ML13346A427

From kanterella
Jump to navigation Jump to search
Cycle 20 Core Operating Limits Report
ML13346A427
Person / Time
Site: Sequoyah Tennessee Valley Authority icon.png
Issue date: 12/04/2013
From: John Carlin
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13346A427 (26)
v • d • e


Text

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 December 4, 2013 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 Facility Operating License No. DPR-77 NRC Docket No. 50-327

Subject:

Sequoyah Unit I Cycle 20 Core Operating Limits Report In accordance with Sequoyah Nuclear Plant (SQN) Unit 1 Technical Specification (TS) 6.9.1.14.c, enclosed is the Unit 1 Cycle 20 Core Operating Limits Report (COLR),

Revision 0. In accordance with TS 6.9.1.14.c, the COLR is required to be provided to the Nuclear Regulatory Commission within 30 days after the cycle start-up (Mode 2) for each reload cycle. Sequoyah Unit 1 entered Mode 2 on November 20, 2013, for the current reload cycle.

There are no new regulatory commitments in this letter. If you have any questions, please contact Michael McBrearty, SQN Site Licensing Manager at (423) 843-7170.

Respectfully, Vi President Sequoyah Nuclear Plant Enclosure Sequoyah Unit 1 Cycle 20 Core Operating Limits Report cc (Enclosure):

NRC Regional Administrator- Region II NRC Senior Resident Inspector - SQN

ENCLOSURE SEQUOYAH UNIT I CYCLE 20 CORE OPERATING LIMITS REPORT

QA Record L36 131101 802 SEQUOYAH UNIT I CYCLE 20 CORE OPERATING LIMITS REPORT REVISION 0 November 2013 Prepared by: // ý J. E.Wtrange, PW Fulgineering Date Verified by:

C..,A.

t Setter, PWVR Fuel Eng-ine-e-ng /kua Date Date%.

R *ewedty /.

D. M. Brown, PWR Fuel Engineering Manager Date L/ rCu'd t

B. S. Catalanotto, ReactorEngineering Manager Date Approved by z PRDate Plant Mana"er Date Revision 0 Pages affected All Reason for Revision: Initial Issue SEQUOYAH-UNIT 1 Page I of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for Sequoyah Unit 1 Cycle 20 has been prepared in accordance with the requirements of Technical Specification (TS) 6.9.1.14.

The TSs affected by this Report are listed below:

TABLE 2.2-1 fi(AI) trip reset function for OTAT Trip (QTNL, QTPL) and rates of trip setpoint decrease per percent Al (QTNS, QTPS)

TABLE 2.2-1 f2(AI) trip reset function for OPAT Trip (QPNL, QPPL) and rates of trip setpoint decrease per percent Al (QPNS, QPPS) 3/4.1.1.3 Moderator Temperature Coefficient (MTC) 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insertion Limits 3/4.2.1 Axial Flux Difference (AFD) 3/4.2.2 Heat Flux Hot Channel Factor (Fo(X,Y,Z))

3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor (FAH(X,Y))

2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in TS 6.9.1.14. The versions of the topical reports which describe the methodologies used for this cycle are listed in Table 1.

The following abbreviations are used in this section:

BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.1 Moderator Temperature Coefficient - MTC (Specification 3/4.1.1.3) 2.1.1 The MTC limits are:

The BOL/ARO/HZP MTC shall be less positive than 0 Ak/k/0 F (BOL limit). With the measured value more positive than -0.03 x10 5 Ak/k/"F (as-measured MTC limit),

establish control rod withdrawal limits to ensure the MTC remains less positive than 0 Ak/k/°F for all times in core life.

The EOL/ARO/RTP MTC shall be less negative than or equal to -4.5 X 104 Ak/k/0 F.

SEQUOYAH-UNIT 1 Page 2 of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 2.1.2 The 300 ppm surveillance limit is:

The measured 300 ppm/ARO/RTP MTC should be less negative than or equal to

-3.75 x 104 Ak/k/°F.

2.2 Shutdown Rod Insertion Limit (Specification 3/4.1.3.5) 2.2.1 The shutdown rods shall be withdrawn to a position as defined below:

Cycle Burnup Steps Withdrawn (MWd/mtU)

>0 > 225 to < 231 2.3 Control Rod Insertion Limits (Specification 314.1.3.6) 2.3.1 The control rod banks shall be limited in physical insertion as shown in Figure 1.

2.4 Axial Flux Difference - AFD (Specification 3/4.2.1) 2.4.1 The axial flux difference (AFD) limits (AFDur"mt) are provided in Figure 2.

