85.0 - 135.3 175.3 85.0 150 85.0 139.6 179.6 85.0 160 85.0 143.5 183.5 85.0 170 85.0 146.9 186.9 85.0 180 85.0 149.9 189.9 85.0 190 85.0 152.7 192.7 85.0 200 85.0 155.4 195.4 85.0 210 85.0 158.1 198.1 85.0 1 220 85.0 160.6 200.6 85.0 l 230 85.0 163.0 203.0 85.0 240 85.0 165.3 205.3 85.0 250 85.0 167.5 207.5 85.0

- 260 85.0 169.6 209.6 85.0 I 270 85.0 171.6 211.6 85.0 280 85.0 173.6 213.6 85.0 290 85.0 175.5 215.5 85.0 300 85.0 177.3 217.3 85.0 310 85.0 179.1 219.1 85.0 320 85.0 180.8 220.8 85.0 330 85.0 182.4 222.4 85.0 340 85.0 184.0 224.0 85.0 350 85.0 185.6 225.6 85.0 360 85.0 187.1 227.1 85.0 370 85.0 188.6 228.6 85.0 375 85.0 189.4 229.4 85.0 375 126.0 189.4 234.6 126.0 380 126.0 190.5 234.6 126.0 390 126.0 193.0 234.6 126.0 400 126.0 197.8 237.8 126.0 4-19

I i

)

u Table 4-4 (Continued)

P-T CITRVE VALUES FOR 32 EFPY Limiting Ncn-Beltline Curve Curve Pressure Temocrature (P Temn (m (osid A B C A 410 126.0 200.1 240.1 126.0 420 126.0 202.4 242.4 126.0 430 126.0 204.6 244.6 126.0 440 126.0 206.7 246.7 126.0 450 126.0 208.8 248.8 126.0 460 126.0 210.8 250.8 126.0 470 126.0 212.8 252.8 126.0 480 126.0 214.7 254.7 126.0 490 126.0 216.5 256.5 126.0 500 126.0 218.3 258.3 126.0 510 126.0 220.1 260.1 126.0 520 ~ 126.0 221.8 261.8 126.0 l 530 126.0 223.4 263.4 126.0 540 126.0 225.1 265.1 126.0 550 126.0 226.7 266.7 126.0 560 126.0 228.2 268.2 126.0 570 126.3 229.7 269.7 126.3 580 128.5 231.2 271.2 128.5 590 130.8 232.7 272.7 130.7 600 135.4 234.1 274.1 132.9 610 139.7 235.5 275.5 134.9 620 143.7 236.9 276.9 136.9 630 147.6 238.2 278.2 138.9 640 151.2 239.5 279.5 140.8 650 154.6 240.8 280.8 142.6 660 157.9 242.1 282.1 144.4 670 161.0 243.4 283.4 146.2 680 164.0 244.6 284.6 147.9 690 166.9 245.8 285.8 149.6 1 700 169.6 247.0 287.0 151.2 l 710 172.3 248.1 288.1 152.8 !

720 174.8 249.3 289.3 154.3 {

730 177.3 250.4 290.4 155.8 l 740 179.7 251.5 291.5 157.3 750 182.0 252.6 292.6 158.8 760 184.2 253.7 293.7 160.2 770 186.3 254.7 294.7 161.6 780 188.4 255.8 295.8 162.9 790 190.4 256.8 296.8 164.3 800 192.4 257.8 297.8 165.6 l 810 194.3 258.8 298.8 166.9 820 196.2 259.8 299.8 168.2 830 198.0 260.7 300.7 169.4 4-20

_ . . _ - - . -- - --. ._. .. - - =. . . . _ - - .

