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Scott A. Bauer Technical Specification 5.6.5.d Department Leader Regulatory Affairs Tel: 623/393-5978 Mail Station 7636 Palo Verde Nuclear Fax: 623/393-5442 P.O. Box 52034 Generating Station e-mail: [email protected] Phoenix, AZ 85072-2034 102-04673-SAB/TNW/GAM March 19, 2002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001 Dear Sirs: Subject: Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50-5281529/530 Core Operating Limits Reports: Unit 1 - Revision 6; Unit 2 - Revision 5; and Unit 3 - Revision 8 Pursuant to PVNGS Technical Specification 5.6.5.d, enclosed are the following revised Core Operating Limits Reports (COLRs) for PVNGS: Unit 1 - Revision 6; Unit 2 - Revision 5; and Unit 3 - Revision 8. These COLR revisions were implemented on March 15, 2002. The changes implemented by these COLR revisions consist of adding clarifying information to section 3.1.7 to define conditions under which the CEA overlap may be modified from the nominal values specified in Figures 3.1.7-1 and 3.1.7-2. No commitments are being made to the NRC by this letter. Please contact Thomas N. Weber at (623) 393-5764 if you have any questions or require additional information. Sincerely, SABITNW/GAM/kg ý4 (:ac"C Enclosure cc: E. W. Merschoff all w/o enclosure J. N. Donohew J. M. Moorman A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway * Comanche Peak * Diablo Canyon * Palo Verde e South Texas Project * Wolf Creek
Transcript
Page 1: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Scott A. Bauer Technical Specification 5.6.5.d Department Leader Regulatory Affairs Tel: 623/393-5978 Mail Station 7636

Palo Verde Nuclear Fax: 623/393-5442 P.O. Box 52034

Generating Station e-mail: [email protected] Phoenix, AZ 85072-2034

102-04673-SAB/TNW/GAM March 19, 2002

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

Dear Sirs:

Subject: Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3 Docket Nos. STN 50-5281529/530 Core Operating Limits Reports: Unit 1 - Revision 6; Unit 2 - Revision 5; and Unit 3 - Revision 8

Pursuant to PVNGS Technical Specification 5.6.5.d, enclosed are the following revised

Core Operating Limits Reports (COLRs) for PVNGS:

Unit 1 - Revision 6; Unit 2 - Revision 5; and Unit 3 - Revision 8.

These COLR revisions were implemented on March 15, 2002. The changes

implemented by these COLR revisions consist of adding clarifying information to section

3.1.7 to define conditions under which the CEA overlap may be modified from the

nominal values specified in Figures 3.1.7-1 and 3.1.7-2.

No commitments are being made to the NRC by this letter.

Please contact Thomas N. Weber at (623) 393-5764 if you have any questions or

require additional information.

Sincerely,

SABITNW/GAM/kg ý4 (:ac"C

Enclosure

cc: E. W. Merschoff all w/o enclosure J. N. Donohew J. M. Moorman

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance

Callaway * Comanche Peak * Diablo Canyon * Palo Verde e South Texas Project * Wolf Creek

Page 2: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Enclosure

Core Operating Limits Reports for

Palo Verde Nuclear Generating Station

Unit 1 - Revision 6;

Unit 2 - Revision 5; and

Unit 3 - Revision 8

Page 3: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Revision 6

PVNGS UNIT I CORE OPERATING LIMITS REPORT

CORE OPERATING LIMITS REPORT

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 1

Revision 6

Page 1 of 26

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Revision 6PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

Table of Contents

Description

Cover Page

Table of Contents

List of Figures

List of Tables

Affected Technical Specifications

Analytical Methods

CORE Operating Limits

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 Length 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 2 of 26

Revision #

6

6

5

5

5

5

6

6

6

6

6

6

6

6

6

6

6 6

2

4

5

6

8

8

8 8

8

9

9

9

9

10

10

10

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Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

List of Figures

Description

Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open

Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed

Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2

Figure 3.1.5-1 Core Power Limit After CEA Deviation

Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power (COLSS in Service)

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

Figure 3.1.8-1 Part Length CEA Insertion Limits Versus Thermal Power

Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)

Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable

Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEACs Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEACs Inoperable)

Page 3 of 26

Revision #

5

5

5

5

5

5

5

5

5

5

5

Page

11

12

13

14

15

16

17

18

19

20

21

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Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

List of Tables

Description Revision # Page

Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 5 22 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98

Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 5 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97

Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 5 24 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff > 0.96

Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 5 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff> 0.95

Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 5 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95

Page 4 of 26

Page 7: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde Unit 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 Length CEA Insertion Limits

3.2.1 Linear Heat Rate (LHR)

3.2.3 Azimuthal Power Tilt (Tq)

3.2.4 Departure From Nucleate Boiling Ratio (DNBR)

3.2.5 Axial Shape Index (ASI)

3.3.12 Boron Dilution Alarm System (BDAS)

3.9.1 Boron Concentration

Page 5 of 26

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Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

ANALYTICAL METHODS

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

Title

1) CE Method for Control Element Assembly Ejection Analysis

2) The ROCS and DIT Computer Codes for Nuclear Design

3) Modified Statistical Combination of Uncertainties

4) System 8 0 TM Inlet Flow Distribution

5) Calculative Methods for the CE Large Break LOCA Evaluation

Model for the Analysis of CE and W Designed NSSS

6) Calculative Methods for the CE Small Break LOCA Evaluation

Model

7) Fuel Rod Maximum Allowable Pressure

8) Arizona Public Service Company PWR Reactor Physics Meth

odology Using CASMO-4/ SIMULATE-3

Report No.

CENPD0190-A

CENPD266-P-A

CEN356(V)-P-A

Enclosure 1-P to LD

82-054

CENPD132

CENPD137-P

CEN-372P-A

NFM002

Rev Date

N.A. January 1976

N.A. April 1983

01-P-A May 1988

N.A. February 1993

N.A. June 1985

N.A. January 1977

N.A. May 1990

0 September 1999

Supplement

N.A.

N.A.

N.A.

1-P

3-P-A

1-P

N.A.

N.A.

Page 6 of 26

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Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

Title

9) Technical Manual for the CENTS Code

Report No.

CE-NPD 282-P-A Vols. 1-3

Rev

N.A.

Date

June 1993

Supplement

1-P

Page 7 of 26

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Revision 6 PNGS UNIT I CORE OPERATING LIMITS REPORT

The cycle-specific operating limits for the specifications listed are presented below.

3.1.1 - Shutdown Margin (SDM) - Reactor Trip Breakers Open

The Shutdown Margin shall be greater than or equal to that shown in Figure 3. 1. 11.

3.1.2 - Shutdown Margin (SDM) - Reactor Trip Breakers Closed

The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.21.

