Text

Palo Verde Unit 1, Core Operating Limits Report - Revision 21
	ML101530487
Person / Time
Site:	Palo Verde
Issue date:	05/21/2010
From:	Weber T N; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-06195-TNW/KAR
	Download: ML101530487 (28)
	v • d • e

Technical Specification 5.6.5 d kFAM Palo Verde Nuclear Generating Station Thomas N Weber Department Leader, Regulatory Affairs Mail Station 7636 Tel. 623-393-5764 PO Box 52034 Fax 623-393-5442 , ,i'Phorenix, Arizona 85072-2034 102-061 May 21,20 ,, ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Dear Sirs:

.

Subject:

Palo Verde Nuclear Generating Station (PVNGS) ,Unit ,1, Docket-No.

STN 50-528 Core Operating Limits'Report (COLR),- UnitlI -Revision 21'I -Pursuant to PVNGS Technical Specifications, Section 5.6.5 d, enclosed is Core Operating Limits Report (COLR), Uhit1 Revision k21, which was made effective April 22, 2010. This revision includes changes to the Moderator Temperature Coefficient (MTC) limits for Technical Specification (TS) 3.1.4 and updated the list of Analytical Methods.By copy of this letter and enclosu~re;;this COLR revision is, being'1provided to the NRC Region IV Administrator and the PVNG-S Senrior Resident n1nsppctor2.

No commitments are being madeeto the NRC by'this-letter,.

Shduld you need further information regarding this submittal,, please contact Russell A., Stroud- Licensing Section Leader, at (623) 393-51 1.1-incerely.,, TNW/RAS/KAR/gat

Enclosure:

PVNGS Unit 1 Core Operating Limits Report (COLR), Revision 21 cc: E. E. Collins Jr.., J. R. Hall L. K. Gibson R. I. Treadway ,NRC. Region. IV Regional Administrator NRC NRR Project Manager NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS (STARS (Strategic Teaming and Resource Sharing) Alliance j A member of the Enclosure PVNGS Unit I Core Operating Limits Report (COLR)Revision 21 PALO VERDE NUCLEAR GENERATING STATION (PVNGS)UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 Effective April 22, 2010 Respo Eginr T b" Digitally signed by Trimble, Responsible Engineer T hi Trimble, Patrick C(Z95337)Date DN: cn=Tdmble, Patrick C Date~~ý: Parc C (.:-Z95337)

PatrickO Reason: I am the author of (Z 53)--I-Tent Date: 2010.04.16 15:49:06-07'00'Independent Reviewer Digitally signed by Wenzel, ItWenzel, Richard R(Z99534)Date DN: cn=Wenzel, Richard R-,, .P..J 'z99534)Richard R Reason: I have reviewed this; , docuenii it~(7.9.O 3,A.) Date: 260.04.16 15:52:47 ( 5 .. .' -07'00'Digitally signed by Rowland, Responsible Section Leader Wla d James W(Z80533)Date W ,,(Z80533)

James V ýReason: I am approving this document as the Responsible-yg~ra-,~v~

Stion Le~der (Z805313 Date: 2010.04.16 16:29:24-07'00'Page 1 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT.Revision 21 Table of Contents Description Page Cover Page 1 Table of Contents 2 List of Figures 3 List of Tables 4 Affected Technical Specifications 5 Analytical Methods 6 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) -Reactor Trip Breakers Open 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 1 CORE OPERATING LIMITS REPORT Revision 21 List of Figures Description Figure 3.1.1-!Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.t.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 Page I1I Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Open Shutdown Margin Versus Cold Leg Temperature Reactor Trip Breakers Closed MTC Acceptable Operation, Modes 1 and 2 Core Power Limit After CEA Deviation CEA Insertion Limits Versus Thermal Power (COLSS in Service)CEA Insertion Limits Versus Thermal Power (COLSS Out of Service)Part Strength CEA Insertion Limits Versus Thermal Power Azimuthal Power Tilt Versus Thermal Power (COLSS in Service)COLSS DNBR Operating Limit Allowance for Both CEACs Inoperable In Any Operable CPC Channel DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, CEAC(s)Operable)DNBR Margin Operating Limit Based on the Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable In Any Operable CPC Channel)12 13 14 15 16 17 18 19 20 21 Page 3 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Table 3.3.12-4 Table 3.3.12-5 Page 22 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff> 0.98 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff > 0.96 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff> 0.95 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 23 24 25 26 Page 4 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 This Report has been prepared in accordance with the requirements of Technical Specification 5.6.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Section 5.6.5 b of the Palo Verde Unit 1 Technical Specifications.

