Text

Core Operating Limits Report, Revision 26
	ML19297E724
Person / Time
Site:	Palo Verde
Issue date:	10/24/2019
From:	Dilorenzo M; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-08002-MDD/TMJ
	Download: ML19297E724 (31)
	v • d • e

Oaps Technical Specification 5.6.5.d Palo Verde Nuclear Generating Station 5871 S. Wintersburg Road Tonopah, AZ 85354 102-08002-MDD/TMJ October 24, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station Unit 3 Docket No. STN 50-530 Core Operating Limits Report, Revision 26

Dear Sirs:

Pursuant to Palo Verde Nuclear Generating Station (PVNGS) Technical Specifications, Section 5.6.5.d, enclosed is the Unit 3 Core Operating Limits Report, Revision 26, which was made effective October 23, 2019. Figure 3.2.4-2 was updated in this revision. A revision bar has been applied to the change.

No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Michael D. DiLorenzo, Licensing Department Leader, at (623) 393-3495.

Sincerely, Michael D. DiLorenzo Nuclear Regulatory Affairs Department Leader MDD/TMJ/mg

Enclosure:

PVNGS Unit 3 Core Operating Limits Report, Revision 26 cc:

S. A. Morris S. P. Lingam C. A. Peabody NRC Region IV Regional Administrator NRC NRR Project Manager for PVNGS NRC Senior Resident Inspector for PVNGS A member of the STARS Alliance LLC Callaway

Diablo Canyon

Palo Verde

Wolf Creek

Enclosure PVNGS Unit 3 Core Operating Limits Report Revision 26

PALO VERDE NUCLEAR GENERATING STATION (PVNGS)

UNITS CORE OPERATING LIMITS REPORT Revision 26 Effective October 23,2019 Responsible Engineer Date U

^ 4-D ^ U

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naUpi/ nUU DN;cn>>Haupt.Rob(Z14254}

Reason: 1 am the dependent engineer for fVl thlsdocument Date:20t9.10.1714J7:12-07'00 r^oic-ylor l^olK/

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VJd^Z.ld/ IXCliy ON;cn-Geiszler,KellyJ(Z07064)

Reason:! am signing as the RE of this J(Z07064)

Date: 2019.10.17 14:33J8-0r00-Independent Reviewer Date

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Digitally signed by Cowdin, L. 0 WQ 1 n,

Christopher £Z12133)

DN: cn=Cowdin, Christopher ChriStOphe IfS have reviewed this document r(Z12133) °;ej019.,0.17,7:,2:45 Responsible Section Leader Date 1/ -s le 1 <-.n. M Digitally signed by Karlson, l\\d n SO n, Charles F(V55086)

DN: cn=Karlson, Charles rkarlpQ V-1 1 a 1 1^0 Reason: 1 am approving thi document F(V55086)

Page 1 of29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 Table of Contents Description Cover Page Table of Contents List of Figures List of Tables Affected Technical Specifications Analytical Methods Page 1

2 3

4 5

6 CORE Operating Limits 3.1.1 Shutdown Margin (SDM) - Reactor Trip Breakers Open 11 3.1.2 Shutdown Margin (SDM) - Reactor Trip Breakers Closed 11 3.1.4 Moderator Temperature Coefficient (MTC) 11 3.1.5 Control Element Assembly (CEA) Alignment 11 3.1.7 Regulating CEA Insertion Limits 11 3.1.8 Part Strength CEA Insertion Limits 12 3.2.1 Linear Heat Rate (LHR) 12 3.2.3 Azimuthal Power Tilt (Tq) 12 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) 12 3.2.5 Axial Shape Index (ASI) 13 3.3.12 Boron Dilution Alarm System (BDAS) 13 3.9.1 Boron Concentration 13 Page 2 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 List of Figures Description Figure 3.1.1-1 Figure 3.1.2-1 Figure 3.1.4-1 Figure 3.1.5-1 Figure 3.1.7-1 Figure 3.1.7-2 Figure 3.1.8-1 Figure 3.2.3-1 Figure 3.2.4-1 Figure 3.2.4-2 Figure 3.2.4-3 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)

