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Core Operating Limits Report, Unit 1 - Revision 14 and Revision 15, and Unit 2 - Revision 13
	ML060040305
Person / Time
Site:	Palo Verde
Issue date:	12/05/2005
From:	Bauer S; APS
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-05385-SAB/TNW/JAP
	Download: ML060040305 (83)
	v • d • e

{{#Wiki_filter:Technical Specification 5.6.5.d LAMS Scott A. Bauer TeL. 623-393-5978 Mail Station 7636 Palo Verde Nudear Department Leader, Fax 623-393-5442 PO Box 52034 Generating Stabtion Regulatory Affairs e-mail: sbauer@apsc.com Phoenix, Arizona 85072-2034 102-05385-SAB/TNW/JAP December 5, 2005 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)Unit I and Unit 2 Docket Nos. STN 50-528 and 50-529 Core Operating Limits Report (COLR), Unit I -Revision 14 and Revision 15, and Unit 2 -Revision 13 Pursuant to PVNGS Technical Specifications, Section 5.6.5.d, enclosed is Unit 1 COLR, Revision 14 (Enclosure 1), which was made effective on November 18, 2005.This revision of the COLR consisted of updating the Departure from Nucleate Boiling Ratio (DNBR) Margin Operating Limit figures 3.2.4-2 and 3.2.4-3 when the Core Operating Limit Supervisory System (COLSS) is out of service, due to power uprate of Unit 1. In addition, editorial word changes were made to Sections 3.1.7, 3.1.8, and Figures 3.2.4-2 and 3.2.4-3, due to replacement of the Core Protection Calculator System (CPCS).Enclosure 2 contains Unit 1 COLR, Revision 15, which was made effective on November 22, 2005. This revision of the COLR made an editorial correction to the coordinate points for the DNBR Margin Operating Limit figure 3.2.4-1, corrected a graphing error to the DNBR Margin Operating Limit figure 3.2.4-2, and reformatted the'revision' numbering for the entire COLR including removal of the individual page revision numbers that were contained in the Table of Contents. This revision replaces Revision 13 and Revision 14 of the Unit 1 COLR.Enclosure 3 contains Unit 2 COLR, Revision 13, which was made effective on November 18, 2005. This revision of the COLR made an editorial correction to the coordinate points for the DNBR Margin Operating Limit figure 3.2.4-1, corrected a graphing error to the DNBR Margin Operating Limit figure 3.2.4-2, and reformatted the'revision' numbering for the entire COLR including, removing the individual revision page numbers that were contained in the Table of Contents. This revision replaces Revision 12 of the Unit 2 COLR.A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Comanche Peak
Diablo Canyon
Palo Verde
South Texas Project
Wolf Creek U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Core Operating Limits Report (COLR), Unit 1 -Revision 14 and Revision 15, and Unit 2 -Revision 13 Page 2 By copy of this letter and the enclosure, this COLR revision is being provided to the NRC Region IV Administrator and the PVNGS Senior Resident Inspector.

This letter does not make any commitments to the NRC.Please contact Thomas N. Weber at (623) 393-5764 if you have any questions or require additional information. Sincerely, SAB/TNW/JAP/ca Enclosure 1: Core Operating Limits Report for PVNGS Unit 1 -Revision 14 Enclosure 2: Core Operating Limits Report for PVNGS Unit 1 -Revision 15 Enclosure 3: Core Operating Limits Report for PVNGS Unit 2 -Revision 13 cc: B. S. Mallett NRC Region IV Regional Administrator M. B. Fields NRC NRR Project Manager G. G. Warnick NRC Senior Resident Inspector for PVNGS Enclosure I Core Operating Limits Report for PVNGS Unit I -Revision 14 Revision 14 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT CORE OPERATING LIMITS REPORT PALO VERDE NUCLEAR GENERATING STATION (PVNGS)UNIT 1 Revision 14 Responsible Engineer Digitally signed by: Petro, Nicole M Date (ZC3341)Date: 11/08/2005 14:0Q4:15 Reason: I am the uthor-of.this document Location: PVNGS Independent Reviewer Digitally signed by: Delorenzi, Mark J Date (ZO1931)Date: 11/08/200514, 10:02 Reason: I have revqwd this document Location: PVNGSr Responsible Section Leader Digitally signed by: yVebb, James R Date (V97187)Date: 11/08/2005 1419:54 Reason: I am appovt s document Location: PVNGSi§Page 1 Revision 13 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table of Contents Description Revision # Page Cover Page 13 1 Table of Contents 13 2 List of Figures 13 3 List of Tables 11 4 Affected Technical Specifications 11 5 Analytical Methods 13 6 Analytical Methods (continued) 12 7 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) -Reactor Trip Breakers Open 13 8 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 13 8 3.1.4 Moderator Temperature Coefficient (MTC) 13 8 3.1.5 Control Element Assembly (CEA) Alignment 13 8 3.1.7 Regulating CEA Insertion Limits 13 8 3.1.8 Part Strength CEA Insertion Limits 13 9 3.2.1 Linear Heat Rate (LHR) 13 9 3.2.3 Azimuthal Power Tilt (Tq) 13 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 13 9 3.2.5 Axial Shape Index (ASI) 13 10 3.3.12 Boron Dilution Alarm System (BDAS) 13 10 3.9.1 Boron Concentration 13 10 Page 2 Revision 14 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT List of Figures Description Revision # Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 11 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 11 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 11 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 11 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 13 15 (COLSS in Service)Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 13 16 (COLSS Out of Service)Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 11 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 11 18 (COLSS in Service)Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 11 19 CEACs Inoperable Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 11 20 Protection Calculators (COLSS Out of Service, CEACs Operable)Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 11 21 Protection Calculators (COLSS Out of Service, CEACs Inoperable) Page 3 Revision 11 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT List of Tables Description Revision # Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 11 22 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 11 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff> 0.97 Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 11 24 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 11 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff> 0.95 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 11 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 Revision 11 PVNGS UNIT I CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde Unit 1 Technical Specifications. AFFECTED PVNGS TECHNICAL SPECIFICATIONS 3.1.1 Shutdown Margin (SDM) -Reactor Trip Breakers Open 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 3.1.4 Moderator Temperature Coefficient (MTC)3.1.5 Control Element Assembly (CEA) Alignment 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Strength CEA Insertion Limits 3.2.1 Linear Heat Rate (LHR)3.2.3 Azimuthal Power Tilt (Tq)3.2.4 Departure From Nucleate Boiling Ratio (DNBR)3.2.5 Axial Shape Index (ASI)3.3.12 Boron Dilution Alarm System (BDAS)3.9.1 Boron Concentration Page 5 Revision 13 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents: Title Report No.Rev Date Supplement

