L-PI-16-054, Pressure and Temperature Limits Report, Revision 5
| ML16175A639 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 06/22/2016 |
| From: | Northard S Northern States Power Co, Xcel Energy |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-PI-16-054, TS 5.6.6.c | |
| Download: ML16175A639 (24) | |
Text
fl Xcel Energy*
Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East JUN 2 2 2016 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie Island Nuclear Generating Plant, Units 1 and 2 Docket Nos. 50-282 and 50-306 Welch. MN 55089 Renewed Facility Operating License Nos. DPR-42 and DPR-60 Pressure and Temperature Limits Report. Revision 5 L-PI-16-054 TS 5.6.6.c
Reference:
- 1. NRC letter to K. Davison, PINGP, Prairie Island Nuclear Generating Plant, Units 1 and 2-Issuance of License Amendments Regarding Revision to Technical Specification 3.5.3, "ECCS-Shutdown" (TAC Nos.
MF0727 and MF0728), dated 5/20/2015 (ADAMS Accession No. ML15062A013)
Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (hereafter "NSPM"), provides the enclosed Revision 5 of the Prairie Island Nuclear Generating Plant (PINGP) Pressure and Temperature Limits Report (PTLR) in accordance with Technical Specification (TS) 5.6.6.c.
Revision 5 deletes reference to TS Section 3.5.3 from Section 3.0 of the PTLR and brings the PTLR into accord with PINGP License Amendment Nos. 213 and 201 for Units 1 and 2, respectively, (Reference 1 ). These amendments deleted reference to the PTLR from the TS Section 3.5.3 Applicability.
Summary of Commitments This letter contains no new commitment and no change to an existing commitment.
Scott Northard Acting Site Vice President, Prairie Island Nuclear Generating Plant Northern States Power Company-Minnesota Enclosure (1)
Document Control Desk Page 2 cc:
Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC State of Minnesota
ENCLOSURE 1 PRESSURE AND TEMPERATURE LIMITS REPORT. REVISION 5 (21 pages follow)
Revision No.
0 1
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Pressure and Temperature Limits Report Approval Date 5/5/98 4/6/00 RECORD OF REVISION Remarks Original Pressure and Temperature Limits Report. Issued after May 4, 1998, approval of License Amendment Request dated March 6, 1998, as Amendment 135/127. Distribution with Technical Specification Revision 135.
Revised discussion of surveillance data credibility.
Revisions to References 5.6 and 5.7 identified which incorporate findings from Comprehensive Revised Response to GL 92-01.
Revised Table 6.5 data to reflect the data incorporated into the updated References 5.6 and 5.7.
Changed title for the operating limit "Temperature for Disabling both Safety Injection Pumps" to the terminology "Safety Injection (SI) Pump Disable Temperature" in preparation for ITS.
Changed titles of Table 6.1 and 6.2 to match Table of Contents.
Changed titles of Figures 6.1 and 6.2 in the Table of Contents to match the titles on the figures.
Distributed with Technical Specification Revision 153.
2 1 0/12/2002 This revision makes the PTLR consistent with the license amendments 158/149.
Details:
Revised Table of Contents to reflect changes in page numbering and the addition of 2 new subsections in section 3: "Pressurizer Temperature Limits" and "Steam Generator Temperature/Pressure Limit".
Revised the wording in section 1.0 to be consistent with license amendments 158/149 5.6.6 as to the items contained in the PTLR document.
Revised the list of Technical Specifications LCO/SRs that reference items in the PTLR. These changes are due to the different license amendments 158/149 numbering.
Revised the "Referenced in" portions of the section 3.0 subparagraphs to reflect the different license amendments 158/149 numbering.
Added subsection "Pressurizer Temperature Limits" to section 3.0.
These limits were moved to the PTLR for license amendments 158/149 versus an LCO in the previous Technical Specification.
Added subsection "Steam Generator Temperature/Pressure Limit" to section 3.0. This limit was moved to the PTLR for license amendments 158/149 versus an LCO in the previous Technical Specification revisions.
Page 1 of 21
Revision No.
3 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Pressure and Temperature Limits Report Approval Date 10/21/2002 RECORD OF REVISION Remarks This revision corrects errors in references to the TRM, a transcription error for the Maximum Pressurizer Cooldown rate and adds Site Director of Engineering as approver.