Page 14 16 17 18 20 21 22 23 Page 3 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 List of Tables Description Table 3.3.12-1 Table 3.3.12-2 Table 3.3.12-3 Table 3.3.12-4 Table 3.3.12-5 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Kefl> 0.98 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.98 > Keff > 0.97 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.97 > Keff > 0.96 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for 0.96 > Keff > 0.95 Required Monitoring Frequencies for Backup Boron Dilution Detection as a Function of Operating Charging Pumps and Plant Operational Modes for Keff < 0.95 Page 25 Page 4 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 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 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 Coelficient (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 of29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 ANALYTICAI. METHODS The COLR contains the complete identification for each of the Technical Specification referenced topical reports (i.e., report number, title, revision, date, and any supplements) and correspondence that provide the NRC-approved analytical methods used to determine the core operating limits, described in the following documents:

T.S Ref#^

Title Report No.

Rev Date Suppl 1

CE Method for Control Element Assem bly Ejection Analysis (NOO1-1301-01204)

CENPD-0190-A N.A.

Januaiy 1976 N.A.

2 The ROCS and DIT Computer Codes for Nuclear Design (NOOl-1900-01412)

CENPD-266-P-A N.A.

April 1983 N.A.

3 Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No. STN 50-470 NUREG-0852 N.A.

November 1981 March 1983 September 1983 December 1987 N.A.

1 2

3 4

Modified Statistical Combination of Uncertainties (NOOl-1303-01747)

CEN-356(V)-P-A 01-P-A May 1988 N.A.

4 System 80' Inlet Flow Distribution (NOOl-1301-01228)

Enclosure 1-PtoLD-82-054 N.A.

February 1993 1-P 5

Calculative Methods for the C-E Large Break LOCA Evaluation Model CENPD-132P N.A.

August 1974 N.A.

5 Calculational Methods for the C-E Large Break LOCA Evaluation Model CENPD-132P N.A.

February 1975 1

5 Calculational Methods for the C-E Large Break LOCA Evaluation Model CENPD-132-P N.A.

July 1975 2-P 5

Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS CENPD-132 N.A.

June 1985 3-P-A Page 6 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 T.S Ref#^

Title Report No.

Rev Date Suppl 5

Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (NOOl-1900-01192)

CENPD-132 N.A.

March 2001 4-P-A Rev. 1 5

Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model (NOO1-0205-00046)

CENPD-132 N.A.

August 2007 4-P-A Adde ndum 1-P-A 5

Revision 4 to the Supplement to Appen dix A of CENPD-132 Supplement 4-P-A (NOO1-0205-00229)

CENPD-132 N.A.

December 2008 SUPP 4-P-A APP A-REV 004 6

Calculative Methods for the C-E Small Break LOCA Evaluation ModeL CENPD-137-P N.A.

August 1974 N.A.

6 Calculative Methods for the C-E Small Break LOCA Evaluation Model CENPD-137 N.A.

January 1977 1-P 6

Calculative Methods for the ABB C-E Small Break LOCA Evaluation Model (NOOl-1900-01185)

CENPD-137 N.A.

April 1998 2-P-A 7

Letter: O.D. Parr (NRC) to F. M. Stem (CE), (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for:

5.6.5.b.6.

N.A.

June 13, 1975 N.A.

8 Letter: K. Kniel (NRC) to A. E. Scherer (CE), (Evaluation of Topical Reports CENPD 133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for 5.6.5.b.6.

N.A.

September 27, 1977 N.A.

9 Fuel Rod Maximum Allowable Pressure (NOO 1-0201-00026)

CEN-372-P-A N.A.

May 1990 N.A.

Page 7 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 T.S Ref#

Title Report No.

Rev Date Suppl 10 Letter: A. C. Thadani (NRC) to A. E.

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

N.A.

April 10, 1990 N.A.

11 Arizona Public Service Company PWR Reactor Physics Methodology Using CASMO-4/S1MULATE-3 (NFM-005)

NFM-005 1

August 2007 N.A.

12 Technical Description Manual for the CENTS Code Volume 1 (CENTS-TD MANUAL-VOL 1)

CE-NPD 282-P-A Vols. 1 2

March 2005 N.A.