AFFECTED PVNGS TECHNICAL SPECIFICATIONS

3.1.1 Shutdown

Margin (SDM) -Reactor Trip Breakers Open 3.1.2 Shutdown Margin (SDM) -Reactor Trip Breakers Closed 3.1.4 Moderator Temperature Coefficient (MTC)3.1.5 Control Element Assembly (CEA) Alignment 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Strength CEA Insertion Limits 3.2.1 Linear Heat Rate (LHR)3.2.3 Azimuthal Power Tilt (Tq)3.2.4 Departure From Nucleate Boiling Ratio (DNBR)3.2.5 Axial Shape Index (ASI)3.3.12 Boron DilutionAlarm System (BDAS)3.9.1 Boron Concentration Page 5 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 ANALYTICAL METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:

Title Report No. Rev Date Suppl CE Method for Control Element Assembly CENPD- N.A. January N.A.Ejection Analysis 0190-A 1976 (13-N001-1301-01204-1)

The ROCS and DIT Computer Codes for CENPD- N.A. April N.A.Nuclear Design 266-P-A 1983 (13-NO01-1900-01412-0)

Modified Statistical Combination of CEN- 01-P-A May N.A.Uncertainties 356(V)-P-A 1988 (13-NOO1 -1303-01747-2)

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

Calculative Methods for the CE Small Break CENPD- N.A. April 2-P-A LOCA Evaluation Model 137-P 1998 (13-NOO1 -1900-01185-3)

Fuel Rod Maximum Allowable Pressure CEN-372- N.A. May N.A.(13-NOO1-0201-00026-1)

P-A 1990 Arizona Public Service Company PWR Reactor NFM-005 1 August N.A.Physics Methodology Using 2007 CASMO-4/SIMULATE-3 (NFM-005)Technical Description Manual for the CENTS CE-NPD 2 March N.A.CodeVolume 1 282-P-A 2005 (CENTS-TD MANUAL-VOL

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

2) Vols. 2 I Page 6 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 Title Report No. Rev Date Supp Technical Description Manual for the CENTS CE-NPD 2 March N.A.CodeVolume 3 282-P-A 2005 (CENTS-TD MANUAL-VOL

3) Vols. 3 Implementation of ZIRLOTM Cladding Material CENPD- 0 November N.A.in CE Nuclear Power Fuel Assembly Designs 404-P-A 2001 (13-NO01--1900-01329-0)

HERMITE, A Multi-Dimensional Space-Time CENPD- July Kinetics Code for PWR Transients 188-A 1976 (HERMITE-TOPICAL)

TORC Code, A Computer Code for Determin-CENPD- April ing the Thermal Margin of a Reactor Core 161-P-A 1986 (NOO-1301-01202)

CETOP-D Code Structures and Modeling Meth- CEN- 1-P September ods for San Onofre Nuclear Generating.Station 160(S)-P 1981 Units 2 and 3, (NOO-1301-01185)

CPC Methodology Changes for the CPC CEN-3 10- 0 April Improvement Program, (NOO 1-1303-02283)

P-A 1986 Loss of Flow, C-E Methods for Loss of Flow CENPD- June Analysis, (NOO1-1301-01203) 183-A 1984 Methodology for Core Designs Containing CENPD- 0 August Erbium Burnable Absorbers 382-P-A 1993 (N001-0201-00035)

Verification of the Acceptability of a 1-Pin Bur- CEN-386- 0 August nup Limit of 60 MWD/kgU for Combustion P-A 1992 Engineering 16 x 16 PWR Fuel (NOO 1-0201-00042)

I Page 7 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 The cycle-specific operating limits for the specifications listed are presented below.3.1.1 -Shutdown Margin (SDM) -Reactor Trip Breakers Open The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.1-1.3.1.2 -Shutdown Margin (SDM) -Reactor Trip Breakers Closed The Shutdown Margin shall be greater than or equal to that shown in Figure 3.1.2-1.3.1.4 -Moderator Temperature Coefficient (MTC)The moderator temperature coefficient (MTC) shall be within the area of Acceptable Operation shown in Figure 3.1.4-1.3.1.5 -Control Element Assembly (CEA) Alignment With one or more full-strength or part-strength CEAs misaligned from any other CEAs in its group by more than 6.6 inches, the minimum required MODES 1 and 2 core power reduction is specified in Figure 3.1.5-1. The required power reduction is based on the initial power before reducing power.3.1.7 -Regulating CEA Insertion Limits With COLSS IN SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limitsI shown in Figure 3.1.7-12; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion 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).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 1 CORE OPERATING LUMITS REPORT Revision 21 c) Both Regulating Group 4 and Regulating Group 5 positions are maintained above the Transient Insertion Limit specified in Figure 3.1.7--i (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 1 CORE OPERATING LIMITS REPORT Revision 21 3.2.5 -Axial Shape Index (ASI)The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits: COLSS OPERABLE-0.18 < ASI< 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%313.12 -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 1 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.1-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN 7 6 5 z 0 3 2 0 0 100 200 300 400 500 COLD LEG TEMPERATURE