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-length or part-length CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES I and 2 core power reduction is specified in Figure 3.1.5-1.

3.1.7 - Regulating CEA Insertion Limits

One or more CEACs OPERABLE: With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1

shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulation CEA groups shall be limited to the withdrawal sequence and to the insertion limits' shown in Figure 3.1.7-22.

A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1. 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours.

2The separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:

Page 8 of 26

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Revision 6

PVNGS UNIT I CORE OPERATING LIMITS REPORT

a) Regulating Group 4 position is between 60 and 150 inches withdrawn.

b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.

c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service)

3.1.8 - Part Length CEA Insertion Limits

One or more CEACs OPERABLE: The part length 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 (.T1()

The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to the limit in Figure 3.2.3-1 with COLSS IN SERVICE.

3.2.4 - Departure From Nucleate Boiling Ratio (DNBR)

COLSS IN SERVICE and Both CEACs INOPERABLE - Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.

COLSS OUT OF SERVICE and Either One or Both CEACs are OPERABLE Operating within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.

COLSS OUT OF SERVICE and CEACs INOPERABLE - Operating within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel.

Page 9 of 26

Page 12: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Revision 6

PVNGS UNIT I CORE OPERATING LIMITS REPORT

32.5 -. Axial Shape Index (ASI)

The core average AXIAL SHAPE INDEX (AST) shall be maintained ývithin the following limits:

COLSS OPERABLE -0.18 < ASI • 0.16 for power > 50% -0.28 < ASI < 0.16 for power < 50%

COLSS OUT OF SERVICE (CPC) -0. 10!< ASI< 0. 10

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 10 of 26

Page 13: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT I CORE OPERATING LIMITS REPORT

FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE

REACTOR TRIP BREAKERS OPENI.

.. .... . . . . . .... . . . . . . . . . . . . . . .

REGION OF

ACCEPTABLE

OPERATION

S. . .. . . . . . . . .. .

100 200

7

6

5

-- 4 z

z

(d

(350, t..o)

S. . .. . . -

300 400 500

COLD LEG TEMPERATURE ('F)

Page 11 of 26

...... -.............. ........ ý500,5 .0).

REGION OF

* . UNACCEPTABLE ------ N .......... ............ ...... .... SOPERATI ON

0

0 600

.................. .........

Revision 5

...........................

........ ......

............. .............................

........ ..... .....................................

Page 14: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

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Page 15: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 5

FIGURE 3.1.4-1

MTC ACCEPTABLE OPERATION, MODES 1 AND 20.5

-- -- --- -- ,, t . . . . . . .. n . . . . i. . .. . ...... . . . !. . . .-- -- -- -- -0 0%0 ........ '3' " ,,, ......... ---------

0.0 (50%0.0) ......

(100%,-0.2 -0 .5 ... ... ... ... ... .... ... .. ... ... ... ... .... ... ... ... ... ... ............................... ... .. ... .. .. ... .... ... .. ..

-0 .5 . . . . . . . . . . . . . ............... . ------.. . . . . . . .

.......... ............. ............ A R E A -O F - ------------...............

ACCEPTABLE

-2.0 - - - .O PER A T IO N ................ . . . . . .

-2.5 - .

-.3 .0 . . . . . . .............. ............ .......... . . ......... ........... . ......... .......-- ---.... ........... ..... ..... ...... ..... .....

(0%,-3..4)

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

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

0 10 20 30 40 50 60 70 80 90 100

CORE POWER LEVEL (% OF RATED THERMAL POWER)

End of Cycle Limit Beginning of Cycle Limit

TECH SPEC 3.1.4 Maximum Upper Limit

Page 13 of 26

o

7

I

0

0 cr•i

0

-4.0

-45

Page 16: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision 5

FIGURE 3.1.5-1

CORE POWER LIMIT AFTER CEA DEVIATION* 30 ..........

2 5 . ....................... ...................... ......................... ......................... ... ................... --. ........... .......

z O .(60 MIN, 20.0%)

- 20

1 5............".""".-.... ............ " ......" .... ..... . ............

z

0 M

0 10 20 30 40 50 60

TIME AFTER DEVIATION, MINUTES

* WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL

POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.

Page 14 of 26

Page 17: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

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Page 18: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

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Page 19: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT I CORE OPERATING LIMITS REPORT

FIGURE 3.1.8-1 PART LENGTH CEA INSERTION LIMITS

VERSUS THERMAL POWER0.0

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

------------ ............. *. . ........... -------... .. .. .

S. .. .. ... i ... .... .. .... .. . . ..... .. . -------.. ... ...

.. .... .... ...... .. .........N ... .... ... ... .. .

•UNACCEPTABLE

.. .. . .............. .............. .....................

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

TRNSI ý.NT INSERTION LI.MVIT (.75,0 !INCHES

z u

z

0

0 u

z

w

H

0D

1.0 0.9 0.8 0.7 0.6 0.5 0.4 0.3

FRACTION OF RATED THERMAL POWER

Page 17 of 26

*1

C

_.-0

&v

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

O.........C PB..........................................LE...... ....................... .................. - -... . . i . .... i . . . .n.. . . . . . . .. ... ...... . . . . . . . . .......

0.2 0.1 0.0

I I 1

an no -on NOW .:.. .. no Wi ........... no,iniuii•i•ni•i•n• •| ||inmmmmmmml

........... OPERA-TION ------

RESTRICTED S. . . .. . . . . . . . . . . .... . . . ... . . ._ _ ... . . ..-- - - -

I . . . . I . A - . . I .• • oI

Revision 5

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PVNGS UNIT I CORE OPERATING LIMITS REPORT

FIGURE 3.2.3-1

AZIMUTHAL POWER TILT VERSUS THERMAL POWER

(COLSS IN SERVICE)

5.0

0.00.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0

CORE POWER LEVEL (% OF RATED THERMAL POWER)

Page 18 of 26

20.0

15.0

10.00

N

REGION OF

UNACCEPTABLE

OPERATION

REGION OF ACCEPTABLE OPERATION

Revision 5

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PVNGS UNIT I CORE OPERATING LIMITS REPORT

FIGURE 3.2.4-1

COLSS DNBR OPERATING LIMIT

ALLOWANCE FOR BOTH CEAC's INOPERABLE

10025 50 75

CORE POWER LEVEL (% OF RATED THERMAL POWER)

Page 19 of 26

25

z 0

Z

C-)

z

(2:. C)

0 u)

20

15

10

5

00

Revision 5

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PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 5

FIGURE 3.2.4-2

DNBR MARGIN OPERATING LIMIT BASED ON

THE CORE PROTECTION CALCULATORS

(COLSS OUT OF SERVICE, CEAC's OPERABLE).. , .. . o. i. I .. . .. . . I .. .. ...I ...t . ... ..| |

ACCEPTABLE OPERATION

ANY POWER LEVEL

MINIMUM OF 1 CEAC OPERABLE

S................ --........ ........ ................. .... ..... ....

