ML032040061
| ML032040061 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 07/15/2003 |
| From: | Terry J Progress Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3f0703-09, ITS 5.6.2.19 | |
| Download: ML032040061 (11) | |
Text
a 0Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: ITS 5.6.2.19(d)
July 15, 2003 3F0703-09 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - Pressure/Temperature Limits Report, Revision 4
Dear Sir:
Progress Energy
- Florida, Inc.
(PEF) hereby submits the Crystal River Unit 3
Pressure/Temperature Limits Report (PTLR), Revision 4, as required by Improved Technical Specifications (ITS) 5.6.2.19(d). The changes made to the PTLR are administrative in nature.
No technical information was changed. The revision number for calculation F-97-0013 was corrected to Revision 4. In addition to the corrected revision number, several minor format changes were made to the graphs on pages 6 through 10 to improve readability.
No new regulatory commitments are made in this letter.
If you have any questions regarding this submittal, please contact Mr. Sid Powell, Supervisor, Licensing and Regulatory Programs at (352) 563-4883.
Sincerely, t Ames H. Terry
()
ngineering Manager JHT/pei Attachment xc:
NRR Project Manager Regional Administrator, Region II Senior Resident Inspector Progress Energy Florida, Inc.
Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR - 72 ATTACHMENT Pressure/Temperature Limits Report (PTLR)
Revision 4
TABLE OF CONTENTS Pag Supporting Information....................................
3 References....................................
4 Allowable Pressure/Temperature Rates.....................................
5 Plant Heatup Curve....................................
6 Plant Cooldown Curve....................................
7 Plant Inservice Leak and Hydrostatic Testing Curve.........................
........... 8 LTOP Curves....................................
9 Plant Composite Curve..............10i.........................................................................
10 P/T LIMITS REPORT, Rev. 4 F97-0013 Rev. 4 Page 2 of 10
1.0 Pressure/Temperature Limits (Ref.4)
This Pressure-Temperature Limits Report for CR3 has been prepared in accordance with the requirements of Technical Specification Section 1.1 and 5.6.2.19. The pressure/temperature (PiT) limits have been developed using the methodology provided in the references (Ref. 1, Ref.2, Ref.3). Additional limits have been included which support the LTOP Technical Specification 3.4.11.
The following pressure-temperature limits are included in this report:
2.0 3.0 1
Allowable plant heatup and cooldown rates 2
Plant heatup P/T curve 3
Plant cooldown PiT curve 4
Plant inservice leak and hydrostatic testing P/T curve 5
LTOP P/T curves 6
Composite PiT curve Fluence and Limiting Material Information (Ref.5)
T/4 Location l
weld LNB to US Circ. Weld (ID 40%)
material SA-1769 fluence 4.27E+18 n/cm2 ART 213.0 F 3/4T Location
{
weld LNB to US Circ. Weld (OD 60%)
material WF-169-1 fluence 1.55E+18 n/cm2 ART 144.5 F__
PTS Evaluation Summary (Ref.6)
Inside Surface weld LNB to US Circ. Weld (ID 40%)
material SA-1769 fluence 7.08E+18 n/cm2 RTpts 239.9 F 4.0 Instrument Uncertainties The values referenced by this document do not include instrument uncertainties.
Uncertainties must be applied based on the specific instruments being used to measure the parameters of interest.
P/T LIMITS REPORT, Rev. 4 Page 3 of 10 F97-0013 Rev. 4
5.0 References
- 1. B&W Owners Group, topical report BAW-1543A, Rev. 2, "Integrated Reactor Vessel Surveillance Program," May 1985, and Addendum 1, July 1987.
- 2. B&W Owners Group, topical report BAW-10046A, Rev. 2, "Methods of Compliance With Fracture Toughness and Operational Requirements of 10CFR50, Appendix G," June 1986.
- 3. B&W Owners Group, topical report BAW-2241P, Rev. 0, "Fluence and Uncertainty Methodologies," May 1997.
November 2000.
June 1997.
June 1997.
P/T LIMITS REPORT, Rev. 4 Page 4 of 10 F97-0013 Rev. 4
ALLOWABLE HEATUP AND COOLDOWN RATES
- a.
For the temperature ranges specified below, the heatup rates are:
1.