Table 4-4 (Continued)

P-T CURVE VALUES FOR 32 EFPY Limiting Non-Beltline Curve Curw Pressure Temnerature (m Temo (m (nsid A B C A 840 199.8 261.7 301.7 170.6 850 201.5 262.6 302.6 171.8 860 203.2 263.6 303.6 173.0 l 870 204.8 264.5 304.5 174.1 880 206.4 265.4 305.4 175.3 890 208.0 266.3 306.3 176.4 900 209.5 267.1 307.1 177.5 l 910 211.0 268.0 308.0 178.6 920 212.5 268.9 308.9 179.6

, 930 213.9 269.7 309.7 180.7 l 940 215.3 270.6 310.6 181.7 950 216.7 271.4 311.4 182.8 960 218.0 272.2 312.2 183.8 970 219.4 273.0 313.0 184.7 j 980 220.7 273.8 313.8 185.7 '

990 221.9 274.6 314.6 186.7 1000 223.2 275.4 315.4 187.6 1010 224.4 276.2 316.2 188.6 l 1020 225.6 276.9 316.9 189.5 1030 226.8 277.7 317.7 190.4 1040 228.0 278.4 318.4 191.3 1050 229.1 279.2 319.2 192.2 1060 230.3 279.9 319.9 193.1 1070 231.4 280.6 320.6 193.9 1080 232.5 281.3 321.3 194.8 1090 233.5 282.0 322.0 195.6 1100 234.6 282.7 322.7 196.4 1110 235.6 283.4 323.4 197.3 1120 236.7 284.1 324.1 198.1 1130 237.7 284.8 324.8 198.9 1140 238.7 285.5 325.5 199.7 1150 239.7 286.1 326.1 200.5 1160 240.6 286.8 326.8 201.2 1170 241.6 287.5 327.5 202.0 1180 242.5 288.1 328.1 202.8 1190 243.5 288.8 328.8 203.5 1200 244.4 289.4 329.4 204.3 1210 245.3 290.0 330.0 205.0 1220 246.2 290.6 330.6 205.7 1230 247.1 291.3 331.3 206.4 1240 248.0 291.9 331.9 207.1 1250 248.8 292.5 332.5 207.8 1260 249.7 293.1 333.1 208.5 4-21

Table 4-4 (Continued)

P-T CURVE VALUES FOR 32 EFPY Limiting Non-Beltline Curve Curve Pressure Tmowetme m Temn (*F)

(osia A B C A 1270 250.5 293.7 333.7 209.2 1280 251.3 294.3 334.3 209.9 1290 252.2 294.9 334.9 210.6 1300 253.0 295.5 335.5 211.3 1310 253.8 2%.0 336.0 211.9 1320 254.6 2%.6 336.6 212.6 1330 255.3 297.2 337.2 213.2 1340 256.1 297.7 337.7 213.9 1350 256.9 298.3 338.3 214.5 1360 257.6 298.9 338.9 215.1 1370 258.4 299.4 339.4 215.8 1380 259.1 300.0 340.0 216.4 1390 259.9 300.5 340.5 217.0 1400 260.6 301.0 341.0 217.6 f

i I

4-22

3 i

u i Table 4-5 P-T CURVE VALUES FOR 48 EFPY Limiting Non-Beltline Curve Curve ,

Pressure Temnerature FF) Temo. FF)

(esic)

A B C A 0 85.0 85.0  %.0 85.0 10 85.0 85.0  %.0 85.0 20 85.0 85.0 96.0 85.0 30 85.0 85.0 96.0 85.0 40 85.0 85.0 100.6 85.0 50 85.0 85.0 113.6 85.0 60 85.0 85.0 124.6 85.0 70 85.0 94.1 134.1 85.0 80 85.0 102.3 142.3 85.0 90 85.0 109.3 149.3 85.0 100 85.0 115.4 155.4 85.0 4 110 85.0 121.0 161.0 85.0 120 85.0 125.9 165.9 85.0 130 85.0 130.7 170.7 85.0 140 85.0 135.3 175.3 85.0 150 85.0 139.6 179.6 85.0

} 160 85.0 143.5 183.5 85.0 170 85.0 146.9 186.9 85.0 180 85.0 149.9 189.9 85.0 190 85.0 152.7 192.7 85.0 200 85.0 155.4 195.4 85.0 210 85.0 158.1 198.1 85.0 220 85.0 160.6 200.6 85.0 230 85.0 163.0 203.0 85.0 1 240 85.0 165.3 205.3 85.0 l 250 85.0 167.5 207.5 85.0 260 85.0 169.6 209.6 85.0 270 85.0 171.6 211.6 85.0 280 85.0 173.6 213.6 85.0 290 85.0 175.9 215.9 85.0 300 85.0 179.7 219.7 85.0 310 85.0 183.4 223.4 85.0 320 85.0 186.8 226.8 85.0 330 85.0 190.1 230.1 85.0 340 85.0 193.2 233.2 85.0 350 85.0 1%.2 236.2 85.0 360 85.0 199.1 239.1 85.0 370 85.0 201.8 241.8 85.0 375 85.0 203.2 243.2 85.0 375 126.0 203.2 248.6 126.0 380 126.0 204.5 248.6 126.0 ,

390 126.0 207.0 248.6 126.0 I 400 126.0 211.8 251.8 126.0  !

