ML030970293

From kanterella
Jump to navigation Jump to search
Core Operating Limits Report for Unit 2 Cycle 18, Revision 3
ML030970293
Person / Time
Site: Dresden Constellation icon.png
Issue date: 03/28/2003
From: Hovey R
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RHLTR: #03-0021
Download: ML030970293 (23)
v • d • e


Text

ExeIenSM Exelon Generation wwwexeloncorp com Nuclear Dresden Generating Station 6500 North Dresden Road Morris, IL 60450-9765 Tel 815-942-2920 March 28, 2003 RHLTR: #03-0021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-0001 Dresden Nuclear Power Station, Unit 2 Facility Operating License No. DPR-19 NRC Docket No. 50-237

Subject:

Core Operating Limits Report for Unit 2 Cycle 18, Revision 3

Reference:

Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U. S.

NRC, "Request for License Amendment regarding Minimum Critical Power Ratio Safety Limit,' dated January 31, 2003 The purpose of this letter is to transmit the Core Operating Limits Report (COLR), Revision 3, for the current operating cycle (D2C1 8) in accordance with Technical Specification (TS) Section 5.6.5, "CORE OPERATING LIMITS REPORT (COLR)." The COLR was revised to support a proposed revision to the Safety Limit for the Minimum Critical Power Ratio (SLMCPR), in TS Section 2.1.1, "Reactor Core SLs," due to the effect of additional uncertainties and an error found for the SLMCPR for Dresden Nuclear Power Station, Unit 2 Cycle 18. All changes to the COLR are in the conservative direction and support the current SLMCPR as well as the anticipated SLMCPR as described in the referenced license amendment. The analytical methods used to determine the operating limits were NRC approved. The COLR is enclosed as an attachment to this letter.

Should you have any questions concerning this letter, please contact Mr. J. Hansen at (815) 416-2800.

Respectfully, DAI\

R.J. Hovey Site Vice President Dresden Nuclear Power Station

Attachment:

Core Operating Limits Report, Dresden Station Unit 2 Cycle 18, Revision 3 cc: Regional Administrator- NRC Region IlIl NRC Senior Resident Inspector - Dresden Nuclear Power Station A00

Core Operating Limits Report for Dresden Unit 2 Cycle 18 2957MWth Rated Power Revision 3

Issuance of Changes Summary Affected Affected Summary of Changes Revision Date Section Pages All All Original Issue (Cycle 18) 0 10/01 Complete reissue. Changes are increased core thermal power level (EPU - 2957 MWt), power and flow dependent limits (ARTS), exposure extended LHGR limits for SPC All All ATRIUM-9B fuel,(TCV support for new Equipment Out of 1 12/01 Service options Slow Closure, PLUOOS, TCV Stuck Closed), clarification of TIP operating requirements, clarification of LPRM calibration frequency, clarification of coastdown overpower requirements.

Change breakpoint exposure in Tables 2-1 and 2-2 to EOR- 1300 MWd/MT.

  • -
  • 2-3, Add thermal limit set for operation with Pressure Regulator References iv, 2-3, Out-of-Service (PROOS) between cycle exposures of References, 2-4, 2-5, 7,716 MWd/MT and 11,023 MWd/MT. 2 12/02 and 5-2 Add footnote in Section 5 indicating TCV Slow Closure limits apply for PROOS.

Increase allowed Final Feedwater Temperature Reduction for the cycle to 120 0F.

v, 2-3, Update OLMCPR limits based on 0.03 increase in References, 2-4, 2-5, SLMCPR. 3 2/03 2, and 5 2-6, 5-1, Added footnote in Section 5 indicating an MSIV OOS is an and 5-2 allowed EOOS option Dresden Unit 2 Cycle 18 ii Revision 3 2957MWth Rated Power

Table of Contents References....... ......................................................... ......................................................... Iv

1. Average Planar Linear Heat Generation Rate (3.2.1 and 3.4.1) .1-1 1.1 Technical Specification Reference .1-1 1.2 Description .1-1
2. Minimum Critical Power Ratio (3.2.2, 3.4.1 and 3.7.7) . .2-1 2.1 Technical Specification Reference .2-1 2.2 Description .2-1
3. Linear Heat Generation Rate (3.2.3) .3-1 3.1 Technical Specification Reference .3-1 3.2 Description .3-1
4. Control Rod Withdrawal Block Instrumentation (3.3.2.1) .4-1 4.1 Technical Specification Reference .4-1 4.2 Description .4-1
5. Allowed Modes of Operation (B 3.2.2, B 3.2.3) .. 5-1
6. Methodology.......................................................................................................... 6-1 Dresden Unit 2 Cycle 18 iii Revision 3 2957MWth Rated Power