Details:
On cover page, added Approval of Site Director of Engineering.
On page 1, changed TRM reference 3.1 0.1 to TRM references 3.4.4 and 3.4.5.
On page 4, subsection "Pressurizer Temperature Limits," revised the Maximum Pressurizer Goold own Rate to 200°F per hour versus 1 OOoF per hour, to correct a transcription error in the last revision.
On page 4, subsection "Pressurizer Temperature Limits," revised "Referenced in" specification to TRM 3.4.4 to make the PTLR consistent with the TRM.
On page 4, subsection "Steam Generator Temperature/Pressure Limit,"
revised the "Referenced in" specification to TRM 3.4.5 to make the PTLR consistent with the TRM.
4 3/30/2015 Updated section 4.0 discussion of ART, RT Prs, fluence, and CF with values applicable to 54 EFPY. Throughout, changed the effective until from 35 EFPY to 54 EFPY.
Updated tables 6.4 and 6.5 with ART values at 54 EFPY.
Added references supporting change to effective until 54 EFPY.
5 8/5/2015 Remove reference to TS section 3.5.3 in section 3.0 of the PTLR which discusses Sl pump disable temperature. Refer to License Amendment 213/201.
Page 2 of 21
Prairie Island Nuclear Generating Plant Units One and Two Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY) 0 Prepared by: /omDt,>jvh!
Print Name Sr. Engineer Engineering Reviewed by:. 1'1\\MI.C P'd:..(JSor/
~~
Print Name
- moo..,~7 ~Ia tory Wr3{ 15Affairs Manager Approved by: G;lrzfr...Joh YJ~I'-~~
rint Name Page 3 of 21
- slrJ~-'
. Date
Section 1.0 2.0 3.0 4.0 5.0 6.0 Table 6.1 Table 6.2 Table 6.3 Table 6.4 Table 6.5 Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
Table of Contents Title Page PURPOSE.................................................................................................................... 5 APPLICABILITY........................................................................................................... 5 OPERATING LIMITS.................................................................................................... 6 DISCUSSION............................................................................................................... 9 REFERENCES........................................................................................................... 13 ATTACHMENTS......................................................................................................... 14 List of Tables 54 EFPY Heatup Data Points.................................................................................. 15 54 EFPY Cooldown Data Points............................................................................. 16 Reactor Vessel Material Surveillance Capsule Removal Schedule........................ 17 Prairie Island Unit 1 1/4T and 3/4T ART Calculations at 54 EFPY......................... 18 Prairie Island Unit 2 1/4T and 3/4T ART Calculations at 54 EFPY......................... 19 List of Figures Figure 6.1 Prairie Island Reactor Coolant System Heatup Limitations Applicable to 54 EFPY....................................................... *....................................................... 20 Figure 6.2 Prairie Island Reactor Coolant System Cooldown Limitations to 54 EFPY.............................................................................................................. 21 Page 4 of 21
1.0 PURPOSE Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
The purpose of the Prairie Island Nuclear Generating Station Pressure and Temperature Limits Report (PTLR) is to present operating limits for Units 1 and 2 relating to; (1) RCS pressure and temperature during Heatup, Cooldown and low temperature operation; (2) RCS heatup and cooldown rates; (3) the Over Pressure Protection System (OPPS) arming temperature; (4) OPPS lift settings; (5) Safety Injection Pump disable temperature as well as (6) thermal stress related temperature limitations for the pressurizer and steam generators. This report has been prepared in accordance with the requirements with Technical Specification 5.6.6.
2.0 APPLICABILITY This report is applicable to both Units 1 and 2 until 54 Effective Full Power Years (EFPY) is reached on that particular units' Reactor Pressure Vessel. The Technical Specifications that are affected by the information contained in this report are:
TS 3.4.3 RCS Pressure and Temperature (PIT) Limits TS 3.4.6 RCS Loops - MODE 4 TS 3.4.7 RCS Loops-MODE 5, Loops Filled TS 3.4.1 0 Pressurizer Safety Valves TS 3.4.12 Low Temperature Overpressure Protection (L TOP)- Reactor Coolant System Cold Leg Temperature (RCSCLT) >Safety Injection (SI) Pump Disable Temperature TS 3.4.13 Low Temperature Overpressure Protection (L TOP)- Reactor Coolant System Cold Leg Temperature (RCSCL T} ~ Safety Injection (SI) Pump Disable Temperature TS 3.5.3 ECCS-Shutdown Miscellaneous Specifications-Technical Requirements Manual TRM 3.4.4 PTLR Compliance-Pressurizer TRM 3.4.5 PTLR Compliance-Steam Generator(s)
Page 5 of 21
3.0 OPERATING LIMITS Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
All limits are valid until 54 EFPY, which is projected to be beyond the expiration of the operating license for each of Prairie Island Units 1 and 2.
