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)
	v • d • e

Technical Specification 5.6.5.d Saps Palo Verde Nuclear Generating Station 102-06686-TNW/RKR 5801 S. Wintersburg Road April 11, 2013 Tonopah, AZ 85354 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element assembly (CEA) insertion limits versus thermal power Corrected the x-axis scale labeling to replace the fully withdrawn (FW) notation with 150 and clarified the description of fully withdrawn Added references to the Analytical Methods reference table and updated the heading information for the reference section Editorial reformatting of Unit 2 and 3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 J. K. Rankin M. A. Brown NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS 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 Effective March 29, 2013 I

Responsible Engineer TDigitally signed by Trimble, Trim ble, Patrick C(Z95337)

Date DN: cn=Trlmble, Patrick Patrick cz95337)

PatrickReason: I am the author of this document C(Z95337)

Date: 2013:03.27 12:08:53

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

Date ON: cn=Bodnar, Walter W

te Reason: I have reviewed this document 5(Z06432)

Date: 2013.03.27 12:18:40 S(Z06432)-07 '00' Digitally signed by Ashton, Responsible Section Leader Ash ton, Jeffrey sz03403)

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

Jeffrey cz003 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 Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Page 12 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes 1 and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)

CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)

Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)

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

Operable)

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

I 13 14 15 16 17 18 19 I 20 21 22 Page 3 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Table 3.3.12-4 Table 3.3.12-5 Page 23 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 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 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 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 I

24 25 26 27 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:

T.S ReS Title Report No.

Rev Date Re f#a SU P-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.

I Page 6 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 T.S ReS Title Report No.

Rev Date Re f#a

- _M 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.

April 10, N.A.

10 Scherer (CE), ("Acceptance for 1990 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 Title Report No.

Rev Date Supp Re ffa 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) 19 Loss of Flow, C-E Methods for Loss of CENPD-0 June N.A.

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

6 5

s I m 9 m m r R m m m m 9 -F T T 1 9 --.m F.....................

z 0

Ell 4

3 REGION OF ACCEPTABLE OPERATION i...........

i

.....(500,5.0)

REGIONOF UNACCEPTABLE

6 N OPERATION 50,i.0) 2 0

I.

(3~

0 100 200 300 400 COLD LEG TEMPERATURE (*F) 500 600 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 7

6 5

z 0

4 3

S.(500,6.5):

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

REGION OF ACCEPTABLI9

.-....... O P E R A T IO N..

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

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

(350,4.0) 7...........

REGION OF UNACCEPTABLE OPERATION

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

....................... ]..................

f I.

I.

2 0

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

I l l l l l l l l l l...................

0 100 200 300 400 COLD LEG TEMPERATURE (F) 500 600 Page 13 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 Revision 22 0.5 0.0

-0.5 0

U rJ-0 0

F-,

02 0-

-1.0

-1.5

-2.0

-2.5

-3.0

.~~~~~~~~

~ ~ ~........

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

((05

%09.0

.............. M T C A R E A O F...................................

ACCEPTABLE OPERATION (100%,-4.4

-3.5

-4.0

-A r

. I I...

I,,

, I...

I...

I..

. I,,

u m,,

,,=r j 0

10 20 30 40 50 60 70 CORE POWER LEVEL

(% OF RATED THERMAL POWER) 80 90 100 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

>80% RTP 15 151

[-,-, 1 5................................

0 u

12

12. *80% to

>70% RTP 10

.10 CO C4r.

1 0

" 1 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) 0 0

1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 I

I

=

INOTE:

w aSee Footnote in Section 3.1.7 for applicability i

following a Reactor Power Cutback.

J ~o meet the Transient Insertion Limit (TIL) all a! conditions below must be met:

°

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

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

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

-C AND CEA Group 4 must be > fully withdrawn* for o

power levels > 70.87%.

CEA Group 4 must be withdrawn > the 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%).

AND z

CEA Group 5 must be withdrawn > the group 5 TIL (TIL5) as indicated on the graph or

'f,

by the equation:

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

oz*

O.

z L.

... - -................ i J........

i 0

GROUP5 I

I I

GROUP3 I

I I

GROUP 1 I

I I

I 150*120 90 60 30 0

150*120 90 60 30 0

GROUP 4 GROUP 2 E* A 9P0 60 3O0

(

INH tW 90 t N

30 CEA POSITION (INCHES WITHDRAWN)

I 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 0

0z0 P-0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0

-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

-conditions below must be met:

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

AND CEA Group 3 must be > fully withdrawn* for

...... power levels > 20%.