1) CE Method for Control Element Assembly Ejection Analysis (13-N001-1301-01204-1)

2) The ROCS and DIT Computer Codes for Nuclear Design (13-NOOI-1900-01412-0)

3) Modified Statistical Combination of Uncertainties (13-NOOI-1303-01747-2)

4) System 8 OTM Inlet Flow Distribu-tion (13-NOOI-1301-01228-0)

5) Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS (13-NOOI-1900-01192-3)

6) Calculative Methods for the CE Small Break LOCA Evaluation Model (13-N001-1900-01185-3)

7) Fuel Rod Maximum Allowable Pressure (13-N001-0201-00026-1)

8) Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-002)CENPD-0190-A CENPD-266-P-A N.A. January 1976 N.A.N.A.N.A.April 1983 CEN-356(V)-P-A 01-P-A (ARI)May 1988 (April 1996)N.A.Enclosure 1-P to LD-82-054 CENPD-132 CENPD-137-P CEN-372-P-A N.A.N.A. February 1993 N.A. March 2001 1-P 4-P-A 2-P-A N.A.N.A.N.A.N.A.N.A.April 1998 May 1990 September 1999 Page 6 Revision 12 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Title Report No.Rev Date Supplement N.A.9) Technical Description Manual for the CENTS Code (13-NOOl-1303-02349-2 for Vol. 1-4)CE-NPD 282-P-A Vols. 1-4 1 April 2004 10) Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs (13-N001-1900-01329-0)

CENPD-404-P-A 0 November 2001 N.A.Page 7 Revision 13 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT The cycle-specific operating limits for the specifications listed are presented below.3.1.1 -Shutdown Margin (SDM) -Reactor Trip Breakers Open The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.1 -1.3.1.2 -Shutdown Margin (SDM) -Reactor Trip Breakers Closed The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.2-1.3.1.4 -Moderator Temperature Coefficient (MTC)The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.3.1.5 -Control Element Assembly (CEA) Alignment With one or more full-strength or part-strength CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1.3.1.7 -Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits 1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulation CEA groups shall be limited to the withdrawal sequence and to the insertion limitsI shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained fully withdrawn 3 while in Modes I and 2 (except while performing SR 3.1.5.3).1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours.2 The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied: a) Regulating Group 4 position is between 60 and 150 inches withdrawn. b) Regulating Group 5 position is maintained at least 10 inches lower than Page 8 Revision 14 PVNGS UNIT I CORE OPERATING LIMITS REPORT Regulating Group 4 position.c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).3 Fully withdrawn ->147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHRI The linear heat rate limit of 13.1 kW/ft shall be maintained. 3.2.3 -Azimuthal Power Tilt (Tg)The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1.3.2.4 -Departure From Nucleate Boiling Ratio (DNBRL COLSS IN SERVICE and Both CEACs INOPERABLE -Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.COLSS OUT OF SERVICE and Either One or Both CEACs are OPERABLE -Operating within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.COLSS OUT OF SERVICE and CEACs INOPERABLE -Operating within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel.Page 9 Revision 13 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 3.2.5 -Axial Shape Index (ASI)The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits: COLSS OPERABLE-0.18 ASI 5.18 for power> 50%-0.28 < ASI < 0.18 for power >20% and < 50%COLSS OUT OF SERVICE (CPC)-0.10 5ASI D.I10 for power >20%3.3.12 -Boron Dilution Alarm System (BDAS)With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.3.9.1 -Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration 2 3000 ppm.Page 10 PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision 1 1 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN-REGION OF 5050 ACCEPTABLH OPERATION cn REGION OF UNACCEPTABLE 2 .. OPERATION c~t0 i ..........0 100 200 300 40,0 500 600 COLD LEG TEMPERATURE CF)Page 11 PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision 1 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7 -. a. is.,.a.. I...6 5 REGION OF ACCEPTABLE -OPIERA-TION-- (500,6.5).. ..... .. ...... ....0 a;. .------ ----- ---..4--................................ (350,4.0).. --------.-. .....e ... ..-- -I .----- ----3 REGION OF ,UNACCEPTABLE ..................................... I ........ ..OPERTIO 2 1:,.,,,.... I t ------------

--i.. .. .. .. .-----------------------

0 Ok--l .a...- --.100 200 300 400 COLD LEG TEMPERATURE (*)500 600 Page 12 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 1-l FIGURE-3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0*............ ..... , .. i ,. , , ...(50%,0.0)..................

I ----..............

Roomo.a.(100%,-0............ ~ t , L A6 C-t1 8 C4 0 0-0.5-1.0-1.5-2.0-2.5-3.0-3.5 L L .-. ...MTC A...... --AREA .F --ACCEPTABLE AOPERATION ........... ,........... .. ....t..........., .. ....-(0%,-3.i) _ .* :----~-... .... ..... ---- ---..... ... .. ............................... -4.0-4.5........ i...I"I, ....... 1-4 ............. t-- ...v.....3 3:I tI :.* 5 I fI:t * * ** * *I-----------------0 10 20 30 40 50 60 70 CORE POWER LEVEL (% OF RATED THERMAL POWER)80 90 100 End of Cycle Limit Beginning of Cycle Limit TECH SPEC 3.1.4 Maximum Ipper Limit Page 13 WuUU"u* 33 EU R PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision I I FIGURE 3.1.5-1 CORE POWER LIMIT AFTER CEA DEVIATION* z 0 K.e'3 p4 30 25 20 15 10 5 0 i 0 10 20 30 40 50 TIME AFTER DEVIATION, MINUTES 60* WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.Page 14 PVNGS UNIT I CORE OPERATING LIMITS REPORT FIGURE 3.1.7-1 Revision 13 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVIC 1.0 0.9 0.8 ml1 Ie EL t 0Z 0.7 0.6 0.5 0.4 0.3 I 0Z.0 :.9;FOR APPLICABILtITY FLl SOWING A REACTOR CUTBACK)(>- RPt 4 POS= (112 shFRACAsWRy+ 253;;RP S PO = (72.5 x FMAC. MWR) -64.5 i.'.'...'..i.' ...... .. .... .....)N331;37.X ZI QE 002 0.1'.0..-- --------------- ----------W~ o,... .. .. .......3.j. .. .. ...1 1A1 tI 1 1__ _ ._GROUP5 GROUP 3 GROUP I PW* 120 90 60 30 0 IFW* 120 90 60 130 O Fw* 120 90 60 30 0 GROUP 4 -GROUP 2 V* 110 6) 3t k F1