!(.3 .3

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

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

(-0.1,2.24)

2.5

2.4

2.3

ACCEPTABLE OPERATION

* POWER AT OR ABOVE 90% a a * MINIMUM OF 1 CEAC OPERABLE

, : (0.05:2.03) Ii

(-0.1,1.96(0N0CCE 2TABL

OPERTION ........

, .......... 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 20 of 26

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

(0.1,2.33)

| . . . . . . . . .--- ---- ---

z;

2;

u) a)

2.2

2.1

2.0

1.9

1.8 I- - - -. . . .. . . . . . . . . . - - - -. . . . . . . . . . . . . . . . . . . . . ..- -l l l l I i i

!

Page 23: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT I CORE OPERATING LIMITS REPORT Revision 5

FIGURE 3.2.4-3

DNBR MARGIN OPERATING LIMIT BASED ON

THE CORE PROTECTION CALCULATORS

(COLSS OUT OF SERVICE, CEAC's INOPERABLE)rn,,r

ACCEPTABLE OPERATION

ANY POWER LEVEL

CEAC's INOPERABLE

3.6

3.5

3.4

0.10 0.15 0.20-0.15 -0.10 -0.05 0.00 0.05

CORE AVERAGE ASI

Page 21 of 26

z

z

u) 0.4

3.3

3.2

3.1

203.0 -0.

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

-- -- -----

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

I I |

IIIll•l

((0.1,3.32)

"" "". .....i " '." i i.l.......... .........ii ~( 1 .1" 1 .'13 .111.12.).". ii ii. i i ....................

1,3.19)

UNACCEPTABLE

OPERATION

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

.. .. . . .. . .. .. I I I . . ..I 1 4 1 1

Il l l l • l l l l l l l . . . .. . . . . . . .. .. -- . .. .. . . . . . . .. . .IlTIlIll

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

Page 24: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

Table 3.3.12-1

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 0.5 hours ONA ONA

4 not on SCS 12 hours 0.5 hours ONA ONA

5 not on SCS 8 hours 0.5 hours ONA ONA

4 & 5 on SCS ONA ONA ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 22 of 26

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Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

Table 3.3.12-2

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 > Keff > 0.9 7

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 1 hour 0.5 hours ONA

4 not on SCS 12 hours 1.5 hours 0.5 hours ONA

5 not on SCS 8 hours 1.5 hours 0.5 hours ONA

4 & 5 on SCS 8 hours 0.5 hours ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 23 of 26

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Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

Table 3.3.12-3

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 > Keff> 0.96

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 2.5 hours 1 hour ONA

4 not on SCS 12 hours 2.5 hours 1 hour 0.5 hours

5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours

4 & 5 on SCS 8 hours 1 hour ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 24 of 26

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Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

Table 3.3.12-4

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 > Keff> 0.95

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 3 hours 1 hour 0.5 hours

4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours

5 not on SCS 8 hours 3.5 hours 1.5 hours 0.75 hours

4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 25 of 26

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Revision 5

PVNGS UNIT 1 CORE OPERATING LIMITS REPORT

Table 3.3.12-5

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff _< 0.95

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 4 hours 1.5 hours 1 hour

4 not on SCS 12 hours 4.5 hours 2 hours 1 hour

5 not on SCS 8 hours 4.5 hours 2 hours 1 hour

4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA

6 24 hours 1.5 hours ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 26 of 26

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Revision 5

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

CORE OPERATING LIMITS REPORT

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 2

Revision 5

Page 1 of 26

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Revision 5

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

Table of Contents

Description

Cover Page

Table of Contents

List of Figures

List of Tables

Affected Technical Specifications

Analytical Methods

CORE Operating Limits

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 Length 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 2 of 26

Revision #

5

5

4

4

4

4

5

5

5

5

5

5

5

5

5 5

Pagae

1 2

4

5

6

8

8 8

8

8

9

9 9

9

10

10

t0

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

List of Figures

Description

Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open

Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed

Figure 3.1.4-1 MTC Acceptable Operation, Modes I and 2

Figure 3.1.5-1 Core Power Limit After CEA Deviation

Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power (COLSS in Service)

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

Figure 3.1.8-1 Part Length CEA Insertion Limits Versus Thermal Power

Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)

Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable

Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEACs Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEACs Inoperable)

Page 3 of 26

Revision #

4

4

4

4

4

4

4

4

4

4

4

121

13

14

15

16

17

18

19

20

21

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

List of Tables

Description Revision # PaUe

Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 4 22 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98

Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 4 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff> 0.97

Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 4 24 Dilution Detection as ' 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 4 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff> 0.95

Table 3 3.12-5 Required Monitoring Frequencies for Backup Boron 4 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff< 0.95

Page 4 of 26

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde Unit 2 Technical Specifications.

AFFECTED PVNGS TECHNICAL SPECIFICATIONS

3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open

3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed

3.1.4 Moderator Temperature Coefficient (MTC)

3.1.5 Control Element Assembly (CEA) Alignment

3.1.7 Regulating CEA Insertion Limits

3.1.8 Part Length 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 (ASD

3.3.12 Boron Dilution Alarm System (BDAS)

3.9.1 Boron Concentration

Page 5 of 26

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

ANALYTICAL METHODS

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

Supplement

1) CE Method for Control Element Assembly Ejection Analysis

.2) The ROCS and DIT Computer Codes for Nuclear Design

3) Modified Statistical Combination of Uncertainties

4) System 8 0 TM Inlet Flow Distribution

5) Calculative Methods for the CE Large Break LOCA Evaluation

Model for the Analysis of CE and W Designed NSSS

6) Calculative Methods for the CE Small Break LOCA Evaluation

Model

7) Fuel Rod Maximum Allowable Pressure

8) Arizona Public Service Company PWR Reactor Physics Meth

odology Using CASMO-4/ SIMULATE-3

CENPD0190-A

CENPD266-P-A

CEN356(V)-P-A

Enclosure 1-P to LD

82-054

CENPD132

CENPD137-P

CEN-372P-A

NFM002

N.A. January 1976

N.A. April 1983

01-P-A May 1988

N.A. February 1993

N.A. June 1985

N.A. January 1977

N.A. May 1990

0 September 1999

Page 6 of 26

Title Report No. Rev Date

N.A.

N.A.

N.A.

1-P

3-P-A

1-P

N.A.

N.A.

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

Title

9) Technical Manual for the CENTS Code

Report No.

CE-NPD 282-P-A Vols. 1-3

Rev

N.A.

Date

June 1993

Supplement

1-P

Page 7 of 26

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Revision 5 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

The cycle-specific operating limits for the specifications listed are presented below.