Over Pressure Protection System (OPPS) Enable Temperature 310 °F*
Referenced in: TS 3.4.6, TS 3.4.7, TS 3.4.10, TS 3.4.12, TS 3.4.13, SR 3.4.12.4, SR 3.4.13.5
- Analytical limit [225 oF] plus indicating instrument channel uncertainty [18 °F]
(Reference 5.11) plus additional margin for operational simplicity.
Safety Injection (51) Pump Disable Temperature 218 Of*
Referenced in: I TS 3.4.12, II
- Analytical limit [200 °F] plus indicating instrument channel uncertainty [18 °F]
(Reference 5.11 ).
Page 6 of 21
Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
RCS Pressure/Temperature (P/Tl Limits Figure 6.1*
RCS PIT limits for heatup Figure 6.2*
RCS PIT limits for cooldown Referenced in: TS 3.4.3, TS 3.4.12, TS 3.4.13, SR 3.4.3.1
- Figures are analytical limits and do not include instrumentation uncertainty.
NOTE:
Tables 6.1 and 6.2 contain a tabulated version of the curves.
Instrumentation Uncertainty for P/T Curves Pressure Uncertainty Temperature Uncertainty NOTE:
These values must be applied to the P/T limit curves in operating procedures (Reference 5.10 and 5.11 ).
RCS Heatup/Cooldown Rate Limits 100 oF per hour Maximum RCS Heatup Rate 100 oF per hour Maximum RCS Cooldown Rate I Referenced in: I TS 3.4.3, SR 3.4.3.1 Over Pressure Protection System COPPS) PORV Setpoint 500 psig*
Referenced in: I TS 3.4.12, TS 3.4.13
- This setpoint accounts for instrument channel uncertainty (Reference 5.8).
Page 7 of 21
Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
RCS Minimum Temperature When Not Vented 86 Of*
Referenced in: I TS 3.4.3,
. TS 5.5.6
- Analytical limit [68°F] plus indicating instrument channel uncertainty [18°F]
(Reference 5.11)
Minimum Boltup Temperature 60 Of**
Referenced in: ITS 5.5.6
- No instrument uncertainty included.
Pressurizer Temperature Limits 100 of per hour Maximum Pressurizer Heatup Rate 200 of per hour Maximum Pressurizer Cooldown Rate Maximum Temperature Difference Between the Pressurizer and the Spray Fluid for which the Pressurizer Spray can be used.
I Referenced in: I TRM Specification 3.4.4 Steam Generator Temperature/Pressure Limit 200 psig Maximum secondary side Pressure if the temperature of the steam generator is below 70 of.
Referenced in: I TRM Specification 3.4.5 Page 8 of 21
4.0 DISCUSSION Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
This PTLR for Prairie Island Units 1 and 2 has been prepared in accordance with the requirements contained in Technical Specification 5.6.6. Periodic adjustments to the curves, limits and setpoints based on new irradiation fluences of the reactor vessel or changes in instrument uncertainty can be made under the conditions of 1 OCFR50.59, with the updated PTLR submitted to the NRC upon issuance.
Changes to the curves, limits, setpoints or parameters in the PTLR resulting from new or additional analysis of either beltline or weld material properties (e.g.
additional capsule data) must be submitted to the NRC prior to issuance of an updated PTLR.
The results of the analysis of the Units 1 and 2 reactor vessel material surveillance capsule tests show that the limitations for Unit 1 are the most restrictive and conservative. For simplicity these results have been applied to both units.
The following parameters were used in the development of the curves, limits, and setpoints given in section 3.0 of this report. These values were obtained from Prairie Island Units 1 and 2 Reactor Vessel Radiation Surveillance Program Data. The surveillance program capsules were removed as indicated in Table 6.3.