CEA Group 3 must be withdrawn > 60" for Z

power > 0% and < 20%.

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

E CEA Group 4 must be withdrawn > the "w-.

group 4 TIL (TIL4) as indicated on the graph or

.rd by the equation:

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

.A N

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

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%).

.0 A

i........ A.......

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

9 Uz I..

GROUP5 I

I I

I I I

GROUP3 GROUPI I

I I

I 150" 120 90 60 30 0

150" 120 90 60 30 0

150" 120 90 60 30 GROUP 4 GROUP 2

ý"A0 P

T0 6

(0 30 6

1W T W190 60 0

CEA POSITION (INCHES WITHDRAWN) 0 I

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 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER Revision 22 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0

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

RA N SI N I

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

0

-......... OPERA-T-ION............

O. PERA-TION.........................

UJNACCEPTABLE RESTRICTED

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

...................................... *............. i..........................

..I..

-. O P E R A T I O N ------..

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

i.....

LONG TERM STEADY STATE INSERTION::LIMITS: (112.5 INCHES)

OPERATION ACCEPTABLE

.......................... J

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

, l,

,, i i

iI I

I

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

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL PC (COLSS IN SERVICE)

Revision 22

)WER 20.0 15.0 I

I I

F-

,J.,

0

.... R E G IO N -O F................................................

UNACCEPTABLE OPERATION 10.0 5.0 REGION OF. LCCEPTABLE I

OPERATION 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 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL Revision 22 25 20 z0 0

0 0

C,,

0u 15 10 (95,20)

(805) 5 0

50 60 70 80 CORE POWER LEVEL

(% OF RATED THERMAL POWER) 90 100 Page 20 of 27

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 22 2.5 2.4 2.3 u

cl FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)

I

. I........

I I.

.I.

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

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

(-0.1,2.28)

ACCEPTABLE OPERATION

POWER AT OR ABOVE 90%

AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC" CHANNEL..............................

(0.05,2.00) 0.,

.0 0

(011.93)

UNACCEPTABLE O P E R A T IO N.....................................

I..

.I.

2.2 2.1 2.0 1.9 1.8

-0.:20

-0.15

-0.10

-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 3.5 3.4 z

u I

(-o.

3.3 I...

. I.

.. I.

ACCEPTABLE IOPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL.....

,3.27)

UNACCEPTABLE OPERATION I

I.......

I:

7 (0.1,3.41).:

3.2 3.1 3.0 '

-0.2

. I.....

llllllllllllllllllll 20

-0.15

-0.10

-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 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 I

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 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 hour 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 I

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 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 hour 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 hour 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 hour 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 hour ONA ONA Notes:

SCS = Shutdown Cooling System ONA = Operation Not Allowed I

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 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 hours 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 I

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 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 hours 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour 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 hours 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 hours 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 hours 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 I

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 Effective March 29, 2013 I

Lb EDigitally signed by Trimble, Responsible Engineer Trim ble, Patrick C(Z95337)

Date DN: cn=Trimble, Patrick Patrickc(z95337, PatrickReason: I am the author of

, this document C(Z95337)

Date: 2013.03.27 12:09:31

/

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

Date DN: cn=Bodnar, Walter W al r

IReason: I thave reviewed this document S(Z06432)

Date: 2013.03.27 12:22:14

-07'00' Responsible Section Leader As

Dton, eDigitally signed by Ashton, Date DN: cn=Ashton, Jeffrey C(Z034103)

Jeffrey dcumento*

Reason: I am approving this document.

C(Z03403) Date: 2013 'o0.27 12:48:57

-07'00' 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 Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Page 12 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes 1 and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)

CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)

Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)

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

Operable)

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

I 13 14 15 16 17 18 19 I 20 21 22 Page 3 of 27

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 18 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Table 3.3.12-4 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> 0.98 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 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 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 Page 23 24 25 26 27 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:

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 (1 3-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.

I Page 6 of 27

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

Rev Date Sup RefW 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.

April 10, N.A.

10 Scherer (CE), ("Acceptance for 1990 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.

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 (N001 -1301-01202)

Page 7 of 27

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

Rev Date Supp RefW 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, (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 withdrawnl 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 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

-0.18 8*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 5

z 0

<0 4

(5 0 0,5.0 ~

REGION OF ACCEPTABLE OPERATION REGION OF UNACCEPTABLE OPERATION (350,1.0)

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

3 2

0 0

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

RG O O F Ii

/

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

-0.5 Z

0t 0

U 0

0 1-0

-1.0

-1.5

-2.0

-2.5

-3.0

-3.5

-4.0 (100%,02.

