Text

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
	ML13108A176
Person / Time
Site:	Palo Verde
Issue date:	04/11/2013
From:	Weber T; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-06686-TNW/RKR
	Download: ML13108A176 (86)
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Technical Specification 5.6.5.d Saps Palo Verde Nuclear Generating Station 102-06686-TNW/RKR 5801 S. Wintersburg Road Tonopah, AZ 85354 April 11, 2013 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, 3 Docket Nos. STN 50-528, 50-529 and 50-530 Unit 1 Core Operating Limits Report (COLR), Revision 22 Unit 2 Core Operating Limits Report (COLR), Revision 18 Unit 3 Core Operating Limits Report (COLR), Revision 21 Pursuant to PVNGS Technical Specifications, Section 5.6.5.d, enclosed are the Units 1, 2 and 3 Core Operating Limits Report (COLR), Revisions 22, 18 and 21, respectively, which were made effective March 29, 2013. The following changes were implemented in these COLR revisions:

" Added clarifying instructions in determining control element assembly (CEA) insertion limits versus thermal power

Corrected the x-axis scale labeling to replace the fully withdrawn (FW) notation with 150 and clarified the description of fully withdrawn

" Added references to the Analytical Methods reference table and updated the heading information for the reference section

Editorial reformatting of Unit 2 and 3 COLR Table of Contents, List of Figures, and the List of Tables to match Unit 1 COLR format

Corrected a typographical error in the y-axis label for Figure 3.1.8-1 in the Unit 2 and Unit 3 COLRs

" Changed the formatting of the title text on Tables 3.3.12-1 through 3.3.12-5 (bolding the text of the KIf range applicable for each table) for clarity No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Mr. Robert K. Roehler, Licensing Section Leader, at (623) 393-5241.

Sincerely, Q, bDI Thomas N. Weber Department Leader, Regulatory Affairs TNW/RKR/CJS/hsc A A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Comanche Peak

Diablo Canyon o Palo Verde e San Onofre e South Texas

Wolf Creek

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Units 1, 2 and 3 Core Operating Limits Report (COLR), Revisions 22, 18 and 21 Page 2

Enclosures:

PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 22 PVNGS Unit 2 Core Operating Limits Report (COLR), Revision 18 PVNGS Unit 3 Core Operating Limits Report (COLR), Revision 21 cc: A.T. Howell III NRC Region IV Regional Administrator J. K. Rankin NRC NRR Project Manager for PVNGS M. A. Brown NRC Senior Resident Inspector for PVNGS

Enclosure PVNGS Unit 1 Core Operating Limits Report (COLR)

Revision 22

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 I

Effective March 29, 2013 Responsible Engineer TDigitally Trim ble, signed by Trimble, Patrick C(Z95337)

Date Patrick cz95337)

DN: cn=Trlmble, Patrick PatrickReason: Iam the author of this document C(Z95337) Date: 2013:03.27 12:08:53

-07'00' Independent Reviewer Bod na r, Digitally signed by Bodnar, Walter S(Z06432)

Date ON: cn=Bodnar, Walter Wte Reason: Ihave reviewed this document 5(Z06432) Date: 2013.03.27 12:18:40 S(Z06432)-07 '00' Responsible Section Leader Ash ton, Digitally signed by Ashton, Jeffrey sz03403)

Date Jeffrey cz003 DN: cn=Ashton, Jeffrey C(Z03403)

Reason: I am approving this document C(Z03403) Date: 2013.03.27 12:46:46

-07'00' Page 1 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 Table of Contents Description Pagge Cover Page 1 Table of Contents 2 List of Figures 3 List of Tables 4 Affected Technical Specifications 5 Analytical Methods 6 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 9 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 3.3.12 Boron Dilution Alarm System (BDAS) 11 3.9.1 Boron Concentration 11 Page 2 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 I

List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 12 I Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 13 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 14 Figure 3.1.5-1 Core Power Limit After CEA Deviation 15 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 16 (COLSS in Service)

Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 17 (COLSS Out of Service)

Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 18 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power (COLSS in Service) 19 I Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 20 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEAC(s)

Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 22 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page 3 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 23 I 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 24 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 25 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 26 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 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:

I T.S ReS Title Report No. Rev Date SU P-Re f#a CE Method for Control Element Assem- CENPD- N.A. January N.A.

1 bly Ejection Analysis 0190-A 1976 (13-N001-1301-01204-1)

The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.

2 Nuclear Design 266-P-A (13-N00 1-1900-01412-0)

Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September CESSAR System 80, Docket No. STN 1983 2 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.

4 Uncertainties 356(V)-P-A (13-NOO1 - 1303-01747-2)

System 8 0 TM Inlet Flow Distribution Enclosure N.A. February 1-P 4 (13-NOO1-1301-01228-0) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. 1 Analysis of CE and W Designed NSSS (13-NO01-1900-01192-3)

Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NO01-1900-01185-3)

Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A.

(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:

5.6.5.b.6.

Page 6 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 T.S ReS Title Report No. Rev Date - _M Re f#a Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.

(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement l-P). NRC approval for 5.6.5.b.6.

Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.

(13-NOO1-0201-00026-1) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.

1990 10 Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.

Arizona Public Service Company PWR NFM-005 1 August N.A.

11 Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)

Technical Description Manual for the CE-NPD 2 March N.A.

12 CENTS CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL 1) Vols. 1 Technical Description Manual for the CE-NPD 2 March N.A.

12 CENTS Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2) Vols. 2 Technical Description Manual for the CE-NPD 2 March N.A.

12 CENTS CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLOTM Cladding CENPD- 0 November N.A.

Material in CE Nuclear Power Fuel 404-P-A 2001 Assembly Designs (13-NOOI-1900-01329-0)

HERMITE, A Multi-Dimensional CENPD- July N.A.