H.
iil.
T > 2800F 2800F 2 T > 850 F 850F 2 T > 600 F
- 70'F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period,
- 50'F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period,
- 150 F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period
- b.
For the temperature ranges specified below, the cooldown rates are:
i.
H.
11.
T > 2800 F 2800F 2 T > 150OF 1500F 2 T S 500F in any 1/2 hour period,
< 250 F in any 1/2 hour period,
- 250F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period
- and,
- c.
A maximum temperature change of less. than or equal to 5 0F in any one hour period during hydrostatic testing operations above system design pressure.
These limits are referred to by Technical Specification 3.4.3.
PIT LIMiTS REPORT, Rev. 4 F97-0013 Rev. 4 Page 5 of 10
REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS FOR HEATUP FOR FIRST 32 EFPY a.w a,
0.
c a,
0 2800 2600 2400 2200 2000 1800 1600 1400 1200 1000 800 600 400 200 0
1 1 I.
DATA POINTS Point Temp Press A
60 368 B
120 368 C
140 383 D
160 416 E
190 497 F
220 547 G
263 692 H
300 909 I
325 1129 J
350 1448 K
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operational use (see note 2)
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50 100 150 200 250 300 350 RCS TEMPERATURE (degF) 400 450 500 550 600 NOTES:
- 1.
The regions of acceptable operation are below and to the right of the limit curve.
- 2.
Margins are Included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve.
Additional margins for instrument uncertainty are not included and must be applied to operating procedures based on the specific Instruments being used to monitor the RCS conditions.
- 3.
Applicable for heatup rates of:
T > 280°F S 70°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, 280°F 2 T > 85°F S 50°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period, 85°F 2 T > 60°F S 15°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period
- 4.
RC Pump Constraints for Heatup:
T > 263°F
- None, 263°F > T 2 220°F No more than 3 RCPs running, 220°F > T 2 85°F No more than 2 RCPs running, 85°F >
T No RCPs running
- 5.
Minimum Temperature for Criticality is 2 525°F (Reference Technical Specification 3.4.2).
- 6.
This curve referred to by Technical Specification 3.4.3 P/T LIM1TS REPORT, Rev. 4 Page 6 of 1(
F97-0013 Rev. 4
)
REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS FOR COOLDOWN FOR FIRST 32 EFPY 2800 V--l1lVTT1TiI 1 H*H a*uu H
I III H II I
I H a a i---
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Point A
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DATA POINTS t
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+/-.
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0 50 100 150 200 250 300 350 RCS TEMPERATURE (degF) 400 450 500 550 600 NOTES:
- 1.
The regions of acceptable operation are below and to the right of the limit curve.
- 2.
Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve.
Additional margins for instrument uncertainty are not included and must be applied to operating procedures based on the specific instruments being used to monitor the RCS conditions.
- 3.
Applicable for cooldown rates of:
T > 280°F
- 50°F In any 1/2 hour period, 280°F 2 T > 150°F 5 250F in any 1/2 hour period, 150°F 2 T 5 25°F in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period
- 4.
RC Pump Constraints for Cooldown:
T > 263°F
- 5.
This curve referred to by Technical Specification 3.4.3 P/T LDIITS REPORT, Rev. 4 F97-0013 Rev. 4 Page 7 of 10
REACTOR COOLANT SYSTEM PRESSURE-TEMPERATURE LIMITS FOR INSERVICE LEAK HYDROSTATIC TESTS FOR FIRST 32 EFPY 0
la l,c M
co CC Q
a)
Q' 3800 3600 3400 3200 3000 2800 2600 2400 2200 2000 1800 1600 1400 1200 1000 800 600 400 200 A
j DATA POINTS Point Temp Press A
60 439 B
140 439 C
160 455 D
190 52.0 E
220 625 F
263 956 J
G 300 1242 H
340 1767 4
I 370 2389 J
395 3115
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.. I...~~~~~~~4-.
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ilT~
I~T~I~
ifii~
'-i-I-rdioir-.'--,-
MUST be applied to this curve for T n ir L.
n-r--
-I-T-operational use (see note 2)
JiJ0__&
.J-L.-1L J...LI...l J1
-e '_LJ_.
