DCL-13-064, Revised Cycle 18 Core Operating Limits Reports

Revised Cycle 18 Core Operating Limits Reports

ML13164A167
Person / Time
Site:	Diablo Canyon
Issue date:	06/13/2013
From:	Welsch J Pacific Gas & Electric Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
DCL-13-064
Download: ML13164A167 (31)

Text

Pacific Gas and Electric Company Diablo Canyon Power Plant James M. Welsch Station Director Mail Code 104/5/502 P. O. Box 56 Avila Beach, CA 93424 June 13, 201 3 805.545.3242 Internal: 691.3242 Fax: 805.545.4234 PG&E Letter DCL-13-064 Internet: JMW1@pge.com U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50 ~275 , OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Power Plant Units 1 and 2 Revised Cycle 18 Core Operating Limits Reports

Dear Commissioners and Staff:

In accordance with Diablo Canyon Power Plant Technical Specification 5.6 .5.d, Pacific Gas and Electric Company (PG&E) is providing the latest revisions of the Cycle 18 Core Operating Limits Reports (COLRs) for Units 1 and 2 to the NRC.

Enclosure 1 briefly describes the changes. Enclosure 2 contains "COLR for Diablo Canyon Unit 1," Revision 7. Enclosure 3 contains "COLR for Diablo Canyon Unit 2,"

Revision 8.

PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this letter.

If there are any questions regarding the COLRs, please contact Mr. Mark Mayer at (805) 545-4674.

Sincerely,

---LL~~ "vG0-U-J~.-~elsch wrl8/6980/50519838 Enclosures cc: Diablo Distribution cc/enc: Thomas R. Hipschman, NRC Senior Resident Inspector Arthur T. Howell, III, NRC Region IV James T. Polickoski, NRR Project Manager A member of the STARS (Strategic Teaming and Resource Shari ng) Alliance Callaway . Comanche Peak . Diablo Canyon . Palo Verde . San Onofre . South Texas Project . Wolf Creek

Enclosure 1 PG&E Letter DCL-13-064 Description of Changes to Core Operating Limits Reports (COLR),

Units 1 and 2

Enclosure 1 PG&E Letter DCL-13-064 Description of Changes to Core Operating Limits Reports, Units 1 and 2 Pacific Gas and Electric Company (PG&E) revised the Cycle 18 Description of Changes to Core Operating Limits Reports (COLRs) for Units 1 and 2 to improve the shutdown margin wording. Step 2.1.1 of COLR 1, "COLR for Diablo Canyon Unit 1," and COLR 2, "COLR for Diablo Canyon Unit 2," previously stated "the shutdown margin with Safety Injection enabled shall be greater than or equal to 1.60/0 ~k/k." This step now states "the shutdown margin shall be greater than or equal to 1.6% ~k/k." PG&E removed the words "with Safety Injection enabled" to clarify that the shutdown margin is a single value independent of condition for all modes of the plant, not just when safety injection is enabled.

Enclosure 2 PG&E Letter DCL-13-064 CORE OPERATING LIMITS REPORT, REVISION 7 DIABLO CANYON POWER PLANT, UNIT 1 EFFECTIVE DATE: MAY 21,2013

• • • ISSUED FOR USE BY: --------------- DATE: - - - - - - - - - EXPIRES: ***

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 NUCLEAR POWER GENERATION REVISION 7 DIABLO CANYON POWER PLANT PAGE 1 OF 13 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 1 1

OS/21/13 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED

1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 1 Cycle 18 has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.5.

1.2 The Technical Specifications affected by this report are listed below:

• 3.1.1 - Shutdown Margin (MODE 2 with keff < 1.0, MODES 3, 4, and 5)

• 3.1.3 - Moderator Temperature Coefficient

• 3.1.4 - Rod Group Alignment Limits

• 3.1.5 - Shutdown Bank Insertion Limits

• 3.1.6 - Control Bank Insertion Limits

• 3.1.8 - PHYSICS TESTING Exceptions - MODE 2

• 3.2.1 - Heat Flux Hot Channel Factor - FQ(Z)

• 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor - F ~H

• 3.2.3 - Axial Flux Difference - (AFD)

• 3.4.1 - RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits

• 3.9.1 - Boron Concentration COLR_lulrD7.DOC 04B 0501.1606

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 7 PAGE 2 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1

2. OPERATING LIMITS The cycle-specific parameter limits for the TS listed in Section 1 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in TS 5.6.5.

2.1 Shutdown Margin (SDM) (TS 3.1.1, 3.1.4, 3.1.5, 3.1.6, 3.1.8)

The SDM limit for MODE 1, MODE 2, MODE 3 and MODE 4 is:

2.1.1 The shutdown margin shall be greater than or equal to 1.6% ~k/k.

2.1.2 In MODES 3 or 4 the shutdown margin with Safety Injection blocked shall be greater than or equal to 1.6% ~k/k calculated at a temperature of 200°F.