References

1. Exelon Generation Company, LLC Docket No. 50-237, Dresden Nuclear Power Station, Unit 2 Facility Operating License, License No. DPR-19.
2. Letter from D. M. Crutchfield to All Power Reactor Licensees and Applicants, Generic Letter 88-16; Concerning the Removal of Cycle-Specific Parameter Limits from Tech Specs, October 3,1988.
3. Supplemental Reload Licensing Report for DRESDEN UNIT 2 Reload 17 Cycle 18 Power Uprate to 2957 MWth, J11-03837-SRLR-2957, Revision 0, TODI NFM0100102 Sequence 0, September 2001.
4. MICROBURN Steady State LHGR Limit Curve Generation for GE-14 Fuel (D2C18),

BNDD:01-008, May 30, 2001.

5. DRESDEN 2 and 3 QUAD CITIES 1 and 2 Equipment Out-Of-Service and Legacy Fuel Transient Analysis, GE-NE-J 11-03912-00-01-R1, TODI NFM01 00091 Sequence 01, November 2001.
6. Instrument Setpoint Calculation Nuclear Instrumentation Rod Block Monitor Dresden 2 & 3, GE DRF C51-00217-01, December 15,1999.
7. OPL-3 Parameters for Dresden Unit 2 Cycle 18 Transient Analysis, TODI NFM0100057 Sequence 00, DG01-000355, May 10, 2001.
8. Fuel Mechanical Design Report Exposure Extension for ATRIUM-9B Fuel Assemblies at Dresden, Quad Cities, and LaSalle Units, EMF-2563(P) Revision 1, August 2001.
9. Dresden Unit 2 Cycle 17 Reload Analysis, NDIT NFM9900187, Sequence 01, EMF-2275 Revision 1, November 1999.
10. General Electric Standard Application for Reactor Fuel (GESTAR II) and US supplement, NEDE-24011-P-A-14, June 2000.
11. Letter from B. Currier to B. Henning, Determination of Middle of Cycle (MOC) Exposure Point for D2C18 EPU Core Operating Limits Report, NFM-MW:01-0390, December 13, 2001.
12. Dresden Unit 2 Cycle 18 FRED Form Revision 1, TODI NFMO100025 Sequence 01, DG01-000317, April 27, 2001.
13. Letter from Carlos de la Hoz to Doug Wise and Alex Misak, 'Approval of GE Evaluation of Dresden and Quad Cities Pressure Regulator Out of Service Analysis," NF-MW:02-0413, October 22, 2002.
14. Letter from F. Russell Lindquist to Jim NevIing, "TSD NFM-MW-B105 Evaluation of reduction in Dresden Unit 2 TCV Slow Closure MCPR Limits for low power operation,"

FRL02DR2-001, December 11, 2002.

15. Letter from Carlos de la Hoz to Doug Wise and Alex Misak, 'Approval of GE Evaluation of Dresden and Quad Cities Extended Final Feedwater Temperature Reduction,"

NF-MW:02-0081, August 27, 2002.

Dresden Unit 2 Cycle 18 iv Revision 3 2957MWh Rated Power

16. Letter from Carlos de la Hoz to Doug Wise and Alex Misak, "Approval of GE Evaluation of MSIV out of Service for Dresden and Quad Cities", NFM-MW:02-0274, dated August 2, 2002.
17. Letter from F. R. Lindquist to A. Giancatarino, 'Dresden Unit 2 Cycle 18 Safety Limit MCPR Change," FRL03DR2-003, February 21, 2003.
18. NF Calculation Note BNDG:02-001, Revision 0, 'Determination of Generic MCPRf Limits,"

5/17/2002.

Dresden Unit 2 Cycle 18 v Revision 3 2957MWt, Rated Power

1. Average Planar Linear Heat Generation Rate (3.2.1 and 3.4.1) 1.1 Technical Specification

Reference:

Sections 3.2.1 and 3.4.1.

1.2

Description:

Tables 1-1,1-2, and 1-3 are used to determine the maximum average planar linear heat generation rate (MAPLHGR) limit for each fuel type. Limits listed in Tables 1-1, 1-2, and 1-3 are for Dual Reactor Recirculation Loop Operation.

