CPSES-200200535, Transmittal of Unit 2 Pressure & Temperature Limits Report, Revision 3
| ML020710645 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/27/2002 |
| From: | Terry C, Walker R TXU Electric |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CPSES-200200535, TAC MB2761, TXX-02042 | |
| Download: ML020710645 (18) | |
Text
TXU TXU Electric C. Lance Terry Comanche Peak Senior Vice President & Principal Nuclear Officer Ref: TS 5.6.6 Steam Electric Station P.O. Box 1002 Glen Rose,TX 76043 Tel: 254 897 8920 Fax:254 897 6652 lance.terry@txu.com CPSES-200200535 Log # TXX-02042 February 27, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NO. 50-446 TRANSMITTAL OF UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT, REVISION 3 REF:
- 1) TXU Electric Letter, logged TXX-01 133, from Mr. C. L. Terry to the NRC dated August 16, 2001, "Revision to the Reactor Vessel Material Surveillance Program Withdrawal Schedule."
- 2)
NRC Safety Evaluation, "Comanche Peak Steam Electric Station, Unit 2 - Request to Revise Reactor Pressure Vessel Material Surveillance Program Schedule (TAC NO. MB2761)" dated February 5, 2002.
Gentlemen:
Per reference 1, TXU Generation Company LP (TXU Energy) requested approval for a revision to the reactor vessel material surveillance program withdrawal schedule for CPSES Unit 2. Reference 2 found that the proposed withdrawal schedule for the capsules for the CPSES Unit 2 reactor pressure vessel surveillance program satisfies the requirements of Appendix H to 10 CFR 50 and is acceptable.
CPSES Technical Specification (TS) 5.6.6 requires that the Pressure and Temperature Limits Report (PTLR) be provided to the NRC upon issuance for each reactor vessel fluence period and for each revision or supplement thereto. Enclosed is the CPSES Unit 2 PTLR, Revision 3. This revision to the PTLR does not change the pressure temperature limits or the Low Temperature Overpressure Protection (LTOP) system setpoints.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway Comanche Peak
- Diablo Canyon Palo Verde South Texas Project Wolf Creek
t TxU TXX-02042 Page 2 of 2 This communication contains no new licensing basis commitments regarding CPSES Unit 2.
Sincerely, TXU Generation Company LP By:
TXU Generation Management Company LLC, Its General Partner C. L. Terry Senior Vice President and Principal Nuclear Officer By:
Roger DW !f*ke' Regulatory Affairs Manager JCH/jch Enclosure c -
E. W. Merschoff, Region IV D. N. Graves, Region IV D. H. Jaffe, NRR Resident Inspectors, CPSES
ENCLOSURE to TXX-02042
ERX-99-003, Rev. 3 CPSES UNIT 2 PRESSURE AND TEMPERATURE LIMITS REPORT (APPLICABLE UP TO 16 EFPY)
February 2002 Prepared:
Parvez Salim Safety Analysis Reviewed:
W. Ja"mes Boatwight Safety Analysis Approved:
/11 c\\'14 Whee G. Cho Safety Analy is Manager Date:
Date:
Date:
,,'_/
DISCLAIMER The information contained in this report was prepared for the specific requirement of TXU Generation Company LP (TXU), and may not be appropriate for use in situations other than those for which it was specifically prepared. TXU PROVIDES NO WARRANTY HEREUNDER, EXPRESSED OR IMPLIED, OR STATUTORY, OF ANY KIND OR NATURE WHATSOEVER, REGARDING THIS REPORT OR ITS USE, INCLUDING BUT NOT LIMITED TO ANY WARRANTIES ON MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE.
By making this report available, TXU does not authorize its use by others, and any such use is forbidden except with the prior written approval of TXU. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein.
In no event shall TXU have any liability for any incidental or consequential damages of any type in connection with the use, authorized or unauthorized, of this report or of the information in it.
Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
TABLE OF CONTENTS D ISC LA IM ER..........................................................
ii TABLE OF CONTENTS..................................................
iii LIST O F FIG URES iv LIST O F TABLES.......................................................
v SECTION PAGE 1.0 INTRO DUCTIO N................................................
1 2.0 OPERATING LIMITS..............................................
2 2.1 RCS Temperature Rate-of-Change Limits (LCO 3.4.3)...............................
3 2.2 P/T Limits for Heatup, Cooldown, Inservice Leak &
Hydrostatic Testing, and Criticality (LCO 3.4.3)....................
