L-PI-06-053, Corrections to Emergency Core Cooling System (ECCS) Evaluation Models

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Corrections to Emergency Core Cooling System (ECCS) Evaluation Models
ML061790021
Person / Time
Site: Prairie Island Xcel Energy icon.png
Issue date: 06/27/2006
From: Thomas J. Palmisano
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-PI-06-053
Download: ML061790021 (6)


Text

N Commrrtsd to Nucl Prairie lsland Nuclear Generating Plant Operated by Nuclear Management Company, LLC L-PI-06-053 10 CFR 50.46 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Prairie lsland Nuclear Generating Plant Unit 1 Docket 50-282 License No. DPR-42 Corrections to Emerqencv Core Cooling Svstem (ECCS) Evaluation Models

Reference:

1) Letter L-PI-06-010 from Nuclear Management Company, LLC to Nuclear Regulatory Commission, "Revised Commitment to Submit Best-Estimate Loss of Coolant Accident (LOCA) Analysis," dated February 2, 2006.

Enclosed is a report of changes to the Prairie lsland Nuclear Generating Plant (PINGP)

Unit 1 Emergency Core Cooling System (ECCS) Evaluation Models. This report is being submitted in accordance with the provisions of 10 CFR 50, Section 50.46, as a 30-day report.

The report includes Large Break Loss of Coolant Accident (LBLOCA) changes reported by Westinghouse. There were no changes to the Small Break Loss of Coolant Accident (SBLOCA) analysis.

The Unit 1 LBLOCA Peak Clad Temperature (PCT) changes (Enclosure 1) are due to the following two changes:

Unit 1 reactor vessel head replacement included a head assembly upgrade package (HAUP) designated as "HAUP LOCA Evaluation" (+3 degree penalty)

Reconstitution of one fuel assembly with two natural uranium rods (+I degree penalty)

The PCT (2043 OF, see Enclosure) for LBLOCA analysis continues to remain below the 10 CFR 50.46 PCT acceptance criterion. The accumulated absolute value of the PCT changes and errors since the original 1995 baseline Analysis of Record is 799 OF. NMC has committed by letter (see Reference I ) to provide a new LBLOCA analysis for PINGP by July 31, 2006. The limiting LOCA analysis for Prairie lsland Unit I , with consideration of all 10 CFR 50.46 assessments, remains the LBLOCA analysis.

1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121

Document Control Desk Page 2 The enclosure to this letter need not be withheld from public disclosure.

Summarv of Commitments This letter contains no new commitments and no revisions to existing commitments Thomas J. Palmisano Site Vice President, Prairie Island Nuclear Generating Plant Nuclear Management Company, LLC Enclosure cc: Administrator, Region Ill, USNRC Project Manager, Prairie Island, USNRC Resident Inspector, Prairie Island, USNRC

ENCLOSURE NUCLEAR MANAGEMENT COMPANY, LLC PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKET NO 50-282 Unit 1 LBLOCA Peak Clad Temperature Summaries (includes plant specific changes and non-zero non-plant specific changes) 3 pages follow

Westinghouse Proprietary Class 2 Our ref: LTR-LIS-06-277 Page 7 of 1 1 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large Break Plant Name: Prairie Island Unit 1 Utility Name: N u c l e a r M a n a g e m e n t C o m p a n y , LLC Revision Date: 5 / 12/06 Analysis Information EM: SECY UP1 Analysis Date: 3/1/95 Limiting Break S i e : C d = 0.4 FQ: 2.4 FdH: 1.77 Fuel: OFA SGTP (%): 15 Notes: Zirlom, O S G SGTP Evaluated up to 24.64% (see also Note e); Fq increased t o 2.5 (Item A.lO); RSG Study at 10% SGTP.