For Single Reactor Recirculation Loop Operation (SLO), the MAPLHGR limits given in Tables 1-1, 1-2, and 1-3 must be multiplied by a SLO MAPLHGR multiplier. The SLO MAPLHGR multiplier for SPC fuel is 0.84 (Reference 3 Section 16). The SLO MAPLHGR multiplier for GE14 fuel is 0.77 (Reference 3 Section 16).

Table 1-1 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for SPC ATRIUM-9B Fuel ATRM9-P9DATB330-1 1GZ-SPC80M-9WR-144-T6-3915 ATRM9-P9DATB348-1 1GZ-SPC80M-9WR-144-T6-3913 ATRM9-P9HATB371-13GZ-SPCIOOT-9WR-144-T6-3914 ATRM9-P9HATB371 -13GZ-SPCIOOT-9WR-144-T6-3912 (Bundles 3915,3913,3914,3912, bundle types 4,5,6,7,35,36,37)

(Reference 3 Section 16)

Planar Average Exposure MAPLHGR (GWd/MTU) (kWlft) 0.0 13.52 17.25 13.52 40.00 10.73 70.00 7.84 Table 1-2 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for SPC 9x9-2 Fuel ANF9x9-2-P9DANB314-9GZ-SPC80M-145-T6-3909 (Bundle 3909, bundle type 1)

(Reference 3 Section 16)

Planar Average Exposure MAPLHGR (GWd/MTU) (kW/ft) 0.0 10.84 25.00 10.84 48.00 7.20 55.00 7.20 Dresden Unit 2 Cycle 18 1-1 Revision 3 2957MWth Rated Power

Table 1-3 Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) for GE14 Fuel GE14-Pl OHNAB408-16GZ-10OT-145-T6-2483 GE14-Pl OHNAB411-4G7.0/9G6.0-10OT-145-T6-2484 (Bundles 2483 & 2484, bundle types 16, 46,17 & 47)

(Reference 3 Section 16)

Planar Average Exposure MAPLHGR (GWd/MTU) (kW/ft) 0.0 11.68 16.00 11.68 50.00 8.02 63.50 6.97 70.00 4.36 Dresden Unit 2 Cycle 18 1-2 Revision 3 2957MWh Rated Power

2. Minimum Critical Power Ratio (3.2.2, 3.4.1 and 3.7.7) 2.1 Technical SDecification

Reference:

Sections 3.2.2, 3.4.1 and 3.7.7.

2.2

Description:

The various MCPR limits are described below.

2.2.1 Manual Flow Control MCPR Limits The Operating Limit MCPR (OLMCPR) is determined from either section 2.2.1.1 or 2.2.1.2, whichever is greater at any given power and flow condition.

2.2.1.1 Power-Denendent MCPR For operation at less than 38.5% core thermal power, the OLMCPR as a function of core thermal power is shown in Table 2-3. For operation at greater than 38.5% core thermal power, the OLMCPR as a function of core thermal power is determined by multiplying the applicable EOOS condition limit shown in Table 2-1 or 2-2 by the applicable MCPR multiplier Kp given in Table 2-

3. For operation at exactly 38.5% core thermal power, the OLMCPR as a function of core thermal power is the higher of either of the two aforementioned methods evaluated at exactly 38.5% core thermal power.

2.2.1.2 Flow-Dependent MCPR Tables 2-4, 2-5 and 2-6 give the MCPRF limit as a function of flow. The MCPRF limit determined from these tables is the flow dependent OLMCPR.

2.2.2 Automatic Flow Control MCPR Limits Automatic Flow Control MCPR Limits are not provided.

2.2.3 Option A and Option B Option A and Option B refer to scram speeds.

Option A scram speed is the Improved Technical Specification scram speed. The core average scram speed insertion time for 20% insertion must be less than or equal to the Technical Specification Scram Speed to utilize Option A MCPR limits. Reload analyses performed by Global Nuclear Fuel (GNF) for cycle 18 Option A MCPR limits utilized a 20%

core average insertion time of 0.900 seconds.

To utilize the MCPR limits for the Option B scram speed, the core average scram insertion time for 20% insertion must be less than or equal to 0.694 seconds (Reference 7 Page 6). If the core average scram insertion time does not meet the Option B criteria, but is within the Option Dresden Unit 2 Cycle 18 2-1 Revision 3 2957MWth Rated Power

A criteria, the appropriate MCPR value may be determined from a linear interpolation between the Option A and B limits with standard mathematical rounding to two decimal places. When performing a linear interpolation to determine MCPR limits, ensure that the time used for Option A is 0.900 seconds, which is the 20% insertion time utilized by GNF in the reload analysis.