dT 0 40 61) 1 CEA POSITION (INCHES WITHIDRAWN)
Fully Withdrawn is defined as >147.75" (Pulse Counter) and >145.25" (RSPT)Page 15 PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)1.0 0,9 0.8.......0 z t lY-0.7 0.6 0.5 0.4 0.3.I I U'.pg 9 4 OhFOR PICAippzLcA tY FOLL G~RP 5 P0S (250.9 i FRAC. I.. ..... .........I....II:.II: i .,..N-3.rwi , _ _ _ , .PWRj+,9.22--
WR,) .80-1 0.2 0.1 0.0... ........ ... .. ..... ... .... ...........

I .. ......... .... .. .. .. ... ...GROUP 5 I I I I .L_GROUP3 GROUP 1 I I II I I 11 I I I I---I 5 I I I I I a I I I I I I f FW* 120 90 60 30:0 0 FW* 120 90 60 30a 0 PW* 120 90 GROUP 4 GROUP 2 I -I -1 i I I I 1 -:' I I r *Ao 41 60 6) 3) (6 FT* b o0 gO0 0 go o CEA POSITION (INCHES WITRAWN)6 I 3 160 30 0*Fully Withdrawn is defined as >147.75" (Pulse Counter) and >145.25" (RSPT)Page 16 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 1I1 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER z go ce 10.0 20.0 30.0 40.0 50,0 .0........... 60.0 70.0 90.0 .....100.0....-- .1 ...... .......--l- ----....I-----I........ .- -----.............. -, ----.....-I -------------------- I I............. -....... -.1....I I------------I

-A..........

1-1--l ... I .....-.- ........--- ------ ......-1 ----I ....--- -----........k............. I ....I--------- I.. ------- -I................... ...............I ---I ---I .... I ,I...I- ......-:.... .. .....-. .-1 I I............... ............ .......... ............ ............ i .........P.RATION ............ iACPAL...... ..... ...... ............. .... ...... .........---- -n- ----N--------- TRANSIENT INSE*TION LIMI (75.0.INCHES ..... ...... .......OPERATION

RESTRICTED I Iu.u 120.0 130.0 140.0 10.o 1_--..------_--...--.

st. _..... ..,. .t... ... ... .._...... .. .. ----- --- ----- -----.-.LONG TERM STEAD'Y STATE INSERTION

Ln1ffTS (112.5 INCES), ,,, ., .., .......... .... ......J ----------

.. .. ... ..----l -s OPERATION ACCEPTABLE ..... ... .......~.. ..... ... ...... .. ..... ......... I.... ...L.........I ......L..L... .... ............ L. ..L.. L... .... .J....L..L...L I 4- I -j *4 I 1.0 0.9 0.8 0.7 0.6 05S -0.4 0.3 0.2 IFRACION OFIMTED ERMAL POWER 0.1 0.0 Page 17 PVNGS UNIT I CORE OPERATING LOMITS REPORT Revi~sion 1 1 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)20.0 15.0 10.0 5.0 REGION OF UNACCEPTABLE OPERATION REGION 'OF ACCEPTABLE OPERATION 0.0Q 20------------ .0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 CORE POWER LEVEL (% OF RATED THERMAL POWER)Page 18 ---PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 1 1 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEAC's INOPERABLE 25;~0 R C)0 C)c:m 20C V 20 15 10 5 0 0 25 50 75 CORE POWER LEVEL (% OP RATED THERMAL POWER)100 Page 19 PYNGS UNIT 1 CORE OPERATING LIMITS REPORT Revisic FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)c.......)n 14 F'4.J~2.4 2.3 S. S SUSS 59_,...... ..._.... --.. ,- .. -(I_... ........ol. ..J. ..1 ......... sa .: ..* .. .... .......g ... ..ACCEPtTABLE OPERATION ANY:PQWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH bPERABtE CPC CIANNEL.... I. ...----- --------,. -,2...2.D.1,2.28).(0.06,2.38 (01,2.3E.,f .3._: ,...ACCEP~TABLE OiPERAThON POWERAT OR ABOVE 90%AT LEAST 1 CE-AC OPERABLE INJ5 ad U (5 b 2.2 2.1 2.0 1.9 EACIHI O~PERABLIE CPC CRN~I ~ (Q.05,2.00) (-01193)UNACCEPTAILE

.~-~SOPERAlN~

I R-0.20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 20 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 14 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)3.6 3.5 _.3.4 _ .g 3.3 .3.2 -_ -3.1 _ ..3.0-0.20-0.1 -0.10 -0.05 0.00 0.05 0.10 CORE AVERAGE ASI 0.15 0.20 Page 21 Revision 11 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff> 0.98 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 0.5 hours ONA ONA 4 not on SCS 12 hours 0.5 hours ONA ONA 5 not on SCS 8 hours 0.5 hours ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 22 Revision 11 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 2 Keff> 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 1 hour 0.5 hours ONA 4 not on SCS 12 hours 1.5 hours 0.5 hours ONA 5 not on SCS 8 hours 1.5 hours 0.5 hours ONA 4 & 5 on SCS 8 hours 0.5 hours ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 Revision 11 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 2 Keff> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 2.5 hours 1 hour ONA 4 not on SCS 12 hours 2.5 hours 1 hour 0.5 hours 5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours 4 & 5 on SCS 8 hours I hour ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 Revision 11 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 2 Keff> 0.95 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 3 hours 1 hour 0.5 hours 4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours 5 not on SCS 8 hours 3.5 hours 1.5 hours 0.75 hours 4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 Revision 11 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff S0.95 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 4 hours 1.5 hours 1 hour 4 not on SCS 12 hours 4.5 hours 2 hours 1 hour 5 not on SCS 8 hours 4.5 hours 2 hours 1 hour 4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA 6 24 hours 1.5 hours ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 I Enclosure 2 Core Operating Limits Report for PVNGS Unit 1 -Revision 15 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT CORE OPERATING LIMITS REPORT PALO VERDE NUCLEAR GENERATING STATION (PVNGS)UNIT 1 Revision 15 Responsible Engineer Digitally signed by: Petro, Nicole M Date (ZC3341)Date: 11/18/2005 1:@4:05 Reason: I am the uthor ofthis document Location:

