RS-13-104, 10 CFR 50.46 Annual Report

10 CFR 50.46 Annual Report

ML13126A116
Person / Time
Site:	Millstone, Quad Cities
Issue date:	05/03/2013
From:	Gullott D Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-13-104
Download: ML13126A116 (4)

Text

4300 Winfield Road 4300 Road 1 Warrenvi0le,ILIL60555 Warrenville, 60555

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Exelon Generation~\

^-- Exelon Generation: 630 657 630 657 2000 2000 Office RS-13-104 RS~13-104 10 10 CFR CFR 50.46 50.46 May 3,2013 May 3, 2013 U.S. Nuclear Regulatory Regulatory Commission Commission ATTN:

A Control Desk TIN: Document Control Washington,DC Washington, DC 20555-0001 Quad Cities Nuclear Power Station, Units 1 and 22 Renewed Facility Operating License Nos. DPR-29 and DPR-30 Renewed NRC Docket Nos. 50-254 and and 50-265 50-265

Subject:

10 CFR 50. 46 Annual Report 50.46

Reference:

Letter from Letter fromD.D. M.

M. Gullott Gullott(Exelon (Exelon Generation Generation Company, LLC) LLC) to U.S. NRC, NRC, "10 CFR "10 CFR 50.46, 50.46, 'Acceptance

'Acceptance criteria for emergency criteria for emergency corecore cooling cooling systemssystemsforfor light-water nuclear light-water nuclear power reactors,' Annual Report," dated May Report, II dated May 4, 4, 2012 2012 provides the annual This letter provides annual report report required required byby10 GFR50.46, 10CFR 50.46,"Acceptance "Acceptancecriteria criteriafor for emergency core cooling cooling systems systemsforfor light-water light-water nuclear power reactors,"

reactors, II for for Quad Cities Cities Nuclear Power Nuclear Power Station Station (QCNPS),

(QCNPS),Units Units11and and2.2. The The attachments describe describe the the changes changesinin accumulated peak cladding temperature temperature (PCT)

(PCT) since since the the previous previous annual annualreport reportsubmitted submitted in in the referenced referenced letter.

letter.

There are nono regulatory regulatory commitments contained in in this letter. Should Should youyou have haveany anyquestions questions concerning this letter, please pleasecontact contactMr.Mr.Kenneth KennethM. M. Nicely Nicely at at (630)

(630) 657-2803.

