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Category:Fuel Cycle Reload Report
MONTHYEARML23122A1912023-04-29029 April 2023 Unit 1 Core Operating Limits Report Revision 32, Unit 2 Core Operating Limits Report Revision 25, Unit 3 Core Operating Limits Report Revision 31 ML22305A5362022-10-28028 October 2022 Core Operating Limits Report, Revision 30 ML22126A1262022-05-0606 May 2022 Unit 1 Core Operating Limits Report Revision 31 ML22301A2012022-04-30030 April 2022 Core Operating Limits Report, Revision 28 ML22026A2032022-01-26026 January 2022 Unit 1 Core Operating Limits Report Revision 30, Unit 2 Core Operating Limits Report Revision 24, Unit 3 Core Operating Limits Report Revision 29 ML21120A3272021-04-30030 April 2021 Unit 3 Core Operating Limits Report, Revision 28 ML20317A3302020-11-12012 November 2020 Core Operating Limits Report, Revision 29 ML20113F0352020-04-22022 April 2020 Unit 1 Core Operating Limits Report Revision 28 Unit 2 Core Operating Limits Report Revision 23 Unit 3 Core Operating Limits Report Revision 27 ML19297E7242019-10-24024 October 2019 Core Operating Limits Report, Revision 26 ML19204A1932019-07-22022 July 2019 Unit 1 Core Operating Limits Report Revision 27, Unit 2 Core Operating Limits Report Revision 22, Unit 3 Core Operating Limits Report Revision 25 ML19116A2682019-04-26026 April 2019 Core Operating Limits Report, Revision 26 ML18339A0302018-12-0505 December 2018 Current Core Operating Limits Report ML18102B6852018-04-12012 April 2018 Core Operating Limits Report (Colr), Revision 25, 21, and 24, Respectively ML16106A2502016-04-15015 April 2016 Current Core Operating Limits Report Revision ML16034A4682016-02-0202 February 2016 Current Core Operating Limits Report Revisions ML13114A2512013-04-17017 April 2013 Emergency Core Cooling System (ECCS) Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for Calendar Year 2012 ML13108A1762013-04-11011 April 2013 Unit 1 Core Operating Limits Report (Colr), Revision 22, Unit 2 Core Operating Limits Report (Colr), Revision 18 and Unit 3 Core Operating Limits Report (Colr), Revision 21 ML11129A0312011-04-27027 April 2011 Unit 2 Core Operating Limits Report (Colr), Revision 17 ML1031300432010-10-29029 October 2010 Revised Core Operating Limits Report (COLR) ML1015304872010-05-21021 May 2010 Core Operating Limits Report - Revision 21 ML0932901072009-11-17017 November 2009 Submittal of Revised Core Operating Limits Reports (Colrs) ML0923702942009-08-0707 August 2009 Correction to Request for Amendment to Technical Specification 5.6.5b, Core Operating Limits Report (COLR) ML0912703892009-04-29029 April 2009 Core Operating Limits Report (COLR) - Revision 18 ML0830908772008-10-24024 October 2008 Core Operating Limits Reports (COLR) - Revision 19 ML0825601772008-08-29029 August 2008 Request for Amendment to Technical Specification 5.6.5b, Core Operating Limits Report (COLR) ML0733902822007-11-27027 November 2007 Core Operating Limits Reports (Colr), Unit 1 - Revision 18, Unit 2 - Revision 15, and Unit 3 - Revision 17 ML0617104592006-06-0909 June 2006 Units, 1, 2, & 3, Core Operating Limits Reports (Colr), Unit 1 - Revision 17, Unit 2 - Revision 14 and Unit 3 - Revision 16 ML0600903202005-12-27027 December 2005 Core Operating Limits Report (Colr), Revision 16 ML0507704192005-03-0707 March 2005 Cycle 12 Startup Report - Supplement 4 ML0505302362005-02-0404 February 2005 Cycle 12 Startup Report ML0432002272004-11-0303 November 2004 Core Operating Limits Report (Colr), Unit 3- Revision 14 ML0425301642004-08-31031 August 2004 Core Operating Limits Reports (Colr), Unit 1 - Revision 12, Unit 2 - Revision 11, and Unit 3 - Revision 13 ML0414602672004-05-13013 May 2004 Core Operating Limits Report (Colr), Unit 1- Revision 11 ML0411703932004-04-16016 April 2004 Core Operating Limits Reports (Colr), Unit 1- Revision 10, Unit 2- Revision 10, and Unit 