PVNGS'1 Independent Reviewer Digitally signed by: Webb, James R Date (V97187)Date: 11/18/2005 18:42:29 Reason: I have reviewed this document Location: PVNGS Responsible Section Leader Digitally signed by: Fannon, Thomas C Date (Z20485)Date: 11/18/2005 1t82 Reason: I am app yogts document Location: PVNGS Page 1 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table of Contents Description Page Cover Page 1 Table of Contents 2 List of Figures 3 List of Tables 4 Affected Technical Specifications 5 Analytical Methods 6 Analytical Methods (continued) 7 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) -Reactor Trip Breakers Open 8 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 8 3.1.4 Moderator Temperature Coefficient (MTC) 8 3.1.5 Control Element Assembly (CEA) Alignment 8 3.1.7 Regulating CEA Insertion Limits 8 3.1.8 Part Strength CEA Insertion Limits 9 3.2.1 Linear Heat Rate (LHR) 9 3.2.3 Azimuthal Power Tilt (Tq) 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 9 3.2.5 Axial Shape Index (ASI) 10 3.3.12 Boron Dilution Alarm System (BDAS) 10 3.9.1 Boron Concentration 10 Page 2 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 15 (COLSS in Service)Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 16 (COLSS Out of Service)Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 18 (COLSS in Service)Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 19 CEACs Inoperable Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 20 Protection Calculators (COLSS Out of Service, CEACs Operable)Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEACs Inoperable) Page 3 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 22 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for KeffI 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff> 0.97 Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 24 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff> 0.95 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde Unit I Technical Specifications. AFFECTED PVNGS TECHNICAL SPECIFICATIONS 3.1.1 Shutdown Margin (SDM) -Reactor Trip Breakers Open 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 3.1.4 Moderator Temperature Coefficient (MTC)3.1.5 Control Element Assembly (CEA) Alignment 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Strength CEA Insertion Limits 3.2.1 Linear Heat Rate (LHR)3.2.3 Azimuthal Power Tilt (Tq)3.2.4 Departure From Nucleate Boiling Ratio (DNBR)3.2.5 Axial Shape Index (ASI)3.3.12 Boron Dilution Alarm System (BDAS)3.9.1 Boron Concentration Page 5 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents: Title Report No.Rev Date Supplement

1) CE Method for Control Element Assembly Ejection Analysis (13-N001-1301-01204-1)

2) The ROCS and DIT Computer Codes for Nuclear Design (13-N0O1-1900-01412-0)

CENPD-0190-A CENPD-266-P-A N.A. January 1976 N.A.N.A.N.A.April 1983 3) Modified Statistical Combination of Uncertainties (13-NOOl-1303-01747-2)

4) System 8OTM Inlet Flow Distribu-tion (13-NOO1-1301-01228-0)

CEN-356(V)-P-A -P to LD-82-054 01-P-A (ARI)May 1988 (April 1996)N.A.1-P N.A. February 1993 5) Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS (13-NOOI-1900-01192-3)

6) Calculative Methods for the CE Small Break LOCA Evaluation Model (13-NOO1-1900-01185-3)

7) Fuel Rod Maximum Allowable Pressure (13-NOO1-0201-00026-1)

8) Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-002)CENPD-132 CENPD-137-P CEN-372-P-A N.A.N.A. March 2001 N.A.N.A.April 1998 May 1990 4-P-A 2-P-A N.A.N.A.N.A. September 1999 Page 6 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Title Report No.Rev Date Supplement

9) Technical Description Manual for the CENTS Code (13-N00l-1303-02349-2 for Vol. 1-4)10) Implementation of ZIRLOTM Cladding Material in CE Nuclear Power Fuel Assembly Designs (13-NOOl-1900-01329-0)

CE-NPD 282-P-A Vols. 1-4 CENPD-404-P-A 1 April 2004 0 November 2001 N.A.N.A.V Page 7 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT The cycle-specific operating limits for the specifications listed are presented below.3.1.1 -Shutdown Margin (SDM) -Reactor Trip Breakers Open The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.1-1.3.1.2 -Shutdown Margin (SDM) -Reactor Trip Breakers Closed The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.2-1.3.1.4 -Moderator Temperature Coefficient (MTC)The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.3.1.5 -Control Element Assembly (CEA) Alignment With one or more full-strength or part-strength CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1.3.1.7 -Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits' shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulation CEA groups shall be limited to the withdrawal sequence and to the insertion limits 1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained fully withdrawn 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3).1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours.2 The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied: a) Regulating Group 4 position is between 60 and 150 inches withdrawn. b) Regulating Group 5 position is maintained at least 10 inches lower than Page 8 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Regulating Group 4 position.c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).3 Fully withdrawn ->147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHR)The linear heat rate limit of 13.1 kW/ft shall be maintained. 3.2.3 -Azimuthal Power Tilt (Tg)The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. Additionally, the AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1.3.2.4 -Departure From Nucleate Boiling Ratio (DNBR)COLSS IN SERVICE and Both CEACs INOPERABLE -Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.COLSS OUT OF SERVICE and Either One or Both CEACs are OPERABLE -Operating within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.COLSS OUT OF SERVICE and CEACs INOPERABLE -Operating within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel.Page 9 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT 3.2.5 -Axial Shape Index (ASI)The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits: COLSS OPERABLE-0.18 IASI :50.18 for power > 50%-0.28 < ASI < 0.18 for power >20% and < 50%COLSS OUT OF SERVICE (CPC)-0.10 ASI LD.l0 for power >20%3.3.12 -Boron Dilution Alarm System (BDAS)With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.3.9.1 -Boron Concentration The boron concentration of all filled portions ofthe Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration 2 3000 ppm.Page 10 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 15 FIGURE 3. 1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 6 5 0 4 3.....................-----.......-------...... .....................REGION O F ACCEPTABLE OPERATION: REGION OF OPERATION , ...4.I' ! ... I..

ii-- ------ -------- -- -- -- -- -- -, ' * ,:0*2 1 n.0 100 200 300 400 COLD LEG TEMPERATURE (T)500 600 Page 11 PVNGS UNIT 1 CORE OPERATING LMITS REPORT Revision 15 FIGURE 1 .2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7 6 5 I I cd 04)4 3., , 1500,6.5)'.