2.5 Heat Flux Hot Channel Factor - Fg(X,Y,Z) (Specification 3/4.2.2)

Fa (X,Y,Z) shall be limited by the following relationships:

FQRTP FQ(X,Y,Z)< *K(Z) for P> 0.5 P

FaRTP Fa (X,Y,Z)* -

  • K(Z) for P*< 0.5 0.5 THERMAL POWER where P =

RATED THERMAL POWER RTP 2.5.1 F0 = 2.62 2.5.2 K(Z) is provided in Figure 3 SEQUOYAH-UNIT 1 Page 3 of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 The following parameters are required for core monitoring per the Surveillance Requirements of Specification 3/4.2.2:

2.5.3 NSLOPEAFD = 1.23 where NSLOPEAFD = Negative AFD limit adjustment required to compensate for each 1% that F0 (X,Y,Z) exceeds BQDES.

2.5.4 PSLOPEAFD = 1.47 where PSLOPEAFD = Positive AFD limit adjustment required to compensate for each 1% that FQ(X,Y,Z) exceeds BQDES.

2 2.5.5 NSLOPEt (AI) = 1.55 where NSLOPE'2 (A) = Adjustment to negative OPAT f2(Al) limit required to compensate for each 1% that FQ(X,Y,Z) exceeds BCDES.

2.5.6 PSLOPE12(.6) = 1.89 where PSLOPE2*(AI) Adjustment to positive OPAT f2(AI) limit required to compensate for each 1% that FQ(X,Y,Z) exceeds BCDES.

2.5.7 BQNOM(X,Y,Z) = Nominal design peaking factor, increased by an allowance for the expected deviation between the nominal design power distribution and the measurement.

2.5.8 BQDES(X,Y,Z) = Maximum allowable design peaking factor which ensures that the F0 (X,Y,Z) limit will be preserved for operation within the LCO limits, including allowances for calculational and measurement uncertainties.

2.5.9 BCDES(X,Y,Z) = Maximum allowable design peaking factor which ensures that the centerline fuel melt limit will be preserved for operation within the LCO limits, including allowances for calculational and measurement uncertainties.

BQNOM(X,Y,Z), BQDES(X,Y,Z), and BCDES(X,Y,Z) databases are provided for input to the plant power distribution analysis codes on a cycle specific basis and are determined using the methodology for core limit generation described in the references in Specification 6.9.1.14.

SEQUOYAH-UNIT I Page 4 of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 2.5.10 The increase in FQM(X,Y,Z) for compliance with the 4.2.2.2.e Surveillance Requirements is defined as follows:

For cycle burnups: 0 to 3118 MWd/mtU, use 2.0 %

For cycle burnups: > 3118 to 4145 MWd/mtU, use 2.29 %

For cycle burnups: > 4145 MWd/mtU, use 2.0 %

2.6 Nuclear Enthalpy Rise Hot Channel Factor - F^H(X.Y) (Specification 3/4.2.3)

F6H(X,Y) shall be limited by the following relationship:

FAH(X,Y) < MAP(X,Y,Z) / AXIAL(X,Y) 2.6.1 MAP(X,Y,Z) is provided in Tables 2a and 2b.

AXIAL(X,Y) is the axial peak from the normalized axial power shape.

The following parameters are required for core monitoring per the Surveillance Requirements of Specification 3/4.2.3:

FAHRM(X,Y) _*BHNOM(X,Y) where FAHR M(X,Y) = FAHM(X,Y) / [MAPm / AXIAL(X,Y)]

FAHM(X,Y) is the measured radial peak at location X,Y.

MAPi is the value of MAP(X,Y,Z) obtained from Tables 2a and 2b for the measured peak.

2.6.2 BHNOM(X,Y) = Nominal design radial peaking factor, increased by an allowance for the expected deviation between the nominal design power distribution and the measurement.

2.6.3 BHDES(X,Y) = Maximum allowable design radial peaking factor which ensures that the FAH (X,Y) limit will be preserved for operation within the LCO limits, including allowances for calculational and measurement uncertainties.

2.6.4 BRDES(X,Y) = Maximum allowable design radial peaking factor which ensures that the steady state DNBR limit will be preserved for operation within the LCO limits, including allowances for calculational and measurement uncertainties.

BHNOM(X,Y), BHDES(X,Y) and BRDES(X,Y) databases are provided for input to the plant power distribution analysis computer codes on a cycle specific basis and are determined using the methodology for core limit generation described in the references in Specification 6.9.1.14.

SEQUOYAH-UNIT I Page 5 of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 2.6.5 RRH = 3.34 when 0.8 < P < 1.0 RRH = 1.67 when P < 0.8 where RRH = Thermal power reduction required to compensate for each 1% that FAH(X,Y) exceeds its limit.

P = Thermal Power / Rated Thermal Power 2.6.6 TRH = 0.0334 when 0.8 < P < 1.0 TRH = 0.0167 when P < 0.8 where TRH = Reduction in OTAT K1 setpoint required to compensate for each 1%

FAH(X,Y) exceeds its limit.

P = Thermal Power / Rated Thermal Power 2.6.7 All cycle burnups shall use a 2% increase in FAHM(X,Y) for compliance with the 4.2.3.2.d.1 Surveillance Requirement.