The SDM limit for MODE 5 is:

2.1.3 The shutdown margin shall be greater than or equal to 1.0% ~k/k. However, an administrative value of 1.6 % ~k/k will be used to address concerns of NSAL-02-0 14.

2.2 Moderator Temperature Coefficient (MTC) (TS 3.1.3)

The MTC limit for MODES 1, 2, and 3 is:

2.2.1 The MTC shall be less negative than -3.9x10-4 ~k/k/oF for all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.

2.2.2 The MTC 300 ppm surveillance limit is -3.0x10-4 ~k/k/oF (all rods withdrawn, RATED THERMAL POWER condition).

2.2.3 The MTC 60 ppm surveillance limit is -3.72x10-4 ~k/k/oF (all rods withdrawn, RATED THERMAL POWER condition).

2.3 Shutdown Bank Insertion Limits (TS 3.1.5) 2.3.1 Each shutdown bank shall be withdrawn to at least 225 steps.

2.4 ' Control Bank Insertion Limits (TS 3.1.6) 2.4.1 The control banks shall be limited in physical insertion as shown in Figure 1.

COLR_Iulr07.DOC 04B 0501.1606

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 7 PAGE 3 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 2.5 Heat Flux Hot Channel Factor - FQ(Z) (TS 3.2.1)

F RTP 2.5.1 FQ(Z)<-Q-*K(Z) for P> 0.5 P

F RTP FQ(Z)<-Q-*K(Z) forP~0.5 0.5 THERMAL POWER where: P RATED THERMAL POWER F~TP = 2.58 K(Z) = 1.0 NOTE: The W(Z) data is appropriate for use only if the predicted axial offset is within

+/-3% of the measured value.

2.5.2 The W(Z) data for Relaxed Axial Offset Control (RAOC) operation, provided in Tables 2A and 2B are sufficient to determine the RAOC W(Z) versus core height for bumups through the end of full power reactivity plus a power coast down of up to 1000 MWD/MTU.

For W(Z) data at a desired bumup not listed in the table, but less than the maximum listed bumup, values at 3 or more bumup steps should be used to interpolate the W (Z) data to the desired bumup with a polynomial type fit that uses the W(Z) data for the nearest three bumup steps.

For W(Z) data at a desired bumup outside of the listed bumup steps, a linear extrapolation of the W (Z) data for the nearest two bumup steps can be used. If data are listed for only 2 bumup steps, a linear fit can be used for both interpolation and extrapolation.

The W(Z) values are generated assuming that they will be used for full power surveillance. When using a flux map instead of the Power Distribution Monitoring System (PDMS) for part power surveillance, the W(Z) values must be increased by the factor lIP (P > 0.5) or 1/0.5 (P:S 0.5), where P is the core relative power during the surveillance, to account for the increase in the F Q(Z) limit at reduced power levels.

Table 1 shows FQ margin decreases that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase F ~ (Z) per SR 3.2.1.2. A 2% penalty factor shall be used at all cycle bumups that are outside the range of Table 1.

COLR_Iulr07.DOC 04B 0501.1606

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DUffiLOCANYONPOWERPLANT REVISION 7 PAGE 4 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 2.5.3 FQ(Z) shall be evaluated to determine if it is within its limits by verifying that F g(Z) and F ~ (Z) satisfy the following:

a. Using the moveable inc ore detectors to obtain a power distribution map in MODE 1.

b. Increasing the measured FQ(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.

c. Satisfying the following relationship:

FRTP *K(Z)

FC(Z)< Q forP> 0.5 Q p FRTP *K(Z)

F C (Z) < Q for P :::; 0.5 Q 0.5 W pRTP F (Z) <-Q-*K(Z) forP>0.5 Q P FRTP F W (Z) :::; _Q_* K(Z) for P :::; 0.5 Q 0.5 where:

F g(Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty.

F ~TP is the FQ limit K(Z) is the normalized FQ(Z) as a function of core height P is the relative THERMAL POWER, and F ~ (Z) is the total peaking factor, F g (Z), multiplied by W (Z) which gives the maximum F Q(Z) calculated to occur in normal operation.

W (Z) is the cycle dependent function that accounts for power distribution transients encountered during normal operation.

F~TP and K(Z) are specified in 2.5.1 and W(Z) is specified in 2.5.2.

COLR_lulr07.DOC 04B 0501.1606

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 7 PAGE 5 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F ~ (TS 3.2.2)

F~H ~ F~P *[1 + PFm * (l-P)]

where:

THERMAL POWER P

RATED THERMAL POWER F ~H = Measured values of F ~ obtained by using the moveable incore detectors to obtain a power distribution map.