3- Revision 12 ML0400606162003-12-23023 December 2003 Core Operating Limits Report: Unit 2 - Revision 9 ML0311404052003-04-17017 April 2003 Core Operating Limits Report, Unit 2-Revision 8 & Unit 3-Revision 11 ML0232303242002-11-0101 November 2002 Docket No.Stn 50-528, Core Operating Limits Report: Unit 1 - Revision 9 ML0230304272002-10-18018 October 2002 Core Operating Limits Reports: Unit 1 - Revision 8; Unit 2 - Revision 7; & Unit 3 - Revision 10 ML0226107122002-09-11011 September 2002 Special Report 2-SR-2002-001-01, Appendix D - G ML0226107102002-09-11011 September 2002 Special Report 2-SR-2002-001-01, Enclosure, Index - Appendix C 2023-04-29
[Table view] Category:Letter
MONTHYEARML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information ML23251A2332023-09-13013 September 2023 Notification of Post Approval Site Inspection for License Renewal and Request for Information Inspection (05000528/2023011) ML23241B0182023-09-13013 September 2023 Use of Honeywell Mururoa V4F1 and MTH2 Supplied Air Suits within Respiratory Protection Program IR 05000528/20243012023-09-0606 September 2023 Notification of NRC Initial Operator Licensing Examination 05000528/2024301; 05000529/2024301; 05000530/2024301 IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) ML23222A2762023-08-10010 August 2023 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canister Identification Numbers AMZDFX175 and AMZDFX176 and Vertical Concrete Cask Identification Numbers AMZDNE175, and AMZDNE176 ML23199A2942023-08-0909 August 2023 Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 ML23207A2482023-07-26026 July 2023 License Renewal Pressurizer Surge Line Inspection ML23188A1872023-07-0707 July 2023 Fourth 10-Year Interval, Second Period Owners Activity Report Number 2R24 ML23166B0832023-07-0505 July 2023 Independence Spent Fuel Storage Installation - Issuance of Exemption ML23181A1602023-06-30030 June 2023 2 to Updated Final Safety Analysis Report, and Revision 3 to Operations Quality Assurance Program Description ML23180A2222023-06-29029 June 2023 Application to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) - Operating, TS 3.5.2, Safety Injection Tanks (Sits) - Shutdown, and TS 3.6.5, Containment Air Temperature ML23181A0772023-06-29029 June 2023 Program Review - Simulator Testing Methodology ML23157A1292023-06-0101 June 2023 Annual Report of Guarantee of Payment of Deferred Premium ML23144A3722023-05-24024 May 2023 Response to Regulatory Issue Summary (RIS) 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23143A3912023-05-23023 May 2023 Independent Spent Fuel Storage Installation - Request for Exemption from NAC-MAGNASTOR Certificate of Compliance 72-1031 - Cask Lid Batch 3 Design Requirements ML23145A2772023-05-17017 May 2023 10-PV-2023-05 Post-Exam Comments ML23132A3392023-05-12012 May 2023 Application to Revise Technical Specifications 3.3.11 to Adopt TSTF-266-A, Revision 3, Eliminate the Remote Shutdown System Table of Instrumentation and Controls IR 05000528/20230012023-05-0808 May 2023 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000528/2023001 and 05000529/2023001 and 05000530/2023001 and 07200044/2023001 ML23128A0692023-05-0808 May 2023 Notification of Biennial Problem Dentification and Resolution Inspection and Request for Information ML23122A1822023-04-29029 April 2023 Transmittal of Technical Specification Bases Revision 76 ML23122A1912023-04-29029 April 2023 Unit 1 Core Operating Limits Report Revision 32, Unit 2 Core Operating Limits Report Revision 25, Unit 3 Core Operating Limits Report Revision 31 ML23116A2772023-04-26026 April 2023 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2022 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 ML23115A4982023-04-25025 April 2023 2022 Annual Environmental Operating Report IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI ML23108A0342023-04-18018 