ML13073A140

San Onofre Nuclear Generating Station, Core Operating Limits Report for Unit 2 Cycle 17 and Unit 3 Cycle 16

ML13073A140
Person / Time
Site:	San Onofre
Issue date:	02/15/2013
From:	Onge R J Edison International Co, Southern California Edison Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC ME0604, TAC ME0605
Download: ML13073A140 (42)

Text

J SOUTHERN CALIFORNIA EDISON°An EDISON INTERNATIONAL&

Company Richard l. St. Onge Director, Nuclear Regulatory Affairs and Emergency Planning 10 CFR 50.4 February 15, 2013 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Docket Nos. 50-361 and 50-362 Core Operating Limits Report San Onofre Nuclear Generating Station, Units 2 and 3

References:

1) NRC letter from James R. Hall (NRC) to Ross T. Ridenoure, dated December 15, 2009, San Onofre Nuclear Generating Station, Units 2 and 3 -Issuance of Amendments Revising Technical Specification 5.7.1.5, "Core Operating Limits Report (COLR)" (TAC NOS. ME0604 and ME0605)

Dear Sir or Madam:

The Core Operating Limits Report (COLR) for Unit 2 Cycle 17 and Unit 3 Cycle 16 for the San Onofre Nuclear Generating Station (SONGS) are provided as an enclosure to this letter as a mid-cycle revision.

This submittal is made in accordance with Section 5.7.1.5.d,"Core Operating Limits Report (COLR)," of the SONGS Technical Specifications.

The COLR is no longer contained in the Unit-Specific Licensee Controlled Specifications (LCS). It has been moved to a unit specific document that is also controlled under 1 OCFR 50.59. Hence, this is an administrative change and there are no technical changes to the COLR.Enclosure 1 contains the COLR for Unit 2 and Enclosure 2 contains the COLR for Unit 3.This submittal contains no new commitments.

If you have any questions regarding this information, please contact Mr. Mark Morgan, Plant Licensing Lead at (949) 368-6745.Sincerely, uV-J P.O. Box 128 San Clemente, CA 92672 Document Control Desk February 15, 2013

Enclosures:

1. Core Operating Limits Report (COLR) San Onofre Nuclear Generating Station (SONGS) Unit 2 2. Core Operating Limits Report (COLR) San Onofre Nuclear Generating Station (SONGS) Unit 3 cc: E. E. Collins, Jr., Regional Administrator, NRC Region IV R. Hall, NRC Project Manager, San Onofre Units 2 and 3 B. Benney, NRC Project Manager, San Onofre Units 2 and 3 G. Warnick, NRC Senior Resident Inspector, San Onofre Units 2 and 3 Enclosure 1: Core Operating Limits Report (COLR)San Onofre Nuclear Generating Station (SONGS) Unit 2 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT SAN ONOFRE NUCLEAR GENERATING STATION UNIT 2 CORE OPERATING LIMITS REPORT Revision 0 Effective Immediately 50.59 review: 201726946-012 Name PQS Code /PQS Ver. Initials Signature Date 265474 Prepared By Kameron Raisi Approvals Documented in SAP Case KMKR 28753 265474 Reviewed By Kevin Balch Approvals Documented in SAP Case KB 28753 265474 Approved By Tom Remick Approvals Documented in SAP Case TR 28753 Page 1 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS Contents TABLE OF CONTENTS .................................................................................................................................

2 LIST OF FIGURES .........................................................................................................................................

3 DESCRIPTION

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

4 AFFECTED TECHNICAL SPECIFICATIONS

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

4 ANALYTICAL M ETHODS .............................................................................................................................

5 CORE OPERATING LIM ITS ..........................................................................................................................

7 3.1.1 Shutdow n M argin (SDM ) -Tavg > 200 Deg F .................................................................

7 3.1.2 Shutdow n M argin (SDM ) -Tavg -< 200 Deg F .................................................................

7 3.1.4 M oderator Tem perature Coefficient (M TC) .....................................................................

7 3.1.5 Control Elem ent Assem bly (CEA) Alignm ent ....................................................................

7 3.1.7 Regulating CEA Insertion Lim its ........................................................................................

8 3.1.8 Part Length Control Elem ent Assem bly (CEA) Insertion Lim its ......................................

8 3.2.1 Linear Heat Rate (LHR) ......................................................................................................

8 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) ............................................................

8 3.2.5 Axial Shape Index (ASI) ......................................................................................................

9 3.4.1 RCS DNB (Pressure, Tem perature and Flow) Lim its ......................................................

