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Category:Fuel Cycle Reload Report
MONTHYEARL-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022 Cycle 29-1 Core Operating Limits Report L-21-260, Core Operating Limits Reports2021-11-15015 November 2021 Core Operating Limits Reports L-21-137, Cycle 28 Core Operating Limits Report2021-05-21021 May 2021 Cycle 28 Core Operating Limits Report L-20-143, Cycle 22 Core Operating Limits Report2020-05-0808 May 2020 Cycle 22 Core Operating Limits Report L-20-078, Cycle 27-1 Core Operating Limits Report2020-03-16016 March 2020 Cycle 27-1 Core Operating Limits Report L-19-239, Cycle 27 Core Operating Limits Report2019-11-0808 November 2019 Cycle 27 Core Operating Limits Report L-18-264, Cycle 21 Core Operating Limits Report2018-11-16016 November 2018 Cycle 21 Core Operating Limits Report L-18-119, Cycle 26 Core Operating Limits Report2018-05-21021 May 2018 Cycle 26 Core Operating Limits Report L-17-344, Cycle 25-1 Core Operating Limits Report2017-11-28028 November 2017 Cycle 25-1 Core Operating Limits Report L-17-071, Cycle 20 Core Operating Limits Report2017-06-0606 June 2017 Cycle 20 Core Operating Limits Report L-16-302, Cycle 25 Core Operating Limits Report2016-10-14014 October 2016 Cycle 25 Core Operating Limits Report L-16-048, Core Operating Limits Reports Midcycle Revision2016-02-11011 February 2016 Core Operating Limits Reports Midcycle Revision L-15-376, Cycle 24-1 Core Operating Limits Report2015-12-28028 December 2015 Cycle 24-1 Core Operating Limits Report L-15-304, Cycle 19, Core Operating Limits Report2015-10-29029 October 2015 Cycle 19, Core Operating Limits Report L-15-162, Cycle 24 Core Operating Limits Report2015-05-14014 May 2015 Cycle 24 Core Operating Limits Report L-14-389, Submittal of Core Operating Limits Report2014-12-11011 December 2014 Submittal of Core Operating Limits Report L-14-141, Pressure and Temperature Limits Reports and Unit No. 2 Cycle 18 Core Operating Limits Report2014-05-12012 May 2014 Pressure and Temperature Limits Reports and Unit No. 2 Cycle 18 Core Operating Limits Report L-13-329, Core Operating Limits Report, Cycle 232013-11-0404 November 2013 Core Operating Limits Report, Cycle 23 L-12-358, Submission of Core Operating Limits Report, Cycle 172012-10-29029 October 2012 Submission of Core Operating Limits Report, Cycle 17 L-12-181, Submittal of Core Operating Limits Report, Cycle 16-12012-06-11011 June 2012 Submittal of Core Operating Limits Report, Cycle 16-1 L-12-140, Core Operating Limits Report, Cycle 222012-05-0707 May 2012 Core Operating Limits Report, Cycle 22 L-10-301, Core Operating Limits Report, Cycle 212010-11-10010 November 2010 Core Operating Limits Report, Cycle 21 L-10-015, Core Operating Limits Report, Cycle 20 Revised2010-02-0101 February 2010 Core Operating Limits Report, Cycle 20 Revised L-09-293, Submission of the Core Operating Limits Report, Cycle 152009-11-0606 November 2009 Submission of the Core Operating Limits Report, Cycle 15 L-09-214, Submittal of the Core Operating Limits Report, Cycle 14-12009-08-20020 August 2009 Submittal of the Core Operating Limits Report, Cycle 14-1 L-09-112, Submittal of Core Operating Limits Report, Cycle 202009-05-12012 May 2009 Submittal of Core Operating Limits Report, Cycle 20 L-08-163, Transmittal of Revision to the Core Operating Limits Report, Cycle 142008-05-0808 May 2008 Transmittal of Revision to the Core Operating Limits Report, Cycle 14 L-07-137, Core Operating Limits Report, COLR 19 and COLR 19-12007-10-25025 October 2007 Core Operating Limits Report, COLR 19 and COLR 19-1 L-07-087, Core Operating Limits Report, COLR 18-3, Rev 3 and COLR 13-2, Rev 2, Pressure and Temperature Limits Report2007-06-25025 June 2007 Core Operating Limits Report, COLR 18-3, Rev 3 and COLR 13-2, Rev 2, Pressure and Temperature Limits Report L-06-155, Core Operating Limits Report, Revision 132006-11-0606 November 2006 Core Operating Limits Report, Revision 13 L-06-062, Cycle 18 Core Operating Limits Report2006-04-14014 April 2006 Cycle 18 