3.0 REACTOR CORE PROTECTIVE LIMITS 3.1 Trip Reset Term [ff(AI)M for Overtemperature Delta-T Trip (Specification 2.2.1)

The following parameters are required to specify the power level-dependent f1(AI) trip reset term limits for the Overtemperature Delta-T trip function:

3.1.1 QTNL=-20%

where QTNL = the maximum negative Al setpoint at rated thermal power at which the trip setpoint is not reduced by the axial power distribution.

3.1.2 QTPL = +5%

where QTPL = the maximum positive Al setpoint at rated thermal power at which the trip setpoint is not reduced by the axial power distribution.

3.1.3 QTNS = 2.50%

where QTNS = the percent reduction in Overtemperature Delta-T trip setpoint for each percent that the magnitude of Al exceeds its negative limit at rated thermal power (QTNL).

SEQUOYAH-UNIT I Page 6 of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 3.1.4 QTPS = 1.40%

where QTPS = the percent reduction in Overtemperature Delta-T trip setpoint for each percent that the magnitude of Al exceeds its positive limit at rated thermal power (QTPL).

3.2 Trip Reset Term rff(AI)] for Overpower Delta-T Trip (Specification 2.2.1)

The following parameters are required to specify the power level-dependent f2(AI) trip reset term limits for the Overpower Delta-T trip function:

3.2.1 QPNL = -25%

where QPNL = the maximum negative Al setpoint at rated thermal power at which the trip setpoint is not reduced by the axial power distribution.

3.2.2 QPPL = +25%

where QPPL = the maximum positive Al setpoint at rated thermal power at which the trip setpoint is not reduced by the axial power distribution.

3.2.3 QPNS = 1.70%

where QPNS = the percent reduction in Overpower Delta-T trip setpoint for each percent that the magnitude of Al exceeds its negative limit at rated thermal power (QPNL).

3.2.4 QPPS = 1.70%

where QPPS = the percent reduction in Overpower Delta-T trip setpoint for each percent that the magnitude of Al exceeds its positive limit at rated thermal power (QPPL).

SEQUOYAH-UNIT I Page 7 of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 Table 1 COLR Methodology Topical Reports

1. BAW-10180-A, Revision 1, "NEMO-Nodal Expansion Method Optimized," March 1993.

(Methodology for Specification 3/4.1.1.3-Moderator Temperature Coefficient)

2. BAW-10169P-A, Revision 0, "RSG Plant Safety Analysis-B&W Safety Analysis Methodology for Recirculating Steam Generator Plants," October 1989.

(Methodology for Specification 3/4.1.1.3-Moderator Temperature Coefficient)

3. BAW-10163P-A, Revision 0, "Core Operating Limit Methodology for Westinghouse-Designed PWRs," June 1989.

(Methodology for Specifications 2.2.1-Reactor Trip Instrumentation Setpoints [fl(Al), f2(AI) limits],

3/4.1.3.5-Shutdown Rod Insertion Limit, 3/4.1.3.6-Control Rod Insertion Limits, 3/4.2.1-Axial Flux Difference, 3/4.2.2-Heat Flux Hot Channel Factor, 3/4.2.3-Nuclear Enthalpy Rise Hot Channel Factor)

4. EMF-2328(P)(A), "PWR Small Break LOCA Evaluation Model," March 2001.

(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)

5. BAW-10227P-A, Revision 1, "Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel," June 2003.

(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)

6. BAW-10186P-A, Revision 2, "Extended Burnup Evaluation," June 2003.

(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)

7. EMF-2103P-A, Revision 0, "Realistic Large Break LOCA Methodology for Pressurized Water Reactors," April 2003.

(Methodology for Specification 3/4.2.2-Heat Flux Hot Channel Factor)

8. BAW-10241P-A, Revision 1, "BHTP DNB Correlation Applied with LYNXT," July 2005.

(Methodology for Specification 3/4.2.3-Enthalpy Rise Hot Channel Factor)

9. BAW-10199P-A, Revision 0, "The BWU Critical Heat Flux Correlations," August 1996.

(Methodology for Specification 3/4.2.3-Enthalpy Rise Hot Channel Factor)

10. BAW-10189P-A, "CHF Testing and Analysis of the Mark-BW Fuel Assembly Design," January 1996.

(Methodology for Specification 3/4.2.3-Enthalpy Rise Hot Channel Factor)

11. BAW-10159P-A, "BWCMV Correlation of Critical Heat Flux in Mixing Vane Grid Fuel Assemblies,"

August 1990.