F~~P = 1.586 (prior to including 4% uncertainty)

PFm = 0.3 = Power Factor Multiplier 2.7 Power Distribution Measurement Uncertainty (TS 3.2.1. and TS 3.2.2):

If the PDMS is OPERABLE, the uncertainty, U FMf, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F ~H' shall be calculated by the following formula:

where: UllH = Uncertainty for enthalpy rise as defined in equation (5-19) in Reference 6.2. However, if the uncertainty is less than 4.0, the uncertainty should be set equal to 4.0. F~~P = 1.65 for PDMS (in the above Section 2.6 equation).

If the PDMS is OPERABLE, the uncertainty, U FQ, to be applied to the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated by the following formula:

U =(1.0+~)*Ue FQ 100.0 where: U Q= Uncertainty for power peaking factor as defined in equation (5-19) in Reference 6.2.

U e = Engineering uncertainty factor

= 1.03 If the PDMS is inoperable, the Nuclear Enthalpy Rise Hot Channel Factor, F ~H ' shall be calculated as specified in Section 2.6.

If the PDMS is inoperable, the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated as specified in Section 2.5.

COLR_lulr07.DOC 04B 0501.1606

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 7 PAGE 6 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 2.8 Axial Flux Difference (TS 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Limits are provided in Figure 2.

2.9 Boron Concentration (TS 3.9.1)

The refueling boron concentration of the Reactor Coolant System, the refueling.canal, and the refueling cavity shall be maintained within the more restrictive of the following limits:

2.9.1 A keff of 0.95 or less, with the most reactive control rod assembly completely withdrawn, or 2.9.2 A boron concentration of greater than or equal to 2000 ppm.

2.10 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limit (TS 3.4.1) 2.10.1 Pressurizer pressure is greater than or equal to 2175 psig.

2.10.2 RCS average temperature is less than or equal to 581.7°F.

NOTE: The DNB RCS TAVG limit is based on the slightly lower and bounding value associated with Unit 1 in order to have the same surveillance limits for both Unit 1 and Unit 2.

3. TABLES 3.1 Table 1, "FQ Margin Decreases in Excess of2% Per 31 EFPD" 3.2 Table 2A, "Load Follow W(Z) Factors at 150 and 5,000 MWDIMTU as a Function of Core Height" 3.3 Table 2B, "Load Follow W(Z) Factors at 12,000 and 22,000 MWDIMTU as a Function of Core Height"

4. FIGURES 4.1 Figure 1, "Control Bank: Insertion Limits Versus Rated Thermal Power" 4.2 Figure 2, "AFD Limits as a Function of Rated Thermal Power"

5. RECORDS None

6. REFERENCES 6.1 NF-PGE-11-93, "Diablo Canyon Unit 1 Cycle 18 Reload Evaluation and Core Operating Limits Report," January 2012 6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August 1994 COLR_lulr07.DOC 04B 0501.1606

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 7 PAGE 7 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Bumup in FQ Margin (MWDIMTU) 150 2.00 313 2.02 475 2.46 638 2.81 800 3.05 963 3.14 1126 3.07 1288 2.86 1451 2.54 1613 2.13 1776 2.00 6329 2.00 6491 2.01 6654 2.36 6817 2.53 6979 2.42 7142 2.31 7305 2.18 7467 2.03 7630 2.00 NOTE: All cycle bumups outside the range of this table shall use a 2% decrease in FQ margin for compliance with SR 3.2.1.2. Linear interpolation is adequate for intermediate cycle bumups.

COLR_Iulr07.DOC 04B 0501.1606

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 7 PAGE 8 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2A: Load Follow W(Z) Factors at 150 and 5000 MWDIMTU as a Function of Core Height HEIGHT 150 MWDIMTU HEIGHT 5000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z)

• 0.0 1.4629 *0.0 1.4788

• 2.4 1.4588 *2.4 1.4755

• 4.8 1.4517 *4.8 1.4687

• 7.2 1.4426 *7.2 1.4595

• 9.7 1.4316 *9.7 1.4479 12.1 1.4173 12.1 1.4327 14.5 1.4015 14.5 1.4153 16.9 1.3841 16.9 1.3957 19.3 1.3656 19.3 1.3743 21.7 1.3461 21.7 1.3514 24.1 1.3259 24.1 1.3274 26.6 1.3049 26.6 1.3025 29.0 1.2836 29.0 1.2773 31.4 1.2608 31.4 1.2515 33.8 1.2376 33.8 1.2290 36.2 1.2227 36.2 1.2076 38.6 1.2159 38.6 1.1960 41.0 1.2112 41.0 1.1954 43.5 1.2073 43.5 1.1920 45.9 1.2032 45.9 1.1877 48.3 1.1982 48.3 1.1827 50.7 1.1916 50.7 1.1763 53.1 1.1847 53.1 1.1692 55.5 1.1790 55.5 1.1612 57.9 1.1735 57.9 1.1555 60.4 1.1671 60.4 1.1497 62.8 1.1609 62.8 1.1433 65.2 1.1588 65.2 1.1357 67.6 1.1631 67.6 1.1274 70.0 1.1668 70.0 1.1311