.. .. .. ....... .. .. .. .. ..ss 44 0 REGIOR OFI.N.F A~UNACCEPTABL/ ........ ' '.--. --....... ............ ........... 2 1 0 0 100, 200 300 400-COLD LEG TEMPERATURE (F)500 600 Page 12 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 15 FIGURED 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0---- ---- ---- -----------------------4dz&Jb.ba16V ' I ....I MI&E -vsms (50%, 0.0)I ....lonvow..a I r T....l ...C-.I':R 0 a-U-0.5-1.0-1.5-2.0-2.5-3.0-3.5--- ----------------- .......... M-TC-AREA-OF-------- ACCEPTABLE OPEIRATION. _ _---------

-------------

__- -----II I I I......... ............ -.-I II t) I I 4.0 A '* ..I....I. -------------- 1.-..--------.v 0 10 20 30 440 50 60 70 80 90 100 CORE POWER LEVEL (% OP RATED THERMAL POWER)End of Cycle Limit Beginning of Cycle Limit MOSS TECH SPEC 3.1.4 Maximum Upper Limit s a a a a a t Page 13 PVNGS UNIT 1 CORE OPERATING LUMITS REPORT Revision 1S FIGURE 3.1.5-1 CORE POWER LIMIT AFTER CEA DEVIATION* 30 25 z MR 0:. t'I -g3 20 15 10 5v 0 0 10 20 30 40 50 TIE A DEVIATION.INUS I* WHENCORE POWER IS REDUCED TO 55% OP RATED THERMAL POWER PER T:IlS LIMIT CURVE, FURTHER REDCTION IS NOT REQUIRED.60 Page 14 PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision 15 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)1.0 0.9 0.8 I I'3i a a1 aI Ui'Ia aa'a l...+ ..i ........... , , .s ,, ffi ,\, .'..\ ..\, , , ]: \ ; .: :: z : , \ .t ..\ * : :\, * .\, ..\ , t .o 0 --' .............. !-' 'g' ' ' >tg\s ' 'I--{SEE--FO(.TNfIIN SEem FOR APPILICABILITY FOLI A REACTOR CUTBACK)GRP $PO$ (172..5 ,x FRAC.: I -.)N 3.,OW NG ix¢0 z 0 0.7 0.6 0.5 0.4 0.3 PWI ,)-+-2 5-.5 ..LS5.--G-- --------i>;--s------_--_1-

.

.- --------- _- ______; _- _ .- -------.C-3 0.2 0.1'0..0 U .* in- ---------- ---- --GROUP 5 t I I~F* 120 96 I:'1 i 1 50 30 0 EN GROUP 4 a I I[OGROUP 3 13I GE i I I I I V* 126 90 60 30 0 FW* 120 G GROUP 2: I i i ' 1 I I.OUP 1 1 a i a l I I I';90 60 a I 0 30 0l I I I I I I I I I I lP1)** 1f0 90 6b 340 6 FWV o sd o ;0 d0 30 ICEA POSITION (INCHES WITHDRAWN) b*Fully Withdrawn is defined as >147.75" (Pulse Counter) and >145.25" (RSPT)Page 15 PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision 15 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POVWER (COLSS OUT OF SERVICE)1.0 0.9;0.8 e I zz 0 z§0.7 0.6 0.5 0.4 0.3 l 0.2 0.1 0.0 GROUP S GROUP 3 XGROUP I I .-.I -------- --I ----.---I ' :1? 1I 11 1 1 1 11 FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0 GROUP 4 GROUP 2 rPit* AlO 0 4 1) 312 b

1* ) 40 Jo 10 0 CEAPOSITI0ON (INCHES WITHDRAWN*Fully Withdrawn is defined as >147.75" (Pulse Counter) and >145.25" (RSPT)Page 16 PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision 15 0.0 10.0 20.0_- 30.0 40.0 50.0: 60.0 u Z 70.0 E 80.0 8 90.0 100.0 t 110.0; 120.0 130.0 140.0 150.0 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER_ ,, , .._ _. ..,...........

.....,.......... _... .,.,..... F,,,,.... ........ .......... ......._..........----------

----- ------- ... ......- -',--!rRANS~iNT INSEPT1ON LIMI (75.0 INCHES)-OPERATION OPE----- RATTION -------,,UNACC.EPTABLE

'RES TED i i n i i i

U *u .i 'U E i i u .W t i I E E i i U i_. ..__. ______. ___.o .._..............

.-. ... ._ --- _*-s --.. .. .... ... ...... .........

~ive.- --_...- _..- --....LON9G TERMK STEAJ)Y STATE ISRINLMT(1125 INCHES)* I *.~~ ~ ...... ....... ....... .... ....i....... ...........

......... .. ..... .. ........... ....... ................. .........--- ------ ---- --- ---- -- -- --- .. .. -- ------- ----1.0 0.9 0.8 0.7 0.6 0.5 :0.4 0.3 0.2 FRACTION OF RATED THERMAL POWER 0.1 0.0 Page 17 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 15 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)20.0 15.0 10.0 5.0 REGION OF UNACCEPTABLE OPERATION REGION OF ACCEPTABLE OPERATION 20,.~~~ ~-- --- .---.-.---....---... .. .. ...,0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 CORE POWYER LEVEL (% OF.1RATED THEMAL POWER)Page 18 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 15 FIGURE 3.2.4-1 COLSS DNBR OPERATING LMT ALLOWANCE FOR BOTH CEAC's INOPERABLE 25 z C4 2:C4^ 9 0 0:U q I 20 15 10 S I 0 0 25 50 75 100 CORE POWER LEVEL (o OF RATED THERMAL POWER)Page 19 PVNGS UNIT 1 CORE OPERATING LIMTS REPORT Revision 15 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)2.5 2.4 2.3 Uf U5U.......... z I 2.2 2.1-(-I.............. ...............- I. ........-i. --... .- +.1 .D.,2.28)ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE PC PC EL... ....*...u..... ........................(Q'.0602.38 , F ----~ ~ ~-- ---- ----- ---------