657-2803.

~~~~-------

David M. Gullott Gullott Manager Manager -- Licensing Attachments:

Attachments:

1. Quad Cities Nuclear Nuclear Power Power Station Station Unit Unit 1, 1, 10 10 CFR CFR 50.46 50.46 Report 0/'1 estinghouse Fuel)

Report (Westinghouse Fuel)

2. Quad Cities Nuclear Nuclear Power Power Station Station Unit Unit 2, 2, 10 10 CFR CFR 50.46 50.46 Report Report (Westinghouse 0/'Iestinghouse Fuel) Fuel)

3. Quad Cities Cities Nuclear Nuclear Power Power Station Station Units Units 11 and and 2, 2, 10 10CFR CFR 50.46 50.46Report ReportAssessment Assessment Notes Notes cc:

cc: NRC Regional Regional Administrator, Administrator, Region Region III III NRC Senior Senior Resident Inspector, Quad Cities Resident Inspector, Quad Cities Nuclear Nuclear Power Power Station Station

ATTACHMENT 11 ATTACHMENT Quad Cities Nuclear Nuclear Power Power Station StationUnit Unit 1, 1,

Report (Westinghouse 10 CFR 50.46 Report (Westinghouse Fuel) Fuel)

PLANT NAME:

NAME: Quad Cities Quad Cities Unit Unit 11 ECCS EVALUATION ECCS EVALUATION MODEL:MODEL: USA5 REPORT REVISION REPORT REVISION DATE:

DATE: 05/03/2013 CURRENT OPERATING OPERATING CYCLE:

CYCLE: 23 ANALYSIS OF RECORD RECORD Evaluation Model:

Model: "Westinghouse BWR "Westinghouse BWR ECCS ECCS Evaluation EvaluationModel:Model:

Supplement 3 to Code Description, Qualification and Supplement 3 to Code Description, Qualification Application to SVEA-96 Optima2 Optima2 Fuel,"

Fuel, WCAP-1 II 6078-P-A, WCAP-16078-P-A, November 2004 Calculations: "Quad Cities 11 &

IIQuad & 2 LOCA Analysis for SVEA-96 Optima2 Fuel," OPTIMA2-TR021QC-LOCA, OPTIMA2-TR021 QC-LOCA, Revision 5, 5, Westinghouse Electric Electric Company, LLC, September 2009 LLC, September Fuel Analyzed inin Calculation: SVEA-96 Optima2 Limiting Fuel Type:

Limiting SVEA-96 Optima2 Limiting Single Limiting Single Failure: Low Pressure Low Pressure Coolant Coolant Injection Injection System Systeminjection injection valve valve Limiting Break Limiting Break Size Size and 1.0 double-ended double-ended guillotine guillotine break break inin the the recirculation recirculation pump pump Location: suction line Reference Peak Cladding PCT = 2150°F Temperature (PCT):

(PCT):

MARGIN ALLOCATION A.

A. PRIOR LOCA MODELMODELASSESSMENTS ASSESSMENTS dated May 7, 10 CFR 50.46 Report dated 7, 2010 2010 (See See Note Note 1)

1) ~PCT =

APCT = 11 11°F

°F 10 CFR 50.46 Report dated May 6, 2011 2011 (See Note Note 2) ~PCT =

APCT =0°FOaF 10 CFR 50.46 Report dated May 4, 2012 (See Note Note 3)

3) APCT =

~PCT = 18°F 18°F Net PCT 2179°F B. CURRENT LOCA MODEL MODEL ASSESSMENTS ASSESSMENTS None (See Note 4) 4) ~PCT =

APCT = OaF 0°F Total Total PCT change fromfrom current currentassessments assessments L~PCT Y_APCT == OaF 0°F Cumulative PCT Cumulative PCT change change from currentassessments from current assessments L Y_ ~PCTII =

I1 APCT = OaF 0°F Net PCT 2179°F

ATTACHMENT 2 Quad Quad Cities Nuclear Power Station Station Unit Unit 2, 10 CFR 10 CFR50.46 50.46 Report Report (Westinghouse (Westinghouse Fuel)

PLANT NAME: Quad Cities Unit 2 Quad ECCS EVALUATION ECCS EVALUATION MODEL:

MODEL: USA5 REPORT REVISION REPORT REVISION DATE: DATE: 05/03/2013 CURRENT OPERATING OPERATING CYCLE:

CYCLE: 22 ANALYSIS OF RECORD Evaluation Model:

Model: "Westinghouse BWR ECCS Evaluation Evaluation Model:

Model:

Supplement 3 to Code Description, Description, Qualification Qualification and and Application to SVEA-96 SVEA-96 Optima2 Optima2 Fuel,"

Fuel,"WCAP-1 WCAP-16078-P-A, 6078-P-A, November 2004 Calculations: "Quad Cities 1 & 2 LOCA Analysis for SVEA-96 SVEA-96 Optima2 Fuel," OPTIMA2-TR021 Fuel," OPTIMA2-TR021QC-LOCA, QC-LOCA, Revision Revision 5, 5,

Westinghouse Electric Company, LLC, LLC, September September 2009 2009 Fuel Analyzed in Calculation: SVEA-96 Optima2 Limiting Fuel Limiting Fuel Type: SVEA-96 Optima2 Limiting Single Limiting Single Failure: Low Low Pressure Coolant Injection Pressure Coolant Injection System Systeminjection injection valve valve LimitingBreak Limiting Break Size Size and 1.0 double-ended guillotine break double-ended guillotine break inin the recirculation recirculation pump Location: suction line line Reference Peak Cladding PCT = 2150°F Temperature (PCT):

MARGIN ALLOCATION A. PRIOR LOCA MODEL ASSESSMENTS 10 CFR 50.46 Report dated May May 7, 2010 (See (See Note Note 1)

1) ~PCT =

APCT = 11 11°F

°F 10 CFR 50.46 Report dated May 6, 2011 (See Note 6,2011 Note 2)

2) ~PCT = 0°F APCT OaF 10 CFR 50.46 Report dated May 4, 2012 (See (See Note Note 3)

3) ~PCT = 18°F APCT 18°F Net PCT 2179°F B. CURRENT LOCA MODEL MODEL ASSESSMENTS ASSESSMENTS None (See Note 4)