2.2.4 Recirculation Pump Motor Generator Settings Cycle 18 was analyzed with a maximum core flow runout of 110%;

therefore the Recirculation Pump Motor Generator scoop tube mechanical and electrical stops must be set to maintain core flow less than 110% (107.8 Mlb/hr) for all runout events (Reference 12 Section 15). This value is consistent with the analyses of Reference 5.

Dresden Unit 2 Cycle 18 2-2 Revision 3 2957MWth Rated Power

Table 2-1 MCPR Option A Based Operating Limits (Reference 3 Section 11. Reference 5 Section 2.3.9, Reference 14, and Reference 17)

EOOS Combination Fuel Typel Cycle Exposure2

<EOR 2-1300MWd/MT EOR '-1300 MWd/MT Base Case GE14 1.57 1.71 ATRIUM-9B 1.56 1.67 Base Case SLO GE14 1.58 1.72 ATRIUM-9B 1.57 1.68 TBPOOS GE14 1.77 1.79 ATRIUM-9B 1.70 1.72 TBPOOS SLO GE14 1.78 1.80 ATRIUM-9B 1.71 1.73 TCV Slow Closure GE14 1.65 1.71 ATRIUM-9B 1.60 1.67 TCV Slow Closure SLO GE14 1.66 1.72 ATRIUM-9B 1.61 1.68 PLUOOS GE14 1.71 1.71 ATRIUM-9B 1.64 1.67 PLUOOS SLO GE14 1.72 1.72 ATRIUM-9B 1.65 1.68 TCV Stuck Closed GE14 1.57 1.71 ATRIUM-9B 1.56 1.67 TCV Stuck Closed SLO GE14 1.58 1.72 ATRIUM-9B 1.57 1.68 7716 MWd/MTto 11023 MWd/MT Pressure Regulator OOS GE14 1.65 7716 MWd/MT to 11023 MWd/MT ATRIUM-9B 1.60

1. SPC 9x9-2 fuel Is bound for all conditions of Table 2-1 by SPC ATRIUM-9B fuel.
2. EOR refers to end of rated power (I e. 100% power/100% flow operation with all rods out)

Dresden Unit 2 Cycle 18 2-3 Revision 3 2957MWt, Rated Power

Table 2-2 MCPR Option B Based Operating Limits (Reference 3 Section I1. Reference 5 Section 2.3.9, Reference 14. and Reference 17)

EOOS Combination Fuel Type' Cycle Exposure 2

<EOR 2 - 1300 MWdlMT ;EOR -1300 MWdlMT Base Case GE14 1.46 1.53 ATRIUM-9B 1.45 1.49

- GE14 1.47 1.54 Base Case SLO ATRIUM-9B 1.46 1.50 TBPOOS GE14 1.59 1.61 ATRIUM-9B 1.52 1.54 TBPOOS SLO GE14 1.60 1.62 ATRIUM-9B 1.53 1.55 TCV Slow Closure GE14 1.48 1.53 ATRIUM-9B 1.45 1.49 TCV Slow Closure SLO GE14 1.49 1.54 ATRIUM-9B 1.46 1.50 PLUOOS GE14 1.53 1.53 ATRIUM-9B 1.47 1.49 PLUOOS SLO GE14 1.54 1.54 ATRIUM-9B 1.48 1.50 TCV Stuck Closed GE14 1.46 1.53 ATRIUM-9B 1.45 1.49 TCV Stuck Closed SLO GE14 1.47 1.54 ATRIUM-9B 1.46 1.50 7716 MWd/MTto 11023 MWdtMT Pressure Regulator 00S GE14 1.48 7716 MWd/MT to 11023 MWd/MT ATRIUM-9B 1.45

1. SPC 9x9-2 fuel Is bound for all conditions of Table 2-2 by SPC ATRIUM-9B fuel
2. EOR refers to end of rated power (i.e. 100% power/100% flow operation with all rods out)

Dresden Unit 2 Cycle 18 2-4 Revision 3 2957MWh Rated Power

Table 2-3 MCPRp for GE and SPC Fuel (Reference 5 Fioures 2-1. 2-3. 2-5, and Sect 2.3.9, Reference 14, and Reference 17)