14 Space-Time Kinetics Code for PWR 188-A N.A. 1976 Transients (HERMITE-TOPICAL)

TORC Code, A Computer Code for CENPD- N.A. April N.A.

15 Determining the Thermal Margin of a 161-P-A 1986 Reactor Core (NOO1-1301-01202)

Page 7 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 T.S ReS Re ffa Title Report No. Rev Date Supp CETOP-D Code Structures and Model- CEN- 1-P September N.A.

16 ing Methods for San Onofre Nuclear 160(S)-P 1981 Generating Station Units 2 and 3, (NO01-1301-01185)

"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.

Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) 17 and November "Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:

Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)."

CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A.

18 Improvement Program, (NOO1-1303- P-A 1986 02283)

Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.

19 Flow Analysis, (NOO-1301-01203) 183-A 1984 Methodology for Core Designs Contain- CENPD- 0 August N.A.

20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOO1-0201-00035)

Verification of the Acceptability of a 1- CEN-386- 0 August N.A.

Pin Burnup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO1-0201-00042)

a. Corresponds to the reference number specified in Technical Specification 5.6.5 I Page 8 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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. The required power reduction is based on the initial power before reducing power.

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 limitsI shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn 1' 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power Regulating Group 3 shall be maintained > fully withdrawn. 1,3 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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 9 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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 (FW) is defined as >147.75" (Pulse Counter indication) and

>145.25" (RSPT indication). No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements.

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 (Tq)

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 in Any OPERABLE CPC Channel - Maintain 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 CEAC(s) OPERABLE - Operate 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 - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.

Page 10 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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 !ý). 17 for power > 50%

-0.28 < ASI < 0.17 for power >20% and < 50%

COLSS OUT OF SERVICE (CPC)

-0.10 *ASI ýD. 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 _>3000 ppm.

Page 11 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 .... sIm 9mmrRmmmm 9-FTT19-- .mF...... ......... ......

6 5 .....(500,5.0)

REGION OF ACCEPTABLE OPERATION 4

z 0 3 Ell

..................... i i ........... REGIONOF 2

UNACCEPTABLE

.............. *6 N..............

OPERATION (3~50,i.0)

I.

0 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (*F)

Page 12 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED

. .................... ....................... 4.................... ................... ............... .............. .

7 S.(500,6.5):

6 5 .- .......

REGION OF ACCEPTABLI9 OP ER A TION .. .......i.....

..... ...... I.........

4 (350,4.0) z

..................... .................................................. 7 . . . . . . . . . . . . . . . . . . . . . .......................

0 3 REGION OF UNACCEPTABLE 2

OPERATION

. ............. . ...................... .......................... i....................... ....................... ]. .................

. .. . . f . . . . . . . . . I . . . . . I . . . . . I . . . .

. . . . q l l l l L. . . . . . . . . I l l l l l l l l l l . . . . . . . . . . . . . . . . . . .

0 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (F)

Page 13 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5

~ ~ ..................

~.......

.~~~~~~~~ ........ . 0 ............... ........... *... .....................

0.0

((05 %09.0

-0.5 0 . .......... ............. .............. ............... ........... ............................................. ............... ..........

-1.0 rJ-

-1.5 ............. . ........... .............. M T C A REA OF ................................... ..............

U ACCEPTABLE OPERATION

-2.0 0

F-, -2.5 02 0

0-

-3.0

-3.5

-4.0 (100%,-4.4

. -. . .I -. . I . . . I , , , I . . . I . . . I . . . I , , u m,,

-A r

,,=rj 0 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Maintain Operation within Boundaryi TECII SPEC 3. 1.4 NMaximum Upper timih .......

Page 14 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION&o

<100% to 16

[- ,-, 15 . ....... ........... 151 .. ...... ..... ....... ....................... ...... ................... ................. .. ... .. >80% RTP 15 0

u 12 12. *80% to

>70% RTP 10 . .. ....................... ...................... ................ .. ... ....... .... ..... ..... ..... ..... ...... ............ .... "1 COC4r.

10 . .10 8yl 8 70% to

>45% RTP 0

5 ......... ... .........- ....... ..............................

---........ 5 4./

3.

0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.

Page 15 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 ! = I = IINOTE:

aSee in Section 3.1.7 for applicability w Footnote i following a Reactor Power Cutback.

... .. ................. J ~omeet the Transient Insertion Limit (TIL) all 0.9 a!conditions below must be met:

° ~CEA Groups 1 and 2 must be >_fully

..... . ................ ......... withdrawn* (see definition below) in MODE 1 0.8 .......

and MODE 2.

AND

.. . ...... -........* ...... CEA Group 3 must be > fully withdrawn* for 0.7 power levels > 20%.

CEA Group 3 must be withdrawn > 60" for power > 0% and < 20%.

-C AND 0.6 CEA Group 4 must be > fully withdrawn* for o power levels > 70.87%.

0 . CEA Group 4 must be withdrawn > the 0.5 "

--..... group 4 TIL (TIL4) as indicated on the graph or z - by the equation:

Z TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%).

0 0.4 AND z < CEA Group 5 must be withdrawn > the

, . group 5 TIL (TIL5) as indicated on the graph or

'f , by the equation:

0.3 TIL5 = (172.5" x Fractional Power) - 64.5" O.

(for powers > 37.39% and < 100%).

oz*

0.2 z

i : !

0.1 L.

......... ....... ... 0 - ....

i ........... ............. J........

0.0 GROUP5 GROUP3 GROUP 1 I I I I I I I I I I I I I I 150*120 90 60 30 0 150*120 90 GROUP 4 60 30 0 150*120 GROUP 2 90 60 30 0 I E*A 9P0 60 3O0 CEA POSITION (INCHES WITHDRAWN)

( INH tW 90 Nt 30 I Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).

No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. I Page 16 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 -r rI - NOTE:

'See Footnote in Section 3.1.7 for applicability

following a Reactor Power Cutback.