Note 4) ~PCT = 0°F APCT OaF Total PCT change Total PCT change from from current currentassessments assessments L~PCT = 0°F XAPCT OaF Cumulative PCT Cumulative PCT change change from from current current assessments assessments L I~PCTI APCT ==O°F 0°F Net PCT 2179°F

ATTACHMENT 3 Quad Cities Nuclear Power Power Station Station Units and 2, Units 11 and 1 10 CFR CFR50.46 50.46 Report ReportAssessment Assessment Notes Notes

1. Prior Loss-of-Coolant Accident (LOCA) Assessment The referenced letter reported aa new Westinghouse letter reported Westinghouse LOCA analysis analysis ofof record record (AOR),

(AOR),

which incorporated modifications for the newly newly added addedrecirculation recirculation pump pump adjustable adjustable speed drives (ASD).

speed drives (ASO). The Thenew newAOR AOR (Revision (Revision 5) 5) updated updated the the LOCA analysis to to apply apply approved updated Westinghouse Westinghouse methods, methods,incorporate incorporate previous previous corrections, corrections, and and update update plant specific plant specific inputs.

inputs. The new Westinghouse LOCA analysis demonstrated demonstrated that that the limitingpeak limiting peak cladding cladding temperature temperature (PCT) (PCT) waswas 2150°F.

2150 ° F. The referenced letter letter also reported the reported the impact impact of of subsequent subsequent corrections corrections for for an incorrect bypass hole incorrect bypass holeflow flow coefficient, and coefficient, and forforupdated updatedvessel vessel leakage values. The PCT impact impact ofof these these twotwo corrections on the limiting limiting PCT PCT was was gOF 9°F and 22°F,° F, respectively.

[

Reference:

Letter Letter from from J. L. L. Hansen Hansen (Exelon (Exelon Generation Generation Company, Company, LLC) to U.S. NRC, NRC, "10 CFR "10 CFR 50.46, 50.46, 'Acceptance

'Acceptance criteria for emergency criteria for emergency core core cooling cooling systems systemsfor forlight-water light-water nuclear power reactors,' Annual Annual Report," dated May Report," dated May 7,2010]

7, 2010]

2. Prior LOCA Assessment The referenced letterletter reported new no PCT PCT assessment assessmentfor forthe theWestinghouse WestinghouseLOCA LOCA analysis. Also, Also, nono emergency emergency core cooling cooling system system (ECCS)-related (ECCS)-related changes changes or modifications occurred modifications occurred at Quad Cities Nuclear Power Station Station (QCNPS)

(QCNPS) that that affected affected the the assumptions of of the ECCS analyses.

[

Reference:

Letter Letter from from J. L. L. Hansen (Exelon (Exelon Generation Generation Company, Company, LLC)LLC) to U.S. NRC, NRC,

" 10CFR "10 CFR50.46, 50.46, 'Acceptance criteria for emergency criteria for emergency core cooling cooling systems systemsfor forlight-water light-water nuclear power reactors,'

reactors,' AnnualAnnual Report,"

Report, II dated May 6, 2011] 2011]

Prior 3.LOCA Prior LOCA Assessment The referenced letterletter provided provided the the annual annual 10 10 CFR CFR 50.46 report for 50.46 report forUnits Units11and and2. The

2. The letter reported letter reported errors errors in inthethe current currentWestinghouse Westinghouse QCNPS LOCA analysis associated with with the the use incorrect R-factors.

use of incorrect R-factors. The impactimpact due to this change change was wasdetermined determinedto to be be an 16° 18°F F increase in in PCT. For For 10 CFR 50.46 50.46 reporting reporting purposes, the PCT PCT update was conservatively applied to to all all bundle bundle types types including including thethe fresh fresh bundles.

bundles. This This PCT PCT update update will remain in will remain in effect effect only until until the the maximum maximum average average planar planar linear linear heat heat generation generationrate rate (MAPLHGR)limits (MAPLHGR) limitsfor forallallbundles bundlesininfuture futureQCNPS QCNPSUnits Units11andand 22 cores are are evaluated evaluated with the correct R-factors.

with R-factors.

[

Reference:

Letter from from O. D. M. Gullott (Exelon M. Gullott (Exelon Generation Company, LLC) LLC) to U.S. NRC, NRC, "10 CFR 50.46, 'Acceptance criteria criteria for foremergency emergency core cooling systems systemsfor for light-water light-water nuclear power reactors,'

reactors, Annual I Annual Report,"

Report, dated May 4, 2012]

II 2012]

4. Current Assessment There are no new new changes, changes,error error corrections, corrections, or or enhancements enhancementsininthe thecurrent current QCNPS QCNPS LOCA analysis. No ECCS-related ECCS-related changes changes or or modifications modifications have occurred occurred at QCNPSQCNPS assumptions in that affect the assumptions in the the LOCA AOR.