L-08-327, Pressure and Temperature Limits Report, Revision 3
| ML082900491 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 10/14/2008 |
| From: | Sena P FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-08-327 | |
| Download: ML082900491 (32) | |
Text
FENOC FirstEnergy Nuclear Operating Company Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 Peter P. Sena III Site Vice President 724-682-5234 Fax: 724-643-8069 October 14, 2008 L-08-327 Beaver Valley Power Station Technical Specification 5.6.4 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001
SUBJECT:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Unit No. 2 Pressure and Temperature Limits Report, Revision 3 FirstEnergy Nuclear Operating Company (FENOC) hereby submits a revision of the Pressure and Temperature Limits Report (PTLR) for Beaver Valley Power Station (BVPS) Unit No. 2 as required by Section 5.6.4 of the BVPS Technical Specifications.
Revision 3 of the BVPS Unit No. 2 PTLR is enclosed.
The revision to the Unit No. 2 PTLR, effective October 9, 2008, was made to include the results of the Capsule X analysis documented in WCAP-16527-NP and WCAP-165127-NP, Supplement 1.
There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -
FENOC Fleet Licensing, at 330-761-6071.
Peter P. Sena III Enclosure Beaver Valley Power Station Unit No. 2, Pressure and Temperature Limits Report, Revision 3
-A 0(0
Beaver Valley Power Station, Unit No. 2 L-08-327 Page 2 cc:
Mr. S. J. Collins, NRC Region I Administrator Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRR Project Manager Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)
Beaver Valley Power Station Unit No. 2 Pressure and Temperature Limits Report Revision 3
Licensing Requirements Manual 5.0 ADMINISTRATIVE CONTROLS 5.2 Pressure and Temperature Limits Report Pressure and Temperature Limits Report 5.2 BVPS-2 Technical Specification to PTLR Cross-Reference Technical PTLR Specification Section Figure Table 3.4.3 5.2.1.1 5.2-1 N/A 5.2-2 5.2-3 5.2-4 5.2-5 5.2-6 3.4.6 N/A N/A 5.2-3 3.4.7 N/A N/A 5.2-3 3.4.10 N/A N/A 5.2-3 3.4.12 5.2.1.2 5.2-8 5.2-3 5.2.1.3 3.5.2 N/A N/A 5.2-3 BVPS-2 Licensing Requirement to PTLR Cross-Reference Licensing PTLR Requirement Section Figure Table LR 3.1.2 N/A N/A 5.2-3 LR 3.1.4 N/A N/A 5.2-3 LR 3.4.6 N/A N/A 5.2-3 PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-i
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report 5.2 Reactor Coolant System (RCS) Pressure. and Temperature Limits Report (PTLR)
The PTLR for Unit 2 has been prepared in accordance with the requirements of Technical Specification 5.6.4. Revisions to the PTLR shall be provided to the NRC after issuance.
The Technical Specifications (TS) and Licensing Requirements (LR) addressed, or made reference to, in this report are listed below:
- 1.
LCO 3.4.3 Reactor Coolant System Pressure and Temperature (P/T)
- Limits,
- 2.
- 3.
LCO 3.4.7 RCS Loops - MODE 5, Loops Filled,
- 4.
LCO 3.4.10 Pressurizer Safety-Valves,
- 5.
LCO 3.4.12 Overpressure Protection System (OPPS),
- 6.
- 7.
LR 3.1.2 Boration Flow Paths - Operating,
- 8.
LR 3.1.4 Charging Pump - Operating, and
- 9.
LR 3.4.6 Pressurizer Safety Valve Lift Involving Loop Seal or Water Discharge 5.2.1 Operatinq Limits The PTLR limits for Beaver Valley Power Station (BVPS) Unit 2 were developed using a methodology specified in the Technical Specifications. The methodology listed in Reference 1 was used with two exceptions:
a)
Use of ASME Code Case N-640, "Alternative Reference Fracture Toughness for Development of P-T Limits for Section XI, Division 1," and b)
Use of methodology of the 1996 version of ASME Section XI, Appendix G, "Fracture Toughness Criteria for Protection Against Failure."
5.2.1.1 RCS Pressure and Temperature (P/T) Limits (LCO 3.4.3)
The RCS temperature rate-of-change limits defined in Reference 2 are:
- a.
A maximum heatup of 60°F in any one hour period.
- b.
A maximum cooldown of 100"F in any, one hour period, and PTLR Revision 3 Beaver Valley Unit 2 5.2 - 1 LRM Revision 62
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report
- c.
A maximum temperature change of less than or equal to 5°F in any one hour period during inservice hydrostatic testing operations above system design pressure.
The RCS P/T limits for heatup, leak testing, and criticality are specified by Figure 5.2-1 and Table 5.2-1. The RCS P/T limits for cooldown are shown in Figures 5.2-2 through 5.2-6 and Table 5.2-2. These limits are defined in Reference 2. Consistent with the methodology described in Reference 1, including the exceptions as noted in Section 5.2.1, the RCS P/T limits for heatup and cooldown shown in Figures 5.2-1 through 5.2-6 are provided without margins for instrument error. The criticality limit curve specifies pressure-temperature limits for core operation to provide additional margin during actual power production as specified in 10 CFR 50, Appendix G. The heatup and cooldown curves also include the effect of the reactor vessel flange.
The P/T limits for core operation (except for low power physics testing) are that the reactor vessel must be at a temperature equal to or higher than the minimum temperature required for the inservice hydrostatic test, and at least 40°F higher than the minimum permissible temperature in the corresponding P/T curve for heatup and cooldown.
Pressure-temperature limit curves shown in Figure 5.2-7 were developed for the limiting ferritic steel component within an isolated reactor coolant loop. The limiting component is the steam generator channel head to tubesheet region.
This figure provides the ASME Ill, Appendix G limiting curve which is used to define operational bounds, such that when operating with an isolated loop the analyzed pressure-temperature limits are known. The temperature range provided bounds the expected operating range for an isolated loop and Code Case N-640.