3. 1.1 - Shutdown Ma- Reactor Trip Breakers Open

The Shutdown Margin shall be greater than or equal to that shown in Figure 3)1. 11.

3.1.2 - Shutdown Margin (SDM) - Reactor Trip Breakers Closed

The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.21.

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-length or part-length CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1.

3.1.7 - Regulating CEA Insertion Limits

One or more CEACs OPERABLE: With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits1

shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulation CEA groups shall be limited to the withdrawal sequence and to the insertion limits1

shown in Figure 3.1.7-22.

I A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours.

2The separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:

Page 8 of 26

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Revision 5 PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

a) Regulating Group 4 position is between 60 and 150 inches withdrawn,

b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.

c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service)

3.1.8 - Part Length CEA Insertion Limits

One or more CEACs OPERABLE: The part length 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 TiltLTq)

The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to the limit in Figure 3.2.3-1 with COLSS IN SERVICE.

3.2.4 - Departure From Nucleate Boiling Ratio (DNBR)

COLSS IN SERVICE and Both CEACs INOPERABLE - Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.

COLSS OUT OF SERVICE and Either One or Both CEACs are OPERABLE Operating within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.

COLSS OUT OF SERVICE and CEACs INOPERABLE - Operating within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel.

Page 9 of 26

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Revision 5

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

3.2.5 - Axial Shape Index(AS)

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

COLSS OPERABLE -0,18 <_ ASI• 0.16 for power > 50% -0.28 < ASI < 0.16 for power < 50%

COLSS OUT OF SERVICE (CPC) -0.10 < ASI < 0.10

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 Ž 3000 ppm.

Page 10 of 26

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PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE

REACTOR TRIP BREAKERS OPEN 7 .............................. ..

6 ... .......... -... ....... ......... ......... ............ - - - --... .......... .......... - - --.............. ......... . . . . . . . . . . . . . . . . . . . .

5 . ............. ........ ---------................... ................................................. .Q ,.) REGION OF

ACCEPTABLE

OPERATION

Z/

REGION OF

UNACCEPTABLE

OPERATION

(350, L.O)

0 ' 00. . . . . . . . .200 4 0 00.. . 0 100 200 300) 400 50IN 600

COLD LEG TEMPERATURE (F)

Page 11 of 26

Revisvi on z-'

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PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

FIGURE 3.1.2-1

SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE

REACTOR TRIP BREAKERS CLOSEDrrrrr1 r, 1 n1

(500,6.5)::

REGION OF

ACCEPTABLE

---------.OPERATION -

(350,4.0)

RE GION OF

UNACCEPTABLE

OPERATION

100 200 300 400 500 60()

COLD LEG TEMPERATURE (TF

Page 12 of 26

7

6

5

4

3

H

00

I$ I 1 g ~ l $ 1 B l l ~ l

1 l l 1 . . i • l . 1 1 1 T t .. . . . . . . . . . . . . . . . . . . . .

Revision 4

---------------- .... a

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

................

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

S......................z. .

-----------

2

-----------

i I

Page 41: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2

0.5

0.0

-0.5

-1.0

-1.5

-2.0

rj

H

0)

0-

0 10 20 30 40 50 60 70 CORE POWER LEVEL

(L% OF RATED THERMAL POWER)

80 90 1O0)

End of Cycle Limit Beginning of Cycle Limit

TECH SPEC 3.1.4 Maximum Upper Limit

Page 13 of 26

-3.0

-3.5

.0.05) "' "" .. .' "r .... .. ..... Ž:

. (50%, 0.0) •. .

-(100%,-0.2 - - - -- - -.-- - -- - - - - - - - . .. . . . . .. .. .. . . . . .. . - - -

F5% 0.0 .. ..

-(0%,-3.4)J

.,.. ... ...... . --- ...... .... .. .... . . . . . . ...... ....... i : . . . . . .:. . ......... ------- ----..

-. ...........- ............ ............................. .. ................ .. ... .......... .... 2............. 7 . . . . ...............

S.. ... ... ... ... .. ... ... ... ... .. ... ... .. T C R E O F ... ... .i............... ......... ...............

: ACCEPTABLEE

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

-- - - - - - ----.. . . . . . . . . . . . . . . .-- . . . . . . . . . . . . . . . .-- - - - - - - - - - -,-- - - - - . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . ..-. . . . . . . . . . .

.- .. . . . : .. . .. . .. .. ... .. ... .. .. . ... . . .. . . ... ... . ... . ... . ... . ... .. " . . .... . . . ...-- - ---- -... .. ..

-(0% ,-3.4)

.. . . .... . . . . .. . . . . . .... ..... ... ..... ... ........ . .i. . . .J . . . .i . . . .--- -- -- --- -- -- --- -- -- ---4.0

-4.5

Revision 4

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PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

FIGURE 3.1.5-1 CORE POWER LIMIT AFTER CEA DEVIATION*

0 10 20 30 40 50

TIME AFTER DEVIATION. MINUTES

* WHEN CORE POWER IS REDUCED TO 55% OF RATED THERMAL POWER PER THIS LIMIT CURVE, FURTHER REDUCTION IS NOT REQUIRED.

60

Page 14 of 26

30

25

z 0

H

z

20

15

10

5

0

Revision 4

Page 43: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

I !

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

........ ........... .. .z-o .. ....... ... ... . . . .

-

-... 0:... ... fr•

.. .............. W .........

*1

0

H r-/

S. . .... ...... --- -• ................. .. . .- t :l v -. • - ., -!.......... .......... ....... -,.......... ..... 0 00 U I: . ~~u~~ir I

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

.... .. ....... O .. ........... ...S . .. 9 . ...... • ..

....... ..... ........ ....~•i • 1 .~ 1 1 i 11" ... ...... i. ... .... --- ------ -- ... .... ........ ......... .......... ...--- -..... .... ..... ......

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

.. . . .. W iO .......... A~I~fS ~~11i~5

Sý1HDN1 801 kdflONIO

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

.... ... ,...........-..:•*v • • • '• ,• "•

.. . ..• , . .... ........ . ........ ..... .... . ........ ....

12 ýI !(., R R 7.r4"TR

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

0ý C. N• ~0 (1 0 0

}JtAMOd 1IVJNd•HH)I CELVW, 4A0 NOIL3VNH,

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(9

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00

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S....... .. ......... ... ........... .

.......... ... ... .............

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

0

0

0

0

I I

.0

0 wn

C;3

0

0

\0

0

C)

01

z

0

Page 44: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

I I -Q

0

o -�

- �

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

. ..............K m .l .- ..... r - •

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. ...........

-- --------

u

0 O

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0

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Cl

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S. . . . . . . . . . . . . . . . . . . . . .