Core Operating Limits Report L-07-043, Cycle 18-2 and Unit 2, Cycle 13-1 Core Operating Limits Mid-Cycle Revision Updates2006-03-26026 March 2006 Cycle 18-2 and Unit 2, Cycle 13-1 Core Operating Limits Mid-Cycle Revision Updates L-05-117, Cycle 17 Core Operating Limits Report Mid-Cycle Revision2005-07-11011 July 2005 Cycle 17 Core Operating Limits Report Mid-Cycle Revision L-05-081, Cycle 12 Reload and Core Operating Limits Report2005-04-22022 April 2005 Cycle 12 Reload and Core Operating Limits Report L-04-147, Cycle 17 Reload and Core Operating Limits Report2004-11-0505 November 2004 Cycle 17 Reload and Core Operating Limits Report L-03-158, Cycle 11 Reload and Core Operating Limits Report2003-10-0909 October 2003 Cycle 11 Reload and Core Operating Limits Report L-03-051, Cycle 16 Reload and Core Operating Limits Report2003-04-17017 April 2003 Cycle 16 Reload and Core Operating Limits Report L-02-079, Mid-Cycle Core Operating Limits Report Revision2002-07-31031 July 2002 Mid-Cycle Core Operating Limits Report Revision 2023-05-17
[Table view] Category:Letter type:L
MONTHYEARL-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2023-04-14014 April 2023 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-061, Submittal of the Decommissioning Funding Status Reports2023-03-31031 March 2023 Submittal of the Decommissioning Funding Status Reports L-23-058, 180-Day Steam Generator Tube Inspection Report2023-03-27027 March 2023 180-Day Steam Generator Tube Inspection Report L-23-066, Annual Notification of Property Insurance Coverage2023-03-21021 March 2023 Annual Notification of Property Insurance Coverage L-23-036, Report of Facility Changes, Tests and Experiments2023-03-13013 March 2023 Report of Facility Changes, Tests and Experiments L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0404 March 2023 Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)2023-03-0404 March 2023 Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027) L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair2023-03-0101 March 2023 Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report2023-02-21021 February 2023 Twenty-Eighth Refueling Outage Inservice Inspection Summary Report L-23-064, Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-02-21021 February 2023 Discharge Monitoring Report, (NPDES) Permit No. PA0025615 L-23-057, Energy Harbor Nuclear Corp Retrospective Premium Guarantee2023-02-20020 February 2023 Energy Harbor Nuclear Corp Retrospective Premium Guarantee L-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H2023-02-14014 February 2023 Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time2023-02-14014 February 2023 Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time L-23-032, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 20222023-01-23023 January 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Second Half of 2022 L-22-281, Discharge Monitoring Report (NPDES) Permit No. PA00256152022-12-16016 December 2022 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-246, Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO2022-12-0707 December 2022 Response to Request for Additional Information Regarding a Request to Consolidate Fuel Decay Time Technical Specifications to New LCO L-22-217, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-11-21021 November 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-226, Emergency Preparedness Plan2022-11-0404 November 2022 Emergency Preparedness Plan L-22-222, Cycle 29-1 Core Operating Limits Report2022-10-31031 October 2022 Cycle 29-1 Core Operating Limits Report L-22-228, Independent Spent Fuel Storage Installation Changes, Tests, and Experiments2022-10-26026 October 2022 Independent Spent Fuel Storage Installation Changes, Tests, and Experiments L-22-200, Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage2022-10-21021 October 2022 Response to Request for Additional Information Regarding a 180-Day Steam Generator Tube Inspection Report Fall 2021 Refueling Outage