Figures 5.2-1 thru 5.2-6 and Tables 5.2-1 and 5.2-2 are based upon analysis of Capsule W per Reference 2. The tables and curves generated as a result of the Capsule X analysis (Reference 12) and presented in Reference 14 are conservative with respect to those for the Capsule W analysis. As a result, while Tables 5.2-5, 5.2-8, and 5.2-9 are updated with Capsule X fluence data and ART calculations, the pressure-temperature limits provided in Tables 5.2-1 and 5.2-2 and Figures 5.2-1 thru 5.2-6 continue to reflect Capsule W values through 22 EFPY and are bounding.
5.2.1.2 Overpressure Protection System (OPPS) Setpoints (LCO 3.4.12)
The power operated relief valves (PORVs) shall each have a nominal maximum lift setting that varies with RCS temperature and which does not exceed the limits in Figure 5.2-8 (Reference 11). The OPPS enable temperature is in accordance with Table 5.2-3. The PORV lift setting provided is for the case with reactor coolant pump (RCP) restrictions. These restrictions are shown in Table 5.2-4, which is taken from Reference 9. Due to the setpoint limitations as a result of the PTLR Revision 3 Beaver Valley Unit 2 5.2 - 2 LRM Revision 62
Licensing RequirementsManual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report reactor vessel flange requirements, there is no operational benefit achieved by restricting the number of RCPs running to less than two below an indicated RCS temperature of 1370F. Therefore, the PORV setpoints shown in Table 5.2-3 will protect the Appendix G limits for the combinations shown.
The PORV setpoint is based on P/T limits which were established in accordance with 10 CFR 50, Appendix G without allowance for instrumentation error and in accordance with the methodology described in Reference 1, including the exceptions noted in Section 5.2.1. The PORV lift setting shown in Figure 5.2-8 accounts for appropriate instrument error.
5.2.1.3 OPPS Enable Temperature (LCO 3.4.12)
Two different temperatures are used to determine the OPPS enable temperature, they are the arming temperature and the calculated enable temperature. The arming temperature (when the OPPS rendered operable) is established per ASME Section XI, Appendix G. At this temperature, a steam bubble would be present in the pressurizer, thus reducing the potential of a water hammer discharge that could challenge the piping limits. Based on this method, the arming temperature with uncertainty is 2370F.
The calculated enable temperature is based on either a RCS temperature of less than 200OF or materials concerns (reactor vessel metal temperature less than RTNDT + 50 0F), whichever is greater. The calculated enable temperature does not address the piping limit attributed to a water hammer discharge. The calculated enable temperature is 2400F.
As the calculated enable temperature is higher and, therefore, more conservative than the arming temperature, the OPPS enable temperature, as shown in Table 5.2-3, is set to equal the calculated enable temperature.
The calculation method governing the heatup and cooldown of the RCS requires the arming of the OPPS at and below the OPPS enable temperature specified in Table 5.2-3, and disarming of the OPPS above this temperature. The OPPS is required to be enabled, i.e., OPERABLE, when any RCS cold leg temperature is less than or equal to this temperature.
The OPPS enable temperature, PORV setpoints, and RCP operating restrictions contained in Tables 5.2-3 and 5.2-4 and Figure 5.2-8 are as described in Reference 2, and are based upon analysis of Capsule.W. The pressure-temperature limits provided in Reference 14 for Capsule X and setpoints evaluation per Reference 15 support the continued use of these existing OPPS/PORV setpoints and RCP operating restrictions for the period up to 22 EFPY. As a result, Tables 5.2-3 and 5.2-4 and Figure 5.2-8 continue to reflect Capsule W values and remain valid for Capsule X up to 22 EFPY.
PTLR Revision 3 Beaver Valley Unit 2 5.2 - 3 LRM Revision 62
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report From a plant operations viewpoint the terms "armed" and "enabled" are synonymous when it comes to activating the OPPS. As stated in the applicable operating procedure, the OPPS is activated (armed/enabled) manually before entering the applicability of LCO 3.4.12. This is accomplished by placing two switches (one in each train) into their "ARM" position. Once OPPS is activated (armed/enabled) reactor coolant system pressure transmitters will signal a rise in system pressure above the variable OPPS setpoint. This will initiate an alarm in the control room and open the OPPS PORVs.
5.2.1.4 Reactor Vessel Boltup Temperature (LCO 3.4.3)
The minimum boltup temperature for the Reactor Vessel Flange shall be _> 60 0F.
Boltup is a condition in which the reactor vessel head is installed with tension applied to any stud, and with the RCS vented to atmosphere.
5.2.2 Reactor Vessel Material Surveillance Proqram The reactor vessel material irradiation surveillance specimens shall be removed and analyzed to determine changes in material properties. The capsule withdrawal schedule is provided in Table 5.3-6 of the UFSAR. Also, the results of these analyses shall be used to update Figures 5.2-1 through 5.2-6, and Tables 5.2-1 and 5.2-2 in this report. The time of specimen withdrawal may be modified to coincide with those refueling outages or reactor shutdowns most closely approaching the withdrawal schedule.
The pressure vessel material surveillance program (References 3 and 4) is in compliance with Appendix H to 10 CFR 50, "Reactor Vessel Radiation Surveillance Program." The material test requirements and the acceptance standards utilize the reference nil-ductility temperature, RTNDT, which is determined in accordance with ASME,Section III, NB-2331. The empirical relationship between RTNDT and the fracture toughness of the reactor vessel steel is developed in accordance with Appendix G, "Protection Against Non-Ductile Failure," to Section Xl of the ASME Boiler and Pressure Vessel Code. The surveillance capsule removal schedule meets the requirements of ASTM E 185-82.
Reference 10 is an NRC commitment made by FENOC to use only the calculated vessel fluence values when performing future capsule surveillance evaluations for, BVPS Unit 2. This commitment is a condition of License Amendment 138 and will remain in effect until the NRC staff approves an alternate methodology to perform these evaluations. Best-estimate values generated using the FERRET Code may be provided for information only.