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.. ......... ý....Mnnm.q ........ woomm.m. . -000. ý, ......

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z

>

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0 '0

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z~ ~ ~~M ..... .... .. .... .. .... ....

0 ~ U ..... ... .... .... m :• .i.........:...........,

S......... • .. • .. ..... ýT -w "'•:• •

.. . .. . . .. • . . ! ... .... .... • i. .... .. .... ...-- -- ... ..... .. . ... : .. .. .. .... .. ... ..! ... .. .. .. . .

............ . ..,...H N .O . ..... .....N ...... • N .. > I --... ...---.- --

.. ..... ........... ....... .... .. .............. .. ....... --- .. ............... S........... ... ..... I• ...... "? • ° t _ _ _ ..

Ji~~ll'1 IOJIN NONIISNVNI*

UVINS kCIVghLS MMJ~ IIIOHS .S3IHDNI 09 ® SdflO'O

...... . .

...........

Page 45: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

FIGURE 3.1.8-1 PART LENGTH CEA INSERTION LIMITS

VERSUS THERMAL POWER0.0

10.0

"20.0

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

- ----- :OPERATION ------ ---

* UNACCEPTABLE

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

------

TRANSIENT INSERTION LIMIT (75.0:INCHESý

OPERATION..o

RESTRICTED -- i............. :..............i . .

z

u z z

0

0

C/)

0

z

H

LONG TERM STEADY STATE INSERTIONLIMITS! (112.5 INCHES) .. . ... . . . . ...... •.............. ...... .. . .i............. -- ---- -- ............. • . . . ................... -- ---- -- -----.......... . . . . . . .

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

OPERATION ACCEPTABLE . ............... . . . . . . . . . . . . . . . . . . . . . .............. . . .-- -- ------ ---.- - -- - ---...................... . .. . . . . . . . . . . . .

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 17 of 26

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

Revision 4

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

........................

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

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

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

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

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

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

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

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

7 ---------------------------- ......

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

............. ............

............

I

I

Page 46: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

FIGURE 3.2.3-1

AZIMUTHAL POWER TILT VERSUS THERMAL POWER

(COLSS IN SERVICE)

0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0

CORE POWER LEVEL (% OF RATED THERMAL POWER)

Page 18 of 26

20.0

15.0

10.0

t

0

N

REGION OF

UNACCEPTABLE

OPERATION

REGION OF ACCEPTABLE OPERATION

5.0

0.0

Revision 4

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PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

FIGURE 3.2.4-1

COLSS DNBR OPERATING LIMIT

ALLOWANCE FOR BOTH CEAC's INOPERABLE

1000 25 50 75

CORE POWER LEVEL (% OF RATED THERMAL POWER)

Page 19 of 26

25

z 2 u F.

ýz

.-.]

0 u

20

15

10

5

0

Revision 4

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PVNGS UNIT 2 CORE OPERATING LIMITS REPORT Revision 4

FIGURE 3.2.4-2

DNBR MARGIN OPERATING LIMIT BASED ON

THE CORE PROTECTION CALCULATORS

(COLSS OUT OF SERVICE, CEAC's OPERABLE)2.5

2.4

2.3

2.2

2.1

2.0

1.9

1.8 -0 0.10 0.15 0.20

Page 20 of 26

z

z

C-) u•

.20 -0.15 -0.10 -0.05 0.00 0.05

CORE AVERAGE ASI

ANY POWER LEVEL

MINIMUM OF 1 :CEAC OPERABLE

S .10 03 2.

S.. ............ ................ ................. i........... ... •................ ;............ . . ............ ................... .

: : II (-0.1,2.24),

----- ---- ----..... .... .. ........ -- -----....... ....... ....... ....... ...... ........................ ... .... ... ........ ! ...... . ...

* I a ACCEPTABLE OPERATION

: POWER AT OR ABOVE 90 % .. .. . ...... • ................ ,........... ........ . . . . . . . . . . . . . . . ................ /. . ............ i................ a. .. . . ..............

NMINIMUM OF ICEAC OPERABW

(0.05:2.03) .... .. .. --...., .. .. : . . (0.1 ,2.0 )

.. . .. . . .... ............. . . . . . .... . ..... . .......... ..... .... .. .... .. .. . ..... .. ... ...... S:

{-0. 1, 1.96.) i! UNACCEPTABLE

....................... . . . ... . ............... O P R A IN-... .. . .. ....--.. . ... .. . .... . .. . .. . OPERATION ----- I ---- - . ....... ..

Page 49: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

FIGURE 3.2.4-3

DNBR MARGIN OPERATING LIMIT BASED ON

THE CORE PROTECTION CALCULATORS

(COLSS OUT OF SERVICE, CEAC's INOPERABLE)

-0.15 -0.10 -0.05 0.00 0.05

CORE, AVERAGE ASI

0.10 0.15 0.20

Page 21 of 26

3.6

3.5

3.4

z

U:

3.3

ACCEPTABLE OPERATION

ANY POWER LEVEL

......... . .

S.. . . . . . . . . i . . . . . . .

0.1.3.32)

OPERATION

I ........... I .... ,,,i., Ik, .. .... I .... ?

CEAC's INOPERABLE

(-0.U1,3.19) N

:UNACCEPTABLE

3.2

3.1

3.0 -0.20

-----------

............

ýt A

1 , 1, ý . I ,, I ... . .. .. .. .I

Revision 4

J

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

Table 3.3.12-1

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 0.5 hours ONA ONA

4 not on SCS 12 hours 0.5 hours ONA ONA

5 not on SCS 8 hours 0.5 hours ONA ONA

4 & 5 on SCS ONA ONA ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 22 of 26

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

Table 3.3.12-2

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 > Keff > 0.97

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 1 hour 0.5 hours ONA

4 not on SCS 12 hours 1.5 hours 0.5 hours ONA

5 not on SCS 8 hours 1.5 hours 0.5 hours ONA

4 & 5 on SCS 8 hours 0.5 hours ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 23 of 26

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

Table 3.3.12-3

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 Ž Keff> 0.96

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 2.5 hours 1 hour ONA

4 not on SCS 12 hours 2.5 hours 1 hour 0.5 hours

5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours

4 & 5 on SCS 8 hours 1 hour ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 24 of 26