'-aI I I aI I....(0.1,2.3E r i s E........ .. ... ..t.. ...:ACCEPTABLE OPRAION I j , : POWER AT OR ABOVE9 9O% : XI I AT LEAST 1 CC OPERBLE IN t EACH. ...RA -E C.CC........ EAC}I PERABLE CPC CdIANNEI^I. .. .... .. .----. .....I I 2.0 1.9 01,.93)i 15 -0.10 '-.(O "5200) p)i UNACCEPTA1BLE AI--OPERALTIWN --m uinu.- ---.I ..... I I9 I* I 6 I I E w -w w w x E g g w w x

F F
r-0.20-0.;C(105 0.00 0.05)RE AVERAGE ASI 0.10 0.15 0.20 Page 20 PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision 15 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)6 1.3I 3.5 3.4_... ...........

_ --- -.... s.'...... ---..ACCEPTABLE OPERATION ANY POWER LEVEL-BOTH-CEACs-INOIPERABLE I--IN ANY OPERABLE CPC CHANNEL............. ..... ( ,3 ,1.)- --------.. --- --- --- --....-.) ......-- -_ --- -C4 Im u 0b 3.3 1,3.27)-- ----- .. ...(-0.3.2 3.1 UNACCEPTAJ3LE OPERATION LJ~JJ.--------. -'- ------------- LJ...L LLJ ------------------- ..L.L J...... .I..LJL.... f..J.LLl.L

, j' 0 ^ .iA 3.0-0.: 20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 21 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 0.5 hours ONA ONA 4 not on SCS 12 hours 0.5 hours ONA ONA 5 not on SCS 8 hours 0.5 hours ONA ONA 4& 5 onSCS ONA ONA ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 22 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 2 Keff > 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 1 hour 0.5 hours ONA 4 not on SCS 12 hours 1.5 hours 0.5 hours ONA 5 not on SCS 8 hours 1.5 hours 0.5 hours ONA 4 & 5 on SCS 8 hours 0.5 hours ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 2 Kef> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 2.5 hours 1 hour ONA 4 not on SCS 12 hours 2.5 hours 1 hour 0.5 hours 5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours 4 & 5 on SCS 8 hours 1 hour ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 2 Keff> 0.95 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 3 hours I hour 0.5 hours 4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours 5 not on SCS 8 hours 3.5 hours 1.5 hours 0.75 hours 4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 Revision 15 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff -0.95 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 4 hours 1.5 hours 1 hour 4 not on SCS 12 hours 4.5 hours 2 hours 1 hour 5 not on SCS 8 hours 4.5 hours 2 hours 1 hour 4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA 6 24 hours 1.5 hours ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 Enclosure 3 Core Operating Limits Report for PVNGS Unit 2 -Revision 13 I, Revision 13 PVNGS UNIT 2 CORE OPERATING 3MITS REPORT CORE OPERATING LIMITS REPORT PALO VERDE NUCLEAR GENERATING STATION (PVNGS)UNIT 2 Revision 13 Responsible Engineer Digitally signed by: rlebb, James R Raespnsbl V971 87)Date Date: 11/18/2005 1 8:7:01 Reason: I am theutoothis document Location:

PVNGS Independent Reviewer Digitally signed by: Hwang, Lun-Chih (Z01668)Date Date: 11/18/200518:248 Reason: I have reviewed this document Location: PVNGS , Responsible Section Leader Digitally signed by: Cannon, Thomas C Date (Z20485)Date: 11/18/2005 1M8:3:32 Reason: I am appr ing this document Location: PVNGx Page 1 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table of Contents Description Page Cover Page 1 Table of Contents 2 List of Figures 3 List of Tables 4 Affected Technical Specifications 5 Analytical Methods 6 Analytical Methods (continued) 7 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) -Reactor Trip Breakers Open 8 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 8 3.1.4 Moderator Temperature Coefficient (MTC) 8 3.1.5 Control Element Assembly (CEA) Alignment 8 3.1.7 Regulating CEA Insertion Limits 8 3.1.8 Part Strength CEA Insertion Limits 9 3.2.1 Linear Heat Rate (LHR) 9 3.2.3 Azimuthal Power Tilt (Tq) 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 9 3.2.5 Axial Shape Index (ASI) 10 3.3.12 Boron Dilution Alarm System (BDAS) 10 3.9.1 Boron Concentration 10 Page 2 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT List of Figures Description Page Figure 3.1. 1-1 Shutdown Margin Versus Cold Leg Temperature 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 15 (COLSS in Service)Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 16 (COLSS Out of Service)Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 18 (COLSS in Service)Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 20 Protection Calculators (COLSS Out of Service, CEAC(s)Operable)Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)Page 3 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 22 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff> 0.97 Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 24 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff> 0.95 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde Unit 2 Technical Specifications. AFFECTED PVNGS TECHNICAL SPECIFICATIONS 3.1.1 Shutdown Margin (SDM) -Reactor Trip Breakers Open 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 3.1.4 Moderator Temperature Coefficient (MTC)3.1.5 Control Element Assembly (CEA) Alignment 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Strength CEA Insertion Limits 3.2.1 Linear Heat Rate (LHR)3.2.3 Azimuthal Power Tilt (Tq)3.2.4 Departure From Nucleate Boiling Ratio (DNBR)3.2.5 Axial Shape Index (ASI)3.3.12 Boron Dilution Alarm System (BDAS)3.9.1 Boron Concentration Page 5 of 26 Revision 13 PVNGS UNMT 2 CORE OPERATING LIMITS REPORT ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents: Title Report No.Rev Date Supplement

1) CE Method for Control Element Assembly Ejection Analysis (13-NOO1-1301-01204-1)

2) The ROCS and DIT Computer Codes for Nuclear Design (13-N001-1900-01412-0)

3) Modified Statistical Combination of Uncertainties (13-NOO1-1303-01747-2)

4) System 80TM Inlet Flow Distribu-tion (13-NOO1-1301-01228-0)

5) Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS (13-NOO1-1900-01192-3)

6) Calculative Methods for the CE Small Break LOCA Evaluation Model (13-NOO1-1900-01185-3)