Clad Temp (OF) Ref. Notes LICENSING BASIS Analysis-Of-Record PCT 2180 12 (a)

PCT ASSESSMENTS (Delta PCT)

A. PRIOR ECCS MODEL ASSESSMENTS 1 . Fixed Heat Transfer Node Ass~gnmentErrorlAccumulator Water -175 3 Injection Error (1995 Report) 2 . I-D Transition Boiling Heat Transfer Error (1 997 Report) 3 . Vessel Channel DX Enor (1997 Report) 4 . Input Consistency (1997 Report) 5 . No Items for 1996 & 1998 Reports 0 4.6 6 . Accumulator LindPressurizer Surge Line Data / Plant Specific Accumulator Level & Line Volume I Plant Specific Restart Errw.

Reanalysis ( I 999 Report) 7 . Modeling Updates and Unheated Conductor Input Corrections (Plant Specific, 2000 Report) 8 . Accumulator Pressure +I- 30 psi Range (Plant Specific, 2001 Repoit) 9 . LHSl Error Enhlation (Plant Specific, 2002 Report) 10 . Sensitlvrty Study for F e 2 . 5 , LHSl Corration, dc. (as listed in note

( f ) ) (Plant Specific, 2003 Report) 1I . Broken Loop Nozzle Loss Cwfficient (Plant Specific) -19 18,19,21, (h) 25 12 . SECY Cold Leg Nozzle Expansion 13 25 B. PLANNED PLANT MODlFlCATlON EVALUATIONS I . Sensitivity S ~ d for y Steam Generator Tube Plugging Increase to 25%

2 . Accumulator Wata Volumc +I- 25 f13 Range 3 . Accumulator Pressure Extended to +I- 55 psi Range 4 . 2 Rcconstitutcd Rods Evaluation 5 . SATP Core Average Burnup 6 . Sensitrviry S ~ d for y Framatwne Replacement Steam Generators 7 . HAUP UH3A Evaluation C. 2006 ECCS MODEL ASSESSMENTS

Westinghouse Proprietary Class 2 Our ref: LTR-LIS-06-277 Page 8 of 1 I Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Large Break Plant Name: Prairie lsland Unit I Utility Name: Nuclear Management Company, LLC Revision Date: 5 /I 2/06 1 .None 0 D. OTHER*

1 . Removal of Reference 14 L.HSI Error Evaluaiion -30 16 (s)

LICENSING BASIS PCT + PCT ASSESSMENTS PCT- 2043

  • It is recommended that the licensee detnmine if these K f allocations be considered with respect to 10 CFR 50.46 reporting requirements.

References:

1 .95NSG-0021, "Updated UP1 LBLOCA," March 24,1995.

2 . WCAP-13919, Addendum 1, "Prairie lsland Units 1 and 2 W C O B M R A C Best Estimate UP1 Large Break LOCA Analysis Engineering Report Addendum 1: Updated Results," December 19%.

3 . NSP-96-202, "Northern States Power Company Prairie lsland Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting," February 20. 1996.

4 . NSP-97-20], "Northern States Power Company Prairie lsland Units 1 and 2 10 CFR 50.46 Annual Notification and Reponing," April 17. 1997.

5 . NSP-98-012, "Northern States Power Company Prairie lsland Units 1 and 2 10 CFR 50.46 Annual Notification and Reponing for 1997." February 27, 1998.

6 . NSP-99-010, "Northern States Power Company Prairie lsland Unlts 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 1998," April 29,1999 7 . NSP-00-005, "Northern States Power Company Prairie lsland Units 1 and 2 10 CFR 50.46 Annual Notification and Reponing f a 1999," February 2000.

8 . NSP-00-057, "Northern Stales Power Company Prairie lsland Units I and 2 LOCA Evaluation of 25% SGTP with Other Modeling Updates," December l I. 2000.

9 . LTR-LIS-06-277, "Reconstitution Evaluation, 10 CFR 50.46 Reporting Plant Specific Text, and Updated Rackup S h m s for F'rairic lsland Unit 1, Cycle 24," 5i2006.

