Text

Core Operating Limits Report (COLR) - Revision 18
	ML091270389
Person / Time
Site:	Palo Verde
Issue date:	04/29/2009
From:	Weber T; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-05998-TNW/KAR
	Download: ML091270389 (32)
	v • d • e

Technical Specification 5.6.5d LAMS Thomas N Weber Mail Station 7636 Palo Verde Nuclear Department Leader, Tel. 623-393-5764 PO Box 52034 Generating Station Regulatory Affairs Fax 623-393-5442 Phoenix, Arizona 85072-2034 102-05998-TNW/KAR April 29, 2009 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde'Nuclear Generating Station (PVNGS) Unit 3 Docket No. STN 50-530 Core Operating Limits Report (COLR), Unit 3 -Revision 18 Pursuant to PVNGS Technical Specifications, Section 5.6.5d, enclosed is Core Operating Limits Report (COLR), Unit 3 -Revision 18, which was made effective April 15, 2009. This revision includes changes to the Moderator Temperature Coefficient (MTC) limits for Technical Specification (TS) 3.1.4, and the Axial Shape Index (ASI) limits for TS 3.2.5.By copy of this letter and the enclosure, this COLR revision is being provided to the NRC Region IV Administrator and the PVNGS Senior Resident Inspector.

This letter does not make any commitments to the NRC. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.Sincerely, TNW/RAS/KAR/gat

Enclosure:

PVNGS Unit 3 Core Operating Limits Report (COLR), Revision 18 cc: E. E. Collins Jr. NRC Region IV Regional Administrator J. R. Hall NRC NRR Project Manager R. I. Treadway NRC Senior Resident Inspector for PVNGS A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Comanche Peak

Diablo Canyon

Palo Verde

San Onofre

South Texas

Wolf Creek Enclosure PVNGS Unit 3 Core Operating Limits Report (COLR)Revision 18 PALO VERDE NUCLEAR GENERATING STATION'(PVNGS)

UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 Re l E e Digitally signed by Hwang, Responsible Engineer Hwang, LusnChih(Zo1668)

Date D DN: cn=Hwang, Lun-Chih Lun-Chih Reason: I am the author of this Date: 2009.03.26 09:46:4 ( Dod) v: 07'00'Independent Reviewer Digitally signed by Wenzel, Wvenzel, Richard R(Z99534)Date DN: cn=Wenzel, Richard R Richard R Reason, I have reviewed this....--oe'meoo (Z 9 5 d3 4)'hý Date: 2609.03.26 09:56:27-07'00'Rs nbW ebb Digitally signed by Webb, Responsible Section Leader W ebb 1 James R(V97187)Date ýi DN: cn=Webb, James R (V97187)Jam es -"Reason:

I am approving.-\ this doc.iment (V97 71 87.;') Date: 2009.03.26 10:28:07"___ /_ -07'00'Page 1 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 Table of Contents Description 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 8 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 8 3.1.4 Moderator Temperature Coefficient (MTC) 8 3.1.5 Control Element Assembly (CEA) Alignment 8 3.1.7 Regulating CEA Insertion Limits 8 3.1.8 Part Strength CEA Insertion Limits 9 3.2.1 Linear Heat Rate (LHR) 9 3.2.3 Azimuthal Power Tilt (Tq) 9 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 9 3.2.5 Axial Shape Index (ASI) 10 3.3.12 Boron Dilution Alarm System (BDAS) 10 3.9.1 Boron Concentration 10 Page 2 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 List of Figures Description Figure 3.1.1-1 Shutdown Margin Versus Cold Leg Temperature 11 Reactor Trip Breakers Open Figure 3.1.2-1 Shutdown Margin Versus Cold Leg Temperature 12 Reactor Trip Breakers Closed Figure 3.1.4-1 MTC Acceptable Operation, Modes 1 and 2 13 Figure 3.1.5-1 Core Power Limit After CEA Deviation 14 Figure 3.1.7-1 CEA Insertion Limits Versus Thermal Power 15 (COLSS in Service)Figure 3.1.7-2 CEA Insertion Limits Versus Thermal Power 16 (COLSS Out of Service)Figure 3.1.8-1 Part Strength CEA Insertion Limits Versus Thermal Power 17 Figure 3.2.3-1 Azimuthal Power Tilt Versus Thermal Power 18 (COLSS in Service)Figure 3.2.4-1 COLSS DNBR Operating Limit Allowance for Both 19 CEACs Inoperable In Any Operable CPC Channel Figure 3.2.4-2 DNBR Margin Operating Limit Based on the Core 20 Protection Calculators (COLSS Out of Service, CEAC(s)Operable)Figure 3.2.4-3 DNBR Margin Operating Limit Based on the Core 21 Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)Page 3 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 List of Tables Description Page Table 3.3.12-1 Required Monitoring Frequencies for Backup Boron 22 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keft'> 0.98 Table 3.3.12-2 Required Monitoring Frequencies for Backup Boron 23 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97 Table 3.3.12-3 Required Monitoring Frequencies for Backup Boron 24 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff> 0.96 Table 3.3.12-4 Required Monitoring Frequencies for Backup Boron 25 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff> 0.95 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron 26 Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 4 of 26 PVNGS UNIT 3 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 3 Technical Specifications.