9 3.9.1 Boron Concentration

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

9 Page 2 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.1.4- 1 Figure 3.1.5-1 Figure 3.1.5-2 Figure 3.1.5-3 Figure 3.1.5-4 Figure 3.1.7-1 Figure 3.1.8-1 Figure 3.2.4-1a Figure 3.2.4-1 b Figure 3.2.4-2 LIST OF FIGURES M TC Acceptable Operation

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

10 Required Power Reduction After Single Non-Group 6 Full Length C E A D eviation ........................................................................................

11 Required Power Reduction After Single Group 6 Full Length CEA D eviation ...........................................................................................

12 Required Power Reduction After Single Part Length CEA Deviation (CEA Initially

> 112.5 Inches Withdrawn)

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

13 Required Power Reduction After Single Part Length CEA Deviation (CEA Initially

< 112.5 Inches Withdrawn)

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

14 Regulating CEA Withdrawal vs. Thermal Power ....................................

15 Part Length CEA Insertion Limit vs. Thermal Power .............................

16 DNBR Operating Limit Based on Core Protection Calculators (COLSS Out Of Service (> 90% RTP), One or Both CEACs OPERABLE)

........ 17 DNBR Operating Limit Based on Core Protection Calculators (COLSS Out Of Service (< 90% RTP), One or Both CEACs OPERABLE)

........ 18 DNBR Operating Limit Based On Core Protection Calculator (COLSS Out Of Service, Both CEACs INOPERABLE)

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

19 Page 3 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT DESCRIPTION This Report has been prepared in accordance with the requirements of Technical Specification 5.7.1.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Technical Specification 5.7.1.5.AFFECTED TECHNICAL SPECIFICATIONS 3.1.1 Shutdown Margin (SDM) -Tavg > 200 Deg F 3.1.2 Shutdown Margin (SDM) -Tavg < 200 Deg F 3.1.4 Moderator Temperature Coefficient (MTC)3.1.5 Control Element Assembly (CEA) Alignment 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Length Control Element Assembly (CEA) Insertion Limits 3.2.1 Linear Heat Rate (LHR)3.2.4 Departure From Nucleate Boiling Ratio (DNBR)3.2.5 Axial Shape Index (ASI)3.4.1 RCS DNB (Pressure, Temperature and Flow) Limits 3.9.1 Boron Concentration Page 4 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT ANALYTICAL METHODS The following Technical Specification 5.7.1.5 analytical methods (identified by report number, title, revision, date, and any supplements), previously reviewed and approved by the NRC, shall be used to determine the core operating limits. Changes to the analytical methods are controlled in accordance with 10CFR50.59.

REPORT TITLE REVISION DATE NUMBER CENPD-132P Calculative Methods for the C-E Large 0 August Break LOCA Evaluation Model 1974 Calculational Methods for the C-E Supplement 1 February Large Break LOCA Evaluation Model 1975 Calculational Methods for the C-E Supplement 2-P July 1975 Large- Break LOCA Evaluation Model Calculative Methods for the C-E Large Supplement 3-P-A June 1985 Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS Calculative Methods for the CE Nuclear Supplement 4-P-A March Power Large Break LOCA Evaluation 2001 Model CENPD-137P Calculative Methods for the C-E Small 0 August Break LOCA Evaluation Model 1974 Calculative Methods for the C-E Small Supplement 1-P January Break LOCA Evaluation Model 1977 Calculative Methods for the ABB C-E Supplement 2-P-A April 1998 Small Break LOCA Evaluation Model (Cycle 2 SER) Letter, G. W. Knighton (NRC) to K.P. N/A January 9, Baskin, "Issuance of Amendment No. 1985 30 to Facility Operating License NPF-10 and Amendment No. 19 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 Page 5 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT REPORT TITLE REVISION DATE NUMBER (Cycle 3 SER) Letter, G. W. Knighton (NRC) to K. P. N/A May 16, Baskin (SCE), "Issuance of Amendment 1986 No. 47 to Facility Operating License NPF-10 and Amendment No. 36 to Faci 1 ity Operating License NPF- 15," San Onofre Nuclear Generating Station Units 2 and 3 CEN-356(V)-P-A Modified Statistical Combination of 01-P-A May 1988 Uncertainties CEN-635(S)