PTLR Revision 3 Beaver Valley Unit 2 5.2 - 4 LRM Revision 62
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report 5.2.3 Supplemental Data Tables The following tables provide supplemental information on reactor vessel material properties and are provided to be consistent with Generic Letter 96-03. Some of the material property values'shown were used as inputs to the P/T limits.
Table 5.2-5, taken from Table 2-4 of Reference 14, shows the calculation of the surveillance material chemistry factors using surveillance capsule data.
Table 5.2-6, taken from Table 2-1 of Reference 14, provides the reactor vessel beltline material property table.
Table 5.2-7, taken from Table 2-2 of Reference 14, provides the reactor vessel extended beltline material property table.
Table 5.2-8, taken from Tables 4-5 and 4-6 of Reference 14, provides a summary of the Adjusted Reference Temperature (ARTs) for 22 EFPY.
Table 5.2-9, taken from Tables 4-5 and 4-6 of Reference 14, shows the calculation of ARTs for 22 EFPY.
Table 5.2-10, taken from Table 6 of Reference 5, provides RTPTS values for 32 EFPY.
Table 5.2-11, taken from Table 7 of Reference 13, provides RTPTS values for the Beltline Region Materials at 54 EFPY.
Table 5.2-12, taken from Table 8 of Reference 13, provides RTPTS values for the Extended Beltline Region Materials at 54 EFPY.
Note that Tables 5.2-5, 5.2-8 and 5.2-9 have been updated to reflect Capsule X analysis and fluence data. This data has not, however, been incorporated into the pressure-temperature limits provided in Figures 5.2-1 thru 5.2-6 and Tables 5.2-1 and 5.2-2, which continue to reflect Capsule W analyses. See Section 5.2.1.1 for additional information.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-5
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report 5.2.4 References
- 1.
WCAP-14040-NP-A, Revision 2, "Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Limit Curves," J. D. Andrachek, et al., January 1996.
- 2.
"WCAP-1 5677, "Beaver Valley Unit 2 Heatup and Cooldown Limit Curves for Normal Operation," J. H. Ledger, August 2001.
- 3.
WCAP-1 5675, Revision 0, "Analysis of Capsule W from First Energy Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," J. H. Ledger, S. L. Anderson, J. Conermann, August 2001.
- 4.
WCAP-9615, Revision 1, "Duquesne Light Company, Beaver Valley Unit No. 2 Reactor Vessel Radiation Surveillance Program," P. A. Peter, June 1995.
- 5.
WCAP-1 5676, "Evaluation of Pressurized Thermal Shock for Beaver Valley Unit 2," J. H. Ledger, August 2001.
- 6.
10 CFR Part 50, Appendix G, "Fracture Toughness Requirements," Federal Register, Volume 60, No. 243, December 19, 1995.
- 7.
10 CFR 50.61, "Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events," May 15, 1991. (PTS Rule)
- 8.
Regulatory Guide 1.99, Rev. 2, "Radiation Embrittlement of Reactor Vessel Materials," U.S. Nuclear Regulatory Commission, May 1988.
- 9.
FENOC Calculation No. 10080-SP-2RCS-006, Revision 4, Addendum 0, "BV-2 LTOPS Setpoint Evaluation Capsule W for 22 EFPY."
- 10.
FirstEnergy Nuclear Operating Company letter L-01-157, "Supplement to License Amendment Requests Nos. 295 and 167," dated December 21, 2001.
- 11.
Westinghouse Letter FENOC-04-31, dated April 14, 2004, "LTOPS Setpoint Evaluation for Beaver Valley Unit 2 Capsule W for 22 EFPY - Calculation Note."
- 12.
WCAP-16527, Revision 0, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," B. N. Burgos, J. Conermann, S. L. Anderson, March 2006.
- 13.
WCAP-16527, Supplement 1, Revision 0, "Analysis of Capsule X from FirstEnergy Nuclear Operating Company Beaver Valley Unit 2 Reactor Vessel Radiation Surveillance Program," B. N. Burgos, July 2007.
PTLR Revision 3 Beaver Valley Unit 2 5.2 - 6 LRM Revision 62
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 5.2 Pressure and Temperature Limits Report
- 14.
WCAP-16528, Revision 1, "Beaver Valley Unit 2 Heatup andCooldown Limit Curves for Normal Operation," June 2008.
- 15.
Westinghouse Letter FENOC-07-92, dated June 8, 2007, LTOPS Setpoint Evaluation for Beaver Valley Unit 2 Capsule X at 22 and 30 EFPY.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-7
Licensing Requirements Manual MATERIAL PROPERTY BASIS LIMITING MATERIAL:
LIMITING ART VALUES AT 22 EFPY:
CURVES APPLICABLE FOR HEATUP PERIOD UP TO 22 EFPY.
Pressure and Temperature Limits Report 5.2 INTERMEDIATE SHELL PLATE B9004-1 1/4T, 140°F 3/4T, 129°F RATES UP TO 60°F/HR FOR THE SERVICE 2500 2250 2000 1750
"" 1500 W 1250 W
< 1000 Z
750 500 250 0
0 50 100 1502 00 2503 00 3504 00 450 500 INDICATED TEMPERATURE (OF)
Figure 5.2-1 (Page 1 of 1)
Reactor Coolant System Heatup Limitations Applicable for the First 22 EFPY (LCO 3.4.3)
NOTE: Values based upon analysis of Capsule W for 22 EFPY and are bounding for Capsule X at 22 EFPY (see Section 5.2.1.1). As a result, ART values shown do not coincide with Tables 5.2-7 and 5.2-8.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-8
Licensing Requirements Manual MATERIAL PROPERTY BASIS Pressure and Temperature Limits Report 5.2.
