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{{#Wiki_filter:Dominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT | {{#Wiki_filter:Dominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dom.com NOV , U. S. Nuclear Regulatory Commission Attention: | ||
P.O. Box | Document Control Desk Washington, DC 20555 Serial No.NSS&L/MLC Docket No.License No.15-520 R0 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT. | ||
Document Control | INC.MILLSTONE POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT. CYCLE 24 In accordance with the Millstone Power Station Unit 2 (MPS2) Technical Specifications (TSs), Section 6.9.1 .8.d, Dominion Nuclear Connecticut, Inc., hereby submits, as an enclosure, the Cycle 24 Core Operating Limits Report (COLR).The MPS2 COLR has been revised to include the following: | ||
INC.MILLSTONE POWER STATION UNIT | * Revision of page headers to reflect Cycle 24.The Cycle 24 COLR has been incorporated into the MPS2 Technical Requirements Manual.If you have any questions or require additional information, please contact Mr. Thomas G.Cleary at (860) 447-1791 Ext. 3232.Sincerely, D. B. Blakeney Director, Nuclear Station Safety and Licensing | ||
* Revision of page headers to reflect Cycle 24.The Cycle 24 COLR has been incorporated into the MPS2 Technical Requirements Manual.If you have any questions or require additional information, please contact Mr. Thomas G.Cleary at (860) 447-1791 Ext. 3232.Sincerely, D. B. | -Millstone | ||
-Millstone | |||
==Enclosure:== | ==Enclosure:== | ||
Core Operating Limits Report, Cycle | Core Operating Limits Report, Cycle 24 Commitments made in this letter: None Th¶-p Serial No. 15-520 Docket No. 50-336 MPS2 Cycle 24 COLR Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd. Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Serial No. 15-520 Docket No. 50-336 ENCLOSURE CORE OPERATING LIMITS REPORT, CYCLE 24 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 2 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 1. CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT for Millstone 2 has been prepared in accordance with the requirements of Technical Specification 6.9.1.8 a through 6.9.1.8 d.The Technical Specifications affected by this report are listed below: Section 2.1 2.2 2.3 2.4 2.5 2.6 Specification 3/4.1.1.1 3/4.1.1.4 3/4.1.3.6 3/4.2.1 3/4.2.3 3/4.2.6 SHUTDOWN MARGIN -(SDM)Deleted (Ref. License Amendment 280)Moderator Temperature Coefficient (MTC)Regulating CEA Insertion Limits Linear Heat Rate TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR --FrT DNB Margin 2.7 Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of the Technical Specifications. | ||
: 2. OPERATING | : 2. OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. | ||
These limits have been developed using | These limits have been developed using the NRC approved methodologies specified in Section 3.2.1 SHUTDOWN MARGIN -(5DM).(Specification 3/4.1.1.1) | ||
The SHUTDOWN MARGIN shall be 3.6% AK/ | The SHUTDOWN MARGIN shall be 3.6% AK/K 2.2 Deleted 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.4) | ||
The moderator temperature coefficient shall be:a. Less positive than 0.7x1 0-4 AK/K/°F whenever THERMAL POWER is <70% | The moderator temperature coefficient shall be: a. Less positive than 0.7x1 0-4 AK/K/°F whenever THERMAL POWER is <70% of RATED THERMAL POWER, b. Less positive than 0.4x10-4 AK/K/°F whenever THERMAL POWER is > 70%of RATED THERMAL POWER, c. Less negative than -3.2x10-4 AK/K/°F at RATED THERMAL POWER.MILLSTONE | ||
-UNIT | -UNIT 2 TRM 8.1-1 LBDCR 15-MP2-010 October 6 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 2.4 Regulating CEA Insertion Limits (Technical Specification 3/4.1.3.6) | ||
The regulating CEA groups shall be limited to the withdrawal sequence and to | The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown in Figure 2.4-1. CEA insertion between the Long Term Steady State Insertion Limits and the Transient Insertion Limits is restricted to: a. <4 hours per 24 hour interval, b. <5 Effective Full Power Days per 30 Effective Full Power Day interval, and c. < 14 Effective Full Power Days per 365 Effective Full Power Day interval.2.5 Linear Heat Rate (Technical Specification 3/4.2.1)The linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed: a. 15.1 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is 360,000 gpm.b. 15.0 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 360,000 gpm and >354,600 gpm.c. 14.9 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 354,600 gpm and __349,200 gpm.During operation with the linear heat rate being monitored .by the Excore Detector Monitoring System, the AXIAL S.HAP. E INDEX shall remain within the limits of Figure 2.5-1.During operation with the linear heat rate being monitored by the Incore Detector Monitor System, the alarm setpoints shall be adjusted to less than or equal to the limit when the following factors are appropriately included in the setting of the alarms: 1. A measurement-calculational uncertainty factor of 1 .07, 2. An engineering uncertainty factor of 1.03, and 3. A THERMAL POWER measurement uncertainty factor of 1.02.MILLSTONE | ||
-UNIT 2 TRM 8.1-2 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR -- FrT (Technical Specification 314.2.3)The calculated value of FrT at RATED THERMAL POWER shall be:_< 1.690 whenever the reactor coolant flow rate is >_ 360,000 gpm._< 1 .664 whenever the reactor coolant flow rate is < 360,000 gpm and > 354,600 gpm._< 1 .639 whenever the reactor coolant flow rate is < 354,600 gpm and > 349,200 gpm.2.6.1 The Power Dependent FrTr limits, whenever the reactor coolant flow rate is > 360,000 gpm, are shown in Figure 2.6-1.2.6.2 The Power Dependent FrT limits, whenever the reactor coolant flow rate is < 360,000 gpm and > 354,600 gpm, are shown in Figure 2.6-2.2.6.3 The Power Dependent FrTr limits, whenever the reactor coolant flow rate is < 354,600 gpm and > 349,200 gpm, are shown in Figure 2.6-3.2.7 DNB Margin (Technical Specification 3/4.2.6)The DNB margin shall be preserved by maintaining the cold leg temperature, pressurizer pressure, reactor coolant flow rate, and AXIAL SHAPE INDEX within the following limits: Parameter Limits Four Reactor Coolant Pumps Operations | |||
2.5 Linear Heat Rate (Technical Specification 3/4.2.1)The linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed:a. 15.1 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is 360,000 gpm.b. 15.0 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 360,000 gpm and >354,600 gpm.c. 14.9 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 354,600 gpm and __349,200 gpm.During operation with the linear heat rate being monitored | |||
.by the Excore | |||
-UNIT 2 TRM 8.1-2 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS | |||
: a. Cold Leg Temperature | : a. Cold Leg Temperature | ||
<549° | <549°F b. Pressurizer Pressure > 2225 psia*c. Reactor Coolant Flow Rate > 360,000 gpm with Linear Heat Rate and FrT limits as specified in Sections 2.5 and 2.6.or>_ 354,600 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.or> 349,200 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.d. AXIAL SHAPE INDEX Figure 2.7-1 Limit not applicable during either the THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.MILLSTONE | ||