JLiJL 1L12..
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50 100 150 200 250 300 350 RCS TEMPERATURE (degF) 400 450 500 550 600 NOTES:
1.
2.
3.
4.
The regions of acceptable operation are below and to the right of the limit curve.
Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve.
Additional margins for instrument uncertainty are not Included and must be applied to operating procedures based on the specific instruments being used to monitor the RCS conditions.
Normal heatup and cooldown restrictions should be used with this curve as applicable.
This curve referred to by Technical Specification 3.4.3 P/T LIMTS REPORT, Rev. 4 Page 8 of 10 F97-0013 Rev. 4
REACTOR COOLANT SYSTEM LOW-TEMPERATURE OVERPRESSURE PROTECTION LIMITS FOR FIRST 32 EFPY 1000 900 -
800-700 -
I I
10 Minute Transient Point A
B C
D E
F G
H I
J Temp 60 85 100 125 150 180 200 220 240 263 Press 300 300 305 317 334 364 393 421 471 551 I -
-I -
4-I 4--
-I
-I j-I
-II-
-I-1--
-I-
.Analytical Point Temp K
60 L
85 M
100 N
125 O
1S0 P
180 Q
200 R
220 S
240 T
263 Limit Press 458 458 467 487 517 567 617 664 751 888
- r ::r--i-
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~-r-m--n__:_
_ L.-_-I-_-_
-- A~
~
~
~ ~~~~~IL-Specific Instrument Uncertainties I
MUST be applied to this curve for I
I-r operational use (see note 2)
-pT 1r1 r-n__
__t__
-~~~~~~~~~-
1
-*--r^-i-_.---
F--r----- ----
+----r-
.4--4
-I
-I
--- i
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1J..L.... E__
- : 4
___J_ _J___
___IJJ_
____J_
_____t_
300 0
50 100
.- 150 200 250 RCS TEMPERATURE (degF)
NOTES:
- 1.
The regions of acceptable operation are below and to the right of the limit curve.
- 2.
Margins are included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve.
Additional margins for instrument uncertainty are not included and must be applied to operating procedures and Technical Specification Umits based on the specific Instruments being used to monitor the RCS conditions.
- 3.
The LTOP curve applies to operation below the enable temperature of 2630F.
- 4.
The LTOP 10 Minute Transient Curve is established based on at least 10 minutes of operation of the limiting transient without exceeding the LTOP Analytical Umits with an initial pressurizer level of 160 in.
- 5.
The PORV setpoint is established to protect the LTOP Analytical Umit Curve.
- 6.
This curve referred to by Technical Specification 3.4.3.
P/T LIMTS REPORT, Rev. 4 Page 9 of 10 F97-0013 Rev. 4
REACTOR COOLANT. SYSTEM COMPOSITE PRESSURE-TEMPERATURE LIMITS FOR FIRST 32 EFPY 2800-2600 -
2400,-
2200 -
2000 -
0-.
wj 1600 -
n) 1400 -
0.U U,
ot 12000-800 -
600-400-200 0
I I.... I DATA POINTS Point Temp I
A 60 B
85 C
100 D
125 E
150 F
187 G
200 H
220 I
240 J
263 K
263 L
300 H
325 N
350 0
389 a_ a I;
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rrla-Specific Instrument Uncertainties MUST be applied to this curve for
- a. operational use (see note 2)
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'350 RCS TEMPERATURE (degF) 400 450.
S00 550 600 NOTES 1.
2.
3.
4-5.
The regions of acceptable operation are below and to the right of the limit curve.
Margins are Included for the pressure differential between point of system pressure measurement and the pressure on the reactor vessel region controlling the limit curve.
Additional margins for instrument uncertainty are not Included and must be applied to operating procedures and Technical Specification Umits based on the specific instruments being used to monitor the RCS conditions.
Normal heatup, cooldown, and LTOP restrictions should be used with this curve as applicable.
The COMPOSITE curve applies to heatup, cooldown, ISLH, and LTOP.
This curve envelopes the heatup, cooldown, ISLH, and LTOP curves referred to by Technical Specification 3.4.3.
PIT LIMTS REPORT, Rev. 4 Page 10 of 14 F97-0013 Rev. 4 3