4-23

Table 4-5 (Continued)

P-T CURVE VALUES FOR 48 EFPY Limiting Non-Beltline Curve Curve Pressure Temocrature m Temo m (esid A B C A 410 126.0 214.1 254.1 126.0 420 126.0 216.4 256.4 126.0 430 126.0 218.6 258.6 126.0 440 126.0 220.7 260.7 126.0 450 126.0 222.8 262.8 126.0 460 126.0 224.8 264.8 126.0 470 126.0 226.8 266.8 126.0 480 126.0 228.7 268.7 126.0 490 126.0 230.5 270.5 126.0 500 126.0 232.3 272.3 126.0 510 126.0 234.1 274.1 126.0 520 126.0 235.8 275.8 126.0 530 126.0 237.4 277.4 126.0 540 126.0 239.1 279.1 126.0 550 126.0 240.7 280.7 126.0 560 128.9 242.2 282.2 126.0 570 134.6 243.7 283.7 126.3 580 139.9 245.2 285.2 128.5 590 144.8 246.7 286.7 130.7 600 149.4 248.1 288.1 132.9 610 153.7 249.5 289.5 134.9 620 157.7 250.9 290.9 136.9 630 161.6 252.2 292.2 138.9 640 165.2 253.5 293.5 140.8 650 168.6 254.8 294.8 142.6 660 171.9 256.1 296.1 144.4 670 175.0 257.4 297.4 146.2 l 680 178.0 258.6 298.6 147.9 l 690 180.9 259.8 299.8 149.6 700 183.6 261.0 301.0 151.2 710 186.3 262.1 302.1 152.8 I 720 188.8 263.3 303.3 154.3 730 191.3 264.4 304.4 155.8 740 193.7 265.5 305.5 157.3 !

750 1%.0 266.6 306.6 158.8 760 198.2 267.7 307.7 160.2 770 200.3 268.7 308.7 161.6 780 202.4 269.8 309.8 162.9 790 204.4 270.8 310.8 164.3 800 206.4 271.8 311.8 165.6 810 208.3 272.8 312.8 166.9 820 210.2 273.8 313.8 168.2 830 212.0 274.7 314.7 169.4 4-24

d Table 4-5 (Continued)

P-T CURVE VALUES FOR 48 EFPY Limiting Non-Beltline Curve Curve Pressure Temocrature ('n Temn (*M (osid A B C A 840 213.8 275.7 315.7 170.6 850 215.5 276.6 316.6 171.8 860 217.2 277.6 317.6 173.0 870 218.8 278.5 318.5 174.1 880 220.4 279.4 319.4 175.3 890 222.0 280.3 320.3 176.4 900 223.5 281.1 321.1 177.5 910 225.0 282.0 322.0 178.6 920 226.5 282.9 322.9 179.6 930 227.9 283.7 323.7 180.7 940 229.3 284.6 324.6 181.7 950 230.7 285.4 325.4 182.8 960 232.0 286.2 326.2 183.8 970 233.4 287.0 327.0 184.7 980 234.7 287.8 327.8 185.7 990 235.9 288.6 328.6 186.7 1000 237.2 289.4 329.4 187.6 1010 238.4 290.2 330.2 188.6 1020 239.6 290.9 330.9 189.5 1030 240.8 291.7 331.7 190.4 1040 242.0 292.4 332.4 191.3 1050 243.1 293.2 333.2 192.2 1060 244.3 293.9 333.9 193.1 1070 245.4 294.6 334.6 193.9 1080 246.5 295.3 335.3 194.8 1090 247.5 2%.0 336.0 195.6 1100 248.6 296.7 336.7 196.4 1110 249.6 297.4 337.4 197.3 1120 250.7 298.1 338.1 198.1 1130 251.7 298.8 338.8 198.9 1140 252.7 299.5 339.5 199.7 1150 253.7 300.1 340.1 200.5 1160 254.6 300.8 340.8 201.2 1170 255.6 301.5 341.5 202.0 1180 256.5 302.1 342.1 202.8 1190 257.5 302.8 342.8 203.5 1200 258.4 303.4 343.4 204.3 1210 259.3 304.0 344.0 205.0 1220 260.2 304.6 344.6 205.7 1230 261.1 305.3 345.3 206.4 1240 262.0 305.9 345.9 207.1 1250 262.8 306.5 346.5 207.8 1260 263.7 307.1 347.1 208.5 i