> 2225 psia*c. Reactor Coolant Flow Rate > 360,000 gpm with Linear Heat Rate and FrT limits | -UNIT 2 TRM 8.1-3 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 3. ANALYTICAL METHODS The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: | ||
-UNIT | |||
3.1 EMF-96-029(P)(A) | 3.1 EMF-96-029(P)(A) | ||
Volumes 1 and 2, "Reactor Analysis System for | Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1 -Methodology Description, Volume 2 -Benchmarking Results," Siemens Power Corporation, January 1997.3.2 ANF-84-73 Revision 5 Appendix B(P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: | ||
Siemens Power Corporation, January 1997.3.2 ANF-84-73 Revision 5 Appendix B(P)(A), | Analysis of Chapter 15 Events," Advanced Nuclear Fuels, July 1990.3.3 XN-NF-82-21(P)(A) | ||
"Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: | Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.3.4 XN-75-32(P)(A) | ||
Analysis of Chapter 15 Events," | Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, October 1983.3.5 EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model S-RELAP5 Based," Framatome ANP, March 2001.3.6 EMF-2087(P)(A), "SEM/PWR-98: | ||
ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999.3.7 XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, October 1983.3.8 XN-NF-621(P)(A) | |||
Revision 1, "Application of Exxon Nuclear Company | Revision 1, "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, September 1983.3.9 XN-NF-82-06(P)(A) | ||
Exxon | Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, October 1986.3.10 ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.MILLSTONE | ||
Supplements 1 through 4, "Computational Procedure | -UNIT 2 TRM 8.1-4 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 3.11 XN-NF-85-92(P)(A) "Exxon Nuclear Uranium DioxidelGadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986.3.12 ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992.3.13 EMF-1961(P)(A) | ||
Exxon Nuclear Company, October 1983.3.5 EMF-2328(P)(A), | Revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000.3.14 EMF-2310(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Framatome ANP, May 2004.3.15 EMF-92-153(P)(A), Revision 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005.3.16 EMF-92-116(P)(A) | ||
"PWR Small Break LOCA Evaluation Model S-RELAP5 Based,"Framatome ANP, March 2001.3.6 EMF-2087(P)(A), | Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, February 1999.MILLSTONE | ||
"SEM/PWR-98: | -UNIT 2 TRM 8.1-5 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.i CORE OPERATING LIMITS REPORT. CYCLE 24 too, ~AN1( 7 ~. 135 Step~3 1 O0]o090 o.80 040 I~030 0.20 0.10 000't 183 pyv~r bLL+I+ _ 1;i.I- "l- 0 NIN INSETRTION LIMIT *I.I...+ :E............, ... ...... ..~..... 7 -- i .. .:... ., 1.0, .¢ '?4-144 t08 B..'41K.1 L ,1...=1 [.. L1 | ||
ECCS Evaluation Model for PWR | ..72 36 0 180 1'4 108 72 38 80 144 103 72 38 0 '130 ....... 1i4.....CE oitb steps w,,'h dra,,1 0 1 0 i P[I 1 44 103 72 36 0.08 .7......i.......36 | ||
Siemens Power Corporation, June 1999.3.7 XN-NF-78-44(NP)(A), | ........Note: Regulating CEAs that are > 176 steps withdrawn are considered fully withdrawn and are acceptable per this figure.Figure 2.4-1 CEA Insertion Limit vs. THERMIAL POWER With Four Reactor Coolant Pumps Operating MILLSTONE | ||
"A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," | -UNIT 2 TRM 8.1-6 LBDCR 15-MP2-0l0 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 120 7"......... | ||
Exxon Nuclear Company, October 1983.3.8 XN-NF-621(P)(A) | |||
Revision 1, "Exxon Nuclear DNB Correlation for PWR | |||
Exxon Nuclear Company, September 1983.3.9 XN-NF-82-06(P)(A) | |||
Revision 1 and Supplements 2, 4, and 5, "Qualification | |||
Exxon Nuclear Company, | |||
Advanced | |||
-UNIT 2 TRM 8.1-4 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS | |||
"Exxon Nuclear Uranium DioxidelGadolinia Irradiation Examination and Thermal Conductivity Results," | |||
Exxon Nuclear Company,November 1986.3.12 ANF-89-151(P)(A), | |||
"ANF-RELAP Methodology for Pressurized Water Reactors: | |||
Analysis of Non-LOCA Chapter 15 Events," | |||
Advanced Nuclear Fuels Corporation, May 1992.3.13 EMF-1961(P)(A) | |||
Revision 0, "Statistical Setpoint/Transient Methodology | |||
Siemens Power Corporation, July 2000.3.14 EMF-2310(P)(A), | |||
Revision 1, "SRP Chapter 15 Non-LOCA Methodology | |||
Framatome ANP, May 2004.3.15 EMF-92-153(P)(A), | |||
Revision 1, "HTP: Departure from Nucleate | |||
Revision 0, "Generic Mechanical Design Criteria for PWR | |||
Siemens Power Corporation, February 1999.MILLSTONE | |||
-UNIT | |||
... ...... ..~..... 7 -- i .. .:... ., 1.0, .¢ '?4-144 | |||
..72 36 0 180 1'4 108 72 | |||
........Note: Regulating CEAs that are > 176 steps withdrawn are considered fully withdrawn and are acceptable per this figure.Figure 2.4- | |||
-UNIT | |||
-......... | -......... | ||
."....U NACCEPTAB LE OPE RATIO"N --- ..... ' .. r.......I " ! ! REGION !!!i-0.08,100) iB D i 0.0Bl 100) | ."....U NACCEPTAB LE OPE RATIO"N --- ..... ' .. r.......I " ! ! REGION !!!i-0.08,100) iB D i 0.0Bl 100) I IO 8 i!RGO | ||
* i" .a, ACCEPTABLE I I.. .........a.. .....; ... .O ERA ION. .....L. ._ .......I. ..... | * i" .a, ACCEPTABLE I I.. .........a.. .....; ... .O ERA ION. .....L. ._ .......I. ..... | ||
I IoB 5 | I IoB 5 I S, B (-0.0&,1C00) | ||
I , I ,I--S 40 ........ .....-. ......;. ...(0*(0,00 101) '- .u 0 (+0.08, 100) ,LU 'j E (÷0.25, 65)120 ........ ....... Note: Point"0' isprovitedforsettingplentins~tr~irnr~relisn only. -;... ....,.......Ope n s notealloted a bore 1005% of rated power. ,,I I 1 I-0.4 -10.3 -0_2 -0_i 0 01_ 0.2 0_3 0.4-AXIAL SHAPE INDEX (AS]I)Figure 2.5- | I , I , I--S 40 ........ .....-. ......;. ...(0*(0,00 101) '- .u 0 (+0.08, 100) , LU 'j E (÷0.25, 65)120 ........ ....... Note: Point"0' isprovitedforsettingplentins~tr~irnr~relisn only. -;... ....,.......Ope n s notealloted a bore 1005% of rated power. ,, I I 1 I-0.4 -10.3 -0_2 -0_i 0 01_ 0.2 0_3 0.4-AXIAL SHAPE INDEX (AS]I)Figure 2.5-1 AXIAL SHAPE INDEX vs.PERCENT OF ALLOWABLE POWER LEVEL MILLSTONE | ||
-UNIT | -UNIT 2 TRM 8.1-7 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 100- (1.690, 160)1[1.78B ......UNACCEP:TABLE | ||
.,90- ...; ........... | ., 90- ...; ........... | ||
oU. 4 ..., .....,... .OPRAIO-a " | oU. 4 ..., .....,... .OPRAIO-a " | ||
* a I £ "" O E A IN ". .... a ...' ~REGION '80.........................-..-.,. -- ............................... | * a I £ "" O E A IN ". .... a ...' ~REGION '80.........................-..-.,. -- ............................... | ||
'-..... .".....1. | '-..... .".....1. | ||
.... ....a a a a I i I a a a a-70................- | .... ....a a a a I i I a a a a-70................- | ||
... ... ... ... ... ..-U 7o- .a . | ... ... ... ... ... ..-U 7o- .a .a i a u i I n a a a a i a P R TO a.... a a a a a.....S5...... ...... ......OEATO .... ...... ... .. .. .....O I 3 n | ||
...... ......OEATO .... ...... ... .. .. .....O I 3 n | |||
* a a a a a a | * a a a a a a | ||
* a | * a a P240......................... | ||
............................ | ............................ | ||
a..a..a...a-...... | a..a..a...a-...... | ||
n 30 ........ ..... .. .. ... .. ... .. .... .. .. .. .. .. .... ....... ..... ....iio l m a u a a a a--* a a a a a I a a ai | n 30 ........ ..... .. .. ... .. ... .. .... .. .. .. .. .. .... ....... ..... ....iio l m a u a a a a--* a a a a a I a a ai | ||
* a | * a ai 20..........a | ||
....0 m | ....0 m | ||