Identification of NRC Safety Evaluation 00 February Report Limitations and/or Constraints 1999 on Reload Analysis Methodology SCE-9801-P-A Reload Analysis Methodology for the 0 June San 1999 Onofre Nuclear Generating Station Units 2 and 3 CENPD-404-P-A Implementation of ZIRLOTM Cladding 0 November Material in CE Nuclear Power Fuel 2001 Assembly Designs SCE-0901-A PWR Reactor Physics Methodology 0 December Using 2009 Studsvik Design Codes Page 6 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT CORE OPERATING LIMITS The cycle-specific operating limits for the specifications listed are presented below.3.1.1 Shutdown Margin (SDM) -Tavg > 200 Dea F For Tavg > 200 Deg F the SDM shall be >_ 5.15% Ak/k 3.1.2 Shutdown Margin (SDM) -Tavg -200 Deg F For Tavg < 200 Deg F the SDM shall be > 4.0% Ak/k 3.1.4 Moderator Temperature Coefficient (MTC)The MTC shall be > [more positive than] -3.7E-4 Ak/k/°F at RTP AND The steady state MTC shall be no more positive than the upper MTC limit shown in Figure 3.1.4-1 3.1.5 Control Element Assembly (CEA) Alignment With one non-group 6 full length CEA trippable and misaligned from its group by > 7 inches, initiate THERMAL POWER reduction in accordance with Figure 3.1.5-1 requirements.

With one group 6 full length CEA trippable and misaligned from its group by > 7 inches, initiate THERMAL POWER reduction in accordance with Figure 3.1.5-2 requirements.

With one part length CEA initially

> 112.5" misaligned from its group by > 7 inches, initiate THERMAL POWER reduction in accordance with Figure 3.1.5-3 requirements.

With one part length CEA initially

< 112.5" misaligned from its group by > 7 inches, initiate THERMAL POWER reduction in accordance with Figure 3.1.5-4 requirements.

Page 7 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT 3.1.7 Regulating CEA Insertion Limits The regulating CEA groups shall be limited to the withdrawal sequence, and insertion limits specified in Figure 3.1.7-1.3.1.8 Part Length Control Element Assembly (CEA) Insertion Limits The Part Length CEA groups shall be limited to the insertion limits specified in Figure 3.1.8-1.3.2.1 Linear Heat Rate (LHR)LHR shall not exceed 12.8 kW/ft.3.2.4 Departure From Nucleate Boiling Ratio (DNBR)The DNBR shall be maintained by one of the following methods: a. Maintaining Core Operating Limit Supervisory System (COLSS) calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR (when COLSS is in service, and either one or both control element assembly calculators (CEACs) are OPERABLE);

b. Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by 13.0% RTP (when COLSS is in service and neither CEAC is OPERABLE);

c. Operating within limits as specified in Figure 3.2.4-1A for initial power > 90%RTP or Figure 3.2.4-1B for initial power < 90% RTP using any OPERABLE core protection calculator (CPC) channel (when COLSS is out of service and either one or both CEACs are OPERABLE);

or d. Operating within limits as specified in Figure 3.2.4-2 using any OPERABLE CPC channel (when COLSS is out of service and neither CEAC is OPERABLE).

Page 8 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT 3.2.5 Axial Shape Index (ASI)Core average ASI shall be within the following limits: a. COLSS OPERABLE -0.27 < ASI < +0.27 b. COLSS OUT OF SERVICE -0.20 < ASI < +0.20 3.4.1 RCS DNB (Pressure, Temperature and Flow) Limits RCS Parameters for pressurizer pressure, cold leg temperature, and RCS total flow rate shall be within the limits specified below: a, Pressurizer pressure > 2025 psia and < 2275 psia;b. RCS cold leg temperature (Tc): 1. For THERMAL POWER less than or equal to 30% RTP, 522°F < Tc < 558°F 2. For THERMAL POWER greater than 30% RTP, 535°F < Tc < 558°F;c. RCS total flow rate > 396,000 gpm.3.9.1 Boron Concentration Boron concentrations of the Reactor Coolant System and the refueling canal shall be maintained within the limit specified below to ensure that the more restrictive of the following reactivity conditions is met.a. Keff< 0.95, OR b. Boron concentration

>2600 ppm.Page 9 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.1.4- 1 MTC Acceptable Operation 0_5 0-0.5-1-1.5 LU 0 I-.11 REGION OF UNACCEPTABLE , ,.LIiOPERATION AT ALL TIMES TSL3.1.4 LiwitLi._R o s P o s it iv e M T C L im it ------- --------. ---r -----(E-4 dK/K/F)=O.5-(0.008 x % RTP)--- -- ---- --- ------- ----- ------ ----- ------ ---------.---.--