I. I -- --

Core Thermal Power (% of rated)

Core Flow EOOS Combination 0 25 1 338.5 38.5 45 1 60 70 70 100

(% of rated)

Oneratina Limit MCPR ;

. 4_,_. - _ - _ _

Base Case S60 3.19 2.61 2.29 1.00 l 1.32 1.28 (otion A or Opbon B) > 60 3.81 3.01 2.59 Base Case SLO S 60 3.20 2 62 2.30 1.32 1.28 1.15 1.00 (Option A or Option B) > 60 3.82 3.02 2 60 TBPOOS s 60 5.60 3.81 2.84 1.37 1.28 1.15 1.00 (Option A or Option B) > 60 6.85 4 66 3.48 TBPOOS SLO _S60 5.61 3 82 2.85 4- + 4 1.37 1.28 1.15 1.00 (Option A or Option B) >60 6.86 4.67 3.49 TCV Slow Closure

  • 60 5.60 3.81 2.84 1.64 1.45 1.26 1.11 1.00 (Option A or Option B) > 60 6 85 4.66 3.48 TCV Slow Closure SLO
  • 60 5.61 3.82 2.85 1.64 1.45 1.26 1.11 1.00 (Option A or Option B) > 60 6.86 4 67 3.49 PLUOOS s 60 5.60 3.81 2.84 1.64 1.45 1.26 1.11 1.00 (Option A or Option B) > 60 6.85 4.66 3.48 PLUOOS SLO
  • 60 5.61 3.82 2.85 1.64 1.45 1.26 1.11 1.00 (Option A or Option B) > 60 6 86 4.67 3.49 TCV Stuck Closed S60 3.19 2.61 2.29 4- t 1.32 1.28 1.15 1.00 (Otion A or Ootion B) >60 3.81 301 2.59

-- - -- 4 -__ _ . _ _. _ .

TCV Stuck Closed SLO *60 3.20 2.62 2.30 1.32 1.28 1.15 1.00 (Opbon A or Option B) >60 3.82 3.02 2.60 Pressure Regulator OOS

  • 60 3 20 2.61 2.29 7716 MWd/MT to 11023 MWd/MT 1.64 1.31 1.14 1.11 1.00 (Option A or Option B) >60 3.80 3 01 2.59 _____

Notes for Table 2-3:

  • Values are interpolated between relevant power levels.
  • For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power multiplier Kp should be applied.
  • Allowable EOOS conditions are listed in Section 5.

Dresden Unit 2 Cycle 18 2-5 Revision 3 2957MWh Rated Power

Table 24 MCPRF limits for GE and SPC Fuel Dual Reactor Recirculation Loop Operation (Reference 18)

Flow (% rated) MCPRF 110.0 1.22 100.0 1.22 0.0 1.86 Table 2-5 MCPRF for GE and SPC Fuel Single Reactor Recirculation Loop Operation (Reference 18)

Flow (% rated) MCPRF 110.0 1.22 100.0 1.22 0.0 1.86 Table 2-6 MCPRF limits for GE and SPC Fuel Dual and Single Reactor Recirculation Loop Operation with TCV Stuck Closed (Reference 18)

Flow(% rated) MCPRF 110.0 1.27 108.9 1.27 0.0 l 1.97 Notes for Tables 2-4, 2-5 and 2-6:

  • Values are interpolated between relevant flow values.
  • Rated flow is 98 Mlb/hr.

Dresden Unit 2 Cycle 18 2-6 Revision 3 2957MWth Rated Power

3. Linear Heat Generation Rate (3.2.3) 3.1 Technical Specification

Reference:

Section 3.2.3.

3.2

Description:

The LHGR Limit is the product of the LHGR Limit from Tables 3-1, 3-2, 3-3 or 3-4 and the minimum of either the power dependent LHGR Factor, LHGRFACp, or the flow dependent LHGR Factor, LHGRFACF. The applicable power dependent LHGR Factor (LHGRFACp) is determined from Table 3-5. The applicable flow dependent LHGR Factor (LHGRFACF) is determined from Tables 3-6 and 3-7.