4 2.3 LTOP System Setpoints (LCO 3.4.12)...........................
4 2.4 Reactor Vessel Material Surveillance Program....................
4
3.0 REFERENCES
9 iii Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
LIST OF FIGURES FIGURE PAGE 2-1 RCS Heatup Limitations - Applicable Up To 16 EFPY....................
6 2-2 RCS Cooldown Limitations - Applicable Up To 16 EFPY..................
7 2-3 PORV Setpoints for Overpressure Mitigation - Applicable Up To 16 EFPY.................................................
8 iv Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
LIST OF TABLES 2-1 Reactor Vessel Material Surveillance Program W ithdrawal Schedule.............................................
5 Revision 3 TABLE PAGE
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
1.0 INTRODUCTION
This report presents the Reactor Coolant System (RCS) Pressure and Temperature (PIT) limits for Comanche Peak Steam Electric Station (CPSES) Unit 2 in accordance with the requirements of Technical Specification 5.6.6. A description of the Low Temperature Overpressure Protection (LTOP) System is also provided in this report. In addition, the requirements of the reactor vessel material surveillance program are discussed.
The following two Technical Specification Limiting Conditions of Operation (LCO) are addressed in this report:
LCO 3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.12 Low Temperature Overpressure Protection (LTOP) System The P/IT Limits (Section 2.2) and the LTOP System Setpoints (Section 2.3) in this report shall not be revised without prior NRC approval.
The analytical methods used to determine the RCS P/T limits are consistent with the following guidance:
10 CFR 50 Appendices G and H (References 1 & 2)
Regulatory Guide 1.99, Revision 2 (Reference 3)
NUREG-0800, Standard Review Plan Section 5.3.2 (Reference 4)
ASME Code Section III, Division 1, Appendix G (Reference 5)
The LTOP limits are consistent with the following guidance:
10 CFR 50 Appendix G (Reference 1)
NUREG-0800, Standard Review Plan Section 5.2.2 (Reference 6)
This report covers CPSES Unit 2 operation for 16 Effective Full Power Years (EFPY), which approximately corresponds to the Cycle 11 operation of the unit.
Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY) 2.0 OPERATING LIMITS RCS P/T Limits The RCS P/T limits presented in this report consist of the RCS (except the pressurizer) temperature rate-of-change limits and P/T limits during heatup, cooldown, inservice leak &
hydrostatic testing, and criticality. The P/T limits for CPSES Unit 2 are based on the Westinghouse procedure outlined in Reference 7.
Appendix G of 10 CFR Part 50 [1] establishes specific fracture toughness requirements for ferritic materials in the Reactor Coolant Pressure Boundary (RCPB) in light water nuclear power reactors. An adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests is also required by this reference. Furthermore, Reference 1 mandates the use of Appendix G,Section III of the American Society of Mechanical Engineers (ASME) Code [5] to establish P/T limits.
The RCS P/T limits for CPSES Unit 2 are presented in Reference 8.
LTOP System The LTOP System acts as a backup to the reactor operators to mitigate RCS pressurization transients at low temperatures so the integrity of RCPB is not compromised by violating the pressure and temperature limits of Appendix G of 10 CFR 50 [1]. The reactor vessel is the limiting RCPB component for demonstrating such protection. The LTOP system provides the maximum allowable actuation logic setpoints for the Power Operated Relief Valves (PORVs) for the existing RCS cold leg temperature during cooldown, shutdown, and heatup to meet the Reference 1 requirements during the LTOP MODES.
The LTOP setpoints for CPSES Unit 2 is presented in Reference 9 (supplemented by Reference 10).
2 Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM The reduction in toughness that results from neutron radiation is measured as an increase in the Nil Ductility Reference Temperature (RTNDT) and reduction of the upper-shelf energy of reactor vessel beltline materials, including welds. At CPSES, these quantities were predicted at 16 EFPY using the methods of Regulatory Guide 1.99, Revision 2 [3]. The predictions showed that the materials in the Unit 1 and Unit 2 reactor vessels responded similarly to neutron irradiation but at 16 EFPY, the plate material in the Unit 1 beltline was most limiting. Forecast properties of the limiting material were used to establish P/T limits for heatup and cooldown curves and LTOP setopints. For uniformity, the Unit 1 curves were adopted for Unit 2.