4-25 l

l t

a

! Table 4-5 (Continued)

, P-T CURVE VALUES FOR 48 EFPY i

a l Limiting Non-Beltline j

l. Curve Curve 4

Pressure Temnerature (*F) Temo. (*F)

(osie)

, A B C A 1270 264.5 307.7 347.7 209.2

1280 265.3 308.3 348.3 209.9

! 1290 266.2 308.9 348.9 210.6 1300 267.0 309.5 349.5 211.3 l 1310 267.8 310.0 350.0 211.9 1320 268.6 310.6 350.6 212.6

, 1330 269.3 311.2 351.2 213.2

1340 270.1 311.7 351.7 213.9 i 1350 270.9 312.3 352.3 214.5 1360 271.6 312.9 352.9 215.1 1370 272.4 313.4 353.4 215.8 1380 273.1 314.0 354.0 216.4 1390 273.9 314.5 354.5 217.0 1400 274.6 315.0 355.0 217.6 i

4-26

I 1 1600 A

N ON- 17 sETUNE EFPy B C 1400 r DISCONTINUITY LIMITS, g RTndt = 66*F,  ;

~ BWR/6 CRD CURVE  ;

3 1200 i To r

j w

I

[

o 1000 i f

\ ,

[ f \ '

s  ! A

$ CORE BELTUNE UMITS C WITH ART OF 138'F

$ 800 j FOR LOWER SHELL y PLATE G 8-6 m

A SYSTEM HYDROTEST UMIT WITH FUEL IN VESSEL E 600 B - NON-NUCLEAR HEATUP/

w j COOLDOWN UMIT f

8 u)

I  ;

C NUCLEAR (CORE CRITICAL)

$ UMIT

!E / N 875 *

[ \ DISCONTINUITY UMITS, RTndt = 60*F '

/ BWR/6 FW CURVE CURVES A,B,C ARE VALID 200 - BOLTUP r FOR 17 EFPY OF OPERATION l 85'F MINIMUM CRITICAUTY

/

/ / p TEMPERATURE = 96*F

/ p /

0 0 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)  :

Figure 4-1. Oyster Creek P-T Curve Valid to 17 EFPY 4-27

1600 A

NON- 22 sRTUNE EPPY B C 1400 7

DISCONTINUITY LIMITS, g RTndt - 66*F, g g

~BWR/6 CRD CURVE f I

3 1200 f E l 5 I I I I 6 l 1 (

I h1000 l s o i N oc #

I f CORE BELTLINE LIMITS S 800 # )' / WITH ART OF 145*F

, FOR LOWER SHELL f PLATE G-8-6

$ /

7-r A - SYSTEM HYDROTEST LIMIT WITH FUEL IN VESSEL E 600 B - NON NUCLEAR HEATUP/

d COOLDOWN LIMIT u) 1 C - NUCLEAR (CORE CRITICAL)

LIMIT "375 PSIG I DISCONTINUITY LIMITS, RTndt = 60*F BWR/6 FW CURVE CURVES A,B,C ARE VALID 200 --

BoLTUP .r FOR 22 EFPY OF OPERATION 85'F f '

MINIMUM CRITICALITY j/ / TEMPERATURE = 96*F

/

0 0 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE ( F)

Figure 4-2. Oyster Creek P-T Curve Valid to 22 EFPY 4-28

1600 A

NON- 21 SELTUNE EFPY B C 1400

, 7 DISCONTINUITY UMITS, g RTndt = 66*F, g j

~BWR/6 CRD CURVE f 3 1200 g E I O

5 / / N '

f O 1000 .