12 Technical Description Manual for the CENTS Code Volume 2 (CENTS-TD MANUAL-VOL 2)

CE-NPD 282-P-A Vols. 2 2

March 2005 N.A.

12 Technical Description Manual for the CENTS Code Volume 3 (CENTS-TD MANUAL-VOL 3)

CE-NPD 282-P-A Vols. 3 2

March 2005 N.A.

13 Implementation of ZIRLO' Cladding Material in CE Nuclear Power Fuel Assembly Designs (NOOl-1900-01329)

CENPD-404-P-A 0

November 2001 N.A.

13 Optimized ZIRLO^*^

(NOO1-0203-00611)

CENPD-404-P-A Addendum 1-A 0

July 2006 N.A.

13 Westinghouse Clad Corrosion Model for ZIRLO and Optimized ZIRLO' (NOO 1-0205-00006)

CENPD-404-P-A Addendum 2-A 0

October 2013 N.A.

14 HERMITE, A Multi-Dimensional Space-Time Kinetics Code for PWR Transients (HERMITE-TOPICAL)

CENPD-188-A N.A.

July 1976 N.A.

15 TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core (NOOl-1301-01202)

CENPD-161-P-A N.A.

April 1986 N.A.

Page 8 of29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 Ref#^

Title Report No.

Rev Date Suppl CETOP-D Code Structures and Model ing Methods for San Onofre Nuclear Generating Station Units 2 and 3 (NOOl-1301-01185)

CEN-160(S)-P 1-P September 1981 N.A.

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

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

N.A.

September 29,2003 November 16,2005 N.A.

CPC Methodology Changes for the CPC Improvement Program (NOOl-1303-02283)

CEN-3I0-P-A April 1986 N.A.

Loss of Flow, C-E Methods for Loss of Flow Analysis (NOOl-1301-01203)

CENPD-183-A June 1984 N.A.

Methodology for Core Designs Contain ing Erbium Burnable Absorbers (NOOl-0201-00035)

CENPD-382-P-A August 1993 N.A.

Verification of the Acceptability of a 1-Pin Bumup Limit of 60 MWD/kgU for Combustion Engineering 16x16 PWR Fuel (NOOl-0201-00042)

CEN-386-P-A August 1992 N.A.

CE 16x16 Next Generation Fuel Core Reference Report (NOOl-0203-00614)

WCAP-16500-P-A August 2007 N.A.

Page 9 of29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 T.S Ref#^

Title Report No.

Rev Date Suppl Application of CE Setpoint Methodol ogy for CE 16x16 Next Generation Fuel (NGF)

(NOO1-0205-00063)

WCAP-16500-P-A December 2010 1

Rev 1 Evolutionary Design Changes to CE 16x16 Next Generation Fuel and Method for Addressing the Effects of End-of-Life Properties on Seismic and Loss of Coolant Accident Analysis (NOO 1-0205-00048)

WCAP-16500-P-A June 2016 2-P-A VIP RE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Thermal-Hydraulic Safety Analysis (NOO1-0205-00002)

WCAP-14565-P-A October 1999 N.A.

Addendum 1 to WCAP-14565-P-A Qualification of ABB Critical Heat Flux Correlations with VIPRE-01 Code (NOO1-0205-00003)

WCAP-14565-P-A, Addendum 1-A August 2004 N.A.

Addendum 2 to WCAP-14565-P-A, Extended Applications of ABB-NV Cor relation and Modified ABB-NV Correla tion WLOP for PWR Low Pressure Applications (NOO 1-0205-00004)

WCAP-14565-P-A, Addendum 2-P-A April 2008 N.A.

ABB Critical Heat Flux Correlations for PWR Fuel (NOO1-0205-00042)

CENPD-387-P-A May 2000 N.A.

Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Sup ported Mixing Vanes (NOO1-0203-00615)

WCAP-16523-P-A August 2007 N.A Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs (NOO 1-0205-00226)

WCAP-16072-P-A August 2004 N.A.

a. Corresponds to the reference number specified in Technical Specification 5.6.5 Page 10 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 The cycle-specific operating limits for the specifications listed are presented below.