REGION OF UNACCEPTABLE OPERATION OPRTONDRN STAD STAT-- ----- -----------------------------------------------------

---

. .........------......----......--------L ......- -REGIN OFACCETABL OPEATIO--------r ------T -------4 ---------------------: -------- -------- -------- ----------- ---------- ---- -- --- ------- ---- ----------- ------ ----------- --- -- ---------COLR Loer Limi-~ ~ ---------------------------

---

-----------

---

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

---

----------

M diN f .i i ,REGION OF UNACCEPTABLE OPERATION I-2-2.5-3-3.5-4 0 10 20 30 40 50 60 70 80 90 100 POWER LEVEL (% RTP)Page 10 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.1.5-1 Required Power Reduction After Single Non-Group 6 Full Length CEA Deviation

• 20 REGION OF ACCEPTABLE (120 Minutes, 15%)15 OPERATION z 0 5 (60 Minutes, 10%)D a Uj REGION OF 2 UNACCEPTABLE

0. 5 OPERATION 15 Minutes, 0%)0 20 40 60 80 100 120 TIME AFTER DEVIATION (MINUTES)When core power is reduced to 50% of rated power per this limit curve, further reduction is not required by this specification.

Page 11 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.1.5-2 Required Power Reduction After Single Group 6 Full Length CEA Deviation

• 20 REGION OF ACCEPTABLE 15 OPERATION z 0 t 10 (120 Minutes, 10%)o (60 Minutes, %-/ UNACCEPTABLE

/ OPERATION: (15 Minutes, 0%) , , 0 20 40 60 80 100 120 TIME AFTER DEVIATION (MINUTES)When core power is reduced to 50% of rated power per this limit curve, further reduction is not required by this specification.

Page 12 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.1.5-3 Required Power Reduction After Single Part Length CEA Deviation (CEA Initially

> 112.5 Inches Withdrawn) 20 NO 0 POWER o 10 aREDUCTION

?REQUIRED 0 0. 5 0 0 20 40 60 80 100 120 TIME AFTER DEVIATION (MINUTES)Page 13 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.1.5-4 Required Power Reduction After Single Part Length CEA Deviation (CEA Initially

< 112.5 Inches Withdrawn)

• 20 0-0 z 0 10 r.5 0 0 20 40 60 80 100 TIME AFTER DEVIATION (MINUTES)120 When core power is reduced to 50% of rated power per this limit curve, further reduction is not required by this specification.

Page 14 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.1.7-1 Regulating CEA Withdrawal vs. Thermal Power 108"GP. 6 S&§S'6 C)0 GP. 6 GP. 4 150 120 90 60 30 0 0 1 20 90 60 30 0 GP. 5 GP. 3 I ..I 150 120 90 I I 60 30 j 0 I I i I 150 120 90 Critical CEA Position -Inches Withdrawn Page 15 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.1.8-1 Part Length CEA Insertion Limit vs. Thermal Power*1 nl 0.90--0.80 -0.70-i 0.60 0.50 (X 0.40-0 0.30-,2 0.20 13o~o, I I I 1 ] I I I I I ---I________-1

,&, 112.5" (75%)-U Transient Insertion Limit Long Term Steady State Inserilon Limit LLSaSaa-~aa----------------I~.___________

22.5w (15%)0) IW I I I 1 -1. 1L 1-.. ...I ----- L.L I L JLI 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0 Part Length CEA PosilIon, Inches Withdrawn Page 16 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.2.4-1a DNBR Operating Limit Based on Core Protection Calculators (COLSS Out Of Service (>_ 90% RTP), One or Both CEACs OPERABLE)COLSS OUT OF SERVICE (>=90% RTP)ONE OR BOTH CEACS OPERABLE 2.5 2A -W2.3 02.2-a j1.< -1.9 .8-I o 1.7 -1.6-1.5 REGION OF ACCEPTABLE OPERATION 0000ý-0.2 <= ASI <= 0.1 DNBR>= 0.6

• ASI + 2.14 0.1 < ASI <= 0.2 DNBR >= 2.2 REGION OF UNACCEPTABLE OPERATION I I I I-0.3-0.2-0.1 0 0.1 CPC AXIAL SHAPE INDEX (ASI)0.2 0.3 Page 17 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.2.4- lb DNBR Operating Limit Based on Core Protection Calculators (COLSS Out Of Service (< 90% RTP), One or Both CEACs OPERABLE)COLSS OUT OF SERVICE (<90% RTP)ONE OR BOTH CEACS OPERABLE 2.8 2.7-2.6-z 2.5-ILl 3:2.4 0<2.3 -S2.2 S 2.1 C.2r REGION OF ACCEPTABLE OPERATION-0.2 <= ASI <- 0.05 DNBR>= 0.6