(*F)600 Page 11 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.2-1 SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED/6 5 4 z 0 3 2 0 REGION OF ACCEPTABL]-OPERATION

... ...... ...I (500 (350,4.0),; , .,.............

......'REGION OF UVNACCEPTABLE

........ .. ... ... .. .. -- ------ -----..... .... .... .... ...-OPERATION-.------------------------------------................I ..i i i i i i i i i i i m i i ............0 100 200 300 400 COLD LEG TEMPERATURE (fF)500 600 Page 12 of 26 1*.PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 CL 10 0 2 0.5 0.0-0.5-1.0-1.5-2.0-2.5-3.0-3.5-4.0-4.5 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES I AND 2-..,...,,'........

d,... .... ,.....i............

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

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

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

.'+ ....... ...0. .% , .:.10%-02............

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

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

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

_ ...,..... ..............

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

T ..........

ACCEPTAB\IJEF OPF R.TION........ .... *.............

".............

"........................................................-

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

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

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

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

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

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

T............ ,T ...........

(0o%.-4.4)

"(0%.-4 ,4 ' i : i i h f l

i i -I -I I L JLI I +/- +/- I I LIL[ I .Lt.LJl J LL.L+/- I L.L.l I i LL. iL+/- I L.LLL.LL.L.L.i .L 0 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL (% OF RATED THERMAL POWER)Maintain Operation within Bounday -TECH SPEC 3.1.4 Maximum Uppea Limit ........Page 13 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT FIGURE 3.1.5-1 Revision 21 CORE POWER REDUCTION AFTER CEA DEVIATION*

-...-. 20 20..............

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

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

.15 I ....z 0 L 0 RI 10 5......................

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

1100% to>80% RTP 12 12 :<80% to>70% RTP 9-- -------------------........8 -70% to>45% RTP----- ----- .. ..... ..... ..... ..... ....15 10 5 4-------------

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

0 10 20 30 40 50 60 TIME AFTER DEVIATION, MINUTES* WHEN CORE POWER IS REDUCED TO 35% OF RATED THERMAL POWER PER THIS LIMIT CURVE. FURTHER REDUCTION IS NOT REQUIRED.Page 14 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.7-1 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE)1.0 0.9 0.8.0.7 0.6 0.5 0 Z 0.4 U 0.3 0.2 0.1 Nfi Z. 0i I I I I I I I I I I--(SEE FOOTNOTE IN SECTION-317

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

7 .FOR APPLICABILITY FOLLOWING:

ARECTORCUTACKJ

-GRP 4 P0S= (172-5 Ix FRAC. -PWR)-+-25.5

.......255 GRP 5POS =(172.5 x FRAC. PWR') -64.5.. °. ..... ......... ,.................

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

-- ---- ---....... ......... .......... ..... .................. ..... ......... .. ... .. .. .... .. .. .... .. .... ..... ... ---....-------------------* *!~---I I L I GROUP5 GROUP3 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 FtI!09+06+

3+0 Fý ot1 6+0 t'CEA POSITION (INCHES WITHDRAWN)

Fully Withdrawn (FW) is defined as > 147.75" (Pulse Counter) and > 145.25" (RSPT).Page 15 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE)1.0 0.9 0.8" 0.7 2 0.6 05 z 0.4 t 0.3 0.2 0.1 n n.....~ ~ ~ ~ ~ ~ ~ ~ ~ ~- -------- ------- --........--.............-.....--........-

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

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

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

...-----(SE E -F O O T N O TE -IN: -S E C T IO N -3 , ,7 .. ..7 ..FOR APPIACABILITY FOLLOWING A. REACTOR CUTBACIK)..

k i-- -- -- -- ...............

v .? .A?.C1...... GRP4POS-=(2O.9 0;9FRA-C.PWRy+-9.82-SGR P0os8 (20.9 PWR -80118....... .. ... ... .......... ........ .... .... ' ....... .......

