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Category:Fuel Cycle Reload Report
MONTHYEARNMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report NMP1L3525, Core Operating Limits Report2023-04-19019 April 2023 Core Operating Limits Report NMP2L2807, Core Operating Limits Report2022-04-0707 April 2022 Core Operating Limits Report NMP2L2748, Core Operating Limits Report2020-10-14014 October 2020 Core Operating Limits Report ML20115E3622020-04-21021 April 2020 Transmittal of Core Operating Limits Report for Cycle 18, Revision 5 ML18143B4572018-05-15015 May 2018 Submittal of Core Operating Limits Report ML18058A7392018-02-12012 February 2018 Submittal of Core Operating Limits Report NMP1L3143, Submittal of Core Operating Limits Report Cycle 23, Revision 32017-04-13013 April 2017 Submittal of Core Operating Limits Report Cycle 23, Revision 3 NMP1L3134, Core Operating Limits Report2017-03-21021 March 2017 Core Operating Limits Report ML16257A4542016-09-0909 September 2016 Transmittal of Response to Core Operating Limits Report NMP2L3088, Core Operating Limits Report2016-05-16016 May 2016 Core Operating Limits Report ML15286A0562015-10-0707 October 2015 Core Operating Limits Report for Cycle 15 ML14126A7242014-04-24024 April 2014 Core Operating Limits Report ML13346A1562013-11-26026 November 2013 Core Operating Limits Report, COLR2-14, Rev. 2 ML13318A0092013-11-0505 November 2013 Submittal of Core Operating Limits Report ML13190A0122013-06-21021 June 2013 Transmittal of Core Operating Limits Report, COLR2-14, Revision 1 ML13142A2932013-05-10010 May 2013 Core Operating Limits Report ML12156A3672012-06-0101 June 2012 Submittal of Core Operating Limits Report ML12156A3682012-05-30030 May 2012 Submittal of Core Operating Limits Report ML1112505442011-04-26026 April 2011 Core Operating Limits Report, COLR1-20 ML1012504712010-04-23023 April 2010 Submittal of Core Operating Limits Report ML0810702642008-04-16016 April 2008 Core Operating Limits Report, COLR2-12 Revision 0, Cycle 12 ML0733205912007-11-15015 November 2007 Core Operating Limits Report, COLR2-11 Revision 1 ML0712803072007-05-0101 May 2007 Core Operating Limits Report, COLR1 -18, Revision 0 ML0613005242006-05-0101 May 2006 Cycle 11 Core Operating Limits Report, Revision 0 ML0517902072005-06-16016 June 2005 Cycle 17 Core Operating Limits Report, Revision 0 ML0423004582004-08-0202 August 2004 Cycle 16 Core Operating Limits Report, Revision 2 ML0412800692004-04-28028 April 2004 Cycle 10 Core Operating Limits Report, Rev. 0 ML0323104282003-08-0707 August 2003 Cycle 16 Core Operating Limits Report, Revision 1 ML0314204872003-05-13013 May 2003 Cycle 16 Core Operating Limits Report, Revision 0 ML0208505982002-03-0808 March 2002 Cycle 8 Core Operating Limits Report, Rev. 2 2024-04-16
[Table view] Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
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Text
Constellation Energy P.O. Box 63 Lycoming, NY 13093 A Nine Mile Point Nuclear Station June 16, 2005 NMP1L 1959 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Nine Mile Point Unit 1 Docket No. 50-220 License No. DPR-63 Cycle 17 Core Operating Limits Report, Revision 0 Gentlemen:
Attached is a copy of the Cycle 17 Core Operating Limits Report (COLR), Revision 0, for Nine Mile Point Unit 1 (NMP 1). This report is being submitted pursuant to NMPl Technical Specification 6.6.5.d.
Very truly yours, 464n kt/
William C. Holston Manager Engineering Services WCH/RF/sac Attachment cc: Mr. S. J. Collins, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector Mr. P. S. Tam, Senior Project Manager, NRR (2 copies)
-DO
NINE MILE POINT UNIT 1 CORE OPERATING LIMITS REPORT Document No.: COLR1-17.