• ASI+ 2.35 0.05 < ASI <= 0.2 DNBR>= 2.38 REGION OF UNACCEPTABLE OPERATION I 1.9-1.8 i j-0.3-0.2-0.1 0 0.1 CPC AXIAL SHAPE INDEX (ASI)0.2 0.3 Page 18 of 19 S02-COLR Revision 0 SONGS UNIT 2 CORE OPERATING LIMITS REPORT Figure 3.2.4-2 DNBR Operating Limit Based On Core Protection Calculator (COLSS Out Of Service, Both CEACs INOPERABLE)

COLSS OUT OF SERVICE BOTH CEACS INOPERABLE 3.7.3.6-O 3.5 -z 0 03.3-J 9J3.2 S3.1 z S3.E 2.9-0 REGION OF ACCEPTABLE OPERATION-0.2 <= ASI <= 0.0 DNBR >= 1.5

• ASI + 3.25 0.0 < ASI <= 0.2 DNBR >= 3.25 REGION OF UNACCEPTABLE OPERATION 2.8-2.7-0.2-0.3 I I I I I I-0.1 0 0.1 0.2 CPC AXIAL SHAPE INDEX (ASI)0.3 Page 19 of 19 Enclosure 2: Core Operating Limits Report (COLR)San Onofre Nuclear Generating Station (SONGS) Unit 3 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT SAN ONOFRE NUCLEAR GENERATING STATION UNIT 3 CORE OPERATING LIMITS REPORT Revision 0 Effective Immediately 50.59 review: 201726946-014 Name PQS Code /PQS Ver. Initials Signature Date 265474 Prepared By Kameron Raisi Approvals Documented in SAP Case KMKR 28753 265474 Reviewed By Kevin Balch Approvals Documented in SAP Case KB 28753 265474 Approved By Tom Remick Approvals Documented in SAP Case TR 28753 Page 1 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT TABLE OF CONTENTS TABLE OF CONTENTS .................................................................................................................................

2 LIST OF FIGURES .........................................................................................................................................

3 DESCRIPTION

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

4 AFFECTED TECHNICAL SPECIFICATIONS

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

4 ANALYTICAL M ETHODS .............................................................................................................................

5 CORE OPERATING LIM ITS ..........................................................................................................................

7 3.1.1 Shutdow n M argin (SDM) -Tavg > 200 Deg F .................................................................

7 3.1.2 Shutdow n M argin (SDM) -Tavg -- 200 Deg F .................................................................

7 3.1.4 M oderator Tem perature Coefficient (M TC) .....................................................................

7 3.1.5 Control Elem ent Assem bly (CEA) Alignm ent ....................................................................

7 3.1.7 Regulating CEA Insertion Lim its ........................................................................................

8 3.1.8 Part Length Control Elem ent Assem bly (CEA) Insertion Lim its ....................................

8 3.2.1 Linear Heat Rate (LHR) ......................................................................................................

8 3.2.4 Departure From Nucleate Boiling Ratio (DNBR) ............................................................

8 3.2.5 Axial Shape Index (ASI) ......................................................................................................

9 3.4.1 RCS DNB (Pressure, Tem perature and Flow ) Lim its ......................................................

9 3.9.1 Boron Concentration

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

9 Page 2 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.1.4- 1 Figure 3.1.5-1 Figure 3.1.5-2 Figure 3.1.5-3 Figure 3.1.5-4 Figure 3.1.7-1 Figure 3.1.8-1 Figure 3.2.4-1a Figure 3.2.4-1b Figure 3.2.4-2 LIST OF FIGURES M TC Acceptable Operation

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

10 Required Power Reduction After Single Non-Group 6 Full Length C E A D eviation ........................................................................................

11 Required Power Reduction After Single Group 6 Full Length CEA D eviation ...........................................................................................