. ....................To meet the Transient Insertion Limit (TIL) all 0.9

-conditions below must be met:

CEA Groups 1 and 2 must be > fully 0.8 ............................................... withdrawn* (see definition below) in MODE 1 and MODE 2.

AND CEA Group 3 must be > fully withdrawn* for 0.7 . . ....... . . ..... power levels > 20%.

CEA Group 3 must be withdrawn > 60" for 0

Z power > 0% and < 20%.

AND 0.6 CEA Group 4 must be > fully withdrawn* for power levels > 54.97%.

. E CEA Group 4 must be withdrawn > the 0.5 .... .---

"w-.-- ........ ....... group 4 TIL (TIL4) as indicated on the graph or

.rd by the equation:

TIL4 = (250.9" x Fractional Power) + 9.82" 0

z 0.4

..... .A.. ....... N (for power > 20% and < 54.97%).

0 " < CEA Group 5 must be withdrawn > the P- Do group 5 TIL (TIL5) as indicated on the graph or by the equations:

0.3 , TIL5 = (250.9" x Fractional Power) - 80.18"

*1X; (for power > 31.96% and < 75.00%).

o 9 o o, TIL5 108" (for power level > 75.00%).

. 90. .. .. .. ... A i. .... ... A....... ........ A............ A........ ......

0.2 U

z 0.1 ................ ....... ....... ....... I ....

0.0 GROUP5 GROUP3 GROUPI I I I I I I I I I I I I I I I I I I 150" 120 90 60 30 0 150" 120 90 GROUP 4 60 30 0 150" 120 GROUP 2 90 60 30 0 I

ý"A0 P 6T0 30 (0 6 1W T CEA POSITION (INCHES WITHDRAWN) 60 W190 0 I Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).

No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. I Page 17 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0

....I ------------- .. ., . . -- --- - -- . .. . . . . : .. . . . . .; ... .. ... :-----------

10.0 20.0 30.0 40.0 50.0 60.0

............ : ............. *............... .............. I............. . ............ ! ............ .............. .. ............ ............

................................................. RA NSI N.....

............ I 70.0 80.0

-......... OPERA-T-ION ............ 0 :O. PERA-TION.........................

............. .. i............. i............. ...

....... ....- ......... . ............ ............... *............. i............... ...........

90.0 UJNACCEPTABLE .. ... . RESTRICTED.. ... ..I.. ....

-.OP E ... RAT .I O .. N ..--..

.*..---- . . .. .. ..........-O. ... ... ... I .ON..

100.0 110.0 - :

120.0 LONG TERM............. . . . . .............

STEADY i..... STATE ............. .................................

INSERTION::LIMITS: (112.5 INCHES) ........... ...........

130.0 OPERATION ACCEPTABLE 140.0 . ......................... J............. ............. ............. ............. ......... ....I.... ....... ...........

. ., . ,,l , , , i , . i . . .. . . . . iI . . . . . . . . I . . . I . .

150.0

.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 FRACTION OF RATED THERMAL POWER Page 18 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL PC)WER (COLSS IN SERVICE) 20.0 I I I 15.0 .................

. ............... ....RE G IO N -OF ............... .................................

UNACCEPTABLE OPERATION F-

,J.,

0 10.0 5.0 REGION OF. LCCEPTABLE OPERATION

. . I . . . , ,, I . . . I , ,

u.u L-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 19 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 (95,20) 20 z

0 0

15 0

10 0

C,,

0 u

5 (805) 0 50 60 70 80 90 100 CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 20 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 . . . . I. . . . . . . ...

. . . . . . I. . . . . . . . I . . . . I. . . . . . . .I . . . . . . . . I .. . . . . .

ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 (0238 (0.1,2.38)

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

2.3

(-0.1,2.28) 2.2 ACCEPTABLE OPERATION

POWER AT OR ABOVE 90%

AT LEAST 1 CEAC OPERABLE IN u 2.1 -.. .................... EACH OPERABLE CPC"CHANNEL ..............................

cl

. .......................................... ............. (0.05,2.00) ... ,

2.0 0. , 0. .0..... .

(011.93) UNACCEPTABLE 1.9 ........................................................ O P E RA T ION ....... .............................. ...............

.. .. I .. ... . .. .. .. I .. ...... I. . . . .I. . . . . . . . . .

1.8

-0.:20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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 I . . . .. I . . . . . I . . . . . I . . . . .

ACCEPTABLE IOPERATION

. . . .I . . . . . . . . . . . .

ANY POWER LEVEL BOTH CEACs INOPERABLE 3.5 7

IN ANY OPERABLE CPC 3.4 CHANNEL

.. (0.1,3.41).:

z 3.3 ................ ...............

(-o. I:,3.27) u 3.2 ......... ..............

UNACCEPTABLE OPERATION 3.1 ................. ...............

,, ., . I .,,, I .... .............. .... I .......

..... llllllllllllllllllll 3.0 '

-0.220 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 22 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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 > Keff> 0.95 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months ONA 6 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 27 of 27

Enclosure PVNGS Unit 2 Core Operating Limits Report (COLR)

Revision 18

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 I

Effective March 29, 2013 Lb EDigitally signed by Trimble, Responsible Engineer Trim ble, Patrick C(Z95337)

Date Patrickc(z95337, DN: cn=Trimble, Patrick PatrickReason: Iam,this document the author of C(Z95337) Date: 2013.03.27 12:09:31

/ -07,00, Independent Reviewer BdOUna r, Digitally signed by Bodnar, Waiter S(Z06432)

Date DN: cn=Bodnar, Walter W alIReason:

r thave I reviewed this document S(Z06432) Date: 2013.03.27 12:22:14

-07'00' Responsible Section Leader As eDigitally Dton, signed by Ashton, Date Jeffrey DN: cn=Ashton, Jeffrey dcumento*

C(Z034103)

Reason: I am approving this C(Z03403) Date: 2013 'o0.27 document.