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DUffiLOCANYONPO~RPLANT REVISION 7 PAGE 9 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2A: Load Follow W(Z) Factors at 150 and 5000 MWDIMTU as a Function of Core Height (Continued)

HEIGHT 150 MWDIMTU HEIGHT 5000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.1749 72.4 1.1407 74.9 1.1858 74.9 1.1504 77.3 1.1943 77.3 1.1592 79.7 1.2018 79.7 1.1669 82.1 1.2078 82.1 1.1734 84.5 1.2121 84.5 1.1783 86.9 1.2149 86.9 1.1824 89.3 1.2161 89.3 1.1869 91.8 1.2149 91.8 1.1923 94.2 1.2113 94.2 1.1958 96.6 1.2053 96.6 1.1973 99.0 1.1963 99.0 1.1970 101.4 1.1857 101.4 1.1946 103.8 1.1777 103.8 1.1901 106.2 1.1728 106.2 1.1871 108.7 1.1751 108.7 1.1858 111.1 1.1788 111.1 1.1838 113.5 1.1809 113.5 1.1845 115.9 1.1936 115.9 1.2046 118.3 1.2209 118.3 1.2232 120.7 1.2499 120.7 1.2351 123.1 1.2763 123.1 1.2438 125.6 1.3016 125.6 1.2553 128.0 1.3240 128.0 1.2692 130.4 1.3492 130.4 1.2672 132.8 1.3749 132.8 1.2775

• 135.2 1.3876 *135.2 1.2902

• 137.6 1.3798 *137.6 1.2820

• 140.0 1.3620 *140.0 1.2747

• 142.5 1.3366 *142.5 1.2669

• 144.9 1.3156 *144.9 1.2592

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 7 PAGE 10 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2B: Load Follow W(Z) Factors at 12000 and 22000 MWDIMTU as a Function of Core Height HEIGHT 12000 MWDIMTU HEIGHT 22000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z)

• 0.0 1.3034 *0.0 1.3483

• 2.4 1.2941 *2.4 1.3352

• 4.8 1.2849 *4.8 1.3219

• 7.2 1.2751 *7.2 1.3079

• 9.7 1.2646 *9.7 1.2926 12.1 1.2553 12.1 1.2789 14.5 1.2469 14.5 1.2668 16.9 1.2368 16.9 1.2533 19.3 1.2263 19.3 1.2398 21.7 1.2155 21.7 1.2262 24.1 1.2042 24.1 1.2131 26.6 1.1927 26.6 1.2007 29.0 1.1811 29.0 1.1883 31.4 1.1688 31.4 1.1754 33.8 1.1572 33.8 1.1674 36.2 1.1548 36.2 1.1592 38.6 1.1548 38.6 1.1603 41.0 1.1543 41.0 1.1749 43.5 1.1558 43.5 1.1889 45.9 1.1594 45.9 1.2016 48.3 1.1629 48.3 1.2129 50.7 1.1653 50.7 1.2228 53.1 1.1666 53.1 1.2301 55.5 1.1669 55.5 1.2355 57.9 1.1661 57.9 1.2397 60.4 1.1647 60.4 1.2402 62.8 1.1609 62.8 1.2469 65.2 1.1587 65.2 1.2725 67.6 1.1681 67.6 1.2931 70.0 1.1840 70.0 1.3121

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 7 PAGE 11 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 Table 2B: Load Follow W(Z) Factors at 12000 and 22000 MWDIMTU as a Function of Core Height (continued)

HEIGHT 12000 MWDIMTU HEIGHT 22000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.1987 72.4 1.3280 74.9 1.2116 74.9 1.3411 77.3 1.2232 77.3 1.3515 79.7 1.2331 79.7 1.3589 82.1 1.2411 82.1 1.3632 84.5 1.2474 84.5 1.3647 86.9 1.2520 86.9 1.3631 89.3 1.2542 89.3 1.3579 91.8 1.2539 91.8 1.3483 94.2 1.2508 94.2 1.3351 96.6 1.2450 96.6 1.3180 99.0 1.2359 99.0 1.2971 101.4 1.2248 101.4 1.2720 103.8 1.2196 103.8 1.2476 106.2 1.2299 106.2 1.2466 108.7 1.2559 108.7 1.2469 111.1 1.2876 111.1 1.2450 113.5 1.3158 113.5 1.2471 115.9 1.3432 115.9 1.2643 118.3 1.3679 118.3 1.2856 120.7 1.3881 120.7 1.3058 123.1 1.4070 123.1 1.3242 125.6 1.4269 125.6 1.3415 128.0 1.4426 128.0 1.3574 130.4 1.4491 130.4 1.3714 132.8 1.4565 132.8 1.3844