Revision 0 Name Title Date Prepared by: C/-5-- S C:. W. Lemne Fuel Engineer CT-Reviewed by:
C-L.Winklebleck
- Fuel Engineer Independently Reviewed by:
R. S. Close Fuel Engineer Approved by:
M. A. Armenta Supervisor, Nuclear Fuels Services z 6-/(--
Approved by:
J. N. Darweeslh Supervisor, Reactor Engineering.
Approved by: s 4 A E0f G. S.avis-7 Director, Nuclear Fuels Services This Controlled Document provides cycle specific core operating limits for use in conjunction with the Nine Mile Point Unit 1Technical Specifications. Document pages may only be changed through a reissue of the entire document.
NINE MILE POINT UNIT 1 COLR1-17 Rev. 0 CORE OPERATING LIMITS REPORT Table of Contents Page 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ........ .1 1.1 Limits for Technical Specification 3.1.7. a ...................................... 1 1.2 Limits for Technical Specification 3.1.7.e .................................... . 1 2.0 MINIMUM CRITICAL POWER RATIO (MCPR) ... . ............................... 2 2.1 Limits for Technical Specification 3.1.7.c ...................................
. 2 2.2 Limits for Technical Specification 3.1.7.e . ... ...... .................. 2 3.0 LINEAR HEAT GENERATION RATE (LHGR) .. ........ .......... 3 3.1 Limits for Technical Specifications 3.1.7.b .... ................................... 3 4.0 POWER/FLOW RELATIONSHIP DURING OPERATION ...... ...... ....4 4.1 Limits for Technical Specification Table 3.1.7.d and e ........................................ 4
5.0 REFERENCES
FOR TECHNICAL SPECIFICATIONS................................................ .4 6.0 SOURCE DOCUMENTS .............................. ... . 5 Pagei
C- .7 NINE MILE POINT UNIT 1 COLRI-17 Rev. 0 CORE OPERATING LIMITS REPORT 1.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 1.1 Limits for Technical Specification 3.1.7.a During power operation, the APLHGR for each type of fuel as function of average planar exposure shall not exceed the limiting values shown in Table 1.
1.2 Limits for Technical Specification 3.1.7.e During partial loop operation with four recirculation loops in operation, the APLHGR as a function of average planar exposure shall not exceed 98 percent of the limiting values shown in Table 1.
During partial loop operation with three recirculation loops in operation, the APLHGR as a function of average planar exposure shall not exceed 98 percent of the limiting values shown in Table 1.
Page 1 of 10
NINE MILE POINT UNIT 1 COLR1-17 Rev. 0 2.0 MINIMUM CRITICAL POWER RATIO (MCPR) 2.1 Limits for Technical Specification 3.1.7.c During power operation, the operating MCPR at rated power and flow shall be greater than or equal to the Operating Limit MCPR of:
1.48(') for cycle exposures(2) from BOC19 to EOR19-2417 MWd/ST, and 1.53(l) for cycle exposures(2) from EORI 9-2417 MWd/ST to EOC 19.
If the feedwater pump configuration, as defined by Nuclear Engineering Report No. NER-IM-022, is such that a feedwater controller failure could result in maximum feedwater flow greater than that for two feedwater pumps (i.e., the shaft-driven pump plus one motor-driven pump), then the Operating Limit MCPR shall be 1.59.
For core flows other than rated, the MCPR limit shall be the Operating Limit MCPR identified above times Kf where Kr is as shown in Figure 2a.
Additional limits for operation between 45% and 90% Rated Thermal Power (RTP) (3) (4) are required for operations without a backup pressure regulator.
These limits are shown in Figure 2b.
2.2 Limits for Technical Specification 3.1.7.e During 3 loop operation, the Operating Limit MCPR shall be increased by 0.02. No adjustment is needed during 4 loop operation.