12 Required Power Reduction After Single Part Length CEA Deviation (CEA Initially

> 112.5 Inches Withdrawn)

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

13 Required Power Reduction After Single Part Length CEA Deviation (CEA Initially

< 112.5 Inches Withdrawn)

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

14 Regulating CEA Withdrawal vs. Thermal Power ....................................

15 Part Length CEA Insertion Limit vs. Thermal Power .............................

16 DNBR Operating Limit Based on Core Protection Calculators (COLSS Out Of Service (> 90% RTP), One or Both CEACs OPERABLE)

........ 17 DNBR Operating Limit Based on Core Protection Calculators (COLSS Out Of Service (< 90% RTP), One or Both CEACs OPERABLE)

........ 18 DNBR Operating Limit Based On Core Protection Calculator (COLSS Out Of Service, Both CEACs INOPERABLE)

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

19 Page 3 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT DESCRIPTION This Report has been prepared in accordance with the requirements of Technical Specification 5.7.1.5. The Core Operating Limits have been developed using the NRC approved methodologies specified in Technical Specification 5.7.1.5.AFFECTED TECHNICAL SPECIFICATIONS 3.1.1 Shutdown Margin (SDM) -Tavg > 200 Deg F 3.1.2 Shutdown Margin (SDM) -Tavg < 200 Deg F 3.1.4 Moderator Temperature Coefficient (MTC)3.1.5 Control Element Assembly (CEA) Alignment 3.1.7 Regulating CEA Insertion Limits 3.1.8 Part Length Control Element Assembly (CEA) Insertion Limits 3.2.1 Linear Heat Rate (LHR)3.2.4 Departure From Nucleate Boiling Ratio (DNBR)3.2.5 Axial Shape Index (ASI)3.4.1 RCS DNB (Pressure, Temperature, and Flow) Limits 3.9.1 Boron Concentration Page 4 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT ANALYTICAL METHODS The following Technical Specification 5.7.1.5 analytical methods (identified by report number, title, revision, date, and any supplements), previously reviewed and approved by the NRC, shall be used to determine the core operating limits. Changes to the analytical methods are controlled in accordance with 1 OCFR50.59.

REPORT TITLE REVISION DATE NUMBER CENPD-132P Calculative Methods for the C-E Large 0 August Break LOCA Evaluation Model 1974 Calculational Methods for the C-E Supplement 1 February Large Break LOCA Evaluation Model 1975 Calculational Methods for the C-E Supplement 2-P July 1975 Large- Break LOCA Evaluation Model Calculative Methods for the C-E Large Supplement 3-P-A June 1985 Break LOCA Evaluation Model for the Analysis of C-E and W Designed NSSS Calculative Methods for the CE Nuclear Supplement 4-P-A March Power Large Break LOCA Evaluation 2001 Model CENPD-137P Calculative Methods for the C-E Small 0 August Break LOCA Evaluation Model 1974 Calculative Methods for the C-E Small Supplement 1-P January Break LOCA Evaluation Model 1977 Calculative Methods for the ABB C-E Supplement 2-P-A April 1998 Small Break LOCA Evaluation Model (Cycle 2 SER) Letter, G. W. Knighton (NRC) to K.P. N/A January 9, Baskin, "Issuance of Amendment No. 1985 30 to Facility Operating License NPF-10 and Amendment No. 19 to Facility Operating License NPF-15," San Onofre Nuclear Generating Station Units 2 and 3 Page 5 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT REPORT TITLE REVISION DATE NUMBER (Cycle 3 SER) Letter, G. W. Knighton (NRC) to K. P. N/A May 16, Baskin (SCE), "Issuance of Amendment 1986 No. 47 to Facility Operating License NPF-10 and Amendment No. 36 to Faci l ity Operating License NPF- 15," San Onofre Nuclear Generating Station Units 2 and 3 CEN-356(V)-P-A Modified Statistical Combination of 01-P-A May 1988 Uncertainties CEN-635(S)

Identification of NRC Safety Evaluation 00 February Report Limitations and/or Constraints 1999 on Reload Analysis Methodology SCE-9801-P-A Reload Analysis Methodology for the 0 June San 1999 Onofre Nuclear Generating Station Units 2 and 3 CENPD-404-P-A Implementation of ZIRLOTM Cladding 0 November Material in CE Nuclear Power Fuel 2001 Assembly Designs SCE-0901-A PWR Reactor Physics Methodology 0 December Using 2009 Studsvik Design Codes Page 6 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT CORE OPERATING LIMITS The cycle-specific operating limits for the specifications listed are presented below.3.1.1 Shutdown Margin (SDM) -Tavg > 200 Deg F For Tavg > 200 Deg F the SDM shall be > 5.15% Ak/k 3.1.2 Shutdown Margin (SDM) -Tavg -200 Deg F For Tavg _< 200 Deg F the SDM shall be > 4.0% Ak/k 3.1.4 Moderator Temperature Coefficient (MTC)The MTC shall be > [more positive than] -3.7E-4 Ak/k/°F at RTP AND The steady state MTC shall be no more positive than the upper MTC limit shown in Figure 3.1.4-1 3.1.5 Control Element Assembly (CEA) Alignment With one non-group 6 full length CEA trippable and misaligned from its group by > 7 inches, initiate THERMAL POWER reduction in accordance with Figure 3.1.5-1 requirements.