Adjusted Reference Temperature (ART)
The adjusted reference temperature is the reference temperature (as defined in the ASME Boiler and Pressure Vessel Code,Section XI, Appendix G for Nil-ductility transition) that has been adjusted for radiation effects. This temperature was determined for all beltline materials for both Prairie Island Units 1 and 2 at the 1/4T and 3/4T thicknesses from the reactor vessel clad/base metal interface radius, where Tis the reactor vessel thickness. Comparison of ARTs for all materials shows that the limiting material at 54 EFPY is the Unit 1 intermediate to lower shell forging circumferential weld material (Table 6.4 and 6.5). The limiting ARTs at 54 EFPY for this material are 150°F for 1/4T, and 133°F for 3/4T.
The Heatup and Cooldown limitations and curves remain unchanged from those developed for 35 EFPY. Because the ART values at 54 EFPY are lower than the values calculated for 35 EFPY in Reference 5.3, the ART values from Reference 5.3 remain as bounding values for development of the Pressure/Temperature limits.
The limiting ARTs used to develop the Pressure/Temperature limits are as follows:
1/4T = 154 °F 3/4T = 136 °F Page 9 of 21
References:
I 5.3, 5.6
Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
End of Life Fluence Reference Temperature (RT m!l The RT pts reference temperature is the end of life reference temperature determined at the clad/base metal interface radius of the reactor vessel and adjusted for radiation effect to the projected end of plant life. The reference temperature has been obtained for all beltline materials in both Prairie Island Units 1 and 2. The projected end of life for both units is 54 Effective Full Power Years (54 EFPY).
Comparison of RT pts for all materials indicates that the limiting material is the Unit 1 upper to intermediate shell forging circumferential weld material. The limiting RT pts is as follows:
RTpts = 157 °F
Reference:
I 5.12 Neutron Fluences (f)
The ARTs are determined, in part, based on neutron fluence that is determined by using analytical techniques and passive neutron flux monitoring devices included within the Reactor Vessel Material Surveillance Program. Neutron fluence is determined for the present and future condition of the reactor vessel. Unit 1 intermediate to lower shell weld neutron fluences used in determining the 54 EFPY limiting ART for the reactor vessels are as follows:
Units are 1019 n/cm2, for energies> 1.0 MeV at 54 EFPY Clad/Base Metal Interface = 4.97 NOTE:
1/4T = 3.33 3/4T = 1.49
References:
15.12, 5.13 These values are not the highest fluences that were obtained in the reactor vessels, but are the values determined for the most limiting material.
The highest fluences were obtained at the unit 2 intermediate shell forging.
(References 5.12 and 5.13).
Page 10 of 21
Chemistry Factor (CF)
Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
Chemistry Factors are parameters used in the development of the ARTs for the beltline materials and account for the Copper and Nickel content in the reactor vessel beltline materials. The chemistry factors determined for the limiting ARTs, corresponding to the Unit 1 intermediate to lower shell circumferential weld, are as follows.
1/4T = 80.8 OF 3/4T = 80.8 °F Reactor Vessel Material Surveillance Program
References:
I 5.13 The Reactor Vessel Material Surveillance Program is described in the USAR (Reference 5.9). The schedule for removal of the Units 1 and 2 capsules is contained in Table 6.3 of this report.
Supplemental Data Tables
References:
5.2, 5.5, 5.9 Tables 6.4 and 6.5 contain the development of all of the ARTs for the beltline materials for Unit 1 and Unit 2 respectfully, including all the parameters.
References:
I 5.13 Page 11 of 21
Surveillance Data Credibility Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
The credibility of surveillance capsule data is determined as specified in Regulatory Guide 1.99, Revision 2, Section B. Four radiation surveillance capsules have been removed from each of the Prairie Island Reactor Vessels, as shown in Table 6.3, and the credibility of these capsule data is analyzed in references 5.2 and 5.5. The credibility of the surveillance data effects how it is applied in the development of the materials' ARTs.