NOTES: (1) Based on a 1.07 MCPR Safety Limit (SLCPR).
(2) These cycle exposures are defined in the Cycle Management Report 3 Below 45% and above 90% RTP no additional limits are required for operation without a backup pressure regulator.
(4) These limits are valid for 3, 4, and 5 loop operation. (Note that for the MCPR Limit for 70% < 90%, i.e. MCPR Limit =
(Rated OLMCPR) / FRTP, the Rated OLMCPR is as determined by 2.1 and 2.2 above.)
Page 2 of 10
NINE MILE POINT UNIT 1 COLR1-17 Rev. 0 3.0 LINEAR HEAT GENERATION RATE (LHGR) 3.1 Limits for Technical Specification 3.1.7b During power operation, the Linear Heat Generation Rate (LHGR) of any rod in any fuel assembly at any axial location shall not exceed the limiting values shown in RSLD-18, Revision 0, "Nine Mile Point Unit 1 Reload 18, Reload Specific Lattice Data". This document contains the LHGR limits for both U02 rods (which contain no gadolinium) and the most limiting gadolinium-bearing rods. Other gadolinium-bearing rods have LHGR limits which lie between these two curves. Compliance with these limits will be monitored by the plant's process computer.
Additional limits for operation between 45% and 90% RTP(t ) are required for operations without a backup pressure regulator. These limits are shown in Figure 3.
NOTE: (1) Below 45% and above 90% RTP no additional limits are required for operation without a backup pressure regulator.
Page 3 of 10
NINE MILE POINT UNIT 1 COLR1-17 Rev. 0 4.0 POWER/FLOW RELATIONSHIP DURING OPERATION 4.1 Limits for Technical Specification 3.1.7.d and e The power/flow relationship shall not exceed the limiting values shown in Figure 4.
5.0 REFERENCES
FOR TECHNICAL SPECIFICATIONS Technical Specification 6.6.5.b:
NEDE 24011-P-A, "General Electric Standard Application for Reactor Fuel,"
U.S. Supplement, Revision 14, June 2000.
Page 4 of 10
NINE MILE POINT UNIT 1 COLRI-17 Rev. 0 6.0 SOURCE DOCUMENTS The Core Operating Limits contained in this report were obtained from the following documents:
CORE OPERATING LIMITS REFERENCE APLHGR Limits (Section 1.0) 0000-0017-3629-SRLR, Revision 1, March 2005, Table I Supplemental Reload Licensing Report for and corresponding three and four Nine Mile Point Nuclear Power Station Unit 1, loop multipliers Reload 18 Cycle 17 MCPR Limits (Section 2) 0000-0017-3629-SRLR, Revision 1, March 2005, Supplemental Reload Licensing Report for Nine Mile Point Nuclear Power Station Unit 1, Reload 18 Cycle 17 0000-0017-3637-ER, Revision 0, March 2005, Engineering Report for Nine Mile Point Nuclear Power Station Unit 1,Reload 18 Cycle 17 Pressure Regulator Out-of-Service GE-NE-J1 1-03433-16-01-Rl, 'Pressure Regulator Restriction Out of Service Calculations for Nine Mile Point Unit 1", January 2005 LHGR Limits (Section 3)
Pressure Regulator Out-of-Service GE-NE-J1 1-03433-16-01-Rl, Pressure Regulator Restriction Out of Service Calculations for Nine Mile Point Unit 1", January 2005 0000-0017-3629-FBIR, Revision 0, "Fuel Bundle Information Report for Nine Mile Point Nuclear Station Unit I Reload 18 Cycle 17," March, 2005.