• 135.2 1.4566 *135.2 1.3906

• 137.6 1.4394 *137.6 1.3835

• 140.0 1.4131 *140.0 1.3657

• 142.5 1.3801 *142.5 1.3403

• 144.9 1.3509 *144.9 1.3193

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 1 DIABLO CANYON POWER PLANT REVISION 7 PAGE 13 OF 13 TITLE: COLR for Diablo Canyon Unit 1 UNIT 1 120 I(-14, 100) I (+10,100) I 100 - j , IUNACCEPTABLE UNACCEPTABLE I--- OPERATION ~ I OPERATION

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Figure 2: AFD Limits as a Function of Rated Thermal Power COLR_lulr07.DOC 04B 0501.1606

Enclosure 3 PG&E Letter DCL-13-064 CORE OPERATING LIMITS REPORT, REVISION 8 DIABLO CANYON POWER PLANT, UNIT 2 EFFECTIVE DATE: MAY 21,2013

• • • ISSUED FOR USE BY: --------------- DATE: - - - - - - - - - EXPIRES: ***

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 NUCLEAR POWER GENERATION REVISION 8 DIABLO CANYON POWER PLANT PAGE 1 OF 13 CORE OPERATING LIMITS REPORT UNIT TITLE: COLR for Diablo Canyon Unit 2 OS/21/13 EFFECTIVE DATE CLASSIFICATION: QUALITY RELATED

1. CORE OPERATING LIMITS REPORT 1.1 This Core Operating Limits Report (COLR) for Diablo Canyon Unit 2 Cycle 18 has been prepared in accordance with the requirements of Technical Specification (TS) 5.6.5.

1.2 The Technical Specifications affected by this report are listed below:

• 3.1.1 - Shutdown Margin (MODE 2 with keff< 1.0, MODES 3,4, and 5)

• 3.1.3 - Moderator Temperature Coefficient

• 3.1.4 - Rod Group Alignment Limits

• 3.1.5 - Shutdown Bank Insertion Limits

• 3.1.6 - Control Bank Insertion Limits

• 3.1.8 - PHYSICS TESTING Exceptions - MODE 2

• 3.2.1 - Heat Flux Hot Channel Factor - FQ(Z)

• 3.2.2 - Nuclear Enthalpy Rise Hot Channel Factor - F ~

• 3.2.3 - Axial Flux Difference - (AFD)

• 3.4.1 - RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits

• 3.9.1 - Boron Concentration COLR_2u2r08.DOC 04B 0501.1607

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 2 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2

2. OPERATING LIMITS The cycle-specific parameter limits for the TS listed in Section 1 are presented in the following subsections. These limits have been developed using the NRC-approved methodologies specified in TS 5.6.5.

2.1 Shutdown Margin (SDM) (TS 3.1.1, 3.1.4, 3.1.5,3.1.6,3.1.8)

The SDM limit for MODE 1, MODE 2, MODE 3 and MODE 4 is:

2.1.1 The shutdown margin shall be greater than or equal to 1.6% ~k:/k.

2.1.2 In Modes 3 or 4 the shutdown margin with Safety Injection blocked shall be greater than or equal to 1.6% ~k:/k calculated at a temperature of 200°F.

The SDM limit for MODE 5 is:

2.1.3 The shutdown margin shall be greater than or equal to 1.0% ~k:/k. However, an administrative value of 1.6 % ~k:/k will be used to address concerns of NSAL-02-014 (Reference 6.3).

2.2 Moderator Temperature Coefficient (MTC) (TS 3.1.3)

The MTC limit for MODES 1, 2, and 3 is:

2.2.1 The MTC shall be less negative than -3.9x10-4 ~k:/k:/°F for all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.

2.2.2 The MTC 300 ppm surveillance limit is -3.0x10-4 ~k:/k:/°F (all rods withdrawn, RATED THERMAL POWER condition).

2.2.3 The MTC 60 ppm surveillance limit is -3.72x10-4 ~k:/k:/°F (all rod's withdrawn, RATED THERMAL POWER condition).

2.3 Shutdown Bank Insertion Limits (TS 3.1.5) 2.3.1 Each shutdown bank shall be withdrawn to at least 225 steps.

2.4 Control Bank Insertion Limits (TS 3.1.6) 2.4.1 The control banks shall be limited in physical insertion as shown in Figure 1.

COLR_2u2rOS.DOC 04B 0501.1607

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DurnLOCANYONPO~RPLANT REVISION 8 PAGE 3 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.5 Heat Flux Hot Channel Factor - FQ(Z) (TS 3.2.1)

F RTP 2.5.1 FQ(Z)<-Q-*K(Z) for P> 0.5 P

F RTP FQ(Z)<-Q-*K(Z) forP~0.5 0.5 THERMAL POWER where: P RATED THERMAL POWER F~TP = 2.58 K(Z) = 1.0 NOTE: The W(Z) data is appropriate for use only if the predicted axial offset is within

+/-3 % of the measured value.