When two or more credible surveillance data sets become available, the data sets may be used to determine the ART values as described in Regulatory Guide 1.99, Revision 2, Position 2.1. If the ART values based on surveillance capsule data are larger than those calculated per Regulatory Guide 1.99, Revision 2, Position 1.1, the surveillance data must be used. If the surveillance capsule data gives lower values, either may be used. In the case of the Prairie Island limiting material, the Unit 1 intermediate to lower shell forging circumferential weld, surveillance data was available but considered non-credible. This resulted in the use of the full crl!. margin of 28°F. The ART calculated using surveillance capsule data is larger than that calculated using position 1.1. For comparison Tables 6.4 and 6.5 contains the ARTs for all those materials in the surveillance programs using both Regulatory Guide 1.99, Revision 2, development methods: Position 1.1 and Position 2.1.
RCS Minimum Temperature When Not Vented This is the RCS lower temperature limit until the system is vented with at least a 3 square inch vent.
Minimum Boltup Temperature The Minimum Boltup Temperature is the minimum temperature of the reactor vessel flange metal required any time reactor vessel flange is under tensioning stress.
Page 12 of 21
5.0 REFERENCES
Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY) 5.1 WCAP-14040-NP-A, Methodology Used to Develop Cold Overpressure Mitigation, Revision 2, January 1996.
5.2 WCAP-14779, Analysis of CapsuleS from the Northern States Power Company Prairie Island Unit 1 Reactor Vessel Radiation Surveillance Program, Revision 2, February 1998.
5.3 WCAP-14780, Prairie Island Unit 1 Heatup and Cooldown Limit Curves Normal Operation, Revision 3, February 1998.
5.4 WCAP-14781, Evaluation of Pressurized Thermal Shock for Prairie Island Unit 1, Revision 3, February 1998.
5.5 WCAP-14613, Analysis of Capsule P from the Northern States Power Company Prairie Island Unit 2 Reactor Vessel Radiation Surveillance Program, Revision 2, February 1998.
5.6 WCAP-14637, Prairie Island Unit 2 Heatup and Cooldown Limit Curves Normal Operation, Revision 3, December 1999.
5.7 WCAP-14638, Evaluation of Pressurized Thermal Shock for Prairie Island Unit 2, Revision 3, December 1999.
5.8 Westinghouse Letter NSP-98-0120, "Prairie Island Units 1 and 2 COMS Setpoint Analysis," Revision 2, February 1998.
5.9 USAR Section 4.7.2, "Reactor Vessel Material Surveillance Program" 5.10 NSP Calculation No. SPCRC002, "Unit 1 Reactor Coolant Hot Leg Pressure Control Room Indication at 1 PR-420 (0-750 psig scale) with 2 RC Pumps Running," Revision 0.
5.11 NSP Calculation No. SPCRC003, "Unit 1 Wide Range RCS Cold Leg Temperature Control Room Indication Loop 1T-450B Uncertainty with Streaming Effects," Revision 0.
5.12 Calculation CN-MRCDA-07-59, "Prairie Island Units 1 and 2 Measurement Uncertainty Recapture: Reactor Vessel Integrity Evaluation".
5.13 Calculation ENG-ME-819, "Adjusted Reference Temperature for Unit 1 and Unit 2 Reactor Vessel Materials at 54 EFPY".
Page 13 of21
6.0 ATTACHMENTS Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY) 6.1 Table 6.1 -54 EFPY Heatup Data Points 6.2 Table 6.2-54 EFPY Cooldown Data Points 6.3 Table 6.3-Reactor Vessel Material Surveillance Capsule Removal Schedule.
6.4 Table 6.4-Prairie Island Unit 1 1/4T and 3/4T ART Calculations at 54 EFPY 6.5 Table 6.5-Prairie Island Unit 2 1/4T and 3/4T ART Calculations at 54 EFPY 6.6 Figure 6.1 - Prairie Island Reactor Coolant System Heatup Limitations Applicable to 54 EFPY.