......................... m........................................................................

( 1 0 0 %,-0.2

-M T C A R E A O F.....................

ACCEPTABLE OPERATION 4...

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

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

-4.5 0

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

(% 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 Re FIGURE 3.1.5-1 CORE POWER REDUCTION AFTER CEA DEVIATION&o vision 18 Iv z

u-0 0LI 10 16 100% to

>80% RTP 12

12. *80% to

>70% RTP 9

8 8

70% to

>45% RTP

/

-45%

T I.

15 10 5

5 0

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 0.9 0.8 0

z 0

U LT.,

0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 See Footno following a F To meet the conditions bi CEA Grc withdrawn and MODE CEA Grl power ]eve CEA Grc power> 0(

W CEA Grc 2!

powerleve 0

F--

CEAGrc group 4 T I by the equ

.Z TIL4=(17 I *"

F (for power U

CEA Grc group 5 TI o C by theequ TIL5 = (17

=

(for power

06. :0o I

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

NOTE:

te in Section 3.1.7 for applicability teactor Power Cutback.

Transient Insertion Limit (TIL) all elow must be met:

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

AND up 3 must be > fully withdrawn* for Is > 20%.

3up 3 must be withdrawn > 60" for

% and < 20%.

AND

)up 4 must be > fully withdrawn* for Is > 70.87%.

up 4 must be withdrawn > the L (TIL4) as indicated on the graph or ation:

2.5" x Fractional Power) + 25.5"

> 20% and < 70.87%).

AND up 5 must be withdrawn > the L (TIL5) as indicated on the graph or ation:

2.5" x Fractional Power) - 64.5" s_> 37.39% and < 100%).

4

,,d 4

4 U

FF1 GROUP 5 I

I I

I GROUP 3 I

I I

GROUP 1 I

I I

150*120 90 60 30 0

GROUP 4 GROUP 2 1

E0*10 OI TIO 3No IN

1E020 WI90 W60 130N)

CEA POSITION (INCHES WITHDRAWN)

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 2 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9 0.8 0.7 Lu 0

F-0z U

LT.

0.6 0.5 0.4 0.3 NOTE:

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

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

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

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

CEA Group 3 must be withdrawn > 60" for Z

power > 0% and < 20%.

AND CEA Group 4 must be > fully withdrawn' for z

power levels > 54.97%.

CEA Group 4 must be withdrawn > the group 4 TIL (TIL4) as indicated on the graph or by the equation:

4 TIL4 = (250.9" x Fractional Power) + 9.82" (for power > 20% and < 54.97%).

i............ !........-----

AND

,=

CEA Group 5 must be withdrawn > the

.4 group 5 TIL (TIL5) as indicated on the graph or by the equations:

4 0.....

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

I

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

z 0.2 0.1 0.0 GROUP5 i

I I

I i

I GROUP3 I

I I

I GROUP I I

I I

I 150* 120 90 60 30 0

150* 120 90 60 30 0

GROUP4 GROUP2 l0*

A0 9P0 6+0 31o t H A90 N60 130 CEA POSITION (INCHES WITHDRAWN)

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 2 CORE OPERATING LIMITS REPORT Revision 18 u

0 C

u 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0 1.I FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER

TRASIET' NSETION, LIMITi (75.~INCHES)

...........P E R A T.

O..........................

OE T.

UNACCEPTABLE:

I ESTRICE

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

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

LONG TERM STEAY STATE INSERTION SELIMITS (112.5 INCHES)

I

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

UN ERTINACCEPTABLE jET:CE LON TER STAD STT ISR IOU IS(1251.NH

. i.

i..

. i.

I 0

0.9 0.8 0.7 0.6 0.5 0.4 0.3 FRACTION OF RATED THERMAL POWER 0.2 0.1 0.0 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 15.0 I

I I

I 0H/.

10.0 REGI(

I

.s R...

... R E G IO N.O F.......-.....................................

UNACCEPTABLE OPERATION 5.0 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 z0 Z<L 0LI z

C-)

25 20 15 10 5

0 50 60 70 80 CORE POWER LEVEL

(% OF RATED THERMAL POWER) 90 100 Page 20 of 27

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

Revision 18 2.5 2.4 2.3 z

C..