2.5.2 The W(Z) data for Relaxed Axial Offset Control (RAOC) operation provided in Tables 2A and 2B are sufficient to determine the RAOC W(Z) versus core height for bumups through the end of full power reactivity plus a power coast down of up to 1000 MWDIMTU.

For W(Z) data at a desired bumup not listed in the table, but less than the maximum listed bumup, values at 3 or more bumup steps should be used to interpolate the W(Z) data to the desired bumup with a polynomial type fit that uses the W (Z) data for the nearest three bumup steps.

For W(Z) data at a desired bumup outside of the listed bumup steps, a linear extrapolation of the W (Z) data for the nearest two bumup steps can be used. If data are listed for only 2 bumup steps, a linear fit can be used for both interpolation and extrapolation.

The W (Z) values are generated assuming that they will be used for full power surveillance. When using a flux map instead of the Power Distribution Monitoring System (PDMS) for part power surveillance, the W(Z) values must be increased by the factor lIP (P > 0.5) or 1/0.5 (P .:s 0.5), where P is the core relative power during the surveillance, to account for the increase in the FQ(Z) limit at reduced power levels.

Table 1 shows FQ margin decreases that are greater than 2% per 31 Effective Full Power Days (EFPD). These values shall be used to increase F ~ (Z) per SR 3.2.1.2. A 2% penalty factor shall be used at all cycle bumups that are outside the range of Table 1.

COLR_2u2rOS.DOC 04B 0501.1607

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 4 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.5.3 FQ(Z) shall be evaluated to determine if it is within its limits by verifying that F g (Z) and F ~ (Z) satisfy the following:

a. Using the moveable incore detectors to obtain a power distribution map in MODE 1.

b. Increasing the measured FQ(Z) component of the power distribution map by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties.

c. Satisfying the following relationship:

FRTP *K(Z)

Fe (Z) < Q for P > 0.5 Q p FRTP *K(Z)

Fe (Z) ~ Q for P ~ 0.5 Q 0.5 W pRTP F (Z)<-Q-*K(Z) forP>0.5 Q P F RTP F W (Z) ~ _Q_* K(Z) for P ~ 0.5 Q 0.5 where:

F g(Z) is the measured FQ(Z) increased by the allowances for manufacturing tolerances and measurement uncertainty.

F ~TP is the FQ limit K(Z) is the normalized F Q(Z) as a function of core height P is the relative THERMAL POWER, and F ~ (Z) is the total peaking factor, F g(Z), multiplied by W(Z) which gives the maximum FQ(Z) calculated to occur in normal operation.

W (Z) is the cycle dependent function that accounts for power distribution transients encountered during normal operation.

F ~TP and K(Z) are specified in 2.5.1 and W(Z) is specified in 2.5.2.

COLR_2u2r08.DOC 04B 0501.1607

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 5 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.6 Nuclear Enthalpy Rise Hot Channel Factor - F ~ (TS 3.2.2) where:

p THERMAL POWER RATED THERMAL POWER F~ = Measured values of F ~ obtained by using the moveable incore detectors to obtain a power distribution map.

F ~~p = 1.586 (prior to including 4% uncertainty)

PF.ill = 0.3 = Power Factor Multiplier 2.7 Power Distribution Measurement Uncertainty (TS 3.2.1. and TS 3.2.2):

If the PDMS is OPERABLE, the uncertainty, UF.ill, to be applied to the Nuclear Enthalpy Rise Hot Channel Factor, F ~, shall be calculated by the following Utili formula: U Ftili = 1.0+--

100.0 where: U AR = Uncertainty for enthalpy rise as defined in equation (5-19) in Reference 6.2. However, if the uncertainty is less than 4.0, the uncertainty should be set equal to 4.0. F ~~p = 1.65 for PDMS (in the above Section 2.6 equation).

If the PDMS is OPERABLE, the uncertainty, U FQ , to be applied to the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated by the following formula:

UFQ=(1.0+~)*Ue 100.0 where: U Q= Uncertainty for power peaking factor as defined in equation (5-19) in Reference 6.2.

U e = Engineering uncertainty factor

= 1.03 If the PDMS is INOPERABLE, the Nuclear Enthalpy Rise Hot Channel Factor, F ~,

shall be calculated as specified in Section 2.6.

If the PDMS is INOPERABLE, the Heat Flux Hot Channel Factor, FQ(Z), shall be calculated as specified in Section 2.5.

COLR_2u2rOS.DOC 04B 0501.1607

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 6 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 2.8 Axial Flux Difference (TS 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Limits are provided in Figure 2.

2.9 Boron Concentration (TS 3.9.1)

The refueling boron concentration of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the more restrictive of the following limits:

2.9.1 A keff of 0.95 or less, with the most reactive control rod assembly completely withdrawn, or 2.9.2 A boron concentration of greater than or equal to 2000 ppm.