* I I I I p | * I I I I p I 1.69 1.70 1.71 1.72 1.73 1.74 1.75 1.76 1.77 1.78 1.79 1.80 1.81 1.82 1.83 1.84 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR- FrT Note: The FrT limit should be reduced for reactor coolant flow.rates __ 349,200 gpm and < 360,000 gpm (see Section 2.6).Figure 2.6-1 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable RATED THERMAL POWER For Reactor Coolant Flow Rates >360,000 gpm MILLSTONE | ||
-UNIT 2 TRM 8.1-8 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS | -UNIT 2 TRM 8.1-8 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 100 .( .84 , , , ___* 11.849,70)" UACETBL: I U I OPi Al1[1lN I SI TOTALRLTRON EDITER DRAILPEKN'ACO-F5 .. ... ... .* ... ... F igure... 2.6..-2 ....L. .........., ..TTLU RODEDGINTERTDRDAPAIGFCO vsrAlwal RTD HRMLPOE Ocobr ,201 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 REG.IONIO n ! s l I i C i C C I C I I I I C I I | ||
" UACETBL:I U I OPi Al1[1lN I | * C .i CI 0)l l I I I I I £83 0,. .= l.... ..I........,.....= | ||
2.6..-2 ....L. .........., ..TTLU RODEDGINTERTDRDAPAIGFCO vsrAlwal RTD | |||
* C .i | |||
..=........a.a..= | ..=........a.a..= | ||
.=........i...= | .=........i...= | ||
... =.=.I. ..-........ | ... =.=.I. ..-........ | ||
= ..=............ | = ..=............ | ||
C C C C C I C n ., .I I I I I I I C I I I I | C C C C C I C n ., .I I I I I I I C I I I I I S.78.J.O I n I. CC i I C l I C I 10 I I I I I C C I l I I I C.I.I I C C C C II C I C C C C 0 II p I I I p TOTLURCCDIEGTE DA PEAIN mAT i- F m ,, .October 6 , , 21 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIIMITS REPORT, CYCLE 24 1.20 -----or -.. ..". ...._ ....., T 'I-'. .I tI.. .SI I I 1.00 "--4UNACCEPTABLE T (-.10,,1.0) -L7 "-"-q --- i UNCEPA... OPERATION | ||
-L7 "-"-q --- i UNCEPA... OPERATION | "-- .. .. .- ....-- ;- ....O 4 .)--- i UN CCP T BERA N ...I REGION __ 7, T- PEATON 4--[%.J. r. J REGION 4 / i .. Tl. ...... .[!......I... | ||
"-- .. .. .- ....-- ;- ....O 4 .)--- i UN CCP T BERA N ...I REGION __ 7, T- PEATON 4--[%.J. r. J | ..--Il ... ...I n0.50-iI I iREGION. i i i....- -i .. .... It + ....+/- .. .. ..4 ....F ... -F ,-:1: [.o i~ I i i , I' T ' ' -" ...... .. ... '1i -- ..-0.5 0.5 -0.4 . -0.1 0 0.1 0.2 09 0.4 0.5 056 AXIAL SHAPE INDEX (ASI).Figure 2.7-1 AXIAL SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating MILLSTONE | ||
..--Il ... ... | -UNIT 2 TRM 8.1-11 LBDCR 15-MP2-01O October 6, 2015 | ||
i i i....- -i .. .... It + ....+/- .. .. ..4 ....F ... -F ,-:1: [.o i~ I i i ,I' T ' ' -" ...... .. ... '1i -- ..-0.5 0.5 -0.4 . -0.1 0 0.1 0.2 09 0.4 0.5 | |||
-UNIT | |||
Dominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT | Dominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dom.com NOV , U. S. Nuclear Regulatory Commission Attention: | ||
P.O. Box | Document Control Desk Washington, DC 20555 Serial No.NSS&L/MLC Docket No.License No.15-520 R0 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT. | ||
Document Control | INC.MILLSTONE POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT. CYCLE 24 In accordance with the Millstone Power Station Unit 2 (MPS2) Technical Specifications (TSs), Section 6.9.1 .8.d, Dominion Nuclear Connecticut, Inc., hereby submits, as an enclosure, the Cycle 24 Core Operating Limits Report (COLR).The MPS2 COLR has been revised to include the following: | ||
INC.MILLSTONE POWER STATION UNIT | * Revision of page headers to reflect Cycle 24.The Cycle 24 COLR has been incorporated into the MPS2 Technical Requirements Manual.If you have any questions or require additional information, please contact Mr. Thomas G.Cleary at (860) 447-1791 Ext. 3232.Sincerely, D. B. Blakeney Director, Nuclear Station Safety and Licensing | ||
* Revision of page headers to reflect Cycle 24.The Cycle 24 COLR has been incorporated into the MPS2 Technical Requirements Manual.If you have any questions or require additional information, please contact Mr. Thomas G.Cleary at (860) 447-1791 Ext. 3232.Sincerely, D. B. | -Millstone | ||
-Millstone | |||
==Enclosure:== | ==Enclosure:== | ||
Core Operating Limits Report, Cycle | Core Operating Limits Report, Cycle 24 Commitments made in this letter: None Th¶-p Serial No. 15-520 Docket No. 50-336 MPS2 Cycle 24 COLR Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd. Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Serial No. 15-520 Docket No. 50-336 ENCLOSURE CORE OPERATING LIMITS REPORT, CYCLE 24 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 2 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 1. CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT for Millstone 2 has been prepared in accordance with the requirements of Technical Specification 6.9.1.8 a through 6.9.1.8 d.The Technical Specifications affected by this report are listed below: Section 2.1 2.2 2.3 2.4 2.5 2.6 Specification 3/4.1.1.1 3/4.1.1.4 3/4.1.3.6 3/4.2.1 3/4.2.3 3/4.2.6 SHUTDOWN MARGIN -(SDM)Deleted (Ref. License Amendment 280)Moderator Temperature Coefficient (MTC)Regulating CEA Insertion Limits Linear Heat Rate TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR --FrT DNB Margin 2.7 Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of the Technical Specifications. | ||
: 2. OPERATING | : 2. OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. | ||
These limits have been developed using | These limits have been developed using the NRC approved methodologies specified in Section 3.2.1 SHUTDOWN MARGIN -(5DM).(Specification 3/4.1.1.1) | ||
The SHUTDOWN MARGIN shall be 3.6% AK/ | The SHUTDOWN MARGIN shall be 3.6% AK/K 2.2 Deleted 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.4) | ||
The moderator temperature coefficient shall be:a. Less positive than 0.7x1 0-4 AK/K/°F whenever THERMAL POWER is <70% | The moderator temperature coefficient shall be: a. Less positive than 0.7x1 0-4 AK/K/°F whenever THERMAL POWER is <70% of RATED THERMAL POWER, b. Less positive than 0.4x10-4 AK/K/°F whenever THERMAL POWER is > 70%of RATED THERMAL POWER, c. Less negative than -3.2x10-4 AK/K/°F at RATED THERMAL POWER.MILLSTONE | ||
-UNIT | -UNIT 2 TRM 8.1-1 LBDCR 15-MP2-010 October 6 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 2.4 Regulating CEA Insertion Limits (Technical Specification 3/4.1.3.6) | ||
The regulating CEA groups shall be limited to the withdrawal sequence and to | The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown in Figure 2.4-1. CEA insertion between the Long Term Steady State Insertion Limits and the Transient Insertion Limits is restricted to: a. <4 hours per 24 hour interval, b. <5 Effective Full Power Days per 30 Effective Full Power Day interval, and c. < 14 Effective Full Power Days per 365 Effective Full Power Day interval.2.5 Linear Heat Rate (Technical Specification 3/4.2.1)The linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed: a. 15.1 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is 360,000 gpm.b. 15.0 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 360,000 gpm and >354,600 gpm.c. 14.9 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 354,600 gpm and __349,200 gpm.During operation with the linear heat rate being monitored .by the Excore Detector Monitoring System, the AXIAL S.HAP. E INDEX shall remain within the limits of Figure 2.5-1.During operation with the linear heat rate being monitored by the Incore Detector Monitor System, the alarm setpoints shall be adjusted to less than or equal to the limit when the following factors are appropriately included in the setting of the alarms: 1. A measurement-calculational uncertainty factor of 1 .07, 2. An engineering uncertainty factor of 1.03, and 3. A THERMAL POWER measurement uncertainty factor of 1.02.MILLSTONE | ||