Table 3-1 LHGR Limits for Bundle Types 17 & 47 GE14-P1 OHNAB408-16GZ-1 OOT-145-T6-2483 (Bundle 2483, bundle types 17 & 47)

(Reference 4 Page A5)

Nodal Exposure LHGR Limit (GWdIMT) (kWft) 0 13.34 2.20 13.35 3.31 13.28 4.41 13.27 7.72 13.27 8.82 13.29 13.07 13.29 13.23 12.96 14.33 12.56 15.43 12.36 16.53 12.20 18.74 11.82 22.05 11.32 27.56 10.52 33.07 9.77 38.58 9.26 44.09 8.77 49.60 8.28 55.12 7.77 58.30 7.77 59.85 7.00 60.63 5.89 63.61 4.49 65.87 4.49 Dresden Unit 2 Cycle 18 3-1 Revision 3 2957MWth Rated Power

Table 3-2 LHGR Limits for Bundle Types 16 & 46 GE14-Pl0HNAB411-4G7.0/9G6.0-0OT-145-T6-2484 (Bundle 2484, bundle types 16 & 46)

(Reference 4 Page A9)

Nodal Exposure LHGR Limit (GWd/MT) (kWlt) 0.00 13.40 12.58 13.40 13.23 13.23 14.33 12.94 15.43 12.81 16.53 12.69 18.74 12.32 22.05 11.81 27.56 11.08 33.07 10.40 38.58 9.75 44.09 9.13 49.60 8.54 55.12 7.97 56.63 7.97 63.03 5.00 64.58 4.90 Table 3-3 LHGR Limits for SPC ATRIUM-9B Fuel ATRM9-P9DATB330-1 1GZ-SPC80M-9WR-144-T6-3915 ATRM9-P9DATB348-1 1GZ-SPC80M-9WR-144-T6-3913 ATRM9-P9HATB371 -13GZ-SPC100T-9WR-144-T6-3914 ATRM9-P9HATB371 -13GZ-SPC100T-9WR-144-T6-3912 (Bundles 3915,3913,3914,3912, bundle types 4,5,6,7,35,36,37)

(Reference 8 Figure 2.1)

Nodal Exposure LHGR Limit (GWd/MT) (kWlft) 0.00 14.40 15.00 14.40 64.30 7.90

  • Table 3-3 is applicable to all ATRIUM-9B fuel types Dresden Unit 2 Cycle 18 3-2 Revision 3 2957MWth Rated Power

Table 3-4 LHGR Limits for SPC 9x9-2 Fuel ANF9X9-2-P9DANB314-9GZ-SPC80M-145-T6-3909 (Bundle 3909, bundle type 1)

(Reference 9 Section 7.2.3)

Nodal Exposure LHGR Limit (GWdIMT) (kWlft) 0.0 14.50 5.0 14.50 25.2 10.80 48.0 7.20 55.0 7.20 Dresden Unit 2 Cycle 18 3-3 Revision 3 2957MWt, Rated Power

Table 3-5 LHGRFACp for GE and SPC Fuel (Reference 5 Figures 2-2, 2-4, and 2-6 and Reference 14)

Core Thermal Power (% of rated)

Core Flow 1 80 1 100 EOOS Combination 0 1 25 1 38.5 1 38.5 1 70 1 70

(% of rated) l I Base Case *60 0 50 0.56 0 59 1 00 (Ontion A or Ontion 1) >60 Base Case SLO

  • 60 0 50 0 56 0 59 0.68 1.00 (Option A or Option B) > 60 TBP OOS c 60 0 22 0 39 0 48 0.54 1.00 (Option A or Option B) > 60 0.33 0 42 TBP OOS SLO I 60 0 22 0 39 0 48 0 54 1.00 (Option A or Option B) > 60 0.33 042 TCV Slow Closure
  • 60 022 048 0 39 1.00 1r)nfinn vVLU A nr L

WitnnA RI

>60

.- V --

0.33 1 042 V_____

TCV Slow Closure SLO

  • 60 0 22 0 39 0 48 0 54 0.73 0 78 1 00 (Option A or Option B) > 60 0 33 0.42 PLUOOS *60 0 22 39 0 0 48 0 54 0.73 0 78 1 00 (Option A or Option B) > 60 0 33 0.42 .