L-22-232, Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes2022-10-21021 October 2022 Withdrawal of a License Amendment Request Associated with Fire Protection Program Changes L-22-238, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-10-20020 October 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-227, Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins2022-10-0303 October 2022 Revised August 2022 Outfall 003 & 004 NPDES Discharge Monitoring Report (Dmr), Revised Daily Effluent Monitoring Report Forms for Outfalls 003 & 004 and Corrective Action Letter from Eurofins L-22-219, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152022-09-26026 September 2022 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-22-204, Submittal of Evacuation Time Estimates2022-09-0707 September 2022 Submittal of Evacuation Time Estimates L-22-137, Request for Fire Protection Program Changes2022-09-0606 September 2022 Request for Fire Protection Program Changes L-21-238, License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident2022-08-31031 August 2022 License Amendment Request for Addition of Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident L-22-188, Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage2022-08-22022 August 2022 Response to Request for Additional Information Regarding Steam Generator Inspection Report- Fall 2021 Refueling Outage L-22-191, Spent Fuel Storage Cask Registration2022-08-17017 August 2022 Spent Fuel Storage Cask Registration 2023-09-14
[Table view] |
Text
FENOC Beaver Valley Power Station P.O. Box 4 FirstEnergy Nuclear Operating Company Shippingport. PA 15077-0004 L. William Pearce 724-682-5234 Vice President Fax: 724-643-8069 April 22,2005 L-05-081 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Cycle 12 Reload and Core Operating Limits Report Beaver Valley Power Station, Unit No. 2 completed the eleventh cycle of operation on April 3, 2005, with a burnup of 19,538.54 MWD/MTU. This letter describes the Cycle 12 reload design, provides a copy of the Core Operating Limits Report (COLR) in accordance with Technical Specification 6.9.5.d, and documents our review in accordance with 10 CFR 50.59 including our determination that no Technical Specification or license amendment was required for the Cycle 12 reload design.
During the 2R1 I refueling, 1 Region 8A, 20 Region l lA, 12 Region 1 IB, 8 Region 12A, and 20 Region 12B assemblies were discharged and replaced with 33 fresh Region 14A fuel assemblies enriched to 4.20 nominal weight percent and 28 fresh Region 14B fuel assemblies enriched to 4.80 nominal weight percent.
FirstEnergy Nuclear Operating Company has performed a review of this reload core design to determine those parameters affecting the design basis limits and the safety analyses for postulated accidents described in the Updated Final Safety Analysis Report (UFSAR). The analytical methods used to determine the core operating limits meet the criteria specified in Technical Specification 6.9.5.a, b and c. The Cycle 12 reactor core reload evaluation concluded that the implementation of the 17 x 17 RFA core will not adversely affect the safety of the plant. The reload evaluation also concluded that the core design will not require any Technical Specification changes, and will not require a license amendment due to new safety analyses changes, fission product barrier design basis limits, or methods of evaluation as described in the UFSAR, pursuant to 10 CFR 50.59. The Beaver Valley Plant Onsite Review Committee has concurred with the conclusions of the reload evaluation.
Beaver Valley Power Station, Unit No. 2 Cycle 12 Reload and Core Operating Limits Report L-05-081 Page 2 The Core Operating Limits Report (COLR) is enclosed in accordance with Technical Specification 6.9.5.d. The COLR has been updated for this cycle by revising the Fxy and maximum FQT* PJEL criteria.
No newv commitments are contained in this submittal. If there are any questions concerning this matter, please contact Mr. Larry R. Freeland, Manager, Regulatory Compliance at 724-682-4284.