-UNIT 2 TRM 8.1-2 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR -- FrT (Technical Specification 314.2.3)The calculated value of FrT at RATED THERMAL POWER shall be:_< 1.690 whenever the reactor coolant flow rate is >_ 360,000 gpm._< 1 .664 whenever the reactor coolant flow rate is < 360,000 gpm and > 354,600 gpm._< 1 .639 whenever the reactor coolant flow rate is < 354,600 gpm and > 349,200 gpm.2.6.1 The Power Dependent FrTr limits, whenever the reactor coolant flow rate is > 360,000 gpm, are shown in Figure 2.6-1.2.6.2 The Power Dependent FrT limits, whenever the reactor coolant flow rate is < 360,000 gpm and > 354,600 gpm, are shown in Figure 2.6-2.2.6.3 The Power Dependent FrTr limits, whenever the reactor coolant flow rate is < 354,600 gpm and > 349,200 gpm, are shown in Figure 2.6-3.2.7 DNB Margin (Technical Specification 3/4.2.6)The DNB margin shall be preserved by maintaining the cold leg temperature, pressurizer pressure, reactor coolant flow rate, and AXIAL SHAPE INDEX within the following limits: Parameter Limits Four Reactor Coolant Pumps Operations | |||
2.5 Linear Heat Rate (Technical Specification 3/4.2.1)The linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed:a. 15.1 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is 360,000 gpm.b. 15.0 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 360,000 gpm and >354,600 gpm.c. 14.9 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 354,600 gpm and __349,200 gpm.During operation with the linear heat rate being monitored | |||
.by the Excore | |||
-UNIT 2 TRM 8.1-2 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS | |||
: a. Cold Leg Temperature | : a. Cold Leg Temperature | ||
<549° | <549°F b. Pressurizer Pressure > 2225 psia*c. Reactor Coolant Flow Rate > 360,000 gpm with Linear Heat Rate and FrT limits as specified in Sections 2.5 and 2.6.or>_ 354,600 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.or> 349,200 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.d. AXIAL SHAPE INDEX Figure 2.7-1 Limit not applicable during either the THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.MILLSTONE | ||
> 2225 psia*c. Reactor Coolant Flow Rate > 360,000 gpm with Linear Heat Rate and FrT limits | -UNIT 2 TRM 8.1-3 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 3. ANALYTICAL METHODS The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents: | ||
-UNIT | |||
3.1 EMF-96-029(P)(A) | 3.1 EMF-96-029(P)(A) | ||
Volumes 1 and 2, "Reactor Analysis System for | Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1 -Methodology Description, Volume 2 -Benchmarking Results," Siemens Power Corporation, January 1997.3.2 ANF-84-73 Revision 5 Appendix B(P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: | ||
Siemens Power Corporation, January 1997.3.2 ANF-84-73 Revision 5 Appendix B(P)(A), | Analysis of Chapter 15 Events," Advanced Nuclear Fuels, July 1990.3.3 XN-NF-82-21(P)(A) | ||
"Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: | Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.3.4 XN-75-32(P)(A) | ||
Analysis of Chapter 15 Events," | Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, October 1983.3.5 EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model S-RELAP5 Based," Framatome ANP, March 2001.3.6 EMF-2087(P)(A), "SEM/PWR-98: | ||
ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999.3.7 XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, October 1983.3.8 XN-NF-621(P)(A) | |||
Revision 1, "Application of Exxon Nuclear Company | Revision 1, "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, September 1983.3.9 XN-NF-82-06(P)(A) | ||
Exxon | Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, October 1986.3.10 ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.MILLSTONE | ||
Supplements 1 through 4, "Computational Procedure | -UNIT 2 TRM 8.1-4 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 3.11 XN-NF-85-92(P)(A) "Exxon Nuclear Uranium DioxidelGadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986.3.12 ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992.3.13 EMF-1961(P)(A) | ||
Exxon Nuclear Company, October 1983.3.5 EMF-2328(P)(A), | Revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000.3.14 EMF-2310(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Framatome ANP, May 2004.3.15 EMF-92-153(P)(A), Revision 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005.3.16 EMF-92-116(P)(A) | ||
"PWR Small Break LOCA Evaluation Model S-RELAP5 Based,"Framatome ANP, March 2001.3.6 EMF-2087(P)(A), | Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, February 1999.MILLSTONE | ||
"SEM/PWR-98: | -UNIT 2 TRM 8.1-5 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.i CORE OPERATING LIMITS REPORT. CYCLE 24 too, ~AN1( 7 ~. 135 Step~3 1 O0]o090 o.80 040 I~030 0.20 0.10 000't 183 pyv~r bLL+I+ _ 1;i.I- "l- 0 NIN INSETRTION LIMIT *I.I...+ :E............, ... ...... ..~..... 7 -- i .. .:... ., 1.0, .¢ '?4-144 t08 B..'41K.1 L ,1...=1 [.. L1 | ||
ECCS Evaluation Model for PWR | ..72 36 0 180 1'4 108 72 38 80 144 103 72 38 0 '130 ....... 1i4.....CE oitb steps w,,'h dra,,1 0 1 0 i P[I 1 44 103 72 36 0.08 .7......i.......36 | ||
Siemens Power Corporation, June 1999.3.7 XN-NF-78-44(NP)(A), | ........Note: Regulating CEAs that are > 176 steps withdrawn are considered fully withdrawn and are acceptable per this figure.Figure 2.4-1 CEA Insertion Limit vs. THERMIAL POWER With Four Reactor Coolant Pumps Operating MILLSTONE | ||
"A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," | -UNIT 2 TRM 8.1-6 LBDCR 15-MP2-0l0 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 120 7"......... | ||
Exxon Nuclear Company, October 1983.3.8 XN-NF-621(P)(A) | |||
Revision 1, "Exxon Nuclear DNB Correlation for PWR | |||
Exxon Nuclear Company, September 1983.3.9 XN-NF-82-06(P)(A) | |||
Revision 1 and Supplements 2, 4, and 5, "Qualification | |||
Exxon Nuclear Company, | |||
Advanced | |||
-UNIT 2 TRM 8.1-4 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS | |||
"Exxon Nuclear Uranium DioxidelGadolinia Irradiation Examination and Thermal Conductivity Results," | |||
Exxon Nuclear Company,November 1986.3.12 ANF-89-151(P)(A), | |||
"ANF-RELAP Methodology for Pressurized Water Reactors: | |||
Analysis of Non-LOCA Chapter 15 Events," | |||
Advanced Nuclear Fuels Corporation, May 1992.3.13 EMF-1961(P)(A) | |||
Revision 0, "Statistical Setpoint/Transient Methodology | |||
Siemens Power Corporation, July 2000.3.14 EMF-2310(P)(A), | |||
Revision 1, "SRP Chapter 15 Non-LOCA Methodology | |||
Framatome ANP, May 2004.3.15 EMF-92-153(P)(A), | |||
Revision 1, "HTP: Departure from Nucleate | |||
Revision 0, "Generic Mechanical Design Criteria for PWR | |||
Siemens Power Corporation, February 1999.MILLSTONE | |||
-UNIT | |||
... ...... ..~..... 7 -- i .. .:... ., 1.0, .¢ '?4-144 | |||
..72 36 0 180 1'4 108 72 | |||
........Note: Regulating CEAs that are > 176 steps withdrawn are considered fully withdrawn and are acceptable per this figure.Figure 2.4- | |||
-UNIT | |||
-......... | -......... | ||
."....U NACCEPTAB LE OPE RATIO"N --- ..... ' .. r.......I " ! ! REGION !!!i-0.08,100) iB D i 0.0Bl 100) | ."....U NACCEPTAB LE OPE RATIO"N --- ..... ' .. r.......I " ! ! REGION !!!i-0.08,100) iB D i 0.0Bl 100) I IO 8 i!RGO | ||