' / N

$ ' f\ \

M / I PxN C

) I CORE BELTLINE LIMITS S 800 j

/ r f WITH ART OF 152*F FOR LOWER SHELL f PLATE G-S-6 l l l j f A - SYSTEM HYDROTEST LIMIT f WITH FUEL IN VESSEL b

E 600 B - NON-NUCLEAR HEATUP/

d COOLDOWN LIMIT 5

(n r C - NUCLEAR (CORE CRITICAL)

$ LIMIT k ) / \

DISCONTINUITY UMITS,

1. RTndt = 60*F BWR/6 FW CURVE CURVES A,B,C ARE VALID 200 - BOLTUP r FOR 27 EFPY OF OPERATION 85'F

/ MINIMUM CRITICALITY p r '

p "

TEMPERATURE = 96*F

/

0 0 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F)

Figure 4-3. Oyster Creek P-T Curve Valid to 27 EFPY 4-29

1600 A

NON. 32 BETUNE EFPY B C 1400

, y r DISCONTINUITY LIMITS,  ;

RTndt = 66'F, g j BWR/6 CRD CURVE g i 1 j l l 3 1200 ,

E '

5  !

6 i '

x 100o l

, j~ f' g

a

$ j l l Hr CORE BELTLINE LIMITS f WITH ART OF 158'F o 800 f ) j FOR LOWER SHELL y / PLATE G 8 6

< l y / J A - SYSTEM HYDROTEST LIMIT _

2  ; WITH FUEL IN VESSEL 5 l g // B - NON-NUCLEAR HEATUP/

g tu

( COOLDOWN LIMIT

$ C - NUCLEAR (CORE CRITICAL) y LIMIT 400 -  ; CURVES A,B,C ARE VAUD 375 PSIG ~

FOR 32 EFPY OF OPERATION N

N APP G REQUIREMENT BASED -

N ON CURVE A @ 1100 PSIG 2

200 -- -

DISCONTINUITY LIMITS, -

5 /  ! RTndt = 60'F, BWR/6 FW CURVE

/ _ _ . MINIMUM CRITICALITY j TEMPERATURE = 96*F o -

5 ' '

o 100 200 soo 400 soo soo MINIMUM REACTOR VESSEL METAL TEMPERATURE (*F) j Figure 4-4. Oyster Creek P-T Curve Valid to 32 EFPY 4-30

1600 A

NON- 48 natWNE PPY B C 1400 DISCONTINUITY LIMITS, g RTndt = 66*F,  ;

BWR/6 CRD CURVE l I

p 1200 ,

a ,

a  !

I o 1000 l d

s j

! / A 'h CORE BELTLINE LIMITS

~

f WITH ART OF 172'F

$ 800 i R L WER SHER y f f PLATE G 8-6 4 1

$ / A - SYSTEM HYDROTEST LIMIT

~

z  ; WITH FUEL IN VESSEL 5 l 3 / j B . NON-NUCLEAR HEATUP/

3 / COOLDOWN LIMIT w

$ C . NUCLEAR (CORE CRITICAL)

@ LIMIT E

CURVES A,B,C ARE VAUD _

400 __375 PSIG f FOR 48 EFPY OF OPERATION N

-,

• APP G REQUIREMENT BASED -

ON CURVE A @ 1100 PSIG 200 -

N DISCONTINUITY LIMITS, BOLTUP r / -

85'F / RTndt = 60*F, BWR/6 FW CURVE

[ __ MINIMUM CRITICALITY s TEMPERATURE = 96*F 0 '[  !

l '

O 100 200 300 400 500 600 MINIMUM REACTOR VESSEL METAL TEMPERATURE ( F)

Figure 4-5. Oyster Creek P-T Curve Valid to 48 EFPY 4-31

1

\ N  ;

i l

Tm=210 F Ty=210 F l ETIVE ACTIVE l FUEL Tm=230 F Tm=210 F RJEL a ZONE ZONE b - -

l l

Tm=210 F '

Tm=188 F Tm=210 F Tm=190 F a) Bottom Head Monitored b) Bottom Head Monitored with Beltline Limits Separately Figure 4-6. Hypothetical Case of Pressure Test Temperature Reduction from Separate Bottom Head Monitoring

l 120 110 i 100 90 2 80 o -

S I

v 70 /

[ - o h

6 60 [

9 5

h y

50 [./

s 40

=;-ro.. rp ,'. * . .