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

Table 3.3.12-4

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 Ž_ Keff> 0.95

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 3 hours 1 hour 0.5 hours

4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours

5 not on SCS 8 hours 3.5 hours 1.5 hours 0.75 hours

4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA

Notes: SCS Shutdown Cooling System ONA = Operation Not Allowed

Page 25 of 26

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Revision 4

PVNGS UNIT 2 CORE OPERATING LIMITS REPORT

Table 3.3.12-5

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff _< 0.95

OPERATIONAL MODE

Number of Operating Charging Pumps

0 1

3

4 not on SCS

5 not on SCS

4 & 5 on SCS

6

12 hours 4 hours

12 hours 4.5 hours

8 hours

8 hours

24 hours

4.5 hours

2 hours

1.5 hours

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 26 of 26

3

1.5 hours

2 hours

2 hours

0.75 hours

ONA

I hour

1 hour

1 hour

ONA

ONA

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Rcvision 8

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

CORE OPERATING LIMITS REPORT

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNIT 3

Revision 8

Page 1 of 26

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Revision 8

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

Table of Contents

Description Revision # Page

Cover Page 8

Table of Contents 8

List of Figures 7

List of Tables 7 4

Affected Technical Specifications 7 5

Analytical Methods 7 6

CORE Operating Limits

3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 8 8

3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 8 8

3.1.4 Moderator Temperature Coefficient (MTC) 8 8

3.1,5 Control Element Assembly (CEA) Alignment 8 8

3.1.7 Regulating CEA Insertion Limits 8 8

3.1.8 Part Length CEA Insertion Limits 8 9

3.2.1 Linear Heat Rate (LHR) 8 9

3.2.3 Azimuthal Power Tilt (Tq) 8 9

3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 8 9

3.2.5 Axial Shape Index (ASI) 8 10

3.3.12 Boron Dilution Alarm System (BDAS) 8 10

3.9.1 Boron Concentration 8 t0

Page 2 of 26

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Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

List of Figures

Description

Figure 3.1.1-1 Shutdown Margin Versus Cold Lea Temperature Reactor Trip Breakers Open

Figure 3, 1.2-1 Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed

Figure 3.1.4-I MTC Acceptable Operation, Modes I and 2

Figure 3.1.5-1 Core Power Limit After CEA Deviation

Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power (COLSS in Service)

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

Figure 3.1.8-1 Part Length CEA Insertion Limits Versus Thermal Power

Figure 3.2.3-i Azimuthal Power Tilt Versus Thernmal Power (COLSS in Service)

Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable

Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEACs Operable)

Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEACs Inoperable)

Page 3 of 26

Revision #

7

7

7

7

7

7

7

7

7

7

Pac~e 11

12

13

14

15

16

17

18

19

20

21

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Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

List of Tables

Description

Table 3.3.12- Required Monitoring Frequencies for Backup Boron 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 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 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 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 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95

Page 4 of 26

Revision

7

7

7

7

7

Lig e

11)1

23

24

25

26

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Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde Unit 3 Technical Specifications.

AFFECTED PVNGS TECHNICAL SPECIFICATIONS

3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open

311.2 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 Length CEA Insertion Limits

3.2.1 Linear Heat Rate (LHR)

3.2.3 Azimuthal Power Tilt (Tq)

3.2.4 Departure From Nucleate Boiling Ratio (DNBR)

3.2.5 Axial Shape Index (ASI)

3.3.12 Boron Dilution Alarm System (BDAS)

3-9 1 Boron Concentration

Page 5 of 26

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Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

ANALYTICAL METHODS

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

Title

1) CE Method for Control Element Assembly Ejection Analysis

2) The ROCS and DIT Computer Codes for Nuclear Design

3) Modified Statistical Combination of Uncertainties

4) System 8 0 TM Inlet Flow Distribution

5) Calculative Methods for the CE Large Break LOCA Evaluation

Model for the Analysis of CE and W Designed NSSS

6) Calculative Methods for the CE Small Break LOCA Evaluation

Model

7) Fuel Rod Maximum Allowable Pressure

8) Arizona Public Service Company PWR Reactor Physics Meth

odology Using CASMO-4/ SIMULATE-3

Report No.

CENPD0190-A

CENPD266-P-A

CEN356(V)-P-A

Enclosure 1-P to LD

82-054

CENPD132

CENPD137-P

CEN-372P-A

NFM002

Rev

N.A.

N.A.

Date

January 1976

April 1983

01-P-A May 1988

N.A. February 1993

N.A. June 1985

N.A. January 1977

N.A.

0

May 1990

September 1999

Supplement

N.A.

N.A.

N.A.

I-P

3-P-A

I-P

N.A.

N.A,

Page 6 of 26

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Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

Title

9) Technical Manual for the CENTS Code

Report No.

CE-NPD "2)S -P- A Vols. 1-3

Rev

N.A.

Date

June 1993

Supplement

I-P

Page 7 of 26

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PVNGS UNIT3 CORE OPERATING LIMITS REPORT

The cycle-specific operating limits for the specifications listed are presented belo~v.

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.

3.1.2 - Shutdown Margin (SDM).- Reactor Trip Breakers Closed

The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.21.

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 fCEA) Alignment

With one or more full-length or part-length CEAs rnisaligned fromn any other CEAs in its group by more than 6.6 inches, the minimum required MODES I and 2 core power reduction is specified in Figure 3.1.5-1.

3.1.7 - Regulating CEA Insertion Limits

One or more CEACs OPERABLE: 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, regulation CEA groups shall be limited to the withdrawal sequence and to the insertion limits' shown in Figure 3.1.7-22.

1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1. 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted. In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 hours.

2The separation between Regulating Groups 4 and 5 may be reduced from the 90 inch value specified in Figures 3.1.7-1 and 3.1.7-2 provided that each of the following conditions are satisfied:

Page 8 of 26

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Reviisic 8

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

a) Regulating Group 4 position is between 60 and 150 inches withdrawn.

b) Regulating Group 5 position is maintained at least 10 inches lower than Regulating Group 4 position.

c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service)

3.1.8 - Part Length CEA Insertion Limits

One or more CEACs OPERABLE: The part length 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 (T])

The AZIMUTHAL POWER TILT (Tq) shall be less than or equal to the limit in

Figure 3.2.3-1 with COLSS IN SERVICE,

3.2.4 - Departure From Nucleate Boiling Ratio (DNBR)

COLSS IN SERVICE and Both CEACs INOPERABLE - Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operation limit based on DNBR decreased by the allowance shown in Figure 3.2.4-1.

COLSS OUT OF SERVICE and Either One or Both CEACs are OPERABLE Operating within the region of acceptable operation of Figure 3.2.4-2 using any operable CPC channel.

COLSS OUT OF SERVICE and CEACs INOPERABLE - Operating within the region of acceptable operation of Figure 3.2.4-3 using any operable CPC channel,

Page 9 of 26

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Revisio'n 8

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

3.2.5 - Axial Shape Index (AST)

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

COLSS OPERABLE -0.18 < ASI < 0.16 for power > 50% -0.28 < ASI < 0. 16 -for power < 50%

COLSS OUT OF SERVICE (CPC)

-0.10•_< ASI•< 0,t0

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 10 of 26

Page 65: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

FIGURE 3.1.1-1

SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE

REACTOR TRIP BREAKERS OPEN7

6

5)

jd

100 200 300

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

(350,J.0)

*I***I3 ISI*uII�**US

400 500 600

COLD LEG TEMPERATURE (°F) Page 11 of 26

REGION OF

ACC:EPTABLE

OPERATION<1

C>

<

z 0

4

3

2

00

I I ~ l ~ l ~ l l l .l • I 1 . . . . . . . . . . . . .