7) Fuel Rod Maximum Allowable Pressure (13-NOOI-0201-00026-1)

8) Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-002)CENPD-0190-A CENPD-266-P-A N.A. January 1976 N.A.N.A.N.A.April 1983 CEN-356(V)-P-A 01-P-A (ARI)May 1988 (April 1996)N.A.Enclosure 1-P to LD-82-054 CENPD-132 CENPD-137-P CEN-372-P-A N.A.N.A. February 1993 N.A. March 2001 I-P 4-P-A 2-P-A N.A.N.A.N.A.N.A.April 1998 May 1990 N.A. September 1999 Page 6 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Title Report No.Rev Date Supplement N.A.9) Technical Description Manual for the CENTS Code (13-NOOI-1303-02349-2 for Vol. 1-4)CE-NPD 282-P-A Vols. 1-4 1 April 2004 10) Implementation of ZIRLOTrm Cladding Material in CE Nuclear Power Fuel Assembly Designs (13-N001-1900-01329-0)

CENPD-404-P-A 0 November 2001 N.A.Page 7 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT The cycle-specific operating limits for the specifications listed are presented below.3.1.1 -Shutdown Margin (SDM) -Reactor Trip Breakers Open The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.1 -1.3.1.2 -Shutdown Margin (SDM) -Reactor Trip Breakers Closed The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.2-1.3.1.4 -Moderator Temperature Coefficient (MTC)The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.3.1.5 -Control Element Assembly (CEA) Alignment With one or more full-strength or part-strength CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1.3.1.7 -Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits 1 shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulation CEA groups shall be limited to the withdrawal sequence and to the insertion limits 1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained fully withdrawn 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3).I A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours.2 The Separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied: Page 8 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT a) Regulating Group 4 position is between 60 and 150 inches withdrawn. b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).3 Fully withdrawn ->147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHR)The linear heat rate limit of 13.1 kW/ft shall be maintained. 3.2.3 -Azimuthal Power Tilt (Ta)The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 10% with COLSS IN SERVICE when power is greater than 20% and less than or equal to 50%. AZIMUTHAL POWER TILT (Tq) shall be less than or equal to 5% with COLSS IN SERVICE when power is greater than 50%. See Figure 3.2.3-1.3.2.4 -Departure From Nucleate Boiling Ratio (DNBR)COLSS IN SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel -Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.COLSS OUT OF SERVICE, CEAC(s) OPERABLE -Operating within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.COLSS OUT OF SERVICE and Both CEACs INOPERABLE in Any OPERABLE CPC Channel -Operating within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE. Page 9 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT 3.2.5 -Axial Shape Index (ASI)The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits: COLSS OPERABLE-0.18 < ASI < 0.18 for power > 50%-0.28 < ASI < 0.18 for power >20% and < 50%COLSS OUT OF SERVICE (CPC)-0.10 < ASI < 0.10 for power >20%3.3.12 -Boron Dilution Alarm System (BDAS)With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.3.9.1 -Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration 2 3000 ppm.Page 10 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 ----- .......... . ...... ------- '------ '- - -REGION OF .. .(0,.ACCEPTABLE OPERATION:.REGIONOF UNACCEPTABLE 2 .:............. ....... jR.................... .............................. ,........... .j .. ........ ............. .............. ......OPERATION-- --- ----- -- -- -- -- --0 .-. ....0 100 200 300 400 S00 600 COLD LEG TEMPERATURE (F)Page 11 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7 6 5-. -.....- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..- ..-REGION OF ACCEPTABLI -OPERATION (500.,6.5): .. .............. ........ /..................... .................. I 0£-cj6 b.................... 4 3............. ....... ................................... (35o,4.0o_...................... _........ .... ............................... 2 0::........... REGION OF UNACCEPTABLE ................... ..................... P....EO ............. N..OP.ERAT10N

I_._*..__g...t.__^.__

':

# §; w s: ; s ; ;* ; :*: t.2

le e :' ' F j s *: *. t; *R s
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i * * -2 i 2 0 1w0 20( 3$0 400 COLD LEG TEMPERATURE (4 F)500 600 Page 12 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0*a R~~a x B, .((%,.5) .0)..,....,....,,,.fj7

............. ...... .. ..' .(50%.Q.O), ........I ....--..-.I- ---I&8aaetog-m .........(I00%,-041 CL 2..0-I 0 0-0.5-1.0-1.5-2.0-2.5-3.0-3S5............ I------ --1 A .~I .... .... .. .- ... ... .....---I............................. I 11 i.1 t-......................- 11 11.....s3M TC-AREA-OF --ACCEPTABLE OPERAJIU N .: 4 ... .......... .......... ............ ............ -(0% -3.4) --4.0-.A q------- ---------------- --- -------.v 0 10 0 30 40 5:0 60 :70 CORE POWER LEVEL (% OF RATED THERMAL POWER)80 90 100 End of Cycle Limit Beginning of Cycle Limit owns==TECH SPEC 3.1.4 Maximum Upper Limit w a

a
a a Page 13 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.1.5-1 CORE POWER LIMIT AFTER CEA DEVIATION*

z 0 ER 30 25 20 15 10 5 0 I.t -.Ii i i .- ., ... i.ti ..

i .t I .,-I S .. i S .I 0 10 20 3^0 O 405 60 TIME AFrER DEVIATION, MINUTES* WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL POWER PER THIS LIM1 CURVE, FURTHER REDUCTION IS NOT REQUIRED.Page 14 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)1.0 0.9 0.8 IN ml al a it a a a a Ia It Ia.1-3 aI aa i a Uf Y. -- ---1 I I (S$EE -FOOT-NOTE -IN SC FOR APPLICABILTYUOJ

....T. -UTBACK)MN .7...'Ow ING 0 0 ZO 0.7 0.6 0.5 0.4 0.3 I_,9----R 4 P I 3=111712.5 x~FI A-CO. WR) +25.5-172.5 x FRAC.KWi-.5'4-- -------- ---------- ----- ----- ---- --- -.. .... ..----3iti~~ I .... ...... .0.2 0.1 0.0 GROUP 5 I 1 1 GROUP3~GROUP I I I..-I+I I L I --I I I I I I I I I I I I FW* 120 90 60 30 0; FW* 120 90 60 GROUP 4 I_ I I I I I I I 30 0 30 O FW* 120 i90 60 GROUP 2 I I......11O O 0 '30 15 FlW* 110 Jo do go 6 CEA POSITION (INCHES WITHDRAWN)