2.2 2.1

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

ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (0(01228)

(.,238:

==......

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

ACCEPTABLE OPERATION POWER AT OR ABOVE 90%

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

(0.0.5,2.00) u!

(.,

.0 0

(01,1.93)

UNACCEPTABLE S.................................... O P E R A T IO N...................

,,LJ LL L LL L.

.L.

L. L.....

!.1 J........

I L.........

L..

I I..

2.0 1.9 1.8

-_).20

-0.15

-0.10

-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 3.5 3.4 z

3.3

(-o.1 ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE i......

O P ER.B...

IN ANY OPERABLE CPC CHANNEL

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

ii............

,3.27)

UNACCEPTABLE OPERATION l.........

I.........

I

.... I......

(0.1,3.41)::

., °.... l,.

li 3.2 3.1

,In I I

I

... I....

I...

I..... I...

-0.20

-0.15

-0.10

-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 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 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 I

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 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 hour 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 I

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 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 hour 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 hour 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 hour 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 hour ONA ONA Notes:

SCS = Shutdown Cooling System ONA = Operation Not Allowed I

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 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 hours 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 I

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 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 hours 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour 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 hours 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 hours 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 hours 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 I

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 Digitally signed by Trimble, Responsible Engineer Tri be, Patrickz33 Date DN: cn=Trimble, Patrick Patrick Reason: I am the author of this document C(Z95337)

Date: 2013.03.27 12:10:07 QZ95337

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

DN: cn=Bodnar, Walter W

alter S(Z06432)

W alterReason: I have reviewed this document S(Z06432)

Date: 201 3.03.27 12:24:40

-07'00' A

h n

Digitally signed by Ashton, Jeffrey C(Z03403)

DN: cn=Ashton, Jeffrey C(Z03403) ey Reason: lam approving this document C(Z03403) Date: 2013.03.27 12:51:01 QZ03403-07'00' Responsible Section Leader Date 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 Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Page 12 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes 1 and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)

CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)

Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)

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

Operable)

DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel) 13 14 15 16 17 18 19 20 21 22 Page 3 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 21 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Table 3.3.12-4 Table 3.3.12-5 Page 23 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 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 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 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 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95 I

24 25 26 27 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. S ReS Title Report No.

Rev Date Supp Re f#a 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. S ReS Title Report No.

Rev Date Re f#a sP-1 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.

April 10, N.A.

10 Scherer (CE), ("Acceptance for 1990 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.

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 (NOO -1301-01202)

Page 7 of 27

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

Rev Date Supp Re fW 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, (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) 19 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 (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 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 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 r :

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

(

....5 0 0,5.o0

.REGION OF(50)

ACCEPTABLE OPERATION i

........................S A ;, A L z..

z 0 3 REGION OF UNACCEPTABLE OPERATION (350,1.0) 0 1.........

......... 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

6 5

REGION OF ACCEPTABLE OPERATION Z

z 0

4 3

2 0

.I (500,6.5)::

(350,4.0)

REGION OF UNACCEPTABLE OPERATION llllllllllllllI 0

100 200 300 400 COLD LEG TEMPERATURE (TF) 500 600 Page 13 of 27

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 Revision 21 0.5 0.0

-0.5 0

0 0

-1.0

-1.5

-2.0

-2.5

.( o%

,o 5*

(5o0%, 0.o) i

............................................. ( j.Q Q 0o,7-o 2)

....... M T C -A R E A O F -........................................

ACCEPTABLE

-OPERATION.

(100%,-4.41

(0%,-4.4)

-3.0

-3.5

-4.0

-4.5

-..I

-I..

I m

,I I.

I.-.

0 10 20 30 40 50 60 70 80 90 1

CORE POWER LEVEL

(% OF RATED THERMAL POWER) 00 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 z0r- -

u 04 0

0 rD 0

z 2

10 16

-100% to

>80% RTP 12

12. *580% to

>70% RTP 9

8.

8 70% to

>45% RTP

// *:

'_45%

RTP"

..I.....

.ll..

lllllll

.l 15 10 5

5 0

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 0.9 0.8 0.7 0.6 0

0~

1-0~

P U

0.5 0

F-,

o q 22 C F-<

NOTE:

See Footnote in Section 3.1.7 for applicability

'following a Reactor Power Cutback.