* i" .a, ACCEPTABLE I I.. .........a.. .....; ... .O ERA ION. .....L. ._ .......I. ..... | * i" .a, ACCEPTABLE I I.. .........a.. .....; ... .O ERA ION. .....L. ._ .......I. ..... | ||
I IoB 5 | I IoB 5 I S, B (-0.0&,1C00) | ||
I , I ,I--S 40 ........ .....-. ......;. ...(0*(0,00 101) '- .u 0 (+0.08, 100) ,LU 'j E (÷0.25, 65)120 ........ ....... Note: Point"0' isprovitedforsettingplentins~tr~irnr~relisn only. -;... ....,.......Ope n s notealloted a bore 1005% of rated power. ,,I I 1 I-0.4 -10.3 -0_2 -0_i 0 01_ 0.2 0_3 0.4-AXIAL SHAPE INDEX (AS]I)Figure 2.5- | I , I , I--S 40 ........ .....-. ......;. ...(0*(0,00 101) '- .u 0 (+0.08, 100) , LU 'j E (÷0.25, 65)120 ........ ....... Note: Point"0' isprovitedforsettingplentins~tr~irnr~relisn only. -;... ....,.......Ope n s notealloted a bore 1005% of rated power. ,, I I 1 I-0.4 -10.3 -0_2 -0_i 0 01_ 0.2 0_3 0.4-AXIAL SHAPE INDEX (AS]I)Figure 2.5-1 AXIAL SHAPE INDEX vs.PERCENT OF ALLOWABLE POWER LEVEL MILLSTONE | ||
-UNIT | -UNIT 2 TRM 8.1-7 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 100- (1.690, 160)1[1.78B ......UNACCEP:TABLE | ||
.,90- ...; ........... | ., 90- ...; ........... | ||
oU. 4 ..., .....,... .OPRAIO-a " | oU. 4 ..., .....,... .OPRAIO-a " | ||
* a I £ "" O E A IN ". .... a ...' ~REGION '80.........................-..-.,. -- ............................... | * a I £ "" O E A IN ". .... a ...' ~REGION '80.........................-..-.,. -- ............................... | ||
'-..... .".....1. | '-..... .".....1. | ||
.... ....a a a a I i I a a a a-70................- | .... ....a a a a I i I a a a a-70................- | ||
... ... ... ... ... ..-U 7o- .a . | ... ... ... ... ... ..-U 7o- .a .a i a u i I n a a a a i a P R TO a.... a a a a a.....S5...... ...... ......OEATO .... ...... ... .. .. .....O I 3 n | ||
...... ......OEATO .... ...... ... .. .. .....O I 3 n | |||
* a a a a a a | * a a a a a a | ||
* a | * a a P240......................... | ||
............................ | ............................ | ||
a..a..a...a-...... | a..a..a...a-...... | ||
n 30 ........ ..... .. .. ... .. ... .. .... .. .. .. .. .. .... ....... ..... ....iio l m a u a a a a--* a a a a a I a a ai | n 30 ........ ..... .. .. ... .. ... .. .... .. .. .. .. .. .... ....... ..... ....iio l m a u a a a a--* a a a a a I a a ai | ||
* a | * a ai 20..........a | ||
....0 m | ....0 m | ||
* I I I I p | * I I I I p I 1.69 1.70 1.71 1.72 1.73 1.74 1.75 1.76 1.77 1.78 1.79 1.80 1.81 1.82 1.83 1.84 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR- FrT Note: The FrT limit should be reduced for reactor coolant flow.rates __ 349,200 gpm and < 360,000 gpm (see Section 2.6).Figure 2.6-1 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable RATED THERMAL POWER For Reactor Coolant Flow Rates >360,000 gpm MILLSTONE | ||
-UNIT 2 TRM 8.1-8 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS | -UNIT 2 TRM 8.1-8 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 100 .( .84 , , , ___* 11.849,70)" UACETBL: I U I OPi Al1[1lN I SI TOTALRLTRON EDITER DRAILPEKN'ACO-F5 .. ... ... .* ... ... F igure... 2.6..-2 ....L. .........., ..TTLU RODEDGINTERTDRDAPAIGFCO vsrAlwal RTD HRMLPOE Ocobr ,201 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 REG.IONIO n ! s l I i C i C C I C I I I I C I I | ||
" UACETBL:I U I OPi Al1[1lN I | * C .i CI 0)l l I I I I I £83 0,. .= l.... ..I........,.....= | ||
2.6..-2 ....L. .........., ..TTLU RODEDGINTERTDRDAPAIGFCO vsrAlwal RTD | |||
* C .i | |||
..=........a.a..= | ..=........a.a..= | ||
.=........i...= | .=........i...= | ||
... =.=.I. ..-........ | ... =.=.I. ..-........ | ||
= ..=............ | = ..=............ | ||
C C C C C I C n ., .I I I I I I I C I I I I | C C C C C I C n ., .I I I I I I I C I I I I I S.78.J.O I n I. CC i I C l I C I 10 I I I I I C C I l I I I C.I.I I C C C C II C I C C C C 0 II p I I I p TOTLURCCDIEGTE DA PEAIN mAT i- F m ,, .October 6 , , 21 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIIMITS REPORT, CYCLE 24 1.20 -----or -.. ..". ...._ ....., T 'I-'. .I tI.. .SI I I 1.00 "--4UNACCEPTABLE T (-.10,,1.0) -L7 "-"-q --- i UNCEPA... OPERATION | ||
-L7 "-"-q --- i UNCEPA... OPERATION | "-- .. .. .- ....-- ;- ....O 4 .)--- i UN CCP T BERA N ...I REGION __ 7, T- PEATON 4--[%.J. r. J REGION 4 / i .. Tl. ...... .[!......I... | ||
"-- .. .. .- ....-- ;- ....O 4 .)--- i UN CCP T BERA N ...I REGION __ 7, T- PEATON 4--[%.J. r. J | ..--Il ... ...I n0.50-iI I iREGION. i i i....- -i .. .... It + ....+/- .. .. ..4 ....F ... -F ,-:1: [.o i~ I i i , I' T ' ' -" ...... .. ... '1i -- ..-0.5 0.5 -0.4 . -0.1 0 0.1 0.2 09 0.4 0.5 056 AXIAL SHAPE INDEX (ASI).Figure 2.7-1 AXIAL SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating MILLSTONE | ||
..--Il ... ... | -UNIT 2 TRM 8.1-11 LBDCR 15-MP2-01O October 6, 2015}} | ||
i i i....- -i .. .... It + ....+/- .. .. ..4 ....F ... -F ,-:1: [.o i~ I i i ,I' T ' ' -" ...... .. ... '1i -- ..-0.5 0.5 -0.4 . -0.1 0 0.1 0.2 09 0.4 0.5 | |||
-UNIT | |||
Revision as of 20:47, 8 July 2018
| ML15320A015 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/04/2015 |
| From: | Blakeney D B Dominion Nuclear Connecticut |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 15-520 | |
| Download: ML15320A015 (14) | |
Text
Dominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dom.com NOV , U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 Serial No.NSS&L/MLC Docket No.License No.15-520 R0 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT.
INC.MILLSTONE POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT. CYCLE 24 In accordance with the Millstone Power Station Unit 2 (MPS2) Technical Specifications (TSs), Section 6.9.1 .8.d, Dominion Nuclear Connecticut, Inc., hereby submits, as an enclosure, the Cycle 24 Core Operating Limits Report (COLR).The MPS2 COLR has been revised to include the following:
- Revision of page headers to reflect Cycle 24.The Cycle 24 COLR has been incorporated into the MPS2 Technical Requirements Manual.If you have any questions or require additional information, please contact Mr. Thomas G.Cleary at (860) 447-1791 Ext. 3232.Sincerely, D. B. Blakeney Director, Nuclear Station Safety and Licensing
-Millstone
Enclosure:
Core Operating Limits Report, Cycle 24 Commitments made in this letter: None Th¶-p Serial No.15-520 Docket No. 50-336 MPS2 Cycle 24 COLR Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd. Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Serial No.15-520 Docket No. 50-336 ENCLOSURE CORE OPERATING LIMITS REPORT, CYCLE 24 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 2 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 1. CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT for Millstone 2 has been prepared in accordance with the requirements of Technical Specification 6.9.1.8 a through 6.9.1.8 d.The Technical Specifications affected by this report are listed below: Section 2.1 2.2 2.3 2.4 2.5 2.6 Specification 3/4.1.1.1 3/4.1.1.4 3/4.1.3.6 3/4.2.1 3/4.2.3 3/4.2.6 SHUTDOWN MARGIN -(SDM)Deleted (Ref. License Amendment 280)Moderator Temperature Coefficient (MTC)Regulating CEA Insertion Limits Linear Heat Rate TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR --FrT DNB Margin 2.7 Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of the Technical Specifications.
- 2. OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections.