3.1.1 - Shutdown Margin tSDM) - 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 rSDMl - 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 TMTO 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-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 limits^ shown in Figure 3.1.7-!^; with COLSS OUT OF SERVICE, regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits' shown in Figure 3.1.7-2.^

Regulating Groups 1 and 2 CEAs shall be maintained > fully withdrawn' ^ while in Modes 1 and 2 (except while performing SR 3.1.5.3). When > 20% power Regulating Group 3 shall be maintained > fully withdrawn.' ^

' 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 OPERATfNG 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 .

'y 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.

Page 11 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 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).

^ Fully withdrawn (FW) is defined as >147.75 (Pulse Counter indication) and

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

3.1.8 - Part Strength CEA Insertion Limits The part strength CEA groups shall be limited to the insertion limits shown in Figure 3.1.8-1.

3.2.1 - Linear Heat Rate (THRI The linear heat rate limit of 13.1 kW/ft shall be maintained.

3.2.3 - Azimuthal Power Tilt (Tgl 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 tPNBRf 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 12 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 3.2.5 - Axial Shape Index ('ASP 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 (BDASl 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 13 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 nGURE3.1.1-l SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS OPEN I£ 4 soe;<S i I

i j I j j i

1 j

j j

1 (500.5.0 R£ AC OP GION OF p:PTABLl

^RATION

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-11///

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1 /

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i i

1 i/

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J REGION UNACCB OF jPTABLE

.................................................................................................!............................................................................../*'

1 /

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OPERAlION I (350.1.0)

I 100 200 300 400 COLD LEG TEMPERATURE (F) 500 600 Page 14 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 nGURE3.1.2-l SHUTDOWN MARGIN VERSUS COLD LEG TEMPERATURE REACTOR TRIP BREAKERS CLOSED o

C£

<2 (500,6.5)

RE AC GION OF CEPTABLl OPEration (350,4.0)

REGION 0 UNACCEF k

rABLE OPERATIC)N 0

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

Page 15 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 FIGURE 3.1.4-1 MTC ACCEPTABLE OPERATION, MODES 1 AND 2 (0%,0.j)

(50%, O.O) 2 -10 MTGAREAOF i lACCEPTABLE OPERATION CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Maintain Operation within Boundary TECH SPEC 3.1.4 Maximum Upper Limit Page 16 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 nGURE3.1.5-l CORE POWER REDUCTION AFTER CEA DEVIATION*

^100% to

>80% RTP 570% to

>45% RTP TIME AFTER DEVIATION. MINUTES

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

NO POWER REDUCTION IS REQUIRED FOR A SINGLE CEA MISALIGNMENT IF THE FOLLOWING CONDITIONS ARE CONTINUOUSLY MET FROM THE TIME OF DEVIATION:

- > 95 % RATED THERMAL POWER

- COLSS IN SERVICE AND CEACS IN SERVICE

- AZIMUTHAL POWER TILT IS LESS THAN 3.0 %

- ALL CEAS REMAIN ABOVE 142.5" WITHDRAWN BY PULSE COUNTER AND ABOVE 140.1" WITHDRAWN BY RSPT INDICATION Page 17 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 nGURE3.1.7-l CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS IN SERVICE) 0.9 2

i.

s I

oz s

0.0 NOTE:

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

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

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

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

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

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

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

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

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

TIL5 = (172.5" X Fractional Power) - 64.5" (for power > 3739% and < 100%).

I..

i..

1*

I I 1 I I I GROUPS I-1-

1-1-

1_

GROUPS

-I

-I-GROUPl ISO* 120 90 60 30 0 ISO* 120 90 60 30 0 ISO* 120 90 60 30 0

GROUP4 GROUP2 I--- 1----1----1-- 1---- 1 I---- 1--- 1-- 1--- 1---- 1 ISO* 120 90 60 30 0 ISO* 120 90 60 30 0

CEA POSmON (INCHES WITHDRAWN)

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

No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.