Sincerely, 446e William Pearce Attachment c: Mr. T. G. Colbum, NRR Senior Project Manager Mr. P. C. Cataldo, NRC Sr. Resident Inspector Mr. S. J. Collins, NRC Region I Administrator Mr. L. E. Ryan (BRP/DEP)
I BVPS .
LICENSING REQUIREMENTS MANUAL 4.1 CORE OPERATING LIMiTS REPORT This Core Operating Limits Report provides the cycle specific parameter limits developed in.
accordance with the NRC approved methodologies specified in Technical Specification Administrative Control 6.9.5..
Specification 3.1.3.5 Shutdown Rod Insertion Limits
- The Shutdown rods shall be withdrawn to at least 225 steps.(l)
Specification 3.1.3.6 Control Rod Insertion Limits :
-1
'Control Banks A and B shall be withdrawn to at least 225 steps.l) .
- ' .. I' Control Banks C and D shall be limited in physical insertion as sho'wn in Figure 4.l-l.(')
Specification 3.2.1 Axial Flux Difference NOTE: The target band is +/-7% about the target flux from 0% to 100% RATED THERMAL POWER The indicated Axial Flux Difference:
- a. Above 90% RATED THERMAL POWER shall be maintained within the +/-7% target band about the target flux difference.
- b. Between 50% and 90% RATED THERMAL POWER is within the limits shown on Figure 4.1-2.
- c. .Below 50% RATED THERMAL POWER may deviate outside the target band.
.Specification 3.2.2 FQ(Z) and Fly Limits .
- I' C -F .. . . . . .
FQ(Z) < -
- K(Z) for P > 0.5 FQ(Z) <-* K(Z) for P 5 0.5 Where: CFQ = 2.3 P= ' THERMAL POWER RATED THERMAL POWER K(Z) = the function obtained from Figure 4.1-3.
(1) As indicated by the group demand counter *1 COLR 12
- BEAVER VALLEY - UNIT 2
BVPS-2 LICENSING REQUIREMENTS MANUAL The Fxy limits [FXy(L)I for RATED THERMAL POWER within specific core planes shall be:
Fxj(L) = Fxy(RTP) (1 + PFxy * (I-P))
Where: For all core planes containing D-Bank:
Fx+(RTP)*<1.71 -
For unrodded core planes:
Fxy(RTP) < 1.75 from 1.8 ft. elevation to 2.3 flt. elevation Fxy(RTP) < 1.79 from 2.3 ft. elevation to 3.7 ft. elevation F1y(RTP) < 1.84 from 3.7 R. elevationto 5.8 ft. elevation FXy(RTP) < 1.85 from 5.8 f. elevation to 7.4 ft. elevation Fxy(RTP) < 1.81 from 7.4 ft. elevation to 9.2 ft. elevation FXy(RTP) < 1.75 from 9.2 ft. elevation to 10.2 ft. elevation
-PF.=0.2 THERMAL POWER.
RATED THERMAL POWER Figure 4.1-4 provides the maximum total peaking factor times relative power (FQT*P) as a function of axial core height during normal core operation.
Specification 3.2.3 FN AH HkCF~ * (I + .PF, (1 _-P)) , ' :
Where: CFAH= 1.62 PPM! = 0.3 THERMAL POWER
= RATED THERMAL POWER COLR 12 BEAVER VALLEY - UNIT 2 4.1-2 . Revision 43
' A~- . . ..
BVPS-2 LICENSING REQUIREMENTS MANUAL 200
- 175
- .150 C,
0.
a1).
ut 125 z
0 CO, I
o 100 E.L z
m 75 a
0 .
50 25 0- .~~
i ,
I - ....I_ - ... I - .. I - ...._
I
.0 10 20 "30 4o0: 50 60 .70 .80 90 100 ..
PERCENT OF RATED THERMAL POWER FIGURE 4.1-1 CONTROL ROD INSERTION LIMITS AS A FUNCTION OF RATED POWER LEVEL COLR 12 BEAVER VALLEY - UNIT 2 4.1-3 Revision 43 -.