AFFECTED PVNGS TECHNICAL SPECIFICATIONS 3.1.1* Shutdown Margin (SDM) -Reactor Trip Breakers Open 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 3.1.4 Moderator Temperature Coefficient (MTC)3.1.5 Control Element Assembly (CEA) Alignment 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Strength CEA Insertion Limits 3.2.1 Linear Heat Rate (LHR)3.2.3 Azimuthal Power Tilt (Tq)3.2.4 Departure From Nucleate Boiling Ratio (DNBR)3.2.5 Axial Shape Index (ASI)3.3.12 Boron Dilution Alarm System (BDAS)3.9.1 Boron Concentration Page 5 of 26 PVNGS UNIT 3 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) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:

Title Report No. Rev Date Supplement

1) CE Method for Control Element Assembly Ejection Analysis (13-NO01-1301-01204-1)

2) The ROCS and DIT Computer Codes for Nuclear Design (13-NOO1-1900-01412-0)

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

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

5) Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS (13-N001-1900-01192-3)

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

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

8) Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/SIMULATE-3 (NFM-005)CENPD-0190-A CENPD-266-P-A N.A. January 1976 N.A.N.A.N.A.April 1983 May 1988 (April 1996)CEN-356(V)-P-A -P to LD-82-054 CENPD-132 CENPD-137-P CEN-372-P-A 01-P-A (ARI)N.A.N.A. February 1993 N.A. March 2001 1-P 4-P-A 2-P-A N.A.N.A.N.A.N.A.April 1998 May 1990 January 2006 NFM-005 N.A.Page 6 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 Title Report No. Rev Date Supplement

9) Technical Description Manual for the CENTS CodeVolume 1 (CENTS-TD MANUAL-VOL 1)10) Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)11) Technical Description Manual for the CENTS CodeVolume 3 (CENTS-TD MANUAL-VOL 3)12) Implementation of ZIRLOTM Cladding Material in CE Nuclear'Power Fuel Assembly Designs (13-N001-1900-01329-0)

CE-NPD 282-P-A Vols. 1 CE-NPD 282-P-A Vols. 2 CE-NPD 282-P-A Vols. 3 CENPD-404-P-A 2 March 2005 N.A.2 March 2005 N.A.2 March 2005 N.A.0 November 2001 N.A.Page 7 of 26 PVNGS UNIT 3 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 3.1.5-1.3.1.7 -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 limitsI shown in Figure 3.1.7-2.2 Regulating Groups 1 and 2 CEAs shall be maintained fully withdrawn 3 while in Modes 1 and 2 (except while performing SR 3.1.5.3).1 A reactor power cutback will cause either (Case 1) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with no sequential insertion of additional Regulating Groups (Groups 1, 2, 3, and 4) or (Case 2) Regulating Group 5 or Regulating Group 4 and 5 to be dropped with all or part of the remaining Regulating Groups (Groups 1, 2, 3, and 4) being sequentially inserted.

In either case, the Transient Insertion Limit and withdrawal sequence specified in the CORE OPERATING LIMITS REPORT can be exceeded for up to 2 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 Regulating Group 4 position.Page 8 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7-1 (COLSS In Service) or Figure 3.1.7-2 (COLSS Out of Service).3 Fully withdrawn

->147.75" (Pulse Counter indication) and >145.25" (RSPT indication) 3.1.8 -Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.3.2.1 -Linear Heat Rate (LHR)The linear heat rate limit of 13.1 kW/ft shall be maintained.