Fully Withdrawn is defined as >147.75" (Pulse Counter) and >145.25" (RSPT)Page 15 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT FIGURE 3.1.7-2 Revision 13 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)1.0 0.9 0.8 I a z 0 z 0.7 0.6.0.5 0.4 03_ ... .\ f ....... ...._. .: --- -- ...... ...................

a3 t* ., .p'* ~' z t t5 z9 Ai'R ta_ _..._ .+\'-g_*j (SEE-FOOTNO-E N -SETION -3.1.7-FOR APPIlCABILITY FOLLOWING A REACTOR CUTBACK)i-- .. i .l 'GRP4 I GRP: I o'POg(=2 I~o I O Po I# v(i" i _F4f -1 I I I :------ ....... I.4147.75" (Pulse Counter) and >145.25" (RSPT)Page 16 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER z k 0--2 z 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 1 10.0 120.0 130.0 140.0 150.0 1.1....---- ------.- ........------------

....------------

....------------ I............ ...... --..------------ I ....:--------- --I.......... --- ---:------- ------------------ I------------ I ....--l- ----..........

---.........

l --------.- ----....------ 1-1 .............. --.--- .......------- ----------------

....I I............I -.- --- -,.-------- -.---------- -.------------ ....I-- --------.............. .- --- --------------- .......I......... --..........

i-----t+i--tz..+.l....*w...+.._.................. TRANSI[NT INSERTION LIMIT (75.0: jNCES)O- OPERATION ............ PR...... .TI* UNACCEPTABLE RESTRICTED

I: .::.:.. -- --- -------------

Z1 W " ":- *---s _ -w --------LONG TERM STEAbY STATE INSEIRTION LIMTlS(112.5 INCHES).. .. ... ....................... ..... ..... ..... ................ .' ... ...-OPERATION ACCEPTABLE -.......... ........... ...... ......... , i. ..i................ D 0.9 0.8 0.7 0.6 0.5 0. :0.3 0.2'FRACTION OF RATED THERMAL POWER 0.1 0.0 Page 17 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL (COLSS IN SERVICE)POWER 20.0 15.0--------------------------------------- m T-...REGIO NO .........: I UNACCEPTABLI OPERATION:I , .1.. .... ...10.0 5.0 r .. .. ...... ...REIO OFACPAL PRTO:__ _ _ _ _ _ _ _ : : : 0.0:20.0 30.0 40.0 50.0 60.0 70.0 80.0 CORE POWER LEVEL (% OF RATED THERMAL POWER)90.0 100.0 Page 18 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEAC's INOPERABLE 2i z 0:D 1:X I 0 P 0 P.9.to 34e I 20 15 10 5 I 0 0 25) 50 75'CORE POWER LEVEL ( OF RATED THERMAL POWER)100 Page 19 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)2.5 24 23:g R u I 2.2 2.1 ACCEXTABLE OPERATION ANY POEVER LIEVEL AT LEAST 1 CEAC OPERABLE IN E ACH 4OPERABLAE CPC CRANNEL (0.06,2.3 (0.1,2.38) _ , ....._ .: _ -. .--*- --- --* -*------ --- --*- -_ --*-(-0).1,2.28).
ACCEP!TABL E OPER:ATION
', l POWER,RAT OR ABOVE 90%A T LET I C AC OP BLE IN.. ............. ....... ... .. .. .. ... .... .... .... ......... ... ...E E PU RAB LE CPC CA--.-,...,... *------- * .r ACCPTBL OPOP ERATION U -UY 7 ..) : :f' :'N'--w--U ----------U ~X++r-pRo- --R 4': X ,: POWRAO,-OV9O i
I i s. i$ i ;3 tll##.e.§"e~~fAT LEAi§.ST..1i
§EAC O-iER'LEIN'U-if~i.t*-* I 2z0'1.9: 1 R A-.-.20-0.15 -0.0-0.05 .00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 20 of 26 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 13 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)3.6 3.5 3.4_- ............. ACCEPTABLE1 OPERATION ANY POWER LEVEL-BOTHtCEACs-INOPERABLE IN ANY OPERABLE CPC CHAN$EL.............. ... 4 iS0 ................34----- -- --- -.. .... ......) ............ I U U c: 3.3 11Ar 3.2 3.1_ _- -_ ----_-______-- -_ -~--^-----~-i ~---- ------- ----- S---- ---- ~--- -----r --- ---- -- -- ----s- -- -----~- ------- --- --- ----------0 ,3.27):':+ IUNACCEPTA0LE , .COPERATION: j..,...i .... ........ .. ... ...'I% I-0.20-0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 21 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table 3.3.12-1 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 0.5 hours ONA ONA 4 not on SCS 12 hours 0.5 hours ONA ONA 5 not on SCS 8 hours 0.5 hours ONA ONA 4& 5 on SCS ONA ONA ONA ONA Notes:SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 22 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table 3.3.12-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 > Keff > 0.97 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 1 hour 0.5 hours ONA 4 not on SCS 12 hours 1.5 hours 0.5 hours ONA 5 not on SCS 8 hours 1.5 hours 0.5 hours ONA 4 & 5 on SCS 8 hours 0.5 hours ONA ONA Notes:SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table 3.3.12-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 > Keff> 0.96 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 2.5 hours 1 hour ONA 4 not on SCS 12 hours 2.5 hours 1 hour 0.5 hours 5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours 4 & 5 on SCS 8 hours I hour ONA ONA Notes:SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Table 3.3.12-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 2 Keff> 0.95 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 3 hours 1 hour 0.5 hours 4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours 5 not on SCS 8 hours 3.5 hours 1.5 hours 0.75 hours N 4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA Notes:SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 26 Revision 13 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT T 3i Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff 0.95 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours 4 hours 1.5 hours 1 hour 4 not on SCS 12 hours 4.5 hours 2 hours 1 hour 5 not on SCS 8 hours 4.5 hours 2 hours 1 hour 4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA 6 24 hours 1.5 hours ONA ONA Notes:SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 26}}

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ML060040305: Difference between revisions

Revision as of 00:58, 14 July 2019

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Dear Sirs:

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