LIMITING MATERIAL: -
INTERMEDIATE SHELL PLATE B9004-1 LIMITING ART VALUES AT 22 EFPY:
1/4T, 140'F 3/4T, 129°F CURVE APPLICABLE FOR COOLDOWN RATES UP TO 0°F/HR FOR THE SERVICE PERIOD UP TO 22 EFPY.
2500 TO
-i 2250 Unacceptable Operation 2000 Acceptable O peration 1750 a..
W 1500 W 1250 W
a-0w 1000 750 500 250 0
0 50 100 15020 0
25030 035 04 0045 0500 INDICATED TEMPERATURE (OF)
Figure 5.2-2 (Page 1 of 1)
Reactor Coolant System Cooldown (up to 0°F/Hr.)
Limitations Applicable for the First 22 EFPY (LCO 3.4.3)
NOTE: Values based upon analysis of Capsule W for 22 EFPY and are bounding for Capsule X at 22 EFPY (see Section 5.2.1.1). As a result, ART values shown do not coincide with Tables 5.2-7 and 5.2-8.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-9
Licensing Requirements Manual MATERIAL PROPERTY BASIS Pressure and Temperature Limits Report 5.2 LIMITING MATERIAL:
INTERMEDIATE SHELL PLATE B9004-1 LIMITING ART VALUES AT 22 EFPY:
1/4T, 140°F 3/4T, 1290F CURVE APPLICABLE FOR COOLDOWN RATES UP TO 20°F/HR FOR THE SERVICE PERIOD UP TO 22 EFPY.
2500 2250 unacceptabl Operation Acceptable 2000 Operation 170 -
a--
uJ 1500 SCooldown Rate 20°F/Hr.
UJ 70 1...
I - 1 0 75 0..
0 50 100 15020 0
2503 0035 04 0045 050 0
INDICATED TEMPERATURE (°F)
Figure 5.2-3 (Page 1 of 1)
Reactor Coolant System Cooldown (up to 20°F/Hr.)
Limitations Applicable for the First 22 EFPY (LCO 3.4.3)
NOTE: Values based upon analysis of Capsule W for 22 EFPY and are bounding for Capsule X at 22 EFPY (see Section 5.2.1.1). As a result, ART values shown do not coincide with Tables 5.2-7 and 5.2-8.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-10
Licensing Requirements Manual MATERIAL PROPERTY BASIS Pressure and Temperature Limits Report 5.2 LIMITING MATERIAL:
INTERMEDIATE SHELL PLATE B9004-1 LIMITING ART VALUES AT 22 EFPY:
1/4T, 140'F 3/4T, 129°F CURVE APPLICABLE FOR COOLDOWN RATES UP TO 40°F/HR FOR THE SERVICE PERIOD UP TO 22 EFPY.
2500 2250 Unacceptable
- Operation 2000.......
1750 0.
W 1500 W 1250 a.
w 1-1000 750 500 250 0
i/
[
Acceptable L
Operation CCooldown Rate 4O0FIHr.
I 0
50 100 15020 0
25030 035 04 0045 0500 INDICATED TEMPERATURE (OF)
Figure 5.2-4 (Page 1 of 1)
Reactor Coolant System Cooldown (up to 400F/Hr.)
Limitations Applicable for the First 22 EFPY (LCO 3.4.3)
NOTE: Values based upon analysis of Capsule W for 22 EFPY and are bounding for Capsule X at 22 EFPY (see Section 5.2.1.1). As a result, ART values shown do not coincide with Tables 5.2-7 and 5.2-8.
PTLR Revision-3 LRM Revision 62 Beaver Valley Unit 2 5.2-11
Licensing Requirements Manual MATERIAL PROPERTY BASIS Pressure and Temperature Limits Report 5.2 LIMITING MATERIAL:
INTERMEDIATE SHELL PLATE B9004-1 LIMITING ART VALUES AT 22 EFPY:
1/4T, 140'F 3/4T, 129 0F CURVE APPLICABLE FOR COOLDOWN RATES UP TO 60°F/HR FOR THE SERVICE PERIOD UP TO 22 EFPY.
2500 2250-Unacceptable Operation 7
Acceptable 2000-L.
Operation 17500 Uf)
Cooldown Rate 60 F/Hr.
WJ 1250 I-1000 7 7
750 500 Boltup Temperature 2 0 20 0
50 100 15020 0
25030 035 04 0045 0500 INDICATED TEMPERATURE (OF)
Figure 5.2-5 (Page 1.of 1)
Reactor Coolant System Cooldown (up to 60°F/Hr.)
Limitations'Applicable for the First 22 EFPY (LCO 3.4.3)
NOTE: Values based upon analysis of Capsule W for 22 EFPY and are bounding for Capsule X at 22 EFPY (see Section 5.2.1.1). As a result, ART values shown do not coincide with Tables 5.2-7 and 5.2-8.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-12
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 MATERIAL PROPERTY BASIS LIMITING MATERIAL:
,INTERMEDIATE SHELL PLATE B9004-1 LIMITING ART VALUES AT 22 EFPY:
1/4T, 140°F 3/4T, 1290F CURVE APPLICABLE FOR COOLDOWN RATES UP TO 100°F/HR FOR THE SERVICE PERIOD UP TO 22 EFPY.
2500 2250
-Unacceptable Operation Acceptable 2000 Operation 1750-U) 15 Cooldown Rate 100'F/Hr.
U 1750 500 Boltup Temperature 250-0t
--... *.ol wr ra e
u r-n.I 0
50 100 15020 0
25030 035 04 0045 0500 INDICATED TEMPERATURE (OF)
Figure 5.2-6 (Page 1 of 1)
Reactor Coolant System Cooldown (up to 100°F/Hr.)