30 o 20

,o:

/ .-

o 10 -

0 14 55

--100 0 100 200 300 TEST TEMPERATURE ( F) t Figure 4-7. Determination of Boltup Temperature for Plate G-307-R1 1

u 5 0 REFERENCES

[1] " Fracture Toughness Requirements," Appendix G to Part 50 of Title 10 of the Code of Federal Regulations, July 1983.

[2] " Radiation Embrittlement ofReactor Vessel Materials," USNRC Regulatory Guide 1.99, Revision 2, May 1988.

[3] Hodge, J. M., " Properties ofHeavy Section Nuclear Reactor Steels," Welding Research Council Bulletin 217, July 1976.

[4] " Fracture Toughness Requirements," USNRC Branch Technical Position MTEB 5-2, Revision 1, July 1981.

[5] Miller, R. L., " Testing and Evaluation ofIrradiated Reactor Vessel Materials Surveillance Program Specimens," GPU Nuclear TDR 725, Revision 3, December 1990.

[6] Manahan et. al., "Exammation, Testing and Evaluation of Specimens from the 210 Irradiated Pressure Vessel Surveillance Capsule for the Oyster Creek Nuclear Generating Station," Battelle Columbus Laboratories Report BCL-382-85-1, Revision 1, October 1985.

[7] " Fracture Toughness Criteria for Protection Against Failure," Appendix G to Section XI of the ASME Boiler & Pressure Vessel Code,1992 Edition.

[8] "PVRC Recommendations on Toughness Requirements for Ferritic Materials," Welding Research Council Bulletin 175, August 1972.

[9] Pierson et. al., " Analytical Report for Jersey Central Reactor Vessel," Combustion Engineering Repon CENC-1143.

6 5-1

[10] GE Nuclear Energy, NEDC-32399-P, " Basis for GE RTm Estimation Method," Report for BWR Owners' Group, San Jose, California, September 1994 (proprietary).

[11] " Safety Assessment by the Office ofNuclear Reactor Regulation BWR Owners' Group Report NEDC-32399-P Basis for GE RTurr Estimation Method Materials and Chemical Engineering Branch Division ofEngineering," USNRC Safety Assessment of Report NEDC-32399-P, December 1994.

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APPENDIX A CHARPY CURVES OF SELECTED VESSEL PLATES l

In order to establish an appropriate, conservative RTsm for the beltline plates and several other plates with low USE values, the Charpy data for each plate were curve fit with a hyperbolic tangent relationship: i l

ENERGY = A + B tanh [(T - T.)/C]

where A, B, To and C are constants determined by statistically fitting the Charpy data to minimize variance.

Once the curve fit for each material was established, the standard deviation of the data relative to the curve (in terms of temperature) was calculated. These values are reponed as ai in Section 2 of the report. The value of T3ot,is shown on the curves in this appendix as well.

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APPENDIX B i BELTLINE P-T CURVE CALCULATION METHOD f l

2 The behLe is the region of the vessel that will accumulate more than 1017 n/cm fluence during operation. The vessel wall from the bottom of active fuel to the top of active fuel meets these conditions. The Oyster Creek vessel beltline consists of two shells of plates and the connectmg welds. Therefore, there are no discontinuity regions to consider in the beltline curve  !

analyses. The methods used for the pressure test and heatup/cooldown curves are described below. The core critical operation curve is simply the heatup/cooldown curve plus 40 F, as ,

required in 10CFR50 Appendix G [1], so the methods for the heatup/cooldown curves apply to i i

- the core critical curves as well.  ;

i B.1 PRESSURE TEST i

In general, the methods of ASME Code Section III, Appendix G [7] are used to calculate i the pressure test beltline limits. The vessel shell, with an inside radius (R) to nummum thickness (t ) ratio of 15, is treated as a thin-walled cylinder. The maximum stress is the hoop stress, I given as o.= PR/t .