(Methodology for Specification 3/4-2.3-Enthalpy Rise Hot Channel Factor)

12. BAW-1 0231 P-A, Revision 1, "COPERNIC Fuel Rod Design Computer Code," January 2004.

(Methodology for Specification 2.2.1-Reactor Trip Instrumentation Setpoints)

SEQUOYAH-UNIT I Page 8 of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 Table 2a Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation M

T Advanced W17 HTP Fuel AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 1.8128 1 2.5969 2 1.8125 2 2.5380 3 1.8122 3 2.4827 4 1.8119 4 2.4411 5 1.8115 5 2.4315 1.1 6 1.8109 1.4 6 2.4800 7 1.8106 7 2.5356 8 1.8104 8 2.4447 9 1.8098 9 2.3555 10 1.8092 10 2.1738 11 1.7599 11 2.0238 1 2.0671 1 2.6723 2 2.0664 2 2.6061 3 2.0656 3 2.5417 4 2.0649 4 2.4913 5 2.0642 5 2.4801 1.2 6 2.0636 1.5 6 2.5380 7 2.0624 7 2.6273 8 2.0615 8 2.5311 9 2.0457 9 2.4447 10 1.9492 10 2.2772 11 1.8589 11 2.0975 1 2.3433 1 2.7308 2 2.3419 2 2.6605 3 2.3412 3 2.5947 4 2.3397 4 2.5371 5 2.3389 5 2.5234 1.3 6 2.3381 1.6 6 2.5906 7 2.3357 7 2.7077 8 2.3130 8 2.6117 9 2.1886 9 2.5240 10 2.0643 10 2.3758 11 1.9439 11 S 2.1662 SEQUOYAH-UNIT I Page 9 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 1 CYCLE 20 Table 2a (continued)

AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 2.7664 1 2.4339 2 2.7083 2 2.4060 3 2.6380 3 2.3856 4 2.5791 4 2.3423 5 2.5639 5 2.3114 1.7 6 2.6359 >1.9 6 2.6006 7 2.7795 7 2.5003 8 2.6870 8 2.4004 9 2.5798 9 2.2989 10 2.4726 10 2.1483 11 2.2304 11 1.9630 1 2.7963 1 2.5057 2 2.7466 2 2.4754 3 2.6775 3 2.4449 4 2.6172 4 2.3591 5 2.6010 5 2.4205 1.8 6 2.6802 2.1 6 2.7643 7 2.8456 7 2.6474 8 2.7552 8 2.5360 9 2.6648 9 2.4400 10 2.5655 10 2.3277 11 2.2931 11 2.0549 1 2.8235 1 2.5380 2 2.7739 2 2.5216 3 2.7125 3 2.4619 4 2.6523 4 2.4294 5 2.6328 5 2.4290 1.9 6 2.7200 2.3 6 2.8222 7 2.9065 7 2.7334 8 2.8193 8 2.6234 9 2.7288 9 2.5186 10 2.6384 10 2.4215 11 2.3482 11 S 2.1250 SEQUOYAH-UNIT I Page 10 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 1 CYCLE 20 Table 2a (continued)

AXIAL(X,Y) ELEVATION (ift) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) 1 2.6440 1 2.2448 2 2.5160 2 2.5535 3 2.5045 3 2.4678 4 2.4488 4 2.3229 5 2.5803 5 2.8913 2.5 6 2.9481 3.1 6 3.1515 7 2.8544 7 3.0181 8 2.7286 8 2.9699 9 2.6450 9 2.8941 10 2.5527 10 2.7819 11 2.1731 11 2.1866 1 2.5554 1 2.0228 2 2.5529 2 2.5172 3 2.5197 3 2.4007 4 2.4375 4 2.2195 5 2.5643 5 3.0496 2.7 6 2.9839 3.3 6 3.2226 7 2.8837 7 3.1446 8 2.7939 8 3.0350 9 2.7040 9 2.9688 10 2.5997 10 2.8533 11 2.1995 11 2.1473 1 2.4223 1 1.7563 2 2.5653 2 2.4566 3 2.5075 3 2.3062 4 2.3955 4 2.0854 5 2.7295 5 3.2045 2.9 6 3.0921 3.5 6 3.2929 7 3.0070 7 3.2627 8 2.8896 8 3.0846 9 2.8058 9 3.0299 10 2.6974 10 2.9117 11 2.2039 11 S 2.0862 SEQUOYAH-UNIT 1 Page 11 of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 Table 2b Maximum Allowable Peaking Limits MAP(X,Y,Z) for Operation Mark-BW Fuel AXIAL(X,Y) ELEVATION (ft) MAP(X,Y,Z) AXIAL(X,Y) ELEVATION (ft) MAP(XY,Z) 2 1.9343 2 2.8143 4 1.9300 4 2.9856 1.1 6 1.9234 1.9 6 3.0073 8 1.9115 8 2.8509 10 1.8894 10 2.7048 2 2.1663 2 2.4405 4 2.1558 4 2.4405 1.2 6 2.1410 >1.9 6 2.7376 8 2.1153 8 2.5906 10 2.0582 10 2.3456 2 2.4023 2 2.5881 4 2.3825 4 2.5881 1.3 6 2.3599 2.2 6 2.9899 8 2.3100 8 2.7800 10 2.1760 10 2.5367 2 2.6453 2 2.6111 4 2.6136 4 2.6111 1.4 6 2.5610 2.6 6 3.2947 8 2.4199 8 3.2055 10 2.2787 10 2.8049 2 2.7189 2 2.9142 4 2.8181 4 2.9142 1.5 6 2.6735 3.0 6 4.0216 8 2.5280 8 3.6527 10 2.3749 10 3.1711 2 2.7720 2 2.9618 4 2.9219 4 2.9618 1.7 6 2.8641 3.5 6 4.2351 8 2.7064 8 3.7452 10 2.5539 10 3.3214 SEQUOYAH-UNIT I Page 12 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 1 CYCLE 20 231 (Fully Withdrawn Region)*