Limitations Applicable for the First 22 EFPY (LCO 3.4.3)
NOTE: Values based upon analysis of Capsule W for 22 EFPY and are bounding for Capsule X at 22 EFPY (see Section 5.2.1.1). As a result, ART values shown do not coincide with Tables 5.2-7 and 5.2-8.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-13
Licensing Requirements Manual 2500 2000 0-1500 a-D LU CL 500 U0 03 500 Pressure and Temperature Limits Report 5.2 50 60 70 80 90 100 110 TEMPERATURE (F) 120 Figure 5.2-7 (Page 1 of 1)
Isolated Loop Pressure - Temperature Limit Curve (LCO 3.4.3)
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-14
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 See Table 5.2-4 for RCP restrictions.
750 700 I-z 0
650 I-w 0
a.
600 z
0z w
uJ
._1
< 550 0-J_J 500 x
a.
o0 450 400 0
100 200 300 400 TRTD-AUCTIONEERED LOW-MEASURED RCS TEMPERATURE (°F)
Figure 5.2-8 (Page 1 of 1)
Maximum Allowable Nominal PORV Setpoint for the Overpressure Protection System (LCO 3.4.12)
NOTE: Data shown reflects analysis for Capsule W thru 22 EFPY and is the same or bounding for Capsule X thru 22 EFPY (See Section 5.2.1.3).
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-15
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-1 (Page 1 of 1)
Heatup Curve Data Points for 22 EFPY (LCO 3.4.3) 60°F/HR HEATUP 60°F/HR CRITICALITY LEAK TEST LIMIT Temp.
Press.
Temp.
Press.
Temp.
Press.
(OF)
(psig)
(OF)
(psig)
(OF)
(psig) 60 0
196 0
178 2000 60 621 196 621 196 2485 65 621 196 621 70 621 196 621 75 621 196 621 80 621 196 621 85 621 196 621 90 621 196 621 95 621 196 621 100 621 196 621 105 621 196 621 110 621 196 621 115 621 196 621 120 621 196 779 120 621 196 799 120 779 196 821 125 799 196 846 130 821 196 874 135 846 196 905 140 874 196 940 145 905 196 978 150 940 200 1021 155 978 205 1068 160 1021 210 1120 165 1068 215 1178 170 1120 220 1242 175 1178 225 1312 180 1242 230 1390 185 1312 235 1476 190 1390 240 1571 195 1476 245 1675 200 1571 250 1791 205 1675 255 1919 210 1791 260 2060 215 1919 265 2215 220 2060 270 2387 225 2215 230 2387 NOTE: Data shown reflects analysis for Capsule W thru 22 EFPY and is the same or bounding for Capsule X thru 22 EFPY (See Section 5.2.1.3).
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-16
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-2 (Page 1 of 1)
Cooldown Curve Data Points for 22 EFPY (LCO 3.4.3) 0°F/HR 20°F/HR 40°F/HR 60°F/HR 100°F/HR Temp.
Press.'
Press.
Press.
Press.
Press.
(OF)
(psig)
(psig)
(psig)
(psig)
(psig) 60 0
0 0
0 0
60 621 621 621 608 532 65 621 621 621 618 544 70 621 621 621 621 557 75 621 621 621 621 572 80 621 621 621 621 588 85 621 621 621 621 606 90 621 621 621 621 621 95 621 621 621 621 621 100 621 621 621 621 621 105 621 621 621 621 621 110 621 621 621 621 621 115 621 621 621 621 621 120 621 621 621 621 621 120 621 621 621 621 621 120 907 884 862 842 807 125 935 914 895 877 849 130 966 948 932 917 897 135.
1001 985 972 961 949 140 1039 1026 1017 1010 1007 145 1081 1072 1066 1064 1071 150 1127 1122 1121 1123 1127 155 1179 1178 1179 1179 1179 160 1235 1235 1235 1235 1235 165 1298 1298 1298 1298 1298 170 1367 1367 1367 1367 1367 175 1444 1444 1444 1444 1444 180 1528 1528 1528 1528 1528 185 1622 1622 1622 1622 1622 190 1725 1725 1725 1725 1725 195 1839 1839 1839 1839 1839 200 1966 1966 1966 1966 1966 205 2105 2105 2105 2105 2105 210 2259 2259 2259 2259 2259 215 2430 2430 2430 2430 2430 NOTE: Data shown reflects analysis for Capsule W thru 22 EFPY and is the same or bounding for Capsule X thru 22 EFPY (See Section 5.2.1.3).
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-17
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-3 (Page 1 of 1)
Overpressure Protection System (OPPS) Setpoints (LCO 3.4.12)
FUNCTION SETPOINT OPPS Enable Temperature 240°F PORV Setpoint Figure 5.2-8 NOTE: Data shown reflects analysis for Capsule W thru 22 EFPY and is the same or bounding for Capsule X thru 22 EFPY (See Section 5.2.1.3).
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-18
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-4 (Page 1 of 1)
Reactor Coolant Pump Restrictions TRCS Running RCPs
< 137°F 0-2
_> 1370F 3
NOTE: Data shown reflects analysis for Capsule W thru 22 EFPY and is the same or bounding for Capsule X thru 22 EFPY (See Section 5:2.1.3).
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2-19
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-5 (Page 1 of 1)
Calculation of Chemistry Factors Using Surveillance Capsule Data(a)
Material Capsule Capsule f(b)
FF(c)
ARTNDT(d)
FF*ARTNDT FF 2 Intermediate U
0.608 0.861 24.0 20.66 0.741 Shell Plate V
2.629 1.259 56.0 70.50 1.585 B9004-2 W
3.625 1.335 71.0 94.79 1.782 (Longitudinal)
X 5.601 1.424 98.0 139.55 2.028 Intermediate U
0.608 0.861 17.7 15.24 0.741 Shell Plate V
2.629 1.259 46.1 58.04 1.585 B9004-2 W
3.625 1.335 63.4 84.64 1.782 (Transverse)
X 5.601 1.424 104.1 148.24 2.028 SUM:
631.66 12.272 CF = Y,(FF*RTNDT) + E(FF 2) = 51.5°F U
0.608 0.861 4.1(e) 3.53 0.741 Surveillance V
2.629 1.259 25.7(e) 32.36 1.585 Weld Metal 83642 W
3.625 1.335 6.0(e) 8.01 1.782 X
5.601 1.424 22.9(e) 32.61 2.028 SUM:
76.51 6.136 CF = E(FF*RTNDT) + E(FF 2) = 12.5°F Notes:
(a) Regulatory Guide 1.99, Revision 2, Position 2.1.