,To meet the Transient Insertion Limit (TIL) all

'conditions below must be met:

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

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

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

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

CEA Group 4 must be withdrawn > the group 4 TIL (TIL4) as indicated on the graph or by the equation:

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

AND CEA Group 5 must be withdrawn > the group 5 TIL (TILS) as indicated on the graph or by the equation:

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

0.4 0.3 0.2 0.1 0.0 U

__t__

__I__

1 I

1 1

GROUP5 GROUP3 I

I I

GROUP I I

I I

i 150" 120 90 60 30 0

150" 120 90 60 30 0

GROUP4 GROUP2 1

EP1I0 9

T0 6N0 3I0 N 1J0 120 W

I90 W60 130 CEA POSITION (INCHES WITHDRAWN)

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 3 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 1.0 0.9 0.8 L.J U

z 0

u 0.7 0.6 0.5 0.4 0.3 0.2 0.1 0.0 See Footno

following a

.........................................'T o m ee t the

conditions b CEA Gr withdrawr and MOD CEA Gr power lev CEA G Z

power_> 0 GEA Gr i

power lev CEA Gr group 4 T by the eq

L -

TIL4=(

(for power:

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

U;! W t:;

CEAGr i

group5T

.by the eq TIL5

(

S-(for power 0: =COO TIL5=1 i

I I

I NOTE:

te in Section 3.1.7 for applicability Reactor Power Cutback.

Transient Insertion Limit (TIL) all

)elow must be met:

oups 1 and 2 must be > fully

" (see definition below) in MODE 1 E 2.

A.N!D oup 3 must be > fully withdrawn* for els > 20%.

roup 3 must be withdrawn > 60" for

)% and < 20%.

AND oup 4 must be >_ fully withdrawn* for els > 54.97%.

oup 4 must be withdrawn > the IL (TIL4) as indicated on the graph or uation:

250.9" x Fractional Power) + 9.82"

> 20% and < 54.97%).

AND oup 5 must be withdrawn > the IL (TIL5) as indicated on the graph or uations:

250.9" x Fractional Power) - 80.18" r > 31.96% and < 75.00%).

08" (for power level >. 75.00%).

v U

0 GROUP5 I

I I

GROUP 3 I

I I

I GROUP I I

I I

I 150*120 90 60 30 0

150*120 90 60 30 0

GROUP4 GROUP2 CEA"10 9PI0 3T 0

IN 1 120 190 W60 D30 CEA POSITION (INCHES WITHDRAWN)

I 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 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER Revision 21 I-v z

u z

0r-2 0

C.)

u z

I-.

0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0

.............IE...........................N T IN SE.T..N L M.............I......

I

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

E t.......................................................

O A............

O P E R A. T IO N........................

NACCEPTABLE RESTRICTED I

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

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

LONG TERM STEADY STAE NSERTNI ISION LIMIT

(

12.5 INCHES OPERATION ACCEPPTARSL LON TER STAYSAEISR IO U IS(125NCE

....*.... i....

I 1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3 0.2 0.1 FRACTION OF RATED THERMAL POWER 0.0 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 15.0 lmmm E-0H, 10.0 REGION i

I.

................. R E G IO N -O F................................-...............

UNACCEPTABLE OPERATION 5.0 0.0 20 OF~ýCCEPTABLE OPERA I

I I,

TION S.1i.

.0 llqlilllllllll 30.0 40.0 50.0 60.0 70.0 CORE POWER LEVEL

(% OF RATED THERMAL POWER) 80.0 90.0 100.0 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) 2 0.5 02 C ) 1 5...............

z C-)

151 0...

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'.

(0.0.,2.00)

.0

.............................. i.................. ~ : : :.................

(011.93) UNACCEPTABLE

1......................

O P 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 3.5 3.4

. m l....................~...........1...........l 04 co z

u 3.3 ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CVC CHANNEL

(-0.1*,3.27)

UNACCEPTABLE OPERATION I

I (0.1,3.41)::

3.2 3.1 12A I

[lillllllllilllllll I

l.

-0.20

-0.15

-0.10

-0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 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 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 I

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 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 hour 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 I

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 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 hour 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 hour 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 hour 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 hour ONA ONA Notes:

SCS = Shutdown Cooling System ONA = Operation Not Allowed I

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 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 hours 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 I

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 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 hours 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1 hour 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 hours 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 hours 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 hours 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 I

Page 27 of 27

ML13108A176

Text

Dear Sirs:

Subject:

Enclosures:

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