3.2.3 -Azimuthal Power Tilt (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 9 of 26 PVNGS UNIT 3 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 < ASI 0.17 for power > 50%-0.28 < ASI < 0.17 for power >20% and < 50%COLSS OUT OF SERVICE (CPC)-0.10 < ASI 0.10 for power >20%3.3.12 -Boron Dilution Alarm System (BDAS)With one or both start-up channel high neutron flux alarms inoperable, the RCS boron concentration shall be determined at the applicable monitoring frequency specified in Tables 3.3.12-1 through 3.3.12-5.3.9.1 -Boron Concentration The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained at a uniform concentration

> 3000 ppm.Page 10 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 6 5 4 z 3 Z 0 0 100 200 300 400 COLD LEG TEMPERATURE

('F)500 600 Page 11 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Re FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED vision 18 7 6 5 4 z 0 3 Cr'2 0 REGION OF ACCEPTABLE

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

O P IER A T IO N ----------------------

(500, (350,4.0)REGION OF UNACCEPTABLE OPERATION!0 100 200 300 400 COLD LEG TEMPERATURE

('F)500 600 Page 12 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 0.5 0.0-0.5 ...........

-1.0 Z 0~0 U 0 0-1.5 ...........

-2 .0 ----------

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

-3.0 S(100%,0 (50%,0.%-0.)

-- -- ----- --M T C -A R E A -0 F .........................

F......................

..ACCEPTABLE

OPERATION 4 ) -------- -- ------ --- ----- --.. .... -- ---- --- ------- -- ----------- -- -- --- -- ---.--.- -- --- -- -I.-- ----.-.I-- ---.- --- --. .. .. .....- -- -- ---..- -- -- --- -------------------------

...I -------- ... .....I. ...-- --- ----- --- ---3.5-4.0-4.5 0 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL (% OF RATED THERMAL POWER)Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit .......Page 13 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT FIGURE 3.1.5-1 CORE POWER LIMIT AFTER CEA DEVIATION*

Revision 18 30 25 z 0 r- Q 20 K ------- ------ ------ ----------

j60 MIN, 20.0%;(IOMIN,0.0%)

.... ...... .I .. ..... ....10 5 0 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 PVNGS UNIT 3 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" 0.7 2 0.6* 0.5 0 z 0.4 0 0.3-.-- (---- -S -EEFOOTNOTE-INSE-CTION-3.1:

7 FOR APPLICABILITY FOLLOWINGi :: iA REACTOR CUTBACK.L)

.. ... P o -- -- --- -- --- ------ ---- ----- ------ -------------- -------- -RP-4-POS=(72-5 "FRA-C.WR-+25-GRPSPOS=(!72.5;xFRAC.

PWR)-64.5 0---,, --r -' -' : ..Z. .- --------- -------.. ..- ------. .--------. .-------.. .--------------. ......................m Z Z" " m " " -' + --: II ._ .-: ...f ..........f ........... ........ ------ -------------------------.i .......-.-, 0: i--I- -- -SI ----------I "i iii% _ __ :_ 0. ............... ............... ..............->1 ~ .....i...0.2 0.1 AAr U.GROUP 5 GROUP 3 GROUP I I I I I I I I I I i I I I I I I I I FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0 GROUP 4 GROUP 2 F EA* I PO 10 T6+O 3(0 I a* ItH jO D CEA POSITION (INCHES WITHDRAWN)

Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).Page 15 of 26 PVNGS UNIT 3 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 0.6 S0.5[-rr.Z 0 z 0.4 0 U 0.3 0.2 0.1 0.0 0 Z 0 00 4PZ ow (SEEI....... (SEE-]FOR .4 X, REA GRP 5-A-- ----- -'OOTNOTE-IN-SEC-TION'3.1;7

......PPLICABILITY FOLLOWING CTOR.CUJTBACK.)-----FRAC.-PWR

+-9.82---POS (250.9 1 FRAC. PWR) -80.I18---------------------------------imilH , I I I a a GROUP5 GROUP3 GROUP I I I I I 11 111 I I II I I I FW* 120 90 60 30 0 FW* 120 90 60 30 0 FW* 120 90 60 30 0 GROUP 4 GROUP 2 F4* 110 9+060 t 1 t FIt* IO1[0 3+0 CEA POSITION (INCHES WITHDRAWN)

Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).Page 16 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 z40.0 50.0 c 60.0 u z Z 70.0 o 80.0 u 90.0 I-z La 100.0 F-I-" 110.0 120.0 130.0 140.0 150.0....F ............_- O.... PERA-TION

...... .....:* NACCEPTABLE

--------------------------------- --- ------ ----------------------I ------ -----------------------

.......-----........---------------.- --.. ...........---.. ..................! ...!.. ..-- ------- --------- --- -- --- -- -- -. ... .. ... .. ..... ... ... .. .. .... .. ... ... .. ..... .... ...TRANSIE-NT INSERTION LIMIT (75.0::INCHES)

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

OPERATION

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

RESTRICTED

...... .. ...--------------------- ---------------.. .... ..........----------------------------------------S -S ...s~. Ii.Sf:1 s LONG TERM STEADY STATE INSERTION:LIMITS (1 12.5 INCHES).......---------------------.. .........-- -- ...........- -....... .....----------------. .-----------------------------.. .............'OPERATION ACCEPTABLE

J. .. I ....I -...-.- -I .- -.. -. -...I ....I ....I ...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 17 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)20.0 15.0[...,-0H.10.0--------- ----------

REGION OF,........I--- REGION-OF

F UNACCEPTABLE OPERATION.................................. .................- -.---------------

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

5.0 kCCEPTABLE OPERATION I ! ..I ., U.u 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 CORE POWER LEVEL (% OF RATED THERMAL POWER)100.0 Page 18 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT R FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 25...... ...... .r.......... , ,, (95,20)2Z z 10 (75,0)0 .. ....................I ........0 25 50 75 t00 evision 18 CORE POWER LEVEL (% OF RATED THERMAL POWER)Page 19 of 26 PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 18 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)2.5 2.4 2.3 I W I W ..... I I I I I I I I I u-P.2.2 2.1 (-0.1,2.28)

(-i.1,93)----------.

... .. ..I... ... .I... ... .I...... .. ..........ACCEPTABLE OPERATION ANY POWER LEVEL AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPC CHANNEL (0,06,2.38)

(0.1,2.38)::

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

.. ............ ............ ...........ACCEPTABLE OPERATION POWER AT OR ABOVE 90%AT LEAST 1 CEAC OPERABLE IN I- EA CH- OPERA-BLE CPC CHA-1NNEL-:------------

(0.0,5,2.00)

(005200)-

'(01 200Y UNACCEPTABLE

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

L L.aLII. .** * * [ L I .L J I LLI. .....L .........

I.IIIIIIII 2.0 1.9 1.8.........

I .........

.........

...... I .. .........-0.20 -0.15 -0.10 -0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 20 of 26 PVNGS UNIT 3 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 i ... ..... .............................

i u cU 3.3----------------

ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL 3----------------

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

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

,3.27)(0.1.341).......

(. ,3.4 1!).....(-0.1 3.2 UNACCEPTABLE OPERATION LJ.LJJJ.J..8.J

~ ~ ~ ~ ~ ~ ~ ------ ------------------------------..

L L ** '* * ~~JLL J.. IJ....L.L.flI J ~ J 3.1 3.0 '-0.2..... ...I ..... .I I... ...I ...... ... I .... ....... I ..... p ..... .. ... I .........

I .........

I ......0-0.15 -0.10-0.05 0.00 0.05 0.10 0.15 0.20 CORE AVERAGE ASI Page 21 of 26 PVNGS UNIT 3 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 Page 22 of 26 PVNGS UNIT 3 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 Page 23 of 26 PVNGS UNIT 3 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 Page 24 of 26 PVNGS UNIT 3 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 Page 25 of 26 PVNGS UNIT 3 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 Page 26 of 26 ZýAM A subsidiary of Pinnacle West Capital Corporation Palo Verde Nuclear Generating Station Thomas N. Weber Department Leader Regulatory Affairs Tel. 623-393-5764 Fax 623-393-5442 Mail Station 7636 PO Box 52034 Phoenix, Arizona 85072-2034 102-05997-TNW/KAR April 28, 2009 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 2008 Annual Environmental Operating Report Enclosed please find the 2008 Annual Environmental Operating Report for PVNGS Units 1, 2, and 3. Arizona Public Service Company is submitting this report pursuant to Section 5.4.1 of Appendix B to the PVNGS Units 1, 2, and 3 Operating License Nos.NPF-41, NPF-51, and NPF-74, respectively.