(b) f = fluence (1019 n/cm 2); Fluence values were taken from Capsule W analysis (Reference 12).
(c) FF = fluence factor = f (0.28- 0.1
- log (d)
ARTNDT values are the measured 30 ft-lb. shift values for BVPS-2 taken from Reference 12.
(e) The surveillance weld metal ARTNDT values have been conservatively adjusted by a ratio factor of 1.0; the calculated ratio was 0.905, which would result in a lower calculated CF.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2 -20
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-6 (Page 1 of 1)
Reactor Vessel Beltline Material Properties Cu Ni Initial RTNDT Material (wt%)
(wt%)
(F)(a)
Closure Head Flange B9002-1 0.0 6 (b) 0.74
-10 Vessel Flange B9001-1 0.0 6 (5) 0.73 0
Intermediate Shell Plate B9004-1 0.065 0.55 60 Intermediate Shell Plate B9004-2 0.06 0.57 40 Lower Shell Plate B9005-1 0.08 0.58 28 Lower Shell Plate B9005-2 0.07 0.57 33 Intermediate to Lower Shell Weld 101-171 (Heat 83642) 0.046 0.086
-30 Intermediate Longitudinal Weld 101-124 A & B (Heat 83642) 0.046 0.086
-30 Lower Longitudinal Weld 101-142 A & B (Heat 83642) 0.046 0.086
-30 Plate Surveillance Material B9004-2 0.06 0.57 40 Surveillance Weld (Heat 83642) 0.065 0.065
-30(0)
Notes:
(a)
The initial RTNDT values for all of the beltline materials are based on measured data.
(b)
According to the BVPS-2 reactor vessel CMTRs and MISC-PENG-ER-021, the material for the closure head flange (B9002-1) and vessel flange (B9001-1) forgings are ASTM A508 Class 2. The ASTM A508 material specification does not require analysis of copper content. The importance of copper content in the irradiation embrittlement of ferritic pressure vessel steel was not recognized or regulated by the NRC or nuclear steam supply system (NSSS) vendors when the BVPS-2 reactor vessel was constructed. Even though the material specification did not require analysis of copper content for ASTM A508 Class 2 material, check analyses on chemistry measurements (including copper) were reported in MISC-PENGER-021. The copper values reported for both the closure head flange (B9002-1) and the vessel flange (B9001-1) was 0.06%.
(c)
The initial RTNDT value is determined in accordance with the requirements of Subparagraph NB-2331 of Section III of the ASME B&PV Code, as specified by Paragraph II - D of 10 CFR Part 50, Appendix G. These fracture toughness requirements are also summarized in Branch Technical Position MTEB Section 11.5-2 ("Fracture Toughness") of the NRC Regulatory Standard Review Plan. Following these requirements, along with the Charpy data reported in Table 3-3 of WCAP-9615 and the TNDT value of
-30°F defined on page 3-14 of WCAP-9615, the initial RTNDT value is concluded to be equal to TNDT (i.e., -30.0°F).
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2 -21
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-7 (Page 1 of 1)
Reactor Vessel Extended Beltline Material Properties (a)
Material Material Heat Number Wt %
Wt%
Initial RTNDT Description ID Cu Ni B9003-1 A9406-1 0.13 0.60 50 Upper Shell B9003-2 B4431-2 0.12 0.60 60 B9003-3 A9406-2 0.13 0.60 50 51912 (3490) 0.156 0.059
-50 51912 (3536) 0.156 0.059
-70 Upper Shell 101-122B EAIB 0.02 0.98 10 (Gen)
Longitudinal Welds 101-122C IAGA 0.03 0.98
-30 BOHB 0.05 1.00 10 (Gen)
BAOED 0.02 1.00
-50 4P5174(1122) 0.09 1.00
-50 perme Shell t2 51922 (3489) 0.05 1.00
-56 (Gen)
Intermediate Shell 103-121 AG
.3 09 7
Girth Weld AAGC 0.03 0.98
-70 KOIB 0.03 0.97
-60 B9011-1 2V2436-01-002 0.11 0.85 60 Inlet Nozzles B9011-2 2V2437-02-001 0.13 0.88 60 (Gen)
B9011-3 2V2445-02-003 0.13 0.84 70 4P5174 (1122) 0.09 1.00
-50 LOHB 0.03 1.03
-60 HABJC 0.02 1.02
-70 BABBD 0.02 1.04
-70 10-2AFABGC 0.03 1.02
-80 Inlet Nozzle Welds 105-121B EOBC 0.02 09
-60 1511CEOBC 0.02 0.96
-60 FAAFC 0.07 1.04
-60 CCJC 0.02 0.99
-60 FAGB 0.02 1.06
-30 BAOED 0.02 1.00
-50 B9012-1 AV8080-2E9558 0.13 0.72
-10 Outlet Nozzles B9012-2 AV8120-2E9560 0.13 0.74
-10 B9012-3 AV8097-2E9559 0.13 0.70
-10 BABBD 0.02 1.04
-70 FAAFC 0.07 1.04
-60 107-121A HAAEC 0.03 1.03
-80 Outlet Nozzle Welds 107-121B HABJC 0.02 1.02
-70 107-121C HAGB 0.02 1.04
-40 GACJC 0.03 1.00
-80 JAHB 0.03 0.97
-40 Notes:
(a) Materials information taken from Reference 13 (b)
Based on Reference 13, the generic Initial RTNDT values were determined in accordance with NUREG-0800 and the 10 CFR 50.61.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2 -22
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-8 (Page 1 of 1)
Summary of Adjusted Reference Temperature (ARTs) for 22 EFPY(a)
Method Used To MATERIAL, DESCRIPTION Calculate the CF(b) 22 EFPY ART 1/4T ART ('F) 3/4T ART ('F)
Intermediate Shell Plate B9004-1 Position 1.1 139 128 Intermediate Shell Plate B9004-2 Position 1.1 115 103 Position 2.1 114 101 Lower Shell Plate B9005-1 Position 1.1 119 105 Lower Shell Plate B9005-2 Position 1.1 116 104 Vessel Beltline Welds(c)
Position 1.1 47 29 Position 2.1
-2
-9 Notes:
(a)
Table updated to reflect Capsule X analysis per Reference 14; 1/4T and 3/4T ART values for B9004-1 will differ from as described on Figures 5.2-1 thru 5.2-6. See Section 5.2.1.1 for additional information.