-07'00' 12:48:57 Page 1 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 9 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 3.3.12 Boron Dilution Alarm System (BDAS) 11 3.9.1 Boron Concentration 11 Page 2 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 I

List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 12 I Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 13 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 14 Figure 3.1.5-1 Core Power Limit After CEA Deviation 15 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 16 (COLSS in Service)

Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 17 (COLSS Out of Service)

Part Strength CEA Insertion Limits Versus Thermal Power 18 Figure 3.1.8-1 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power (COLSS in Service) 19 I Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 20 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEAC(s)

Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 22 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page 3 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 23 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 24 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 25 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 26 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 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:

I T.S Ref#a Title Report No. Rev Date Supp CE Method for Control Element Assem- CENPD- N.A. January N.A.

1 bly Ejection Analysis 0190-A 1976 (13-N001-1301-01204-1)

The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.

2 Nuclear Design 266-P-A (13-N001 - 1900-01412-0)

Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September CESSAR System 80, Docket No. STN 1983 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.

4 Uncertainties 356(V)-P-A (13-N001-1303-01747-2)

System 8 0 TM Inlet Flow Distribution Enclosure N.A. February 1-P 4 (13-NOO-1301-01228-0) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. 1 Analysis of CE and W Designed NSSS (13-NOO1-1900-01192-3)

Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-NOO - 1900-01185-3)

Letter: O.D. Parr (NRC) to F. M. Stern N.A. N.A. June 13, N.A.

(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:

5.6,5.b.6.

Page 6 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 T.

ReSS Title Report No. Rev Date RefW Sup Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.

(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement I-P). NRC approval for 5.6.5.b.6.

Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.

(13-N001-0201-00026-1) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.

1990 10 Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.

Arizona Public Service Company PWR NFM-005 I August N.A.

I Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)

Technical Description Manual for the CE-NPD 2 March N.A.

12 CENTS CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL 1) Vols. I Technical Description Manual for the CE-NPD 2 March N.A.

12 CENTS Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2) Vols. 2 Technical Description Manual for the CE-NPD 2 March N.A.

12 CENTS CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLOTM Cladding CENPD- 0 November N.A.

Material in CE Nuclear Power Fuel 404-P-A 2001 Assembly Designs (13-N001 -1900-01329-0)

HERMITE, A Multi-Dimensional CENPD- July N.A.

Space-Time Kinetics Code for PWR 188-A N.A. 1976 14 Transients (HERMITE-TOPICAL)

TORC Code, A Computer Code for CENPD- N.A. April N.A.

15 Determining the Thermal Margin of a 161-P-A 1986 Reactor Core (N001 - 1301-01202)

Page 7 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 T. S ReS Title Report No.

RefW Rev Date Supp CETOP-D Code Structures and Model- CEN- 1-P September N.A.

160(S)-P 1981 16 ing Methods for San Onofre Nuclear Generating Station Units 2 and 3, (N001-1301-01185)

"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.

Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) 17 and November "Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:

Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)."

CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A.

18 Improvement Program, (NOO1-1303- P-A 1986 02283)

Loss of Flow, C-E Methods for Loss of CENPD- 0 June N.A.

Flow Analysis, (NOO1-1301-01203) 183-A 1984 Methodology for Core Designs Contain- CENPD- 0 August N.A.

20 ing Erbium Burnable Absorbers 382-P-A 1993 (N001-0201-00035)

Verification of the Acceptability of a 1- CEN-386- 0 August N.A.

Pin Burnup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO 1-0201-00042)

a. Corresponds to the reference number specified in Technical Specification 5.6.5. I Page 8 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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. The required power reduction is based on the initial power before reducing power.

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 limitsI shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawnl1 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power Regulating Group 3 shall be maintained > fully withdrawn. 1,3 1A 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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 9 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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 (FW) is defined as >147.75" (Pulse Counter indication) and

>145.25" (RSPT indication). No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements.

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 (Tq)

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 in Any OPERABLE CPC Channel - Maintain 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 CEAC(s) OPERABLE - Operate 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 - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.

Page 10 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 3.2.5 - Axial Shape Index (ASI)

The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:

COLSS OPERABLE

-0.188*ASI *).17 for power> 50%

-0.28 < ASI < 0.17 for power >20% and < 50%

COLSS OUT OF SERVICE (CPC)

-0.10 _*ASI IJ.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 > 3000 ppm.

Page 11 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7

6

.... ....................... (500,5.0~

5 REGION OF ACCEPTABLE OPERATION 4

z<0 0 3 REGION OF

..UNACCEPTABLE 2

OPERATION (350,1.0)

. . . . . . . . . . . I . . . . . . . . . I . . . . . . . . . I . . . . . . . . . . . . . . . . .

0 0 100 200 300 400 500 600 COLD LEG TEMPERATURE ('F)

Page 12 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED (500,6.5):

6 .-.- ..-.-. O OF Ii........................ --

RG......................

... -------- . . . .. . /. . .. . . . .. ... ................ .

REGION OF.

ACCEPTABLI/

5 ........... ..OP E R A T IO N ... . .............

4 .

z (350,4.0) z REGION OF UNACCEPTABLE 2 ..................... .................................................. 7....................... ................ ....... .... ... ............ .

OPERATION 0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . L. . . . . . . . . . . . . . . . .

0 100 200 300 400 500 600 COLD LEG TEMPERATURE (*F)

Page 13 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0 (100%,02.

-0.5 Z . ........... ............. m............. ............. ..... ......... ............... ............... ....... (100 %,-0 .2 0t

-1.0 0

-1.5 ....... ......... . .... -MTC AR E A O F .....................

U ACCEPTABLE OPERATION

-2.0 0 ...........4...

0 -2.5 1-0 -3.0

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

-3.5

-4.0

.(%,-4.4)(1%-4

-4.5 0 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL

(%OF RATED THERMAL POWER)

Maintain Operation within Boundary TECH- SPEC 3.1.4 Maximum Upper Limit ........