220 Z (.575 f 25) 200 (1.0,182) 180 160 BAN C C 140 I -

0 IL 120- /

Q. /(0,110) u)100 BAN 80 0

60 40 20 (.09,0 0

0 0.2 0.4 0.6 0.8 I (Fully Inserted) Fraction of Rated Thermal Power Figure 1 Rod Bank Insertion Limits Versus Thermal Power, Four Loop Operation Fully withdrawn region shall be the condition where shutdown and control banks are at a position within the interval of ':225 and 5231steps withdrawn, inclusive.

Fully withdrawn shall be the position as defined below, Cycle Burnup (MWd/mtu) Steps Withdrawn

>0 >225to< 231 This figure is valid for operation at a rated thermal power of 3455 MWth when the LEFM is in operation.

If the LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power level must be reduced by 1.3% in power, and the rod insertion limit lines must be increased by 3 steps withdrawn until the LEFM is returned to operation.

SEQUOYAH-UNIT 1 Page 13 of 15 Revision 0

COLR FOR SEQUOYAH UNIT I CYCLE 20 120 1

110 _ -1(4 1 010 0 -"a 1 31 (7 ,-0 -0)-r --

UcUce ble U_ atcc Ptabble 9 0* p e ra t i n - -- - O p "a t io n 4180 *--

  • Opperatin J-_---*

80 *Acceptable 5-60 360 -2 400 20-l-_ _ 0)_81 OL

-50 -40 -30 -20 -10 0 10 20 30 40 50 Flux Difference (AI) %

FIGURE 2 Axial Flux Difference Limits As A Function of Thermal Power For Burnup Range of 0 EFPD to EOL This figure is valid for operation at a rated thermal power of 3455 MWth when the LEFM is in operation.

Ifthe LEFM becomes inoperable, then prior to the next NIS calibration, the maximum allowable power level must be reduced by 1.3% in power, and the AFD limit lines must be made more restrictive by 1% in AFD until the LEFM is returned to operation.

SEQUOYAH-UNIT I Page 14 of 15 Revision 0

COLR FOR SEQUOYAH UNIT 1 CYCLE 20 1.2 1.0

- -I

- - -I 0.8 -~~

Eea ion KI 0.0 I.00

- - - - -- - - 6 . 8 . 0 0- - - - - - - - - - - - - - -

0.6 7.9 1.000 9.0 1.000 1200 1.00 0.4 0.2 0.0 0 2 4 6 8 10 12 Core Height (Feet)

FIGURE 3 K(Z) - Normalized FQ(X,Y,Z) as a Function of Core Height For Mk-BW and Advanced W17 HTP TM Fuel SEQUOYAH-UNIT I Page 15 of 15 Revision 0

Tennessee Valley Authority, Post Office Box 2000, Soddy Daisy, Tennessee 37384-2000 December 4, 2013 10 CFR 50.4 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-001 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328

Subject:

Annual Non-Radiological Environmental Operating Report The purpose of this letter is to submit the enclosed Sequoyah Nuclear Plant (SQN) 2013 Annual Non-Radiological Environmental Operating Report. The Tennessee Valley Authority is submitting this report in accordance with Section 5.4.1 of Appendix B, "Environmental Technical Specifications (Non-Radiological)," of the SQN, Units 1 and 2, Operating Licenses. This report, which addresses the period from October 1, 2012, through September 30, 2013, is required to be submitted within 90 days following each anniversary of issuance of the operating licenses. Issuance dates for the SQN, Units 1 and 2, Operating Licenses were September 17, 1980, and September 15, 1981, respectively, indicating this report to be submitted no later than December 14, 2013.