(b)
Regulatory Guide 1.99, Revision 2.
(c)
All Beltline Welds are from Heat #83642, Linde 0091, Flux Lot #3536.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2 -23
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-9 (Page 1 of 1)
Calculation of Adjusted Reference Temperatures (ARTs) for 22 EFPY(a)
PARAMETER VALUES Operating Time 22 EFPY Material - Intermediate Shell Plate 89004-1 B9004-1 Location 1/4T 3/4T Chemistry Factor, CF (OF) 40.5 40.5 Fluence, (f), (1019 n/cm2)(b) 1.515 0.589 Fluence Factor, FF 1.115 0.852 ARTNDT = CF x FF(°F) 45.16 34.50 Intitial RTNDT, 1(°F) 60 60 Margin, M(°F) 34 34 ART, per Regulatory Guide 1.99, Revision 2 139 128 Notes:
(a)
Table updated to reflect Capsule X analysis per Reference 14; 1/4T and 3/4T ART values for B9004-1 will differ from as described on Figures 5.2-1 thru 5.2-6. See Section 5.2.1.1 for additional information.
(b)
Fluence (f), is based upon fsuf (1019 n/cm2, E > 1.0 MeV) = 2.43 at 22 EFPY. The Beaver Valley Unit 2 reactor vessel wall thickness is 7.875 inches at the beltline region.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2 -24
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-10 (Page 1 of 1)
RTPTS Calculation for Beltline Region Materials at EOL (32 EFPY)
Material Method f (a)
FF(b)
CF A RTPTS Margin RTNDT(U) (C)
RTPTs Fluence (OF)
(OF)
(OF)
(OF)
(OF)
Intermediate Shell Plate B9004-1 RG 1.99, R2, P1.1 3.847 1.348 40.5 54.6 34 60 149 Intermediate Shell Plate B9004-2 RG 1.99, R2, P1.1 3.847 1.348 37.0 49.9 34 40 124 RG 1.99, R2, P2.1 3.847 1.348 41.9 56.5 17 40 114 Lower Shell Plate B9005-1 RG 1.99, R2, P1.1 3.847 1.348 51.0 68.7 34 28 131 Lower Shell Plate B9005-2 RG 1.99, R2, P1.1 3.847 1.348 44.0 59.3 34 33 126 Vessel Beltline Welds RG 1.99, R2, P1.1 3.847 1.348 34.4 46.4 46.4
-30 63 RG 1.99, R2, P2.1 3.847 1.348 10.6 14.3 14.3
-30
-1 Notes:
(a) f = peak clad/base metal interface fluence (1019 n/cm2, E>1.0 MeV) at 32 EFPY (450 fluence for longitudinal welds)
(b)
FF = f (0.28-0.10 logf)
(c)
RTNDT(U) values are measured values.
(d)
All Beltline Welds are from Heat #83642, Linde 0091, Flux Lot #3536.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2 -25
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-11 (Page 1 of 1)
RTPTS Calculation for Beltline Region Materials at Life Extension (54 EFPY)
Margin(c)
RTNDT(d)
RTpTS(e)
Material Ps (xl 0' 9 n/cm 2 FF(a)
CF (0F)
(F)
(0F)
(0F)
Pos.
E>1.0 MeV)
(OF)
(OF)
(OF)
(OF)
(OF)
Intermediate Shell Plate B9004-1 1.1 6.22 1.4429 40.5 58.4 34.0 60.0 152.4 1.1 6.22 1.4429 37.0 53.4 34.0 40.0 127.4 Intermediate Shell Plate B9004-2 2.1 6.22 1.4429 51.5 74.3 17.0 40.0 131.3 Lower Shell Plate B9005-1 1.1 6.29 1.4449 51.0 73.7 34.0 28.0 135.7 Lower Shell Plate B9005-2 1.1 6.29 1.4449 44.0 63.6 34.0 33.0 130.6 Lower Shell Longitudinal Welds 1.1 1.78 1.1584 34.4 39.8 39.8
-30.0 49.7 101-142 A&B (Heat 83642) 2.1 1.78 1.1584 12.5 14.5 14.5
-30.0
-1.0 Intermediate Shell Longitudinal 1.1 1.76 1.1554 34.4 39.7 39.7
-30.0 49.5 Weld 101-124 A&B (Heat 83642) 2.1 1.76 1.1554 12.5 14.4 14.4
-30.0
-1.1 Intermediate to Lower Shell Girth 1.1 6.24 1.4435 34.4 49.7 49.7
-30.0 69.3 Weld 101-171 (Heat 83642) 2.1 6.24 1.4435 12.5 18.0 18.0
-30.0
6.1 Notes
(a) FF = fluence factor= f (0.28-0.1 log(f))
(b) ARTPTS = CF *FF.
(c) M = 2 *(yi2 + GT2)1/2.
(d) Initial RTNDT values are measured values.