These limits have been developed using the NRC approved methodologies specified in Section 3.2.1 SHUTDOWN MARGIN -(5DM).(Specification 3/4.1.1.1)
The SHUTDOWN MARGIN shall be 3.6% AK/K 2.2 Deleted 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.4)
The moderator temperature coefficient shall be: a. Less positive than 0.7x1 0-4 AK/K/°F whenever THERMAL POWER is <70% of RATED THERMAL POWER, b. Less positive than 0.4x10-4 AK/K/°F whenever THERMAL POWER is > 70%of RATED THERMAL POWER, c. Less negative than -3.2x10-4 AK/K/°F at RATED THERMAL POWER.MILLSTONE
-UNIT 2 TRM 8.1-1 LBDCR 15-MP2-010 October 6 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 2.4 Regulating CEA Insertion Limits (Technical Specification 3/4.1.3.6)
The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown in Figure 2.4-1. CEA insertion between the Long Term Steady State Insertion Limits and the Transient Insertion Limits is restricted to: a. <4 hours per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval, b. <5 Effective Full Power Days per 30 Effective Full Power Day interval, and c. < 14 Effective Full Power Days per 365 Effective Full Power Day interval.2.5 Linear Heat Rate (Technical Specification 3/4.2.1)The linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed: a. 15.1 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is 360,000 gpm.b. 15.0 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 360,000 gpm and >354,600 gpm.c. 14.9 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 354,600 gpm and __349,200 gpm.During operation with the linear heat rate being monitored .by the Excore Detector Monitoring System, the AXIAL S.HAP. E INDEX shall remain within the limits of Figure 2.5-1.During operation with the linear heat rate being monitored by the Incore Detector Monitor System, the alarm setpoints shall be adjusted to less than or equal to the limit when the following factors are appropriately included in the setting of the alarms: 1. A measurement-calculational uncertainty factor of 1 .07, 2. An engineering uncertainty factor of 1.03, and 3. A THERMAL POWER measurement uncertainty factor of 1.02.MILLSTONE
-UNIT 2 TRM 8.1-2 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR -- FrT (Technical Specification 314.2.3)The calculated value of FrT at RATED THERMAL POWER shall be:_< 1.690 whenever the reactor coolant flow rate is >_ 360,000 gpm._< 1 .664 whenever the reactor coolant flow rate is < 360,000 gpm and > 354,600 gpm._< 1 .639 whenever the reactor coolant flow rate is < 354,600 gpm and > 349,200 gpm.2.6.1 The Power Dependent FrTr limits, whenever the reactor coolant flow rate is > 360,000 gpm, are shown in Figure 2.6-1.2.6.2 The Power Dependent FrT limits, whenever the reactor coolant flow rate is < 360,000 gpm and > 354,600 gpm, are shown in Figure 2.6-2.2.6.3 The Power Dependent FrTr limits, whenever the reactor coolant flow rate is < 354,600 gpm and > 349,200 gpm, are shown in Figure 2.6-3.2.7 DNB Margin (Technical Specification 3/4.2.6)The DNB margin shall be preserved by maintaining the cold leg temperature, pressurizer pressure, reactor coolant flow rate, and AXIAL SHAPE INDEX within the following limits: Parameter Limits Four Reactor Coolant Pumps Operations
- a. Cold Leg Temperature
<549°F b. Pressurizer Pressure > 2225 psia*c. Reactor Coolant Flow Rate > 360,000 gpm with Linear Heat Rate and FrT limits as specified in Sections 2.5 and 2.6.or>_ 354,600 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.or> 349,200 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.d. AXIAL SHAPE INDEX Figure 2.7-1 Limit not applicable during either the THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.MILLSTONE
-UNIT 2 TRM 8.1-3 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 3. ANALYTICAL METHODS The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
3.1 EMF-96-029(P)(A)
Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1 -Methodology Description, Volume 2 -Benchmarking Results," Siemens Power Corporation, January 1997.3.2 ANF-84-73 Revision 5 Appendix B(P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors:
Analysis of Chapter 15 Events," Advanced Nuclear Fuels, July 1990.3.3 XN-NF-82-21(P)(A)
Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.3.4 XN-75-32(P)(A)
Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, October 1983.3.5 EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model S-RELAP5 Based," Framatome ANP, March 2001.3.6 EMF-2087(P)(A), "SEM/PWR-98:
ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999.3.7 XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, October 1983.3.8 XN-NF-621(P)(A)
Revision 1, "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, September 1983.3.9 XN-NF-82-06(P)(A)
Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, October 1986.3.10 ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.MILLSTONE
-UNIT 2 TRM 8.1-4 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 3.11 XN-NF-85-92(P)(A) "Exxon Nuclear Uranium DioxidelGadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986.3.12 ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992.3.13 EMF-1961(P)(A)
Revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000.3.14 EMF-2310(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Framatome ANP, May 2004.3.15 EMF-92-153(P)(A), Revision 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005.3.16 EMF-92-116(P)(A)
Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, February 1999.MILLSTONE
-UNIT 2 TRM 8.1-5 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.i CORE OPERATING LIMITS REPORT. CYCLE 24 too, ~AN1( 7 ~. 135 Step~3 1 O0]o090 o.80 040 I~030 0.20 0.10 000't 183 pyv~r bLL+I+ _ 1;i.I- "l- 0 NIN INSETRTION LIMIT *I.I...+ :E............, ... ...... ..~..... 7 -- i .. .:... ., 1.0, .¢ '?4-144 t08 B..'41K.1 L ,1...=1 [.. L1
..72 36 0 180 1'4 108 72 38 80 144 103 72 38 0 '130 ....... 1i4.....CE oitb steps w,,'h dra,,1 0 1 0 i P[I 1 44 103 72 36 0.08 .7......i.......36
........Note: Regulating CEAs that are > 176 steps withdrawn are considered fully withdrawn and are acceptable per this figure.Figure 2.4-1 CEA Insertion Limit vs. THERMIAL POWER With Four Reactor Coolant Pumps Operating MILLSTONE
-UNIT 2 TRM 8.1-6 LBDCR 15-MP2-0l0 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 120 7".........
-.........
."....U NACCEPTAB LE OPE RATIO"N --- ..... ' .. r.......I " ! ! REGION !!!i-0.08,100) iB D i 0.0Bl 100) I IO 8 i!RGO
- i" .a, ACCEPTABLE I I.. .........a.. .....; ... .O ERA ION. .....L. ._ .......I. .....
I IoB 5 I S, B (-0.0&,1C00)
I , I , I--S 40 ........ .....-. ......;. ...(0*(0,00 101) '- .u 0 (+0.08, 100) , LU 'j E (÷0.25, 65)120 ........ ....... Note: Point"0' isprovitedforsettingplentins~tr~irnr~relisn only. -;... ....,.......Ope n s notealloted a bore 1005% of rated power. ,, I I 1 I-0.4 -10.3 -0_2 -0_i 0 01_ 0.2 0_3 0.4-AXIAL SHAPE INDEX (AS]I)Figure 2.5-1 AXIAL SHAPE INDEX vs.PERCENT OF ALLOWABLE POWER LEVEL MILLSTONE
-UNIT 2 TRM 8.1-7 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 100- (1.690, 160)1[1.78B ......UNACCEP:TABLE
., 90- ...; ...........
oU. 4 ..., .....,... .OPRAIO-a "
- a I £ "" O E A IN ". .... a ...' ~REGION '80.........................-..-.,. -- ...............................
'-..... .".....1.
.... ....a a a a I i I a a a a-70................-
... ... ... ... ... ..-U 7o- .a .a i a u i I n a a a a i a P R TO a.... a a a a a.....S5...... ...... ......OEATO .... ...... ... .. .. .....O I 3 n
- a a a a a a
- a a P240.........................
............................
a..a..a...a-......
n 30 ........ ..... .. .. ... .. ... .. .... .. .. .. .. .. .... ....... ..... ....iio l m a u a a a a--* a a a a a I a a ai
- a ai 20..........a
....0 m
- I I I I p I 1.69 1.70 1.71 1.72 1.73 1.74 1.75 1.76 1.77 1.78 1.79 1.80 1.81 1.82 1.83 1.84 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR- FrT Note: The FrT limit should be reduced for reactor coolant flow.rates __ 349,200 gpm and < 360,000 gpm (see Section 2.6).Figure 2.6-1 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable RATED THERMAL POWER For Reactor Coolant Flow Rates >360,000 gpm MILLSTONE
-UNIT 2 TRM 8.1-8 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 100 .( .84 , , , ___* 11.849,70)" UACETBL: I U I OPi Al1[1lN I SI TOTALRLTRON EDITER DRAILPEKN'ACO-F5 .. ... ... .* ... ... F igure... 2.6..-2 ....L. .........., ..TTLU RODEDGINTERTDRDAPAIGFCO vsrAlwal RTD HRMLPOE Ocobr ,201 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 REG.IONIO n ! s l I i C i C C I C I I I I C I I
- C .i CI 0)l l I I I I I £83 0,. .= l.... ..I........,.....=
..=........a.a..=
.=........i...=
... =.=.I. ..-........