The stress intensity factor, Kr., is calculated using Figure G-2214-1 of [7], accounting for the proper ratio of stress to yield strength. Figure G-2214-1 was taken from Welding Research Council (WRC) Bulletin 175 [8], and is based on a 1/4 T radial flaw with a six-to-one aspect ratio (length of 1.5 T). The flaw is oriented normal to the maximum stress, in this case a vertically oriented flaw. This orientation is used even in the case where the circumferential weld is the limiting beltline material, as mandated by the NRC in the past. l l

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B-1

Pressure test Km is the calculated value Kw multiplied by a safety factor of 1.5, per [7]. The relationship between Km and temperature relative to reference temperature (T - RTan) is shown in Figure G-2210-1 of[7], represented by the relationship l

Km- 26.78 = 1.223 e [ 0.0145 ( T - RTurr + 160 )] (B1)

This relationship is derived in [8] as the lower bound of all dynamic fracture toughness and crack arrest toughness data. This relationship provides values of pressure (from Km) versus T (from (T-RTun)).

B.2 HEATUP/COOLDOWN The beltline curves for heatup/cooldown conditions are influenced by pressure stresses and thermal stresses, according to the relationship in [7]

Km = 2.0 Kw + Ka, (B-2) 1

. where Kw is primary membrane K due to pressure and Ka is radial thermal gradient K due to heatup/cooldown.

The pressure stress intensity factor Kw is calculated by the method described in section B.1, the

' only difference being the larger safety factor applied. The thermal gradient stress intensity factor calculation is described below.

The thermal stresses in the vessel wall are caused by a radial thermal gradient which is created by changes in the adjacent reactor coolant temperature in heatup or cooldown conditions. j The stress intensity factor is computed by multiplying the coefficient M. from Figure G-2214-2 of  :

[7] by the through-wall temperature gradient AT.,-given that the temperature gradient has a through-wall shape similar to that shown in Figure G-2214-3 of[7].

The relationship used to compute through-wall AT, is based on one-dimensional heat  ;

conduction through an insulated flat plate:

B-2

2 2 8 T(x,t)/ dx = 1/ (6T(x,t)/ St), where (B-3)

T(x,t) is temperature of the plate at depth x and time t E is thermal diffusivity (ft2/hr).

Maximum stress will occur when the radial thermal gradient reaches a quasi-steady state distribution, so that BT(x,t)/ at = dT(t)/dt = G, where G is the heatup/cooldoven rate, in this case 100*F/hr. The differential equation is integrated over x for the following boundary conditions, shownin Figure B-1:

l 1. Vessel inside surface (x = 0) temperature is the name as the coolant temperature, T..

2. Vessel outside surface (x = C) is perfectly insulated, so the thermal gradient dT/dx = 0.

The integrated solution results in the following relationship for wall temperature:

l T = Gx'/2 - GCx/ + T. (B-4) i This equation is normahzed to plot (T - T.)/AT versus x/C in Figure B-2. The resulting through-wall gradient compares very closely with Figure G-2214-3 of [7]. Therefore, AT, calculated from Equation B-4 is used with the appropriate ht of Figure G-2214-2 of [7] to compute Kn for heatup and cooldown.

The ht relationships were derived in [8] for infinitely long cracks of 1/4 T and 1/8 T. For the flat plate geometry and radial thermal gradient, orientation of the crack is not important.

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u The stress generated by the thermal gradient is a bending stress that changes sign from one side of the plate to the other. In combining pressure and thermal stresses, it is usually necessary to evaluate stresses at the 1/4 T location (inside surface flaw) and the 3/4 T location (outside surface flaw). This is because the thermal gradient tensile stress ofinterest is in the inner wall during cooldown and is in the outer wall during heatup. However, as a conservative simplification, the thermal gradient stress at the 1/4 T is assumed to be tensile for both heatup and cooldown. This results in the conservative approach of applying the maximum tensile stress at the 1/4 T location. This approach is conservative because irradiation effects cause the allowable toughness, Km, at 1/4 T to be less than that at 3/4 T for a given metal temperature. This conservatism of the approach causes no operation difficulties, since the BWR is at steam saturation conditions during normal heatup or cooldown, well above the heatup/cooldown curve limits.

