JAFP-13-0096, James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models

James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models

ML13214A107
Person / Time
Site:	FitzPatrick
Issue date:	08/01/2013
From:	Adner C Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
JAFP-13-0096
Download: ML13214A107 (5)

Text

Entergy Nuclear Nort heast Entergy Nuclear Operations, Inc.

James A. FitzPatrick NPP

~ Entergy P.O. Box 110 Lycoming , NY 13093 Tel 3 15-342-3840 Chris M. Adner Licensing Manager JAFP-13-0096 August 1, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models James A FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-059

Reference:

Entergy Nuclear Operations, Inc. to USNRC, JAFP-12-0089, dated August 1, 2012, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models_

Dear Sir or Madam:

The attached report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2012 to July 31, 2013 for Entergy's James A. FitzPatrick Nuclear Power Plant (JAF). There have been no changes to the Loss of Coolant Accident (LOCA) Peak Cladding Temperatures (PCTs) since the publication of Reference 1.

This letter contains no new commitments. Should you have any questions, please contact me Sine&,l.L_

at (315) 349-6766.

Chris M. Adner Licensing Manager CMA/ks/mh cc: next page

JAFP-13-0096 Page 2 of 2 : 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2012 to July 31, 2013 cc:

Mr. William Dean Regional Administrator, Region I U. S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-2713 Resident Inspectors Office U.S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093-0136 Mr. Mohan Thadani Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

JAFP-13-0096 ATTACHMENT 1 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2012 to July 31, 2013 (2 Pages)

JAFP-13-0096 Attachment 1 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2012 to July 31, 2013 INTRODUCTION This report summarizes changes and errors in emergency core cooling system (ECCS) evaluation models in accordance with 10 CFR 50.46(a)(3)(ii) for the period August 1, 2012 to July 31, 2013 for Entergys James A. FitzPatrick Nuclear Power Plant.

Since the last reporting update (Reference 5), FitzPatrick has been subject to a change that utilizes the NRC approved procedure (Reference 7) to estimate the magnitude of the change in Peak Cladding Temperature (PCT) due to the change in fuel properties from GESTR to PRIME. Applying this estimated change in Licensing Basis PCT constitutes interim implementation of the PRIME fuel properties as it pertains to the analysis basis Evaluation Model for the plant, pending a plant ECCS-LOCA re-analysis explicitly using PRIME.

The JAF core is uniformly loaded with the GNF2 fuel type. The GNF2 fuel type, with the Licensing Basis PCT 1890°F, is well below the 2200°F a peak cladding temperature acceptance criterion of 10 CFR 50.46.

Table 1 summarizes the current FitzPatrick Emergency Core Cooling System (ECCS) evaluation models.

TABLE 1 - ACCOUNTING OF LICENSING BASIS PEAK CLAD TEMPERATURES FOR FITZPATRICK GNF2 Fuel(1)

Notification Nature of PCT Report Change in ECCS Evaluation Estimated Licensing Period PCT Impact Basis PCT Cycle 19 Core Load Using GNF2 n/a 1800°F Type Fuel, (Ref. 1, 2) 2011-02, Impact of Database Error Prior for Heat Deposition on the Peak 45°F 1845°F Reporting Cladding Temperature (PCT) for 10 X Period 10 Fuel Bundles (Ref. 3)

(Ref. 5) 2011-03, Impact of Updated Formulation for Gamma Heat 5°F 1850°F Deposition to Channel Wall for 9 X 9 and 10 X 10 Fuel Bundles, (Ref. 4)

Cumulative sum of absolute magnitude of errors prior to this reporting period 50°F 2012-01, Change in an acceptable evaluation model or application of August 1, such model due to PRIME Fuel 2012 - July 40°F 1890°F Properties Implementation for Fuel 31, 2013 Rod T/M Performance, replacing GESTR Fuel Properties (Ref. 6)

Cumulative sum of absolute magnitude of errors in this reporting period 40°F Cumulative sum of absolute magnitude of errors including this reporting period 90°F NOTE: (1) GNF2 fuel was first installed during Refueling Outage 18, October 2008 Page 1 of 2

JAFP-13-0096 Attachment 1 10 CFR 50.46(a)(3)(ii) Annual Report on Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models for the period from August 1, 2012 to July 31, 2013 REFERENCES

1. General Electric Nuclear Energy, "James A. FitzPatrick Nuclear Power Plant SAFER/GESTER-LOCA, Loss-of-Coolant Analysis," Licensing Topical Report NEDC-31317P, Class III (proprietary), Revision 2, April 1993.

2. GE Report, James A. FitzPatrick Nuclear Power Plant GNF2 ECCS-LOCA Evaluation, 0000-0076-4111-R0, August 2008 (Proprietary) (internal report #JAF-RPT-08-00014 R0)

3. General Electric 10 CFR 50.46 Notification Letter 2011-02, dated July 20, 2011 regarding Impact of Database Error for Heat Deposition on the Peak Cladding Temperature (PCT) for 10 X 10 Fuel Bundles. (Proprietary)

4. General Electric 10 CFR 50.46 Notification Letter 2011-03, dated July 20, 2011 regarding Impact of Updated Formulation for Gamma Heat Deposition to Channel Wall for 9 X 9 and 10 X 10 Fuel Bundles. (Proprietary)

5. Entergy Nuclear Operations, Inc. letter to USNRC, JAFP-12-0089, dated August 1, 2012, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models.

6. General Electric 10 CFR 50.46 Notification Letter 2012-01, dated November 29, 2012 regarding PRIME Fuel Properties Implementation for Fuel Rod T/M Performance, replacing GESTR Fuel Properties. (Proprietary)(letter LRW-ENO-GEN-12-131)

7. Implementation of PRIME Models and Data in Downstream Methods, NEDO-33173 Supplement 4-A, Revision 1, November 2012.

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