There are no regulatory commitments in this letter. Please direct questions concerning this report to Michael McBrearty at (423) 843-7170.

jj eully ar in President Sequoyah Nuclear Plant

Enclosure:

Tennessee Valley Authority - Sequoyah Nuclear Plant Annual Non-Radiological Environmental Operating Report, October 1, 2012 - September 30, 2013 cc: See page 2

U.S. Nuclear Regulatory Commission Page 2 December 4, 2013 cc (Enclosure):

NRC Regional Administrator - Region II NRC Senior Resident Inspector - SQN NRR Project Manager - SQN Division of Radiological Health - State of Tennessee

ENCLOSURE TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ANNUAL NON-RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT October 1, 2012 through September 30, 2013

TABLE OF CONTENTS TA B LE O F C O NT E NT S ................................................................................................................................ 1 I. INT R O D UC T ION................................................................................................................................ 2 II. REPORTING FOR THOSE PROGRAMS NOT CONCERNED WITH WATER QUALITY OR PROTECTION OF AQUATIC BIOTA, WHICH ARE REGULATED BY THE CLEAN WATER ACT ..................................................................................................... 2 II1. ENVIRONMENTAL MONITORING PERFORMED ..................................................................... 3 IV. REPORTS PREVIOUSLY SUBMITTED AS SPECIFIED IN THE SQN NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM (NPDES) PERMIT .......................................................... 4 V. ENVIRONMENTAL TECHNICAL SPECIFICATION (ETS) NONCOMPLIANCES ....................... 5 VI. CHANGES MADE TO APPLICABLE STATE AND FEDERAL PERMIT CERTIFICATIONS ..... 5 VII. CHANGES IN FACILITY DESIGN OR OPERATION .................................................................. 5 VIII. NON-ROUTINE REPORTS ..................................................................................................... 6 IX . S P EC IAL S T UD IE S ........................................................................................................................... 6 X. CHANGES IN APPROVED ENVIRONMENTAL TECHNICAL SPECIFICATIONS ...................... 7 E-1

I. INTRODUCTION The Sequoyah Nuclear Plant Annual Non-Radiological Environmental Operating Report for the period of October 1, 2012 through September 30, 2013 has been prepared in accordance with Environmental Technical Specifications (ETS) (Non-Radiological), Appendix B, Section 5.4.1. This report includes a summary of:

A. Reporting for those programs not concerned with water quality or protection of aquatic biota, which are regulated by the Clean Water Act B. Environmental monitoring performed C. Reports previously submitted as specified in the SQN National Pollutant Discharge Elimination System (NPDES) Permit No. TN0026450 D. ETS noncompliances and the corrective actions for remediation E. Changes made to applicable State and Federal permits and certifications F. Changes in station design that could involve a significant environmental impact or change the findings of the Final Environmental Statement (FES)

G. Nonroutine reports submitted per ETS Section 4.1 H. Special studies I. Changes in approved ETS Reporting, monitoring, and inspections conducted as required by permits and regulations indicated no adverse impacts upon the environment as a result of station operation.

II, REPORTING FOR THOSE PROGRAMS NOT CONCERNED WITH WATER QUALITY OR PROTECTION OF AQUATIC BIOTA, WHICH ARE REGULATED BY THE CLEAN WATER ACT A. Third Quarter 2012 Summary of Asbestos Removal Projects - submitted to the Hamilton County Air Pollution Control Bureau on October 3, 2012 B. Waste Evaluation Application for TPH Contaminated Soil (Non-PCB Contaminated) -

submitted to Tennessee Department of Environment and Conservation on November 17, 2012 C. Annual Asbestos Removal Notification - submitted to Hamilton County Air Pollution Control Bureau on December 6, 2012 D. Fourth Quarter 2012 Summary of Asbestos Removal Projects - submitted to the Hamilton County Air Pollution Control Bureau on January 3, 2013 E. Report on Diesel Fuel Shipments for Auxiliary Boilers A and B - submitted to the Hamilton County Air Pollution Control Bureau on January 3, 2013 F. Waste Evaluation Application for Spent Sand Blasting Media - submitted to Tennessee Department of Environment and Conservation on February 13, 2013 G. Tier Two Emergency and Hazardous Chemical Inventory - submitted to Soddy-Daisy Fire Department, Hamilton County Local Emergency Planning Commission, and the Tennessee Emergency Management Agency on February 26, 2013 H. Notification for New Waste Streams 72, 73, and 74 - submitted to Tennessee Department of Environment and Conservation on February 26, 2013 I. Air Pollution Control Demolition Permit Request for demolition of Alpine Village - submitted to Hamilton County Air Pollution Control Bureau. Air Pollution Control Demolition Permit 3043 issued February 27, 2013 J. Annual Hazardous Waste Activity Report for 2012 - submitted to the Tennessee Department of Environment and Conservation on February 28, 2013 K. Sequoyah Nuclear Plant Hazardous Waste Minimization Plan - maintained on file at Sequoyah Nuclear Plant since March 1, 2013 L. First Quarter 2013 Summary of Asbestos Removal Projects - submitted to the Hamilton County Air Pollution Control Bureau on April 8, 2013 M. Sequoyah Nuclear Plant Annual Report on The Hours of Operation for diesel permitted equipment - submitted to the Hamilton County Air Pollution Control Bureau on May 13, 2013 N. Waste Evaluation Application for Petroleum Contaminated Gravel - submitted to Tennessee Department of Environment and Conservation on June 7, 2013 E-2