10 . NSP-01-006. "Northern States Power Company Rairie lsland Units 1 and 2 10 CFR 50.46 Annual Notification and Repolting for 2000," March 6.2001.

I I . NSP-02-9, "Nuclear Management Company Prairie lsland Units 1 and 2 LBUW3A Accumulator Pressure and Volume Ranges Evaluation," February 15, 2002.

12 . NSP-02-5. "Nuclear Management Company t h i n e lsland Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2001," March 2002.

13 . NSP-02-59lLTR-ESI-02-194, "Final Evaluation of Large Brcak LOCA Enor," December 2002.

14 . NSP-03-19, 'Wuclear Management Company Prairie bland Units 1 and 2 10 CFR 50.46 Annual Notification and Reporting for 2002," March 2003.

IS . MP92-TAk-0394 1 ET-NSL-OPL-1-92-518, "NSPC Prairie lsland Units 1 and 2, SG Tube Row Area Rcduaion under LOCA I SSE - Fiml Repon", October 21,1992.

16 . NSP-04-10 "Safely Analysis Transtion Program Transmittal of Engineering Report," February 20,2004.

17 . NSP-93-513, Rev IET-NSL-OPL-1-93-313, RN. I , Lcner from T. A. Hawley (W) to K. E. Higar (NSP). "Final Transmittal of Assumptions to be used for the Large and Small Break LOCA Analyses, Rev. I ",July 7,1993. Confirmed by : Lmer from K. E. Higar (NSP) to Mr. T. Hawley (W), "Acceptance ofNSP 513, Rev. I", July 30,1993.

18 . NSP-04-38, "Nuclear Management Company Rairic lsland Units 1 and 2 10 CFK 50.46 Annual Notification and Reponing for 2003," March 2004.

19 . WCAP-162M-P, "SAW Engineering Report for Prairie Island." February 2004.

Westinghouse Proprietary Class 2 Our ref: LTR-LIS-06-277 Page 9 of 1 l 20 . NF-NMC-04-49, "Nuclear Management Company Prairie lsland Unit 1 Cycle 22 Final RSE," April 2004.

21 . NSP-04-65, "Nuclcar Management Company Prairie lsland Unlts I & 2 Safety Analyas Transillon Program Rcpsonsc lo 10 CFR 50.46 inquiry," Apnl21,2004.

22 . NF-NMC-04-129. "Nuclear Management Company Prairie lsland Unit 1, Cycle 23 Final RSE," August 2004.

23 . NSP-04-114, "Nuclear Management Company Prairie lsland Units 1 & 2, Safery Analysis Transition Program. Transmittal of LBLOCA Replacement Steam Generator (RSG)Engineering Report Addendum," (WCAP-16206-P-Addendum I), June 24 . NSP-05-155, "Nuclear Management Company, Reactor Vesxl Head Replacement Project, Prairie Island Units 1 & 2," May

18. 2005.

25 . NSP-05-191, "Miscellanmus LBLOCA SECY EM Enor Notification," August 2005.

Notes:

(a) P-bar-HA increaxd from 1.57 to 1.59 fb) Reanalysis for all listed i s s u s (c) Keanalys~sfor both i s s u a (d) Related ICO in existence (NSP-01-030). NMC cognizant of uncertainty application and PCT sheet categonzition.

(e) It is assumed that NMC is applying the 0.36% SGTF' allowance factor branch of the SG LOCA / SSE issue (Refermcc IS).

Thus the 25% SGTP Smdy (Item B.1) suppons a net SGTP limit of 24.64%.

(f) Sensitivity Study for: FQ2.50, PAD 4.0 Implementation, Restoration ofLHS1 to Reference 17 values, SGlLoop AP Re-hming, Core Pown Ratoration.

(g) Thc note (f) sensitivity study allows for the removal ofthe Reference 13 engineering assessment.

(h) Items A.10 and A.11 presented as aggregate -66 O F entry prior to Reference 21 decomposition.