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

........ ....... .......z-- --- --- --........ -- -- --- --.- ----- ---- ---.- ----.- --.. ... ...o g~z.................

........ : L....-- --- --- ------ ...........

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

......L........

.........kJ GROUP5 GROUP3 GROUP 1! 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 CE 1A0 9P0 610O 3+0 ( Ft ItE 0 j0 6I0 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 1 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.1.8-1 PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER z u C7~0 I-z 0.0 10.0 20.0 30.0 40.0 50.0 60.0 70.0 80.0 90.0 100.0 110.0 120.0 130.0 140.0 150.0.. ... .......I .. ......... ........... .....OPERA.T.ION.........................

UNACCEPTABLE

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

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

!.............

...........

..r.. ..............

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

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

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

,.............

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

,............

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

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

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

.............-TRANSIE.T rNSE.RTION LIMIT (75.0:INCHES)

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

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

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

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

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

O PEI- -T IO N .............

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

RESTRICTED

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

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

...........

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

LONG TERM STEADY STATE INSERTION:LIMITS:

(112.5 INCHES)...........

O P E R A TI O N A C P B E ---- --- -- -.............

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

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

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

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

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

--------..

OPERATION ACCEPTABLE

.... ..I .........I.. ..I.. ...... ...I.. ..I ... .... I .. .-- -I-- --------------1 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 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE)20.0 15.0 0 ,.2 ,-.10.0--------- ------ ---- ---------REGION OF i...I ...I .... .1..REGION--OF.-

UNACCEPTABLE OPERATION 5.0 LCCEPTABLE OPERATION.. .I ...I ........ ..u.u 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 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL Revision 21 25 20 z 0 z<02 15 I0----------

60..........................

(95,20)5 0 , ,... .... .... .....7 o .... .... .... ..-- -- --.- -- -:(80,5)(70 0): 70 80 CORE POWER LEVEL (% OF RATED THERMAL POWER)50 90 100 Page 19 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.2.4-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)2.5 2.4 2.3 2.2 2.1 u-P,......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):

(-9.1.2.28)

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

.....

..........

= .....................................................

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

....-: ACCEPIABLE OPERATION POWER AT OR ABOVE 90%AT LEAST 1 CEAC OPERABLE IN.... EACH OPERABLE-CPC CIIANNEL ..............

* (0.06,2.00)

(0193)UNACCEPTABLE

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

....O P E RZA T IO N ...- -- -- ----- ---.. ...........2.0 1.9 1.8-0.20 -0.15 -0.10 -0.05 0.00 0.05 CORE AVERAGE ASI 0.10 0.15 0.20 Page 20 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 FIGURE 3.2.4-3 DNBR MARGIN"OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL)3.6 .........

r .........

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

ACCEPTABLE OPERATION ANY POWER IEVEL BOTH CEACs INOPERABLE 3.5 -.-----.-.

---.------

.........

........ .......... A Y O E B ~ ~ ..............................

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

IN ANY OPERABLE CPC CHANNEL 3 .4 -------- ...... .. ....... -------------

...........

...... .._ ....(0 .................

z u (-0.1,3.27) 3 .2 ....... .... ..... .... .. ... ..... ... ..... ..... ...... .. .. ...........

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

-- -------.. .. .. .... .. .. ..... .. .. .. .. .. .... .UNACCEPTABLE OPERATION 3 .1 -- -- --- ---..... ..........

.. ................,. ......... ..................._3.0 ' ,,,......

........ ....... .! .........

I.........

I....-0.20 -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 1 CORE OPERATING LIMITS REPORT Revision 21 Table 3.3.12-1 REQUIRED MONITORINGFREQUENCIESFOR

.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 1 CORE OPERATING LIMITS REPORT Revision 21 Table 3.3.12-2 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.98 > Keff> 0.97 OPERATIONAL Number of Operating Charging Pumps MODE .0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1 hour 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 23 of 26 4 1~PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Table 3.3.12-3 Revision 21 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 1 CORE OPERATING LIMITS REPORT Revision 21 Table 3.3.12-4 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.96 > Keff> 0.95 OPERATIONAL Number of Operating Charging Pumps MODE 0 1 2 3 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3 hours 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4 not on SCS 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 5 not on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months 4 & 5 on SCS 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ONA Notes: SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 25 of 26 PVNGS UNIT 1 CORE OPERATING LIMITS REPORT Revision 21 Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CHARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff < 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

ML101530487

Text

Dear Sirs:

Subject:

Enclosure:

3.1.1 Shutdown

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