..... 2.
W*Qw* { .:
BVPS-2 LICENSING REQUIREMENTS MANUAL
. . . .i 0 1L - -10 ._1: 20 -130. 40
-50 30 -20 -10.:0 - 10 20 30.40 :50:
Flux Difference (Al) %
FIGURE 4.1-2 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER COLR 12 : I ..
BEAVER VALLEY - UNIT 2 4.1-4 . Revision 43
- BVPS-2 L. R LICENSING REQUIREMENTS MANUAL 1.2
. I.1 1:'1'1-1 1 1 1:11 1 1.0 ,, =l 101 I-7:7-1;1 I_1
. .8 1 111:11 l l Tr 1 1-0t0-125 ll
- - 1:'1'...1 1'-1 AX 1-..
.N 0.6
..- - i 010- 0'1L1 X 0.4
_--_:1X104 7 I :TTI TI l :
0.2
__ T:I I Tl- T-I l 0 .__X :1...:1--1.1 .-1.1.1 0 2 4 :6 8 :10 12 Core Height (feet)
FIGURE 4.1-3 FQT NORMALIZED OPERATING ENVELOPE, K(Z)
COLR 12 BEAVER VALLEY - UNIT 2 .4.1-5 . . . Revision 43 .; t,
BVPS-2 LICENSING REQUIREMENTS MANUAL 2.4 rss jJJ u
2.30 1 AA . . . IA .AA A .4 Z
,tNl; , , , -.
1 nn 7A1 . Ti&-k AA-A I.... - I----TIAO A 17. -..- . I z I
.0 - U - -- - AA-4
.2. .00, = ==. _
.80 - _ ... - - - -.
'80 1: .60 = . - _ = =12 0,.2.127.5l I, ,
.40 =
-~r .1.
.20 A LL - BASIS FXY
.91 .00 FROM 1.8 FT. UP TO 2.3 FT. < 1.75 FROM 2.3 FT. UP TO, 3.7 FT. < 1.79 0.80 A FROM 3.7 FT. UP TO 5.8 FT. < 1.84 L
FROM 5.8 FT. UP TO 7.4 FT. < 1.85 0.60 FROM 7.4 FT. UP TO 9.2 FT. < 1.81
-0.40 FROM .
9.2 FT...-UP TO .
10.2 FT. < 1.75 0 . *20 - ll - t l
1 - 11.i 1.
1 t t l
-1.
l l § I .l . l I 0.0 n 1 I i 7 T I I u L - I - L- L - I - I - .L - - I. - 1. - L - I. -
0 2 4 .6 . 8 10 12 CORE HEIGHT (FT)
FIGURE 4.14 MAXIMUM (FQT*PREL) VS. AXIAL CORE HEIGHT DURING NORMAL OPERATION COLR 12 BEAVER VALLEY - UNIT 2 ..- .4.1-6 - Revision 43 - -.
LBVPS-2
- . LICENSING RE UIREMENTS MANUAL :
Specification 3.3.1.1 Reactor Trip' System Instrumeniation Setnoints. Table 3.3-1 Table Notations A antlA ,
Overtemperature AT Setpoint Parameter Values:
Parameter Value Overtemperature AT reacfortrip setpoint' -. "' (1'* 01.31 ' '
Overtemperature AT reactor trip setpoint Tavg coefficient K2Ž20.01S3/0 F .'
Overtemperature AT. reactor trip setpoint pressure coefficient . K3 2 0.00082/psia
-Tavg at RATED THERMAL POWER . T` -<576.2*F Nominal pressunzer pressure ; P' Ž2250 psia .
Measured reactor vessel AT lead/lag time constants T 2 8 sec .