PLUOOS SLO 5 60 0 22 0 39 0 48 0 54 0.73 0 78 1 00 (Option A or Option B) > 60 0 33 0.42 TCV Stuck Closed

  • 60 0 50 0.56 0 59 0 68 1.00 (Option A or Option B) > 60 __ _

TCV Stuck Closed SLO

  • 60 0 50 0 56 0.59 0 68 1 00 (Option A or Option B) > 60 _ 1 Pressure Regulator OOS < 60 0 22 0 48

> 60 0.33 0 39 0.42 0 54 0.73 0 78 1.00 7716 MWd/MT to 11023 MWd/MT (Option A or Option B)_

Notes for Table 3-5:

  • Values are interpolated between relevant power levels.
  • For thermal limit monitoring at greater than 100% core thermal power, the 100% core thermal power LHGRFACp multiplier should be applied.
  • Allowable EOOS conditions are listed in Section 5.

Dresden Unit 2 Cycle 18 3-4 Revision 3 2957MWth Rated Power

Table 3-6 LHGRFACF multipliers (Reference 5 Figure 3-3)

Flow (% rated) LHGRFACF 0 0.28 30 0.55 40 0.64 50 0.77 80 1.00 100 1.00 Table 3-7 LHGRFAC multipliers for Turbine Control Valve Stuck Closed (Reference 5 Table 2-17)

Flow (% rated) LHGRFACF 0 0.14 30 0.41 40 0.50 50 0.63 80 0.86 98.3 1.00 100 1.00 Notes for Tables 3-6 and 3-7:

Values are interpolated between relevant flow values.

  • 98 Mlb/hr is rated flow.
  • For thermal limit monitoring at > 100%

rated flow, the 100% rated flow multiplier should be used.

LHGRFACF multipliers listed are bounding for all fuel types installed in Cycle 18.

  • Table 3-6 is valid for both SLO and dual loop operating conditions for all EOOS scenarios except TCV stuck closed.
  • Table 3-7 is valid for both SLO and dual loop operating conditions with a TCV stuck closed.

Dresden Unit 2 Cycle 18 3-5 Revision 3 2957MWth Rated Power

4. Control Rod Withdrawal Block Instrumentation (3.3.2.1) 4.1 Technical Specification

Reference:

Table 3.3.2.1-1 4.2

Description:

The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown below (Reference 6 Page 11):

ROD BLOCK MONITOR l UPSCALE TRIP FUNCTION l ALLOWABLE VALUE Two Recirculation Loop 0.65 Wd + 55%

Operation Single Recirculation Loop 0.65 Wd + 51 %

Operation _ _ _ _ _ _ _ _ _ _ _

The setpoint may be lower/higher and will still comply with the Rod Withdrawal Event (RWE) Analysis because RWE is analyzed unblocked.

Wd - percent of drive flow required to produce a rated core flow of 98 Mlb/hr.

Dresden Unit 2 Cycle 18 4-1 Revision 3 2957MWth Rated Power

5. Allowed Modes of Operation (B 3.2.2, B 3.2.3)

The Allowed Modes of Operation with combinations of Equipment Out-of-Service are as described below:

I ---- OPERATING REGION---- I POWERPLEX Equipment Out of Service Standard MELLLA Coastdown 3 Thermal Limit 1pin'5 Set Number Base Case 2Option

, 2Option A A YesYesYes_1 Yes Yes Yes 2 Base Case SLO2, Option A Yes Yes Yes 2 TBPOOS2 , Option A Yes Yes Yes 3 TBPOOS SL0 2 , Option A Yes Yes Yes 4 TCV Slow Closure4 , Option A Yes Yes Yes 5 TCV Slow Closure SLO4, Option A Yes Yes Yes 6 PLUOOS, Option A Yes Yes Yes 7 PLUOOS SLO, Option A Yes Yes Yes 8 TCV Stuck Closed, Option A Yes Yes Yes 9 TCV Stuck Closed SLO, Option A Yes Yes Yes 10 2

Base Case , Option B Yes Yes Yes 11 Base Case SILa 2 , Option B Yes Yes Yes 12 TBPOOS2, Option B Yes Yes Yes 13 TBPOOS SLO2, Option B Yes Yes Yes 14 TCV Slow Closure 4 , Option B Yes Yes Yes 15 TCV Slow Closure SLO4 , Option B Yes Yes Yes 16 PLUOOS, Option B Yes Yes Yes 17 PLUOOS SLO, Option B Yes Yes Yes 18 TCV Stuck Closed, Option B Yes Yes Yes 19 TCV Stuck Closed SLO, Option B Yes Yes Yes 20 Pressure Regulator OOS 4 , Option A, Yes Yes No N/A 7716 MWd/MT to 11023 MWdIMT Pressure Regulator OOS, Option B, Yes Yes No 31 7716 MWd/MT to 11023 MWd/MT I I Dresden Unit 2 Cycle 18 5-1 Revision 3 2957MWt, Rated Power

1 Each OOS Option may be combined with up to 18 TIP channels OOS (provided the requirements for utilizing SUBTIP methodology are met) with all TIPS available at startup from a refuel outage, a 120OF reduction in feedwater temperature throughout the cycle (provided the requirements of Reference 15 are met, Final Feedwater Temperature Reduction was analyzed for the entire cycle), and up to 50% of the LPRMs OOS with an LPRM calibration frequency of 2500 Effective Full Power Hours (EFPH) (2000 EFPH

+25%).