6.7 Figure 6.2-Prairie Island Reactor Coolant System Cooldown Limitations Applicable to 54 EFPY.
Page 14 of 21
Heatup Curves 60 Heatup T
p 60 0
60 584 65 584 85 584 90 584 95 584 100 586 105 591 110 597 115 604 120 613 125 622 130 633 135 645 140 658 145 672 150 687 155 704 160 722 165 741 170 761 175 784 180 808 185 833 190 861 195 891 200 923 205 957 210 994 215 1033 220 1076 225 1121 230 1170 235 1223 240 1279 245 1339 250 1404 255 1473 260 1548 265 1628 270 1713 275 1805 280 1903 285 2007 290 2119 295 2231 300 2347 305 2471 Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
Table 6.1 54 EFPY Heatup Data Points (Without Instrumentation Uncertainty Margins)
Critical. Limit 100 Heatup Critical. Limit Leak Test Limit T
p T
p T
p T
p 273 0
60 0
273 0
251 2000 273 594 60 560 273 560 273 2485 273 587 65 560 273 560 273 584 85 560 273 560 273 584 90 560 273 560 273 586 95 560 273 560 273 591 100 560 273 560 273 597 105 560 273 560 273 604 110 560 273 562 273 613 115 562 273 566 273 622 120 566 273 571 273 633 125 571 273 577 273 645 130 577 273 585 273 658 135 585 273 594 273 672 140 594 273 604 273 687 145 604 273 615 273 704 150 615 273 627 273 722 155 627 273 641 273 741 160 641 273 656 273 761 165 656 273 672 273 784 170 672 273 690 273 808 175 690 273 709 273 833 180 709 273 730 273 861 185 730 273 752 273 891 190 752 273 777 273 923 195 777 273 802 273 957 200 802 273 831 273 994 205 831 273 861 273 1033 210 861 273 893 273 1076 215 893 273 928 273 1121 220 928 273 966 273 1170 225 966 273 1006 275 1223 230 1006 275 1049 280 1279 235 1049 280 1096 285 1339 240 1096 285 1149 290 1404 245 1146 290 1199 295 1473 250
' 1199 295 1257 300 1548 255 1257 300 1318 305 1628 260 1318 305 1384 310 1713 265 1384 310 1455 315 1805 270 1455 315 1531 320 1903 275 1531 320 1612 325 2007 280 1612 325 1699 330 2119 285 1699 330 1792 335 2231 290 1792 335 1892 340 2347 295 1892 340 1998 345 2471 300 1998 345 2112 305 2112 350 2233 310 2233 355 2363 315 2363 Page 15 of 21
Cooldown Curves Steady State T
p 60 0
60 590 65 594 70 599 75 605 80 611 85 617 90 621 95 621 100 621 105 621 110 621 115 621 116 621 116 668 120 676 125 687 130 699 135 712 140 726 145 741 150 757 155 774 160 793 165 813 170 834 175 857 180 882 185 909 190 937 195 968 200 1001 205 1036 210 1075 215 1115 220 1159 225 1206 230 1257 235 1311 240 1370 245 1432 250 1500 255 1572 260 1649 265 1732 270 1820 275 1915 280 2017 285 2126 290 2243 295 2367 Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
Table 6.2 54 EFPY Cooldown Data Points (Without Margins for Instrumentation Uncertainty) 20 deg F 40 deg F 60 deg F T
p T
p T
p 60 0
60 0
60 0
60 563 60 537 60 510 65 568 65 542 65 515 70 573 70 547 70 520 75 579 75 552 75 526 80 585 80 558 80 532 85 591 85 565 85 539 90 598 90 572 90 546 95 605 95 580 95 554 100 613 100 588 100 563 105 621 105 597 105 572 110 621 110 607 110 582 115 621 115 617 115 592 116 621 120 628 120 604 116 644 125 640 125 616 120 652 130 653 130 630 125 664 135 667 135 644 130 676 140 682 140 660 135 690 145 698 145 676 140 704 150 715 150 695 145 720 155 734 155 714 150 736 160 754 160 735 155 754 165 776 165 757 160 773 170 799 170 782 165 794 175 824 175 808 170 816 180 851 180 836 175 841 185 880 185 866 180 866 190 911 190 899 185 894 195 945 195 934 190 924 200 981 200 972 195 956 205 1019 205 1012 200 990 210 1061 210 1056 205 1027 215 1106 215 1102 210 1067 220 1154 220 1153 215 1110 225 1205 220 1156 225 1205 Page 16 of 21 100 deg F T
p 60 0
60 455 65 460 70 465 75 471 80 478 85 485 90 493 95 502 100 511 105 520 110 531 115 543 120 555 125 568 130 583 135 599 140 615 145 634 150 653 155 674 160 697 165 722 170 748 175 777 180 808 185 841 190 876 195 915 200 956 205 1001 210 1048 215 1100 220 1155
Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
Table 6.3 Reactor Vessel Material Surveillance Capsule Removal Schedule Recommended Surveillance Capsule Removal Schedule for Unit 1 Capsule Location Lead Factor(a)
Withdrawal Fluence(a)
Capsule (degree)
EFPY(b)
(n/cm2, E> 1.0 MeV) v 77 2.94 1.34 5.630 X 1018(c) p 247 1.72 4.60 1.318 X 1019(c)
R 257 2.99 8.56 4.478 X 10 19(c) s 57 1.77 18.12 4.017 X 1019(c)
T 67 1.89 Standby N
237 1.77 Standby Recommended Surveillance Capsule Removal Schedule for Unit 2 Capsule Location Lead Factor(d)
Withdrawal Capsule (degree)
EFPY(b) v 77 2.95 1.39 T
67 1.75 4.00 R
257 2.99 8.81 p
247 1.84 17.24 N
237 1.72 Standby s
57 1.72 Standby Notes:
(a) Updated in Capsule S dosimetry analysis.