2.10 RCS Pressure and Temperature Departure from Nucleate Boiling (DNB) Limit (TS 3.4.1) 2.10.1 Pressurizer pressure is greater than or equal to 2175 psig.

2.10.2 RCS average temperature is less than or equal to 581.7°F.

NOTE: The DNB RCS TAVG limit is based on the slightly lower and bounding value associated with Unit 1 in order to have the same surveillance limits for both Unit 1 and Unit 2.

3. TABLES 3.1 Table 1, "FQ Margin Decreases in Excess of2% Per 31 EFPD" 3.2 Table 2A, "Load Follow W(Z) Factors at 150 and 4,000 MWDIMTU as a Function of Core Height" 3.3 Table 2B, "Load Follow W(Z) Factors at 12,000 and 20,000 MWDIMTU as a Function of Core Height"

4. FIGURES 4.1 Figure 1, "Control Bank Insertion Limits Versus Rated Thermal Power" 4.2 Figure 2, "AFD Limits as a Function of Rated Thermal Power"

5. RECORDS None

6. REFERENCES 6.1 NF-PGE-13-17,"Diablo Canyon Unit 2 Cycle 18 Reload Evaluation and Core Operating Limits Report, Revision 1," March 4,2013.

6.2 WCAP-12473-A (Non-Proprietary), "BEACON Core Monitoring and Operations Support System," August 1994.

6.3 Westinghouse Nuclear Safety Advisory Letter NSAL-02-14, Revision 2, "Steam Line Break During Mode 3 for Westinghouse NSSS Plants," August 4,2005.

COLR_2u2r08.DOC 04B 0501.1607

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 7 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 6.4 Table 1: FQ Margin Decreases in Excess of 2% Per 31 EFPD Cycle Max. % Decrease Bumup inFQ Margin (MWDIMTU) 150 2.00 312 2.01 475 2.98 637 3.75 799 4.27 961 4.48 1124 4.40 1286 4.08 1448 3.59 1611 3.02 1773 2.43 1935 2.00 5668 2.00 5830 2.57 5993 2.99 6155 2.86 6317 2.72 6480 2.62 6642 2.52 6804 2.41 6967 2.29 7129 2.17 7291 2.05 7453 2.00 NOTE: All cycle bumups outside the range of this table shall use a 2% decrease in FQ margin for compliance with SR 3.2.1.2. Linear interpolation is adequate for intermediate cycle bumups.

COLR_2u2r08.DOC 04B 0501.1607

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 8 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWDIMTU as a Function of Core Height HEIGHT 150 MWDIMTU HEIGHT 4000 MWDIMTU (INCHES) W(Z) (INCHES W(Z)

• 0.0 1.5137 *0.0 1.4970

• 2.4 1.4961 *2.4 1.4781

• 4.8 1.4777 *4.8 1.4611

• 7.2 1.4590 *7.2 1.4462

• 9.7 1.4402 *9.7 1.4340 12.1 1.4187 12.1 1.4193 14.5 1.3947 14.5 1.4020 16.9 1.3704 16.9 1.3828 19.3 1.3517 19.3 1.3618 21.7 1.3321 21.7 1.3394 24.1 1.3107 24.1 1.3161 26.6 1.2902 26.6 1.2916 29.0 1.2722 29.0 1.2675 31.4 1.2551 31.4 1.2458 33.8 1.2390 33.8 1.2250 36.2 1.2261 36.2 1.2070 38.6 1.2156 38.6 1.1944 41.0 1.2074 41.0 1.1873 43.5 1.2052 43.5 1.1846 45.9 1.2023 45.9 1.1816 48.3 1.1982 48.3 1.1777 50.7 1.1930 50.7 1.1727 53.1 1.1869 53.1 1.1671 55.5 1.1800 55.5 1.1606 57.9 1.1722 57.9 1.1533 60.4 1.1638 60.4 1.1452 62.8 1.1543 62.8 1.1370 65.2 1.1449 65.2 1.1284 67.6 1.1425 67.6 1.1204 70.0 1.1524 70.0 1.1273

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 9 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2A: Load Follow W(Z) Factors at 150 and 4000 MWDIMTU as a Function of Core Height (Continued)