Page 14 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION&o Iv 16 100% to

>80% RTP 15 z

u-0 12 12. *80% to

>70% RTP 0LI 10 10 9

8 8 70% to

>45% RTP 5 5

/ / -45% T 0 . .

..... I.

0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES

WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.

Page 15 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 NOTE: 4 See Footno te in Section 3.1.7 for applicability 4

,,d following a Fteactor Power Cutback. 4 To meet the Transient Insertion Limit (TIL) all 0.9 conditions bielow must be met:

CEA Grc ups 1 and 2 must be >. fully 0.8 ..... . withdrawn (see definition below) in MODE 1 and MODE 2.

AND CEA Grl up 3 must be > fully withdrawn* for 0.7 power ]eve Is > 20%.

CEA Grc3up 3 must be withdrawn > 60" for 0

- power> 0(% and < 20%.

AND 0.6

. W CEA Grc)up 4 must be > fully withdrawn* for 2! powerleve Is > 70.87%.

0 F-- - . CEAGrc up 4 must be withdrawn > the LT., 0.5 . .............. group 4 T IL (TIL4) as indicated on the graph or by the equ ation:

.Z :-. <- _. : I *" '* TIL4=(17 2.5" x Fractional Power) + 25.5"

.. F .. . (for power > 20% and < 70.87%).

z 0.4 AND 0 U .. CEA Grc up 5 must be withdrawn > the U group 5 TI L (TIL5) as indicated on the graph or o C . . by theequ ation:

0.3 TIL5 = (172.5" x Fractional Power) - 64.5"

06. :0o

= (for power s_> 37.39% and < 100%).

0.2 U

0.1

...... ................. I ..........I.... FF1 0.0 GROUP 5 GROUP 3 GROUP 1 I I I I I I I I I I I I I I I I 150*120 90 60 30 GROUP 4 0 150*120 90 60 30 GROUP 2 0 150*120 90 60 30 0 I

1 E0*10OI TIO 3No IN WI90

1E020 W60 130N)

CEA POSITION (INCHES WITHDRAWN)

Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).

No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements I Page 16 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 NOTE:

See Footnote in Section 3.1.7 for applicability following a Reactor Power Cutback.

To meet .. the Transient Insertion Limit (TIL) all 0.9 conditions below must be met:

CEA Groups 1 and 2 must be > fully 0.8 ....... awithdrawn* (see definition below) in MODE 1 and MODE 2. .

.4 AND CEA Group 3 must be > fully withdrawn* for Lu 0.7 power levels > 20%.

CEA Group 3 must be withdrawn > 60" for 0

Z power > 0% and < 20%.

0.6 AND CEA Group 4 must be > fully withdrawn' for z power levels > 54.97%.

F- CEA Group 4 must be withdrawn > the 0.5 ....... . ...... ......... group 4 TIL (TIL4) as indicated on the graph or by the equation: 4 TIL4 = (250.9" x Fractional Power) + 9.82" i .... ... ..... ! . ... . ...-----

-< (for power > 20% and < 54.97%).

0 ..... AND z 0.4 LT. ,= ! ! CEA Group 5 must be withdrawn > the U *.4 !, group 5 TIL (TIL5) as indicated on the graph or by the equations:

0.3 40..... . TIL5 = (250.9" x Fractional Power) -80.18" I- (for power > 31.96% and < 75.00%).

I 0TIL5 108" (for power level > 75.00%). .4 0.2 z

0.1 0.0 GROUP5 GROUP3 GROUP I i I I I i I I I I I I I I I I I I I 150* 120 90 60 30 GROUP4 0 150* 120 90 60 30 GROUP2 0 150* 120 90 60 30 0 I l0* CEA A09P0 6+0 31o tH A90N60 130 POSITION (INCHES WITHDRAWN)

Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).

No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements I Page 17 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 40.0 50.0 u

............* .............:.............I:

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

60.0 0

I 70.0 :TRASIET' NSETION, LIMITi (75.~INCHES)

C 80.0 u -.. ......... ... ......................... . ...... ....... OE ... .PE R AT. T.O................... .......

90.0

UNACCEPTABLE: I ESTRICE 100.0

.:............. i.. ... ...

..... i.... ...... ............ .......... ... ... .... ... ... ... ...... ... .

110.0 LONG TERM UN STEAY STATE INSERTION jET:CE ERTINACCEPTABLE (112.5 INCHES)

SELIMITS I ...... ..................... ........................

120.0 130.0 TER STAD STT ISR LON IOU IS(1251.NH

. . .. .i . . i . . . i . . . ... . . . ....

140.0 150.0 0

1.I 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 FRACTION OF RATED THERMAL POWER Page 18 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 I .I . . .. . . . I . . .

I

. . . . . . . I . . . .s 15.0 ............. ...RR...

E GIO N .OF .......-....... ............................. .

UNACCEPTABLE OPERATION 0 10.0 H/.

5.0 REGI( WLCEPTABL:E OPERATION

-. . .. .... . .. i . . I . .

0.0 L 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 19 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 20 z

0 15 Z<L 0LI 10 z

C-)

5 0

50 60 70 80 90 100 CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 20 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2.5 . . . . . . . . . . . .. . .. . . . . . . I .. . . . . . . . . . . . . . . . .. .. . . . . . .

ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2.4 (0(01228) (.,238:

2.3

. ..... ................... *. ............ ==......

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

2.2 ACCEPTABLE OPERATION z POWER AT OR ABOVE 90%

AT LEAST I CEAC OPERABLE IN 2.1 ............... --- EACH OPERABLE CPC CHANNEL ...........................

C..

........................ . .... . ........... ....... (0.0.5,2.00)

............ * ( . , u!0 .0........

