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Category:Fuel Cycle Reload Report
MONTHYEARML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 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 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 2024-04-19
[Table view] Category:Letter
MONTHYEARML24262A0972024-09-23023 September 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000529/2024011) ML24241A2782024-08-28028 August 2024 License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code ML24241A2542024-08-28028 August 2024 Inservice Inspection Request for Information ML24240A2682024-08-27027 August 2024 Transmittal of Technical Specification Bases Revision 79 IR 05000528/20240052024-08-22022 August 2024 Updated Inspection Plan for Palo Verde Nuclear Generating Station - Units 1, 2, and 3 (Report 05000528/2024005, 05000529/2024005, 05000530/2024005) ML24208A0612024-08-20020 August 2024 Issuance of Amendment Nos. 224, 224, and 224 Regarding Revision to Technical Specifications 3.5.1, 3.5.2 and 3.6.5 IR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24177A3222024-06-25025 June 2024 Invalid Specified System Actuation of Train B Emergency Diesel Generator ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a IR 05000528/20243012024-06-17017 June 2024 NRC Examination Report 05000528/2024301; 05000529/2024301; 05000530/2024301 ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A ML24157A3392024-06-0505 June 2024 Inoperable Boron Dilution Alarm System(Bdas) with Technical Specification Violation ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium ML24144A2772024-05-23023 May 2024 Valid Specified System Actuations of Unit 2 Train B Emergency Diesel Generator and Train B Auxiliary Feedwater ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24129A1482024-05-0707 May 2024 and Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 ML24109A0712024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24032A1542024-04-0303 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24089A1892024-03-28028 March 2024 Present Levels of Financial Protection ML24068A2522024-03-0808 March 2024 License Amendment Request to Revise Technical Specifications 3.5.1 and 3.5.2 Using Risk-Informed Process for Evaluations ML24066A0472024-03-0606 March 2024 Response to Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown and TS IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 ML24053A3972024-02-22022 February 2024 License Renewal - Alloy 600 Management Program Plan ML24047A3632024-02-16016 February 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX177, AMZDFX178, AMZDFX179 Vertical Concrete Cask Identification No. AMZDNE179, AMZDNE178 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owner’S 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 2024-09-23
[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