With one group 6 full length CEA trippable and misaligned from its group by > 7 inches, initiate THERMAL POWER reduction in accordance with Figure 3.1.5-2 requirements.

With one part length CEA initially

> 112.5" misaligned from its group by > 7 inches, initiate THERMAL POWER reduction in accordance with Figure 3.1.5-3 requirements.

With one part length CEA initially

< 112.5" misaligned from its group by > 7 inches, initiate THERMAL POWER reduction in accordance with Figure 3.1.5-4 requirements.

Page 7 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT 3.1.7 Regulating CEA Insertion Limits The regulating CEA groups shall be limited to the withdrawal sequence, and insertion limits specified in Figure 3.1.7-1.3.1.8 Part Length Control Element Assembly (CEA) Insertion Limits The Part Length CEA groups shall be limited to the insertion limits specified in Figure 3.1.8-1.3.2.1 Linear Heat Rate (LHR)LHR shall not exceed 12.8 kW/ft.3.2.4 Departure From Nucleate Boiling Ratio (DNBR)The DNBR shall be maintained by one of the following methods: a. Maintaining Core Operating Limit Supervisory System (COLSS) calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR (when COLSS is in service, and either one or both control element assembly calculators (CEACs) are OPERABLE);

b. Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by 13.0% RTP (when COLSS is in service and neither CEAC is OPERABLE);

c. Operating within limits as specified in Figure 3.2.4-1A for initial power > 90%RTP or Figure 3.2.4-1B for initial power < 90% RTP using any OPERABLE core protection calculator (CPC) channel (when COLSS is out of service and either one or both CEACs are OPERABLE);

or d. Operating within limits as specified in Figure 3.2.4-2 using any OPERABLE CPC channel (when COLSS is out of service and neither CEAC is OPERABLE).

Page 8 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT 3.2.5 Axial Shape Index (ASI)Core average ASI shall be within the following limits: a. COLSS OPERABLE -0.27 < ASI _< +0.27 b. COLSS OUT OF SERVICE -0.20 < ASI < +0.20 3.4.1 RCS DNB (Pressure.

Temperature and Flow) Limits RCS Parameters for pressurizer pressure, cold leg temperature, and RCS total flow rate shall be within the limits specified below: a. Pressurizer pressure > 2025 psia and < 2275 psia;b. RCS cold leg temperature (Tc): 1. For THERMAL POWER less than or equal to 30% RTP, 522°F < Tc < 558 0 F 2. For THERMAL POWER greater than 30% RTP, 535°F < Tc < 558°F;c. RCS total flow rate > 396,000 gpm.3.9.1 Boron Concentration Boron concentrations of the Reactor Coolant System and the refueling canal shall be maintained within the limit specified below to ensure that the more restrictive of the following reactivity conditions is met.a. Keff< 0.95, OR b. Boron concentration

>2600 ppm.Page 9 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.1.4- 1 MTC Acceptable Operation L-0 t-I--0.5 0--0.5-1-1.5-2-2.5-3-3.5 REGION OF UNACCEPTABLE

-TS!3.1.4 Lirait OEPRATION AT ALL TIMES S----------

-- I._R os Positive MTC Limit ----- ----- ........ ... ..... ------UNACCEPTABLE OPERATION DURING STEADY STATE REGION OF ACCEPTABLE OPERATIONJ

---

. T --------------------......----------------------------. .--. .........r ----------- ----------.------------

---

---

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

COLR Lower Limit----- --------------

---

---

.---.---

-~---------U

~~ T REGION OF UNACCEPTABLE OPERATIO=N

____-4 0 10 20 30 40 50 60 70 80 90 100 POWER LEVEL (% RTP)Page 10 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.1.5-1 Required Power Reduction After Single Non-Group 6 Full Length CEA Deviation

• 20 -REGION OF ACCEPTABLE (120 Minutes, 15%)S15 OPERATION I-N z 0 o UNACCEPTABLE

a. 5 /OPERATION 15 Minutes, 0%) .....D 020 40 60 80 100 120 TIME AFTER DEVIATION (MINUTES)When core power is reduced to 50% of rated power per this limit curve, further reduction is not required by this specification.