The actual neutron-induced shifts in the RTNDT and the upper-shelf energy is periodically measured by withdrawing a surveillance capsule and evaluating the specimens of the limiting beltline material that it contains. The CPSES capsules were built under the ASTM E 185-70 Standard [11]. The evaluation of the irradiated reactor vessel material specimens is conducted in accordance with ASTM E 185-82 [12] and Appendix H of 10 CFR 50 [2]. The operating P/T limit curves are adjusted, as necessary, based on the evaluation findings and the recommendations of Regulatory Guide 1.99, Revision 2 [3].
The analysis of Capsule U from CPSES Unit 2 is presented in Reference 13.
2.1 RCS Temperature Rate-of-Change Limits (LCO 3.4.3) 2.1.1 Maximum Heatup Rate The RCS heatup rate limit is 100°F in any 1-hour period.
2.1.2 Maximum Cooldown Rate The RCS cooldown rate limit is 100°F in any 1-hour period.
2.1.3 Maximum Temperature Chanaqe During Inservice Leak and Hydrostatic Testing During inservice leak and hydrostatic testing operations above the heatup and 3
Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY) cooldown limit curves, the RCS temperature change limit is 10°F in any 1-hour period.
2.2 P/T Limits for Heatup, Cooldown. Inservice Leak &
Hydrostatic Testing, and Criticality (LCO 3.4.3) 2.2.1 P/T Limits for Heatup, Inservice Leak & Hydrostatic Testin., and Criticality The P/T limits for heatup, inservice leak & hydrostatic testing, and criticality are specified in Figure 2-1.
2.2.2 P/T Limits for Cooldown The P/T limits for cooldown are specified in Figure 2-2.
2.3 LTOP System Setpoints (LCO 3.4.12)
The maximum allowable PORV pressure setpoints as a function of RCS temperature are shown in Figure 2-3.
2.4 Reactor Vessel Material Surveillance Program The vessel material surveillance schedule is provided in Table 2-1. This schedule was approved by the NRC in Reference 14.
4 Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
Table 2-1 Reactor Vessel Material Surveillance Program - Withdrawal Schedule VESSEL LOCATION 58.50 238.50 121.50 301.50 61.00 241.00 LEAD FACTOR 4.10 4.10 4.10 4.10 3.74 3.74 WITHDRAWAL TIME 0.9 EFPY*
9 EFPY 14 EFPY Standby Standby Standby "Capsule withdrawn and analyzed 5
Revision 3 CAPSULE NUMBER U
x W
Z V
Y
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
MATERIAL PROPERTY BASIS CONTROLLING MATERIAL:
INITIAL RTNDT:
ART AT 16 EFPY:
INTERMEDIATE SHELL PLATE R3807-2 10°F 1/4T: 81'F 3/4T: 62°F APPLICABLE FOR HEATUP RATES UP TO 100°F/HR FOR THE SERVICE PERIOD UP TO 16 EFPY. CONTAINS MARGINS OF 10°F AND 110 PSIG FOR POSSIBLE INSTRUMENTATION ERRORS.
tj2~j;kW 11 11 111til1 II~
~I III;I LEAK TEST LIMIT UNACCEPTABLE OPERATION HEATUP RATES UP TO 20"F/HR
.1
w I 1-114 20"/H HtTU RAT F-:BCRITICALITY LIMIT CORRESPONDING TO 5CRITIALITY LIIT
-CORRESPONDINGG TO IO0"F/HR HEATUP RATE'
" ~~ ~ ~ ~ 1.
I I
lI,,
I!I
- I
- HEATUP RATES-UP TO 60"F/HR
" I I I 1
l I
HEATUP RATESJ UP TO
- IO0"F/HR ACCEPTABLE OPERATION
......RIO UP11 1 1 TOl 16 EFPi SI I I I I
I I I V 1 I0
, I I I I I I I f*
CRITICALITY LIMIT BASED ON INSERVICE
.50ROTATIC TEST 50 TEMPERATURE (230-F)
FOR THE SERVICE PERIOD UP TO 16 EFPY" O0 50 100 150 200 250 300 350 400 450 500 INDICATED TEMPERATURE (DEG.F)
Figure 2-1 RCS Heatup Limitations - Applicable Up To 16 EFPY 6
Revision 3 2250 2000 1750 I nff](
1250 1000 750 IL w
- i.
w C
7 N rl 0 I
11
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
MATERIAL PROPERTY BASIS CONTROLLING MATERIAL:
INITIAL RTNDT:
ART AT 16 EFPY:
INTERMEDIATE SHELL PLATE R3807-2 10°F 1/4T: 81°F 3/4T: 62°F APPLICABLE FOR COOLDOWN RATES UP TO 1000F/HR FOR THE SERVICE PERIOD UP TO 16 EFPY. CONTAINS MARGINS OF 10"F AND 110 PSIG FOR POSSIBLE INSTRUMENTATION ERRORS.