HEIGHT 150 MWDIMTU HEIGHT 4000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.1650 72.4 1.1390 74.9 1.1751 74.9 1.1494 77.3 1.1847 77.3 1.1592 79.7 1.1931 79.7 1.1680 82.1 1.2001 82.1 1.1757 84.5 1.2057 84.5 1.1821 86.9 1.2096 86.9 1.1870 89.3 1.2118 89.3 1.1905 91.8 1.2129 91.8 1.1931 94.2 1.2118 94.2 1.1938 96.6 1.2084 96.6 1.1923 99.0 1.2026 99.0 1.1892 101.4 1.1943 101.4 1.1833 103.8 1.1836 103.8 1.1752 106.2 1.1737 106.2 1.1760 108.7 1.1736 108.7 1.1870 111.1 1.1767 111.1 1.2017 113.5 1.1767 113.5 1.2131 115.9 1.1808 115.9 1.2230 118.3 1.1824 118.3 1.2303 120.7 1.1860 120.7 1.2383 123.1 1.1910 123.1 1.2458 125.6 1.1940 125.6 1.2511 128.0 1.1980 128.0 1.2589 130.4 1.2007 130.4 1.2758 132.8 1.1998 132.8 1.2865

• 135.2 1.2065 *135.2 1.2949

• 137.6 1.2170 *137.6 1.2988

• 140.0 1.2160 *140.0 1.2936

• 142.5 1.2044 *142.5 1.2838

• 144.9 1.1959 *144.9 1.2754

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 10 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWDIMTU as a Function of Core Height HEIGHT 12000 MWDIMTU HEIGHT 20000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z)

• 0.0 1.2703 *0.0 1.3120

• 2.4 1.2689 *2.4 1.3146

• 4.8 1.2674 *4.8 1.3127

• 7.2 1.2660 *7.2 1.3080

• 9.7 1.2615 *9.7 1.3003 12.1 1.2538 12.1 1.2890 14.5 1.2446 14.5 1.2764 16.9 1.2346 16.9 1.2631 19.3 1.2240 19.3 1.2495 21.7 1.2131 21.7 1.2357 24.1 1.2019 24.1 1.2216 26.6 1.1904 26.6 1.2073 29.0 1.1787 29.0 1.1928 31.4 1.1662 31.4 1.1773 33.8 1.1558 33.8 1.1606 36.2 1.1529 36.2 1.1564 38.6 1.1527 38.6 1.1598 41.0 1.1536 41.0 1.1716 43.5 1.1557 43.5 1.1839 45.9 1.1570 45.9 1.1950 48.3 1.1567 48.3 1.2046 50.7 1.1573 50.7 1.2129 53.1 1.1595 53.1 1.2189 55.5 1.1604 55.5 1.2231 57.9 1.1601 57.9 1.2254 60.4 1.1595 60.4 1.2256 62.8 1.1559 62.8 1.2253 65.2 1.1549 65.2 1.2322 67.6 1.1686 67.6 1.2533 70.0 1.1868 70.0 1.2733

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 11 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 Table 2B: Load Follow W(Z) Factors at 12000 and 20000 MWDIMTU as a Function of Core Height (Continued)

HEIGHT 12000 MWDIMTU HEIGHT 20000 MWDIMTU (INCHES) W(Z) (INCHES) W(Z) 72.4 1.2028 72.4 1.2893 74.9 1.2175 74.9 1.3035 77.3 1.2306 77.3 1.3152 79.7 1.2421 79.7 1.3245 82.1 1.2517 82.1 1.3311 84.5 1.2592 84.5 1.3347 86.9 1.2648 86.9 1.3358 89.3 1.2688 89.3 1.3346 91.8 1.2706 91.8 1.3298 94.2 1.2696 94.2 1.3218 96.6 1.2660 96.6 1.3105 99.0 1.2598 99.0 1.2959 101.4 1.2507 101.4 1.2780 103.8 1.2388 103.8 1.2586 106.2 1.2312 106.2 1.2449 108.7 1.2295 108.7 1.2322 111.1 1.2279 111.1 1.2183 113.5 1.2233 113.5 1.2078 115.9 1.2217 115.9 1.1998 118.3 1.2252 118.3 1.1950 120.7 1.2300 120.7 1.2015 123.1 1.2334 123.1 1.2206 125.6 1.2357 125.6 1.2398 128.0 1.2399 128.0 1.2633 130.4 1.2562 130.4 1.2847 132.8 1.2667 132.8 1.2968

• 135.2 1.2720 *135.2 1.3096

• 137.6 1.2712 *137.6 1.3183

• 140.0 1.2598 *140.0 1.3124

• 142.5 1.2410 *142.5 1.2929

• 144.9 1.2244 *144.9 1.2774

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 12 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 225 V I (0.583,225) I 200 /

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0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 Fraction of Rated Thermal Power Figure 1: Control Bank Insertion Limits Versus Rated Thermal Power COLR_2u2r08.DOC 04B 0501.1607

PACIFIC GAS AND ELECTRIC COMPANY NUMBER COLR 2 DIABLO CANYON POWER PLANT REVISION 8 PAGE 13 OF 13 TITLE: COLR for Diablo Canyon Unit 2 UNIT 2 120 I (-14,100) I I 100 -

d UNACCEPTABLE OPERATION V

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Figure 2: AFD Limits as a Function of Rated Thermal Power COLR_2u2r08.DOC 04B 0501.1607