Revision 7

-.......................--------- 500,5.0) .,,

REGION::OF

*UNACCEPTABLE

*OPERATION

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

-----------

I

--- ----- --.. . . a . .

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

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

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

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

Page 66: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE

REACTOR TRIP BREAKERS CLOSED

REGION OF

ACCEPTABLE

..OPERATION

REG

UNA

OPE

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

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

100

(500,6.5);:

(350,4.0)

ION OF

LCCEPTABLE S. ............ .. , -- - - - - - - - - -............. .... ..... . . . . . . . . . . .

;RATION

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

200 300 400

COLD LEG TEMPERATURE (TF)

Page 12 of 26

6

5

z H

©t

00 500 600

Revision 7

............ ...

Page 67: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

FIGURE 3.1.4-1

MTC ACCEPTABLE OPERATION, MODES 1 AND 20.5

0.0

0 10 20

-0.5

-1.0

-1.5

-2.0

-2.5

-3.0

-3.5

-4.0

-4.5

End of Cycle Limit Beginning of Cycle Limit

TECH SPEC 3.1.4 Maximum Upper LimitU* U - US

Page 13 of 26

(100%',6 . ~ ~ ~ ~ ~ ~ ~ .... ...6 " '•,,,,}. .t,.,% .,,.5:,"+' " ' : "J'"'"'..,,,,,,• ... .. ... • ........ + ......... .... oo ,

-- -- -- -.. .. . -- -- .. . . . . .. "-• •- --+ ------............ . ....... ... " * . (50%. 6.0) .........

* (100%,-o.2

. .

..... ...... ....... ......... ---M TC A REA -O F ..

ACCEPTABLE

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

-............ --- .................................. ------------ --. - -.. .............. ------------- .............. -- -----...-, -..

S.. ... . . .. . .. ... .. .............. . .... .... .... ...... ........ ................................ . ....... ..... . ... ...- ......... ...

-(o%,-3.4)

-----. . . .. . . . . . . . . .. . . . . . .......... .. -- --- .............. .............. i........ ...... :.......................................

[.L.

"z U

0 U

0

[.0

0:.

30 40 50 60 70 80 90 100

CORE POWER LEVEL (% OF RATED THERMAL POWER)

Revision 7

Page 68: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

ION SIKNOIIDflGTh1 XIHDMflJ AýMfD IHAJY SIH, Nad NEIMPOd 'IVFIqUHHI U3IJVS -IO /o 01 U3JflCThI SI S9EAAOd 39IOD NaHPA

SahLflNIN 'NOIlVIA3CQ '8ThLV RNIJI

09 09 017 0 C 0z 01 0

z

.............. ...... ..... .

....... ....N----------- --------- ---------- 09) * z

*NOIVIIAG V~ ~J3IAVIIIAI ~HX~d DJO --- -- -- ---- .. .. .. --- -- -

----- ---I~ > --- d3~ --- ~1 ---- ~d -- 0 -- --- f -----------------------

Page 69: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

.o tr. $•

Na3kOd '1VVa• I•I •,IVN1 JO NOIIDVNt

Cl 6 6

0•

-4

H

C,.)

IIIII II

~ ~ ~ ~ ~~ ~- - - - - - -. . .. . . , . . . . . . . . . . . . . . . . • . . . . . . . ., . . . . . . . . . . . .. . . . . . . . . . . . . . . . . , . . . .... . . ... .-- - . . . . . . . . . . . . . . . , . . . . . . .. . . . . . . .. . . . . . . . . . . . . .

...... ....:. .......

S... .. . .. • . .. • . .. ........ .. .. --- --- .. .....• • ...... . .... ......... .................. .............. .. ... .... .....

....... • .• " 6 :• " o •i. ......... . . . . ....... ............-- ------ ----- ----- .... ....... . . . . . . . . . .... .. ... ..... ... .............

S. . ... . .. .. . ... Q ----- 4 i ........... V ý •. .... ....... ! ................ ... .. ........... ................... i.. ... .......... ....... . .. . ... ..... ..

. .. ... .... ... ......

S.. .. .... .. • . . • -. ..-- .............. '. . ....... . ... ... .. " .......... . . .: .................. ----------- .. ................. . . . . . . . . . . . . . . .

S. . .. .. .i. . ... .. ... .. .. . .. .. .. . ,.. ...... . ....... .. ........ .... ..... : .... ........ ..... .; . . .... ... .... ....... ........ ................. ,..... ..... . .

I" I: I: I"SHHDNl 8091_ 9g dflOHDO

~~ i SI

-- ----- ------ -- . .... ----- -- ------- ----- -......... ........... . < .. . . . . . . . .

-- ----- -- ---- -- .. ... ...... ... .... HýDN 819 .lN

0

--I

01

0

.1

cr�

0

z

-o

o 0

C) o

-. u z ~ 0<

z

0

0

"-C-1

o < 0

- 0

0--

C/)

C.)

1-1

F_

0

z

0

u ©

ýO

H.

00

0

"cl

A0

Page 70: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

0 ON 6

I:

0

0

H

C/)

z

(.)4

00

S:HDM 801 T o dflO-do i In !

S 6 6 0O

HY1AOd 1Vrl'NHItJ cI•hLVHI f1O NOLLDV'dH

0

II I I

i .......... ..... ......... . :............. ............... ....------ ..............

S... ............. ,4 ..... z ... •...... ........... !..................................

z. 0 u

: .. .. .. .... .Z . . • --- ....... ..... . -. .................... ...... ... . .. .

, , , ............ ... ... 0... ............ •.:...... .....-----................

... .. .. . .... ..' .. .. ...

S............. .... • .... ..i-............------ ----------------. .............-.

.... .......... .......... ....... ! ........ .. . ..... !..... ............. i.... ..... ..........

C., -.., 6 6 6

... ... ...... .....iii .. .... .... . ............. i............ ... i... ..... .. ...

S. . .... . ......... N 0 9 DIO

0

0

0 0...

0d

ci

0 H-.

0

F0

(/€)

Q

0

z

z 0 z

..................

............

...........

.. . . .

....... .................

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

03

0

0.

'0 "0 "

0'

Cl

0

0 -1

.. .. . . .Iml................. W." ...... w ........mmmmm

1,0

,0

oz 91.