2.0 (01,1.93) UNACCEPTABLE 1.9 S .................................... O P E R A TION ... ................ ..................................

,,, ,, LL,,. ..L LL

,,LJ L . .L. L. L..... ! .1 J........ I L......... L.. . . . I . . . . I .. . . .

1.8

-_).20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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 ACCEPTABLE OPERATION ANY POWER LEVEL 3.5 i...... .. OPER.B...

BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL ii............ .............

(0.1,3.41)::

3.4 -.. ........ ... . (.0.0 3,4 1) ..................

z 3.3

(-o.1li,3.27) 3.2 ..................... . ................. ................

UNACCEPTABLE OPERATION

.. .. . , ° .... l ..

3.1 l ......... I......... I ..... .... I...... ...

,In I ... I ....I ...I .....I ..... ..

I . I

-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 22 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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 > Keff> 0.95 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months ONA 6 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 27 of 27

Enclosure PVNGS Unit 3 Core Operating Limits Report (COLR)

Revision 21

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 Effective March 29, 2013 Responsible Engineer Tri be, Digitally signed by Trimble, Patrickz33 Date DN: cn=Trimble, Patrick Patrick Reason: I am the author of this document C(Z95337)

QZ95337 Date: 2013.03.27 12:10:07

-07T00, Digitally signed by Bodnar, Independent Reviewer Bod na r, Walter S(Z06432)

Date Walter S(Z06432)

DN: cn=Bodnar, Walter W alterReason: Ihave document reviewed this S(Z06432) Date: 201 3.03.27 12:24:40

-07'00' Responsible Section Leader h A n Digitally signed by Ashton, Jeffrey C(Z03403)

Date DN: cn=Ashton, Jeffrey C(Z03403) ey Reason: lam approving document this C(Z03403) Date: 2013.03.27 12:51:01 QZ03403-07'00' Page 1 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 9 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 9 3.1.4 Moderator Temperature Coefficient (MTC) 9 3.1.5 Control Element Assembly (CEA) Alignment 9 3.1.7 Regulating CEA Insertion Limits 9 3.1.8 Part Strength CEA Insertion Limits 10 3.2.1 Linear Heat Rate (LHR) 10 3.2.3 Azimuthal Power Tilt (Tq) 10 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 10 3.2.5 Axial Shape Index (ASI) 11 3.3.12 Boron Dilution Alarm System (BDAS) 11 3.9.1 Boron Concentration 11 Page 2 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 I

List of Figures Description Page Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 13 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 14 Figure 3.1.5-1 Core Power Limit After CEA Deviation 15 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 16 (COLSS in Service)

Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 17 (COLSS Out of Service)

Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 18 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 19 (COLSS in Service)

Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 20 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, CEAC(s)

Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 22 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)

Page 3 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 23 I 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 24 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 25 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 26 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 27 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 4 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:

I T.

ReSS Title Report No. Rev Re f#a Date Supp CE Method for Control Element Assem- CENPD- N.A. January N.A.

I bly Ejection Analysis 0190-A 1976 (13 -N00 1-1301-01204-1)

The ROCS and DIT Computer Codes for CENPD- N.A. April 1983 N.A.

2 Nuclear Design 266-P-A (13-NOO - 1900-01412-0)

Safety Evaluation Report related to the NUREG- N.A. March 1983 1 Final Design of the Standard Nuclear 0852 Steam Supply Reference Systems September CESSAR System 80, Docket No. STN 1983 2 50-470 December 1987 3 Modified Statistical Combination of CEN- 01-P-A May 1988 N.A.

4 Uncertainties 356(V)-P-A (13-NOO-1303-01747-2)

System 8 0 TM Inlet Flow Distribution Enclosure N.A. February 1-P 4 (13-N001-1301-01228-0) 1-P to LD- 1993 82-054 Calculative Methods for the CE Large CENPD- N.A. March 4-P-A Break LOCA Evaluation Model for the 132 2001 Rev. 1 Analysis of CE and W Designed NSSS (13-N001-1900-01192-3)

Calculative Methods for the CE Small CENPD- N.A. April 2-P-A 6 Break LOCA Evaluation Model 137-P 1998 (13-N001 - 1900-01185-3)

Letter: O.D. Parr (NRC) to F. M. Stem N.A. N.A. June 13, N.A.

(CE), (NRC Staff Review of the 1975 7 Combustion Engineering ECCS Evaluation Model). NRC approval for:

5.6.5.b.6.

Page 6 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 T.

ReSS Title Report No. Rev Date sP-1 Re f#a Letter: K. Kniel (NRC) to A. E. Scherer N.A. N.A. September N.A.

(CE), (Evaluation of Topical Reports 27, 1977 8 CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.

Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.

(13-NOO1-0201-00026-1) P-A 1990 Letter: A. C. Thadani (NRC) to A. E. N.A. N.A. April 10, N.A.

1990 10 Scherer (CE), ("Acceptance for Reference CE Topical Report CEN-372-P"). NRC approval for 5.6.5.b.9.

Arizona Public Service Company PWR NFM-005 I August N.A.

Reactor Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)

Technical Description Manual for the CE-NPD 2 March N.A.

12 CENTS CodeVolume I 282-P-A 2005 (CENTS-TD MANUAL-VOL 1) Vols. I Technical Description Manual for the CE-NPD 2 March N.A.

12 CENTS Code Volume 2 282-P-A 2005 (CENTS-TD MANUAL-VOL 2) Vols. 2 Technical Description Manual for the CE-NPD 2 March N.A.

12 CENTS CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL 3) Vols. 3 Implementation of ZIRLOTM Cladding CENPD- 0 November N.A.

Material in CE Nuclear Power Fuel 404-P-A 2001 Assembly Designs (13-NOO-1900-01329-0)

HERMITE, A Multi-Dimensional CENPD- July N.A.