Page 1 Iof 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.1.5-2 Required Power Reduction After Single Group 6 Full Length CEA Deviation

• 20 REGION OF ACCEPTABLE S15 OPERATION z 0 U 10 (120 Minutes, 10%)U 1 o (60 Minutes, 5%)UNACCEPTABLE OPERATION 0 (15 Minutes, 0%)0 20 40 60 80 100 120 TIME AFTER DEVIATION (MINUTES)When core power is reduced to 50% of rated power per this limit curve., further reduction is not required by this specification.

Page 12 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.1.5-3 Required Power Reduction After Single Part Length CEA Deviation (CEA Initially

> 112.5 Inches Withdrawn) 20.15 NO 0 POWER o 10 U. REDUCTION 3REQUIRED 0 0*0 20 40 60 80 100 120 TIME AFTER DEVIATION (MINUTES)Page 13 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.1.5-4 Required Power Reduction After Single Part Length CEA Deviation (CEA Initially

< 112.5 Inches Withdrawn)

• 20 -REGION OF ACCEPTABLE (15 Miue,0)UACPAL TOPERATION z 0 10 0 (12(0 Minutes, 5%)(15 Minutes, 0%) UNACCEPTABLE OPERATION 0 0 20 40 60 80 100 120 TIME AFTER DEVIATION (MINUTES)When core power is reduced to 50% of rated power per this limit curve, further reduction is not required by this specification.

Page 14 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.1.7-1 Regulating CEA Withdrawal vs. Thermal Power I-S.5 0 S 4-U 0 GP. 6 GP. 4! I 9 6 I 0 1 120 I 60 150 120 90 60 30 0 150 120 90 60 GP. 5 I 1 I 0 3 0 150 120 90 60 30 0 I 30 0 GP.3 50 120 90 Critical CEA Position -Inches Withdrawn Page 15 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.1.8-1 Part Length CEA Insertion Limit vs. Thermal Power*0 1.00 I i I --- T1 I 1 I I -F -I*****~ ~ I 0.90 -0.80 ,,, 112.5" (75%)0.70 -0.5 0.4 0.3 0.2 0.1'U N Transient-0 Insertion Limit o- Long Term Steady State-Insertion Limil____________

m-- nn-- ---------------------------------------------------

___m_ _=22.5" (15%)10 10 O -.I I I 1 -1 1. 1 -- --L -I -L. I I I 150 140 130 120 110 100 90 BO 70 60 50 40 30 20 10 Part Length CEA Position, Inches Withdrawn Page 16 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.2.4-1a DNBR Operating Limit Based on Core Protection Calculators (COLSS Out Of Service (> 90% RTP), One or Both CEACs OPERABLE)COLSS OUT OF SERVICE (>=90% RTP)ONE OR BOTH CEACS OPERABLE 2.5 2A -W 2.3-M 2.2-a 0-I1.j< 2-2 1.7-1.6-1.5 REGION OF ACCEPTABLE OPERATIONl r ,,"U. <A=/ I <-- U./DNBR>= 0.6

• ASI + 2.14 0.1 < ASI <- 0.2 DNBR >= 2.2 REGION OF UNACCEPTABLE OPERATION 7-0.2-0.3-0.1 0 0.1 CPC AXIAL SHAPE INDEX (ASI)0.2 0.3 Page 17 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.2.4-lb DNBR Operating Limit Based on Core Protection Calculators (COLSS Out Of Service (< 90% RTP), One or Both CEACs OPERABLE)COLSS OUT OF SERVICE (<90% RTP)ONE OR BOTH CEACS OPERABLE 2.8 2.7 s2.6 z 02.5 02 uJ 2.4 2J ,4 2.3$2.2 2.1 CL 0.0 2 1.9 1.8-0.3-0.2 -0.1 0 0.1 0.2 CPC AXIAL SHAPE INDEX (ASI)0.3 Page 18 of 19 S03-COLR Revision 0 SONGS UNIT 3 CORE OPERATING LIMITS REPORT Figure 3.2.4-2 DNBR Operating Limit Based On Core Protection Calculator (COLSS Out Of Service, Both CEACs INOPERABLE)

COLSS OUT OF SERVICE BOTH CEACS INOPERABLE 3.5 3.4-to 3.3 -z 0 o03.2 -~31 -0*-j S3-2.9 -0.2.7-2.6-REGION OF ACCEPTABLE OPERATION I~I-0.2 <= ASI <=- 0.01.0

• ASI+ 3.1 0.0 < ASI <= 0.2 DNBR>= 3.1 REGION OF UNACCEPTABLE OPERATION 0 1;~1-0.3-0.2 0.2-0.1 0 0.1 CPC AXIAL SHAPE INDEX (ASI)0.3 Page 19 of 19