Page 18 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 FIGURE 3.1.7-2 CEA INSERTION LIMITS VERSUS THERMAL POWER (COLSS OUT OF SERVICE) 0.8 0.7 2

I uu0 1

0.0

<<fSg-s NOTE:

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

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

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

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

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

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

CEA Group 4 must be withdrawn > the group 4 TIL (TTL4) as indicated on the graph or by the equation:

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

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

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

TIL5 = 108" (for power lever > 75.00%).

- - 1........................>

GROUPS -- 1-- -I-GROUP3

-II----1 GROUPl 150* 120 90 60 30 0 150* 120 90 60 30 0 150* 120 90 GROUP4 GROUP2

-I----1----1----1---- 1 I----1---- 1-----1----1 1

-I 60 30 0

150* 120 90 60 30 0 150* 120 90 60 30 0

CEA POSITION (INCHES WITHDRAWN)

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

No further CEA withdrawal above FW is required for CEAs to meet the TIL requirements.

Page 19 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 nGURE3.1.8-l PART STRENGTH CEA INSERTION LIMITS VERSUS THERMAL POWER 0.0 10.0 20.0 30.0 40.0 50.0 60.0 Z

70.0 o

B g

80.0 oz 90.0 100.0 in

<< 110.0 120.0 130.0 140.0 150.0 j

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LorigterMsteaDY STATE IN^RTIOI^ LIMTlis (112.5

.1 5) pPER

! U i <

I o 0.8 0.7 0.6 0.5 0.4 0.3 0.2 FRACTION OF RATED THERMAL POWER 0.0 Page 20 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 HGURE 3.2.3-1 AZIMUTHAL POWER TILT VERSUS THERMAL POWER (COLSS IN SERVICE) 20.0 15.0 O 10.0 REGIONGF UNACCEPTABLE OPERATION REGION OF ACCEPTABLE OPERATION 0.0 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 21 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 FIGURE 3.2.4-1 COLSS DNBR OPERATING LIMIT ALLOWANCE FOR BOTH CEACs INOPERABLE IN ANY OPERABLE CPC CHANNEL (95.20)

CORE POWER LEVEL

(% OF RATED THERMAL POWER)

Page 22 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 HGURE 3.2A-2 DNBR MARGIN OPERATING LIMIT BASED ON THE CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE, CEAC(s) OPERABLE)

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

ACCEPTABLE OPERATION POWER AT OR ABOVE 90%

AT LEAST 1 CEAC OPERABLE IN EACH OPERABLE CPCCPANNEL (0.08,2.07)

, (0.1,2.07)

UNACCEPTABLE rOPERATIGN CORE AVERAGE ASI Page 23 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 HGURE 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)

ACCEPTABLE OPERATION ANY POWER LEVEL BOTH CEACs INOPERABLE

...............................<.....................................}..............................................................

IN ANY OPERABLE CPC CHANNEL (0.1,3.41)

(-0.1,3.27)

UNACCEPTABLE OPERATION CORE AVERAGE ASI Page 24 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 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 K^ff> 0.98 OPERATIONAL MODE Number of Operating Charging Pumps 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 25 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 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 > Ke^ > 0.97 OPERATIONAL MODE Number of Operating Charging Pumps 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 26 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 Table 3.3.12-3 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CFIARGING PUMPS AND PLANT OPERATIONAL MODES FOR 0.97 > Ke^ > 0.96 OPERATIONAL MODE Number of Operating Charging Pumps 0

I 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 I 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 I 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 I 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 I hour ONA ONA Notes:

SCS = Shutdown Cooling System ONA = Operation Not Allowed Page 27 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 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 > K^ff> 0.95 OPERATIONAL MODE Number of Operating Charging Pumps 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 28 of 29

PVNGS UNIT 3 CORE OPERATING LIMITS REPORT Revision 26 Table 3.3.12-5 REQUIRED MONITORING FREQUENCIES FOR BACKUP BORON DILUTION DETECTION AS A FUNCTION OF OPERATING CFIARGING PUMPS AND PLANT OPERATIONAL MODES FOR Keff < 0.95 OPERATIONAL MODE Number of Operating Charging Pumps 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 29 of 29

ML19297E724

Text

Subject:

Dear Sirs:

Enclosure:

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