(b) Effective Full Power Years (EFPY) from plant startup.
(c) Plant specific evaluation.
(d) Updated in Capsule P dosimetry analysis.
Page 17 of 21 Fluence(d)
(n/cm2, E> 1.0 MeV) 6.206 X 10 18(c) 1.199 X 1019(c) 4.376 X 10 19(c) 4.165 X 1019(c)
Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
Table 6.4 Prairie Island Unit 11/4T and 3/4T ART Calculations at 54 EFPY Material CF f@54 114T f 114T FF(d) l(e)
M(g)
.1RT NDT EFPY(a) 314Tf 314T FF CF)
(oF)
CF) 1/4T Calculations Upper Shell 51 1.770 1.185 1.047
-4 34 53.4 Forging B Upper to Inter. Shell 79.5 1.770 1.185 1.047 o<c) 66 83.3 CircWeldW2 Intermediate Shell 44.0 5.162 3.455 1.324 14 34 58.2 Forging C Using SIC Data 54.7 5.162 3.455 1.324 14 34(b) 72.4 Inter. to Lower 69.7 4.969 3.326 1.315
-13 56 91.6 SheiiWeldW3 Using SIC Data 80.8 4.969 3.326 1.315
-13 56(b) 106.2 Lower Shell Forging D 44.0 5.026 3.364 1.318
-4 34 58.0 3/4T Calculations Upper Shell 51 1.770 0.5307 0.823
-4 34 42.0 Forging B Upper to Inter. Shell 79.5 1.770 0.5307 0.823 o<c) 66 65.4 CircWeldW2 Intermediate Shell 44.0 5.162 1.548 1.121 14 34 49.3 Forging C Using SIC Data 54.7 5.162 1.548 1.121 14 34(b) 61.3 Inter. to Lower 69.7 4.969 1.490 1.110
-13 56 77.4 SheiiWeldW3 Using SIC Data 80.8 4.969 1.490 1.110
-13 56(b) 89.7 Lower Shell Forging D 44.0 5.026 1.507 1.114
-4 34 49.0 NOTE:
(a)
Fluence values (f) are x 1019 n/cm2 (E > 1.0 MeV). (Ref. 5.13)
(b)
The full cr!J. margin of 17"F for the forging and 28°F for the weld was used since the surv. data was deemed not credible (Ref. 5.3).
(c)
Estimated per Standard Review Plan Section 5.3.2 (Ref. 5.3).