2 The base case condition supports 1 Turbine Bypass Valve OOS if the assumed opening profile for the remaining group of Turbine Bypass Valves Is met. If the opening profile is not met, or if more than one Turbine Bypass Valve is OOS, utilize the TBPOOS condition. Ensure unit's license supports operation with I Turbine Bypass Valve out of service prior to crediting this flexibility.

3 Coastdown operation is defined as any cycle exposure beyond the full power, all rods out condition with plant power slowly lowering to a lesser value while core flow is held constant (Reference 10 Section 4.3.1.2.8). Up to a 15% overpower Is analyzed per Reference 5.

4 For operation with a Pressure Regulator Out-of-Service (PROOS), the TCV Slow Closure limits should be applied (Reference 13) and the operational notes from Reference 13 reviewed. Between cycle exposures of 7716 MWd/MT and 11023 MWd/MT, the specific thermal limit set for PROOS may be used instead of the TCV Slow Closure set. PROOS and TCV Slow Closure is not an analyzed out-of-service combination.

5 A single Main Steam Isolation Valve (MSIV) may be taken OOS (shut) under any and all OOS Options so long as core thermal power is maintained

<75% of 2957 MWt (Reference 16).

Dresden Unit 2 Cycle 18 5-2 Revision 3 2957MWth Rated Power

6. Methodology The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1. ANF-1 125 (P)(A) and Supplements 1 and 2, 'Critical Power Correlation - ANFB," April 1990.
2. ANF-524 (P)(A) and Supplements 1 and 2, 'ANF Critical Power Methodology for Boiling Water Reactors," Revision 2, November 1990.
3. XN-NF-79-71 (P)(A) Revision 2 and Supplements 1, 2 & 3, 'Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors," March 1986.
4. XN-NF-80-1 9 (P)(A) Volume I Supplement 3, Supplement 3 Appendix F, and Supplement 4, "Exxon Nuclear Methodology for Boiling Water Reactors," November 1990.
5. XN-NF-85-67 (P)(A) Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," September 1986.
6. ANF-913 (P)(A) Volume 1 Revision 1, and Volume I Supplements 2, 3,4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transients Analysis," August 1990.
7. XN-NF-82 (P)(A) Supplement 1 Revision 2, "Qualification of Exxon Nuclear Fuel for Extended Burnup Supplement 1 Extended Burnup Qualification of ENC 9x9 BWR Fuel Grand Gulf Reactors,"

May1988.

8. ANF-89-14(P)(A) Revision 1 and Supplements 1 & 2, "Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9X9 - IX and 9x9 - 9X BWR Reload Fuel,"

October 1991.

9. ANF-89-14(P), "Advanced Nuclear Fuels Corporation Generic Mechanical Design for Advanced Nuclear Fuels Corporation 9X9 - IX and 9x9 - 9X BWR Reload Fuel," May 1989.
10. ANF-89-98 (P)(A), Generic Mechanical Design Criteria for BWR Fuel Designs, Revision 1 and Revision 1 Supplement 1, May 1995.
11. ANF-91-048 (P)(A), "Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR ECCS Evaluation Model," January 1993.
12. Commonwealth Edison Company Topical Report NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods," Revision 0 and Supplements on Neutronics Licensing Analysis (Supplement 1) and La Salle County Unit 2 benchmarking (Supplement 2), December 1991, March 1992, and May 1992, respectively.
13. EMF-85-74 (P) Revision 0 and Supplement 1(P)(A) and Supplement 2(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," February 1998.
14. NEDE-2401 1-P-A-14 Revision 14, "General Electric Standard Application for Reactor Fuel (GESTAR),"

June 2000.

Dresden Unit 2 Cycle 18 6-1 Revision 3 2957MWth Rated Power

Retrieved from "https://kanterella.com/w/index.php?title=ML030970293&oldid=2666553"