188-A N.A. 1976 14 Space-Time Kinetics Code for PWR Transients (HERMITE-TOPICAL)

TORC Code, A Computer Code for CENPD- N.A. April N.A.

15 Determining the Thermal Margin of a 161 -P-A 1986 Reactor Core (NOO - 1301-01202)

Page 7 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 T._SS ReS Title Report No.

Re fW Rev Date Supp CETOP-D Code Structures and Model- CEN- 1-P September N.A.

ing Methods for San Onofre Nuclear 160(S)-P 1981 16 Generating Station Units 2 and 3, (NOO 1-1301-01185)

"Safety Evaluation related to Palo Verde N.A. N.A. September N.A.

Nuclear Generating Station, Unit 2 29, 2003 (PVNGS-2) Issuance of Amendment on Replacement of Steam Generators and Uprated Power Operation, (September 29, 2003) 17 and November "Safety Evaluation related to Palo Verde 16, 2005 Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendments Re:

Replacement of Steam Generators and Uprated Power Operations and Associated Administrative Changes, (November 16, 2005)."

CPC Methodology Changes for the CPC CEN-3 10- 0 April N.A.

18 Improvement Program, (NOO1-1303- P-A 1986 02283)

CENPD- 0 June N.A.

19 Loss of Flow, C-E Methods for Loss of Flow Analysis, (NOO1-1301-01203) 183-A 1984 Methodology for Core Designs Contain- CENPD- 0 August N.A.

20 ing Erbium Burnable Absorbers 382-P-A 1993 (NOO-0201-00035)

Verification of the Acceptability of a I- CEN-386- 0 August N.A.

Pin Burnup Limit of 60 MWD/kgU for P-A 1992 21 Combustion Engineering 16 x 16 PWR Fuel (NOO 1-0201-00042)

a. Corresponds to the reference number specified in Technical Specification 5.6.5. I Page 8 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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. The required power reduction is based on the initial power before reducing power.

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 limitsi shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1 shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn 1' 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power 1

Regulating Group 3 shall be maintained > fully withdrawn. ' 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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 9 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 (FW) is defined as >147.75" (Pulse Counter indication) and

>145.25" (RSPT indication). No further CEA withdrawal above FW is required for CEAs' to meet the Transient Insertion Limit (TIL) requirements.

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 (Tq)

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 in Any OPERABLE CPC Channel - Maintain 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 CEAC(s) OPERABLE - Operate 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 - Operate within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel with both CEACs INOPERABLE.

Page 10 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 L.17 for power> 50%

-0.28 < ASI < 0.17 for power >20% and < 50%

COLSS OUT OF SERVICE (CPC)

-0.10 .!ASI *). 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 > 3000 ppm.

Page 11 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 , , , .. . . . , , , . . ,., ,, , , . . . , ,. ......, ,

5............. ........6 .N.... : .................. I........................ ....5 r ...... ( 00,5.o0

.REGION OF(50)

ACCEPTABLE OPERATION z..

i . . . . . . . . . . . . . . . . . . . . .... ...................... .. ..................... . . . . . . .. . . . .....................

z ..........

..... .......... ........................S A; ,AL 3 .....

0................

REGION OF UNACCEPTABLE OPERATION (350,1.0) 01 . . . . . . . . . . .. . . . . .. I . . . . . . . . . I . . . . . . . . . I . . . . . . . . . I . . . . . . . . .l 0 100 200 300 400 500 600 COLD LEG TEMPERATURE (°F)

Page 12 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED 7

(500,6.5)::

6 REGION OF ACCEPTABLE 5 OPERATION 4

Z (350,4.0) z 0 3 REGION OF UNACCEPTABLE 2

OPERATION

.I ........

0 llllllllllllllI ............................................

0 100 200 300 400 500 600 COLD LEG TEMPERATURE (TF)

Page 13 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5

.(o% ,o5* * ....... :.. .

0.0 ...........

(5o0%, 0.o).........................

' ' i

.......... .......... .. .. .. .. .. .. .. . .. ... .. .... .......... .... .................... ( j.QQ0o,7-o2)

-0.5 0

-1.0

-1.5 -. -.----. ...... ..................... ...... ....... M T C -AR EA O F -. ............ ...........................

ACCEPTABLE 0

-OPERATION.

-2.0

-2.5 0

-3.0

-3.5

-4.0 (100%,-4.41

(0%,-4.4)

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

-4.5 0 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL

(%OF RATED THERMAL POWER)

Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit .......

Page 14 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION&o 20 15 16

-100% to

>80% RTP

. 15 z

0 r-u -04 12 12. *580% to 0

>70% RTP 10 0 10 9

rD

8. 8 70% to -

>45% RTP 0

z 2

5 ..................... ................... ... ........ ....... .......... .... ... .. ... ...... .............. .................... 5

// *: '_45% RTP" 0 .

, . .I..... .ll. . .l lllllll 0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES

WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.

Page 15 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 1.0 NOTE:

See Footnote in Section 3.1.7 for applicability

'following a Reactor Power Cutback.

0.9 ,To meet the Transient Insertion Limit (TIL) all

'conditions below must be met:

CEA Groups 1 and 2 must be > fully 0.8 withdrawn* (see definition below) in MODE 1 and MODE 2.

AND CEA Group 3 must be > fully withdrawn* for 0.7 power levels > 20%.

CEA Group 3 must be withdrawn > 60" for 0

power > 0% and < 20%.

AND 0.6 CEA Group 4 must be > fully withdrawn* for 0

power levels > 70.87%.

0~ F-, CEA Group 4 must be withdrawn > the 0.5 group 4 TIL (TIL4) as indicated on the graph or by the equation:

1- TIL4 = (172.5" x Fractional Power) + 25.5" (for power > 20% and < 70.87%).

0~ 0.4 AND P CEA Group 5 must be withdrawn > the oq group 5 TIL (TILS) as indicated on the graph or U

by the equation:

0.3 22C TIL5 = (172.5" x Fractional Power) - 64.5" (for powers > 37.39% and < 100%).