April 2023 NRC Initial Operator Licensing Examination Approval 05000528/2023301; 05000529/2023301; 05000530/2023301 ML23103A4642023-04-13013 April 2023 Annual Radiological Environmental Operating Report 2022 ML23103A4312023-04-13013 April 2023 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2022 IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 ML23102A3292023-04-12012 April 2023 Application for Authorized Use of Mururoa Single-Use, Supplied Air Suits, Models V4F1 and MTH2 ML23102A3242023-04-12012 April 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-107-A, Separate Control Rods That Are Untrippable Versus Inoperable ML23089A4002023-03-30030 March 2023 Consolidated Decommissioning Funding Status Report - 2022 ML23088A4012023-03-30030 March 2023 Project Manager Assignment IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) ML23080A3002023-03-21021 March 2023 Present Levels of Financial Protection 2024-01-19
[Table view] |
Text
Technical Specification 5.6.5.d A member of the STARS Alliance LLC Callaway Diablo Canyon Palo Verde Wolf Creek Palo Verde Nuclear Generating Station 5871 S. Wintersburg Road Tonopah, AZ 85354 102-07906-MDD/MSC April 26, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Palo Verde Nuclear Generating Station Unit 1 Docket No. STN 50-528 Unit 1 Core Operating Limits Report, Revision 26
Dear Sirs:
Pursuant to Palo Verde Nuclear Generating Station Technical Specifications, Section 5.6.5.d, enclosed is the Unit 1 Core Operating Limits Report, Revision 26, which was made effective April 19, 2019. Figure 3.2.4-2 was updated in this revision. A revision bar has been applied to the change. No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Matthew S. Cox, Licensing Section Leader, at (623) 393-5753.
Sincerely,
Michael D. DiLorenzo Nuclear Regulatory Affairs Department Leader
MDD/TMJ/mg
Enclosure:
Unit 1 Core Operating Limits Report, Revision 26 cc: S. A. Morris NRC Region IV Regional Administrator S. P. Lingam NRC NRR Project Manager for PVNGS C. A. Peabody NRC Senior Resident Inspector for PVNGS Dilorenzo, Michael D(Z99838)Digitally signed by Dilorenzo, Michael
D(Z99838)
DN: cn=Dilorenzo, Michael D(Z99838)
Reason: I am approving this document Date: 2019.04.26 13:46:09 -07'00' Enclosure PVNGS Unit 1 Core Operating Limits Report Revision 26 T rimble, Patrick C(Z95337)Digitally signed by Trimble, Patrick C(Z95337)
DN: cn=Trimble, Patrick C(Z95337)
Reason: I am the author of this document Date: 2019.04.16 13:08:45 -07'00'
- Cowdin, Christophe
r (Z12133)
Digitally signed by Cowdin, Christopher (Z12133)
DN: cn=Cowdin, Christopher (Z12133)
Reason: I have reviewed this
document Date: 2019.04.16 13:30:29
-07'00'Karlson, Charles F(V55086)Digitally signed by Karlson, Charles F(V55086)
DN: cn=Karlson, Charles
F(V55086)
Reason: I am approving this
document Date: 2019.04.16 13:47:18
-07'00'
0 1 2 3 4 5 6 7 0 100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)COLD LEG TEMPERATURE (F)
FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 1.0)
(500, 5.0)
0 1 2 3 4 5 6 7 0 100 200 300 400 500 600 SHUTDOWN MARGIN (% K/K)COLD LEG TEMPERATURE (F)
FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350, 4.0)
(500, 6.5)
-4.5-4.0-3.5-3.0-2.5-2.0-1.5-1.0-0.5 0.0 0.5 0 10 20 30 40 50 60 70 80 90 100 MODERATOR TEMPERATURE COEFFICIENT (x 104F)CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 MTC AREA OF ACCEPTABLE OPERATION (0%,0.5)(100%,0)(50%, 0.0)
(100%,-0.2)
(0%,-4.4)(100%,-4.4)
Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit 0 5 10 15 20 0 10 20 30 40 50 60 MINIMUM REQUIRED POWER REDUCTION (% OF RATED THERMAL POWER)
TIME AFTER DEVIATION, MINUTES FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION*
20100% to>80% RTP 16 12 8 4 0 1580% to>70% RTP 12 9 6 3 1070% to>45% RTP 8 6 4 2 545% RTP 4 3 2 1* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.
- NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:- > 95 % RATED THERMAL POWER- COLSS IN SERVICE AND CEACS IN SERVICE- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150*120 90 60 150*30 120 0 90 150*60 120 30 90 0 60 150*30 120 0 90 150*60 120 30 90 0 60 30 0 FRACTION OF RATED THERMAL POWER FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)
NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be fully withdrawn* for power levels 20%. CEA Group 3 must be withdrawn 60" for power 0% and < 20%.
AND CEA Group 4 must be fully withdrawn* for power levels 70.87%. CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (172.5" x Fractional Power) + 25.5" (for power 20% and < 70.87%).
AND CEA Group 5 must be withdrawn the group 5 TIL (TIL5) as indicated on the graph or by the equation:
TIL5 = (172.5" x Fractional Power) - 64.5" (for power 37.39% and 100%).TRANSIENT INSERTION LIMITGROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMITGROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMITGROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 150*120 90 60 150*30 120 0 90 150*60 120 30 90 0 60 150*30 120 0 90 150*60 120 30 90 0 60 30 0 FRACTION OF RATED THERMAL POWER FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)
NOTE:
See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.
To meet the Transient Insertion Limit (TIL) all conditions below must be met:
CEA Groups 1 and 2 must be fully withdrawn* (see definition below) in MODE 1 and MODE 2.
AND CEA Group 3 must be fully withdrawn* for power levels 20%. CEA Group 3 must be withdrawn 60" for power 0% and < 20%.
AND CEA Group 4 must be fully withdrawn* for power levels 54.97%. CEA Group 4 must be withdrawn the group 4 TIL (TIL4) as indicated on the graph or by the equation:
TIL4 = (250.9" x Fractional Power) + 9.82" (for power 20% and < 54.97%).
AND CEA Group 5 must be withdrawn the group 5 TIL (TIL5) as indicated on the graph or by the equations:
TIL5 = (250.9" x Fractional Power) - 80.18" (for power 31.96% and 75.00%). TIL5 = 108" (for power lever 75.00%).TRANSIENT INSERTION LIMITGROUP 5 60 INCHES SHORT TERM STEADY STATE INSERTION LIMITGROUP 5 108 INCHES LONG TERM STEADY STATE INSERTION LIMITGROUP 3 60 INCHES GROUP 5 GROUP 4 GROUP 3 GROUP 2 GROUP 1
CEA POSITION (INCHES WITHDRAWN)
0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 PART STRENGTH CEA POSITION (INCHES WITHDRAWN)
FRACTION OF RATED THERMAL POWER FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER OPERATION ACCEPTABLE OPERATION UNACCEPTABLE OPERATION RESTRICTED LONG TERM STEADY STATE INSERTION LIMITS (112.5 INCHES)
TRANSIENT INSERTION LIMIT (75.0 INCHES)
(50% RATED THERMAL POWER)
0.0 5.0 10.0 15.0 20.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 AZIMUTHAL POWER TILT (%)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)
REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION
0 5 10 15 20 25 50 60 70 80 90 100 COLSS DNBR POWER OPERATION LIMIT REDUCTION (% OF RATED THERMAL POWER)
CORE POWER LEVEL
(% OF RATED THERMAL POWER)
FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL (95, 20)(80, 5)(70, 0)
1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5-0.20-0.15-0.10-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)
(-0.1, 1.99)
(-0.1, 2.28)
(0.06, 2.38)
(0.08, 2.07)
(0.1, 2.38)
(0.1, 2.07)
ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL ACCEPTABLE OPERATION POWER AT OR ABOVE 90%
AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION
3.0 3.1 3.2 3.3 3.4 3.5 3.6-0.20-0.15-0.10-0.05 0.00 0.05 0.10 0.15 0.20 CPC MINIMUM DNBR CORE AVERAGE ASI FIGURE 3.2.4-3 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL)
(-0.1, 3.27)
(0.0, 3.41)
(0.1, 3.41)
ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL UNACCEPTABLE OPERATION