.-0

0< -ON

•-0.Q

z

S.... .............. I -....... .................. ..... ....... .........................

J.I..I'. .... s• . oHSNI 2ILVIS AGIVaS WdlL'd{OHS

*a~~~~~ ............. ....... as .~ saa ~ *5 as a ..- a... ...

.. . . . . ... . ...

.. ....

Page 71: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 7

FIGURE 3.1.8-1

PART LENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER

0.0

10.0

20.0

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

o

-.OPERATION .........

UNACCEPTABLE

S.............. .......... .................. ............ tn

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

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

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

4 i ..... . ... . .. .. .i ... . ... . . .. .r . .. . .. .. . .. -. .. . .. ... . .. : . . . . .

ANSIET INSRTIONLIMIT(75.0INHS

-- --.--..-.--.OPER

REST S............. !............

A- T IO N ............. --...........

RICTED S. .... .... ..... ------ -- --- ---.. ..i . .. ..

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

z

z 0

F

r.•

0

u

z Ei.

H

LONG TERM STEADY STATE INSERTION:LIMITS: (112.5 INCHES) . . . . . . . . . . . . . . . . . . . . . . . . . .. , . . . . . . . . . . . . .... . . . . . .. . .... . . . . . . . . -- -- -. . .. . . . . . . . . . . . . . . .. .. . . . . . . . . .. . . . . . . . . . . . .

OPERATION ACCEPTABLE

S. . . . i . . . . . . ... . . . ... .: . . . .. - . . ... ... -- --- --. . . . . . ... .

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 17 of 26

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

S. . . . . . . i l l l l 4 D i l l l i m b

..........

..........

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

Page 72: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

FIGURE 3.2.3-1

AZIMUTHAL POWER TILT VERSUS THERMAL POWER

(COLSS IN SERVICE)

0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0

CORE POWER LEVEL (% OF RATED THERMAL POWER)

Page 18 of 26

20.0

15.0

10.0

H=,=

0.

H

N

REGION OF

UNACCEPTABLE

OPERATION

REGION OF ACCEPTABLE OPERATION

5.0

0.0 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --. . | I . . . .

Revision 7

Page 73: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

FIGURE 3.2.4-1

COLSS DNBR OPERATING LIMIT

ALLOWANCE FOR BOTH CEAC's INOPERABLE

25 50 75 100

CORE POWER LEVEL (% OF RATED THERMAL POWER)

Page 19 of 26

25

0 u 0

(9

0~I

0

z

0m (9l -.

20

15

10

5

00

Revision 7

Page 74: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 7

FIGURE 3.2.4-2

DNBR MARGIN OPERATING LIMIT BASED ON

THE CORE PROTECTION CALCULATORS

(COLSS OUT OF SERVICE, CEAC's OPERABLE)2.5

2.4

2.3

1,2.33)

-OPERATION

......................I- - - -. _ _. ... .. .. .. ... I .I -

-0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20

CORE AVERAGE ASI

Page 20 of 26

ACCEPTABLE OPERATION

ANY POWER LEVEL

MINIMUM OF 1 CEAC OPERABL

ý(o.032.33?)

(-0.1,2.24) U U

ACCEPTABLE OPERATION a U

POWER AT OR ABOVE 90 % S........................ ...... ...............

MINIMUM OF 1 CEAC OPERABL]4

S(0.05i2.03) : ... .... .. ........... ---------- -------..... ..-- ' ,'.7 i

(-0.,1.6 iUNACCEPTABLE

z

rh

rz.

2.2

2.1

2.0

1.9

1 9

-0.20

. . . .. i i i i l I I . .

(0.1,2.20.3).

. . . .l . . . .i . i. I .. .. . .. I . .. . . . . . .l . l . l.. . . l . .. . . . . l.. l. . l. . l. . l.. . .

(0.

.................

I

Page 75: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revisior

FIGURE 3.2.4-3

DNBR MARGIN OPERATING LIMIT BASED ON

THE CORE PROTECTION CALCULATORS

(COLSS OUT OF SERVICE, CEAC's INOPERABLE)

-0.15 -0.10 -0.05

CORE

0.00 0.05

AVERAGE ASI

0.10 0.15 0.20

Page 21 of 26

3.5

3.4

z

z3.3

3.2

3.1

ACCEPTABLE OPERATION

ANY: POWER LEVEL

CEAC's INOPERABLE

(0.1,3.32):(0.0,3.32)

(-0.1,3.19)

UNACCEPTABLE

* OPERATION

.I - .I I�I B t�t*I I LLJLA4LAA B S II II 53,55 I I I

-0.20

.. .. ... .. .. .. ...lll ll

a 7

.......... ................

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

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

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

S.........-- ....

Page 76: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

Table 3.3.12-1

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff > 0.98

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 0.5 hours ONA ONA

4 not on SCS 12 hours 0.5 hours ONA ONA

5 not on SCS 8 hours 0.5 hours ONA ONA

4 & 5 on SCS ONA ONA ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 22 of 26

Page 77: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

Table 3.3.12-2

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 Ž Keff > 0. 9 7

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 1 hour 0.5 hours ONA

4 not on SCS 12 hours 1.5 hours 0.5 hours ONA

5 not on SCS 8 hours 1.5 hours 0.5 hours ONA

4 & 5 on SCS 8 hours 0.5 hours ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 23 of 26

Page 78: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

Table 3.3.12-3

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 _Ž Keff> 0.96

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 2.5 hours 1 hour ONA

4 not on SCS 12 hours 2.5 hours 1 hour 0.5 hours

5 not on SCS 8 hours 2.5 hours 1 hour 0.5 hours

4 & 5 on SCS 8 hours 1 hour ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 24 of 26

Page 79: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

Table 3.3.12-4

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 Ž Keff> 0.95

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 3 hours 1 hour 0.5 hours

4 not on SCS 12 hours 3.5 hours 1.5 hours 0.75 hours

5 not on SCS 8 hours 3.5 hours 1.5 hours 0.75 hours

4 & 5 on SCS 8 hours 1.5 hours 0.5 hours ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 25 of 26

Page 80: Palo Verde Nuclear Generating Station Units 1, 2 and 3 ... · Revision 5 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT This Report has been prepared in accordance with the requirements

Revision 7

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT

Table 3.3.12-5

REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING

CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff •< 0.95

OPERATIONAL Number of Operating Charging Pumps

MODE 0 1 2 3

3 12 hours 4 hours 1.5 hours 1 hour

4 not on SCS 12 hours 4.5 hours 2 hours I hour

5 not on SCS 8 hours 4.5 hours 2 hours 1 hour

4 & 5 on SCS 8 hours 2 hours 0.75 hours ONA

6 24 hours 1.5 hours ONA ONA

Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed

Page 26 of 26


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