T2 < 3 sec Measured reactor vessel AT lag time constant .73
- sec Measured reactor vessel average temperature lead/lag time constants ;r4 Ž30sec
.r 5<4sec
'MeaLsured reactor vessel average temperature lag time constant tr6 < 0'sec f(&I) is a function of the indicated difference between top and bottom detectors of the power-range:
nuclear ion chambers; with gains to be selected based on measured instrument response'during plant startup tests such that:
'(i) For q, - qb between -32% and +11%, f 1(AI) 0, where qt and qb are percent RATED THERMAL POWER in the top and bottom halves of the core respectively, and qt + qb is tota THERMAL POWER in percent of RATED THERMAL POWER; '
,..(ii) For each'percent that the magnitude of qt- 'qexceed -32%,"the AT Trip Setp oi strhoabe' :'
- automatically reduced by 146% of its Value at RATED THERMAL POWER, and'...
.(iii] )For each'percent that the magnitude of q1 - qb exceeds +11%, the AT Trip Setpoint shall be automatically reduced by 1.56% of its value at RATED THERMAL POWER.
COLR12 . ..I BEAVER VALLEY - UNIT 2 .. 4.1-7 .:,Revision 43
' '. LICE G BVPS-2 .
< s... : .. ......... LICENSING REQUIRMENTS MANUAL ............... ..-.- :
Overpower AT Setpoint Parameter Values:
-Parameter - Value
,Overpower AT reactor trip setpoint K4 < 1.094 Overpower AT reactor trip setpoint Tavg rate/lag coefficient K5 2 0.00/°F for increasing ... .
. . -::-. average0 temper e K5 0/ Ffor
- - . decreasing average temperature OverowerAT reactor tripsetpointeTavg he cofficient K6Ž 0.0012/F forT>. :-
. . - K6 = Ffor'T <T Tavg at RATED THERMAL POWER .':.. < T" 5i62 0 F
.- . Mea'ured reactor vessel AT lead/ ag time constants' '. >-8 sec -.
-2 *3.sec Measured reactor vessel AT lag time constant T3 < 0 sec Measured reactor vessel average temperature lag time constant -6 *.0 sec Measured reactor vessel average temperature rate/lag time constant s.ec" '..0 T<rs
,1
.. i
.COLR12 ' . . -1. - - --.:,
..BEAVER VALLEY - UNIT 2 4.1-8, Revision 43*
- . . I . ,. .... ....
. . .t . 1
. . . : ., I. !. .
I ..
. . BVPS-2'
'LICENSING REQUIREMENTS MAINUAL Soecification 3.2.5 DNB Parameters Parameter 'Indicated Value Reactor CCoolant System Tavg Tavg < 579.9oF(1)
.Pressuriz' er Pressure Pressure 2 2214 psia..
Reactor CCoolant System Total Flow Rate 'Flow 2 267,200 gprn( 3 )
.I (1) The Reactor Coolant Sy-stem (RCS) T'gvalue includes allowances for rod control opelation' and verification via control board indication.
(2) Thle pressurizer precssure valuecincludesiallowanlces forpr'essurizer pressure control operation a'nd" verification via control board indication.
(3) The RCS total -flowrate includes' allowances for normalization' of the cold leg elbow taps with a beginning of cycle precision RCS floiw calorimcetric measurement atndverification on a periodic basis via plant -proces's computer. If periodic verification of flow rate is performed via the process computer, the required flow value'is Ž267,200 g'pm.
COLR 12 BEAVER VALLEY - UNIT-2 . .4.1-9 Revision 43
.. , ! : 4, .!-. . :.
BVPS-2 LICENSING REQUIREMENTS MANUAL U1.
0
..t I.g I
.590
... . . 1 . .. - .
8.0....
. 580
- 0. 0.2 0.4 0.6 :- 0.8 1 1.2 1.4 FRACTION OF RATED THERMAL POWER Figure 4.1-5 REACTOR'CORE SAFETY LIMiT THREE LOOP OPERATION (Technical Specification Safety Limit 2.1.1)
COLR 12 BEAVER VALLEY - UNIT 2 4.1-10' Revision 43 1I
. 1.,..m..
-....