0.2 F-<

0.1 U __t__ __ __I__

0.0 1 I 1 1 1 1 1 1 GROUP5 GROUP I I I I I I I I GROUP3 I I I I I I I I I i 150" 120 90 60 30 GROUP4 0 150" 120 90 60 30 GROUP2 0 150" 120 90 60 30 0 I

1 EP1I0 9 T0 3I0 N 6N0 I90 W60 1J0W 120 130 CEA POSITION (INCHES WITHDRAWN)

Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).

No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. I Page 16 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 NOTE:

See Footno te in Section 3.1.7 for applicability

following a Reactor Power Cutback.

0.9 .............. ........ ....... ........... .'To m ee t the Transient Insertion Limit (TIL) all

conditions b)elow must be met:

CEA Gr oups 1 and 2 must be > fully 0.8 withdrawr *"(see definition below) in MODE 1 and MOD E 2.

A.N!D CEA Gr oup 3 must be > fully withdrawn* for 0.7 ...... power lev els > 20%.

CEA Group 3 must be withdrawn > 60" for Z power_> 0)% and < 20%.

AND 0.6 GEA Gr oup 4 must be >_fully withdrawn* for

. . i power lev els > 54.97%.

L.J CEA Gr oup 4 must be withdrawn > the 0.5 group 4 T IL (TIL4) as indicated on the graph or by the eq uation:

L- ; TIL4=( 250.9" x Fractional Power) + 9.82" U (for power: > 20% and < 54.97%).

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

z 0.4 AND 0 U;! Wt:; *CEAGr oup 5 must be withdrawn > the u i group5T IL (TIL5) as indicated on the graph or

-. .by the eq uations:

0.3 , !. TIL5 ( 250.9" x Fractional Power) - 80.18" S-(for powerr > 31.96% and < 75.00%).

0: =COO TIL5=1 08" (for power level >. 75.00%).

v 0.2 U

0.1 0

i I I I I I I I 0.0 GROUP5 GROUP 3 GROUP I I I I I I I I I I I I I I I I I I 150*120 90 60 30 0 150*120 GROUP4 90 60 30 GROUP2 0 150*120 90 60 30 0 I CEA"10 9PI0 3T0 CEA POSITION (INCHES WITHDRAWN)

IN 1 W60 190 120D30 I

Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).

No further CEA withdrawal above FW is required for CEAs' to meet the TIL requirements. I Page 17 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 40.0 I-v 50.0

. ............ ....... ...... .............. ... .......... .......... ... ......... t............. . .. ............ ............... ............

60.0 z

u z ............. IE...........................N T INSE.T..N I .......... .......... L M.............I......

. E I..

I 70.0 0

r-2

............. I * . . . . .* . ............. .............. : . . ........ i................ ...........

0 80.0

. O

............ A............

....... ...... .............. O PERA.TIO N ........................

C.) ... ..... ..... .:...:.. ...

.. ... .. : .. ... .. .. . ... .. . w i............ . ............ ..............

u 90.0

NACCEPTABLE RESTRICTED z

100.0 I-.

110.0 LONG TERM STEADY STAE NSERTNI ISION LIMIT 12.5 INCHES (

120.0 130.0 LON TER STAYSAEISR IO U IS(125NCE OPERATION ACCEPPTARSL

..... . . . . i..............

140.0 150.0 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 FRACTION OF RATED THERMAL POWER Page 18 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 .- lmmm E- .- .... .... .... ....

15.0 ................. RE G IO N -OF ............... .................-...............

UNACCEPTABLE OPERATION 0H, 10.0 5.0 REGION OF~ ýCCEPTABLE OPERA TION

. . i . . I . . .. I . . . I . . . I , , S.1i. ,

0.0 llqlilllllllll ........................

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 19 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25 .. .

(95,20) 02 20 .5 ............................................................................................................. .. ............ . . . . . .

z C-)

10... ...................... ...... -------

C) 15 . .. . . . . . ...............

15 0 0 z

.-4 0

(80,5)

(70 0)/

0 . .. . . . .. . ..

50 60 70 80 90 100 CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 20 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE) 2 .5 ......... .. . . . .i ........ . . . .

......... , ......... ......... I ........ r ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL 2 .4 . ............................... .................................... .........................- ....... .. ............... ................

(0.06,2.38) ('0.1,2.38):

2.32 . .1,228)

S 2.2 ... .. -

ACCEPTABLE OPERATION POWER AT OR ABOVE 90%/c ZAT LEAST I CEAC OPERABLE IN 2.1 -.------.-- ........-- "EACH OPERABLE CPC CHANNEL' . .......

.0

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

~ : : : .................

(0.0.,2.00) ...............

(011.93) UNACCEPTABLE

1. . . . . ................. OP R TO....i ................. i.................. ...............

1.9 ......OPERATION---

1.8 1 . . . . . . .. . . . .. . . .. . . . .. .. .. . . . .. . . .. . .. .. . . . . . . . . .. . . . . . . . . .

-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 l....................~...........1...........l ACCEPTABLE OPERATION m .......

ANY POWER LEVEL INOPERABLE 3.5

.. ...BOTH......... .CEACs IN ANY OPERABLE CVC CHANNEL

...... . .......... ............. - ......... . . . . (0.1,3.41)::

3.4 04 co z

3.3 - ............ .........

(-0.1*,3.27) u 3.2 UNACCEPTABLE OPERATION 3.1

. . . . . .... .... ...... . . I I 12A I ....... ......... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . [lillllllllilllllll Il. .. . . . . . . . . .

-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 22 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA 4 & 5 on SCS ONA ONA ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 24 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 Ž Keff> 0.96 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 > Keff> 0.95 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 26 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 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 50.95 I OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months ONA 6 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 27 of 27

ML13108A176

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