Power/Flow Relationship (Section 4) NMPI Technical Specification Amendment 92, Figure 3.1.7.aa Page 5 of 10
NINE MILE POINT UNIT 1 COLRI-17, Revision 0 Table I MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Average Planar Exposure MAPLHGR Limits (kwft)
GWdWST Bundle Bundle Bundle Bundle Bundle GE11-C14 GE11C15 GE11-C16A GE11C16B GE11-C17 0.00 8.90 8.82 9.93 9.93 9.81 0.20 8.90 8.82 9.93 9.93 9.81 1.00 8.96 8.89 9.89 9.90 9.78 5.00 9.32 9.22 9.78 9.70 9.64 10.00 9.66 9.56 9.61 9.67 9.49 15.00 9.57 9.50 9.53 9.53 9.36 17.50 9.33 9.49 9.53 9.53 _
20.00 8.64 9.44 8.88 8.88 8.87 25.00 8.46 8.58 8.61 8.61 8.41 30.00 8.32 8.45 8.45 _
35.00 7.90 8.26 8.42 8.42 8.30 45.00 6.79 8.34 8.44 8.44 8.31 50.00 6.31 - 8.47 8.47 _
55.00 - 8.41 8.48 8.48 8.37 65.00 6.38 8.48 6.38 6.38 8.46 NOTE:
(1) A "-" indicates that there is no entry for this box and the limit can be determined by linearly interpolating between the previous and next point in each column.
MAPLHGRs are interpolated between exposure points for which explicit values are given.
(2) These MAPLHGR are not lattice dependent. The values shown also correspond to the limiting value for the most limiting lattice for use when hand calculations are required.
Fuel Tyoe ID GE I-P9DUB339-12GZ-1 OOT-145-T6-2537 GE11-C14 GE1I-P9DUB362-13GZ-1 OOT-145-T6-3899 GE11-C15 GE1I-P9DUB376-12GZ-1 OOT-145-T6-2585 GE11-C16A GE1I-P9DUB376-12GZ-1 OOT-145-T6-2586 GE11-16B GE1 1-P9DUB382-13GZ-1 OOT-145-T6-2831 GE11-C17 Page 6 of 10
NINE MILE POINT UNIT 1 COLR.1-17, Revision 0 Figure 2a NMP-1 K(f Curve for MCPR II 1.5 ,
K(f) = 1.50 when 45% > Flow, Otherwise:
- 102.5% K(f) = MAX( 1.0. 1.33075 - 0.441
- 107.0% K(f) = MAX( 1.0, 1.35280 - 0.441
- 112.0% K(f) = MAX( 1.0, 1.37926 - 0.441
1.4 - 117.0% K(f) = MAX( 1.0, 1.40352 - 0.441
- Automatic K(f) = MAX( 1.0,1.441 - 0.441
I I 1.3 -- -
Automatic Flow Control a.
0 C.02 117% Scoop Tube Setting C--
Y.-
1.2 -- 17cT--------u----------------Tn 112% Scoop Tube Setting 1.1 107% Scoop Tube Setting 1 I -- - - - - - - - - - - - - - - - -
0.9 0 20 40 60 80 100 120 Core Flow (% of Rated)
Page 7 of 10
NINE MILE POINT UNIT I COLRI-17, Rev 0 Figure 2b: MCPR Limits for Operation Between 45% and 90% RTP Without a Backup Pressure Regulator E
W 2 a-U 45 50 55 60 65 70 Core Thermal Power (P) In units of % Rated Thermal Power (%RTP)
Page 8 of 10
NINE MILE POINT UNIT I COLRI-17 Rev. 0 Figure 3: LHGR.Limits for Operation Between A5% and 90% RTP Without a Backup Pressure Regulator 1.2 0
0.8 E
a 0.6 0I U-0.4 0.2 45 50 55 60 65 70 75 80 85 90 Core Thermal Power (P)In units of % Rated Thermal Power (%RTP)
Page 9 of 10
NINE MILE POINT UNIT 1 COL111-17, Revision 0 Rgue4 Lirifing Powl FRow ULm 0
I-CA A:
0 UzltirgibAe/m m II 0
0 a.
I-00 QW 0 Z2 60 D, 1ic 12D OzeRoNv/cdRbo Page 10 of 10