0. Waste Evaluation Application for Nonhazardous Roofing Debris - submitted to Tennessee Department of Environment and Conservation on June 7, 2013 P. Hazardous Waste Contingency Plan - submitted to Soddy Daisy Fire Department, Soddy Daisy Police Department, Tennessee Emergency Response Commission, Hamilton County Local Emergency Planning Committee, Memorial North Park Hospital, Erlanger Medical Center, and TVA Sequoyah Nuclear Fire Operations on June 14, 2013 Q. Revised Waste Evaluation Application for Spent Sand Blasting Media to increase approved amount generated- accepted by Tennessee Department of Environment and Conservation on June 18, 2013 R. Revised Tier Two Emergency and Hazardous Chemical Inventory - submitted to Soddy Daisy Fire Department, Hamilton County Local Emergency Planning Commission, and the Tennessee Emergency Management Agency on June 24, 2013 S. Forms A and R Toxic Chemical Release Information CY2011 Required by Emergency Planning and Community Right to Know Act - submitted to the Environmental Protection Agency EPCRA Reporting Center and Tennessee Department of Environment and Conservation on June 28, 2013 T. Written Annual Document Log of PCBs and PCB Items for Calendar Year 2012 - maintained on file since June 25, 2013 U. Second Quarter 2013 Summary of Asbestos Removal Projects - submitted to the Hamilton County Air Pollution Control Bureau on July 3, 2013 V. Report on Diesel Fuel Shipments for Auxiliary Boilers A and B - submitted to the Hamilton County Air Pollution Control Bureau on July 5, 2013 W. Notification for New Waste Stream 75 - submitted to Tennessee Department of Environment and Conservation on July 11, 2013 Ill. ENVIRONMENTAL MONITORING PERFORMED A. Storm water samples collected at required frequencies and Best Management Practices implemented as required by General Industrial Storm Water Discharge Permit TNR050015 B. Semi-annual facility inspections as required by General Industrial Storm Water Discharge Permit TNRO50015 C. Outfall sampling and inspection is performed as required by NPDES Permit TN0026450 (results previously submitted to NRC as required)

D. Monthly erosion and sediment control inspections are conducted as required by General Industrial Storm Water Discharge Permit TNR050015 E. Weekly tank, piping, and secondary containment inspections are performed as required by General Industrial Storm Water Discharge Permit TNR050015 and the Spill Prevention Controls and Countermeasure Plan F. Weekly and monthly hazardous waste inspections conducted as required by 40CFR261 and by the Tennessee Rule Chapter 1200-1-11, Hazardous Waste Management G. Weekly landfill inspections performed as required by 40CFR258 and by the Tennessee Rule Chapter 1200-1-7, Solid Waste Processing and Disposal H. Daily operational hours of Auxiliary Boilers A and B, Emergency Generators 1A, 1 B, 2A, and 2B, and Blackout Generators 1 and 2 as required by Federally Enforceable Certificate of Operation Nos. 4150-10200501-08C and 4150-20200102-11 C I. Monthly operational hours of Auxiliary Boilers A and B, Emergency Generators 1A, 1B, 2A, and 2B, and Blackout Generators 1 and 2, High Pressure Diesel Fire Pump, Security Backup Diesel Generator, I/S Diesel Generator, and Communications Backup Diesel Generator as required by 40CFR63 J. Intake forebay aeration system sampling, maintenance, and operation performed as required by the State of Tennessee K. Air emissions inspected monthly for equipment permitted by the Hamilton County Air Pollution Control Bureau L. Refrigeration equipment performance and repairs are tracked weekly to ensure compliance with Title VI of the Clean Air Act M. Waste sampling and characterization as required by 40CFR261 and by the Tennessee Rule Chapter 1200, Hazardous Waste Management E-3

N. Quarterly PCB transformer inspections as required by 40CFR761

0. Daily inspections of leaking PCB transformers as required by 40CFR761 P. PCB spill and leak cleanup as required by 40CFR761 Q. Asbestos removal tracking as required by the Hamilton County Air Pollution Control Bureau R. Hazardous waste minimization (such as chemical control and substitution) as required by the Tennessee Rule Chapter 1200, Hazardous Waste Management S. National Environmental Policy Act (NEPA) reviews conducted to evaluate potential environmental impact of temporary or permanent facility modifications as required by 40CFR1 500 T. EOC-1201-NPG-SQN(Water)-E - SQN Environmental Compliance U. Miscellaneous Media Reviews IV. REPORTS PREVIOUSLY SUBMITTED AS SPECIFIED IN THE SQN NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM (NPDES) PERMIT The following reports were submitted as specified in the SQN NPDES Permit No. TN0026450, General Industrial Discharge Storm Water Permit No. TNR050015.