B.3 EXAMPLE CALCULATION - 17 EFPY PRESSURE TEST AT 1000 PSIG The following inputs were used in the beltline limit calculation:

ART................................................. . 138"F Vessel Height.......... . . . . . .. . . . . . . . . . . 766 inch Bottom of Active Fuel Height...... ....... . . . . . 209.3 inch Vessel Radius .. .. . . .. . . . . . . . . . . . . . . . . . . . . . . . . 106.7 inch Vessel Thickness.. .. ... .. .. ........ .. ... .. . 7.125 inch Beltline Material Sy. .. . . . ... . ... .. . . .... .... 62.7 ksi Pressure was calculated to include hydrostatic pressure for a full vessel:

P = 1000 psi + (766-209.3) inch

• 0.0361 psi / inch = 1020.1 osie Pressure stress:

o = PR/t = 1020.1 psig

• 106.7 inch / 7.125 inch = 15276 psi B-4

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The factor hb depends on (c/Sy) and d:

o/S, = 15276 / 62700 = 0.24 (use o/Sy = 0.5) d = (7.125)v2 = 2.67 I

hk = 1.52 The stress intensity factor, Kw, is M.

• a:

Ka = 2.57

• 15276 = 39259 psid = 39.3 ksid Equation (B-1) can be rearranged, and 1.5'Kw substituted for Km, to solve for (T - RTsm):

(T - RTxm) = In[(1.5 *Kw - 26.78)/1.223]/0.0145 - 160 (T - RTmyr) = In[(1.5*39.3 - 26.78)/1.223]/0.0145 - 160 (T - RTmyr) = 65'F l

Adding the adjusted RTmyr for 17 EFPY of 138'F:

T = 203*F l

B.4 EXAMPLE CALCULATION - 17 EFPY HEATUP/COOLDOWN CURVE AT 1000 PSIG The heatup/cooldown curve at 1000 psig uses the same Kw as the pressure test curve, but with a safety factor of 2.0 instead of 1.5. In addition, there is a Km term for the thermal stress.

The additional inputs used to calculate Kn are:

G = 100 F/hr C = 7.34 inches, including clad thickness 2

= 0.354 ft /hr at 550 F (most conservative value)

B-5

1 Equation B-4 can be solved for the through-wall temperature (r-C), resulting in the absolute value of AT for heatup or cooldown of AT = GC2/2 For the values above, AT = 52.8'F.

The analyzed case for thermal stress is a 1/4 T flaw depth with wall thickness of 7.34 inches.

From ASME Appendix G Figure G-2214-2, the corresponding value ofM is M = 012 Thus the thermal stress intensity factor, Ka = M

• AT, is calculated to be  ;

1 Ka = 16.9 ksid l

i The pressure and thermal stress terms are substituted into Equation B-1 to solve for (T - RTer):

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(T - RTer) = In[((2.0*39.2 + 16.9) - 26.78)/1.223]/0.0145 - 160 (T - RTer) = 118'F j Adding the adjusted RTer for 17 EFPY of 138'F:

T = 256*F l

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Ngure B-1. Boundary Conditions for Heatup/Cooldown Temperature l

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APPENDIX C IMPACT ON P-T CURVES OF IIEATUP/COOLDOWN RATE l

Given the form of the equation by which AT is determined, the heatup/ccoldown rate of 100 F/hr for brittle fracture purposes refers to an instantaneous rate. Instantaneous rates in excess of 100 F/hr are allowed for in the Technical Specification, as long as a temperature change of 100 F in a one hour period is not exceeded. This is based on the fact that the 1/4 T location of the assumed flaw sees little if any effect of small perturbations in the 100 F/hr rate, due to the I thermal inertia of the vessel wall. It is understood in this Tech Spec allowance that operators will track vessel coolant heatup or cooldown to stay as close to a 100 F/hr rate as possiole. l i

The method of calculating Ka in Appendix B can be used to conservatively adjust the P-T  ;

curves for higher heatup/cooldown rates. While it is expected that short periods of excessive I i

rates will not affect the 1/4 T location, a conservative approach is to increase the thermal K l

proportionally to the increased rate. Thus, for a 200 F/hr heatup or cooldown, Kawould double. j l

The calculation of beltline P-T limits was modified to include a 200 F/hr heatup/cooldown rate. The resulting P-T curve for 17 EFPY of operation is shown in Figure C-1. The non-beltline I limits are not changed because they are based on more severe transient conditions at the I discontinuities. In cases where the vessel coolant instantaneous heatup or cooldown rate, as j measured by the steam dome pressure, exceeds 100 F/hr but is less than 200*F/hr, Figure C-1 can be used to assure that vessel P-T requirements have not been exceeded.

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