= ..=............
C C C C C I C n ., .I I I I I I I C I I I I I S.78.J.O I n I. CC i I C l I C I 10 I I I I I C C I l I I I C.I.I I C C C C II C I C C C C 0 II p I I I p TOTLURCCDIEGTE DA PEAIN mAT i- F m ,, .October 6 , , 21 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIIMITS REPORT, CYCLE 24 1.20 -----or -.. ..". ...._ ....., T 'I-'. .I tI.. .SI I I 1.00 "--4UNACCEPTABLE T (-.10,,1.0) -L7 "-"-q --- i UNCEPA... OPERATION
"-- .. .. .- ....-- ;- ....O 4 .)--- i UN CCP T BERA N ...I REGION __ 7, T- PEATON 4--[%.J. r. J REGION 4 / i .. Tl. ...... .[!......I...
..--Il ... ...I n0.50-iI I iREGION. i i i....- -i .. .... It + ....+/- .. .. ..4 ....F ... -F ,-:1: [.o i~ I i i , I' T ' ' -" ...... .. ... '1i -- ..-0.5 0.5 -0.4 . -0.1 0 0.1 0.2 09 0.4 0.5 056 AXIAL SHAPE INDEX (ASI).Figure 2.7-1 AXIAL SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating MILLSTONE
-UNIT 2 TRM 8.1-11 LBDCR 15-MP2-01O October 6, 2015
Dominion Nuclear Connecticut, Inc.Rope Ferry Rd., Waterford, CT 06385 Mailing Address: P.O. Box 128 Waterford, CT 06385 dom.com NOV , U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555 Serial No.NSS&L/MLC Docket No.License No.15-520 R0 50-336 DPR-65 DOMINION NUCLEAR CONNECTICUT.
INC.MILLSTONE POWER STATION UNIT 2 CORE OPERATING LIMITS REPORT. CYCLE 24 In accordance with the Millstone Power Station Unit 2 (MPS2) Technical Specifications (TSs), Section 6.9.1 .8.d, Dominion Nuclear Connecticut, Inc., hereby submits, as an enclosure, the Cycle 24 Core Operating Limits Report (COLR).The MPS2 COLR has been revised to include the following:
- Revision of page headers to reflect Cycle 24.The Cycle 24 COLR has been incorporated into the MPS2 Technical Requirements Manual.If you have any questions or require additional information, please contact Mr. Thomas G.Cleary at (860) 447-1791 Ext. 3232.Sincerely, D. B. Blakeney Director, Nuclear Station Safety and Licensing
-Millstone
Enclosure:
Core Operating Limits Report, Cycle 24 Commitments made in this letter: None Th¶-p Serial No.15-520 Docket No. 50-336 MPS2 Cycle 24 COLR Page 2 of 2 cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd. Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager -Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Serial No.15-520 Docket No. 50-336 ENCLOSURE CORE OPERATING LIMITS REPORT, CYCLE 24 DOMINION NUCLEAR CONNECTICUT, INC.MILLSTONE POWER STATION UNIT 2 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 1. CORE OPERATING LIMITS REPORT This CORE OPERATING LIMITS REPORT for Millstone 2 has been prepared in accordance with the requirements of Technical Specification 6.9.1.8 a through 6.9.1.8 d.The Technical Specifications affected by this report are listed below: Section 2.1 2.2 2.3 2.4 2.5 2.6 Specification 3/4.1.1.1 3/4.1.1.4 3/4.1.3.6 3/4.2.1 3/4.2.3 3/4.2.6 SHUTDOWN MARGIN -(SDM)Deleted (Ref. License Amendment 280)Moderator Temperature Coefficient (MTC)Regulating CEA Insertion Limits Linear Heat Rate TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR --FrT DNB Margin 2.7 Terms appearing in capitalized type are DEFINED TERMS as defined in Section 1.0 of the Technical Specifications.
- 2. OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections.
These limits have been developed using the NRC approved methodologies specified in Section 3.2.1 SHUTDOWN MARGIN -(5DM).(Specification 3/4.1.1.1)
The SHUTDOWN MARGIN shall be 3.6% AK/K 2.2 Deleted 2.3 Moderator Temperature Coefficient (Specification 3/4.1.1.4)
The moderator temperature coefficient shall be: a. Less positive than 0.7x1 0-4 AK/K/°F whenever THERMAL POWER is <70% of RATED THERMAL POWER, b. Less positive than 0.4x10-4 AK/K/°F whenever THERMAL POWER is > 70%of RATED THERMAL POWER, c. Less negative than -3.2x10-4 AK/K/°F at RATED THERMAL POWER.MILLSTONE
-UNIT 2 TRM 8.1-1 LBDCR 15-MP2-010 October 6 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 2.4 Regulating CEA Insertion Limits (Technical Specification 3/4.1.3.6)
The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown in Figure 2.4-1. CEA insertion between the Long Term Steady State Insertion Limits and the Transient Insertion Limits is restricted to: a. <4 hours per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval, b. <5 Effective Full Power Days per 30 Effective Full Power Day interval, and c. < 14 Effective Full Power Days per 365 Effective Full Power Day interval.2.5 Linear Heat Rate (Technical Specification 3/4.2.1)The linear heat rate, including heat generated in the fuel, clad and moderator, shall not exceed: a. 15.1 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is 360,000 gpm.b. 15.0 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 360,000 gpm and >354,600 gpm.c. 14.9 kw/ft whenever the reactor coolant flow rate (determined per Technical Specification 3/4.2.1) is < 354,600 gpm and __349,200 gpm.During operation with the linear heat rate being monitored .by the Excore Detector Monitoring System, the AXIAL S.HAP. E INDEX shall remain within the limits of Figure 2.5-1.During operation with the linear heat rate being monitored by the Incore Detector Monitor System, the alarm setpoints shall be adjusted to less than or equal to the limit when the following factors are appropriately included in the setting of the alarms: 1. A measurement-calculational uncertainty factor of 1 .07, 2. An engineering uncertainty factor of 1.03, and 3. A THERMAL POWER measurement uncertainty factor of 1.02.MILLSTONE
-UNIT 2 TRM 8.1-2 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 2.6 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR -- FrT (Technical Specification 314.2.3)The calculated value of FrT at RATED THERMAL POWER shall be:_< 1.690 whenever the reactor coolant flow rate is >_ 360,000 gpm._< 1 .664 whenever the reactor coolant flow rate is < 360,000 gpm and > 354,600 gpm._< 1 .639 whenever the reactor coolant flow rate is < 354,600 gpm and > 349,200 gpm.2.6.1 The Power Dependent FrTr limits, whenever the reactor coolant flow rate is > 360,000 gpm, are shown in Figure 2.6-1.2.6.2 The Power Dependent FrT limits, whenever the reactor coolant flow rate is < 360,000 gpm and > 354,600 gpm, are shown in Figure 2.6-2.2.6.3 The Power Dependent FrTr limits, whenever the reactor coolant flow rate is < 354,600 gpm and > 349,200 gpm, are shown in Figure 2.6-3.2.7 DNB Margin (Technical Specification 3/4.2.6)The DNB margin shall be preserved by maintaining the cold leg temperature, pressurizer pressure, reactor coolant flow rate, and AXIAL SHAPE INDEX within the following limits: Parameter Limits Four Reactor Coolant Pumps Operations
- a. Cold Leg Temperature