2500 TBXN I'
I 2250 I~ ~ ~
i77 III IIIIIIIIII II UNACCEPTABLE OPERATION 4
w n,.
Crw) w qC 70 z
1750 1500 1250 1000 750 500 250 ACCEPTABLE OPERATION 1
- COOLDOWN RATES O
F/MR 20 40 10060714 I1 I I I
U 0 50 100 150 200 300 350 400 450 INDICATED TEMPERATURE (DEG.F)
Figure 2-2 RCS Cooldown Limitations - Applicable Up To 16 EFPY 7
500 Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
CD
- a.
z 0 a-RCS TEMPERATURE, DEG F Figure 2-3 PORV Setpoints for Overpressure Mitigation - Applicable Up To 16 EFPY 8
Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
3.0 REFERENCES
- 1.
"Code of Federal Regulations, 10 CFR 50, Appendix G, "Fracture Toughness Requirements," U.S. Nuclear Regulatory Commission, Washington, D.C.
- 2.
"Code of Federal Regulations, 10 CFR 50, Appendix H, "Reactor Vessel Material Surveillance Program Requirements," U.S. Nuclear Regulatory Commission, Washington, D.C.
- 3.
Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials," U.S. Nuclear Regulatory Commission, Washington, D.C., May 1988.
- 4.
Branch Technical Position MTEB 5-2, "Fracture Toughness Requirements," NUREG 0800 Standard Review Plan 5.3.2, Pressure-Temperature Limits, July 1981, Rev. 1.
- 5.
ASME Boiler and Pressure Vessel Code,Section III, Division 1 - Appendices, "Rules for Construction of Nuclear Power Plant Components, Appendix G, Protection Against Nonductile Failure," pp. 558-563, 1986 Edition, American Society of Mechanical Engineers, New York, 1986.
- 6.
Branch Technical Position RSB 5-2, "Overpressurization Protection of Pressurized Water Reactors While Operating at Low Temperatures," NUREG-0800 Standard Review Plan 5.2.2, Overpressure Protection, November 1988, Rev. 2.
- 7.
"Procedure for Developing Heatup and Cooldown Curves," Westinghouse Electric Corporation, Generation Technology Systems Division Procedure GTSD-A-1.12 (Rev.
0), July 13, 1988.
- 8.
"Comanche Peak Steam Electric Station Unit Number 1 & 2, Heatup and Cooldown Curves Using 110 psig and 10°F Margins for Instrument Error," Westinghouse Letter WPT-14868, October 12,1992.
9 Revision 3
Pressure and Temperature Limits Report for CPSES Unit 2 (Applicable Up To 16 EFPY)
- 9.
"Setpoint Program Determination for the Westinghouse Overpressure Mitigation System in Comanche Peak Units 1 and 2," Westinghouse Letter Report transmitted via Letter WPT-14228, January 3, 1992.
- 10.
"Results of Review of Comanche Peak Cold Overpressure Mitigation System Nonconservatism," Westinghouse Letter Report transmitted via Letter WPT-14881, September 2, 1992.
- 11.
ASTM E 185-70, "Standard Recommended Practice for Surveillance Tests for Nuclear Reactor Vessels."
- 12.
ASTM E 185-82, "Standard Practice for Conducting Surveillance Tests for Light-Water Cooled Nuclear Power Reactor Vessels, E706 (IF)."
- 13.
"Analysis of Capsule U from the Texas Utilities Electric Company Comanche Peak Unit No. 2 Reactor Vessel Radiation Surveillance Program," Westinghouse Report WCAP 14315, July 1995.
- 14.
"Comanche Peak Steam Electric Station, Unit 2 - Re Request to Revise Reactor Pressure Vessel Material Surveillance Program Schedule," Letter from David H. Jaffe (NRC) to C. Lance Terry (TXU), February 5, 2002.
10 Revision 3