(e) RTPTS = Initial RTNDT + ARTPTS + Margin.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2 -26
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-12 (Page 1 of 2)
RTPTS Calculation for Extended Beltline Region Materials at Life Extension (54 EFPY)
Margin(c)
RTNDT(d)
RTPTS(e)
Material (xl 019 n/cm 2 FF(a)
(OF)
(OF)
(OF)
(OF)
(OF)
E>1.0 MeV)
Upper Shell Plate B9003-1 1.1 0.4920 0.8022 91.00 73.0 34.0 50.0 157.0 Upper Shell Plate B9003-2 1.1 0.4920 0.8022 83.00 66.6 34.0 60.0 160.6 Upper Shell Plate B9003-3 1.1 0.4920 0.8022 91.00 73.0 34.0 50.0 157.0 Upper Shell. Long Weld 51912-3490 1.1 0.4920 0.8022 73.71 59.1 56.0
-50.0 65.1 Upper Shell Long Weld 51912-3536 1.1 0.4920 0.8022 73.71 59.1 56.0
-70.0 45.1 Upper Shell Long Weld EAIB 1.1 0.4920 0.8022 27.00 21.7 40.3 10.0 72.0 Upper Shell Long Weld IAGA 1.1 0.4920 0.8022 41.00 32.9 32.9
-30.0 35.8 Upper Shell Long Weld BOHB 1.1 0.4920 0.8022 68.00 54.5 64.3 10 128.8 Upper Shell Long Weld BAOED 1.1 0.4920 0.8022 27.00 21.7 21.7
-50.0
-6.7 Upper to Inter Girth Weld 4P5174 1.1 0.5950 0.8546 122.00 104.3 56.0
-50.0 110.3 Upper to Inter Girth Weld 51922 1.1 0.5950 0.8546 68.00 58.1 65.5
-56.0 67.6 Upper to Inter Girth Weld AAGC 1.1 0.5950 0.8546 41.00 35.0 35.0
-70.0 0.1 Upper to Inter Girth Weld KOIB 1.1 0.5950 0.8546 41.00 35.0 35.0
-60.0 10.1 Inlet Nozzle B9011-1 1.1 0.0490 0.2895 77.00 22.3 22.3 60.0 104.6 Inlet Nozzle B9011-2 1.1 0.0490 0.2895 96.00 27.8 43.9 60.0 131.7 Inlet Nozzle B9011-3 1.1 0.0490 0.2895 96.00 27.8 27.8 70.0 125.6 Inlet Nozzle Welds 4P5174 1.1 0.0490 0.2895 122.00 35.3 35.3
-50.0 20.6 Inlet Nozzle Welds LOHB 1.1 0.0490 0.2895 41.00 11.9 11.9
-60.0
-36.3 Inlet Nozzle Welds HABJC 1.1 0.0490 0.2895 27.00 7.8 7.8
-70.0
-54.4 Inlet Nozzle Welds BABBD 1.1 0.0490 0.2895 27.00 7.8 7.8
-70.0
-54.4 Inlet Nozzle Welds FABGC 1.1 0.0490 0.2895 41.00 11.9 11.9
-80.0
-56.3 Inlet Nozzle Welds EOBC 1.1 0.0490 0.2895 27.00 7.8 7.8
-60.0
-44.4 Inlet Nozzle Welds FAAFC 1.1 0.0490 0.2895 95.00 27.5 27.5
-60.0
-5.0 Inlet Nozzle Welds CCJC 1.1 0.0490 0.2895 27.00 7.8 7.8
-60.0
-44.4 Inlet Nozzle Welds FAGB 1.1 0.0490 0.2895 27.00 7.8 7.8
-30.0
-14.4 PTLR Revision 3 5.2 - 27 LRM Revision 62 Beaver Valley Unit 2
Licensing Requirements Manual Pressure and Temperature Limits Report 5.2 Table 5.2-12 (Page 2 of 2)
RTPTS Calculation for Extended Beltline Region Materials at Life Extension (54 EFPY)
Margin(c)
RTNDT(d)
RTpTs(e)
Material Ps (xl 09 n/cm 2 FF(a)
CF (0F)
(F)
(0F)
(0F)
Pos.
E>1.0 MeV)
(OF)
(OF)
(OF)
(F)
.(OF)
Inlet Nozzle Welds BAOED 1.1 0.0490 0.2895 27.00 7.8 7.8
-50.0
-34.4 Outlet Nozzle B9012-1 1.1 0.0234 0.1894 94.00 17.8 17.8
-10.0 25.6 Outlet Nozzle B9012-2 1.1 0.0234 0.1894 94.50 17.9 17.9
-10.0 25.8 Outlet Nozzle B9012-3 1.1 0.0234 0.1894 93.50 17.7 17.7
-10.0 25.4 Outlet Nozzle Weld BABBD 1.1 0.0234 0.1894 27.00 5.1 5.1
-70.0
-59.8 Outlet Nozzle Weld FAAFC 1.1 0.0234 0.1894 95.00 18.0 18.0
-60.0
-24.0 Outlet Nozzle Weld HAAEC 1.1 0.0234 0.1894 41.00 7.8 7.8
-80.0
-64.5 Outlet Nozzle Weld HABJC 1.1 0.0234 0.1894 27.00 5.1 5.1
-70.0
-59.8 Outlet Nozzle Weld HAGB 1.1 0.0234 0.1894 27.00 5.1 5.1
-40.0
-29.8 Outlet Nozzle Weld GACJC 1.1 0.0234 0.1894 41.00 7.8 7.8
-80.0
-64.5 Outlet Nozzle Weld JAHB 1.1 0.0234 0.1894 41.00 7.8 7.8
-40.0
-24.5 Notes:
(a) FF = fluence factor = f(o.28 -o.1 log(f))
(b) ARTPTS = CF *FF.
(c) M = 2 *(a2 +
A2)1 2.
(d) Initial RTNDT value for the upper shell forging is a measured value. All other values are generic.
(e) RTPTS = Initial RTNDT + ARTPTS + Margin.
PTLR Revision 3 LRM Revision 62 Beaver Valley Unit 2 5.2 -28