A. Monthly Discharge Monitoring Report for September 2012, and August 2012, 101T corrections (toxicity results) - submitted to Tennessee Department of Environment and Conservation on October 10, 2012 B. Monthly Discharge Monitoring Report for October 2012 - submitted to Tennessee Department of Environment and Conservation on November 10, 2012 C. Monthly Discharge Monitoring Report for November 2012 - submitted to Tennessee Department of Environment and Conservation on December 14, 2012 D. Monthly Discharge Monitoring Report for December 2012 - submitted to Tennessee Department of Environment and Conservation on January 7, 2013 E. Water Withdrawal Registration Forms - submitted to Tennessee Department of Environment and Conservation on February 11, 2013 F. 2012 Biocide/Corrosion Treatment Plan (B/CTP) Annual Report - submitted to Tennessee Department of Environment and Conservation on February 11, 2013 G. Monthly Discharge Monitoring Report for January 2013 - submitted to Tennessee Department of Environment and Conservation on February 11, 2013 H. Monthly Discharge Monitoring Report for February 2013 - submitted to Tennessee Department of Environment and Conservation on March 11, 2013 I. DMR - QA Study 33 Address Verification - submitted to Tennessee Department of Environment and Conservation on March 12, 2013 J. Thirty Day Notification and Sixty Day Response to Storm Water Cut-off Concentration Exceedances Outfall 3- submitted to Tennessee Department of Environment and Conservation on March 20, 2013 K. Multi-Sector Storm Water General Permit 2012 Storm Water Monitoring Report - submitted to Tennessee Department of Environment and Conservation on March 20, 2013 L. Monthly Discharge Monitoring Report for March 2013 - submitted to Tennessee Department of Environment and Conservation on April 12, 2013 M. Monthly Discharge Monitoring Report for April 2013 - submitted to Tennessee Department of Environment and Conservation on May 10, 2013 N. Notification of Intent to reduce inspection frequency for temporarily stabilized areas covered under the construction storm water general permit submitted to Tennessee Department of Environment and Conservation on May 13, 2013

0. Application for Renewal - submitted to Tennessee Department of Environmental and Conservation on May 2, 2013 P. Monthly Discharge Monitoring Report for May 2013 - submitted to Tennessee Department of Environment and Conservation on June 12, 2013 Q. Notice of Termination of coverage for Alpine Village building demolition under the general permit for storm water discharges associated with construction activity- TNR191316 submitted to Tennessee Department of Environment and Conservation on June 24, 2013.

E-4

R. Monthly Discharge Monitoring Report for June 2013 - submitted to Tennessee Department of Environment and Conservation on July 10, 2013.

S. Monthly Discharge Monitoring Report for July 2013 - submitted to Tennessee Department of Environment and Conservation on August 12, 2013 T. DMR - QA Study 33 Provider Graded Test Results - submitted to Tennessee Department of Environment and Conservation on August 19, 2013 U. Revised operating procedure for the SQN Intake Forebay Fish Refuge submitted to Tennessee Department of Environment and Conservation on August 19, 2013.

V. Monthly Discharge Monitoring Report for August 2013 - submitted to Tennessee Department of Environment and Conservation on September 12, 2013 V. ENVIRONMENTAL TECHNICAL SPECIFICATION (ETS) NONCOMPLIANCES None.

VI. CHANGES MADE TO APPLICABLE STATE AND FEDERAL PERMIT CERTIFICATIONS None.

VII. CHANGES IN FACILITY DESIGN OR OPERATION In accordance with Technical Specification 5.3.c, facility design and operational changes were reviewed for potential effect on the environment. This review is completed per Tennessee Valley Authority upper tier Instruction IX Environmental Review and implementing Environmental Management System (EMS) procedures Environmental Review Process and Standards and Criteria for Environmental Reviews, in compliance with the National Environmental Policy Act.

A. Special Tests There were no special tests conducted during this period that met environmental impact criteria B. Temporary Alterations There were no temporary alterations conducted during this period that met environmental impact criteria.

C. Design and Operational Changes The facility design and operational changes made during this reporting period with a potential impact on the environment were found to' be within the scope of existing permits and in compliance with environmental regulations. Those changes reviewed are as follows:

Environmental Assessments None Categorical Exclusion Checklists

1. Generic SQN Blanket Review
2. Generic TVA Paving
3. Generic Facilities HVAC
4. Generic SQN Fire Hydrant Repair or Replacement
5. Containment Pressure Test
6. Alpine Village Demolition
7. Relocation of 2 Siren Sites at SQN
8. Relocation of 1 EP Siren for SQN
9. Roof Replacement Project E-5
10. SQN3556 NFPA Sprinkler Systems Additions and Upgrades VIII. NON-ROUTINE REPORTS None.

IX. SPECIAL STUDIES None.

X. CHANGES IN APPROVED ENVIRONMENTAL TECHNICAL SPECIFICATION There were no changes in approved ETSs during this period.

E-6

Retrieved from "https://kanterella.com/w/index.php?title=ML13346A427&oldid=2454449"