<549°F b. Pressurizer Pressure > 2225 psia*c. Reactor Coolant Flow Rate > 360,000 gpm with Linear Heat Rate and FrT limits as specified in Sections 2.5 and 2.6.or>_ 354,600 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.or> 349,200 gpm with Linear Heat Rate and FrT limit reductions as specified in Sections 2.5 and 2.6.d. AXIAL SHAPE INDEX Figure 2.7-1 Limit not applicable during either the THERMAL POWER ramp increase in excess of 5% of RATED THERMAL POWER per minute or a THERMAL POWER step increase of greater than 10% of RATED THERMAL POWER.MILLSTONE
-UNIT 2 TRM 8.1-3 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 3. ANALYTICAL METHODS The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
3.1 EMF-96-029(P)(A)
Volumes 1 and 2, "Reactor Analysis System for PWRs Volume 1 -Methodology Description, Volume 2 -Benchmarking Results," Siemens Power Corporation, January 1997.3.2 ANF-84-73 Revision 5 Appendix B(P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors:
Analysis of Chapter 15 Events," Advanced Nuclear Fuels, July 1990.3.3 XN-NF-82-21(P)(A)
Revision 1, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, September 1983.3.4 XN-75-32(P)(A)
Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company, October 1983.3.5 EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model S-RELAP5 Based," Framatome ANP, March 2001.3.6 EMF-2087(P)(A), "SEM/PWR-98:
ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation, June 1999.3.7 XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient for Pressurized Water Reactors," Exxon Nuclear Company, October 1983.3.8 XN-NF-621(P)(A)
Revision 1, "Exxon Nuclear DNB Correlation for PWR Fuel Designs," Exxon Nuclear Company, September 1983.3.9 XN-NF-82-06(P)(A)
Revision 1 and Supplements 2, 4, and 5, "Qualification of Exxon Nuclear Fuel for Extended Burnup," Exxon Nuclear Company, October 1986.3.10 ANF-88-133(P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels PWR Design Methodology for Rod Burnups of 62 GWd/MTU," Advanced Nuclear Fuels Corporation, December 1991.MILLSTONE
-UNIT 2 TRM 8.1-4 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 3.11 XN-NF-85-92(P)(A) "Exxon Nuclear Uranium DioxidelGadolinia Irradiation Examination and Thermal Conductivity Results," Exxon Nuclear Company, November 1986.3.12 ANF-89-151(P)(A), "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, May 1992.3.13 EMF-1961(P)(A)
Revision 0, "Statistical Setpoint/Transient Methodology for Combustion Engineering Type Reactors," Siemens Power Corporation, July 2000.3.14 EMF-2310(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized Water Reactors," Framatome ANP, May 2004.3.15 EMF-92-153(P)(A), Revision 1, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Power Corporation, January 2005.3.16 EMF-92-116(P)(A)
Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation, February 1999.MILLSTONE
-UNIT 2 TRM 8.1-5 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.i CORE OPERATING LIMITS REPORT. CYCLE 24 too, ~AN1( 7 ~. 135 Step~3 1 O0]o090 o.80 040 I~030 0.20 0.10 000't 183 pyv~r bLL+I+ _ 1;i.I- "l- 0 NIN INSETRTION LIMIT *I.I...+ :E............, ... ...... ..~..... 7 -- i .. .:... ., 1.0, .¢ '?4-144 t08 B..'41K.1 L ,1...=1 [.. L1
..72 36 0 180 1'4 108 72 38 80 144 103 72 38 0 '130 ....... 1i4.....CE oitb steps w,,'h dra,,1 0 1 0 i P[I 1 44 103 72 36 0.08 .7......i.......36
........Note: Regulating CEAs that are > 176 steps withdrawn are considered fully withdrawn and are acceptable per this figure.Figure 2.4-1 CEA Insertion Limit vs. THERMIAL POWER With Four Reactor Coolant Pumps Operating MILLSTONE
-UNIT 2 TRM 8.1-6 LBDCR 15-MP2-0l0 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT. CYCLE 24 120 7".........
-.........
."....U NACCEPTAB LE OPE RATIO"N --- ..... ' .. r.......I " ! ! REGION !!!i-0.08,100) iB D i 0.0Bl 100) I IO 8 i!RGO
- i" .a, ACCEPTABLE I I.. .........a.. .....; ... .O ERA ION. .....L. ._ .......I. .....
I IoB 5 I S, B (-0.0&,1C00)
I , I , I--S 40 ........ .....-. ......;. ...(0*(0,00 101) '- .u 0 (+0.08, 100) , LU 'j E (÷0.25, 65)120 ........ ....... Note: Point"0' isprovitedforsettingplentins~tr~irnr~relisn only. -;... ....,.......Ope n s notealloted a bore 1005% of rated power. ,, I I 1 I-0.4 -10.3 -0_2 -0_i 0 01_ 0.2 0_3 0.4-AXIAL SHAPE INDEX (AS]I)Figure 2.5-1 AXIAL SHAPE INDEX vs.PERCENT OF ALLOWABLE POWER LEVEL MILLSTONE
-UNIT 2 TRM 8.1-7 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 100- (1.690, 160)1[1.78B ......UNACCEP:TABLE
., 90- ...; ...........
oU. 4 ..., .....,... .OPRAIO-a "
- a I £ "" O E A IN ". .... a ...' ~REGION '80.........................-..-.,. -- ...............................
'-..... .".....1.
.... ....a a a a I i I a a a a-70................-
... ... ... ... ... ..-U 7o- .a .a i a u i I n a a a a i a P R TO a.... a a a a a.....S5...... ...... ......OEATO .... ...... ... .. .. .....O I 3 n
- a a a a a a
- a a P240.........................
............................
a..a..a...a-......
n 30 ........ ..... .. .. ... .. ... .. .... .. .. .. .. .. .... ....... ..... ....iio l m a u a a a a--* a a a a a I a a ai
- a ai 20..........a
....0 m
- I I I I p I 1.69 1.70 1.71 1.72 1.73 1.74 1.75 1.76 1.77 1.78 1.79 1.80 1.81 1.82 1.83 1.84 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR- FrT Note: The FrT limit should be reduced for reactor coolant flow.rates __ 349,200 gpm and < 360,000 gpm (see Section 2.6).Figure 2.6-1 TOTAL UNRODDED INTEGRATED RADIAL PEAKING FACTOR vs. Allowable RATED THERMAL POWER For Reactor Coolant Flow Rates >360,000 gpm MILLSTONE
-UNIT 2 TRM 8.1-8 LBDCR 15-MP2-010 October 6, 2015 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 100 .( .84 , , , ___* 11.849,70)" UACETBL: I U I OPi Al1[1lN I SI TOTALRLTRON EDITER DRAILPEKN'ACO-F5 .. ... ... .* ... ... F igure... 2.6..-2 ....L. .........., ..TTLU RODEDGINTERTDRDAPAIGFCO vsrAlwal RTD HRMLPOE Ocobr ,201 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIMITS REPORT, CYCLE 24 REG.IONIO n ! s l I i C i C C I C I I I I C I I
- C .i CI 0)l l I I I I I £83 0,. .= l.... ..I........,.....=
..=........a.a..=
.=........i...=
... =.=.I. ..-........
= ..=............
C C C C C I C n ., .I I I I I I I C I I I I I S.78.J.O I n I. CC i I C l I C I 10 I I I I I C C I l I I I C.I.I I C C C C II C I C C C C 0 II p I I I p TOTLURCCDIEGTE DA PEAIN mAT i- F m ,, .October 6 , , 21 TECHNICAL REQUIREMENTS MANUAL APPENDIX 8.1 CORE OPERATING LIIMITS REPORT, CYCLE 24 1.20 -----or -.. ..". ...._ ....., T 'I-'. .I tI.. .SI I I 1.00 "--4UNACCEPTABLE T (-.10,,1.0) -L7 "-"-q --- i UNCEPA... OPERATION
"-- .. .. .- ....-- ;- ....O 4 .)--- i UN CCP T BERA N ...I REGION __ 7, T- PEATON 4--[%.J. r. J REGION 4 / i .. Tl. ...... .[!......I...
..--Il ... ...I n0.50-iI I iREGION. i i i....- -i .. .... It + ....+/- .. .. ..4 ....F ... -F ,-:1: [.o i~ I i i , I' T ' ' -" ...... .. ... '1i -- ..-0.5 0.5 -0.4 . -0.1 0 0.1 0.2 09 0.4 0.5 056 AXIAL SHAPE INDEX (ASI).Figure 2.7-1 AXIAL SHAPE INDEX Operating Limits With Four Reactor Coolant Pumps Operating MILLSTONE