No commitments are being made to the NRC in this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section Leader, at (623) 393-5111.Sincerely, Y)Y#t.,L TNW/RAS/KAR/gat Enclosure cc: E. E. Collins Jr.R. Hall R. I. Treadway A. V. Godwin T. Morales NRC Region IV Regional Administrator NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS Arizona Radiation Regulatory Agency (ARRA)Arizona Radiation Regulatory Agency (ARRA)A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Comanche Peak

Diablo Canyon

Palo Verde

San Onofre

South Texas

Wolf Creek ENCLOSURE Palo Verde Nuclear Generating Station Units 1, 2, and 3 2008 Annual Environmental Operating Report I. INTRODUCTION The Palo Verde Nuclear Generating Station (PVNGS) is located in Maricopa County, Arizona, approximately 50 miles west of the Phoenix metropolitan area.The PVNGS site comprises approximately 4280 acres. Site elevations range from 890 feet above mean sea level at the southern boundary to 1030 feet above mean sea level at the northern boundary.

The station consists of three pressurized water reactor electrical generating units. Units 1, 2 and 3 have a rated thermal power of 3990 MW.PVNGS was issued low power operating licenses NPF-34, NPF-46 and NPF-65 for Units 1, 2 and 3 by the United States Nuclear Regulatory Commission (NRC)on December 31, 1984, December 9, 1985, and March 25, 1987, respectively.

The Unit 1 full power operating license NPF-41 was issued June 1, 1985. The Unit 2 full power operating license NPF-51 was issued'April 24, 1986. The Unit 3 full power operating license NPF-74 was issued November 25, 1987. Appendix B to these operating licenses is entitled the "Environmental Protection Plan (Non Radiological)".

The Environmental Protection Plans (EPP) for each of the current operating licenses are identical.

The EPP purpose is to provide for protection of environmental values during construction and operation of the nuclear facility.

The principal objectives of the EPP are as follows: (1) Verify that the station is operated in an environmentally acceptable manner, as established by the FES (Final Environmental Statement) and other NRC environmental impact assessments.

(2) Coordinate NRC requirements and maintain consistency with other Federal, State and Local requirements for environmental protection.

(3) Keep NRC informed of the environmental effects of facility construction and operation and actions taken to control those effects.This Annual Environmental Operating Report is required by Section 5.4.1 Of the EPP. This report describes the activities during calendar year 2008 related to the PVNGS EPP. For purposes of this report, references to the EPP are considered to be the EPP of NPF-41, NPF-51, and NPF-74.

11. ENVIRONMENTAL MONITORING SUMMARIES AND ANALYSIS A. Cultural Resources Section 4.2.1 of the EPP requires that an archaeological survey be performed when final alignment of the PVNGS-to-Saguaro transmission line is completed.

As of the date of this report, plans for this transmission line have been indefinitely suspended.

Therefore, there has been no activity with regard to this requirement of the EPP.B. Terrestrial Ecology Monitoring As communicated in a letter from William F. Conway, APS, to NRC, dated December 30, 1991, the salt deposition monitoring program was discontinued at the end of 1991.II1. PLANT DESIGN AND OPERATION CHANGES Section 3.1 of the EPP allows changes in station design or operation or the performance of tests or experiments affecting the environment provided that such changes, tests, or experiments do not involve an unreviewed environmental question and do not involve a change to the EPP. Changes, tests, or experiments in which all measurable non-radiological effects are confined to the on-site areas previously disturbed during site preparation and plant construction or in which the environment is not affected are exempt from the evaluation and reporting requirements of Section 3.1.Section 3.2 of the EPP also exempts changes, tests, or experiments, which are required to comply with other Federal, State, or local environmental regulations.

No design and operational changes were initiated in 2008 that required an evaluation to determine if they involved either an unreviewed environmental question or constituted a change in the EPP.IV. EPP NON-COMPLIANCES There were no instances of non-compliance with the EPP identified during 2008.V. NON-ROUTINE REPORTS There were no non-routine reports required by Section 5.4.2 of the EPP submitted during 2008.

ML091270389

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Dear Sirs:

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