(d)
FF, Fluence Factor= f(0.28-0.1*1ogf) (Ref. 5.13)
(e)
I is the unirradiated material reference temperature. (Ref. 5.3)
(g)
M is a margin term required for conservative results. (Ref. 5.3)
Page 18 of 21 ART (oF) 84 149 107 121 135 150 88 72 131 98 110 121 133 79
Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
Table 6.5 Prairie Island Unit 2 1/4T and 3/4T ART Calculations at 54 EFPY Material CF f@54 1/4T f 1/4T FF(c) l(d)
M(e)
~RTNDT ART EFPY 3/4T f(a) 3/4T FF (oF)
(oF)
CF)
(oF) 1/4T Calculations Upper Shell Forging B 44.0 1.743 1.167 1.043
-13 34 45.9 67 Upper to Inter. Shell Weld 70.0 1.743 1.167 1.043
-13 56 72.7 116 W2 Using Unit 1 SIC Data
80.8 1.743 1.167 1.043
-13 56 84.3 128 Intermediate Shell Forging 44.0 5.196 3.478 1.325 14 34 58.3 107 c
Inter. to Lower Shell Weld 52.0 5.043 3.375 1.318
-31 56 68 93 W3 Using SIC Data 80.0 5.043 3.375 1.318
-31 28 105.7 103 Lower Shell Forging D 51.0 5.112 3.421 1.321
-4 34 67.4 98 Using SIC Data 60.0 5.112 3.421 1.321
-4 34(1) 78.8 109 3/4T Calculations Upper Shell Forging B 44.0 1.743 0.5226 0.8187
-13 34 36.0 57 Upper to Inter. Shell Weld 70.0 1.743 0.5226 0.8187
-13 56 57.1 101 W2 Using Unit 1 SIC Data
80.8.
1.743 0.5226 0.8187
-13 56 66.2 110 Intermediate Shell Forging 44.0 5.196 1.558 1.123 14 34 49.4 98 c
Inter. to Lower Shell Weld 52.0 5.043 1.512 1.114
-31 56 57.5 83 W3 Using SIC Data 80.0 5.043 1.512 1.114
-31 28 89.4 87 Lower Shell Forging D 51.0 5.112 1.533 1.118
-4 34 57.0 87 Using SIC Data 60.0 5.112 1.533 1.118
-4 34(1) 66.6 97 NOTE:
(a)
Fluence values (f) are x 1019 nlcm2 (E > 1.0 MeV). (Ref. 5.13)
(b)
This calculation is using the chemistry factor based on the surveillance capsule data for the Prairie Island Unit 1 surveillance program. Per WCAP-14779 Rev. 1, the surveillance weld data is not credible, therefore, a full Of'> of 28°F was used in the margin term.
(c)
FF, Fluence Factor= f(0.28-0.1 *logf). (Ref. 5.13)
(d)
I is the unirradiated material reference temperature. (Ref. 5.6)
(e)
M is a margin term required for conservative results. (Ref. 5.6)
(f)
The full Of'> margin of 1rF for the forging was used since the surveillance data was deemed not credible (Ref. 5.6).
Page 19 of 21
Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
Figure 6.1 Prairie Island Reactor Coolant System Heatup Limitations Applicable to 54 EFPY (w/o Margins for Instrument Uncertainty) 2500 2000 Ci l
1500 CD...
- 1 Ul Ul CD...
Q.
"C CD -
<II 1000 u ;:;
-=
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. 17
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Heatup Rate
~II-lnseJVice Hydrostatic Test Up to 100 F/Hr 1
Te":lperature (238 F) For the 1-+---1-- Boltup1 I
SubcriticaJ*
- 1 SeJVJce Period up to 54 EFPY Temp.l 1
1 l1 i
l~
I I
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,j 0
0 50 100 150 200 250 300 350 400 Indicated Temperature (Deg. F)
- For each cur.<e, acceptable operation is to the right and below the cur.<e.
Page 20 of 21
Figure 6.2 1800 1600 1400 1200 m
0.. -
~ 1000 en Ill Gl...
ll.
"'C 800 Gl as u
"'C
.E 600 f--
Cooldown f--
Rates*
f--
I--
Peg_ F I Hr I--
I--
0 f--
20 f--
40 f--
1-60 400 1-100 200 0
0 50 Pressure and Temperature Limits Report Revision 5 (Effective until 54 EFPY)
Prairie Island Reactor Coolant System Cooldown Limitations to 54 EFPY (w/o Margins for Instrument Uncertainty)
I I
/
I UNACCEPTABLE
/
OPERATION
/
17 J
IJ II)'
..41~
~
Ai;:Jr'l ACCEPTABLE A W/
~ ~
OPERATION
_/. ~ 'l
~---
1-:/ 1:/:: ~
1/
v
~
1Boltup 1Temp_
100 150 200 250 300 350 Indicated Temperature (Deg. F)
- For each curve, acceptable operation is to the right and below the curve.
Page 21 of 21